ML17285B362
| ML17285B362 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/28/1990 |
| From: | Zimmerman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Oxsen A WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| NUDOCS 9007090004 | |
| Download: ML17285B362 (4) | |
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Docket No. 50-397 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V 1450 MARIALANE,SUITE 210 WALNUTCREEK, CALIFORNIA94596 June 28, 1990 Washington Public Power Supply System P.O.
Box 968 300 George Washington Way Richland, Washington 99352 Attn:
Mr. A. L. Oxsen Assistant Managing Director for Operations Gentlemen:
SUBJECT:
NUCLEAR PLANT NO. 2, REQUEST FOR WAIVER OF COMPLIANCE RELATIVE TO TECHNICAL SPECIFICATION 3.8.1.2, A.C.
SOURCES -
SHUTDOWN In your letter dated June 26, 1990, and in discussions with the NRC staff held on June 27 and June 28, 1990, you requested temporary relief from Technical Specification (TS) requirement 3.8.1.2, "A.C. Sources - Shutdown".
Your letter states that you are requesting a temporary waiver of compliance in order to conduct three inspection and test activities associated with the Division II Emergency Diesel Generator (EDG).
To conduct these activities the Division II EDG must be removed from service.
Since the Division I EDG is currently being repaired off-site, no EDG would be available while the proposed test activities were being conducted.
You concluded that removing the Division II EDG from service for this period of time results in a negligible increase in risk for the following reasons:
It would take approximately two hours to restore the Division II EDG to operable status should that be necessary.
WNP-2 will have been shutdown for 68 days and approximately 28 percent of the core is fuel that makes a negligible contribution to decay heat.
As such, the decay heat level is very low.
Should a loss of offsite power occur, and the full two hour s mentioned above be required to restore the Division II EDG or an offsite power source, the reactor coolant temperature would only increase from the current temperature'of 135 to 159 degrees F.
A temperature of up to 200 degrees F would be acceptable for this condition.
Under the current plant conditions, the spent fuel temperature would increase from 90 to 92 degrees F in a period of two hours.
A temperature of 125 degrees F would be acceptable.
The High Pressure Core Spray with its diesel is available for ECCS and alternate shutdown cooling.
This system could provide adequate decay heat removal for at least four days.
~r V The reliability of the Bonneville Power Association (BPA) grid has been
>> Y evaluated to be very high and a complete loss of power is very improbable.
IIZ>ICNATED OHIGIH 900709000 o50003'>7
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Certifiel Bg I
In addition to those compensatory measures identified in your June 26, 1990 letter, it is our understanding 'that you have agreed to add the following compensatory measures during the time the Division II EDG is out of service:
No work on the on-site electrical distribution systems, or work which can effect the reliability of the off-site ring buss, will be conducted unless concurred in by the Plant Manager.
Arrangements to this effect will be agreed upon between the Supply System and BPA prior to removing the Division II EDG from service.
No work will be conducted on the High Pressure Core Injection System (HPCIS) including all sub-systems necessary for'peration of the HPCIS, unless concurred in by the Plant Hanager.
With the exception of interlock and local leak rate testing of the containment personnel
- hatch, primary containment integrity will be maintained and containment isolation ability will be available.
At a minimum, either the inner or outer door of the containment personnel hatch will be shut at all times.
A 210 KW EDG is available from the Department of Energy.
This generator is available for the use of Nuclear Plant No.
2 during the period the Division, II EDG is removed from service.
Equipment and personnel are available to complete installation, if necessary.
A portable power supply is staged near the Division II generator room with portable lights and connecting cables to be used to provide lighting if offsite power were lost.
A time and task analysis has been conducted by your personnel that substantiates that the EDG can be restored to operability in approximately two hours.
A loss of power recovery plan has also been prepared and approved, which lists the specific actions required to restore the EDG to an operable condition.
The procedures for doing the work on the Division II EDG have been completed and approved in accordance with regulatory requirements.
With your commitments described
- above, as well as discussions with the NRC Office of Nuclear Reactor Regulation (NRR), we have evaluated your request and concluded that your request to take the Division II EDG out of service and conduct the three tests described in your letter of June 26, 1990, is acc'eptable.
Based on the above, a temporary waiver of compliance for the subject Technical Specification only, is granted from 5 a.m.
(PDT), June 29,
- 1990, for a 36-hour consecutive period to expire no later than 6:00 p.m.
(PDT)
July 2, 1990.
All other Technical Specification requirements remain in effect.
If our understanding of your commitments as stated above is not correct, it is necessary that you notify this office prior to removing the Division II EDG from service.
cc:
J. Taylor, EDO J. Sniezek, EDO T.'urley, NRR "F. Mirgalia, NRR D. Crutchfield, NRR J. Larkins, NRR R. Samworth, NRR S. Varga, NRR J.
Lieberman, OE J. Martin, RV Sincerely,
/7 I
R. P.
immerman, Director Division of Reactor Safety and Projects Based on the above, a temporary waiver of compliance for the subject Technical Specification only, is granted from 5 a.m.
(PDT), June 29, 1990, for a 36-hour consecutive period to expire no later than 6:00 p.m.
(PDT)
July 2, 1990.
All other Technical Specification requirements remain in effect.
If our understanding of your commitments as stated above is not correct, it is necessary that you notify this office prior to removing the Division II EDG from service.
Sincerely, cc:
J. Taylor, EDO J. Sniezek, EDO T. Murley, NRR F. Mirgalia, NRR D. Crutchfield, NRR J. Larkins, NRR R. SamworttI, NRR S. Varga, NRR J. Lieberman, OE J. Martin, RV p~
CONCURRENCES:
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PMorri 1 1/nw J Larks ns 6/i7/90 6/A7/90 R. P.
Zimmerman, Director Division of Reactor Safety and Projects pp+
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DCrutc ield RZimmerman 6/~/90 6/9490 ST COPY R
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