ML17156B290
| ML17156B290 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/09/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156B291 | List: |
| References | |
| NUDOCS 8908170037 | |
| Download: ML17156B290 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Enclosure 1
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUESTS FOR DEVIATION FROM CERTAIN FIRE PROTECTION PROVISIONS OF APPENDIX R TO 10 CFR PART 50 SUSQUEHANNA STEN ELECTRIC STATION, UNITS 1
AND 2 DOCKET NO. 50-387 AND 50-388
- 1. 0 INTRODUCTION By letter dated June 30, 1988, the licensee (Pennsylvania Power and Light Company - PPSL) submitted Revision No.
3 to the Susquehanna Steam Electric
- Station, Units 1 and 2 Fire Protection Revision Report.
That submittal, along with prior submittals, including requests from the staff for additional information and the licensee's responses to the requests, was reviewed for NRC by Science Application International Corporation (SAIC).
SAIC submitted their evaluation (Technical Evaluation Report dated June 22, 1989) of the various PPSL documents.
We have reviewed the SAIC Technical Evaluation Report (TER) and agree with the details of their evaluations and conclusions.
The SAIC Susquehanna TER is attached to and is a part of this safety evaluation.
- 2. 0 CONCLUSION By way of recapitulation, the conclusions from the SAIC Technical Evaluation Report are repeated.
2.1 Based on the evaluations in the SAIC TER, the following deviations from certain commitments of the licensee's Fire Protection Progam have been found acceptable and may be granted:
Section Title 2.1 2.2 2.3 2.4 2.6 2.7 2.9 2.10 2.11 2.12 2.13 2.14 Battery Room Exhaust Fans'uppression Pool Temperature Indication Non-Rated Fire Doors Wraparound Area Non-Fireproofed Structural Steel Fire Spread Limitations HVAC Penetrations Reactor Building Fire Walls Fire Barriers Without Fire Dampers in Vertical Ventilation Duct Penetrations Essential redundant Raceway Protection Reactor Building Fire Zones Without Fire Detection Fire Areas in the Control Structure Without Fire
. Suppression Emergencv Switchgear Room Cooling System Components - Insufficient Spatial Separation 89081,70037 890805'DR ADOCK 05000387 F
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~ Section rn TER Title 2.15 2.16 2.17 2.18 2.19 2.20 2.21 2.22 2.23 2.24 2.25 2.26 2.27 2.28 2.29 Kaowool System as an Acceptable 1-Hour Barrier Wrap Incomplete Fire Suppression and Fire Detection in Diesel Generator Fire Areas Penetration Seals - Conduits Control Structure - Fire Zones Without Fire Detection and/or Fire Suppression
'Control Structure - Fire Areas CS-9, Partial Fire Suppression Automatic Fire Suppression in Fire Zone 2-5D Automatic Fire Suppression and Intervening Combustibles in Fire Zone 1-3A Automatic Fire Suppression and Intervening Combustibles in Fire Zone 2-3B-N Nuclear Boiler Instrumentation in Fire Zone 1-5A-S Nuclear Boiler Instrumentation in Fire Zone 2-5A-N Category I Components in Fire Zones 1-3C-W and 2-3C-W I
Control Structure HVAC System Components - Fire Zones 0-29B and 0-30A Outside Areas - Lack of Separation of Safe Shutdown Components and Electrical Cables Reactor Coolant Makeup and Depressurization Systems Control Structure Chiller ESW Valves-Insufficient Fire Barrier, Fire Zone 1-3A Control Room Raised Floor and Control Structure Cable Chase Fire Protection 2.2 Based on evaluations in the SAIC TER, the following requests for deviation from Appendix R have been found not necessary and should be withdrawn:
Section 1 ~
I I:ii 2.5 2.8 Title Partial Ratino of Walls and Floor/Ceiling Fire Area D-3 Boundaries 2.3 Based on evaluations in the SAIC TER, adequate justification has not been demonstrated for the following deviation from the provision of Appendix R and this, therefore, remains an open item:
Section
~n IEEil Titie 2.30 Safe Shutdown Analysis - Evaluation of High Impedance Faults
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