ML20037C712
| ML20037C712 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/27/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 8102190638 | |
| Download: ML20037C712 (5) | |
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){fk UNITED STATES
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NUCLEAR REGULATORY COMMISSION 8
WASHINGTON. D. C. 20555
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p January 27, 1980 1
Docket Nos. 50-266 N
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Mr. Sol Surstein
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Wisconsin Electric Power Company
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231 West Michigan Street
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Milwaukee, Wisconsin 53201
Dear Mr. Burstein:
In conducting our review of your December 12, 1975 Technical Specification change request an:! exemption request relating to requirements of 10 CFR 50 Appendix J at Point Beach Nuclear Plant, Units No. I and 2 and follow-up letter dated October 10, 1977, we have determined that we will need the additional information identified in the enclosure to continue the review.
In order for us to maintain our review schedule, your response is requested within 30 days of your receipt of this letter. Three signed originals and forty copies are required.
Please contact us if you have any questions concerning this request.
Sincerely, f(,0[, c, V Gu
,n Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page B10219 0 tloN.
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Mr. Sol Burstein Wisconsin Electric Power Company Mr. William Guidemond Mr. Bruce Churchill, Esquire USNRC Resident Inspectors Office cc:
Shaw, Pittman, Potts and Trowbridge 6612 Nuclear Road 1800 M Street, N.W.
Two Rivers, Wisconsin 54241 Washington, D. C.
20036 Joseph Mann Library 1516 Si~xteenth Street Two Rivers, Wisconsin 54241 Mr. Glenn A. Reed, Man.?ger Nuclear Operations Wisconsin Electric Pcwer Cecpany Point Beach Nuclear Plant 6510 Nuclear Road Two Rivers, Wiscensin 54241 Mr. Gordon Blaha Town Chairman Town of Two Creeks Route 3 Two Rivers, Wisconsin 54241 Ms. Kathleen M. Falk General Counsel Wisconsin's Environmental Decade 302 E. Wishington Avenue Madison, Wisconsin 53703 Director, Criteria and 5candards Divisien Office of ?.adiaticn Prograns (AN3-L60)
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U.S. I:rtirc:5: ental Protecti:n Agency Washington, D.C.
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U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
EIS COORDINATOR 230 S..Dearborn Street Chicago, Illinois 60604 Chairman Public Service Cocmission of Wisconsin Hill Farms State Office Bufiding Madison, Wisconsin 53702
REQUEST FOR ADDITIONAL INFORMATION f CONTAINMENT LEAKAGE RATE TESTING WISCONSIN ELECTRIC POWER COMPANY l POINT 3EACH UNITS 1 AND 2
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l NRC DOCKET NO.
50-266, 50-301 NRC TAC NO-C7711, 06404 I
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1.
BACKGROUND In a letter dated December 12, 1975, Wisconsin Electric Power Company (WEP) requested certain exe=ptions from the requirements of 10CFR50, Appendix J.
Additionally, follo. ring a containment integrated leakage rate test at i
Point Beach Unit 1 in October 1977 which was observed by NRC Region III person-nel, several questions were raised as to the status of the containment leakage testing program at Point Beach in so far as compliance with Appendix J is con-cerned.
2.
INFORMATION REOUIRED 2.1 CONTAINMENT INTEGRATED 1.EAKAGE PATE (TYPE A) TESTING In Ites I.A of the December 12, 1975 letter, WEP coccitted to venting and draining certain systems in crder to comply with the requirements of Appendix J,Section III. A.1. (d), while conducting the Type A test. Ecwever, in reply to certain NP.C concerns resulting from the observation of a Type A test at Unit 1 in Octcher 1977. WEP f:rwarded a letter dated October 10, 1977 in which WEP indicated objections to certain requirerents of Appendix J with regard to venting and draining reactor coolant systems.
Provide the following information needed to complete our review of the implementatien of Appendix J at Point Beach relative to the venting and draining of the reactor coolant system and siailar MRC concerns identified during the October 1977 Type A test.
1.
I.ist the specific deviations from the requirements of Section III. A. l. (d) with regard to the venting and draining of syste=s in preparation for a T pe A ccst and provide justi-j fication for each deviation.
2.
Identify procedures used to correct the results of the Type A test to account for repairs to valves which were isolated from the Type A test because of excessive leakage.
3.
Identify the time period specified in your procedures as the minimum required to perform a Type A test. Provide justi-fication for this time period.if it is less than the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> required by ANSI N45.4-1972.
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I 2.2 CONTAINMENT /.iRI.0CK TF. STING In Ite= II.A of the December 12, 1975 letter, WEP reqasted an exemption f rom the requirerents of Appendix J Section III.D.2, which requires an airlock test af ter each use.
In a. letter dated July 18, 197.7, kI? emphasited that, although the airlock doors are designed with a double-gasketed seal, the design did not allow testing between the gaskets at near-design pressures. bT.? anti-cipated that no more than 3 to 5 psig could be put between the 0-rings 'and that repeatability was unknown.
Section III.D.2 of Appendix J, regarding testing of airlocks, was revised as of October 22, 1980.
This revised section was published in the Federal Register / Vel. I.5, No. 183/ Monday, Sep tember 22,1980/ Rules and Regulations (pg. 62789).
Provide an airlock testinc program whi:h satisfies the requirements of the revised Sectien III.D.2.
If a reduced pressure test is te be used to satisfy the 3-day testing requirement, a method to extrapolate the reduced pressure test results to Pa should be provided.
2.3 CCNTAINMENT SPRAY SYSS CHECK VA1.\\TS In Ites III.C of the Dece=ber 12, 1975 letter, WEP requested an exemption f rom the Type C testing requirements of Appendix J,Section II.H.3.
In a i
second letter dated July 18, 1977, WEP further stated that there is no adverse effect due to leakage back through these valves with regard to radiation exposure because the fluid on the outlet side is the same as the fluid on the inlet side of the valves.
With respect to the above state =ent, provide a basis for the implied i
assumption that there is suf ficient fluid inventory in this system to prevent the eventual back-leakage of containment atscsphere, with resultant release to the surrounding atmosphere, throughout the post-accident period.
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