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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:INCOMING CORRESPONDENCE
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 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) 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 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 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 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 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 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 ML20195C6601999-06-0101 June 1999 Forwards Response to NRC 990216 RAI Re Summary Rept of USI A-46 Program 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 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 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 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 ML20206H0221999-05-0303 May 1999 Informs That Licensee Changes Bases for TS 3/4.6.1.2, Containment Leakage. Changes Allow Use of Other NRC Staff Approved/Endorsed Integrated Leak Test Methodologies to Perform Containment Leakage Rate Testing.Ts Bases Page,Encl ML20206G9481999-05-0303 May 1999 Informs NRC That Insp of 58 Accessible safety-related Pipe Supports Completed in Response to NOV from Insp Rept 50-338/98-05 & 50-339/98-05.Commitments Made Include Plans to Perform Assessment of Welding & Welding Insp ML20205T1181999-04-16016 April 1999 Requests NRC Approval Prior to Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit.Nrc Concurrence with Irradiation Program Requested by End of June 1999 ML20205P1891999-04-0808 April 1999 Forwards ISI Program for Third ten-yr ISI Interval for North Anna Unit 1 for Class 1,2 & 3 Components & Component Support.Third ten-yr Insp Interval for North Anna Unit 1 Begins on 990501.Page 2-26 of Encl Not Included ML20205K3631999-04-0505 April 1999 Requests That Relief Request IWE-3 Be Removed from 980804 Relief Requests Submitted to Nrc.Subject Relief Request Was Inadvertently Retained in Attachment 1 for Unit 1 ML20205K2191999-04-0101 April 1999 Forwards Response to NRC 990106 RAI Re Util Summary Rept on USI A-46 Program,Submitted 970527.Calculations & Corrected Table 11.1-1,encl ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML20205E2701999-02-25025 February 1999 Forwards Rept on Status of Decommissioning Funding for North Anna Power Station,Units 1 & 2.Trust Agreement Between Old Dominion & Bankers Trust Co,Effective 990301,attached ML20207A8741999-02-25025 February 1999 Draft Response to NRC Telcon Re Licensee Request for Approval of LBB Evaluation in Support of Elimination of Augmented Insp Program on RCS Loop Bypass Lines.Response Justifies Use of Less than One Gpm Detectable Leakage Rate ML18152B5401999-02-11011 February 1999 Requests Relief from Specific Requirements of Subsection Iwl of 1992 Edition with 1992 Addenda of ASME Section Xi,Per 10CFR50.55a(a)(3) ML20203C8181999-02-0505 February 1999 Forwards Response to NRC 981217 Telcon RAI Re risk-basis of Nitrogen Accumulator Action Statement to Complete NRC Review of 951025 Proposed TS Changes 1999-09-27
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VIHOINIA EU!CTHIC AND POWEH COMI%NY llicII M ox u, VIIWINI A 20061 June 18, 1993 United States Nuclear Regulatory Commission Serial No.93-374 Attention: Document Control Desk NOAVFR R2 Washington, D. C. 20555 Docket Nos. 50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 AND 2 10 CFR 50 APPENDIX E EXEMPTION REQUEST Pursuant to 10 CFR Part 50.12, Virginia Electric and Power Company (VEPCO) requests a one-time exemption from the requirement, specified in 10 CFR Part 50, Appendix E, Section IV.F.2., for each licensee at each site to annually exercise its emergency plan. Specifically, we request a one-time exemption from the requirement to conduct the 1993 North Anna Power Station Emergency Plan partial par'icipation exercise presently scheduled for August 18,1993.
The request for exemption is based on the implementation of VEPCO's emergency response capability during the April 24,1993 Alert at the North Anna Power Station.
The implementation of the North Anna and Corporate emergency plans, along with the demonstration of the response capability, satisfy the requirements for the partial participation (small scale) exercise demonstration as specified in the North Anna Emergency Plan. Furthermore, this response demonstration included involvement of the cognizant State and local jurisdictions and was critiqued by VEPCO and evaluated by the Nuclear Regulatory Commission (NRC).
