[Federal Register Volume 68, Number 92 (Tuesday, May 13, 2003)]
[Notices]
[Pages 25664-25667]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 03-11840]
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NUCLEAR REGULATORY COMMISSION
Notice of Availability of Model Application Concerning Technical
Specification Improvement To Eliminate Post Accident Sampling
Requirements for Babcock and Wilcox Reactors Using the Consolidated
Line Item Improvement Process
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of availability.
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SUMMARY: Notice is hereby given that the staff of the Nuclear
Regulatory Commission (NRC) has prepared a model application relating
to the elimination of post accident sampling requirements for Babcock
and Wilcox (B&W) Reactors. The purpose of this model is to permit the
NRC to efficiently process amendments that propose to remove
requirements for Post Accident Sampling Systems (PASS) from Technical
Specifications (TS). Licensees of nuclear power reactors to which the
model applies may request amendments utilizing the model application.
DATES: The NRC staff issued a Federal Register Notice (68 FR 10052,
March 3, 2003) which provided a model safety evaluation (SE) and a
model no significant hazards consideration (NSHC) determination
relating to elimination of requirements for PASS for B&W Reactors. The
NRC staff hereby announces that the model SE and NSHC determination may
be referenced in plant-specific applications to eliminate requirements
for post accident sampling. The staff has posted a model application on
the NRC web site to assist licensees in using the consolidated line
item improvement process (CLIIP) to eliminate PASS-related TS. The NRC
staff can most efficiently consider applications based upon the model
application if the application is submitted within a year of this
Federal Register Notice.
FOR FURTHER INFORMATION CONTACT: Robert Dennig, Mail Stop: O-12H4,
Division of Regulatory Improvement Programs, Office of Nuclear Reactor
Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone 301-415-1156.
SUPPLEMENTARY INFORMATION:
Background
Regulatory Issue Summary 2000-06, ``Consolidated Line Item
Improvement Process for Adopting Standard Technical Specification
Changes for Power Reactors,'' was issued on March 20, 2000. The CLIIP
is intended to improve the efficiency of NRC licensing processes. This
is accomplished by processing proposed changes to the standard
technical specifications (STS) in a manner that supports subsequent
license amendment applications. The CLIIP includes an opportunity for
the public to comment on proposed changes to the STS following a
preliminary assessment by the NRC staff and finding that the change
will likely be offered for adoption by licensees. The CLIIP directs the
NRC staff to evaluate any comments received for a proposed change to
the STS and to either reconsider the change or to proceed with
announcing the availability of the change for proposed adoption by
licensees. Those licensees opting to apply for the subject change to TS
are responsible for reviewing the staff's evaluation, referencing the
applicable technical justifications, and providing any necessary plant-
specific information. Each amendment application made in response to
the notice of availability will be processed and noticed in accordance
with applicable rules and NRC procedures.
This notice involves the elimination of requirements for PASS and
related administrative controls in TS for B&W Reactors. This proposed
change was proposed for incorporation into the STS by the B&W Owners
Group (BWOG) participants in the Technical Specification Task Force
(TSTF) and is designated TSTF-442. TSTF-442 is supported by the NRC
staff's SE dated November 14, 2002 (ADAMS Accession Number
ML0225601190), for the BWOG topical report BAW-2387, ``Justification
for the Elimination of the Post Accident Sampling System (PASS) from
the Licensing Basis of Babcock and Wilcox Plants,'' which was submitted
to the NRC on June 25, 2001. The BWOG request followed the staff's
approval of similar requests for elimination of PASS requirements from
the Combustion Engineering Owners Group (CEOG), the
[[Page 25665]]
Westinghouse Owners Group (WOG), and the Boiling Water Reactor Owners
Group (BWROG). TSTF-442 can be viewed on the NRC Web site:
(www.nrc.gov/reactors/operating/licensing/techspecs/changes-issued-for-adoption.html).
Applicability
This proposed change to remove requirements for PASS from TS (and
other elements of the licensing bases) is applicable to B&W Reactors.
To efficiently process the incoming license amendment applications,
the staff requests each licensee applying for the changes addressed by
TSTF-442 using the CLIIP to address the following plant-specific
verifications and regulatory commitments. The CLIIP does not prevent
licensees from requesting an alternative approach or proposing the
changes without the requested verifications and regulatory commitments.
