ML19095A044
| ML19095A044 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/27/1977 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Case E, Reid R Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19095A044 (2) | |
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, VIRGINIA ELECTRIC AND PO~E~ COMPANY RIOHMOND, VIRGINIA 23261 May 27, 1977 Mr. Edson G. Case, Acting Director Office of Nuclear Reactor Regulation Attn:
Mr. Robert W. Reid, Chief.
Operating Reactors Branch No. 4 Division of Operating Reactors
- U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Case:
l, AMENDMENT TO OPERATING LICENSES DPR-32 AND DPR-37 TECHNICAL SPECIFICATION CHANGE NO. 53 SURRY POWER STATION UNITS NOS. l Aff02 Pursuant to 10CFR50.90, the Virginia Electri_c and Power Company" hereby requests an amendment, in the form of changes to the Technical Specifica-tions, to Operating Licenses DPR-32 and DPR-37 for the Surry Pm-Jer Station, Unit Nos. l and 2.
The proposed changes are enclosed herewith and have been designated as Change No. 53.
The pl"'bposed change modifies Section.5.4. B to specify that spent fuel will be stored in an array with a distance of 14 inches between assemblies while maintaining keff less thari or equal to 0.95, even if unborated water
. were used in the spent fuel pool.
This change is to be accomplished by replacing the existing spent fuel racks with high density spent fuel racks, i.e. the center to center spacing is reduced fro~ 21 inches to 14 inches.
This modification will increase the storage capacity of the spent fuel pool from 464 storage locations to 1044 storage locations. This modification is described in the report attached hereto.
"Summary of Proposed Modifica-tions to the Spent Fuel Pool Associated With Increasing Storage Capacity
.for Surry Power Station Unit Nos. l and 2 11 dated May 20, 1977. Subsequent to the preparation of much of the material in this report, the position of the Carter administration.concerning speht fuel feprocessing was announced.
No attempt was made to update the report, since the unavailability of re-processing increases the need for th~ proposed Technical Specification change.
This proposed change has been reviewed by the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Commit-tee. It has been determined that this change does not involve an unreviewed safety question as deffoed in 10CFR50.59.
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NIA EU:CTHlC AND Pow1rn COMPANY e Mr* Edson-G. Case Page 2 It is requested that this modification receive an expeditious review in order to eliminate any impact on the steam generator replacement schedule.
We would be pleased to meet with your itaff at their convenience to discuss the proposed modification.
Attachments cc:
Norman C. ~i'osel ey, Director yery truly ~ours,
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C. M. Stallings Vice President - Power Supply and Production Operations Office of Inspection & Enforcement Region II
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