[Federal Register Volume 62, Number 198 (Tuesday, October 14, 1997)]
[Notices]
[Pages 53353-53354]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-27083]


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NUCLEAR REGULATORY COMMISSION


Assurance of Sufficient Net Positive Suction Head for Emergency 
Core Cooling and Containment Heat Removal Pumps; Issue

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of issuance.

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SUMMARY: The Nuclear Regulatory Commission (NRC) has issued Generic 
Letter 97-04 to all holders of operating licenses for nuclear power 
plants, except those who have permanently ceased operations and have 
certified that fuel has been permanently removed

[[Page 53354]]

from the reactor vessel, to request that addressees submit information 
necessary to confirm the adequacy of the net positive suction head 
available for emergency core cooling (including core spray and decay 
heat removal) and containment heat removal pumps.
    The generic letter is available in the NRC Public Document Room 
under accession number 9710060324.

DATES: The generic letter was issued on October 7, 1997.

ADDRESSES: Not applicable.

FOR FURTHER INFORMATION CONTACT: William O. Long at (301) 415-3026.

SUPPLEMENTARY INFORMATION: This generic letter only requests 
information from addressees under the provisions of Section 182a of the 
Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f). The 
requested information will enable the staff to determine whether the 
NPSH analyses of addressees conform with the current licensing basis 
for their respective facilities, including the licensing safety 
analyses and the principal design criteria which require and/or commit 
that safety-related components and systems be provided to mitigate the 
consequences of design-basis accidents.
    New NPSH analyses are neither requested nor required to be 
performed to respond to this information request. However, new NPSH 
analyses may be warranted if an addressee determines that changes in 
plant design or procedures have occurred which may have reduced the 
available NPSH. In such cases, each affected addressee must take 
appropriate corrective action to restore its facility to compliance, in 
accordance with the requirements stated in Appendix B to 10 CFR Part 
50.

    Dated at Rockville, Maryland, this 7th day of October 1997.

    For the Nuclear Regulatory Commission.
Jack W. Roe,
Acting Director, Division of Reactor Program Management, Office of 
Nuclear Reactor Regulation.
[FR Doc. 97-27083 Filed 10-10-97; 8:45 am]
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