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| {{#Wiki_filter:ACCESSION NBR FACXL:50-244 AUTH.NAME MECREDY,R,.C. | | {{#Wiki_filter:CATEGORY 1 REGULAT INFORMATION DISTRIBUTION 'YSTEM (RIDS) |
| RECIP.NAME VISSING, G.S.CATEGORY 1 REGULAT INFORMATION DISTRIBUTION
| | ACCESSION NBR :9906210069 DOC.DATE: 99/06/11 NOTARIZED: NO FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G DOCKET 05000244 I |
| 'YSTEM (RIDS):9906210069 DOC.DATE: 99/06/11 NOTARIZED: | | AUTH. NAME AUTHOR AFFXLIATION MECREDY,R,.C. Rochester Gas & Electric Corp. |
| NO Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTHOR AFFXLIATION Rochester Gas&Electric Corp.RECIPIENT AFFILIATION DOCKET I 05000244 S UBJECT: Responds to NRC RAI re licensee GL 96-05 program.Encl info verifies that util is implementing provisions of JOG program on MOV periodic verification; DISTRIBUTION CODE: A073D COPIES RECEIVED:LTR L ENCL SIZE: TITLE: GL-96-05 Periodic Verif.of Design Basis Capability of Safety-Related NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). | | RECIP.NAME RECIPIENT AFFILIATION VISSING, G. S . |
| O5OOO244 E RECIPIENT ID CODE/NAME LPD1-1 PD COPIES LTTR ENCL 1 1 RECIPIENT ID CODE/NAME VISSING,G. | | S UBJECT: Responds to NRC RAI re licensee GL 96-05 program. Encl info verifies that util is implementing provisions of JOG program on MOV periodic verification; DISTRIBUTION CODE: A073D COPIES RECEIVED:LTR L ENCL SIZE: |
| COPIES LTTR ENCL 1 1 INTERNAL: AEOD/SOD/RAB NRR/DE/EMEB RES/DET/EIB/B RES/DST/PRAB 1 1 FILE CENTER 01 1 1.NRR I A 1 1 RES/DST 1 1 1 1 1 1 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D U'E N NOTE TO ALL"RIDS" RECIPIENTS:
| | TITLE: GL-96-05 Periodic Verif. of Design Basis Capability of Safety-Related NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). O5OOO244 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL: AEOD/SOD/RAB 1 1 FILE CENTER 01 1 1 NRR/DE/EMEB 1 1 . NRR IA 1 1 RES/DET/EIB/B 1 1 RES/DST 1 1 RES/DST/PRAB 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D |
| PLEASE HELP US TO REDUCE WASTE.'TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415"2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 11 AND ROCHESTER GAS AND ELECTRIC CORPORATION | | U |
| ~89 EASTAVFNUE, ROCHESTER, N.Y 146d9-OOOI AREA CODE716 5'-27OO ROBERT C.MECREDY Vice President Nvcteor operations June 11, 1999 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555 | | 'E N |
| | NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE.'TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415"2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 11 |
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| | AND ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EASTAVFNUE, ROCHESTER, N. Y 146d9-OOOI AREA CODE716 5'-27OO ROBERT C. MECREDY Vice President June 11, 1999 Nvcteor operations U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| Response to RAI concerning GL96-05 R.E.Ginna Nuclear Power Plant Docket No.50-244 | | Response to RAI concerning GL96-05 R. E. Ginna Nuclear Power Plant Docket No. 50-244 |
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| ==Dear Mr.Vissing:== | | ==Dear Mr. Vissing:== |
| This letter is in response to a request for additional information regarding our Generic Letter 96-05 program, dated February 3, 1999.This information verifies that RGB's implementing the provisions of the Joint Owners Group (JOG)Program on MOV Periodic Verification. | | |
| This submittal was delayed from its original due date in order to incorporate testing data developed during the 1999 Refueling Outage.Very t y yours, Robert C.Mecredy Attachment xc: Mr.Guy S.Vissing (Mail Stop 8C2)Project Directorate I-1 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Regional Administrator, Region I U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 po~3 U.S.NRC Ginna Senior Resident Inspector'st'st062'i0069 | | This letter is in response to a request for additional information regarding our Generic Letter 96-05 program, dated February 3, 1999. This information verifies that RGB's implementing the provisions of the Joint Owners Group (JOG) Program on MOV Periodic Verification. This submittal was delayed from its original due date in order to incorporate testing data developed during the 1999 Refueling Outage. |
| 'st'tt06ii PDR ADGCK 05000244 j~P P,DR | | Very t y yours, Robert C. Mecredy Attachment xc: Mr. Guy S. Vissing (Mail Stop 8C2) |
| | Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I po~3 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector |
| | 'st'st062'i0069 'st'tt06ii PDR ADGCK 05000244 j~ |
| | P P,DR |
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| ==Attachment:== | | ==Attachment:== |
| | RG&E Responses to NRC Request for Additional Information regarding GL 96-05 dated 2/3/99. |
| | NRC Question 1: |
