ML20206B312
| ML20206B312 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/03/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206B310 | List: |
| References | |
| NUDOCS 8704090069 | |
| Download: ML20206B312 (3) | |
Text
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o UNITED STATES 83)
NUCLEAR REGULATORY COMMISSION
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wAsHWGTON, D. C. 20566
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...e SAFETY EVALUATION BY THE OFFICE OF h0 CLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.108 TO FACILITY OPERATING LICENSE N0. DPR-59 l
POWER AUTHORITY OF THE STATE OF NEW YORK l
l JAMES A. FITZPATRICK NUCLEAR POWER PLANT p0CKETNO.50-333
1.0 INTRODUCTION
l By letter dated December 19, 1986,.the Power of Authority of the State of New York (the licensee) proposed changes to the Technical Specifications (TS) to support installation of and operation with additional isolation valves in the Traveling Incore Probe (TIP) Purge System, Recirculation Pump Mint-Purge (RPMP) System, Automatic Depressurization System (ADS) Accumulator System, and Reactor Water Cleanup (RWCU) System.
Installation of these valves will be completed during the Reload 7/ Cycle 8 refueling outage.
By letter dated January 3,1987, the licensee informed the NRC that installation of the new valve for the RWCU Systen would not be performed during the Reload / Cycle 8 refueling outage and would be deferred. Also, as a result of discussions with the staff, the licensee provided clarification to the proposed TS revisions by letter dated March 13, 1987.
2.0 EVALUATION In order to implement NUREG-0737 Items II.E.4.2 (Containment Isolation Dependability) and II.K.3.28 (Qualification of ADS Accumulators), the licensee previously committed to install new, automatic, isolation valves with diverse actuation signals in the TIP, RPMP and ADS Systems.
These modifications necessitated revising TS Table 3.7-1 which addresses the characteristics of process piping containment penetrations, a)
Traveling Incore Probe Purge System The licensee will replace the existing check valve located outside containment with a new hand-operated globe valve and a new solenoid-operated valve that will close upon loss of power, low reactor water level, or high drywell pressure. A new check valve will also be installed inside containment. These modifications are necessar/ to satisfy the criteria of NUREG-0737 Item II.E.4.2 and GDC 54, 55, and 56 of Appendix A to 10 CFR 50.
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'A D b)
Recirculation Pump Mini-purge Systg The licensee will replace the two existing check valves located outside containment with one new solenoid-operated valve inside containment and one new solenoid-operated valve outside containment. The new valves will close upon loss of power, low-low-low reactor water level or high drywell pressure. These modifications are necessary to satisfy the criteria of flUREG-0737 Item II.E.4.2 and GDC 54, 55, and 56 of Appendix A to 10 CFR 50.
c)
ADS Accumulator System NUREG-0737 Item II.K.3.28 requires the ADS Accumulator System to remain functional for periods up to one-hundred days following a postulated accident. As part of a system upgrade to assure long-term operability, two isolation valves will be added to a new redundant nitrogen supply line to the ADS accumulators. One of these valves, located outside containment, is solenoid-operated and fails open to ensure an adequate supply of nitrogen to the accumulators. The other valve, located inside containment, is a check valve. The two valves in combination satisfy GDC 56' In addition, a hand-operated valve on the existing nitrogen supply line will be replaced by a remote-manual, scienoid-operated valve which fails open to ensure an adequate nitrogen supply to the ADS accumulators.
We have reviewed the modifications and associated TS revisions described by the licensee in the above referenced submittals. We find that the modifications to the TIP, RPMP, and ADS Accumulator Systems will improve the safety functional capability of these systems, will bring these systems into compliance with the applicable criteria of GDC 54, 55, and 56, and will implement the requirements of Items II.E.4.2 and II.K.3.28 of flVREG-0737. We therefore conclude that the associated revisions to TS Table 3.7-1, which are necessary to support operation with these modifications are acceptable.
3.0 Ef1VIR0fiMEllTAL C0flSIDERATI0flS This 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. The 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. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set J
forthin10CFR51.22(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.
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4.0 CONCLUSION
We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendrent will not be inimical to the common defense ano security or to the health and safety of the public.
Principal Contributor:
P. Hearn Dated: April 3, 1987 I