ML20128N515

Forwards SE Granting Relief Request Re Pump & Valve Inservice Testing Program

ML20128N515
Person / Time
Site:	Limerick
Issue date:	02/17/1993
From:	Chris Miller Office of Nuclear Reactor Regulation
To:	Beck G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Shared Package
ML20128N518	List: ML20128N515 ML20128N531
References
GL-89-04, GL-89-4, TAC-M83243, TAC-M83244, TAC-M83561, TAC-M83562, NUDOCS 9302230272
Download: ML20128N515 (4)

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3 UNITED STATES o

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NUCLEAR REGULATORY COMMISSION l

en WASHINGTON D.C. 205E I

\\......o February 17, 1993 i

i Docket Nos. 50-352 and 50-353 1

Mr. George J. Beck Manager-Licensing, MC 52A-5 Philadelphia Electric Company i

Nuclear Grcap Headquarters l

Correspondence Control Desk P.O. Box No. 195 l

Wayne, Pennsylvania 19087-0195 l

SUBJECT:

SAFETY EVALUATION FOR PUMP AND VALVE INSERVICE TESTING PROGRAM (IST)

RELIEF REQUEST,-LIMERICK GENERATING STATION,-UNITS 1 AND-2 l

(TAC N05. M83243, M33244,-M83561, AND M83562) l By letters dated April 15, and May 1,1992, you addressed the 15 anomalies-i identified in our letter dated March 5,1991'. Our March 5, 1991, transmittal-contained a technical evaluation that addressed the licensee's first ten-year i

inservice testing program. Appendix A to that report; identified the subject anomalies. Your first response addressed relief request 52-VRR-1, while the j

second submittal addressed the remaining anomalies. We have reviewed your i

submittals following the guidance-of Generic _ Letter (GL) 89-04, '" Guidance on Developing Acceptable Inservice Testing Programs." Our safety evaluation i

report co_ntains the evaluation of relief requests 52-VRR-1, GPRR-1, and GVRR-1.

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' Pursuant to 10 CFR 50.55a(f)(4), it is required that certain Class 1, 2, and 3 pumps and valves in water cooled nuclear facilities meet the inservice testing i

requirements stated in the ASME Boiler and Pressure-VessellCode,Section XI,-

specifically, Subsection _ IWP,L" Inservice Testing of Pumps in Nuclear Plants,"

and Subsection IWV, " Inservice Testing of Valves in Nuclear Power. Plants."

However, the Commission can authorize alternatives pursuant to 10 CFR 50.55a(a)(3)(i) and (ii),-.and grant reliefs-pursuant to (f)(6)(i),. from ASME Code requirements upon making the necessary findings.

Table 1 provides our summary of the anomalies.

It;-includes the description, and Philadelphia Electric Company's (PEco) actions, past and _ future.

Item-2 3'

in Table 1 addresses-full-stroke exercising of the residual heat removal-mini-flow check valves.

PECo's' proposed method of testing is not in compliance with the ASME Code requirements.

PEco should submit a relief request for these valves within 90 days of the date of this letter.

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Mr. George J. Beck February 17, 1993 l-4 I

Further, in the Safety Evaluation (SE)/ Technical Evaluation Report (TER)-

transmitted to you on March 5, 1991, Relief Request 43-V_RR-1 was evaluated in Section 3.4.1.1 of the TER and granted by the staff as requested.

However, the SE Table 1, page 3, incorrectly identified this relief request. The staff has noted the error and does consider Relief Request 43-VRR-1 granted.

l Additional relief requests or changes to approved relief requests should be i

submitted for staff review and approval prior to implementation.

However, new l

or revised relief requests meeting the positions of GL 89-04 -should be i

submitted to the NRC staff, but can be implemented pr]vided the guidance of GL 89-04, Section D, is followed. Also, IST Program changes that involve additions or deletions of components from the IST Program should be provided' to the NRC.

i The reliefs granted are authorized by law and will not endanger life or l-property or the common defense and security and are otherwise in the public interest given due consideration to the burden upon the licensee that could j

-result if the requirements were imposed on the facility.