As the implementation of the emergency plan was demonstrated and evaluated, we conclude that the adequacy of the emergency preparedness program implementation has already been demonstrated during 1993. There are numerous examples throughout the industry of similar licensee requests receiving relief from the subject requirement when there has been an actual emergency response. Attachment 1 provides a supporting rationale for this request.
The Commonwealth of Virginia has made a similar request of the Federal Emergency Management Agency with respect to select six year plan demonstration requirements and is in full agreement and support of our request. We note that emergency plan commitments will continue to be met with the exception of the subject exercise.
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ADOCK 05000338 F PDR
We would appreciate your review of this request prior to the currently scheduled August 18,1993 North Anna Power Station Emergency Plan partial participation exercise. To facilitate your review, we are prepared to meet with you at your earliest-convenience.
Should you have any questions, please contact us.
Very truly yours, W. L. Stewart h
Senior Vice President ~- Nuclear Attachment
- 1. Appendix E Exemption Request - Supporting Rationale -
- 2. References cc: Mr. Stewart D. Ebneter Region ll l
101 Marietta Street, N. W.
I Suite 2900 Atlanta, Georgia 30323 ,
l Mr. K. P. Barr Region 11 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 NRC Resident inspector North Anna Power Station Mr. George O'N. Urquhart Department of Emergency Services 310 Turner Road Richmond, Virginia 23225
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NORTH ANNA POWER STATION UNITS 1 AND 2 10CFR50 APPENDIX E EXEMPTION REQUEST ANNUAL EMERGENCY EXERCISE SUPPORTING RATIONALE EXEMPTION REQUEST
SUMMARY
Pursuant to 10 CFR Part 50.12, Virginia Electric and Power Company (VEPCO) requests a one-time exemption from the requirement to conduct the 1993 North Anna Power Station Emergency Plan partial participation exercise. Specifically, we request a one-time exemption from the provision requiring each site to annually exercise its emergency plan as specified in 10 CFR Part 50, Appendix E, Section IV.F.2.
Generically, this requirement has been interpreted as the conduct of an integrated exercise scheduled for NRC evaluation. The 1993 NRC evaluated Emergency Plan partial participation exercise for North Anna Power Station is presently scheduled for August 18,1993.
The request for exemption from the requirement to conduct the scheduled annual exercise with NRC evaluation is based on the implementation of VEPCO's response capability during the April 24,1993 Alert at the North Anna Power Station. That response met the requirements for the partial participation (small scale) exercise demonstration as specified in the North Anna Emergency Plan in Section 8.6.2.
Pursuant to the April 24,1993 Alert, the NRC conducted an inspection that evaluated the adequacy of VEPCO's implementation of the North Anna Emergency Plan in response to that event.
BACKGROUND Emergency planning regulations, promulgated as a result of the March,1979 accident at Three Mile Island, govern virtually all aspects of a licensee's emergency preparedness program and have done much to lay the basis for a structured formal response capability. These requirements cover a broad spectrum, including emergency organizational structure, emergency equipment and response facilities, and emergency assessment mechanisms such as the Safety Parameter Display System (SPDS), and dose assessment methodologies. The requirement for a licensee to hold an exercise on an annual basis is but one of many indicators designed to provide reasonable assurance that actions can and will be taken during an emergency situation that will provide for the health and safety of the public.
The purpose for conducting an annual exercise is to demonstrate the adequacy of the licensee's emergency response capability and emergency preparedness program.
The licensee's demonstration of its ability to respond to an event, coupled with it's ability to assess the adequacy of it's own response, is routinely assessed and evaluated by the NRC. An evaluation of an annual exercise provides an indication of the adequacy and level of a licensee's emergency response program. To that end, VEPCO's response to the April 24,1993 Alert was critiqued by VEPCO and evaluated by the NRC.
l TECHNICAL BASIS The North Anna Power Station Emergency Plan, at Section 8.6.2, states that "(s) mall scale exercises shall include:
a) An emergency classification of at least Alert b) Use of communication systems c) Activation of at least one offsite emergency response plan action (e.g., >
medical transport, fire assistance, offsite monitoring, law enforcement assistance)" ,
Meeting the requirement of an emergency classification of at least an Alert is self evident.
