ML20137G801
| ML20137G801 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/14/1986 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20137G738 | List: |
| References | |
| RTR-NUREG-0123, RTR-NUREG-123 NUDOCS 8601210216 | |
| Download: ML20137G801 (7) | |
Text
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BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of Docket Nos. 50-277 PHILADELPHIA ELECTRIC COMPANY 50-278 APPLICATION FOR AMENDMENT OF FACILITY OPERATING LICENSES DPR-44 & DPR-56 Edward G. Bauer, Jr.
Eugene J. Bradley 2301 Market Street Philadelphia, Pennsylvania 19101 Attorneys for Philadelphia Electric Company 6
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of Docket Nos. 50-277 PHILADELPHIA ELECTRIC COMPANY 50-278 APPLICATION FOR AMENDMENT OF f
FACILITY OPERATING LICENSES DPR-44 & DPR-56 Philadelphia Electric Company, Licensee under Facility Operating Licenses DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station Unit No. 2 and Unit No. 3, respectively, hereby requests that the Technical Specifications contained in Appendix A of the Operating Licenses be amended by revising certain sections as indicated by a vertical bar in the margin of attached pages 228a and 232.
The proposed change removes an ambiguous specification for the spent fuel storage pool water level and replaces it with the water level requirement that is based upon the Standard Technical Specifications for General Electric Boiling Water Reactors, NUREG-0123, Revision 3..
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Limiting Condition 3.10.C (page 228a) of the Technical l
Specifications currently states, "Whenever irradiated fuel is stored in the spent fuel pool, the pool water level shall be maintained at or above 8 1/2 feet above the top of the fuel".
1 The intent of the existing specification is to establish the minimum water coverage above the fuel while it is being transported by the fuel handling equipment.
However, the current wording could be misinterpreted as meaning the minimum water coverage above the fuel while it is stored in the storage racks at the bottom of the pool which would conflict with the actual design of the storage pool.
The value for water coverage in the Standard Technical Specifications (NUREG-0123, Rev. 3, page 3/4
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9-11) is based on water coverage above the fuel in the storage racks.
F Accordingly, Licensee requests a revision to Specification 3.10.C and associated Bases of the Peach Bottom Operating License that conform, except for one minor change, to the Standard Technical Specifications with regards to both the l
l limiting condition for operation and the associated action statement.
The proposed revision incorporates the value
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corresponding to the minimum water coverage above the fuel positioned in the storage racks.
The only deviation from the l
Standard Technical Specifications is the reference to " irradiated l
fuel" rather than " irradiated fuel assemblies" in Specification 3.10.C.
The deletion of the word " assemblies" is intended to avoid a potential misinterpretation that the fuel bundle lifting handle should be considered in the determination of minimum water l
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l coverage.
The change was discussed with the NRC staff in a l
telecon on November 19, 1985 and found to be acceptable, i
The revision does not change the design or operating l
procedures associated with the storage pool water level.
The 1
lowest elevation of the pool overflow weir to the skimmer surge l
tank'is such that more than 22 feet is always maintained above the fuel stored in the storage racks.
Finally, a statement in l
the Bases section (page 232) is proposed addressing minimum water coverage for the fuel stored in the storage racks.
Significant Hazards Consideration Determination l
The requested changes will not reduce the requirements l
of the current Technical Specifications.
The revision to the spent fuel storege pool limiting conditions for operation and the addition of an action statement conform, except for one minor change, to NRC guidance provided in the Standard Technical Specifications.
The proposed changes do not involve a significant hazards consideration since:
1.
The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because they improve compliance with the specification by enhancing the clarity of the limiting conditions for operation.
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2.
The proposed changes do not create the possibility of a new or different kind of accident from any accident 1
previously evaluated because they improve compliance with the specification by enhancing the clarity of the limiting conditions for operation.
3.
The changes do not involve a significant reduction in the margin of safety because the addition of an action statement for the water level limit minimizes the probability of a refueling accident with a below normal
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water level condition.
Indeed the change improves thet
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margin of safety assurance by providing a clearer
- v understanding of the inventory of water to be maintained in the spent fuel pool.
The Plant Operating Review Committee and the Nuclear Review Board have reviewed the proposed changes to the Technical Specifications, and have also concluded that they do not involve an unreviewed safety question or a significant hazards consideration, and will not endanger the health and safety of the public.
Respectfully submitted, PHILADELPHIA ELECTRIC'C MPANY 3
V i l
' Vice President
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1 COMMONWEALTH OF PENNSYLVANIA :
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~ COUNTY OF PHILADELPHIA S. L. Daltroff, being first duly sworn, deposes and says:
That he is Vice President of Philadelphia Electric Company, the Applicant herein; that he has read the foregoing Application for Amendment of Facility Operating Licenses and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
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/t i-4 Subscribed and sworn to before me this/
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/fN of Notary Public l
PATRICIA D. SCHOt1 Notary Pubsc, PhiNetphia. Philadelphis Co.
My Comtnission Empires February 10,1986 b
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e CERTIFICATE OF SERVICE I certify that service of the foregoing Application was made upon the Commonwealth of Pennsylvania, by malling a copy thereof, via first-class mail, to Thomas R. Gerusky, Director, Bureau of Radiological Protection, P. O. Box 2063, Harrisburg, PA 17120; all this 14th day of January,1936 h
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I Euge J Bradley Attorney for Philadelphia Electric Company J
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