ML17263A441
| ML17263A441 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/20/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17263A440 | List: |
| References | |
| NUDOCS 9311040296 | |
| Download: ML17263A441 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 S
F TY EVA UATION BY THE OFFICE OF NUCL AR REACTOR REGULATION RELATED TO AMENDM NT NO. 56 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 1,
1990, the Rochester Gas and Electric Corporation (the licensee) submitted a request for changes to the R.
E. Ginna Nuclear Poder Plant Technical Specifications (TS).
The requested changes would change TS
- 3. 10.2.5 to specify time limits when required to shut down the plant due to =
quadrant to average power tilt ratio exceeding
- 1. 12.
- 2. 0 EVALUATION The quadrant power tilt ratio (gPTR) limit ensures that the gross radial power distribution remains consistent with the design values used in the safety analyses.
Precise radial power distribution measurements are made during startup testing, after refueling, and periodically during power operation.
The gPTR limiting condition for operation (LCO) precludes core power distributions that violate the following fuel design criteria:
a.
During a large break loss of coolant accident, the peak cladding temperature must not exceed 2200 'F (as required by 10 CFR 50.46);
b.
During a loss of forced reactor coolant flow accident, there must be at least 95X probability at the 95X confidence level (the 95/95 departure from nucleate boiling (DNB) criterion) that the hot fuel rod in the core does not experience a
DNB condition; c.
During an ejected rod accident, the fission energy input to the fuel must not exceed 280 cal/gm (per Regulatory Guide 1.77);
and d.
The control rods must be capable of shutting down the reactor with a minimum r equired shutdown margin with the highest worth control rod stuck fully withdrawn (as required by 10 CFR Part 50, Appendix A, GDC 26).
The gPTR limits ensure that F< and F0(Z) remain below their limiting values by preventing an undetected change in the gross radial power distribution.
In MODE 1, the F>H and F0(Z) limits must be maintained to preclude core power distributions from exceeding design limits assumed in the safety analyses.
931 1040296,931020 PDR ADOCK 05000244 P
The staff has reviewed the licensee's amendment request.
Considering that the proposed amendment will establish completion times where none currently exist, for required actions that already exist, the result is more conservatism.
The time provided to reach hot shutdown (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 50X power + 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to hot shutdown) is comparable to the time provided by the shutdown LCO (LCO 3.0. 1) of the existing Ginna TS (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to initiate action
+ 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to hot shutdown).
It should be noted that the defined hot shutdown MODE for Ginna, a
two loop Westinghouse pressurized water reactor (PWR), corresponds to the hot standby MODE for the standard four loop Westinghouse PWR (for which the Standard Technical Specification shutdown LCO (LCO 3.0.3) allows 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to reach).
The TS changes proposed by the licensee will provide a reasonably short period of time to correct the core power distribution to within the gPTR limits or reduce total core power.
These actions will ensure that the fuel design limits criteria will be satisfied or the plant will be shutdown.
The peHiod of vulnerability while the gross power distribution may be outside the limits is comparable to the time required for a controlled plant shutdown.
Therefore, the proposed a change is 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.
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 (55 FR 40474).
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
~CO C
US 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:
T.
R. Tjader Date:
October 20, 1993
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Sholly Coordinator October 20, 1993 Local Public Document Room location:
Rochester Public Library, 115 South
- Avenue, Rochester, New York 14610.
Original signed by Allen R. Johnson, Project Hanager Project Directorate I-3 Division of Reactor Projects I/II DISTRIBUTION:
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Sholly Coordinator October 20, 1993 Local Public Document Room location:
Rochester Public Library, 115 South
- Avenue, Rochester, New York 14610.
lien R. Johnson Project Manager Pr ate I-3 Division of Reactor Projects - I/II