ML18153A038
| ML18153A038 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/08/1996 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 96-356, NUDOCS 9608130253 | |
| Download: ML18153A038 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 8, 1996 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 SPENT FUEL COMMITMENTS Serial No.
NL&OS/GDM Docket Nos.
License Nos.96-356 R1 50-280 50-281 DPR-32 DPR-37 In your letter dated July 3, 1996, the NRG requested Virginia Electric and Power Company to confirm certain commitments associated with spent fuel and to indicate the completion dates for those actions. These commitments/actions included: 1) revising the Updated Final Safety Analysis Report (UFSAR) to clarify that a full core offload is the routine practice at Surry Power Station during each refueling outage, and 2) revising operating procedure 1-0P-FH-001, "Controlling Procedure for Refueling," to reference Technical Specification (TS) 3.1 O.A.12. This Technical Specification limits the maximum load that can be moved over the SFP to 110 percent of the weight of one fuel assembly (not including the fuel handling tool). Your letter also requested that we identify the means of ensuring that the thermal load associated with a specific full core offload is being adequately considered with respect to the spent fuel pool heat removal capacity.
UFSAR Revision Section 9.5, "Fuel Pool Cooling System," of the UFSAR was revised and submitted to the NRG on April 23, 1996 (Serial No.96-170) as part of Revision 26 of the UFSAR.
Section 9.5 states that..."A normal core offload condition is a planned offload of up to a full core. The most limiting condition for a normal core offload is a full core offload following refueling of the other unit." Therefore, the UFSAR appropriately describes the normal refueling practice as up to a full core offload.
Revision of 1-0P-FH-001 The Unit 2 operating procedure 2-0P-FH-001, "Controlling Procedure for Refueling,"
was revised to reference TS 3.1 O.A.12 in support of the recent Unit 2 refueling outage.
The Unit 1 procedure 1-0P-FH-001 is scheduled to be revised by November 30, 1996
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e to support the next Unit 1 refueling outage which is currently scheduled for February 1997.
Thermal Heat Load Associated With a Full Core Offload The bounding spent fuel heat loads for both normal and abnormal refueling conditions have been conservatively determined, and are discussed in detail in Section 9.5.3.4 of the April 1996 revision of the UFSAR. The refueling offload of the core is assumed to begin 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown and finish 130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> after shutdown. The 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> offload restriction is a Technical Specifications requirement and is included in the applicable refueling procedures.
The 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> assumed for core offloading is conservative with respect to actual practice.
Contingent upon a component cooling water (CCW) temperature restriction imposed in the normal core offload case, these bounding conditions for core offload have been determined to be within the design limits of the spent fuel pool cooling system. The CCW temperature restriction has been included in the Unit 2 refueling procedure and will be included in the Unit 1 refueling procedure in the scheduled revision noted above.
Therefore, verification of the thermal loads associated with core specific *offloads is not necessary prior to the core being stored in the spent fuel pool.
If you have any questions or require additional information, please contact us.
Very truly yours,
~?mo~
Senior Vice President - Nuclear cc:
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station