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| | issue date = 08/30/1985 | | | issue date = 08/30/1985 |
| | title = Revised Application for Amends to Licenses DPR-32 & DPR-37, Changing Administrative Portion of Tech Spec to Reflect Reorganization of Nuclear Operations Dept & Changes to LER Sys | | | title = Revised Application for Amends to Licenses DPR-32 & DPR-37, Changing Administrative Portion of Tech Spec to Reflect Reorganization of Nuclear Operations Dept & Changes to LER Sys |
| | 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 = DENTON H R, VARGA S A | | | addressee name = Denton H, Varga S |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000280, 05000281 | | | docket = 05000280, 05000281 |
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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 = 5 | | | page count = 5 |
| | | project = |
| | | stage = Request |
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| * VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 w. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS August 30, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
| | VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 |
| VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGES Serial No. NO/JDH:acm Docket Nos. License Nos. 85-589 50-280 50-281 DPR-32 DPR-37 In our letter dated November 2, 1984 (Serial No. 577), we submitted a request for an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Unit Nos. 1 and 2. The proposed changes were to the administrative portion of the Technical Specifications (Section 6) and reflected a reorganization of the Nuclear Operations Department. | | : w. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS August 30, 1985 Mr. Harold R. Denton, Director Serial No. 85-589 Office of Nuclear Reactor Regulation NO/JDH:acm Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen: |
| On April 17, 1985 (Serial No. 577A), we supplemented the proposal to address a change in the Health Physics organization at Surry. As a result of several subsequent discussions with the NRC Surry Project Manager and technical reviewers, we are again supplementing the proposed change. A discussion of these additional changes is provided in Attachment | | VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGES In our letter dated November 2, 1984 (Serial No. 577), we submitted a request for an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Unit Nos. 1 and 2. The proposed changes were to the administrative portion of the Technical Specifications (Section 6) and reflected a reorganization of the Nuclear Operations Department. On April 17, 1985 (Serial No. 577A), we supplemented the proposal to address a change in the Health Physics organization at Surry. As a result of several subsequent discussions with the NRC Surry Project Manager and technical reviewers, we are again supplementing the proposed change. A discussion of these additional changes is provided in Attachment 1. |
| : 1. In roughly the same time frame, we had also proposed and supplemented changes to the Technical Specifications to reflect the new Licensee Event Report System. These proposed changes were submitted on November 30, 1984 (Serial No. 198) and supplemented on April 12, 1985 (Serial No. 198A). Many of the pages affect.ed by this revision were also affected by the reorganization changes. In order to simplify the processing and issuance of the requested changes, we have consolidated all five submittals (i.e., the November 2 and 30, 1984 requests, the April 12 and 17, 1985 requests, and this request) into one package. The consolidated pages incorporating all five requests are included as Attachment
| | In roughly the same time frame, we had also proposed and supplemented changes to the Technical Specifications to reflect the new Licensee Event Report System. These proposed changes were submitted on November 30, 1984 (Serial No. 198) and supplemented on April 12, 1985 (Serial No. 198A). |
| : 2. 8509100199 850830 PDR ADOCK 05000280 p PDR '°p/ 11~,,
| | Many of the pages affect.ed by this revision were also affected by the reorganization changes. |
| e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton Page 2 This submittal does not alter the conclusions, safety review, or significant hazards determination of the previous requests. | | In order to simplify the processing and issuance of the requested changes, we have consolidated all five submittals (i.e., the November 2 and 30, 1984 requests, the April 12 and 17, 1985 requests, and this request) into one package. The consolidated pages incorporating all five requests are included as Attachment 2. |