| | In NRC Inspection Report No. 50-244/98-06, the NRC staff closed its review of the motor-operated valve (MOV) program implemented at R.E. Ginna Nuclear Power Plant (Ginna) in response to Generic Letter (GL) 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance." In the inspection report, the NRC staff discussed certain aspects of the licensee's MOV program to be addressed over the long term. For example, the inspectors noted that the licensee had established plans to perform additional dynamic tests or use the Electric Power Research Institute (EPRI) Performance Prediction Model (PPM) to provide a long-term basis for the predicted thrust and torque requirements applied to selected valves in Groups B, D, and E. The licensee should provide a summary status of the actions taken to address this specific long-term aspect of the MOV program at Ginna noted in the NRC inspection report. |
| | RG&E Response 1: |
| | The long term actions to address selected valves in groups B, D and E began immediately following receipt of initial NRC comments on Motor-Operated Valve Qualification Program Plan Attachment K "Calculation Assumption Verification Criteria" Revision 0 . |
| | Initially, valve groups were created based on similar valve characteristics with the final grouping criteria being valve type, size and ANSI class. Although this was considered a feasible method, there was not enough in house data available to support this method. A reevaluation of the process was performed and it was decided that the Ginna program would group valves with identical gate or globe characteristics and similar design basis system conditions. This would help to ensure that a bounding valve factor for a given valve type was selected. The valves were regrouped, analyzed and long term actions assigned as detailed in Motor-Operated Valve Qualification Program Plan Attachment K "Calculation Assumption Verification Criteria" Revision 1. Using this methodology, group B now becomes group AD1. Group D now becomes groups C4, C5, C6, C7, V3 and R1. Group E now becomes groups V1 and V2. |
| | Group AD1 consists of seven valves 857A, 857B, 857C, 860A, 860B, 860C and 860D. |
| | The long term resolution approach was to perform D/P testing on 857C and 860A/B/C/D. |
| | Current status is as follows: |
| | 857A Sufficient D/P test data is available. In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value. |
| | |
| | 857B Sufficient D/P test data is available. This valve is currently in the JOG program. In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value. |
| | 857C Sufficient D/P test data is available. In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value. |
| | 860A,B,C,D A walk down of the valves and system determined that sufficient D/P testing data is unattainable. An EPRI PPM hand calculation has been performed and the valves are currently set to meet the EPRI PPM value. |
| | Group C4 consists of one valve, MOV 4670. Sufficient D/P test data is available, and a long term valve factor has been applied. |
| | Group CS consists of two valves, MOVs 738A and 738B. Sufficient D/P test data is available and a long term valve factor has been applied. In addition, the torque switch settings were reset last year to improve the close margin. |
| | Group C6 consists of one valve, MOV 4664. Sufficient D/P test data is available, and a long term valve factor has been applied. |
| | Group C7 consists of one valve, MOV 4615. Sufficient D/P test data is available, and a long term valve factor has been applied. |
| | Group V3 consists of two valves, MOVs 700 and 701. These valves do not meet the general requirements of GL 89-10 but are being administratively treated as such. System alignment prevents these valves from being D/P tested. A major valve inspection was completed during the 1999 spring refueling outage. The valves were found to be in excellent condition. Internal measurements were made to assist in performing an EPRI PPM calculation in the future. |
| | Group R1 consists of one valve, MOV 4616. Sufficient D/P test data is available, and a long term valve factor has been applied. |
| | Group Vl consists of two valves, MOVs 871A and 871B. Sufficient D/P test data is available, and a long term valve factor has been applied. |
| | Group V2 consists of two valves, MOVs 852A and 852B. System alignment prevents these valves Rom being D/P tested. A major valve inspection was performed during the 1999 spring refueling outage and a hole was drilled in the disk to address potential pressure locking concerns. The valves were found to be in excellent condition. Internal measurements were made to assist in performing an EPRI PPM calculation in the future. |
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| | NRC Question 2: |
| | In a letter dated November 18, 1996, the licensee stated its commitment to implement the Joint Owners Group (JOG) Program on MOV Periodic Verification in response to GL 96- |
| | : 05. The JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significance are the responsibility of each participating licensee. As Ginna is a pressurized-water reactor (PWR) nuclear plant designed by Westinghouse, is the licensee applying the Westinghouse Owners'roup (WOG) methodology for ranking MOVs based on their safety significance as described in WOG Engineering Report V-EC-1658-A (Revision 2, dated August 13, 1998), "Risk Ranking Approach for Motor-Operated Valves in Response to Generic Letter 96-05," and the NRC safety evaluation dated April 14, 1998'? Ifnot, the licensee should describe the methodology used for risk ranking MOVs at Ginna in more detail, including a description of (1) the process used to develop sample lists of high-risk MOVs Rom other Westinghouse plants; and (2) how expert panels were used to evaluate MOV risk significance. |