Internal communications systems were activated and utilized throughout the various emergency response facilities as evidenced by numerous responder logs available for review during the NRC inspection. Communications with offsite authorities included ,
coordination with State officials from the Department of Emergency Services and the Bureau of Radiological Health responding to the Local Emergency Operations Facility (EOF). Additionally,13 formal notifications were made to the State and local risk '
jurisdictions over the Insta-phone telecommunications system and~ communications '
with federal authorities included activation of the Emergency _ Response Data System (ERDS) and use of the FTS-2000 system for Emergency Notification System (ENS) and Health Physics Network (HPN) communications. The NRC inspection of VEPCO's implementation of the plan resulted in the identification of an inspector Follow-up Item (IFI) pedaining to ENS communications with the NRC. That IFl (50-338,339/93-14-01) -
is documented within inspection Report Nos. 50-338/93-14 and 50-339/93-14 (Reference 1).
With respect to the third requirement of the plan, we note that the State staffed, 3 activated and operated their Emergency Operations Center (EOC) and, as mentioned earlier, dispatched personnel from the Department of Emergency-Services and the Bureau of Radiological Health to coordinate with the VEPCO emergency response ,
organization members in the Local EOF. Coordination between the State and VEPCO i included accident assessment and public information activities.
DISCUSSION 10 CFR Part 50, Appendix E, Section IV.F.2. states that "Each licensee at each site shall annually exercise its emergency plan." Generically, this requirement has been interpreted as an integrated exercise conducted and assessed by the licensee. This conduct and assessment of the demonstrated response capability is then subject to NRC evaluation.
On April 24,1993, an Alert was declared at the North Anna Power Station due to observed vibrations of the Unit 2 feedwater piping and reports that indicated a possible leak in the feedwater line. As a result of the Alert declaration, and-as-provided for under the North Anna Emergency Plan, all VEPCO emergency response 3 facilities were fully staffed, activated, and operated in accordance with Emergency l Plan' implementing Procedures.
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In consideration of the commitment of resources and as a result of the implementation of the North Anna Emergency Plan in response to the Alert, we request a one-time exemption for North Anna from the provision requiring each licensee at each site to annually exercise its emergency plan. Approval of this exemption is requested in order to reduce the duplication of demonstration of emergency response elements. We believe that the conduct of a partial participation exercise would be an unnecessary use of Federal, Company, State and local resources that would only serve to reconfirm the established adequacy of the plan as well as the Company's capability to implement the plan. Performance of the 1993 North Anna Emergency Plan partial participation exercise, given our specific circumstances and performance in this area, represents an undue regulatory burden with minimal benefit to public safety.
It is noted that an NRC inspection of the North Anna Power Station 1992 Emergency Exercise, detailed in Inspection Report Nos. 50-338/92-01 and 50-339/92-01 (Reference 2), identified no violations or deviations. The NRC noted that full participation exercise, which was also evaluated by FEMA, demonstrated "[t]he licensee's . . . ability to implement the Emergency Plan and Implementing Procedures in a manner which provided adequate protection of the health and safety of the public and site personnel. Exercise strengths included a challenging scenario, a well-trained controlling staff, and a thorouch criticue orocess." (emphasis added).
North Anna's latest SALP of record covered the period from September 1,1990 through November 2,1991 and resulted in a repeat Category 1 rating. The report further comirms VEPCO's sustained commitment and positive performance in emergency preparedness (Reference 3). The NRC cover letter transmitting North Anna's SALP ratings stated that with respect to emergency preparedness, the Company had ". . . maintained their superior level of performance" and that ". . .
[i]mproved performance in several activities was influenced significantly by initiatives implemented during the assessment period . . ." The SALP report identified six program strengths and discussed Company initiatives regarding enhancements, as well as taking ". . . the initiative (during) this assessment period to install an Emergency Response Data System (ERDS) well in advance of ERDS becoming.a regulatory requirement." These regulatory observations confirm the state of operational i readiness at an overall Company level. l JUSTIFICATION 10 CFR 50.12 states that the Commission may grant exemptions from the ,
requirements of the regulations contained in the 10 CFR 50 provided that: (1) the i I
exemption is authorized by law, (2) the exemption will not precent an undue risk to the public health and safety, (3) the exemption is consistent with the common defense and security, and (4) special circumstances as defined in 10 CFR 50.12(a)(2) are present. ;
- 1. The Recuested Exemotion is Authorized by Law No law exists which would preclude the activities covered by this exemption request. Also, this exemption, if approved, would not create a conflict with any existing law.
