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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217K4391999-10-18018 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 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 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 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 ML20212G5091999-09-22022 September 1999 Forwards in Triplicate,Applications for Renewal of Licenses for Listed Individuals.Encls Withheld,Per 10CFR2.790(a)(6) 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 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. 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 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 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 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 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 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 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. 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 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 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 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 05000338/LER-1999-005, Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl1999-07-0808 July 1999 Forwards LER 99-005-00,IAW 10CFR50.73.Commitment Made by Util Encl ML20209E3711999-07-0202 July 1999 Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations 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 ML20196G2581999-06-23023 June 1999 Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity 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 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 ML20196G2211999-06-21021 June 1999 Forwards Licensee Sampling & Testing Obligations Re Vpdes Permit VA0052451 Reissuance Application.Details of Requests for Sampling & Testing Waivers,Included 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 ML20195J1391999-06-11011 June 1999 Submits Addl Info as Addendum to Original Application Which Proposed Use of Three Chemicals in Bearing Cooling Tower at North Anna Power Station,Per Reissuance of Vpdes Permit 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 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program ML20207C9851999-05-28028 May 1999 Requests Regrading of Rt Robinson 990408 Written Exam,Based on Listed Reasons.Answer C for Question 18 Is Requested to Be Reconsidered as Correct or Question Be Deleted ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML20206U7441999-05-20020 May 1999 Informs That NRC Unable to Conclude That NAPS Has Met Intent of Supplement 4 to GL 88-20.RAI Re Fire Area of IPEEE Encl. Response Requested within 90 Days of Submittal Date ML20207A8541999-05-20020 May 1999 Forwards RAI Re Licensee Listed Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 90 Days of Submittal Date ML20195B5381999-05-14014 May 1999 Forwards Rev 8,Change 2 to North Anna Units 1 & 2 IST Programs for Pumps & Valves. Summaries of Program Changes Provided for Each Unit IST Program.Relief Requests Have Been Removed from IST Programs ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML20206L4661999-05-10010 May 1999 Forwards SE Accepting Request to Delay Submitting Plant, Unit 1 Class Piping ISI Program for Third Insp Interval Until 010430,to Permit Development of Risk Informed ISI Program for Class 1 Piping 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212J9101999-10-0101 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 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 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 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 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 ML20209E3711999-07-0202 July 1999 Forwards Insp Repts 50-338/99-03 & 50-339/99-03 on 990425-0605.Violations Being Treated as Noncited Violations ML20196G2581999-06-23023 June 1999 Discusses Closure of GL 92-01,rev 1,suppl 1,reactor Vessel Structural Integrity ML20206U7441999-05-20020 May 1999 Informs That NRC Unable to Conclude That NAPS Has Met Intent of Supplement 4 to GL 88-20.RAI Re Fire Area of IPEEE Encl. Response Requested within 90 Days of Submittal Date ML20207A8541999-05-20020 May 1999 Forwards RAI Re Licensee Listed Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 90 Days of Submittal Date ML20206L4661999-05-10010 May 1999 Forwards SE Accepting Request to Delay Submitting Plant, Unit 1 Class Piping ISI Program for Third Insp Interval Until 010430,to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206P6401999-05-0505 May 1999 Refers to Public Meeting Conducted at North Anna Power Station on 990413 to Discuss Results of North Anna Plant Performance Review.List of Attendees Encl ML20205S0321999-04-21021 April 1999 Forwards SER Accepting Util 980804 Requests for Relief from Certain Requirements of Subsections IWE & Iwl of 1992 Addenda of ASME Section Xi.Alternatives for IWE2,IWE4,IWE6 & IWL2,authorized Pursuant to 10CFR50.55a(a)(3)(ii) ML20205Q2451999-04-12012 April 1999 Forwards Insp Repts 50-338/99-01 & 50-339/99-01 on 990131- 0313.