| | RG&E Response 2: |
| | RG8rE did use the methodology described in WOG Engineering Report V-EC-1658-A to rank MOVs based on their safety significance. A combination of PSA risk-ranking and Maintenance Rule expert panel determinations was used to compile this list. RGB's an active member of the JOG, with two valves (MOVs 857B and 9629A) designated as "JOG valves". Both valves have been tested twice, most recently during the 1999 refueling outage, and the data is being transmitted to JOG. The third and final test is scheduled for the year 2000. |
| | NRC Question 3: |
| | The JOG program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions. In the NRC safety evaluation dated October 30, 1997, on the JOG program, the NRC staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. The licensee should describe the plan at Ginna for ensuring adequate ac and dc MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1. |
| | RG&E Response 3: |
| | As previously stated, R.E. Ginna Nuclear Power Plant is dedicated to the Joint Owners Group Program on MOV Periodic Verification in response to GL 96-05. Program aspects are being integrated into the present active curriculum. In addition, steps are being taken to address Limitorque Technical Bulletin 98-01 and Supplement 1. The following table reflects our action plan and the current status of each item: |
| | |
| | Action Item Status Review JOG program for impact on present program Complete Review Limitorque Technical Bulletin 98-01 and Supplement Complete 1 for impact on program Revise MOV calculations incorporating Limitorque TB 98-01 Complete Revise margin table incorporating new calc values Complete Identify MOVs in need of a margin increase Complete A total of eight valves require a motor upgrade to improve Complete margin as a result of Limitorque TB 98-01. |
| | Two other valves require a procedure administrative Procedures have been adjustment in order to improve margin as a result of updated. Design Basis Limitorque TB 98-01 Analysis and Design Basis Thrust Calcs to be updated by December 1999. |
| | Review/Rework/Develop weak link analysis for motor Complete upgrades Review/Rework A.C. Motor-Operated Valve Degraded Complete Voltage document Update MOV database reflecting all changes Complete Obtain a specific configuration review from Limitorque for Waiting for Limitorque those SMB-1 valves with a 66:1 ratio (2 MOV's GL 89-10 Response sufficient margin exists for this concern) |
| | Incorporate all changes into the Motor-Operated Valve 95% complete Qualification Program Plan Independent review to be completed by 12/99. |
| | Update reptasks in the work control system incorporating the Complete revised test intervals Maintain an active role in the JOG Program Currently assigned as a WOG core group member for reviewing all JOG data With respect to DC actuators, there are only two in the GL 89-10 program. These two valves are stroked under pressure four times a year. In addition, differential pressure testing was completed for both valves and a long term valve factor has been applied. |
| | These valves are low risk with high margin but are inspected/tested at a more frequent interval due to their service and environment. |
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| RG&E Responses to NRC Request for Additional Information regarding GL 96-05 dated 2/3/99.NRC Question 1: In NRC Inspection Report No.50-244/98-06, the NRC staff closed its review of the motor-operated valve (MOV)program implemented at R.E.Ginna Nuclear Power Plant (Ginna)in response to Generic Letter (GL)89-10,"Safety-Related Motor-Operated Valve Testing and Surveillance." In the inspection report, the NRC staff discussed certain aspects of the licensee's MOV program to be addressed over the long term.For example, the inspectors noted that the licensee had established plans to perform additional dynamic tests or use the Electric Power Research Institute (EPRI)Performance Prediction Model (PPM)to provide a long-term basis for the predicted thrust and torque requirements applied to selected valves in Groups B, D, and E.The licensee should provide a summary status of the actions taken to address this specific long-term aspect of the MOV program at Ginna noted in the NRC inspection report.RG&E Response 1: The long term actions to address selected valves in groups B, D and E began immediately following receipt of initial NRC comments on Motor-Operated Valve Qualification Program Plan Attachment K"Calculation Assumption Verification Criteria" Revision 0.Initially, valve groups were created based on similar valve characteristics with the final grouping criteria being valve type, size and ANSI class.Although this was considered a feasible method, there was not enough in house data available to support this method.A reevaluation of the process was performed and it was decided that the Ginna program would group valves with identical gate or globe characteristics and similar design basis system conditions.
