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| {{#Wiki_filter:--' -*-------~\-----~ -e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWAR'.r VxcE PRESXDENT NUCLEAR 0PERA.TXONS January 11, 1984 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 Connnission Washington, D. C. 20555 Gentlemen: | | {{#Wiki_filter:- |
| Serial No. 179C NO/WDC:jab Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 AMENDMENT TO OP~RATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE In our letter dated May 4, 1983, (Serial No. 179) and supplemental letters dated September 23, 1983, (Serial No. 179A) and November 4, 1983, (Serial No. 179B), the Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-3 7 for the Surry Power Station, Unit Nos. 1 and 2. The proposed change included the Radiological Effluent Technical Specifications (RETS) in the Surry Technical Specifications.
| | -~\- --- -~ - |
| A supplement to the proposed change is enclosed. | | e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWAR'.r VxcE PRESXDENT NUCLEAR 0PERA.TXONS January 11, 1984 Mr. Harold R. Denton, Director Serial No. 179C Office of Nuclear Reactor Regulation NO/WDC:jab 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 Connnission DPR-37 Washington, D. C. 20555 Gentlemen: |
| This supplement is proposed to clarify the Radiological Effluent Technical Specification and comply with the requirements of NUREG -0472, Revision 3. The proposed Technical Specification changes are provided in Attachment | | AMENDMENT TO OP~RATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE In our letter dated May 4, 1983, (Serial No. 179) and supplemental letters dated September 23, 1983, (Serial No. 179A) and November 4, 1983, (Serial No. |
| : 1. A discussion of the proposed changes is provided in Attachment
| | 179B), the Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-3 7 for the Surry Power Station, Unit Nos. 1 and 2. The proposed change included the Radiological Effluent Technical Specifications (RETS) in the Surry Technical Specifications. A supplement to the proposed change is enclosed. |
| : 2. In addition to the supplemental changes, VEPCO requests additional time to implement RETS. Since the submittal of May 4, 1983, a review of station procedures and equipment has revealed implementation difficulties which may interfere with the smooth transition between Surry's current specification and the standardized RETS. Procedures currently under development provide a manual method to implement the RETS gaseous instantaneous effluent dose rate specification and liquid instantaneous concentration limits, prior to release of radioactive material.
| | This supplement is proposed to clarify the Radiological Effluent Technical Specification and comply with the requirements of NUREG - 0472, Revision 3. |
| The procedures also provide for manual calculation and tracking of the dose or dose connnitment to the maximum exposed member of the public from radioactive materials in the liquid and gaseous effluents. | | The proposed Technical Specification changes are provided in Attachment 1. A discussion of the proposed changes is provided in Attachment 2. |
| Due to the complex and tedious nature of the manual method, calculations are performed after the release has occurred and the release data sunnnarized. | | In addition to the supplemental changes, VEPCO requests additional time to implement RETS. Since the submittal of May 4, 1983, a review of station procedures and equipment has revealed implementation difficulties which may interfere with the smooth transition between Surry's current specification and the standardized RETS. |
| To facilitate the complex calculations, the number of releases and the number of various release :8401170437 840111 ; PDR ADOCK 05000280 p PDR i =--.!.... = ---*---~ e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton pathways, computerized dose calculation and dose trending are needed. Since the dose or dose commitment is the most limiting specification placed upon the effluent releases, this more desirable pre-release review and trending methodology should be implemented. | | Procedures currently under development provide a manual method to implement the RETS gaseous instantaneous effluent dose rate specification and liquid instantaneous concentration limits, prior to release of radioactive material. |
| Implementation of the computerized methodology will require an additional 4-6 months to develop and implement._ | | The procedures also provide for manual calculation and tracking of the dose or dose connnitment to the maximum exposed member of the public from radioactive materials in the liquid and gaseous effluents. Due to the complex and tedious nature of the manual method, calculations are performed after the release has occurred and the release data sunnnarized. To facilitate the complex calculations, the number of releases and the number of various release |
| | :8401170437 840111 ~ |
| | ; PDR ADOCK 05000280 p PDR |
| | |
| | i |
| | =-- .!.... = - - -*---~ |
| | e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton pathways, computerized dose calculation and dose trending are needed. Since the dose or dose commitment is the most limiting specification placed upon the effluent releases, this more desirable pre-release review and trending methodology should be implemented. Implementation of the computerized methodology will require an additional 4-6 months to develop and implement._ |
| In addition to procedural difficulties, certain channels of the Radiological Effluent Monitoring Instrumentation could place Surry in an action mode, as specified by Table 3.7-5(a) and Table 3.7-5(b), due to current maintenance and calibration problems. | | In addition to procedural difficulties, certain channels of the Radiological Effluent Monitoring Instrumentation could place Surry in an action mode, as specified by Table 3.7-5(a) and Table 3.7-5(b), due to current maintenance and calibration problems. |