| The submittal has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. Since this information supplements our previous submittal, which included the appropriate application fee, no additional application fee is included. | | '°p/ |
| | ( 8509100199 850830 PDR ADOCK 05000280 11~,, |
| | p PDR |
| | |
| | i e |
| | VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton Page 2 This submittal does not alter the conclusions, safety review, or significant hazards determination of the previous requests. The submittal has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. |
| | Since this information supplements our previous submittal, which included the appropriate application fee, no additional application fee is included. |
| If you have any questions, or need additional information, please contact us ;immediately. | | If you have any questions, or need additional information, please contact us ;immediately. |
| Very truly yours, W. L. Stewart Attachments | | Very truly yours, W. L. Stewart Attachments |
| : 1. Discussion of Proposed Changes 2. Consolidated Set of Proposed Technical Specification Changes cc: Dr. J. Nelson Grace Regional Administrator Region II Mr. D. J. Burke NRG Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 i COMMONWEALTH OF VIRGINIA) ) CITY OF RICHMOND ) The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L. Stewart who is Vice President | | : 1. Discussion of Proposed Changes |
| -Nuclear Operations, of Virginia Power. 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 ~0~\'--day of My Commission expires: _"\~~-~ ....... ~-0-c...:=~~~
| | : 2. Consolidated Set of Proposed Technical Specification Changes cc: Dr. J. Nelson Grace Regional Administrator Region II Mr. D. J. Burke NRG Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 |
| ...... \-~--~' 19 -~-~---~ \ (SEAL) S/001 ATTACHMENT 1 DISCUSSION OF PROPOSED CHANGES e e DISCUSSION OF PROPOSED CHANGES On November 2, 1984, we submitted a proposed TS change on reorganization. | | |
| We supplemented the change on April 17, 1985. As a result of several discussions with the NRC Surry Project Manager and technical reviewers, we are again supplementing the proposed change as follows: Section 6.1.B.l and 6.1.B.3. In our November 2, 1984 submittal, we proposed to revise the minimum qualifications standard referenced in the TS from ANSI N.18.1-1971 to ANS 3.1 (12/79 Draft). This change was proposed to make the TS consistent with the current QA topical report, VEP-1 (Revision 4), approved by the NRC, which references ANS 3.1. We subsequently noted that the originally proposed wording in section 6 .1 implied that we intended to meet ANS 3.1, without exception. | | COMMONWEALTH OF VIRGINIA) |
| That is not correct. Exceptions to the standard are identified in VEP-1 and we propose to add a footnote for clarification. | | ) |
| The footnote states: "Exceptions to this requirement are specified in VEPCO' s QA Topical Report, VEP-1, Quality Assurance Program, Operations Phase." Section 6.1.C.l.g. | | CITY OF RICHMOND ) |
| In our November 2, 1984 submittal, we proposed that SNSOC provide written approval of 1) procedures and procedure changes; 2) all proposed that test and experiments, and 3) all proposed changes or modifications to plant systems or equipment. | | The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L. Stewart who is Vice President - |
| We are clarifying this change to identify the responsible individual, an Assistant Station Manager, who will certify all SNSOC approvals in writing. The additional sentence states: "SNSOC approval shall be certified in writing by an Assistant Station Manager." Section 6.6 The current specification identifies the Director of the appropriate IE Regional Office as the recipient of several reports. The proposed changes revises the TS to reflect the current NRC organization, i.e., Regional Administrator of an NRC regional office. Section 6.6.3.f. This specification requires that we submit a special summary technical report on the initial containment structural tests. These reports were submitted on August 18, 1972 (Surry 1) and May 11, 1973 (Surry 2). The specification is a one-time requirement that has been met. We propose that Section 6.6.3.f. be deleted. These changes supplement and clarify the proposed Technical Specification changes submitted to the NRC on November 2, 1984 and April 17, 1985. These changes do not alter the conclusions, 50.59 reviews, or no significant hazards consideration determinations of the previous submittals. | | Nuclear Operations, of Virginia Power. 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 ~0~\'-- day of |
