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| | * , * |
| | * 4. |
| | Re$! 3000 $u Girn ARen. Wginia 23060 804e273*3331 a. |
| | l f) r 5 |
| | July 31,1998 |
| | * MdD e |
| | { |
| | 1%a5 |
| | ! Chairman Shirley A. Jackson ' |
| | Commissioner Nils J. Diaz |
| | ! Commissioner Edward McGaffigan i |
| | Nuclear Regulatory Commission |
| | [ One White Flint North |
| | ; 11555 Rockville Pike |
| | ; Rockville, MD 20852-2738 1 |
| | j |
| | |
| | ==Dear Chairman Jackson and Commissioners Diaz and McGaffigan:== |
| | |
| | \ NRC STAKEHOLDER MEETING, JULY 17,1998 l |
| | The stakeholder meeting hold on July 17 was a candid and productive exchange l |
| | of ideas. I was encouraged by the receptivity of everyone at the table to the j suggestions and criticisms raised by others. |
| | During the meeting, there were several references to the recent Technical Specification changes made at Surry and North Anna Power Stations to reflect the change in title from Plant Manager to Site Vice President. To get an accurate perspective of these comments, you should be aware of some relevant history regarding our Technical Specificatio'1s. |
| | In the early 90's, Virginia Power agreed to work with the NRC Staff to convert the Technical Specifications. In fact, North Anna was the pilot Westinghouse plant for a Technical Specification conversion starting in 1990. Unfortunately, the effort continued on for an unacceptably long period of time without clear direction, and with ongoing changes and additions by the NRC Staff. Instead of becoming simpler and more understandable, the Technical Specifications were l |
| | becoming more complex. After spending more than $2 million over a two year ' |
| | period with r,o prospects of completion in sight, we reluctantly decided to withdraw from the project. - Two years ago, we agreed to convert to the improved Technical Specification format at both the Surry and North Anna Power Stations. |
| | This effort has been delayed because we had to reallocate our resources to . |
| | - verify tha completeness and accuracy of our FSARs and to the parallel design basis documentation effort. |
| | 9811100291 981029 7 PDR ADOCK 05000338 P PDR , |
| | 98/HD0M/ |
| | |
| | ,')'' |
| | ~ |
| | Commissionar McGaffigan suggsstad aftsr the mrmting that wn could h , |
| | rsqutsted or to titles |
| | 'zational eliminuta ths stction of the Technical Spscifications that ind"* |
| | jHowsysTthe bian naa previously told us that they would I |
| | entire Technical Specifications to the improved pg*7 Te issues raised at the meeting. Virginia Power ha and cordial relationship with the NRC for years. We may not always agr , |
| | the NRC findings or conclusions, but we have felt free to discuss the iss frank manner. Similarly, we have found the Staff willing to listen to ou j and professional in getting licensng amendments and other NRC action completed. |
| | However, there are areas where we believe that the NRC-licensee inte can be improved. Virginia Power, like the rest of the utility industry, has b more efficient during the last few years. We have lowered our operating c and have prioritized our activities based on safety significance. We hope would have seen comparable improvements at the NRC. We have shown safe but performance more wisely utilized,cannot only be maintained, but also improved, with urces. |
| | enforcement actions, reque; Nevertheless, many inspections, |
| | .or information, etc., require us to spend resources significance. on activities that we perceive are inconsistent with their safety i |
| | f(dy p |
| | ! The use of risk information was widely supported by all at the table. We al O '' |
| | concur with the increased use of risk information in the regulatory process. 'q The Staff response in this area, however, has not always been supportive W, or encouraging. |
| | i In September 1995, we submitted a request for a Technical i Specification change for the allowed outage time of our diesel generators a pending.Anna Power Station based on risk information. |
| | North That request is still |
| | ! We have paid over $50,000 in NRC review fees alone on this i |
| | proposed change and revised the submittal two times at the direction of the StMf, yet the Staff is still not sure of how or whether to approve the change Cg industry is being forced to work simultaneously in two realms - one risk-infor and one deterministic. |
| | p i resources, This causes a great deal of confusion and wastes k |
| | Timeliness was another area discussed at the stakeholder meeting. We a to see the commission and NRC management willing to improve the timeliness of NRC actions. As noted before in the emergency diesel generator allowed outage time example, some licensing actions take unreasonable amounts of time to complete. Additionally, resolution of proposed generic activities often languis in spite of the cost benefit without safety consequence. For example, our 1 l |
| | proposed rulemaking on final audits for security, emergency planning, and A r |
| | .m', ,_ ~ - _ , ~ ~ . _ . _ - ~-, _- - D |
| | |
| | ,,/ |
| | fitn:ss for cuty w:s suomitt:0 on Doc $mber 30, 1993, cnd hks y$t to be |
| | ,4. |
| | * dispositioned. |
| | i i |
| | - Again, I want to personally thank the Commission for embarking in such a constructive exchange with its stakeholders. We support efforts to focus the inspection and enforcement areas, to better prioritize activities, and to improve I the interaction with the licensees. I hope that we can continue to work together to improve the safety and performance of our plants while maintaining cost control. |
| | Sincerely, i l |
| | 771b h t |
| | James P. O'Hanlon cc: Mr. L. J. Callan l |
| | Mr. S. J. Collins Mr. J. F. Colvin I |
| | Ms. K. D. Cyr Mr. D. A. Lochbaum Mr. C. A. McNeill, Jr. |
| | I Mr. E. A. Nye Mr. Z. T. Pate Mr H. B. Ray Mr. F. J. Remick Mr. L. A. Reyes l |
| | i.}} |
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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 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) 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 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 ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution 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 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 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 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 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) ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls 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 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 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 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 1999-09-08
[Table view] |
Text
. . . . . _ . - _ _. . _ . _ . _ - ~ - - - - - - - - - - ~ ~ ~ " " ~ ' ~ ~ ~ ~ ~ ^ ^ ^ ^ ^ ~ ~ ~ ~ ^ ^ ^ ~ ~ ~ ^ ~ ~ ~ ~ ~
Re$! 3000 $u Girn ARen. Wginia 23060 804e273*3331 a.
