ML18153B923
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| ML18153B923 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/12/1989 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18153B924 | List: |
| References | |
| 89-693, NUDOCS 8910170226 | |
| Download: ML18153B923 (3) | |
Similar Documents at Surry | |
|---|---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
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ML18153B0041994-07-14014 July 1994 Application for Amends to Licenses DPR-32 & DPR-37, Requesting Amendments in Form of Changes to TS to Eliminate Remaining References to cycle-specific Parameters in Surry TS ML18153A9651994-06-0909 June 1994 Application for Amends to Licenses DPR-32 & DPR-37,modifying in Part,Chemical & Vol Control Sys Specs & Safety Injection Sys Specs in Accordance w/NUREG-0452,Rev 4,NUREG-1431 & Generic Ltr 93-05 ML18153A8801994-02-25025 February 1994 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys in Accordance W/Gl 93-05, Line-Item TS Improvements to Reduced Srs.... 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TS to Permit Operation W/Three Degree Increase in Svc Water Temp Limit for Containment Air Partial Pressures of 9.1,9.2 & 9.35 Psia ML18153D3931993-07-16016 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 to Implement Revised 10CFR20,revise Frequency of Radiological Effluent Release Repts from Semiannual to Annual & Clarify Site Maps ML18153D3791993-07-0202 July 1993 Application for Amends to Licenses DPR-32 & DPR-37,updating Augmented Insp Program for Sensitized Stainless Steel to Incorporate Newer Code Requirements While Maintaining Increased Insp Philosophy of ASLB ML18153D3781993-07-0202 July 1993 Application for Amends to Licenses DPR-32 & DPR-37 Modifying TS to Include COLR Which Presents reload-specific Limits for Key Core Operating Parameters ML18152A4471993-05-0606 May 1993 Application for Amend to License DPR-37,modifying TS to Support Operation of Unit 2 w/100 Psi Reduction in RCS Nominal Operating Pressure Through End of Operating Cycle 12,per Enforcement Discretion Granted by NRC on 930504 ML18153D3141993-04-21021 April 1993 Application for Amends to Licenses DPR-32 & DPR-37,providing Clarification of Design Response Time of Containment Hydrogen Analyzers & Deleting Unnecessary Channel Check for Analyzers ML18153D3111993-04-21021 April 1993 Suppl to 930315 Application for Amends to Licenses DPR-32 & DPR-37,modifying LCO & Action Statements for Main Control Room & Emergency Switchgear Room Air Conditioning Sys ML18153D2771993-03-19019 March 1993 Application for Amends to Licenses DPR-32 & DPR-37,revising TS to Address Operation W/Control Rod Urgent Failure Condition ML18153D2691993-03-15015 March 1993 Application for Amends to Licenses DPR-32 & DPR-37,changing TS to Permit Use of Two New Main Control Room & Emergency Switchgear Room Air Conditioning Sys Chillers,When Fully Operational,To Meet LCO ML18153D2281993-01-26026 January 1993 Application for Amends to Licenses DPR-32 & DPR-37,adding NRC Std Fire Protection License Condition to Each OL & Relocating Fire Protection Requirements from TS to Updated Fsar,Per GL 86-10 & GL 88-12 ML20128A5221993-01-22022 January 1993 Amends 173 & 172 to Licenses DPR-32 & DPR-37,respectively, Revising TS to Modify Acceptance Criteria for Functional Testing of Anchor Darling Mechanical Snubbers ML18153D1971992-12-11011 December 1992 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 ML18153D1681992-11-10010 November 1992 Application for Amends to Licenses DPR-32 & DPR-37, Specifying Action Statement for Operable Svc Water Flow Paths to Main Control & Emergency Switchgear Room Air Conditioning Condensers Governed by TS 3.14.C ML18153D1611992-10-26026 October 1992 Application for Amends to Licenses DPR-32 & DPR-37 to Increase Limit for Intermediate Range High Flux Reactor Trip Setpoint & to Eliminate Redundant Stipulation That Predicted Critical Rod Position Be Above Zero Power Insertion Limit ML18153D1171992-09-0404 September 1992 Suppl to 911230 Amend Applications 165 & 164 to Licenses DPR-32 & DPR-37,respectively,reinstating Allowed Outage Time for Surveillance Testing of Nonessential Svc Water Isolation Actuation Logic & Reformatting Logic ML18153D1141992-09-0404 September 1992 Application for Amends to Licenses DPR-32 & DPR-37,changing TS to Modify Acceptance Criteria for Functional Testing of Anchor/Darling Mechanical Snubbers to Reflect Replacement of Pacific Scientific Snubbers W/Anchor/Darling Snubbers ML18153D0871992-08-0707 August 1992 Application for Amends to Licenses DPR-32 & DPR-37, Establishing Operating Requirements for Recirculation Mode Transfer (Rmt) Function,Including LCO Action Statement & SR for Rmt & Deleting RWST Max Vol Requirements ML18153D0861992-08-0404 August 1992 Suppl to 911008 Application for Amends to Licenses DPR-32 & DPR-37,upgrading Portions of Section 3.0 & 4.0,per Generic Ltr 87-09 to Restrict Changes of Operational Conditions While in LCO & Delaying Entry Into Action Statement ML18153D0701992-07-28028 July 1992 Application for Amends to Licenses DPR-32 & DPR-37,deleting Operability & SRs of Hydrogen Monitor from Explosive Gas Monitoring Instrumentation Requirements for Waste Gas Holdup Sys & Including Requirements to Submit Special Rept to NRC 1999-04-28 |
Text
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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 12, 1989 United States Nuclear Regulatory Commission Serial No.89-693 Attention: Document Control Desk NURPC 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 CHANGE CONTROL ROD DROP TIME TEST FREQUENCY Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Units 1 and 2.
The proposed Technical Specification change will replace the portion of the control rod drop time test frequency requirement associated with "the breach of the Reactor Coolant System integrity." In substitution thereof, the test frequency will be clarified by using conditions similar to those that appear in the Westinghouse Standard Technical Specification.
The proposed change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this change does not involve an unreviewed safety question as defined in 10 CFR 50.59 and invo,lves no significant hazards considerations as defined in 10 CFR 50.92.
This request has been evaluated in accordance with the criteria of 10 CFR 170.12.
W. L. Stewart Senior Vice President - Power Attachments
- 1. Proposed Technical Specification Changes
- 2. Discussion and Significant Hazards Consideration Evaluation 8910 l 7022/:.. :=:9 j n 1 *::*
1:'DR P,:OOCI< 6~:i6i:>02:30
' 1-* PDC
cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland 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 docum*ent was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. R. Cartwright, who is Vice President - Nuclear, for W. L. Stewart, who is Senior Vice President -
Power, 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 /Z7l' day of (0~ , 19 8t:J.
My Commission Expires: ,~~!/ ZS , 19 q,1 .
--~~J_!dL__
Notary Public (SEAL)
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