4 The requests for. relief comply with the standards and requirements of the Atomic Energy'Act of 1954, as amended-(the Act), and the Commission's rules and regulations-.

4 This letter closes TAC N m. M83243, M83244, M83561, and M83562, If you have any questions, please call Frank Rinaldi at (301) 504-1444.

i Sincerely,

/S/

1 Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i

Enclosure:

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Mr. George J. Beck February 17, 1993 th, -

F.urther, in the Safety Evaluation (SE)/ Technical Evaluation Report (TER) transmitted to you on March 5,1991, Relief Request 43-VRR-1 was evaluated in-j Section 3.4.1.1 of the TER and granted by the staff as requested.

However, the SE Table 1, page 3, incorrectly identified this relief request.

The staff has noted the error and does consider Relief ReqJest 43-YRR-1 granted.

Additional relief requests or changes to approved relief requests should be submitted for staff review and approval prior to implementation. However, new or revised relief requests meeting the positions of GL 89-04 should be submitted to the NRC staff, but can be implemented provided the guidance of j

GL 89-04, Section D, is followed. Also, IST Program changes that involve additions or deletions of components from the IST Program should be provided i

to the NRC.

The reliefs granted are authorized by law and will not endanger life or 1

property or the common defense and security and are otherwise in the public interen given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

The requests for relief comply with the standards and requirements of-the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.

This letter closes TAC Nos. M83243, M83244, M83561, and M83562.

If you have i

any questions, please call Frank Rinaldi at (301) 504-1444.

Sincerely, f

C[ d MWbdw Charles L. Miller, Director i

Project Directorate I-2 i

Division of Reactor Projects - I/II l

Office of Nuclear Reactor-Regulation Enclosure w he Safety Eva cm cc w/er.closw e D T.

See next page v n 4

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Mr. George J. Beck Limerick Generating Station, Philadelphia Electric Company Units 1 & 2 cc:

J. W. Durham, Sr., Esquire Mr. William P.-Dornsife, Director Sr. V.P. & General Counsel Bureau of Radiation Protection l

Philadelphia Electric Company PA Dept. of Environmental Resources 2301 Market Street P. O. Box 2063 1

Philadelphia, Pennsylvania 19101 Harrisburg, Pennsylvania 17120 Mr. Rod Krich 52A Mr. James A. Muntz Philadelphia Electric Company Superintendent-Technical l

955 Chesterbrook Boulevard Limerick Generating Station Wayne, Pennsylvania 19087-5691 P. O. Box A Sanatoga, Pennsylvania 19464 Mr. David R. Helwig, Vice President i

Limerick Generating Station Mr. Gil J. Madsen Post Office Box A Regulatory Engineer i

Sanatoga, Pennsylvania 19464 Limerick Generating Station P. O. Box A 2 -

Mr. John Doering Sanatoga, Pennsylvania 19464 Plant Manager j

Limerick Generating Station Library P.O. Box A US Nuclear Regulatory Commission Sanatoga, Pennsylvania 19464 Region I L

475 Allendale Road j

Regional Administrator King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission i

Region I Mr. George A. Hunger 475 Allendale Road Project Manager King of Prussia, PA 19406 Limerick Generating Station i

P. O. Box A Mr. Thomas Kenny Sanatoga, Pennsylvania 19464 l

Senior Resident Inspector US Nuclear Regulatory Commission Mr. Larry Hopkins-

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P. O. Box 596 Superintendent-Operations Pottstown, Pennsylvania 19464 Limerick Generating Station P. O. Box A

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Mr. Richard W. Dubiel Sanatoga, Pennsylvania 19464 Superintendent Services Limerick Generatir.g Station P.O. Box A Sanatoga, Pennsylvania 19464 i

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