[Federal Register Volume 59, Number 122 (Monday, June 27, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-15485]


[[Page Unknown]]

[Federal Register: June 27, 1994]


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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-272 and 50-311]

 

Public Service Electric and Gas Co.; Correction

    On July 27, 1989 (54 FR 31270) was published in the Federal 
Register which contained exemptions to 10 CFR part 50, appendix R, 
related to the Salem Nuclear Generating Station, Units 1 and 2. The 
following corrections should be incorporated:
    1. Page 31271, Column 1, Line 53, change ``1 & 2'' to ``12''.
    2. Page 31271, Column 2, replace Line 3 through Line 32 with the 
following:
    ``The rooms within this area are separated by hollow core metal 
office partitions except the air conditioning rooms, which are 
separated by a reinforced concrete wall. The two control rooms are 
separated by a 10-foot wide corridor. Room partitions between the 
control rooms and the senior shift and shift supervisor's office 
contain glass panels. The control rooms are separated from their 
associated control equipment rooms by built-in steel frame control 
cabinets. Dropped ceilings are finished with acoustic tile.''
    3. Page 31272, Column 1, Line 5, change ``1006'' to ``100G''.
    4. Page 31272, Column 2, Line 35, change ``781'' to ``78I''.
    5. Page 31272, replace Column 2, Line 37 to Column 3, Line 44, with 
the following:
``4.1  Exemption Requested
    An exemption was requested from Section III.G.2.c to the extent 
that it requires the separation of redundant cables and equipment by 
hour rated fire barriers plus area-wide suppression and detection. 
Specifically, these locations are not protected by automatic fire 
suppression system or area-wide fire detection systems.
4.2  Discussion
    This fire area consists of the mechanical penetration areas on 
elevations 78 feet and 100 feet of the auxiliary building. It is 
constructed of reinforced concrete with 3-hour fire rated barriers. 
Doors, dampers, and HVAC duct penetrations are not 3-hour rated; 
however, these are the subject of a generic exemption previously 
evaluated to be acceptable.
    Elevation 100 ft contains the fuel handling area exhaust 
ventilation equipment and the containment pressure relief exhaust unit 
and the steam generator blowdown tanks. The area also contains some 
safety-related instrument panels. Elevation 78 ft. contains piping for 
various systems which run between the auxiliary and the containment 
building. The area also contains service water piping which enters the 
auxiliary building from the service water intake structure. Partial 
area fire detection is provided for the protection of the major fire 
hazards on elevations 78 ft. and 100 ft. Continuous thermal strip 
detectors are also provided to protect charcoal filters in the 
ventilation units. Additionally, automatic fire suppression is provided 
in the ventilation units by a water deluge spray system actuated by the 
thermal strip detectors. Portable fire extinguishers and manual hose 
stations are also provided on elevation 100 ft.
    The redundant equipment located in this area includes piping and 
valves associated with the following systems:

--Auxiliary Feedwater
--Component Cooling
--Charging System
--Containment Ventilation
--Service Water
--Residual Heat Removal
--Main Steam
4.3  Evaluation
    The fire protection in this area does not comply with the technical 
requirements of Section III.G.2.c of Appendix R because the redundant 
cables are protected by a 1-hour rated barrier but, without automatic 
suppression and area-wide detection.
    There was a concern that a fire in this fire area could cause the 
loss of normal shutdown capability. The in-site combustibles in the 
Mechanical Penetration area will result in a total fire load of 
approximately 28,000 BTU/ft2 (21 minutes on the ASTM time-
temperature curve). The major combustibles in this area consist of the 
charcoal filters and electrical cable insulation. The charcoal filters 
are protected by automatic deluge suppression systems. The electrical 
cables are widely dispersed and protected by the partial detection 
system. There is a reasonable assurance that a fire in this area will 
be detected by the partial fire detection system in its early stages 
and extinguished by the fixed fire suppression system or the fire 
brigade before adjacent safety-related areas are threatened. The 1-hour 
fire barriers would maintain one division of cables needed for safe 
shutdown free of fire damage until the fire brigade could extinguish 
the fire.
4.4  Conclusion
    Based on the above evaluation, it is concluded that the existing 
fire protection features already in place combined with the 1-hour fire 
barriers in the above described fire areas provide a level of fire 
protection equivalent to the technical requirements of Section 
III.G.2.c of Appendix R. Therefore, the exemption is granted.''
    6. Page 31275, Column 1, Line 8, change ``Panel 35'' to ``Panel 
355''.
    7. Page 31275, Column 3, Line 67, change ``1&2 FA-AB-122A'' to ``12 
FA-AB-122A''.
    8. Page 31276, Column 1, Line 16, change ``781'' to ``78I''.
    9. Page 31276, Column 1, replace Lines 18 through 24 with the 
following:
    ``7. Lack of complete 1-hour fire rated barriers between redundant 
shutdown systems in the 460V switchgear room. (Areas 1&2 FA-AB-84A) 
(Licensee Exemption 6);''
    10. Page 31276, Column 1, replace Lines 30 through 33 with the 
following:
    ``9. Lack of complete 1-hour fire rated barriers between redundant 
shutdown system and a manually actuated fire suppression system in lieu 
of an automatic system in the 4160V switchgear room (Areas 1&2 FA-AB-
64A) (Licensee Exemption 9);''
    11. Page 31276, Column 1, Line 46, change ``45A'' to ``45A and B''.

    Dated this day at Rockville, Maryland, this 17th day of June, 
1994.

    For the Nuclear Regulatory Commission.
Charles L. Miller,
Director, Project Directorate I-2 Division of Reactor Projects--I/II 
Office of Nuclear Reactor Regulation.
[FR Doc. 94-15485 Filed 6-24-94; 8:45 am]
BILLING CODE 7590-01-M