Variations from the approach recommended in this notice may, however,
require additional review by the NRC staff and may increase the time
and resources needed for the review. In making the requested regulatory
commitments, each licensee should address: (1) That the subject
capability exists (or will be developed) and will be maintained; (2)
where the capability or procedure will be described (e.g., severe
accident management guidelines, emergency operating procedures,
emergency plan implementing procedures); and (3) a schedule for
implementation. The amendment request need not provide details about
designs or procedures.
Each licensee should verify that it has, and make a regulatory
commitment to maintain (or make a regulatory commitment to develop and
maintain):
a. A capability for classifying fuel damage events at the Alert
level threshold (typically this is 300 [mu]Ci/ml dose equivalent
iodine). This capability may use a normal sampling system or
correlations of letdown line dose rates to coolant concentrations;
b. Contingency plans for obtaining and analyzing highly radioactive
samples from the reactor coolant system, containment sump, and
containment atmosphere; and
c. Offsite capability to monitor radioactive iodines.
Public Notices
In a notice in the Federal Register dated March 3, 2003 (68 FR
10052), the staff requested comment on the use of the CLIIP to process
requests to delete post-accident sampling requirements from B&W
Reactors. The staff had previously issued notices of availability on
the use of the CLIIP to process requests to delete post-accident
sampling requirements from plants with Westinghouse and Combustion
Engineering designs (65 FR 65018, October 31, 2000) and BWR designs (67
FR 13027, March 20, 2002). The notice of availability for Westinghouse
and Combustion Engineering plants followed the staff's disposition of
comments received in response to a notice requesting comment (65 FR
49271, August 11, 2000). The notice of availability for BWR plants
followed the staff's disposition of comments received in response to a
notice requesting comment (66 FR 66949, December 27, 2001). Each
request to eliminate PASS requirements by licensees for Westinghouse,
CE, and BWR plants using the CLIIP has also included notices prior to
issuance of the subject license amendments and upon issuance.
TSTF-442, as well as the NRC staff's safety evaluation and model
application, may be examined, and/or copied for a fee, at the NRC's
Public Document Room, located at One White Flint North, 11555 Rockville
Pike (first floor), Rockville, Maryland. Publicly available records are
accessible electronically from the ADAMS Public Library component on
the NRC Web site, (the Electronic Reading Room).
The staff did not receive comments following the notice soliciting
comments about modifying the TS requirements regarding post accident
sampling for B&W Reactors.
As described in the model application prepared by the staff,
licensees may reference in their plant-specific applications to
eliminate PASS-related TS the SE and NSHC determination previously
published in the Federal Register (68 FR 10052, March 3, 2003).
Dated at Rockville, Maryland, this 6th day of May 2003.
For the Nuclear Regulatory Commission.
Robert L. Dennig,
Section Chief, Technical Specifications Section, Operating Reactor
Improvements Program, Division of Regulatory Improvement Programs,
Office of Nuclear Reactor Regulation.
Enclosure for Inclusion on Technical Specification Web Page
The following example of an application was prepared by the NRC
staff to facilitate the use of the consolidated line item improvement
process (CLIIP). The model provides the expected level of detail and
content for an application to eliminate pass requirements using CLIIP.
Licensees remain responsible for ensuring that their actual application
fulfills their Administrative requirements as well as NRC regulations.
U.S. Nuclear Regulatory Commission, Document Control Desk,
Washington, DC 20555
Subject:
Plant Name
Docket No. 50-
Application for Technical Specification Improvement to Eliminate
Requirements for Post Accident Sampling System for Babcock and
Wilcox Reactors Using the Consolidated Line Item Improvement Process
Gentlemen: In accordance with the provisions of 10 CFR 50.90,
[LICENSEE] is submitting a request for an amendment to the technical
specifications (TS) for [PLANT NAME, UNIT NOS.].
The proposed amendment would delete Technical Specification (TS)
5.5.3, ``Post Accident Sampling,'' and thereby eliminate the
requirements to have and maintain the post accident sampling system
at [PLANT]. The changes are consistent with NRC approved Industry/
Technical Specification Task Force (TSTF) Standard Technical
Specification Change Traveler, TSTF-442, ``Elimination of
Requirements for a Post Accident Sampling System (PASS).'' The
availability of this technical specification improvement was
announced in the Federal Register on [DATE OF NOTICE OF
AVAILABILITY] as part of the consolidated line item improvement
process (CLIIP).
