ML19269E402

Application for Amend to License DPR-54 to Modify Tech Specs Re Emergency Svc Water Pump Test Acceptance Criteria. Proposed Changes & Safety Evaluation Encl

ML19269E402
Person / Time
Site:	FitzPatrick
Issue date:	06/26/1979
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Office of Nuclear Reactor Regulation
Shared Package
ML19269E400	List: ML19269E399 ML19269E402
References
NUDOCS 7906280124
Download: ML19269E402 (5)

Text

BEFORE Tile UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of )

)

POWER AUTHORITY OF THE STATE OF NEW YORK ) Docket No. 50-333

)

James A. FitzPatrick Nuclear Power Plant )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission (NRC), the Power Authority of the State of New York, as holder of Fac'lity Operating License No. DPR-59, hereby applies for an Amendment to the Technical Specifications contained in Appendix A of this license.

The proposed change to the FitzPatrick Technical Specification seeks revision to Section 4.ll.D.l.b for surveillance requirements regarding emergency service water pump test acceptance criteria.

Proposed changes to the Technical Specifications are presented in Attachment I to this Application. The Safety Evaluation is in-cluded in Attachment II.

POWER AUTHORITY OF THE STATE OF NEW YORK

,)

• By / -

'g Paul /J. Earlf i

Assistant Ch4ef Engineer-Projects Subscribed and sworn to before me this v26 day df June, 1979.

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Notary ri i . S ta N 1. 30 0 03423 New Ycrk 7906280/2f' g Can!Tcd 1.1 N~~ w Cr""'Y ComrM m EeT kc3 "d 2 W p-

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i ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO EMERGENCY SERVICE WATER PUMP TESTING POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 JUNE 22, 1979 2170 150

3 3.11 (cont'd) JAFNPP 4.11 (cont'd) ..

D. Emergency Service Water System D. Emergency Service Water System

l. To ensure the adequate 1. Surveillance of the ESW system equipment and area cooling, shall be performed as follows:

operable when the requirements of specification 3.5.A and Item Frequency 3.5.B must be satisfied, except as specified below in a. Simulated Each specification 3.ll.D.2. Automatic operating Actuation cycle Test

b. Flow Rate Once/

Test - ESW 3 months pumps shall deliver at least 3,250 gpm against a system head corresponding to a total pump head of

> 80 psi, as determined from the pump certifi-cation curve by measuring the pump shutoff head which shall be > 117 psi ps) c. Pump Once/ month

__. Operability

~~a O d. Motor once/ month Operated

-~^

Valves Un 240

ATTACHMENT II SAFETY EVALUATION EMERGENCY SERVICE WATER PUMP TESTING POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 JUNE 22, 1979 2170 152

SAFETY EVALUATION EMERGENCY SERVICE WATER PUMP TESTING Section I - Basis for the Modification Technical Specification Section 4.ll.D.l.b has been proposed to be modified in order to allow for normal emergency service water pump wear while still assuring capability to meet system requirements.

Emergency Service Water System flow requirements are 2915 gpm as stated in Table 9.7.1 of the FSAR. The Technical Specification refers to 3700 gpm at 80 psi which is taken off the pump curve at design point.

Recent shutoff head measurements (Ref. 1) represent a reduction of 2.0 psi from the original pump curve. In discussions with the pump vendor a 4% reduction in shutoff head identified as a point where overhaul should reasonably be considered. The resulting criteria would be approximately 117 psi. The pump vendor further indicated that reductions in shutoff head, if applied throughout the head-capacity curve, would provide a conservative indication of pump performance after normal wear. The resulting capacity at 80 psi would be 3250 gpm, i.e., 11.5% above the required capacity of 2915 gpm.

Section II - Impact of the Change A review of the FSAR and SER Accident Analyses indicate that there are no changes to the parameters used, and that the conclusions reached are unchanged, as a result of this modification.

Section III - Implementation of the Modification The modifications as proposed will not impact the ALARA or Fire Protection Program at JAF.

Section IV - Conclusions The incorporation of this modification: a) will not increase the probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an acci-dent or malfunction of a different type than any evaluated previously in the Safety Analyses Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification.

Section V - References

1. Letter: J.D. Leonard, Jr. (PASNY) to Mr. Boyce H. Grier (NRC) of May 24, 1979. E, s }

2.

3.

JAF FSAR JAF SER 2170