| | ~ ~ *}} |
| This would help to ensure that a bounding valve factor for a given valve type was selected.The valves were regrouped, analyzed and long term actions assigned as detailed in Motor-Operated Valve Qualification Program Plan Attachment K"Calculation Assumption Verification Criteria" Revision 1.Using this methodology, group B now becomes group AD1.Group D now becomes groups C4, C5, C6, C7, V3 and R1.Group E now becomes groups V1 and V2.Group AD1 consists of seven valves 857A, 857B, 857C, 860A, 860B, 860C and 860D.The long term resolution approach was to perform D/P testing on 857C and 860A/B/C/D.
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| Current status is as follows: 857A Sufficient D/P test data is available.
| |
| In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value.
| |
| 857B Sufficient D/P test data is available.
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| This valve is currently in the JOG program.In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value.857C Sufficient D/P test data is available.
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| In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value.860A,B,C,D A walk down of the valves and system determined that sufficient D/P testing data is unattainable.
| |
| An EPRI PPM hand calculation has been performed and the valves are currently set to meet the EPRI PPM value.Group C4 consists of one valve, MOV 4670.Sufficient D/P test data is available, and a long term valve factor has been applied.Group CS consists of two valves, MOVs 738A and 738B.Sufficient D/P test data is available and a long term valve factor has been applied.In addition, the torque switch settings were reset last year to improve the close margin.Group C6 consists of one valve, MOV 4664.Sufficient D/P test data is available, and a long term valve factor has been applied.Group C7 consists of one valve, MOV 4615.Sufficient D/P test data is available, and a long term valve factor has been applied.Group V3 consists of two valves, MOVs 700 and 701.These valves do not meet the general requirements of GL 89-10 but are being administratively treated as such.System alignment prevents these valves from being D/P tested.A major valve inspection was completed during the 1999 spring refueling outage.The valves were found to be in excellent condition.
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| Internal measurements were made to assist in performing an EPRI PPM calculation in the future.Group R1 consists of one valve, MOV 4616.Sufficient D/P test data is available, and a long term valve factor has been applied.Group Vl consists of two valves, MOVs 871A and 871B.Sufficient D/P test data is available, and a long term valve factor has been applied.Group V2 consists of two valves, MOVs 852A and 852B.System alignment prevents these valves Rom being D/P tested.A major valve inspection was performed during the 1999 spring refueling outage and a hole was drilled in the disk to address potential pressure locking concerns.The valves were found to be in excellent condition.
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| Internal measurements were made to assist in performing an EPRI PPM calculation in the future.