| | .......~-0-c.. :=~~~......\-~--~' 19 -~-~---~ |
| | My Commission expires: _"\~~-~ |
| | \ |
| | (SEAL) |
| | S/001 |
| | |
| | ATTACHMENT 1 DISCUSSION OF PROPOSED CHANGES |
| | |
| | e e DISCUSSION OF PROPOSED CHANGES On November 2, 1984, we submitted a proposed TS change on reorganization. We supplemented the change on April 17, 1985. As a result of several discussions with the NRC Surry Project Manager and technical reviewers, we are again supplementing the proposed change as follows: |
| | Section 6.1.B.l and 6.1.B.3. In our November 2, 1984 submittal, we proposed to revise the minimum qualifications standard referenced in the TS from ANSI N.18.1-1971 to ANS 3.1 (12/79 Draft). This change was proposed to make the TS consistent with the current QA topical report, VEP-1 (Revision 4), approved by the NRC, which references ANS 3.1. |
| | We subsequently noted that the originally proposed wording in section 6 .1 implied that we intended to meet ANS 3.1, without exception. That is not correct. Exceptions to the standard are identified in VEP-1 and we propose to add a footnote for clarification. The footnote states: "Exceptions to this requirement are specified in VEPCO' s QA Topical Report, VEP-1, Quality Assurance Program, Operations Phase." |
| | Section 6.1.C.l.g. In our November 2, 1984 submittal, we proposed that SNSOC provide written approval of 1) procedures and procedure changes; 2) all proposed that test and experiments, and 3) all proposed changes or modifications to plant systems or equipment. We are clarifying this change to identify the responsible individual, an Assistant Station Manager, who will certify all SNSOC approvals in writing. The additional sentence states: |
| | "SNSOC approval shall be certified in writing by an Assistant Station Manager." |
| | Section 6.6 The current specification identifies the Director of the appropriate IE Regional Office as the recipient of several reports. The proposed changes revises the TS to reflect the current NRC organization, i.e., |
| | Regional Administrator of an NRC regional office. |
| | Section 6.6.3.f. This specification requires that we submit a special summary technical report on the initial containment structural tests. These reports were submitted on August 18, 1972 (Surry 1) and May 11, 1973 (Surry 2). The specification is a one-time requirement that has been met. We propose that Section 6.6.3.f. be deleted. |
| | These changes supplement and clarify the proposed Technical Specification changes submitted to the NRC on November 2, 1984 and April 17, 1985. These changes do not alter the conclusions, 50.59 reviews, or no significant hazards consideration determinations of the previous submittals. |
| MISC/136/JH/cgs}} | | MISC/136/JH/cgs}} |
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MONTHYEARML18152B6571999-04-28028 April 1999 Application for Amends to Licenses DPR-32 & DPR-37,revising TSs Re Refueling Water Chemical Addition Tank Min Vol ML18152B5431999-02-16016 February 1999 Application for Amends to Licenses DPR-32 & DPR-37,revising TS Re Augmented Insp Requirements for Reactor Coolant Pump Flywheels ML18152B5501999-02-16016 February 1999 Application for Amends to Licenses DPR-32 & DPR-37,proposing Administrative Change That Will Consolidate AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6 ML18152B6131998-11-0404 November 1998 Application for Amends to Licenses DPR-32 & DPR-37,revising EDG Start & Load Time Testing Requirements in TS 4.6.A.1.b ML18153A3291998-09-24024 September 1998 Application for Amends to Licenses DPR-32 & DPR-37,modifying Testing Requirements for Reactor Trip Bypass Breaker ML18151A6801998-06-19019 June 1998 Application for Amends to Licenses DPR-32 & DPR-37, Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers.Application Revised 971105 Submittal ML18153A2891998-03-25025 March 1998 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,revising Station Mgt Titles to Reflect New Positions Approved by Vepc Power Board of Directors on 980220 ML18153A3451997-12-18018 December 1997 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Terminology Used for Describing Equipment Surveillances Conducted in Refueling Interval Frequency. Amend Consistent W/Info Provided in Rev 1 of NUREG-1431 ML18151A9791997-11-0505 November 1997 Application for Amends to Licenses DPR-32 & DPR-37, Respectively.Amends Will Revise TS to Increase Maximum Allowable Fuel Enrichment from 4.1 to 4.3 Weight Percent U-235.Description of Change Encl ML18152A0761997-11-0505 November 1997 Application for Amends to Licenses DPR-32 & DPR-37, Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers ML18153A6331996-11-26026 November 1996 