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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20212J9101999-10-0101 October 1999 Forwards SE Accepting Licensee 990916 & 27 Relief Requests IWE-3 for Plant.Se Addresses Only IWE-3 Due to Util Urgent Need for Relief.Requests IWE-7 & IWE-8 Will Be Addressed at Later Date ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 ML20211N2531999-09-0808 September 1999 Responds to Request to Exceed 60,000 Mwd/Mtu Lead Rod Burnup in Small Number of Fuel Rods in North Anna Unit 2.Informs That NRC Offers No Objection to Requested Use of Rods in Reconstituted Fuel Assembly.Se Supporting Request Encl ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211J2211999-08-31031 August 1999 Approves Request to Remove Augmented ISI (Aii) Program for RCS Bypass Lines from North Anna Licensing Basis.Se Re Request to Apply LBB to Eliminate Augmented Insp Program on RCS Bypass Lines Encl ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML20211B3871999-08-17017 August 1999 Requests Permission to Routinely Discharge from SW Reservior to Waste Heat Treatment Facility Under Existing Vpdes Permit Through Outfalls 108 & 103.Discharges Are Scheduled to Commence on 990907,due to High Priority Placed on Project ML20210T0671999-08-13013 August 1999 Informs of Completion of Review of Proposed Revs of Schedule for Withdrawal of Rv Surveillance Capsules Submitted by VEPCO on 981217.Approves Proposed Revs.Forwards Safety Evaluation ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210N2921999-08-0505 August 1999 Discusses Which Submitted Proposed TSs Bases Change for Containment Leakage. Licensee Changes to Bases May Be Subj to Future Insps or Audits ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML20217K4391999-10-18018 October 1999 Provides Response to RAI to Support USI A-46 Program Submittal for North Anna Power Station,Units 1 & 2.Rev 10 to BNL Rept 52361,encl ML20217H3301999-10-14014 October 1999 Forwards Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su. No New Commitments Intended by Ltr ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML20216K1681999-10-0101 October 1999 Forwards Vols I-VIII of Rev 35 to UFSAR for Naps.Rev Also Includes Update to Chapter 17 of Ufsar,Which Contains Operational QA Program.Changes to Program Description Do Not Reduce Commitments Contained Therein ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216E6661999-09-10010 September 1999 Forwards Analysis of Capsule W Virginia Power North Anna Unit 1 Nuclear Power Plant Reactor Vessel Matl Surveillance Program, for Capsule Withdrawn on 980922 ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML20211L9151999-09-0101 September 1999 Forwards Response to NRC Request for Comments Re Closure of Review of Response to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211H4131999-08-27027 August 1999 Informs That Util Revised Encl Bases for TS 2.2.1, Reactor Trip Sys Instrumentation Setpoints, Discussing Steam Flow/ Feed Flow Mismatch Portion of Steam Flow/Feed Flow Mismatch & Low SG Water Level Reactor Trip Setpoint ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML20138B3241999-08-23023 August 1999 Forwards Draft Response to Question 1 Re NAPS USI A-46 ML20211D9041999-08-20020 August 1999 Forwards Revised Pages to Third Ten Year ISI Program & Relief Requests, Replacing Pages in 990408 Submittal ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q9841999-08-12012 August 1999 Forwards Rev 1 to Vepc COLR for North Anna Unit 2,Cycle 13 Pattern Ud, Per TS 6.9.1.7.d.COLR Was Revised to Include Temp Coastdown Operation at End of Cycle 13 ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML20210J8861999-08-0202 August 1999 Provides Clarification to Commitment Made in Identifying Extent by Which Existing Plant Design Complied with RG 1.97,specifically Re Variable, Radiation Exposure Rate ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML20210F6121999-07-28028 July 1999 Forwards Supplemental Info on Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit,Documenting Info Provided During 990624 Meeting & Suppl Original Submittal ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20209E7621999-07-0909 July 1999 Provides Addl Info to Justify Use of Less than One Gpm Detectable Leakage Rate to Establish Required Margin for