ML20062C431
| ML20062C431 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/18/1990 |
| From: | Engle L Office of Nuclear Reactor Regulation |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| Shared Package | |
| ML20062C434 | List: |
| References | |
| TAC-68572, TAC-68573, NUDOCS 9010310231 | |
| Download: ML20062C431 (4) | |
Text
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UNITED STATES o
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s, ).C WASHINGTON, D C. 20555 October 18, 1990
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Docket Nos. 50-338 and 50-339 Mr. W. L. Stewart Senior Vice President - Nuclear Virginia Electric and Power Company 5000 Dominion Blvd.
Glen Allen, Virginia 23060
Dear Mr. Stewart:
SUBJECT:
SAFETY EVALUATION TOR STATION BLACK 0UT (SBO) RULE FOR NORTH ANNA POWER STATION, UNITS NO. 1 AND NO. 2 (NA-182) (TAC NOS. 68572 AND 68573) i By letters dated April 17, 1989 April 20, 1989 and March 30, 1990, you l
submitted responses to the SB0 rule for NA-182. The responses were reviewed by an NRC contractor, Science Applications International Corporation (SAIC) and the NRC staff.
Enclosed is our Safety Evaluation (SE andtheassociatedSAICTechnicalEvaluationReport(TER))SAIC-90/1370,of your resp
" North Anna Power Station, Units 1 and 2, Station Blackout Evaluation,"
dated September 24, 1990 (Attachment 1 of the enclosure). NA-182 presently has four emergency diesel generators (EDGs), with two EDGs dedicated to each unit. You propose additional switchgear and electrical connections between the 4160V buses of Units 1 and 2 so that either one of the two EDGs of one unit couldserveasanalternateAC(AAC)powersourcefortheoppositeunit during an SB0 on the opposite unit.
Your submittal states that the proposed AAC source is available within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the onset of the SB0 event, and has sufficient capability to provide power for the safe shutdown of both units for an 8-hour SB0 duration.
However, a July 2,1990 telefax to the NRC from you, showing a preliminary) tabulation of loads on the AAC source (non-blackout (NBO) and blacked-out (BO unit loads) did not include several of the normal loss-of-offsite power loads on the NB0 unit. Subsequently, during a telecon on July 3 1990, you discussed a proposed load management scheme en the NB0 unit that would be applicable Surry and NA-182. The staff stated that such load management on the NB0 unit in order to make excess capacity available from the AAC source to the SB0 unit did not conform to the SB0 rule. By letter dated August 1,1990 revised tabulation of the AAC source loading (NB0 and SBd you submitted aunit loads) for Surry Power Station. No similar tabulation was presented for NA-182. However, the staff understood that the above revised tabulation also applied to NA-1&2.
The revised tabulation for Surry excluded normal LOOP loads such as the residual heat removal pumps and the turbine generator auxiliaries.
Even with these loads excluded, the )ercent capacity margin of the AAC source was 3 percent less compared to tie actual SB0 loads.
Based on the July 2, 1990 preliminary tabulation of the AAC loads for NA-182 and the revised August 1, 1990 tabulation for Surry (assumed to apply to NA-1&2), the staff concludes that the NA-1&2 EDGs do not have the excess capacity available to qualify them l
as an AAC sou ce, po 28u M$8*
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2 The staff has reviewed your proposed actions and finds that they do not conform to the guidance on the use of existing EDGs as an AAC power source as documented in the 10 CFR 50.63, Regulatory Guide (RG) 1.155 Position C.3.3.5, NUMARC 87-00 Section 2.3.1(3), and NUMARC 87-00 Supplemental Questions and Answers dated December 27, 1989.
The areas of non-conformance are identified in the enclosed Safety Evaluation (SE).
In addition, the following areas.aay require follow-up inspection by the NRC to verify that the implementation of any modifications and the supporting documentation which you may propose as a result of this evaluation are adequate to meet the SB0 rule.
Inspection guidance for this is being developed.
a.
Hardware and procedural modifications, b.
SB0 procedures in accordance with RG 1.155, Position 3.4, and NUMARC 87-00, Section 4, c.
Operator staffing and training to 'ollow the identified actions in the SB0 procedures, d.
EDG reliability program meeting, as a minimum, the guidelines of RG 1.155, e.
Equipment and components required to cope with an SB0 are incorporated in a QA program that meets the guidance of RG 1.155, Appendix A, and f.
Actions taken pertaining to the specific recomendations noted in the SE.
TheguidanceprovidedonTechnicalSpecifications(TS)for.anSB0statesthat the TS should be consistent with the Interim Commission Policy Statement on Technical Specifications. The staff has taken the position that TS are required for SB0 responso equipment. However, the question of how specifications for the SB0 equipment will be applied is currently being considered generically by the NRC in the context of the Technical S)ecification Improvement Program and remains an open item at this time.
In t1e interim, the staff expects plant procedures to reflect the appro)riate testing and surveillance requirements to ensure the operability of tie l
necessary SB0 equipment.
If the staff later determines that TS regarding the
)
SB0 equipment is warranted, you will be notified of the implementation requirements.
A revised response to the SB0 rule which addresses the areas of non-conformance should be submitted for staff review within 60 days of receipt of this letter.
Subject to an acceptable resolution of the identified non-conformances, the issue of conformance to the 580 rule remains an open item at NA-1&2.
3 The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respondents; therefore, OMB clearance is not required pursuant to P. L. 96 511.
Sincerely, (Original Signed By)
Leon B. Engle, Project Manager Project Directorate 11-2 Division of Reactor Projects. I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
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STEWART MEM0 2
Mr. W. L. Stewart North Anna Power Station Virginia Electric & Power Company Units 1 and 2 cc:
Mr. William C. Porter, Jr.
C. M. G. Buttery, M.D., M.P.H.
County Administrator Department of Health Louisa County 109 Governor Street P.O. Box 160 Richmond, Virginia 23219 Louisa, Virginia 23093 Regional Administrator, Region !!
Michael W. Maupin, Esq.
U.S. Nuclear Regulatory Commission Hunton and Williams 101 Marietta Street N.W., Suite 2900 P. O. Box 1535 Atlanta, Georgia 30323 Richmond, Virginia 23212 Mr. W. T. Lough Virginia Corporation Commission Mr. G. E. Kane, Manager Division of Energy Regulation North Anna Power Station P. O. Box 1197 P.O. Box 402 Richmond, Virginia 23209 Mineral, Virginia 23117 Old Dominion Electric Cooperative Mr. J. P. O'Hanlon c/o Executive Vice President Vice President - Nuclear Services Innsbrook Corporate Center Virginia Electric and Power Company 4222 Cox Road, Suite 102 5000 Dominion Blvd.
Glen Allen, Virginia 23060 Glen Allen, Virginia 23060 Mr. E. Wayne Harrell Mr. R. F. Saunders Vice President - Nuclear Operations Manager - Nuclear Licensing Virginia Electric and Power Co.
Virginia Electric and Power Company 5000 Dominion Blvd.
5000 Dominion Blvd.
Glen Allen, Virginia 23060 Glen Allen, Virginia 23060 Mr. Patrick A. O' Hare Office of the Attorney General Supreme Court Building 101 North 8th Street Richmond, Virginia 23219 l
Senior Resident Inspector North Anna Power Station U.S. Nuclear Regulatory Commission Route 2, Box 78 Mineral, Virginia 23117 L