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,respectively,eliminating Records Retention Requirements Section of Ts,Per GL 95-06 & Adminstrative Ltr 95-06 ML18153A6881996-04-15015 April 1996 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Applicability of Quadrant Power Tilt Ratio Requirements ML18153A5371996-03-21021 March 1996 Application for Amends to Licenses DPR-32 & DPR-37, Clarifying Requirements for Testing Charcoal Adsorbent in Auxiliary Ventilation & Control Room Air Filtration Sys as Outlined in Tech Specs 4.12 & 4.20,respectively ML18153A5781996-01-30030 January 1996 Application for Amends to Licenses DPR-32 & DPR-37, Eliminating Surveillance Requirement for Certain Reactor Coolant Liquid Samples ML18153A6741995-11-20020 November 1995 Application for Amends to Licenses DPR-32 & DPR-37,permiting Use of 10CFR50 App J,Option B Performance-Based Containment Leakage Rate Testing. ML18153A7121995-07-20020 July 1995 Application for Amends to Licenses DPR-32 & DPR-37,proposing Changes to Ts,By Establishing New Setpoint Limit for Steam Generator high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints ML18153A6971995-07-14014 July 1995 Application for Amends to Licenses DPR-32 & DPR-37,providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing Su Accumulators in Lieu of Isolation ML18152A1841995-02-14014 February 1995 Application for Amends to Licenses DPR-32 & DPR-37,revising TS 4.4.D to Permit Approved Exemptions to ILRT Frequency Requirements,Including one-time Exemption Request from Section III.D.1(a) of 10CFR50,App J for Surry Unit 2 ML18153B2111995-01-24024 January 1995 Application for Amends to Licenses DPR-32 & DPR-37,modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves ML18153B1601994-11-29029 November 1994 Application for Amends to Licenses DPR-32 & DPR-37,revising TSs to Implement Zirlo Fuel Cladding ML18153B1561994-11-22022 November 1994 Application for Amends to Licenses DPR-32 & DPR-37,deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries ML18153B1481994-11-10010 November 1994 Application for Amends to Licenses DPR-32 & DPR-37 to TS Re Changes to TS to Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic ML18153B0921994-10-11011 October 1994 Application for Amends to Licenses DPR-32 & DPR-37,modifying Surveillance Frequencies of Hydrogen Analyzers in Accordance W/Generic Ltr 93-05 ML18153B0491994-08-30030 August 1994 Application for Amends to Licenses DPR-32 & DPR-37,revising TS to Accomodate Core Uprating,In Accordance w/WCAP-10263, Review Plan for Uprating Licensed Power of PWR Power Plant. 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.... ML18153B4301993-12-27027 December 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,changing TS to Revise Review Responsibilities of Station Nuclear Safety & Operating Committee & Mgt Safety Review Committee ML18153B3481993-10-19019 October 1993 Application for Amends to Licenses DPR-32 & DPR-37,adding Operability & Action Statements for RSHX Service Water Outlet Radiation Monitors to TS Table 3.7-6 & SRs for Monitors to TS Table 4.1-2 ML18153B3301993-09-29029 September 1993 Application for Amends to Licenses DPR-32 & DPR-37,modifying TS to Require Insp Frequency of Low Pressure Turbine Blades to Permit Blade Insp to Perform Concurrent W/Disk & Hub Insp ML18153D3951993-07-20020 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 Proposing Changes of Deletion of Requirement for Station Nuclear Safety & Operating Committee & Audit Frequencies ML18153D3901993-07-16016 July 1993 Application for Amends to Licenses DPR-32 & DPR-37,proposing Changes to 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
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Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261
- w. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS August 30, 1985 Mr. Harold R. Denton, Director Serial No.85-589 Office of Nuclear Reactor Regulation NO/JDH:acm Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGES In our letter dated November 2, 1984 (Serial No. 577), we submitted a request for an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Unit Nos. 1 and 2. The proposed changes were to the administrative portion of the Technical Specifications (Section 6) and reflected a reorganization of the Nuclear Operations Department. On April 17, 1985 (Serial No. 577A), we supplemented the proposal to address a change in the Health Physics organization at Surry. As a result of several subsequent discussions with the NRC Surry Project Manager and technical reviewers, we are again supplementing the proposed change. A discussion of these additional changes is provided in Attachment 1.
