ML19254F235

Informs That Util Meets Commitments Re Pipe Stress Evaluation Program.Of 989 Pipe Supports Originally Requiring Review,Only 37 Require Mods

ML19254F235
Person / Time
Site:	FitzPatrick
Issue date:	11/02/1979
From:	Early P POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Ippolito T Office of Nuclear Reactor Regulation
References
JPN-79-71, NUDOCS 7911070410
Download: ML19254F235 (4)

Text

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POWER AUTHORITY OF THE STATE OF NEW YORK to CoLUMeus CIRCLE NEW YORK. N. Y. loo 19 (2126 397.6200 TRUSTEES GEORGET. BERRY JQHN S.DYSON ",",',*',C,',"T,*,,C,",'g'g#,

CMA!RMAM GEORGE L. ING ALLS E ECu svE V CE

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RICH ARD M. FLYN N JCSEPH R. SCHMIEDER EXECuflVE VICE ROSERT 1. MILLONZI PRE CENT & CHIEF rREDERicx R. CLARK November 2, 1979 L E R Og.,s m cy,,,,,,,

JPN-79-71 . CmEr n A Cm.

OFFICER THOM AS R. FR EY SENIOR VICE PRESIDENT

& GENERAL COLNSEL Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Thomas A. Ippolito, Chief Operating Reactors Branch No. 3 Division of Operating Reactors

Subject:

. James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Pipe Stress Reevaluation Program

Reference:

NRC Letter dated August 14, 1979, Docket No. 50-333, Edson G. Case to George T. Berry

Dear Sir:

The referenced letter issued an Order lifting the suspension of facility 7peration required by the Order to Show Cause dated March 13, 1979, for the James A. FitzPatrick Nuclear Power Plant.

The Order which lifted suspension of facility operation specified certain commitments made by the Authority to the NRC.

This letter restates these commitments below, and indicates that the Authority has now fully met each of these commitments.

1. That all modifications to correct all piping systems, equipment nozzles and containment penetrations and all modifications to supports located in areas inaccessible during normal plant operation shall be completed prior to plant start-up.

This commitment was met, as reported to you in our letters of August 2, 1979, August 10, 1979, and August 14, 1979. Our letter of September 5, 1979 i advised you that ascent in power commenced on 0 September 3, 1979. g 10 1'"2 183 7911070Y/O f

U. S. Nuclear Regulatory Commission 2. That the Authority shall both complete reanalyses of the remaining pipe supports in areas accessible during normal plant operation and propose a schedule for implementation of any necessary modification within sixty-(60) days of plant start-up.

This letter notifies you that reanalysis of the remaining pipe supports in areas accessible during normal plant operation is now complete. There are 37 of these supports which require modification, but which have been determined to be operable; i.e.,

support loads are less than a factor of safety of two to ultimate and/or are within the limits of ASME B&PV Code,Section III, Subsection NF. All of these supports are scheduled to be modified prior to a return to power following the 1980 scheduled refueling outage. Since these supports have been determined operable, there is no undue risk to public health and safety from continued operation of the FitzPatrick Plant in the interim.

3. For each modification identified as a result of reanalysis of the remaining supports in accessible areas after resumption of facility operation, when a support is deemed inoperable the NRC shull be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after making each such determination. The adfected system shall be con-sidered inoperable until the necessary modifica-tions are implemented within seven days or the time frame allowed by the facility Technical Specifica-tions, whichever is less, unless a reanalysis of the affected piping system is performed which:

(1) demonstrates that the overstressed support remains operable, or (2) demonstrates, with the overstressed support removed from the system, that the system remains operable.

Completion of reanalysis of the remaining supports in accessible areas indicated 23 supports to be inoperable. In each case, the Authority's site personnel transmitted an LER to the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of such a de termination. In each case, the necessary modifications were implemented within seven days or the time frame allowed by the Fitz-Patrick Plant Technical Specifications; or analysis was executed demonstrating that the system remained operable with the overstressed support removed.

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U. S. Nuclear Regulatory Commission 4. The FitzPatrick Plant shall be shut down if an earthquake with an acceleration greater than .01 occurs (site accelerometers are set at 0.01 g) and the licensee shall inspect all safety-related piping systems which have not been reanalyzed and shown to be acceptable at the 0.07 g level of the OBE. Prior to resuming operations following an earthquake, the licensee shall demonstrate to the Commission that no functional damage has occurred to those features necessary for continued operation without undue risk tc the health and safety of the public.

The Order which lifted facility suspension stated chat the above commitment is required only until such time that the reanalysis for the OBE loading condition, and any necessary modifications, are completed. The reanalysis executed in response to the Order to Show Cause considered both the ,

DBE and OBE loading conditions for all piping, equipment nozzles and containment penetrations.

In regrid to pipe supports, the DBE loading con-dition was applied in all cases, and the OBE loading condition was applied in all but a few isolated cases. For these isolated cases, review of the OBE loading condition is expected to be completed by November 15, 1979. At that time you will be informed accordingly, and the Authority considers it will be released from its commitment to shut down and inspect safety-related piping systems in the event of an earthquake with an accele ation greater than .01 g.

As noted in our July 9, 1979 letter to the NRC Region I Director, the Authority considers that the criteria of I&E Bulletin 79-14 was fully met for both the inaccessible and accessible piping systems within the scope of reanalysis re-quired by the March 13, 1979 Order to Show Cause. The procedure for conducting field verifications was reported to you in our August 2, 1979 letter. Also, wherever pipe support modifica-tions were necessary, the baseplate and anchor bolts were designed to be in conformance with the criteria of I&E Bulletin 79-02 (if a concrete anchor bolt design was used).

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U. S. Nuclear Regulatory Commission Completed analytical piping packages are presently be.iig compiled and are available for your inspection, as are any field modifications to supports which resulted from the reanalysis effort.

In summation, of the 989 pipe supports which originally existed and which required review under the Order to Show Cause, only 37 supports, all determined to be cperable, still require modificction. The failure of any of these supports will not render its associated system incperable. All other 952 supports have either been reviewed and found to meet present standards, or were modified. Therefore, continued operation of the FitzPatrick Plant provides no undue risk to the public health and safety.

Very truly yours,

.s

. wl .>r Paul J. Early!

Assistant Chjef Engineer-Projects cc: Mr. Boyce H. Grier, Director Office of Inspection and Enforcement Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19406 l'"'2 186

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