ML20006E268

Forwards Application for Amend to License DPR-59,revising Tech Specs Re RHR Pump Operability

ML20006E268
Person / Time
Site:	FitzPatrick
Issue date:	02/09/1990
From:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20006E269	List: ML20006E268 ML20006E275 ML20006E276 ML20006E277
References
JPN-90-013, JPN-90-13, NUDOCS 9002220486
Download: ML20006E268 (2)

Text

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[ John C. Brons Ewcutwe Vice President Nuclear Generation I

Pehruary 9, 1990 l JIW-90-013 i U.S. Nuclear Regulatory Commission Mall Station P1 137 Washington, D.C. 20555 ATTN: Document Control Desk

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Changes to the Technical Specifications j Regarding RHR Pump Operability (JPTS-90-002)  ;

References:

'1. General Electric Co., Nuclear Safety Evaluation for a 10% Decrease in LPCI Flow, JAF SE 9CMT24, dated February 5,1990. )

Dear Sir:

j l

The Authority has recently determined, based on performance test results, that two )

Residual Heat Removal (RHR) pumps in one of the two low pressure coolant injection i (LPCI) subsystems require refurbishment. An extrapolation of pump performance data l indicates that the pumps may fall to meet the Technical Specification acceptance requirements during the next scheduled surveillar,ce test. The Authority intends to refurbish  !

the pumps as soon as practicable. Engineering work and the procurement of replacement parts are being expedited, so that pump refurbishment may begin at the earliest on March 17,1990.  !

A refuel outage is schedule to start March 31,1990. Temporary relief from the  !

requirements of the James A. FitzPatrick Technical Specifications will be needed to avoid the potentla! for a premature plant shutdown. In accordance with 10 CFR 50.91(a)(6), the Authority requests changes to the James A. FitzPatrick Technical Specifications on an exigent basis. The changes involve: 1) a reduction of the RHR pump flow rate surveillance i requirement, and 2) an extension in the allowable out of service for the LPCI and ,

Containment Cooling subsystems. i RHR Pump Flow Rate Surveillance Requirement The next surveillance test for the affected RHR pumps is scheduled for the week of February 25,1990. Due to the performance trends of- these pumps, a change to the '

Technical Specifications is proposed to allow the pumps to be operable at a reduced flow  ;

rate. Therefore, a temporary change to the Technical Specifications is proposed to reduce

- the allowable RHR pump flow rate from 9,900 gpm to 8,910 gpm. Reference 1 substantiates the acceptability of a 10% reduction in flow requirements. ,

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< Exteded Out-of4ervice Time for LPCI and Containment Cooling j hS . Pump performance trending on RHR pumps 'A' and 'C' necessitates refurbishment of l

these pumps. These pumps are needed in the shutdown cooling mode of RHR during the  !

upcoming refueling outage to permit schedule overhaul of the "B" and *D' RHR pumps j

( motors. The Authority would like to begin the refurbishment of the "A" and 'C' RHR pumps  ;

prior to the refuel outage. Taking these pumps out of service for maintenance during power i l

operation would require that the corresponding LPCI and Containment Cooling subsystems be declared inoperable, placing the plant in a 7 day LCO. A one time extension to the LCO

from 7 to 14 days is required. Pump work will be performed to minimize out of service time. j The Authority ,4 quests that this application for amendment be processed on an exigent J basis under the provisions of 10 CFR 50.91(a)(6), since insufficient time exists to provide for i a 30 day public comment period. As described in Attachment II, this request satisfies the ,

criteria for an exigent technical spectilcation change. For the reasons detailed in the

]

attachment, this situation could not have been foreseen or avolded. Approval of this '

amendment application is requested by February 23,1990.

Enclosed for filing is the signed original of a document entitled .* Application for  !

Amendment to Operating Ucense," with Attachments I and 11 thereto, comprising a j stelement of the proposed changes to the Technical Specifications and the associated  !

Safety. Evaluation. Attachment lli is the General Electric safety evaluation for a 10%

decrease in LPCI flow. .i L in accordance with 10 CFR 50.91, a copy of this application and the associated  !

attachments are being provided to the designated New York State official. I l Should you or your staff have any c;uestions regarding the proposed changes, please j i contact Ms. S. M. Toth of my staff. )

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,Very truly yours, W

kW. roks~ \

Executive Vice President j Nuclear Generation

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J Encl. j cc: 1 Regional Administrator Mr, David E. LaBarge U.S. Nuclear Regulatory Commission Project Directorate 11 475 Allendale Road '

King of Prussia, PA 19406 Division of Reactor Projects 1/11 U.S. Nuclear Regulatory Commission Office of the Resident inspector Mall Stop 14 B2 U.S. Nuclear Regulatory Commission Washington, DC 20555 P.O. Box 136 Lycoming, NY 13093 Ms. Donna Rosa New York State' Energy Office 2 Empire State Plaza 16th Floor  !

Albany, NY 12223 1

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