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20205T1411999-04-0909 April 1999 Informs That on 990407,A Royal & Ho Christensen Confirmed Initial Operator Licensing Exam Scheduled for Y2K.Initial Exam Dates Scheduled for Wks of 000925 & 1002 for Approx 11 Candidates ML20196K9891999-03-29029 March 1999 Confirms Plans to Hold Meeting on 990413 at North Anna Nuclear Information Center to Discuss North Anna Plant Performance Review ML20205B5641999-03-24024 March 1999 Forwards Audit Rept of North Anna Power Station,Units 1 & 2 Conducted on 990126-28 in Glen Allen,Va.Audit Team Assessment of Y2K Project Plan Identified Plan as well-structured,well Organized & Well Implemented ML20196L0021999-03-24024 March 1999 Discusses Plant Performance Review of North Anna Power Station Completed by NRC on 990205.Found Overall Performance at North Anna to Be Acceptable.Several Examples of Inadequate or Untimely Problem Resolution Were Noted ML20207E1331999-03-0101 March 1999 Forwards Insp Repts 50-338/98-11 & 50-339/98-11 on 981220- 990130.No Violations Noted.Util Conduct of Activities at North Anna Power Station Generally Characterized by Safety Conscious Plant Operations & Good Maintenance ML20203F8681999-02-16016 February 1999 Forwards Request for Addl Info Re Util 970527 plant-specific Summary Rept in Response to USI A-46 Program at North Anna Power Station,Units 1 & 2 ML20196K3681999-01-21021 January 1999 Discusses Closure of Tasks Re Generic Implication of part- Length Control Rod Drive Mechanism Housing Leak at Prairie Island,Unit 2 & Anna Power Station,Units 1 & 2 ML20199K3221999-01-14014 January 1999 Forwards Insp Repts 50-338/98-10 & 50-339/98-10 on 981108- 1219.No Violations Identified.Conduct of Activities at North Anna Power Station Generally Characterized by safety-conscious Plant Operations ML20198S3921999-01-0606 January 1999 Forwards Request for Addl Info on Resolution of USI A-46 for North Anna Power Station,Units 1 & 2 IR 05000338/19980051999-01-0606 January 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-338/98-05 & 50-339/98-05 on 981105 ML20198H8951998-12-22022 December 1998 Forwards Corrected Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval & Se.Authorization Ltr Erroneously Dtd as 981103 & End Dates of Second 10-yr Insp Intervals Incorrect ML20198P0401998-12-14014 December 1998 Refers to 981210 Open Meeting at Licensee Request at Region II Re Weld Discrepancies Identified on Various Auxiliary Feedwater Sys Pipe Supports During Safety Sys Engineering Insp.List of Attendees & Util Presentation Handouts Encl ML20196J5591998-12-0808 December 1998 Submits Correction to Transmittal Ltr ,which Forwarded SE Authorizing Licensee Relief Request Re Rev to NDE-32, Svc Water Sys Leaks, Per 10CFR50.55a(a)(3)(ii). Corrected Date Should Be 981203 ML20198A7491998-12-0404 December 1998 Confirms 981203 Telcon Between L Hart of Licensee Staff & V Mccree of NRC Re Meeting Scheduled for 981210 in Atlanta, Ga Concerning Pipe Support Potential Construction Errors or Drawing Errors ML20198H9341998-12-0303 December 1998 Forwards SE Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant,Per Util 970224 Relief Request ML20196G9431998-12-0202 December 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting,Completed on 981102.Details of Insp Plan for Next 4 Months Encl ML20196A6581998-11-25025 November 1998 Forwards Notice of Withdrawal of 960321 Application for Amends to Licenses NPF-4 & NPF-7 for Plant.Changes Would Have Clarified Requirements for Testing Charcoal Absorbent in Waste Gas Charcoal Filter Sys ML20196B0011998-11-23023 November 1998 Forwards Emergency Response Data Sys Implementation Documents,Which Include Data Point Library Updates for Listed Plants.Changes Should Be Made to Data Base as Soon as Possible.Without Encl ML20196H3951998-11-0505 November 1998 Forwards Insp Repts 