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| NRC Question 2: In a letter dated November 18, 1996, the licensee stated its commitment to implement the Joint Owners Group (JOG)Program on MOV Periodic Verification in response to GL 96-05.The JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significance are the responsibility of each participating licensee.As Ginna is a pressurized-water reactor (PWR)nuclear plant designed by Westinghouse, is the licensee applying the Westinghouse Owners'roup (WOG)methodology for ranking MOVs based on their safety significance as described in WOG Engineering Report V-EC-1658-A (Revision 2, dated August 13, 1998),"Risk Ranking Approach for Motor-Operated Valves in Response to Generic Letter 96-05," and the NRC safety evaluation dated April 14, 1998'?If not, the licensee should describe the methodology used for risk ranking MOVs at Ginna in more detail, including a description of (1)the process used to develop sample lists of high-risk MOVs Rom other Westinghouse plants;and (2)how expert panels were used to evaluate MOV risk significance.
| |
| RG&E Response 2: RG8rE did use the methodology described in WOG Engineering Report V-EC-1658-A to rank MOVs based on their safety significance.
| |
| A combination of PSA risk-ranking and Maintenance Rule expert panel determinations was used to compile this list.RGB's an active member of the JOG, with two valves (MOVs 857B and 9629A)designated as"JOG valves".Both valves have been tested twice, most recently during the 1999 refueling outage, and the data is being transmitted to JOG.The third and final test is scheduled for the year 2000.NRC Question 3: The JOG program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions.
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| In the NRC safety evaluation dated October 30, 1997, on the JOG program, the NRC staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation.
| |
| The licensee should describe the plan at Ginna for ensuring adequate ac and dc MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1.RG&E Response 3: As previously stated, R.E.Ginna Nuclear Power Plant is dedicated to the Joint Owners Group Program on MOV Periodic Verification in response to GL 96-05.Program aspects are being integrated into the present active curriculum.
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| In addition, steps are being taken to address Limitorque Technical Bulletin 98-01 and Supplement 1.The following table reflects our action plan and the current status of each item:
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| Action Item Review JOG program for impact on present program Status Complete Review Limitorque Technical Bulletin 98-01 and Supplement 1 for impact on program Revise MOV calculations incorporating Limitorque TB 98-01 Complete Complete Revise margin table incorporating new calc values Complete Identify MOVs in need of a margin increase A total of eight valves require a motor upgrade to improve margin as a result of Limitorque TB 98-01.Two other valves require a procedure administrative adjustment in order to improve margin as a result of Limitorque TB 98-01 Review/Rework/Develop weak link analysis for motor upgrades Review/Rework A.C.Motor-Operated Valve Degraded Voltage document Update MOV database reflecting all changes Complete Complete Procedures have been updated.Design Basis Analysis and Design Basis Thrust Calcs to be updated by December 1999.Complete Complete Complete Obtain a specific configuration review from Limitorque for those SMB-1 valves with a 66:1 ratio (2 MOV's GL 89-10 sufficient margin exists for this concern)Incorporate all changes into the Motor-Operated Valve Qualification Program Plan Update reptasks in the work control system incorporating the revised test intervals Maintain an active role in the JOG Program Waiting for Limitorque Response 95%complete-Independent review to be completed by 12/99.Complete Currently assigned as a WOG core group member for reviewing all JOG data With respect to DC actuators, there are only two in the GL 89-10 program.These two valves are stroked under pressure four times a year.In addition, differential pressure testing was completed for both valves and a long term valve factor has been applied.These valves are low risk with high margin but are inspected/tested at a more frequent interval due to their service and environment.
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Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
[Table view] |
Text
CATEGORY 1 REGULAT INFORMATION DISTRIBUTION 'YSTEM (RIDS)
ACCESSION NBR :9906210069 DOC.DATE: 99/06/11 NOTARIZED: NO FACXL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G DOCKET 05000244 I
AUTH. NAME AUTHOR AFFXLIATION MECREDY,R,.C. Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING, G. S .
S UBJECT: Responds to NRC RAI re licensee GL 96-05 program. Encl info verifies that util is implementing provisions of JOG program on MOV periodic verification; DISTRIBUTION CODE: A073D COPIES RECEIVED:LTR L ENCL SIZE:
TITLE: GL-96-05 Periodic Verif. of Design Basis Capability of Safety-Related NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). O5OOO244 E RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LPD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL: AEOD/SOD/RAB 1 1 FILE CENTER 01 1 1 NRR/DE/EMEB 1 1 . NRR IA 1 1 RES/DET/EIB/B 1 1 RES/DST 1 1 RES/DST/PRAB 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D
U
'E N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.'TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415"2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 11
AND ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EASTAVFNUE, ROCHESTER, N. Y 146d9-OOOI AREA CODE716 5'-27OO ROBERT C. MECREDY Vice President June 11, 1999 Nvcteor operations U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
Response to RAI concerning GL96-05 R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing:
This letter is in response to a request for additional information regarding our Generic Letter 96-05 program, dated February 3, 1999. This information verifies that RGB's implementing the provisions of the Joint Owners Group (JOG) Program on MOV Periodic Verification. This submittal was delayed from its original due date in order to incorporate testing data developed during the 1999 Refueling Outage.