Crack Stability in LBB Analysis,Per 980623 Application on Reactor Coolant Loop Bypass Lines ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML20196F1151999-06-22022 June 1999 Forwards Relief Requests NDE-047 & NDE-048 for North Anna Power Station,Unit 1 Re ASME Section XI ISI Program ML20212J2951999-06-22022 June 1999 Forwards Corrected Markup & Typed Version of Affected Pages. Requests That Attached Pages for Those Previously Provided in 990506 Submittal Be Replaced & Incorporated Into NRC Review of Proposed TS ML20195J7011999-06-15015 June 1999 Forwards Revised EPIP 2.01 Which Corrects Typo That Was Found in Step 10 of Procedure.Rev Does Not Implement Actions That Decrease Effectiveness of EP ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 1999-09-08
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 17, 1999 U.S. Nuclear Regulatory Commission Serial No. 99-002A Attention: Document Control Desk NL&P/MAE: R1" Washington, D.C. 20555-0001 Docket Nos. 50-280/-281 50-338/-339 License Nos. DPR-32/-37 NPF-4/-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 GENERIC LETTER 96-05, PERIODIC VERIFICATION OF DESIGN-BASIS CAPABILITY OF SAFETY-RELATED MOTOR-OPERATED VALVES (MOVs)
On September 18, 1996, the NRC issued Generic Letter (GL) 96-05, entitled "Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves." The generic letter required a 60 day response and a 180 day response. Virginia Electric and Power Company's (Virginia Power's) 60 day response was documented in a letter dated November 13, 1996 (Serial No.96-504). The 180 day response required utilities to provide a written summary description of its MOV periodic verification program established in accordance with the requested actions. Virginia Power's 180 day response was documented in a letter dated March 12, 1997 (Serial No. 96-504A).
Virginia Power notified the NRC on May 26, 1999 (Serial No.99-002) that our MOV periodic verification program as described in our 180 day response would be revised to conform with the Joint Owners' Group (JOG) Program on MOV periodic verification.
Attached is our revised 180 day response to GL 96-05. This response supercedes the previously submitted March 12, 1997 response in its entirety.
If you have any questions, please contact us.
Very truly yours, David A. Christian Vice President - Nuclear Operations Attachment
~---- - _;."> _,,t .: __ , _***'. :\.~., - \,
, - -- 9909240220 990917 PDR ADOCK 05000280 p PDR
.CommitrT1ents rnade by this letter:
- 1. None.
cc: Regional Administrator U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23 T85 Atlanta, Georgia 30303-3415 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station Mr. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station
COMMONWEALTH OF VIRGINIA )
)
COUNTY OF HENRICO )
The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by David A. Christian, who is Vice President - Nuclear Operations, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this J ~1/J day of bplentru , 19 qq.
My Commission Expires: 3/!JJ / fl(J{i) otary Public (SEAL)
VIRGINIA POWER MOV PERIODIC VERIFICATION PROGRAM I. Purpose Establish the requirements for implementing the motor operated valve (MOV) periodic verification program for Virginia Power at Surry and North Anna Power Stations. The periodic verification program consists of dynamic diagnostic testing, static diagnostic testing, and preventive maintenance.
II. Scope The Virginia Power. MOV Periodic Verification Program addresses MOVs that were included in the scope of Generic Letter 89-10. The program is being enhanced to address possible MOV changes in performance resulting from degradation as discussed in GL 96-05. This program has been revised to conform, as applicable, to the Joint Owners' Group (JOG) program on MOV periodic verification.
Virginia Power. will implement the Joint Owners' Group Program on Periodic Verification of Motor-Operated Valves in accordance with JOG Topical Report MPR-1807, Revision 2, titled "Joint BWR, Westinghouse and Combustion Engineering Owners' Group Program on Motor-Operated Valve (MOV) Periodic Verification."
The JOG program consists of three elements:
A. JOG Dynamic Test Program
- 1. Participating utilities in the JOG program dynamically test a small population of MOVs and share the results with other program participants.