Attachment 1 provides a description of the proposed change, the
requested confirmation of applicability, and plant-specific
verifications. Attachment 2 provides the existing TS pages marked-up
to show the proposed change. Attachment 3 provides revised clean
technical specification pages. Attachment 4 provides a summary of
the regulatory commitments made in this submittal. [IF APPLICABLE:
Attachment 5 provides the existing TS Bases pages marked-up to show
the proposed change (for information only).]
[LICENSEE] requests approval of the proposed License Amendment
by [DATE], with the amendment being implemented [BY DATE OR WITHIN X
DAYS].
In accordance with 10 CFR 50.91, a copy of this application,
with attachments, is being provided to the designated [STATE]
Official.
I declare under penalty of perjury under the laws of the United
States of America that I am authorized by [LICENSEE] to make this
request and that the foregoing is true and correct. [Note that
request may be notarized in lieu of using this oath or affirmation
statement].
If you should have any questions regarding this submittal,
please contact [ ].
Sincerely,
Name,
Title
Attachments:
1. Description and Assessment
2. Proposed Technical Specification Changes
3. Revised Technical Specification Pages
4. Regulatory Commitments
5. Proposed Technical Specification Bases Changes (if applicable)
cc:
[[Page 25666]]
NRR Project Manager
Regional Office
Resident Inspector
State Contact
Attachment 1--Description and Assessment
1.0 DESCRIPTION
The proposed License amendment deletes the program requirements of
TS (5.5.3), ``Post Accident Sampling.''
The changes are consistent with NRC approved Industry/Technical
Specification Task Force (TSTF) Standard Technical Specification Change
Traveler, TSTF-442. The availability of this technical specification
improvement was announced in the Federal Register on [DATE] as part of
the consolidated line item improvement process (CLIIP).
2.0 ASSESSMENT
2.1 Applicability of Published Safety Evaluation
[LICENSEE] has reviewed the safety evaluation published on March 3,
2003 (68 FR 10052) as part of the CLIIP. This verification included a
review of the NRC staff's evaluation as well as the supporting
information provided to support TSTF-442 (i.e., BAW -2387,
``Justification for the Elimination of the Post Accident Sampling
System (PASS) from the Licensing Basis of Babcock and Wilcox-Designed
Plants,'' which was submitted to the NRC on June 25, 2001, and the
associated NRC safety evaluation dated November 14, 2002). [LICENSEE]
has concluded that the justifications presented in the TSTF proposal
and the safety evaluation prepared by the NRC staff are applicable to
[PLANT, UNIT NOS.] and justify this amendment for the incorporation of
the changes to the [PLANT] Technical Specifications.
2.2 Optional Changes and Variations
[LICENSEE] is not proposing any variations or deviations from the
technical specification changes described in TSTF-442 or the NRC
staff's model safety evaluation published on March 3, 2003.
Plant-specific submittals may also include one or more of the
following:
(1) Requirements for installing and maintaining PASS were included
in a confirmatory order for [PLANT] issued on [DATE]. This amendment
request includes superseding the requirements imposed by that
confirmatory order.
(2) As described in the model safety evaluation published on March
3, 2003, the elimination of the TS and other regulatory requirements
for PASS result in additional changes to the TS. These changes are
[DESCRIBE ADDITIONAL CHANGES]. The changes are necessary due to the
removal of the TS section on PASS. The changes do not revise technical
requirements beyond that addressed by the NRC staff in the model safety
evaluation published on March 3, 2003. [Note that these changes could
involve the deletion or modification of license conditions in addition
to other TS.]
(3) The elimination of PASS results in changes to the TS Bases. The
revised Bases are provided in Attachment 5. [LICENSEE] will formally
address the changes to the Bases in accordance with [the Bases Control
Program or administrative procedure for revising Bases] and will
provide the actual revised Bases pages in a future submittal.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Determination
[LICENSEE] has reviewed the proposed no significant hazards
consideration determination published on March 3, 2003 (68 FR 10052) as
part of the CLIIP. [LICENSEE] has concluded that the proposed
determination presented in the notice is applicable to [PLANT] and the
determination is hereby incorporated by reference to satisfy the
requirements of 10 CFR 50.91(a).