Very t y yours, Robert C. Mecredy Attachment xc: Mr. Guy S. Vissing (Mail Stop 8C2)
Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I po~3 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector
'st'st062'i0069 'st'tt06ii PDR ADGCK 05000244 j~
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Attachment:
RG&E Responses to NRC Request for Additional Information regarding GL 96-05 dated 2/3/99.
NRC Question 1:
In NRC Inspection Report No. 50-244/98-06, the NRC staff closed its review of the motor-operated valve (MOV) program implemented at R.E. Ginna Nuclear Power Plant (Ginna) in response to Generic Letter (GL) 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance." In the inspection report, the NRC staff discussed certain aspects of the licensee's MOV program to be addressed over the long term. For example, the inspectors noted that the licensee had established plans to perform additional dynamic tests or use the Electric Power Research Institute (EPRI) Performance Prediction Model (PPM) to provide a long-term basis for the predicted thrust and torque requirements applied to selected valves in Groups B, D, and E. The licensee should provide a summary status of the actions taken to address this specific long-term aspect of the MOV program at Ginna noted in the NRC inspection report.
RG&E Response 1:
The long term actions to address selected valves in groups B, D and E began immediately following receipt of initial NRC comments on Motor-Operated Valve Qualification Program Plan Attachment K "Calculation Assumption Verification Criteria" Revision 0 .
Initially, valve groups were created based on similar valve characteristics with the final grouping criteria being valve type, size and ANSI class. Although this was considered a feasible method, there was not enough in house data available to support this method. A reevaluation of the process was performed and it was decided that the Ginna program would group valves with identical gate or globe characteristics and similar design basis system conditions. This would help to ensure that a bounding valve factor for a given valve type was selected. The valves were regrouped, analyzed and long term actions assigned as detailed in Motor-Operated Valve Qualification Program Plan Attachment K "Calculation Assumption Verification Criteria" Revision 1. Using this methodology, group B now becomes group AD1. Group D now becomes groups C4, C5, C6, C7, V3 and R1. Group E now becomes groups V1 and V2.
Group AD1 consists of seven valves 857A, 857B, 857C, 860A, 860B, 860C and 860D.
The long term resolution approach was to perform D/P testing on 857C and 860A/B/C/D.
Current status is as follows:
857A Sufficient D/P test data is available. In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value.
857B Sufficient D/P test data is available. This valve is currently in the JOG program. In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value.
857C Sufficient D/P test data is available. In addition, an EPRI PPM hand calculation has been performed and the valve is currently set to meet the EPRI PPM value.
860A,B,C,D A walk down of the valves and system determined that sufficient D/P testing data is unattainable. An EPRI PPM hand calculation has been performed and the valves are currently set to meet the EPRI PPM value.
Group C4 consists of one valve, MOV 4670. Sufficient D/P test data is available, and a long term valve factor has been applied.
Group CS consists of two valves, MOVs 738A and 738B. Sufficient D/P test data is available and a long term valve factor has been applied. In addition, the torque switch settings were reset last year to improve the close margin.
Group C6 consists of one valve, MOV 4664. Sufficient D/P test data is available, and a long term valve factor has been applied.
Group C7 consists of one valve, MOV 4615. Sufficient D/P test data is available, and a long term valve factor has been applied.
Group V3 consists of two valves, MOVs 700 and 701. These valves do not meet the general requirements of GL 89-10 but are being administratively treated as such. System alignment prevents these valves from being D/P tested. A major valve inspection was completed during the 1999 spring refueling outage. The valves were found to be in excellent condition. Internal measurements were made to assist in performing an EPRI PPM calculation in the future.
Group R1 consists of one valve, MOV 4616. Sufficient D/P test data is available, and a long term valve factor has been applied.
Group Vl consists of two valves, MOVs 871A and 871B. Sufficient D/P test data is available, and a long term valve factor has been applied.