| The Component Cooling Service Water Effluent Line Monitor is the originally installed equipment used to monitor gross leakage in the Component Coolant Heat Exchanger. | | The Component Cooling Service Water Effluent Line Monitor is the originally installed equipment used to monitor gross leakage in the Component Coolant Heat Exchanger. During the past 10 years of operation, the system has experienced design problems associated with sample pump reliability. Sample pump replacement or sample line relocation may provide monitor operability but design modification may be required to provide long term reliability and increased sensitivity. Refurbishment and a re-evaluation of the system design is in process. The proposed RETS requires reporting in the Semi-annual Radioactive Effluent Report if the system is not returned to operable status within 30 days of monitor failure. Current status of the system will place Surry in this action mode. |
| During the past 10 years of operation, the system has experienced design problems associated with sample pump reliability. | | The Waste Gas Holdup System Explosive Gas Monitors have experienced similar reliability problems. Constant recirculation through the gas monitors will be required to maintain monitor operability. The system has experienced sample recirculation problems with low tank pressure. The action mode for failure of this system places the station in a program of daily sampling of the Waste Gas Decay Tanks. |
| Sample pump replacement or sample line relocation may provide monitor operability but design modification may be required to provide long term reliability and increased sensitivity. | | The Condenser Air Ejector System flow rate measuring device will require factory calibration. Replacement monitors, calibrated at the factory, are in the process of being purchased, to be installed in the place of devices currently installed. |
| Refurbishment and a re-evaluation of the system design is in process. The proposed RETS requires reporting in the Semi-annual Radioactive Effluent Report if the system is not returned to operable status within 30 days of monitor failure. Current status of the system will place Surry in this action mode. The Waste Gas Holdup System Explosive Gas Monitors have experienced similar reliability problems. | | In view of these problems, an implementation date of July 1, 1984, is requested. This implementation date will eliminate the need for submitting two Semi-annual Radioactive Effluent Release Reports covering the first six months of 1984. The Radioactive Effluent Release Report for the first and second quarter shall be submitted in the format specified by the current Technical Specifications and the third and fourth quarter will be submitted in the format specified by the proposed RETS. The Semi-annual Radioactive Effluent Report submitted 60 days after January 1, 1985, shall include an evaluation of the dose commitment for the entire year. |
| Constant recirculation through the gas monitors will be required to maintain monitor operability. | | The extended date will facilitate smooth implementation of the proposed Radiological Effluent Technical Specifications and provide a sufficient period of time to eliminate the previously discussed problems. |
| The system has experienced sample recirculation problems with low tank pressure. | | This request has been reviewed and approved by the Surry Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. |
| The action mode for failure of this system places the station in a program of daily sampling of the Waste Gas Decay Tanks. The Condenser Air Ejector System flow rate measuring device will require factory calibration. | | It has been determined that this request does not pose a significant hazards |
| Replacement monitors, calibrated at the factory, are in the process of being purchased, to be installed in the place of devices currently installed. | | |
| In view of these problems, an implementation date of July 1, 1984, is requested. | | e e VJROINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton consideration as defined in 10CFR50. 92 or an unreviewed safety question as defined in 10CFR50.59. |
| This implementation date will eliminate the need for submitting two Semi-annual Radioactive Effluent Release Reports covering the first six months of 1984. The Radioactive Effluent Release Report for the first and second quarter shall be submitted in the format specified by the current Technical Specifications and the third and fourth quarter will be submitted in the format specified by the proposed RETS. The Semi-annual Radioactive Effluent Report submitted 60 days after January 1, 1985, shall include an evaluation of the dose commitment for the entire year. The extended date will facilitate smooth implementation of the proposed Radiological Effluent Technical Specifications and provide a sufficient period of time to eliminate the previously discussed problems. | | Very truly yours, |
| This request has been reviewed and approved by the Surry Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not pose a significant hazards e e VJROINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton consideration as defined in 10CFR50. 92 or an unreviewed safety question as defined in 10CFR50.59. | | &t~ |
| Very truly yours, &t~ W. L. Stewart Attachments: | | W. L. Stewart Attachments: |
| : 1. Proposed Technical Specification Change 2. Discussion of Proposed Technical Specification Change cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors NRC Project Manager -Surry Operating Reactors Branch No. 1 Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219}} | | : 1. Proposed Technical Specification Change |
| | : 2. Discussion of Proposed Technical Specification Change cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219}} |
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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.... 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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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWAR'.r VxcE PRESXDENT NUCLEAR 0PERA.TXONS January 11, 1984 Mr. Harold R. Denton, Director Serial No. 179C Office of Nuclear Reactor Regulation NO/WDC:jab 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 Connnission DPR-37 Washington, D. C. 20555 Gentlemen:
AMENDMENT TO OP~RATING LICENSES DPR-32 AND DPR-37 SURRY POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE In our letter dated May 4, 1983, (Serial No. 179) and supplemental letters dated September 23, 1983, (Serial No. 179A) and November 4, 1983, (Serial No.
