ML20155H009

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Forwards RAI Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, for Plant,Unit 1
ML20155H009
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 11/05/1998
From: Colburn T
NRC (Affiliation Not Assigned)
To: Langenbach J
GENERAL PUBLIC UTILITIES CORP.
References
GL-96-05, GL-96-5, TAC-M97111, NUDOCS 9811090285
Download: ML20155H009 (3)


Text

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q Novenber 5, 1998 Mr. James W. Langenbach, Vice President and Director, TMI GPU Nuclear, Inc.  !

P.O. Box 480 I Middletown, PA 17057

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING GPU NUCLEAR'S RESPONSE TO GENERIC LETTER (GL) 96-05 FOR THE THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 (TMI-1)(TAC NO. M97111) 1

Dear Mr. Langenbach:

The staff has reviewed your letter dated May 13,1998, regarding GL 96-05, " Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves." The staff has determined '

that it will need the additional information identified in the enclosure to complete its review of your  !

response. i l

During a telephone conference with Mr. Gregory M. Gurican of your staff, it was agreed that a I 90 day response to this request is reasonable and within the ability of your staff resources.

Sincerely, j

Original signed by i

Timothy G. Colbum, Senior Project Manager j Project Directorate I-3 1 Division of Reactor Projects - t/11  !

Office of Nuclear Reactor Regulation Docket No. 50-289 I

Enclosure:

Request for AdditionalInformation cc w/ encl: See next page DISTRIBUTION Ol0/

. Docket File , ACRS RWessman DTerao PUBLIC CHehl, RI OGC TScarbrough PDl-3 r/f JZwolinski TClark TColbum DOCUMENT NAME: G:\COLBURN\THI97111.rai To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" - No copy 0FFICE P01 3/PM ,, , l POI 3/LA , [l[] lt POI;7/D , pW I L

NAME TColburn P TCtark L _/ifN PTh#'/ I DATE f/ / T /98 // / 6 /98 V/'/ C /98 n OFFICIAL RECORD COPY D 89 P PDR . , -  :

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. J.Langenbach Three Mile Island Nuclear Station, Unit No.1 l cc:

/ ,.

Michael Ross Robert B. Borsum l Director, O&M, TMl . B&W Nuclear Technologies GPU Nuclear, Inc. Suite 525 i P.O. Box 480 1700 Rockville Pike Middletown, PA 17057 Rockville, MD 20852 John C. Fomicola William Domsife, Acting Director Director, Planning and - Bureau of Radiation Protection l Regulatory Affairs Pennsylvania Department of GPU Nuclear, Inc. Environmental Resources 4

100 Interpace Parkway P.O. Box 2063 Psrsippany, NJ 07054 Harrisburg, PA 17120 Jack S. Wetmore Dr. Judith Johnsrud Manager, TMI Regulatory Affairs National Energy Committee GPU Nuclear, Inc. Sierra Club

a. P.O. Box 480 433 Orlando Avenue

. Middletown, PA 17057 State College, PA 16803 Emest L. Blake, Jr., Esquire Peter W. Eselgroth, Region i

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- Shaw, Pittman, Potts & Trowbridge U.S. Nuclear Regulatory Commission 2300 N Street, NW.' 475 Allendale Road Washington, DC 20037 King of Prussia, PA .19406 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman -

Board of Supervisors of LondondenyTownship R.D. #1, Geyers Church Road i Middletown, PA 17057 Wayne L. Schmidt Senior Resident inspector (T.MI 1)

U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 i Regional Administrator Region i U.S. Nuclear Regulatory Commis. tion 4 475 Allendale Road i K:'ng of Prussia, PA 19406 4

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REQUEST FOR ADDITIONAL INFORMATION THREE MILE ISLAND NUCLEAR STATION, UNIT NO.1 (TMI 1) l RESPONSE TO GENERIC LETTER (GL) 96-05 l

1. In NRC Inspection Report No. 50-289/97-07, the NRC staff closed its review of the motor- )

operated valve (MOV) program implemented at the Three Mile Island Nuclear Station, Unit 1 (TMI-1) in response to Generic Letter (GL) 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance," based on the results of the inspection and the licensee's plans to resolve several outstanding MOV issues as described in a letter dated June 17, 1997, in a letter dated December 31,1997, the licensee notified the NRC staff that it had competed the commitments specified in its letter dated June 17,1997, with the exception of

. some recommendations from its MOV Independent Review Team that were targeted for completion in 1998. The licenses should provide the status of those remaining actions.

2. In a letter dated May 13,1998, the licensee updated its commitment to implement the Joint Owners Group (JOG) Program on MOV Periodic Verification in response to GL 96-05. The

. JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significance are the responsibility of each participating licensec. In a 4 previous letter dated March 18,1997, tt e licensee stated that the ranking of MOVs at TMI-1 would be based on the Boiling Water Reactor Owners' Group (BWROG) methodology as described in BWROG Topical Report NEDC 32264 (Revision 2, dated September 1996). As TMI 1 is a pressurized water reactor (PWR) designed by Babcock & Wilcox (B&W), the licensee shou'd describe the application of the BWROG methodology to TMI 1, including (1) the preparatic. ;f a sample list of high-risk MOVs frorn other B&W nuclear plants, and (2) consideration . ".he conditions and limitations discussed in the NRC safety evaluation dated February 27,1996, on the BWROG methodology. In responding to this request, the licensee 1 might apply insights from the guidance provided in the Westinghouse Owners Group (WOG)

Engineering Report V EC 1658-A (Revision 2, dated August 13,1998), " Risk Ranking Approach for Motor-Operated Valves in Response to Generic Letter 96-05," and the NRC safety evaluation dated April 14,1998, son the WOG methodology for risk ranking MOVs at Westinghouse-designed PWR nuclevr plants.

3. The JOG program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions. In the NRC safety evaluation dated October 30,1997, on the JOG program, the NRC staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. The licensee should describe the plan et TMI-1 for ensuring adequate MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1.

Enclosure

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