Group V2 consists of two valves, MOVs 852A and 852B. System alignment prevents these valves Rom being D/P tested. A major valve inspection was performed during the 1999 spring refueling outage and a hole was drilled in the disk to address potential pressure locking concerns. The valves were found to be in excellent condition. Internal measurements were made to assist in performing an EPRI PPM calculation in the future.
NRC Question 2:
In a letter dated November 18, 1996, the licensee stated its commitment to implement the Joint Owners Group (JOG) Program on MOV Periodic Verification in response to GL 96-
- 05. The JOG program specifies that the methodology and discrimination criteria for ranking MOVs according to their safety significance are the responsibility of each participating licensee. As Ginna is a pressurized-water reactor (PWR) nuclear plant designed by Westinghouse, is the licensee applying the Westinghouse Owners'roup (WOG) methodology for ranking MOVs based on their safety significance as described in WOG Engineering Report V-EC-1658-A (Revision 2, dated August 13, 1998), "Risk Ranking Approach for Motor-Operated Valves in Response to Generic Letter 96-05," and the NRC safety evaluation dated April 14, 1998'? Ifnot, the licensee should describe the methodology used for risk ranking MOVs at Ginna in more detail, including a description of (1) the process used to develop sample lists of high-risk MOVs Rom other Westinghouse plants; and (2) how expert panels were used to evaluate MOV risk significance.
RG&E Response 2:
RG8rE did use the methodology described in WOG Engineering Report V-EC-1658-A to rank MOVs based on their safety significance. A combination of PSA risk-ranking and Maintenance Rule expert panel determinations was used to compile this list. RGB's an active member of the JOG, with two valves (MOVs 857B and 9629A) designated as "JOG valves". Both valves have been tested twice, most recently during the 1999 refueling outage, and the data is being transmitted to JOG. The third and final test is scheduled for the year 2000.
NRC Question 3:
The JOG program focuses on the potential age-related increase in the thrust or torque required to operate valves under their design-basis conditions. In the NRC safety evaluation dated October 30, 1997, on the JOG program, the NRC staff specified that licensees are responsible for addressing the thrust or torque delivered by the MOV motor actuator and its potential degradation. The licensee should describe the plan at Ginna for ensuring adequate ac and dc MOV motor actuator output capability, including consideration of recent guidance in Limitorque Technical Update 98-01 and its Supplement 1.
RG&E Response 3:
As previously stated, R.E. Ginna Nuclear Power Plant is dedicated to the Joint Owners Group Program on MOV Periodic Verification in response to GL 96-05. Program aspects are being integrated into the present active curriculum. In addition, steps are being taken to address Limitorque Technical Bulletin 98-01 and Supplement 1. The following table reflects our action plan and the current status of each item:
Action Item Status Review JOG program for impact on present program Complete Review Limitorque Technical Bulletin 98-01 and Supplement Complete 1 for impact on program Revise MOV calculations incorporating Limitorque TB 98-01 Complete Revise margin table incorporating new calc values Complete Identify MOVs in need of a margin increase Complete A total of eight valves require a motor upgrade to improve Complete margin as a result of Limitorque TB 98-01.
Two other valves require a procedure administrative Procedures have been adjustment in order to improve margin as a result of updated. Design Basis Limitorque TB 98-01 Analysis and Design Basis Thrust Calcs to be updated by December 1999.
Review/Rework/Develop weak link analysis for motor Complete upgrades Review/Rework A.C. Motor-Operated Valve Degraded Complete Voltage document Update MOV database reflecting all changes Complete Obtain a specific configuration review from Limitorque for Waiting for Limitorque those SMB-1 valves with a 66:1 ratio (2 MOV's GL 89-10 Response sufficient margin exists for this concern)
Incorporate all changes into the Motor-Operated Valve 95% complete Qualification Program Plan Independent review to be completed by 12/99.
Update reptasks in the work control system incorporating the Complete revised test intervals Maintain an active role in the JOG Program Currently assigned as a WOG core group member for reviewing all JOG data With respect to DC actuators, there are only two in the GL 89-10 program. These two valves are stroked under pressure four times a year. In addition, differential pressure testing was completed for both valves and a long term valve factor has been applied.
These valves are low risk with high margin but are inspected/tested at a more frequent interval due to their service and environment.
~ ~ *