In roughly the same time frame, we had also proposed and supplemented changes to the Technical Specifications to reflect the new Licensee Event Report System. These proposed changes were submitted on November 30, 1984 (Serial No. 198) and supplemented on April 12, 1985 (Serial No. 198A).
Many of the pages affect.ed by this revision were also affected by the reorganization changes.
In order to simplify the processing and issuance of the requested changes, we have consolidated all five submittals (i.e., the November 2 and 30, 1984 requests, the April 12 and 17, 1985 requests, and this request) into one package. The consolidated pages incorporating all five requests are included as Attachment 2.
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VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton Page 2 This submittal does not alter the conclusions, safety review, or significant hazards determination of the previous requests. The submittal has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.
Since this information supplements our previous submittal, which included the appropriate application fee, no additional application fee is included.
If you have any questions, or need additional information, please contact us ;immediately.
Very truly yours, W. L. Stewart Attachments
- 1. Discussion of Proposed Changes
- 2. Consolidated Set of Proposed Technical Specification Changes cc: Dr. J. Nelson Grace Regional Administrator Region II Mr. D. J. Burke NRG Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219
COMMONWEALTH OF VIRGINIA)
)
CITY OF RICHMOND )
The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L. Stewart who is Vice President -
Nuclear Operations, of Virginia Power. 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 ~0~\'-- day of
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My Commission expires: _"\~~-~
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ATTACHMENT 1 DISCUSSION OF PROPOSED CHANGES
e e DISCUSSION OF PROPOSED CHANGES On November 2, 1984, we submitted a proposed TS change on reorganization. We supplemented the change on April 17, 1985. As a result of several discussions with the NRC Surry Project Manager and technical reviewers, we are again supplementing the proposed change as follows:
Section 6.1.B.l and 6.1.B.3. In our November 2, 1984 submittal, we proposed to revise the minimum qualifications standard referenced in the TS from ANSI N.18.1-1971 to ANS 3.1 (12/79 Draft). This change was proposed to make the TS consistent with the current QA topical report, VEP-1 (Revision 4), approved by the NRC, which references ANS 3.1.
We subsequently noted that the originally proposed wording in section 6 .1 implied that we intended to meet ANS 3.1, without exception. That is not correct. Exceptions to the standard are identified in VEP-1 and we propose to add a footnote for clarification. The footnote states: "Exceptions to this requirement are specified in VEPCO' s QA Topical Report, VEP-1, Quality Assurance Program, Operations Phase."
Section 6.1.C.l.g. In our November 2, 1984 submittal, we proposed that SNSOC provide written approval of 1) procedures and procedure changes; 2) all proposed that test and experiments, and 3) all proposed changes or modifications to plant systems or equipment. We are clarifying this change to identify the responsible individual, an Assistant Station Manager, who will certify all SNSOC approvals in writing. The additional sentence states:
"SNSOC approval shall be certified in writing by an Assistant Station Manager."
Section 6.6 The current specification identifies the Director of the appropriate IE Regional Office as the recipient of several reports. The proposed changes revises the TS to reflect the current NRC organization, i.e.,
Regional Administrator of an NRC regional office.
Section 6.6.3.f. This specification requires that we submit a special summary technical report on the initial containment structural tests. These reports were submitted on August 18, 1972 (Surry 1) and May 11, 1973 (Surry 2). The specification is a one-time requirement that has been met. We propose that Section 6.6.3.f. be deleted.
These changes supplement and clarify the proposed Technical Specification changes submitted to the NRC on November 2, 1984 and April 17, 1985. These changes do not alter the conclusions, 50.59 reviews, or no significant hazards consideration determinations of the previous submittals.
MISC/136/JH/cgs