ML18153C930: Difference between revisions

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| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 2
| page count = 2
| project =
| stage = Supplement
}}
}}


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9203170203 920309 PDR ADOCK 05000280 p                  PDR
9203170203 920309 PDR ADOCK 05000280 p                  PDR


i
i The change request of January 22, 1992 was reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It was determined that those proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The resubmittal of the entire Section 3.23 to cross-reference previously NRC approved, unit-specific NRC license amendments into both operating licenses is administrative in nature and does not impact the safety evaluation or the previously submitted Significant Hazards Consideration Determination. The previously approved, unit-specific NRC SERs form the basis for the cross-reference resubmittal.
* The change request of January 22, 1992 was reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It was determined that those proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The resubmittal of the entire Section 3.23 to cross-reference previously NRC approved, unit-specific NRC license amendments into both operating licenses is administrative in nature and does not impact the safety evaluation or the previously submitted Significant Hazards Consideration Determination. The previously approved, unit-specific NRC SERs form the basis for the cross-reference resubmittal.
   ~~
   ~~
   ~ - Stewart Senior Vice President - Nuclear Attachments cc:    U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
   ~ - Stewart Senior Vice President - Nuclear Attachments cc:    U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W.Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health*
Suite 2900 Atlanta, Georgia 30323 Mr. M. W.Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health*
Room 400 109 Governor Street Richmond, Virginia 23219}}
Room 400 109 Governor Street Richmond, Virginia 23219}}

Latest revision as of 22:37, 2 February 2020

Supplemental Application for Amends to Licenses DPR-32 & DPR-37,including cross-referenced TS Section 3.23 Re Main CR & Emergency Switchgear Room Air Handling Units
ML18153C930
Person / Time
Site: Surry  Dominion icon.png
Issue date: 03/09/1992
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153C931 List:
References
92-033A, 92-33A, NUDOCS 9203170203
Download: ML18153C930 (2)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 e

March 9, 1992 United States Nuclear Regulatory Commission Serial No. 92-033A Attention: Document Control Desk NO/ETS Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION FOR THE MAIN CONTROL ROOM AND EMERGENCY SWITCHGEAR ROOM AIR CONDITIONING SYSTEM - SUPPLEMENTAL SUBMITTAL In support of the Main Control Room (MCR) and Emergency Switchgear Room (ESGR) air conditioning system upgrades, several Technical Specifications amendments have been necessary for both Units 1 and 2. Initially, both the Units 1 and 2 Technical Specifications were concurrently changed to provide interim operating restrictions (Amendment Nos. 129/129, dated May 30, 1989). Subsequently, each unit's Technical Specifications were individually modified to account for unit specific Air Handling Unit (AHU) replacements, which occurred during sequential refueling outages. Unit specific Technical Specification changes were granted which removed the interim operating restrictions on the AHUs (Amendments 145, dated October 11, 1990 and 151, dated April 11, 1991, for Units 1 and 2 respectively). On January 22, 1992, Virginia Electric and Power Company requested an amendment, in the form of a change to the Technical Specifications, for Surry Power Station Units 1 and 2 to complete additional air conditioning system upgrades. This change would permit continued operation for seven days with one of two AHUs in each ventilation space out of service to install chilled water connections for planned modifications to add chiller capacity.

As a shared system with cross-referenced Technical Specifications these multiple unit-specific changes to Section 3.23 of the Technical Specifications have resulted in several administrative inconsistencies between the individual unit's Technical Specifications (i.e., incorrect cross-reference requirements, format, and pagination problems). To clarify this condition, we are resubmitting our January 22, 1992 request for both units to include a complete cross-referenced Section 3.23. This change provides consistency in the cross-referencing of opposite unit's requirements by integrating the previously NRC approved unit-specific Technical Specification changes (Amendments 145 and 151) into both operating licenses. The modified Technical Specification change request is included in Attachment 1. The changes for the administrative cross-referencing between units are identified with a single bar and the original change request is identified with double bars. Please replace Attachment 2 of the January 22, 1992 letter with Attachment 1 of this letter.

-~-- - ---~

9203170203 920309 PDR ADOCK 05000280 p PDR

i The change request of January 22, 1992 was reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It was determined that those proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The resubmittal of the entire Section 3.23 to cross-reference previously NRC approved, unit-specific NRC license amendments into both operating licenses is administrative in nature and does not impact the safety evaluation or the previously submitted Significant Hazards Consideration Determination. The previously approved, unit-specific NRC SERs form the basis for the cross-reference resubmittal.

~~

~ - Stewart Senior Vice President - Nuclear Attachments cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W.Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health*

Room 400 109 Governor Street Richmond, Virginia 23219

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