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- 2. The Recuested Exemotion Does Not Present an Undue Risk to the Public Health and Safety Considering the implementation of the North Anna Power Station Emergency Plan in response to the April 24,1993 Alert, the one-time exemption from the requirement to annually exercise the emergency plan at each site does not present an undue risk to the public health and safety. A significant portion of the Company's emergency response capability has been evaluated by the NRC pursuant to the Alert. No plant components are affected by this exemption.
Therefore, an exemption from the North Anna annual exercise does not increase the risk to the public health and safety.
- 3. The Recuested Exemotion Will Not Endancer the Common Defense and Security The common defense and security are not an issue in this exemption request.
- 4. Soecial Circumstances as Defined in 10 CFR 50.12(a)(2)
The following special circumstances pursuant to 10 CFR 50.12(a)(2) are identified as applicable to this exemption request:
Item (ii) " Application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule." As discussed above, we contend that the provisions of the North Anna Power Station Emergency Plan have been met and, therefore, the underlying intent of the rule has already been met by virtue of the Company's implementation of the plan in response to the April 24, 1993 Alert. Furthermore, the implementation of the plan was evaluated within the context of an NRC inspection. See inspection Report Nos. 50-338/93-14 and 50-339/93-14 (Reference 1). Requiring the scheduled annual exercise at North Anna is merely duplicative confirmation and unneeded to establish an assessment of the adequacy of the emergency preparedness program.
Item (v) "The exemption would provide only temporary relief from the applicable regulation and the licensee or applicant has made good faiih efforts j to comply with the regulation." A one-time exemption, based on already 1 established performance is not permanent, but rather, provides relief only for 1993. VEPCO's performance to date has shown " good faith" to comply with the intent of the regulation.
l item (vi) "There is present any other material circumstances not considered l when the regulation was adopted for which it would be in the public interest to grant an exemption. . ." The regulation does not anticipate the occurrence of events that would prompt the classification of an emergency and its associated response. Therefore, the regulation does not specifically anticipate an actual emergency response satisfying the annual requirement to demonstrate the licensee's response capability. Furthermore, "other material circumstances"
Include an additional basis whereby.the public interest would be served by applying resources, now directed to duplicating response capability confirmation, to other safety priority issues.
CONCLUSION As the implementation of the emergency plan was demonstrated during the response
- to the April 24,1993 Alert at North Anna and the implementation of the plan was subsequently evaluated by the NRC, we conclude that the adequacy of the emergency
. preparedness program has been demonstrated and the provisions of the plan have
- been satisfied. An additional partial participation exercise at North Anna during .1993 i will do nothing to further demonstrate that adequate protective measures can and will j be taken in the event of a radiological emergency and is not necessary to establish j reasonable assurance of the health and safety of the public.
Approval of this exemption is requested to reduce the duplication of demonstration of
- emergency response elements. We believe the conduct of the exercise to be an j unnecessary use of Federal, Company, State and local resources that would only i serve to reconfirm the established adequacy of the plan as well as the Company's i capability to implement the plan. Performance of the 1993 North Anna Emergency i Plan partial participation exercise, given our specific circumstances and performance
! in this area, represents an undue regulatory burden with. minimal benefit to public j safety.
j Granting a one-time exemption from conducting the scheduled annual partial j participation emergency exercise at the North Anna. Power Station on August 18,1993 i is warranted based on the adequate implementation of_VEPCO's Emergency Plan in
- response to the April 24,1993 Alert and, therefore, by virtue of already meeting the intent of the regulation.
j For these reasons, we conclude that the requested exemption will.not present an i undue risk to the public health and safety and is consistent with the common defense j and security, and meets the special circumstance described in 10 CFR' Part j 50.12(a)(2)(ii).
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REFERENCES
- 1. NRC Inspection Report Nos. 50-338/93-14 and 50-339/93-14 dated June 3, 1993
- 2. NRC Inspection Report 50-338,339/92-01 dated February 12,'1992
- 3. NRC Inspection Report 50-338,339/91-25 dated January 13,1992 l
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