ML20059C841
| ML20059C841 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/29/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059C836 | List: |
| References | |
| NUDOCS 9401060126 | |
| Download: ML20059C841 (3) | |
Text
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UNITED STATES I
E-NUCLEAR REGULATORY COMMISSION EE "f
WASHINGTON, D.C. 20556-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 203 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated September 24, 1993, 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 make miscellaneous admir.istrative changes including typographical and editorial corrections to the Appendix A TSs and Appendix B Radiological Effluent TSs (RETS).
2.0 EVALUATION The licensee has proposed miscellaneous typographical and editorial corrections to the Appendix A TSs and Appendix B RETS. The staff has reviewed these proposed changes and determined that they are acceptable since they do not involve any substantive changes to requirements.
In addition to the above noted typographical and editorial corrections, the licensee also proposed to delete an erroneous surveillance requirement from Appendix A TS 4.3.C.3.b.
TS 4.3.C.3.b currently requires verification that after placing the mode switch in the SHUTDOWN position the scram discharge instrument volume (SDIV) drain and vent valves open when the scram signal is reset or the SDIY trip is bypassed. The proposed change would require verification that the drain and vent valves open when the scram signal is reset, and delete reference to bypassing of the SDIV trip. When the mode switch is placed in the SHUTDOWN position as part of this testing, the scram discharge volume isolation valve solenoids de-energize to close the SDIV drain and vent valves. At the end of the testing, the operator clears all signals to reset the reactor protection system including the SDIV high-level signal, if necessary.
Once all signals are cleared, the operator can_ reset the scram which will reopen the drain and vent valves.
It is the scram reset and not the SDIV high-level trip bypass that causes the SDIV vent and drain valves to open. The requirement in TS 4.3.C.3.b to verify that the SDIV vent and drain valves open when the SDIV trip is bypassed is, therefore, inconsistent with the design of the plant.
9401060126 931229 PDR ADDCK 05000333 P
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. The staff has reviewed the above change to the surveillance requirement in Appendix A TS 4.3.C.3.b and found it to be consistent with the design of the plant and Section 3.1.8.3 of NUREG-1433, " Standard Technical Specifications for General Electric Boiling Water Reactors (BWR/4)." The proposed change is, therefore, acceptable.
3.0 STATE CONSULTATION
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 (58 FR 62155). Accordingly, the amendment meets the eligibility criteria 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 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 issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
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M. Griggs i
Date: December 29, 1993
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i December 29, 1993 y-
_ Docket No. 50-333 1
Mr..Ra1ph E. Beedle Executive Vice President - Nuclear Generation i
Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Beedle:
1
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M87857)
The Commission has issued the enclosed Amendment No. 203 to Facility 0perating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The o
amendment consists of changes to the Technical-Specifications (TSs)~ in response to your application transmitted by letter dated September 24, 1993.
The amendment makes miscellaneous administrative changes including typographical and editorial corrections to the Appendix A TSs and Appendix B Radiological Effluent TSs. The amendment does not make any substantive changes to the TSs.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance Ewill be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, John E. Menning, by: ject Manager Ori inal si ied Pro Project Directorate I-l
. Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No. 203 to DPR-59 2.
Safety Evaluation
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i cc w/ enclosures:
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