ML18153D197: Difference between revisions

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| issue date = 12/11/1992
| issue date = 12/11/1992
| title = Application for Amends to Licenses DPR-32 & DPR-37, Eliminating Operability Requirements for RCS Loop Stop Interlocks & Establishing Requirements for Operation of Loop Stop Valves
| title = Application for Amends to Licenses DPR-32 & DPR-37, Eliminating Operability Requirements for RCS Loop Stop Interlocks & Establishing Requirements for Operation of Loop Stop Valves
| author name = STEWART W L
| author name = Stewart W
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name =  
| addressee name =  
Line 14: Line 14:
| 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 = 3
| page count = 3
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 11, 1992 United States Nuclear Regulatory Commission Attention:
{{#Wiki_filter:e                                       e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 11, 1992 United States Nuclear Regulatory Commission                     Serial No. 92-672 Attention: Document Control Desk                               NO/ETS Washington, D. C. 20555                                         Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY.
VIRGINIA ELECTRIC AND POWER COMPANY. SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION REACTOR COOLANT SYSTEM LOOP STOP VALVE INTERLOCKS Serial No. NO/ETS Docket Nos. License Nos. 92-672 50-280 50-281 DPR-32 DPR-37 Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests changes to the Technical Specifications for Operating License Nos. DPR-32 and DPR-37, Surry Power Station Units 1 and 2, respectively.
SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION REACTOR COOLANT SYSTEM LOOP STOP VALVE INTERLOCKS Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests changes to the Technical Specifications for Operating License Nos. DPR-32 and DPR-37, Surry Power Station Units 1 and 2, respectively. The proposed changes eliminate the operability requirements for the Reactor Coolant System loop stop valve interlocks and
The proposed changes eliminate the operability requirements for the Reactor Coolant System loop stop valve interlocks and
* establish requirements for operation of the loop stop valves.
* establish requirements for operation of the loop stop valves. The proposed changes have been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee.
The proposed changes have been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It has been determined that the proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59, nor create a significant hazards consideration as defined in 10 CFR 50.92. A discussion of the changes and the basis for our no significant hazards consideration determination are included in Attachment 2.
It has been determined that the proposed changes do not involve an unreviewed safety question as defined in 1 O CFR 50.59, nor create a significant hazards consideration as defined in 1 O CFR 50.92. A discussion of the changes and the basis for our no significant hazards consideration determination are included in Attachment  
Ve~urai t~CS~\--*--\
: 2. Ve~urai t~CS~\--*--
: w. L:Srewart Senior Vice President - Nuclear Attachments
: w. L:Srewart  
: 1. Proposed Technical Specification
\ Senior Vice President  
: 2. Discussion and Significant Hazards Consideration
-Nuclear Attachments  
    ' 92121702~50 92f211 * ~-----...
: 1. Proposed Technical Specification  
PDR ADOCK 05000280
: 2. Discussion and Significant Hazards Consideration  
    . p                   PDR
' 92121702~50 92f211 * ~-----...
                                                                                      ~I I I
PDR ADOCK 05000280 . p PDR ~I I I 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 e COMMONWEAL TH OF VIRGINIA ) ) COUNTY OF HENRICO )
 
* The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vice President  
cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
-Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief. Acknowledged before me this mday of farun l:uJ , 199.Z.._.
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
My Commission Expires: ( 3/ , 19!J!l ~-~/Ila£ Notaryubhc (SEAL)}}
 
e COMMONWEALTH OF VIRGINIA )
                                    )
COUNTY OF HENRICO                   )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vice President -
Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this mday of       farun l:uJ , 199.Z.._.
My Commission Expires: (   ~ 3/               , 19!J!l
                                                      ~- ~/Ila£ Notaryubhc (SEAL)}}

Latest revision as of 22:33, 2 February 2020

Application for Amends to Licenses DPR-32 & DPR-37, Eliminating Operability Requirements for RCS Loop Stop Interlocks & Establishing Requirements for Operation of Loop Stop Valves
ML18153D197
Person / Time
Site: Surry  Dominion icon.png
Issue date: 12/11/1992
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153D198 List:
References
92-672, NUDOCS 9212170250
Download: ML18153D197 (3)


Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 11, 1992 United States Nuclear Regulatory Commission Serial No.92-672 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 REACTOR COOLANT SYSTEM LOOP STOP VALVE INTERLOCKS Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests changes to the Technical Specifications for Operating License Nos. DPR-32 and DPR-37, Surry Power Station Units 1 and 2, respectively. The proposed changes eliminate the operability requirements for the Reactor Coolant System loop stop valve interlocks and

  • establish requirements for operation of the loop stop valves.

The proposed changes have been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It has been determined that the proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59, nor create a significant hazards consideration as defined in 10 CFR 50.92. A discussion of the changes and the basis for our no significant hazards consideration determination are included in Attachment 2.

Ve~urai t~CS~\--*--\

w. L:Srewart Senior Vice President - Nuclear Attachments
1. Proposed Technical Specification
2. Discussion and Significant Hazards Consideration

' 92121702~50 92f211 * ~-----...

PDR ADOCK 05000280

. p PDR

~I I I

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

e COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vice President -

Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this mday of farun l:uJ , 199.Z.._.

My Commission Expires: ( ~ 3/ , 19!J!l

~- ~/Ila£ Notaryubhc (SEAL)