ML20094P310
| ML20094P310 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 03/27/1992 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-REGGD-01.155, RTR-REGGD-1.155 TAC-M68564, TAC-M68565, NUDOCS 9204070342 | |
| Download: ML20094P310 (6) | |
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h DUKEPOWER March 27, 1992 U.
S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.
C.
20555
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Subject:
McGuire Nuclear Station, Units 1 and 2 Decket Nos. $0-369 and 50-370 Station Blackout (SBO).(10 CFR 50.63)
Fesponse to NRC Recommendations (TACS M68564/M68565)
Reference Letter from T.A. Reed (NRC) to T.C. McMeekin(DPC),
dated February 19,1992 Dear Sir;
.By a February 19, 1992 letter, the NRC transmitted.its Safety Evalvetion Report (SER) and supporting Technical Evaluation Report (TER) of their review of ths-Duke Power Company's response to the SB0 rule for the McGuire Nuclear Station.
The NRC' staff found that the McGuire-Nuclear Station design conforma with the SB0 rule, the Guidance of Regulatory Guide 1.155, NUMARC 87-00, and NUMARC 87-00 Supplemental Questions / Answers and Major Assumptions (dated December 27, l
1989), contingent upon the satisfactory resolution of the L
recommendations identified within the SER.
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You: lette.t of February 19, 1992, requested that we review the recommendations and to submit a response within 30 days of_ receipt of the SER in accordanes with 10 crR 50.63(c){4)..
Accordingly, please find attached-the documentation of the results of our evaluation of-the recommendations.
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9204070342 920327 POR ADOCK 05000369 P
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U.
S. Nuclear Regulatory Commisston March 27, 1992 page 2 If you have any questions regard 1.ng this matter, pleara contact Paul Guill at (704) 875-4')02.
Very truly yours, llc Y,n y,
Ted C. McMeekin, Vice President McGuire Nuclear Site
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Ebneter Regional Administrator, Region II P.
K. Van Doorn Senior Resident Inspector, McGuire 1,'
T.
A. Reed, Project Manager ONRR h
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E. Nuclear Regulatory Commission idarch 27, 1992 page 3 1
bxc: with attachment G. D. Gilbert R. O.
Sharpo K. P. Mullen L. J.
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F. Guill K.
J. Caldwell L.
Brown B.
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R. L. Gill (NS)
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W. N. Matthews R.
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ATTACHMENT DUKE POWER COMPANY MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 STATION BLACKOUT RULE, (10 CFR 50.63)
RESPONSE TO NRC RECOMMENDATIONS NRC Recommendation _11 The licensee should ensure and confi m the accessibility to the above cited valves and the habitability in the areas where those valves are located during an SBO event.
DPC RESPONSE lt The cited valvos mentioned in the NRC SER are the steam generator safety valves (SVs), the atmospheric dump valvos (ADVs), and tho-AFW flow control valves.
Further, the SER stated that during an GBO event, that the SVs would be used to remove decay heat and if cooldown was necessary, pursuant to procedure ECA 0.0, that the ADvs would be operated manually.
Before responding to this recommendation, clarification of what valvos and which procedure would be used to cooldown during an SBO event is warranted.
If it became necessary to cooldown the plant during an SBO event tho steam generater Power Operated Rollof Valves (PORVs) would be manually operated instead of the ADVs referred to within thu NRC CER, as specified by procedure EP/1(2)/5000/09.
In addition, plasse note that the SVs do not require any manual action at the valvo location in order for it to function during an SBO event.
Accordingly,:the recommendation regarding the steam generator _SVs is considered by Duke to be fully addressed and-thorofore closed.
Two cf the steam generator PORVs are located in the outboard doghouse at McGuire.
The outboard doghouses are not a dominant area of concern as they are vented to the outside environment and are not provided with forced ventilation.
Therefore, the SBO environment would not be different from the normal operating onvironmont.
The other two steam generators PORVs are locatea in the inborard doghouses.
The inboard doghouses have been classified as a dominate area of concern._
If plant cooldown was necessary during an SBO event, the two PORVs within the outboard doghouse wou.1d be sufficient for cooldown.
Duke considers the portion of this recommendation pertaining to the steam generator
-PORVs fully addressed and f.herefore closed.
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The AFW flow control valves are located in the CA pump rooms at McGuire.
The AFW pump room is identified as a dominant area of concern. Although the valves are located in the AFW pump rooms, the expected temperature should not preclude manual operation of those valves.
Duke considers the portion of this recommendation pertaining to the AFW flow control valves fully addresend and therefore closed.
I NRC Recommendation 2:
The licenseo should ensure the accessibility and habitability in thene areas for the manual operation of the AFW flow control valves during an-S80 ovent.
DPC RESPONSE __2 This recommendation appears to be the same as Recommendation 1, as such, please see Response 1 pertaining to the AFW flow control valves.
Duke considers this recommendation fully addressed and therefore closed.
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NRC Recommendation 3:
The 11censeo should provide a procedure which will require the operators to open instrument cabinet doors within 30 minutes i
fallowing an SB0 in accordance with the guidance described in NUMARC 87-00.
DPC RESPONSE 3:
3 i
AP/0/5500/39, Control Room High Temperature procedure, contains instructions for opening the instrument cabinet doors duo to high l
control room temperature.
The, opening of the cabinets is i
performed based on the following observed symptoms; 9
- 1) Increasing. control room temperature
- 2) Control room air handling supply unit high temperature alarm
- 3) Control room area chiller high temperature alarm 1
Duke considers this recommendation fully addressed and therefore closed.
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o NRC__. Recommendation 4:
The licensee should verify that no manual operation of SBO response equiprent in the annulus and mechanical penetration rooms is required during an SBO event.
DPC RESPONSE 4:
There is no 6B0 response equipment within the annulus that requires manual operator action during an SBO event.
Accordingly, Duke considers this portion of the recommendation pertaining to the annulus fully addressed and therefore closed.
The Loss of all AC power procedure, EP/1(2)/A/5000/09, does instruct the operator to close certain valves that are located within the mechanical penetration rooms.
This action is only undertaken if certain valves can not be closed from the Standby
-Shutdown Facility (SSF); or if the SSF standby makeup pump fails to start; or if LOCA conditions exist.
This action is only undertaken as a precautionary step, due to some failure or if a certain response is not observed.
Accordingly. the recommendation pertaining to the mechanical penetration rooms is considered by Duke to be fully addressed and thus closed.
NPC Recommendation 5:
'he-licensee should provide confirmation and include in the Tdocumentation supporting the SBO submittal that a program meeting as a minimum the guidance of RG 1.155, position 1.2, is in place or will be implemented.
DPC__ RESPONSE h Duke Power Company currently has in place for McGuire a program which is designed to maintain the reliability of the emergency power sources.
This program includes, among other things, maintenance, testing, surveillance, and root cause investigation.
-Additionally, Duke Power Company is closely following the progress of Generic Issue B-56.
Upon resolution of this Generic Issue, Duke Power Company will review its emergency power source reliability program and make changes as necessary.
Duke power l
Company considers this recommendation fully addressed and therefore closed.
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