ML20197K150

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Safety Evaluation Supporting Amend 241 to License DPR-59
ML20197K150
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 12/02/1997
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20197K146 List:
References
NUDOCS 9801050234
Download: ML20197K150 (3)
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4 UNITED STATES ij NUCLEAR REGULAf0RY COMMISSION s#

t WASHINGTON. o.C. 306MM001

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 241 TO FACILITY OPERATING LICENSE NO. DPR-59 EQWER AUTHORITY OF THE STATE OF NEW Y085 JAMES A. FITZPATRICK NUCLEAR POWER PLANT L

DQCKET NO. 50-333 1.0 JMRODUCTION By letter dated December 14, 1995, as supplemented September 26, 1997, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A. ritzPatrick Nuclear Power Plant Technical Specifications (TSs).

The requested changes would incorporate the inservice tes+ing (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 Technical 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 fndividual test requirements with a single requirement.

Reactor fore Isolation Cooling (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.

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

% 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 Plan 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, rspectivel.y, of Section XI of the ASME Code.

The allowable ranges cf 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 comply with these rules."

The licensee has proposed revising TS s.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 9901050234 971202 PDR ADOCK 05000333 P

PDR

! 10 CFR Part 50, Section 50.55a(f)(6)(1).

Only those changes to the testing frequency of pumps and valves allowed 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 systems:

  • Containment Cooling (4.5.B)
  • High-Pressure Coolant injet. tion (4.5.C)
  • Pressure Suppression Chamber-Reactor Building and Pressure Suppressicn Chamber-Drywell Vacuum Breakers (4.7.A.4 & 5)

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 Categery A and B Valves."

The RCIC System is not part of the IST program or the tCCS.

However, the RCIC System is included with the ECCS section of the TS because of their similar functions. The RCIC System is designed to operate either automatically or manually following reactor pressure vessel (RPV) isolation accompanied by a loss-of-coolant flow from the feedwater system to provide adequate core cooling and control of the RPV water level. Under these conditions, the high-pressure coolant injection (HPCI) and RCIC systems perform similar functions.

The RCIC pump flow rates ensure that the system can maintain reactor coolant inventory during pressurized conditions with the RPV isolated.

The flow tests for the RCIC System are performed at two different pressure ranges such that system capability to provide cated flow is tested both at the higher and lower operating ranges of the system. A 92-day Frequency for Surveillance Requirement 4.5.E.1.c is consistent with the IST program requirements and will ensure that the system will limit the release of radioactive materials to the environment following a loss-of-coolant accident (LOCA).

The changing of the testing requirements of the pump and valves for multiple individual test requirements to a single requirement in the TS listed above is consistent with the BWR4 Standard Technical Specifications, NUREG-1433 and does not change the ability of the system to limit the release of radioactive materials to the environment following a LOCA. NRC staff finds the above proposed changes to the James A. FitzPatrick Nuclear Power Plant TS acceptable.

I l

l There are three issues within this amendment proposal that will be addressed in separate amendments:

1) Changing the verification that a containment penetration with an inoperable isolation valve is properly isolated from once per day to once per 31 days.
2) The wording used in specifications 3.5.G, 4.5.G.1, 4.5.G.2 and 4.5.G.3 has been changed to nake it ansistent with Standard Technical Specifications, SR 3.5.1.2 and 3.5.3.1.

3)

Changing SR 4.7. A.5.a from monthly to quarterly.

3.0 STATE CONSULTATIOJ In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.

The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.

The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (61 FR 1635).

Accordingly, the amendment meets the eligibility criteria for categorical exclusien set forth in 10 CFR Sl.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 reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuanc.e of the amendment will not be inimical to the common defense and securn) or to the health and safety of the public.

Principal Contributor: Karen R. Cotton Date:

December 2, 1997

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