50-338/98-05 & 50-339/98-05 on 980713- 17,27-31 & 0921-25 & Notice of Violation & Re Failure to Implement Adequate Corrective Actions to Resolve Corrosion of AFW Tunnel Pipe Supports Identified in Sept 1996 ML20196G1161998-11-0303 November 1998 Forwards Safety Evaluation Authorizing Rev to ISI Program Relief Reuest NDE-32 Re SWS Leaks,Submitted on 980224,for Remainder of Second 10-yr Insp Interval for Each Unit ML20155H8061998-10-29029 October 1998 Responds to Discussing NRC Initiatives & Efforts. Plans for Another Stakeholders Meeting Underway for 981113. Staff Will Continue to Solicit Feedback & Comments from Public on Initiatives ML20154Q8331998-10-21021 October 1998 Informs That Info Submitted in 980911 Application & Affidavit Re WCAP-15063-P, W In-Reactor Creep Model, Marked Proprietary,Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20154G3611998-10-0707 October 1998 Informs That Util 951018,960722 Responses to Anomalies Identified in SER Dtd 950924,acceptable & Subject to NRC Inspection.Request for Relief from Valve Quarterly Tests & Proposal to Extend Test Interval,Not Acceptable ML20155B0531998-10-0202 October 1998 Forwards Exam Repts 50-338/98-301 & 50-339/98-301 on 980817- 21 & 31-0903.Fourteen Candidates Passed & One Failed Exam ML20155B3741998-09-25025 September 1998 Cancels Meeting Which Was Scheduled for 981109.Purpose of Meeting Was to Discuss SALP for North Anna Power Station. Informs That NRC Has Suspended SALP Program Until Staff Completes Review of NPP Performance Assessment Process ML20239A3801998-09-0202 September 1998 Confirms 980819 Telephone Conversation Between D Summers & L Garner Re Meeting at NRC Request Which Has Been Scheduled for 981109.Purpose of Meeting Will Be to Discuss SALP for North Anna Power Station ML20151T9351998-08-27027 August 1998 Informs of Change Being Implemented by Region II Re Administrative Processing of Licensee Responses to Novs. Licensee NOV Responses Which Accept Violations & Require No Addl Communication to Be Ack in Cover Ltr of Next Insp Rept ML20237E0111998-08-25025 August 1998 Discusses Completion of Licensing Action for GL 97-05, Steam Generator Tube Insp Techniques, ML20151T5531998-08-18018 August 1998 Forwards Insp Repts 50-338/98-07 & 50-339/98-07 on 980720-23.No Violations Noted.Insp Observed Selected Portions of Emergency Organization Response in Key Facilities During EP Plume Exposure Exercise IR 05000338/19980011998-08-0404 August 1998 Discusses Re Insp Rept Review & Three Clarifications Re Insp Repts 50-339/98-01 & 50-338/98-01 Discussions of Security at ISFSI ML20237B0001998-07-30030 July 1998 Confirms 980728 Telcon Between D Sommers & R Haag Re Meeting Scheduled for 980810 in Atlanta,Ga to Discuss Recent Mgt Changes & Items of Interest ML20236M0291998-07-0808 July 1998 Forwards Request for Addl Info Re ASME Section XI Relief Requests NDE-37,through NDE-41 for North Anna Power Station, Unit 1 ML20236K5451998-07-0707 July 1998 Forwards SER Accepting Proposed Change in Commitment on Inservice Insp Program for Protection Against Dynamic Effects Associated W/Postulated Rupture of High Energy Main Steam & Feedwater Piping,In Mechanical Equipment Room ML20236F7311998-06-29029 June 1998 Forwards Request for Addl Info Related to Fire,Seismic & High Wind,Flood & Other External Events Areas of IPEEE Submittal IR 05000338/19980021998-06-25025 June 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-338/98-02, 50-339/98-02 & 72-0016/98-02 ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20248M0381998-06-0909 June 1998 Forwards Request for Addl Info Re Revised Loop Stop Valve Operation.Changes Will Modify Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves 1999-09-08
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November 18, 1997
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! Virginia 1 Electric and Power Company-ATTN: Mr. J. P, O'Hanlon-Senior-Vice President - Nuclear
.Innsbrook Technical Center 5000 Dominion Boulevard-Glen Allen, VA 23060 SUBJECT: - NRC'I;i5FELTION REPORT NOS. 50-338/97-06 AND 50-339/97-06
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Dear Mr. O'Hanlon:
Thank you _for your response of October 1,1997, to ot< ( tice of Violation, issued on September 5,1997, concerning activities corm ted at your North Anna facility. In your response to the Notice of Violation (Notice), you c stated that you believed that the representation of Examples 3 and 4 did not accurately characterize the identified non-compliance.