179B), the Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-3 7 for the Surry Power Station, Unit Nos. 1 and 2. The proposed change included the Radiological Effluent Technical Specifications (RETS) in the Surry Technical Specifications. A supplement to the proposed change is enclosed.
This supplement is proposed to clarify the Radiological Effluent Technical Specification and comply with the requirements of NUREG - 0472, Revision 3.
The proposed Technical Specification changes are provided in Attachment 1. A discussion of the proposed changes is provided in Attachment 2.
In addition to the supplemental changes, VEPCO requests additional time to implement RETS. Since the submittal of May 4, 1983, a review of station procedures and equipment has revealed implementation difficulties which may interfere with the smooth transition between Surry's current specification and the standardized RETS.
Procedures currently under development provide a manual method to implement the RETS gaseous instantaneous effluent dose rate specification and liquid instantaneous concentration limits, prior to release of radioactive material.
The procedures also provide for manual calculation and tracking of the dose or dose connnitment to the maximum exposed member of the public from radioactive materials in the liquid and gaseous effluents. Due to the complex and tedious nature of the manual method, calculations are performed after the release has occurred and the release data sunnnarized. To facilitate the complex calculations, the number of releases and the number of various release
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e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton pathways, computerized dose calculation and dose trending are needed. Since the dose or dose commitment is the most limiting specification placed upon the effluent releases, this more desirable pre-release review and trending methodology should be implemented. Implementation of the computerized methodology will require an additional 4-6 months to develop and implement._
In addition to procedural difficulties, certain channels of the Radiological Effluent Monitoring Instrumentation could place Surry in an action mode, as specified by Table 3.7-5(a) and Table 3.7-5(b), due to current maintenance and calibration problems.
The Component Cooling Service Water Effluent Line Monitor is the originally installed equipment used to monitor gross leakage in the Component Coolant Heat Exchanger. During the past 10 years of operation, the system has experienced design problems associated with sample pump reliability. Sample pump replacement or sample line relocation may provide monitor operability but design modification may be required to provide long term reliability and increased sensitivity. Refurbishment and a re-evaluation of the system design is in process. The proposed RETS requires reporting in the Semi-annual Radioactive Effluent Report if the system is not returned to operable status within 30 days of monitor failure. Current status of the system will place Surry in this action mode.
The Waste Gas Holdup System Explosive Gas Monitors have experienced similar reliability problems. Constant recirculation through the gas monitors will be required to maintain monitor operability. The system has experienced sample recirculation problems with low tank pressure. The action mode for failure of this system places the station in a program of daily sampling of the Waste Gas Decay Tanks.
The Condenser Air Ejector System flow rate measuring device will require factory calibration. Replacement monitors, calibrated at the factory, are in the process of being purchased, to be installed in the place of devices currently installed.
In view of these problems, an implementation date of July 1, 1984, is requested. This implementation date will eliminate the need for submitting two Semi-annual Radioactive Effluent Release Reports covering the first six months of 1984. The Radioactive Effluent Release Report for the first and second quarter shall be submitted in the format specified by the current Technical Specifications and the third and fourth quarter will be submitted in the format specified by the proposed RETS. The Semi-annual Radioactive Effluent Report submitted 60 days after January 1, 1985, shall include an evaluation of the dose commitment for the entire year.
The extended date will facilitate smooth implementation of the proposed Radiological Effluent Technical Specifications and provide a sufficient period of time to eliminate the previously discussed problems.
This request has been reviewed and approved by the Surry Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.
It has been determined that this request does not pose a significant hazards
e e VJROINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton consideration as defined in 10CFR50. 92 or an unreviewed safety question as defined in 10CFR50.59.
Very truly yours,
&t~
W. L. Stewart Attachments:
- 1. Proposed Technical Specification Change
- 2. Discussion of Proposed Technical Specification Change cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. Don Neighbors NRC Project Manager - Surry Operating Reactors Branch No. 1 Division of Licensing Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219