ML17254A964
| ML17254A964 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 10/05/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17254A963 | List: |
| References | |
| NUDOCS 8410090256 | |
| Download: ML17254A964 (5) | |
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t UNITEDSTATES-NUCLEAR R EG ULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
64 TO PROVISIONAL 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 January 18, 1984, Rochester Gas and Electric Corporation (RG&E), the licensee, requested that the Technica1 Specifications set forth in Appendix A to Provisional Operating License DPR-18 be amended to delete the spacing restriction on storage of recently discharged fuel assemblies in the spent fuel pool.
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Re<eister on July 24, 1984 (49 FR 29919).
Ro requests for hearing and no punTic comments were received.
2.0 BACKGROUND
The Technical Specifications require that fuel assemblies with less than 60 days decay since irradiation not be placed in storage positions with less
,than a specified intercellular spacing.
The licensee requested the restriction be deleted in order to allow storage of spent fuel with less than 60 days decay in additional cells as well as in those already approved.
".3.0 EVALUATION 3.1 Cask Dro /Ti Accidents
~
Technical Specification 3.11.5 states that "The spent fuel shipping cask shall not be carried by the auxiliary building crane, pending the evaluation of the spent fuel cask drop accident and the crane design by RG&E, and NRC review and approval."
Since the shipping cask cannot presently be carried by the auxiliary building crane by this administrative control, a cask drop/tip accident is precluded for the proposed technical specification amendment.
A request to delete section 3.11.5 is currently under review by the staff.
,. -84'1'0090256
- 841005,
3.2 Tornado Missile Accidents The design values for tornado wind speed and missile characteristics were those established in the staff review of Systematic Evaluation Program (SEP)
Topics III-2, Wind and Tornado Loadin s, and III-4.A, Tornado Missiles.
The design miss1 e is state to e
a 1490 lb wooden po e, 3
eet
>n ength and 13.5 inches in diameter, which could impact the racks with a vertical velocity of 70 ft/sec.
The licensee's submittal states that the worst position for impact of this missile would be that centered on a fuel storage location where, because of the 13.5 inch missile diameter compared to a
diagonal dimension of the spent fuel storage box of 11.9 inches, the corners of four other fuel storage cells would be damaged.
This relative impact
'orientation of missile and storage cell configuration would have an extremely low likelihood of occurrence, however.
The staff judges that a conservative estimate of damage to stored spent fuel
, assemblies from impact of the design missile is sufficient damage to two assemblies to result in the release of their concomitant volatile gap activities.
In performing the radiological consequence analysis, it is assumed that the fuel has been discharged from the reactor after operation at a steady-state power level of 1551 Mll for an extended period of time.
The assumptions in the staff analysis are tisted in Table 1 below.
The
'alculated (0-2 hr) offsite radiological consequences are estimated to be 63 Rem thyroid and 0.1 Rem whole'body at the Exclusion Area Boundary, well within the guidelines of 10 CFR Part 100.
The staff concludes that since the spent fuel shipping cask may not be carried by the auxiliary building crane; cask drop/tip accidents need not be considered.
The staff also concludes that a tornado missile accident resulting in damage to two 30,000 MWd/t,spent fuel assemblies with at least l00 hours of cool-down time will result in atmospheric radionuclide releases with consequences which are well within the guidelines of 10 CFR Part 100.
Because the cask/tip accident does not need to be considered and the consequences of a tornado missile accident are within 10 CFR Part 100 limits, the staff concludes that the Technical Specification change is acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determ'ined 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this 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 this amendment.
- 5. 0 CONCLUSION The staff has further concluded, based on the considerations discussed
- above, that: (I) 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 this amendment will not be inimical to the common defense and security or to the health and safety of the public.
, 6.0 ACKNOWLEDGEMENT M. Wohl and A. Singh prepared this Safety Evaluation.
Dated:
October 5, 1984
Tabl e 1
Assumption in Staff Offsite Radiological Consequence Analysis of Postulated Tornado Missile Accident Reactor Power Level Effective Pool decontamination Factor fot Iodine 1551 MWth 100 Radial Power Peaking Factor
'I, Fuel Exposure for Impacted Spent Fuel Assembly Number of Equivalent Impacted Spent Fuel Assemblies Cooldown Time for Impacted Spent Fuel Assembly Diffusion and Transport Atmospheric Relative Concentration, 0-2 hours, at Exclusion Area Boundary Filters 1.2 30 000 NWd/t 100 hr 2.2 x 10 sec/m none assumed operational
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