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After careful consideration of the basis for your statement, we have F concluded, for the reasons presented in the enclosure to this letter that the i representation of Examples 3 and 4 was accurate as stated in the Notice. We recognize that under the specific circumstances, these individual examples are not significant. However, several additional examples of failure to effectively implement your requirements for procedural compliance were
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i_ identifled in the Notice and during a subsequent NRC inspection at North Anna.
Collectively we believe these examples indicated that various members of your p staff lack an adequate understanding of your procedural compliance
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requirements, specifically during plant testing evolutions.
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0n-November 13, 1997, _Mr. Robert Haag of my staff had a telephone conversation with Mr. David Heacock of your staff to further discuss the ::ited violation and additional actions you plan to take regarding procedural compliance.
Based on'this conversation it is our understanding that Maintenance Department
' Administrative Procedure M0AP-0019 " Maintenance Procedure Usage " will be
revised to further clarify _ management's expectations on verbatim procedural
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compliance and to provide additional guidance when taking credit for previously performed work. No additional response to this letter is required based on the actions stated-in the above noted telephone conversation.and the corrective actions-stated for the other examples in the Notice. These combined actions are sufficient for. examples 3 and 4.
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I OFFICIAL COPY .I
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9712040087 971118 PDR- ADOCK 05000338-G PDR ,
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VEPC0 2
- We will examine the implementation of-your-actions to correct-the violation-during future inspections.
We appreciate your. cooperation in this matter.
Sincerely
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Orig signed by Loren n11sco for Jon Johnson. Director Division of Reactor Prcjects Docket Nos. 5b 338, 50-339 License Nos. NPF-4, NPF-7 Enclosure: Evaluations and Conclusions cc w/ encl:
J. H. McCarthy, Manager Nuc'iear Licensing and Operations Support Virginia Electric & Power Company 5000 Dominion Boulevard G',en Allen, VA 23060 David A. Christian. Manager
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Surry Power Station Virginia Electric & Power Company 5570 Hog Island Road Surry, VA 23883 W. R. Matthews, Manager North Anna Power Station P. O. Box 402 Mineral. VA 23117 Executive Vice President Old Dominion Electric Cooperative 4201 Dominion Boulevard Glen Allen. VA 23060 County Administrator-Louisa County P. O. Box 160 Louisa. VA 23093
- cc_w/ encl
- See page 3
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VEPC0 3
=cc w/ encl: Continued Virginia State Corporation Comission Division of Energy Regulation P. O. Box 1197 Richmond. VA 23209 Hichael W. Maupin Hunton and Williams Riverfront Plaza. East Tower 951 E. Byrd Street Richmond, VA 23219 State Health Comissioner Office of the Commissioner Virginia Department of Health P. O. Box 2448 Richmond, VA 23218 Attorney General Supreme Court Building 900 East Main Street Richmond, VA 23219 Distribution w/ encl:
N. K11yanam. NRR R. Gibbs. RII P. Fillion. RII R. Aiello. RII W. Stansberry RII A. Boland. RII D. Jones. RII PUBLIC NRC Resident Inspector U.S. Nuclear Regulatory Commission Surr, Nuclear Power Station 58bo Hog Island Road Surry. VA 23883 NRC Resident Inspector U.S. Nuclear Regulatory Commission 1024 Haley Drive Mineral. VA 23117
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EVALUATIONS AND CONCLUSIONS
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On September 5. 1997, a Notice of Violation (Notice) was-issued for a violation identified during a routine NRC inspection. Virginia _ Electric and Power Company (the licensee) responded to the Notice on October 1.1997. The licensee stated that two examples of the identified non-compliance were not accurately characterized. The NRC's evaluations and conclusions regarding the licensee's response are es i'ollows:
Restatement of the Violation .
