ML19322D172
| ML19322D172 | |
| Person / Time | |
|---|---|
| Site: | Crane, Washington Public Power Supply System  |
| Issue date: | 06/11/1975 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Anders W NRC COMMISSION (OCM) |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8002100011 | |
| Download: ML19322D172 (4) | |
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NUCLEAR REGULATORY COMT.11SSION WASHING ton. D. C. 20555 June 11, 1975 I
i Honorable William A. Anders Chairman
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U. S. Nuc1 car Regulatory Co enission Washington, D. C.
20555
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Subject:
REPORP Ot3 WASimUIQ3 PUBLIC PO1ER SUPPLY SYSTEM UUCLEAR POWER STATIOt1S h7IP 1 and 4
Dear Mr. Anders:
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At'its 182nd meeting, June 5-7, 1975, the Advisorf Comittee on Reactor Safeguards completed its review of the applicatioAof M A-f the Washington Public Power Supply System for permission d constr i
the Washington Muc1 car Power (h?iP) Stations 1 and 4.
W ese plants were previously considered at a Subcommittee meeting on May 16, at Richland, 9
Washington, and the site was visited on May 15, 1975. During its review the Conmittee had the benefit of discussions with representatives of Washington Public Power Supply System and consultants, the s
Babcock and Wilc.ox Company (B&ti), and the NRC Staff. no Committee.
3 also had the benefit of the doctrnents listed.
%c WNP Station site is located on the Energy Research and Development Administration's IIanford Reservation in Benton County, Washington, eight miles north of Richland, Washington, the nearest population center (1970 population 26,290). n e exclusion radius is 6400 feet. We low population zone is four miles in radius.
In 1970 there were 38 residents within the low population zone.
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%e Fast Flux Test Facility and WPPSS Hanford-2 (N P-2) Reactor
,~4 are the only installations within the low population zone.
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he safe shutdown carthquake is 0.25g horizontal acceleration at
. i's the foundations. % e operating basis carthquake is 0.125g.
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which is not Seismic Categccy L. and Seismic Category I spray ponds designed to provide a 30 day emergency water supply for each unit.
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Honorable william A. Anders June 11, 1975
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%e nucicar steam supply system supplied by B&W is identical in design to that of Dellefonte Nuclear Plant, Units 1 and 2, i
previously reported on in the ACRS letter of July 16,1974.
%e design operating power is 3600 m(t). %e reactor core will user 205 B&W Park C (17x17) fuel assemblies. %e Comnitteo
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'recommnded in its report of January 7,1972, on Interim 5
Acceptance Criteria for ECCS, that significantly improved ECCS capability should be provided for reactors for which construction
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permit applications were filed after January 7,1972. %is position was repeated in its report of Septcirlier 10,1973, on
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Acceptance Criteria for ECCS. %e Mark C fuel assemblies are responsive to this reconmndation. %e new fuel assemblies will J
be operated at lower linear heat generation rates and are expected to yield greater thermal rargins for fuel design limits and improved safety margins in the analyses of the loss of coolant b
accidents, An extensive program has been initiated for i
determining the mechanical and thermal / hydraulic characteristics
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of the new fuel assem1511er, A program of control rod tests also J
'is proposed, incitding testing of trip times and control rod Should modifications become necessary as a result of the a
wear.
i control rod tests, rotesting of the entire control rod drive muld be undertaken. hhile many of the details of the proposed design 9
are available, complete analyses of the performance of the Mark C fuel are not yet available, and the NRC Staff has not completed
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its review. We Committee reserves judgment concerning the final
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design until the required performance information is presented and has been reviewed. %e Committee recommends that the applicant i
continue sttdies directed at further improvement in the capability and reliability of the ECCS. %e Conmittee wishes to be kept informed.
We NRC Staff has determined that the ECCS performance evalua-tion for WNP Stations 1 and 4 meets the Interim Acceptance Criteria-G.
of June 1971.
In addition the Applicant's ECCS performance g
evaluation, using an approved B&W model, to show compliance with.the q
Final Acceptance Criteria of 10CFR50.46 and Appendix K, must be W
reviewed and approved by the NRC Staff. %e Committee wishes to h 3-kept informed.
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% e applicant proposes to utilize a new reactor protection
' 0, system designated as RPS-II. %e sy5 tem, a hybrid using both 9
analog and digital techniques, represents an evolution from the i.
analog system, RPS-I, currently in use in the Cbonee reactors.
Jp ne applicant has proposed a series of environmental, reliability, 10 and in situ tests for qualification of this system prior to v
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Honorable William A. Anders June 11, 1975
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Its use in Bellefonte Units 1 and 2, the lead plant. %is
.mtter should be resolved in a manner satisfactory to the NRC dtaff.
A problem considered to be generic by the ACRS is the environ-nontal and seismic qualifications of Class I instrumentation i;
and electrical equipment. An important aspect is that of
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defining what represents an acceptable aging procedure for multi-component systems. %is issue should be resolved by
'.J the applicant and the imC Staff. 'Ihe Committee wishes to e,,
be kept informed.
1.A A question has arisen concerning loads on the vessel support structure for certain postulated loss-of-coolant accidents C~-
in pressurized water reactors. % is matter should be resolved
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for the WNP 1&4 Plants, in a manner satisfactory to the NRC
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Staff.
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Generic problems relating to large water reactors have been identified by the NRC Staff and the ACRS and discussed
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problems should be dealt with appropriately by the imC Staff b;j and the applicant.
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%e Mvisory Co:anittee on Reactor Safeguards believes that the items mentioned above can be resolved during construction J
and that, if due consideration is given to the foregoing, the Washington Public Power Supply System Plants WNP 1 and 4, can be constructed with reasonable assurance that they can be N
operated without undue risk to the health and safety of the 2.?t public.
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Sincerely yours, l
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&L William Kerr
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Chairman l
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'; 3 Referenc'es Attached.
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Ilonorable William A. Anders June 11, 1975 b,:
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References t
1.
Preliminary Safety Analysis Report, Washington Nuclear u
Projects 1 and 4.
(Including Amendrients 1 thru 17).
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" Safety Evaluation of the Washington !!ucicar Projects 1 and
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4", NUREG - 75/036, Docket tbs. 50-460, 50-513, May, 1975, 4
ONRR, U. S. Nuclear Regulatory Conmission, Washington, D. C.
.g 3.
WPPSS Intter dated May 14, 1975, J. J. Stein to Angelo f.
Giambusso, DRL, ONRR, USNRC,
Subject:
WPPSS Nuclear 3
Projects Nos.1 and 4, On-site !btcorological data.
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Supplerent 1. to the Safety Evaluation Report, Intter from
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Voss A. ! bore, Asst. Dir. for Light Water Reactors, Group 2 Division of Reactor' Licensing, USNRC to Dr. William Kerr,
.I Chairman ACRS dated June 2,1975.
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