ML20235K880

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Forwards Safety Evaluation Re Reactor Pressure Vessel Flaw. Flaw Meets Analytical Evaluation Criteria in Article IWB-3600 of ASME Code Section XI & Reactor Vessel Acceptable for 40 Yrs of Svc Life of Plant
ML20235K880
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 07/09/1987
From: Wagner D
Office of Nuclear Reactor Regulation
To: Fay C
WISCONSIN ELECTRIC POWER CO.
Shared Package
ML20235K884 List:
References
TAC-65440, NUDOCS 8707160473
Download: ML20235K880 (2)


Text

T JUL 0 91987 Docket Nos. 50-266 DISTRIBUTION:

,DocketJiles< EJordan NRC PDR JPartlow Local PDR JPartlow PDIII-3 r/f ACRS(10)

PDIII-3 s/f GHolahan PKreutzer Mr. C. W. Fay, Vice President DWagner Nuclear Power Department DWigginton Wisconsin Electric dower Company OGC-Bethesda 231 W. Michigan Street, Room 308 Milwaukee, Wisconsin 53201 l

Dear Mr. Fay:

SUBJECT:

POINT BEACH NUCLEAR PLANT UNIT 1, REACTOR PRESSURE VESSEL FLAW (TAC #6544D)

During a scheduled inservice inspection of the Point Beach Nuclear Plant Unit 1 (PBNP-1) reactor pressure vessel, Wisconsin Electric Power Company detected an ultrasonic flaw that appeared to exceed the acceptance standards of Article IWB-3500 of ASME Code Section XI. Wisconsin Electric Power Company performed an analytical evaluation of the flaw in accordance with the criteria in Article IWB-3600 of ASME Code XI. The evaluation was submitted for our review in a letter dated June 2, 1987.

We have completed our review of the submittal. Our evaluation is contained in the enclosure to this letter.

Weconcludethattheflawmeetstheanalytical.f evaluation criteria in Article IWB-3600 of ASME Code Section XI and the reactor vessel is acceptable for the 4D years of service life of the plant.  !

We consider this flaw to be conditionally acceptable in accordance with subarticle IWB-3123 of Section XI of the ASME Code and, therefore, require i augmented inservice inspections based on 10 CFR 50.55a(g)(4). We require that l the best available techniques and instrumentation be used during the next I inservice inspection to evaluate the flaw. Additionally, we require that you provide a report at least 6 months before the scheduled outage describing detailed plans for this inspection. We intend to perform a detailed review of the examination results to determine whether the flaw has been accurately sized and growth has not occurred.

l Sincerely, e707160473 870709 e PDR ADOCK 05000266 )

P PDR l

David H. Wagner, Project Manager Project Directorate III-3 Division of Reactor Projects

Enclosure:

Safety Evaluation l cc: See next page ,

Office: LA/{D,yI-3 'fM/PEhl-3 PD/PDIII-3 Surname: PKrett'zer DWagner/tg DWigginton Date: 07/7/87 07/ /87 07/}/87

Mr. C. W. Fay Point Beach Nuclear Plant Wisconsin Electric Power Company Units 1 and 2 cc:

Mr. Bruce Churchill, Esq.

Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.

Washington, DC 20037 Mr. James J. Zach, Mar,ager Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Town Chairman Town of Two Creeks Route 3 Two Rivers, Wisconsin 54241 Chairman Public Service Commission of Wisconsin Hills Farms State Office Building Madison, Wisconsin 53702 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 799 Roosevelt Road l Glen Ellyn, Illinois 60137 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, Wisconsin 54241

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