During an NRC inspection conducted on June 22 through August 9.1997, a violation cf NRC requirements was identified. In accordance with the " General Statement of Policy and Procedures for NRC Enforcement Actions." NUREG-1600.
the violation is listed below:
Technical Specification 6.8.1.a requires that written procedures shall be established, implemented and maintained covering the applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33.
Revision 2. February 1978.
Regulatory Guide 1.33. " Quality Assurance Program Requirements (Operations)," Appendix "A". Paragraphs 1.c and 8.b require procedures for equipment control and surveillance tests, respectively.
Operations Department Administrative Procedure. OPAP-0010. " Tag-Outs."
Revision 8. Step 6.10.2.a requires the use of the appropriate procedure (e.g.. Maintenance Operating Procedure) in conjunction with the tagging record, as instructions to align components and remove equipment tags.
Unit 1 Periodic Test (PT) Procedure 1-PT-36.18. " Train B Reactor Protection and Engineered Safety Feature Logic Channel Functional Test."
Revis;on 19. Step 6.2.3.C.2. requires closure of the reactor trip bypass breaker compartment door before an ooerator reopens the door and racks the bypass breaker into the connect position in the following step.
Unit 1 Periodic Test Procedure.1-PT-32.3.5. " Steam Generator B Steam Flow / Feed Flow Protection IV Channel Functional Test." Revision 28.
Steps 6.1.5 and 6.1.8 require verification of the correct test switch positions prior to actual testing. Step 6.1.6 requires that the test cabinet door be opened before testing. Step 6.3.6 requires that the test switch cabinet door, which was opened in Step 6.1.6. is to be locked closed when testing is complete.
Unit 1 Periodic Test Procedure. 1-PT-32.3.6. " Steam Generator C Steam Flow / Feed Flow Protection IV Channel Functional Test." Revision 27.
Enclosure
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Steps 5.1.5 and 6.1.8 require verification of the correct test switch positions prior to actual testing. Step 6.1.6 requires that the test cabinet door be opened b2 fore testing.
Contrary to the above, equipment control and surveillance test procedures were not im91emented as evidenced by:
1. On July. 9.1997, while returning the Service Water System to service following maintenarce. the unit shift supervisor failed to use 0-H0P-49.14 with Tagging Record (N) 0-97-SW-0015 to align components and remove equipment tags.
2. On July 10. 1997, during performance of 1-PT-36.1B. the assigned electrician failed to perform Step 6.2.3.C.2.
3. On August 2, 1997, during performance of 1-PT-32.3.5. the instrument and control technicians failed to perform Steps 6.1.5.
6.1.6. 6.1.8. and 6.3.6.
4. On August 2.1997. during performance of 1-PT-32.3.6. the instrument and control technicians failed to perform Steps 6.1.5.
6.1.6. and 6.1.8.
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This is a Severity Level IV violation (Supplement I)
Summary of Licensee's Response to Violation (Examoles 3 and 4)
In the licensee's response they stated that the Notice of Violation (Examples 3 and 4) did not accurately characterize the identified noncompliance for failure to perform Steps 6.1.5. 6.1.6. and 6.1.8. These steps are found in 1-PT-32.3.5. " Steam Generator B Steam Flow and Feed Flow Protection Channel IV (F-MS-1485 and F-FW-1486) Channel Functional Test." and 1-PT-32.3.6. " Steam Generator C Steam Flow and Feed Flow Protection Channel IV (F-MS-1495 and F-FW-1496) Channel Functional Test.' The licensee believes that Steps 6.1.5.
