ML20057F209
| ML20057F209 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/07/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057F206 | List: |
| References | |
| NUDOCS 9310140292 | |
| Download: ML20057F209 (4) | |
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UNITED STATES E
E NUCLEAR REGULATORY COMMISSION E*
i WASHINGTON, D.C. 205554X101 l
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i
RELATED TO AMENDMENT NO.199 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT i
DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated June 24, 1993, the Power Authority of the State of New York 1
(the licensee) proposed changes to the Technical Specifications (TSs) for the i
James A. FitzPatrick Nuclear Power Plant (FitzPatrick). The proposed changes i
would remove TS 4.6.A.7 which provides the schedule for removing reactor vessel material specimens. Guidance on the proposed TS changes was provided in Generic Letter (GL) 91-01, " Removal of the Schedule for the Withdrawal of i
Reactor Vessel Material Specimens from Technical Specifications," dated January 4, 1990.
2.0 EVALUATION Technical Specification 3/4.6.A, " Pressurization / Temperature Limits," contains i
a limiting condition for operation (LCO) for the Reactor Coolant System (RCS) that limits the rate of change in temperature and pressure to values consistent with the fracture toughness requirements of the American Society of Mechanical Engineers (ASME) Code and Appendix G to Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Changes in the values of these limits are necessary because the fracture toughness properties of ferritic materials in the reactor vessel change as a function of the reactor operating time (neutron fluence).
For this reason, the TSs include a Surveillance Requirement, TS 4.6.A.7, that requires the removal and examination of the irradiated specimens of reactor vessel material. The licensee examines the specimens to determine the changes in material properties in accordance with the requirements of Appendix H to 10 CFR Part 50. GL 91-01 allows removal of the schedule from the Surveillance -
Requirement or removal of the complete Surveillance Requirement if it does not specify that the results of the examination are to be used to update the pressure and temperature limits of LCO 3.6.A.
This change is consistent with the improved Standard Technical Specifications -which have no Surveillance Requirement for specimen removal and updating of the LCO.
-l The removal of the schedule for withdrawing material specimens from the TSs will eliminate the necessity of a license amendment to make changes to this i
schedule. However,Section I.B.3 of Appendix H to 10 CFR Part 50 requires the 1
submittal of a proposed withdrawal schedule for material specimens to the U.S.
9310140292 931007 PDR ADOCK 05000333
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s Nuclear Regulatory Comission (NRC) and approval by the NRC before imple-mentation. Hence, adequate regulatory controls exist to control changes to this schedule without the necessity of subjecting it to the license amendment i
process by including it in TSs.
The licensee has provided a comitment to include this schedule in the next I
revision of the updated Final Safety Analysis Report (FSAR).
In addition, the licensee will include any subsequent NRC-approved revisions to this schedule in an update of the FSAR.
The inclusion of the withdrawal schedule in the FSAR provides a source for this information that is readily available as a reference for NRC inspectors and other staff use.
The licensee has proposed a change to TS 4.6.A.7 that is consistent with the guidance provided in GL 91-01 for the removal of the complete Surveillance l
Requirement. The NRC has reviewed this matter and finds that the proposed changes are acceptable.
The NRC staff has also reviewed the proposed changes to the Bases and has no objections to them.
3.0 STATE CONSULTATION
In accordance with the Comission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official i
had no coments.
4.0 ENVIRONMENTAL CONSIDERATION
l The amendment 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 Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public coment on such finding (58 FR 41511). 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.
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5.0 CONCLUSION
Therefore, the staff concludes 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 these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
Thomas G. Dunning, OTSB/ DORS Maudette Griggs, PDI-1/DRPE Date:
October 7, 1943
October 7, 1993 Docket No. 50-333 i
Mr. Ralph E. Beedle Executive Vice President - Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Beedle:
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M86956)
The Commission has issued the enclosed Amendment No.199 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant.
The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated June 24, 1993.
The amendment removes TS 4.6. A.7 which provided the schedule for removing reactor vessel material specimens. Guidance on the TS change was provided in Generic Letter 91-01, " Removal of the Schedule for the Withdrawal of Reactor Vessel Material Specimens from Technical Specifications," dated January 4, 1990. The amendment also incorporates associated changes to the TS Bases.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance r
will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely John E. Men ing, Project tanager Project Directorate I-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No.
to DPR-59 2.
Safety Evaluation t
cc w/ enclosures:
See next page
- See previous concurrence OFFICE PDI-1:LA PDI-1:PM
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OfflCIAL RECORD COPY FILENAME: G:\\FITZ\\ FIT 86956.AMD
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