ML20203L265

Safety Evaluation Supporting Amend 242 to License DPR-59

ML20203L265
Person / Time
Site:	FitzPatrick
Issue date:	02/27/1998
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20203L252	List: ML20203L249 ML20203L265
References
NUDOCS 9803050422
Download: ML20203L265 (3)

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21 UNITED STATES y-s

'j NUCLEAR REGULATORY COIAMISSION t

WASH 1HOToN, D.o. 2006H001 k...../

HAffTY EVAIJ)60.QMDX,IHE OFFlQf OF N'JCLF,AR REACTOR REGULATION RELATED TO AMENDME_NT.JO. 242 TO FACILITY OPERATING LICENSE NO. DPR 12 POWER AUTHORITY OF THE STATE OF NEW YORK LARES.A. FIT 2 PATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333

1.0 INTRODUCTION

By letter dated December 14,1995, as supplemented September 20,1997, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A.

FitzPatrick Nuclear Power Plant Technical Specifications (TSs). The requested changes would incorporate the inservice testing (IST) requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code). This proposed amendment replaces the existing Techaical Specifications Surveillance test requirements for pumps and valves with the requirements and criteria of ASME Section XI. This revises the testing frequency of pumps and valves to be consistent with ASME Section XI. The change replaces multiple individual test requirements with a single requirement. Reactor Core I olation Coo:ing (RCIC) system pump and valve testing (which is not part of the Inservice Testing Program)is also changed from monthly to once per 92 days. This makes RCIC testing consistent with ASME Section XI testing of emergency core cooling system (ECCS). The September 26,1997, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.

1.0 EVALUATION The proposed amendment incorporates the requirements of the NRC approved version of the Section XI ASME Coc's for inspecting and testing of ASME Code Class 1,2, and 3 components.

The proposed testing program for pumps and valves follows the requirements of ASME Section XI,, Paragraph IWP-3400, " Frequency of Inservice Tests," and Paragraph IWV-3400, " Inservice Tests, category A and B Valves" and the NRC Standard Review Pian 3.9.6, " Inservice Testing of Pumps and Valves," which states in part, "The pump and valve test programs are acceptable if they meet the requirements for establishing reference values and the periodic testing schedule of IWP-3000 and IWV-3000, respectively, of Section XI of the ASME Code. The allowable ranges of inservice test quantities, corrective actions, and bearing temperature tests for pumps are established by IWP-3000 and IWP-4000. The pump test schedule in the plant technical specification is required to complywith these rules." The licensee has proposed adding TS 4.0.E to provide that the licensee shall follow and perform all required pump and valve testing in accordance with ASME Section XI, except when written relief has been granted by the NRC pursuant to 10 CFR Part 50, Section 50.55a(f)(6)(l). Only those changes to the testing frequency of pumps and valves alloweo under ASME section XI can be made without requesting NRC approval through a relief request. The FitzPatrick TSs contain,in part, pump and valve surveillance test requirements for the following systers:

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' e Standby Liquid Control System (4.4.A) e e Core Spray System and Residual Heat Removal System (4.5.A) e Containment Cooling (4.5.8) o High Pressure Coolant injection (4.5 C) p

- o - Reactor Core Isolation Cooling System (4.5.E) e Emergency Ccre Cooling System - Cold Condition (4.5.F)

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e Primary Containment Isolation Valves (4.7.D) j e Pressura Suppression Chamber-Reactor Building and Pressure Suppression Chamber-j Drywell Vacuum Brealsers (4.7.A.4 & 5) e Emergency Service Water System (4.11.D) 4 The proposed amendment would modify the TS to follow the requirements of ASME Section XI,

- Paragraph IWP-3400, " Frequency of inservice Tests," and Paragraph IWV-3400, " Inservice Test for Category A and B Valves."

The RCIC System is not part of the IST program or the ECCS. However, the RCIC System is included with the ECCS section of the TS because of their similar functions. The RCic System i

is designed to operate either automatically or manually folicwing reactor pressure vessel (RPV)

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isolation accompanied by a loss-of-coolant flow from the fed. vater system to provide adequate core cooling and control of the RPV, water level. Under these conditions, the high-pressure -

i coolant injection (HPCI) and RCIC systems perform similar functions. Ti,e RCic pump flow rates ensure that the system can maintain reactor coolant inventory during pressurized condit;ons with L

the RPV isolated. The flow tests for the RCIC System are performed at two different pressure ranges such that system capability to provide rated flow is tested both at the higher and lowor operating rangen of the system. A g2-day Freqecy for Surveillance Requirement 4.5.E.1.c is consistent with the IST program requirements and will ensure that the system will limit the '

- telease of radioactive materials to the environment following a loss-of-coolant accident (LOCA),

F The changing of the testing requirements of the pump and valve-for multiple individual test requirements to a single requirement in the TS listed above is consistent with the BWRd

. Standard Technical Specifications; NUREG-1433 and does not change the ability nf the system to limit the relasse of radioactive materials to the environment following a LOCA. NRC staff finds i.

the above proposed changes to the James A. FitzPatrick Nuclear Power Plant TS acceptable.

t There are three issues v.ithin this amendment proposal that will be addressed in separate amendments:

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Changing the urification that a containment penetration with an inoperable isolation valve is property !solated from once per day to once per 31 days.

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2) The wording used in specifications 3.5.G,4.5.G 1,4.5.G.2 and 4.5 G.3 has been changsd to make it consistent with Standard Technical Specifications, SR 3.5.1.2 and -

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Changing SR 4.7.A.5.a from monthly to quarterty. -

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3.0 STATE 70NSULTATION l

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in accoidance with the Commis:lon's regulations, the New York 6tata official was notified of the

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proposed issuance of the amendment. The State official had no corr.monts, I

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes e requirement with respect to installation or use of a facility component j

located within the restricted area as defined in 10 CFR Part 20 and changas surveillance requirements, The NRC staff has determined that the amendment involves no signifcant increase in the amounts, and no significant change in the types, of any effluents that may be 4

released offsite, and that there is no significant increase in Individaal or cumulative occupational i

radiation exposure. The Commiss!on has previously issued a proposed finoing that the 4

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amendment involves w significar,t hazards consideration, and there has been no public comment on such finding (61 FR 1635), Accordingly, the amendment meets the eligibility criteria l

for categorical exclusion set forth in 10 CFR 51.22(c)(9), Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is

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reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities w31 be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defenso and security or to the health and safMy of the public.

Principal Contributon Karen R. Cotton Date: February 27, 1998 4

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