6.1.6. and 6.1.8 were followed because the same steps were performed previously during the performance of 1-PT-32.3.4 " Steam Generator A Steam Flow and Feed Flow Protection Channel IV (F-MS-1475 and F-FW-1476) Channel Functional Test." Periodic Test 1-PT-32.3.4 was the first test in a series of tests which-included 1-PT-32.3.5 and 1-PT-32.3.6. The licensee contends that having successfully performed these steps in 1-PT-32.3.4 allows them to take credit for satisfactorily performing these steps in 1-PT-32.3.5 and 1-PT-32.3.6. The licensee's basis for their position is found in MDAP-0019.
" Maintenance Procedure Usage." Step 6.1.3.c which states. "If a procedure step states an action to be performed.-and the action was performed previously l.
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NRC Evaluation of Licensee's Resoonse i The NRC staff reviewed the licensee's response and has concluded tn# Steps 6.1.5. 6.1.6. and 6.1.8 should have been performed as. described in 1-P1 <2.3.5 and 1-PT-32.3.6 and remain as two examples of failure to follow approved written procedures; There are two bases for the NRC staff disagreeing with the licensee's position that credit can be taken for Steps 6.1.5. 6.1.6.'and i 6.1.8 since they had been performed earlier while completing 1-PT-32.3.4.
The first basis involves MDAP-0019. Step 6.1.3.c which requires that procedure steps shall be verified to be completed and initialed when taking credit for action that was previously performed. Steps 6.1.5 and 6.1.8 involved verification of plant switch positions. Step 6.1.5 used the action verb
" verify" and Step 6.1.8 used the action verb " ensure." The licensee's definition of verify is provided in VPAP-0213. " Abbreviations. Acronyms, and Action Verbs." Revision 2. Verify is defined as. "To observe that an expected characteristic or condition exists." Procedure VPAP-0213 did not define ensure. The inspectors were informed that the definition of ensure was being added to VPAP-0213 and would De similar to the verify definition in that an
- observation would be required. During performance of the steps in question
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the inspectors noted that no action was taken to observe the switch positions in Steps 6.1.5 and 6.1.8. The licensee improperly took credit for the verify and ensure actions of the switch positions which had been previously performed while implementing 1-PT-32.3.4. ,
Step 6.1.6 was an action step to open the door wnere the testing took place -'
and verify that an annunciator was received. The inspectors noted that the technician did not perform these actions. Since the door in question was at the panel were the technician was performing the PT. the NRC recognizes that )
- the technician could verify that the door was open by the fact that he was working at the panel and the door was open to allow this testing to occur.
However the technician took no action associated with the annunciator. The licensee contends that performing this step again was not necessary because of
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the procedural flexibility provided by MDAP-0019. Step 6.1.3.c and the fact-that this step had been completed satisfactorily while earlier performing 1-PT-32.3.4. As stated above. Step 6.1.3.c requires that the step shall be verified to be completed and the step initialed when taking credit for action that was previously completed. There was no verification that the annunciator was received.
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The second basis for disagreeing with the licensee's position that credit could be taken for Steps 6.1.5. 6.1.6 and 6.1.8. which had been previously performed involves Step 6.1.1 of MDAP-0019. This step requires that periodic
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test procedures shall be performed in a step-by-step manner with each step completed prior to the performance of the next step. Based on this requirement the NRC concluded that the procedural flexibility' provioed by MDAP-0019. Step 6.1.3.c. i.e. relying on previously performed work, is not applicable to pts. Therefore, the steps in question should have been completed in each of the periodic test procedures in the specified sequence.
NRC Conclusion The NRC staff concludes that failure to perform Steps 6.1.5. 6.1.6. and 6.1.8 in procedures 1-PT 32.3.5 and 1-PT-32.3.6 remain as examples of failure to follow approved written procedures and did accurately characterize the non-compliance.
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