ML17262B123
| ML17262B123 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/29/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17262B122 | List: |
| References | |
| NUDOCS 9212300261 | |
| Download: ML17262B123 (4) | |
Text
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P0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 50 TO FACILITY OPERATING LICENSE NO.
DPR-18 ROCHESTER GAS AND ELECTRIC CORPORATION R.
E.
GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244
- 1. 0 INTRODUCTION By letter dated June 22, 1992, the Rochester Gas and Electric Corporation (the licensee) requested an amendment to Facility Operating License No.
DPR-18 to change the technical specifications (TS) for the R.
E. Ginna Nuclear Power Plant.
The proposed change removes TS 4.3. 1.2 and the table that provides the schedule for reactor vessel material specimen withdrawal, which is a part of TS 4.3. 1. 1.
Guidance on the proposed TS change was provided by Generic Letter (GL 91-01) dated January 4,
1991, to all holders of operating licenses or construction permits for nuclear power reactors.
2.0 EVALUATION TS 3. 1.2, "Heatup and Cooldown L'imit Curves for Normal Operation," contains the limiting condition for operation 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 Hechanical Engineers (ASHE)
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 TS includes a surveillance requirement, TS 4.3. 1, "Reactor Vessel Haterial Surveillance Testing," to require 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.
TS 4.3. 1. 1 includes a table that identifies the material specimens and specifies the schedule for removal of each specimen.
TS 4.3. 1.2 states that the report of the reactor vessel material surveillance shall be a summary technical report as required by Appendix H to 10 CFR Part 50.
The removal of the schedule for withdrawing material specimens from the TS will eliminate the necessity of a license amendment to make changes to this schedule.
- However,Section I,B.3 of Appendix H to 10 CFR Part 50 requires the submittal of a proposed withdrawal schedule for material specimens to the U.S.
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Nuclear Regulatory Commission (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 process by including it in the TS.
Likewise, the requirements of TS 4.3. 1.2 are redundant to the requirements of Appendix H to 10 CFR Part 50 and are, therefore, unnecessary.
The licensee has provided a commitment to include'his schedule in the next revision of the Updated Final Safety Analysis Report (UFSAR).
In addition, the licensee will include any subsequent NRC-approved revisions to this schedule in an update of the UFSAR.
The inclusion of the withdrawal schedule in the UFSAR provides a source for this information that is readily available as a reference for NRC inspectors and other staff use.
Finally, the surveillance requirements for removing material specimens and the bases section for this specification remain unchanged.
The licensee has proposed a change, to TS 4.3. 1. 1 and the removal of TS 4.3. 1.2 that is consistent with the guidance provided in Generic Letter 91-01 for the removal of the table of reactor vessel material specimen withdrawal schedule from the TS.
The NRC has reviewed this matter and finds that the proposed changes to the Ginna TS are 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 comme'nts.
- 4. 0 ENVIRONMENTAL CONSIDERATION This amendment changes a requirement with respect to the 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'ssued a
proposed finding that the amendment involves no significant hazards consideratio'n and there has been no public comment on such finding (57 FR 55589).
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
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 Contributors:
Thomas G. Dunning Allen R. Johnson Date:
December 29, 1992
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