- 2. Virginia Power will diagnostically test four valves per nuclear station under differential pressure conditions as described in the JOG program as a participant of the five-year JOG Dynamic Test Program.
B. JOG Interim Periodic Test Program
- 1. Static diagnostic testing frequency is based upon MOV margin and risk ranking.
Page 1 of 6
l C. JOG Long -Term Periodic Test Program
- 1. The Long-Term Periodic Test Program involves evaluation of the data from the JOG Dynamic Test Program. The industry test data will be analyzed and distributed by the JOG at the conclusion of the current five-year test program. (Scheduled for completion in mid-2002.)
- 2. The results of the test data will be given in a final report that specifies the final periodic verification criteria and associated justification.
111. Structure of Program The Virginia Power MOV Periodic Verification Program is comprised of three areas of focus.
A. Dynamic MOV Diagnostic Testing The purpose of dynamic diagnostic testing for periodic verification is to identity age-related degradations in the valve assembly that may lead to an increase in the actuator thrust or torque requirements. Dynamic diagnostic testing will be performed on various MOVs within the scope of this program.
- 1. Virginia Power will diagnostically test specific MOVs under differential pressure conditions as a participant of the JOG Dynamic Test Program.
- 2. Other program MOVs may be diagnostically tested in a dynamic system situation based on the following factors:
a) Utility experience b) Industry experience c) Joint Owners' Group Feedback Notices d) Susceptibility to age-related degradation e) Low design margin f) Ability to be tested (1) Ability to conduct a test that approaches design basis conditions and is repeatable.
(2) Ability to monitor necessary MOV parameters such as thrust and torque.
(3) Ability to monitor system conditions such as pressure, flow, differential pressure, and system temperature.
Page 2 of 6
(4) Periormance of the test does not place the plant at risk.
- 3. Regulatory approved analytical techniques in combination with static test data may be applied to exclude program MOVs from dynamic diagnostic testing. *
- 4. Sufficient information should be obtained during the course of the JOG Dynamic Test Program to identify immediate safety concerns from potential age-related degradation that applies to all MOVs.
Therefore, the need for dynamic diagnostic testing of valves outside the scope of the JOG Dynamic Test Program will be addressed at the completion of the JOG Dynamic Test Program when adequate statistical data is gathered from the industry.
- 5. Upon completion of the JOG Dynamic Test Program and subsequent final report, Virginia Power will incorporate the JOG final periodic verification criteria into the Virginia Power MOV Program, as applicable, and determine the necessity for further diagnostic differential pressure testing.
- 6. MOVs selected for dynamic diagnostic testing will be scheduled through the use of the preventive maintenance program.
- 7. Diagnostic test evaluations will be documented in a test report.
B. Static MOV Diagnostic Testing The purpose of static diagnostic testing is to detect. age-related degradations in motor, actuator, and stem factor. These degradations may be manifested in a decrease in motive force delivered to the valve.
Static diagnostic testing will be periormed on MOVs within the scope of this program.
Virginia Power will maintain the current method of static diagnostic testing until the JOG Interim Periodic Test Program is implemented.
- 1. The JOG Interim Periodic Test Program revises testing frequency based upon design margin and risk ranking.
a) The safety significance of each MOV will be evaluated using probabilistic safety assessment (PSA) models. The MOVs will be categorized as having high, - medium, or low risk significance.
b) To assist in accurate risk ranking, the MOVs within the scope of GL 96-05 will be reviewed for operating or Page 3 of 6
environmental conditions that could induce age-related degradation (e.g., valves normally stroked under significant differential pressure, valves in raw water systems).
c) An expert panel will review the MOV risk ranking and may adjust it based upon their evaluation. The Station Nuclear Safety and Operating Committee will review the results as appropriate.
d) To implement the JOG Interim Periodic Test Program, Virginia Power will utilize the Westinghouse Owners Group (WOG) risk ranking methodology in accordance with engineering report V-EC-1658, Revision 2, titled "Risk Ranking Approach for Motor-Operated Valves in Response to Generic Letter 96-05."
e) The implementation and application of the WOG risk ranking methodology tb all GL 96-05 program valves allows the maximum period of time between static diagnostic tests to be ten years.
