ML25197A082
| ML25197A082 | |
| Person / Time | |
|---|---|
| Issue date: | 10/16/1975 |
| From: | Kerr W Advisory Committee on Reactor Safeguards |
| To: | Anders W NRC/Chairman |
| References | |
| Download: ML25197A082 (1) | |
Text
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 October 16, 1975 Honorable William A. Anders Olairman
- u. s. Nuclear Regulatory Conmission Washington, D.C. 20555 SUbject:
REroRT CE ~
STERLn1; FOJER PRO.JEC'l' NOCLFAR mIT 1
Dear Mr. Anders:
Iuring its 186th meeting, Cktober 9-11, 1975, the Advisory Conmittee on Reactor Safeguards reviewed the application of Rochester Gas and Electric Corporation for a permit to construct the Sterling Power Project, Unit I<<>. 1. 01 September 24, 1975, the site was visited and a Subcarmittee meeting was held in Sterling, New York to review site-related matters. '!he *standardized Nuclear Unit Power Plant System* (SNUPPS) to be utilized at the Sterling site, and at three other plant sites, was reviewed at Subconmittee meetings held at Washington, D. C. on August 19, 1975, and at &rp:>ria, Kansas on September 26, 1975, and at the 185th and 186th meetings of the Conmittee. ruring its reviews, the Conmittee had the benefit of dis-cussions with the Nuclear Regulatory Conmission (Nie) Staff and repre-sentatives of the applicant, the westinghouse Electric Corporation and the Bechtel Corporation. '!he Conmittee also had the benefit of the docl.Bllents listed below.
'!he Sterling unit will be located on a 280G-acre site of partially wooded rural land located on the southeastern shore of lake Oltario, approximately 7 miles southwest of OSwego, New York the nearest popu-lation center (1970 population: 23,844). '!he minimum exclusion area boundary distance from the center of the reactor building is 1190 meters.
Part of the exclusion area exteoos into Ia.ke Oltario.
In the event the applicant is unable to gain control over those three acres of shore land within the exclusion zone which he does not now own, the minimum exclu-sion area boundary distance will be reduced to 945 meters. me staff calculations indicate that the applicant can meet the siting dose guide-lines at this reduced distance without additional engineered safety features.
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It>norable William October 16, 1975 less for l 7xl 7 assemblies than for a lSx:15 array, the Comni ttee believes that the applicant should continue stooies that are responsive to the COnmittee's septanber 10, 1973 report. If stooies establish that signifi-cant further ECCS improvements can be achieved, consideration should be given to incorporating them into this unit.
'lhe part of the exclusion zone which extends into rake Oltario, including the points of intake and discharge of e:nergency service cooling water, will be under control of the Ulited States Coast Guard. 'lhe Conmittee recorrmends that the NRC staff and the applicant give particular attention to assure proper coordination between the applicant and the Coast Guard appropriate to protection of the e:nergency equipnent.
'lhe Conmittee believes that the applicant and the NRC staff should continue to review the Sterling plant design for features that could reduce the possibility and consequences of sabotage.
'lhe Conmittee recorrmends that the NRC staff and the applicant review the design features that are intended to prevent the occurrence of damaging fires and to minimize the consequences to safety-related equipnent should a fire occur. 'Ibis matter should be resolved to the satisfaction of the NRC Staff. 'lhe Conmittee wishes to be kept infonned.
Generic problems relating to large water reactors are discussed in the Conmittee's report dated March 12, 1975. 'lhese problems should be dealt with appropriately by the NRC staff and the applicant.
'lhe Advisory Conmittee on Reactor Safeguards believes that the items mentioned above and the items mentioned in its callaway letter, which are relevant to the Sterling application, can be resolved during construc-tion and that if due consideration is given to the foregoing, the Sterling Power Project Nuclear Ulit No. l can be constructed with reasonable assur-ance that it can be operated without undue risk to the health and safety of the public.
Sincerely yours,
- w. Kerr Olairman 1602
Honorable William October 16, 1975
'!he SNOPPS will utilize the RESAR-3 consolidated Version, four-loop pressurized water nuclear reactor with a core power output of 3411 MW(t).
'lhis design is similar to that utilized at the Comanche Peak Steam Elec-tric Station, Units land 2, reported on by the Comnittee in its letter of Q:tober 18, 1974. 'lhe Comnittee's continuing review of the SNUPPS was reported on in its callaway letter of September 17, 1975, and is further reported on in this letter. It is anticipated that the Com-mittee's report on the remainder of its review of SNOPPS will be included in its report on the 'fyrone ai;.plication.
'!he NBC Staff has identified several items in its review of the Sterling application which are not yet carpleted. '!he COnmittee reconmends that any outstanding issues which may develop in the course of canpleting these reviews be dealt with in a manner satis-factory to the NRC Staff. '!he Comnittee wishes to be kept informed on the resolution of the following items:
- 1. 'lhe emergency core cooling system evaluation in carpliance with the Final Acceptance Criteria.
- 2. '!he analyses of the effects of anticipated transients without scram.
- 3. '!he evaluation of the plant design to neet the requirements of the new Appendix I of 10 CFR Part so.
'!he R&SAR-3 consolidated Version nuclear design utilizes the Westing-house l 7xl 7 fuel assembly. testinghouse has identified an integrated test program to confirm the safety margins associated with this design, which it plans to carplete late this year. '!he RESAR-3 reactor core design has been calculated by i'estinghouse to be stable against radial xenon oscillations. ~stinghouse has agreed to verify this stability in a startup physics test for a 193 fuel assembly core similar to-SNUPPS.
'!he Ccmnittee will continue to review these matters as appropriate docu-mentation is submitted.
'!he Ccmnittee reconmended in its report of September 10, 1973, on acceptance criteria for ECCS, that significantly improved ECCS capability should be provided for reactors for which construction permit requests are filed after January 7, 1972. '!he SNUPPS design is in this category.
'lhese units will use the 17xl7 fuel assemblies similar to those to be used in Comanche Peak Steam Electric Station, Units 1 and 2. Although calculated peak clad temperatures in the event of a postulated IOCA are 1601
Honorable William Cktober 16, 1975
- 1. SNOPPS Preliminary Safety Analysis Report with Revisions 1 through 10 and the Sterling Site Addendum Report with Revisions 1 through
- 11.
- 2. RESAR-3 Consolidated version, testinghouse Reference Safety Analysis Report with Amendnents 1 through 6.
- 3. Safety Evaluation Report, NOROO 75/082 related to the Construction of the Sterling R:>wer Project, Nuclear Ulit No. 1, n>cket No. S'DI 50-485, September, 1975.
- 4. ~solution by the Town of Sterling Town Pioard, dated May 12, 1975.
- 5. Ietter dated September 17, 1975, fran Ms. sue Reinert, F.cology Action of Oswego.
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