3.2 Verification and Commitments
As discussed in the model SE published in Federal Register on March
3, 2003 for this technical specification improvement, plant-specific
verifications were performed as follows:
1. [LICENSEE] [verified that it has or is making a regulatory
commitment to develop] contingency plans for obtaining and analyzing
highly radioactive samples from the RCS, containment sump, and
containment atmosphere. The contingency plans will be contained in
[specified document or program] and implementation [is complete, will
be completed with the implementation of the License amendment, or will
be completed within X days (<6 months) after the implementation of the
License amendment]. Establishment and maintenance of contingency plans
is considered a regulatory commitment.
2. The capability for classifying fuel damage events at the Alert
level threshold [has been or will be] established for [PLANT] at
radioactivity levels of [300 mCi/cc dose equivalent iodine]. This
capability will be described in [specified document or program] and
implementation [is complete, will be completed with the implementation
of the License amendment, or will be completed within X days (<6
months) after the implementation of the License amendment]. The
capability for classifying fuel damage events is considered a
regulatory commitment.
3. [LICENSEE] [verified that it has or is making a regulatory
commitment to develop] an ability to assess radioactive iodines
released to offsite environs. The capability for monitoring iodines
will be maintained within the [specified document or program].
Implementation of this commitment [is complete, will be completed with
the implementation of the License amendment, or will be completed
within X days (<6 months) after the implementation of the License
amendment]. The capability to monitor radioactive iodines is considered
a regulatory commitment.
4.0 ENVIRONMENTAL EVALUATION
[LICENSEE] has reviewed the environmental evaluation included in
the model safety evaluation published on March 3, 2003 (68 FR 10052) as
part of the CLIIP. [LICENSEE] has concluded that the staff's findings
presented in that evaluation are applicable to [PLANT] and the
evaluation is hereby incorporated by reference for this application.
Attachment 2--Proposed Technical Specification Changes (Mark-Up)
Attachment 3--Proposed Technical Specification Pages
Attachment 4--List of Regulatory Commitments
The following table identifies those actions committed to by
[LICENSE] in this document. Any other statements in this submittal are
provided for information purposes and are not considered to be
regulatory commitments. Please direct questions regarding these
commitments to [ ].
[[Page 25667]]
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Regulatory commitments Due date/event
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[LICENSEE] [verified that it has or is [Complete, implemented with
making a regulatory commitment to amendment OR within X days of
develop] contingency plans for implementation of amendment].
obtaining and analyzing highly
radioactive samples from the RCS,
containment sump, and containment
atmosphere. The contingency plans will
be contained in [specified document or
program] and implementation [is
complete, will be completed with the
implementation of the License
amendment, or will be completed within
x days (< 6 months) after the
implementation of the License
amendment]. Establishment and
maintenance of contingency plans is
considered a regulatory commitment.
The capability for classifying fuel [Complete, implemented with
damage events at the Alert level amendment OR within X days of
threshold [has been or will be] implementation of amendment].
established for [PLANT] at
radioactivity levels of [300 mCi/cc
dose equivalent iodine]. This
capability will be described in
[specified document or program] and
implementation [is complete, will be
completed with the implementation of
the License amendment, or will be
completed within x days (< 6 months)
after the implementation of the License
amendment]. The capability for
classifying fuel damage events is
considered a regulatory commitment.
[LICENSEE] [verified that it has or is [Complete, implemented with
making a regulatory commitment to amendment OR within X days of
develop] an ability to assess implementation of amendment].
radioactive iodines released to offsite
environs. The capability for monitoring
iodines will be maintained within the
[specified document or program].
Implementation of this commitment [is
complete, will be completed with the
implementation of the License
amendment, or will be completed within
x days (< 6 months) after the
implementation of the License
amendment]. The capability to monitor
radioactive iodines is considered a
regulatory commitment.
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Attachment 5--Possible Changes to TS Bases Pages
[FR Doc. 03-11840 Filed 5-12-03; 8:45 am]
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