- 2. MOVs within the scope of the GL 96-05 program will have periodic static testing scheduled through the use of the preventive maintenance program.
- 3. Diagnostic test evaluations will be documented in a test report.
C. Preventive Maintenance The purpose* of preventive maintenance is to both identify and prevent age and environmentally initiated degradations. Preventive maintenance will be performed on MOVs within the scope of this program.
- 1. A preventive maintenance program is established for MOVs in accordance with the appropriate administrative procedure.
- 2. Val.ve actuator stem factor degradation will be minimized through performance of frequent valve stem lubrication preventive maintenance evolutions.
- 3. Preventive maintenance evaluations will consider the following items:
a) Manufacturer's recommendations b) Engineering analysis c) Equipment operating history d) Industry findings and recommendations Page 4 of 6
e) Lessons learned and station experience f) Conditions of operation (system and environmental)
- 4. MOVs within the scope of the GL 96-05 program will have preventive maintenance tasks scheduled through the use of the preventive maintenance program.
IV. Frequencies A. Preventive Maintenance frequencies are governed by the appropriate administrative procedure.
B. Until the JOG Interim Periodic Test Program for static diagnostic testing is implemented, the current static diagnostic test frequency of three refueling outages or five years, which ever is longer, will be applied. A +/- 25%
grace period for frequency adjustment will be used for test scheduling purposes.
C. Upon implementation of the JOG Interim Periodic Test Program for static testing, the static diagnostic test frequency will be in accordance with the periodic verification test criteria for MOVs (categorized in three levels of safety significance) as described in the JOG Topical Report MPR-1807. A
+/- 25% grace period for frequency adjustment will be used for test scheduling purposes. The maximum interval between static diagnostic tests, including the grace period, will not exceed 10 years.
D. Dynamic diagnostic testing for the valves selected under the JOG Dynamic Test Program will be conducted for three consecutive periods (each period will be a minimum of one year); however, the dynamic diagnostic testing will not extend beyond the JOG Dynamic Test Program.
E. Test frequencies for static and dynamic diagnostic testing may be modified in accordance with the JOG Program based upon the following conditions:
- 1. Plant specific maintenance data
- 2. Plant specific test data
- 3. Manufacturer's recommendations
- 4. Industry-information
- 5. PSA reviews
- 6. Regulatory requirements
- 7. Maintenance Rule information
- 8. Advances in testing and evaluation methods
- 9. Joint Owners' Group Feedback Notices
- 10. Changes in design margin Page 5 of 6
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- e F. Changes in testing and preventive maintenance frequencies and methods
,* wiil be formally evaluated and documented in accordance with the appropriate administrative procedures.
V. Design Margin Margin is the difference between available thrust (or torque) capability of the actuator and the thrust (or torque) required by the valve under design basis conditions.
Design margin will be calculated as described in the JOG Topical Report MPR-1807, Revision 2.
VI. Post Maintenance Testing Post maintenance testing will be controlled through the use of the appropriate administrative procedure to ensure that the MOV continues to be capable of performing its design functions following maintenance.
VI I. Acceptance Criteria Acceptance criteria will be delineated in the appropriate procedures and will ensure that the MOV is capable of performing its design basis functions.
VIII. Corrective Action A. Corrective action will be initiated for any MOV for which test analysis shows it may not have sufficient margin to ensure operability at the time of the next scheduled test. This corrective action can include rescheduling of a diagnostic test that would monitor the MOV's condition at a time to ensure continued operability.
B. Conditions which would cause an MOV to become inoperable before the next scheduled test will be evaluated to assess the impact on related MOVs in the same group.
C. If any differential pressure testing evaluation shows a negative margin trend, or an MOV appears to require more margin than was previously estimated, then the design margin value will be reviewed. Appropriate corrective action will be taken to ensure valve operability until the next scheduled review interval. Margin assessments for other similarly grouped MOVs will also be performed.
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