l f) r 5
July 31,1998
{
1%a5
! Chairman Shirley A. Jackson '
Commissioner Nils J. Diaz
! Commissioner Edward McGaffigan i
Nuclear Regulatory Commission
[ One White Flint North
- 11555 Rockville Pike
- Rockville, MD 20852-2738 1
j
Dear Chairman Jackson and Commissioners Diaz and McGaffigan:
\ NRC STAKEHOLDER MEETING, JULY 17,1998 l
The stakeholder meeting hold on July 17 was a candid and productive exchange l
of ideas. I was encouraged by the receptivity of everyone at the table to the j suggestions and criticisms raised by others.
During the meeting, there were several references to the recent Technical Specification changes made at Surry and North Anna Power Stations to reflect the change in title from Plant Manager to Site Vice President. To get an accurate perspective of these comments, you should be aware of some relevant history regarding our Technical Specificatio'1s.
In the early 90's, Virginia Power agreed to work with the NRC Staff to convert the Technical Specifications. In fact, North Anna was the pilot Westinghouse plant for a Technical Specification conversion starting in 1990. Unfortunately, the effort continued on for an unacceptably long period of time without clear direction, and with ongoing changes and additions by the NRC Staff. Instead of becoming simpler and more understandable, the Technical Specifications were l
becoming more complex. After spending more than $2 million over a two year '
period with r,o prospects of completion in sight, we reluctantly decided to withdraw from the project. - Two years ago, we agreed to convert to the improved Technical Specification format at both the Surry and North Anna Power Stations.
This effort has been delayed because we had to reallocate our resources to .
- verify tha completeness and accuracy of our FSARs and to the parallel design basis documentation effort.
9811100291 981029 7 PDR ADOCK 05000338 P PDR ,
98/HD0M/
,')
~
Commissionar McGaffigan suggsstad aftsr the mrmting that wn could h ,
rsqutsted or to titles
'zational eliminuta ths stction of the Technical Spscifications that ind"*
jHowsysTthe bian naa previously told us that they would I
entire Technical Specifications to the improved pg*7 Te issues raised at the meeting. Virginia Power ha and cordial relationship with the NRC for years. We may not always agr ,
the NRC findings or conclusions, but we have felt free to discuss the iss frank manner. Similarly, we have found the Staff willing to listen to ou j and professional in getting licensng amendments and other NRC action completed.
However, there are areas where we believe that the NRC-licensee inte can be improved. Virginia Power, like the rest of the utility industry, has b more efficient during the last few years. We have lowered our operating c and have prioritized our activities based on safety significance. We hope would have seen comparable improvements at the NRC. We have shown safe but performance more wisely utilized,cannot only be maintained, but also improved, with urces.
enforcement actions, reque; Nevertheless, many inspections,
.or information, etc., require us to spend resources significance. on activities that we perceive are inconsistent with their safety i
f(dy p
! The use of risk information was widely supported by all at the table. We al O
concur with the increased use of risk information in the regulatory process. 'q The Staff response in this area, however, has not always been supportive W, or encouraging.
i In September 1995, we submitted a request for a Technical i Specification change for the allowed outage time of our diesel generators a pending.Anna Power Station based on risk information.
North That request is still
! We have paid over $50,000 in NRC review fees alone on this i
proposed change and revised the submittal two times at the direction of the StMf, yet the Staff is still not sure of how or whether to approve the change Cg industry is being forced to work simultaneously in two realms - one risk-infor and one deterministic.
p i resources, This causes a great deal of confusion and wastes k
Timeliness was another area discussed at the stakeholder meeting. We a to see the commission and NRC management willing to improve the timeliness of NRC actions. As noted before in the emergency diesel generator allowed outage time example, some licensing actions take unreasonable amounts of time to complete. Additionally, resolution of proposed generic activities often languis in spite of the cost benefit without safety consequence. For example, our 1 l
proposed rulemaking on final audits for security, emergency planning, and A r
.m', ,_ ~ - _ , ~ ~ . _ . _ - ~-, _- - D
,,/
fitn:ss for cuty w:s suomitt:0 on Doc $mber 30, 1993, cnd hks y$t to be
,4.
i i
- Again, I want to personally thank the Commission for embarking in such a constructive exchange with its stakeholders. We support efforts to focus the inspection and enforcement areas, to better prioritize activities, and to improve I the interaction with the licensees. I hope that we can continue to work together to improve the safety and performance of our plants while maintaining cost control.
Sincerely, i l
771b h t
James P. O'Hanlon cc: Mr. L. J. Callan l
Mr. S. J. Collins Mr. J. F. Colvin I
Ms. K. D. Cyr Mr. D. A. Lochbaum Mr. C. A. McNeill, Jr.
I Mr. E. A. Nye Mr. Z. T. Pate Mr H. B. Ray Mr. F. J. Remick Mr. L. A. Reyes l
i.