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| *Virginia Electric and Power Company | | *Virginia Electric and Power Company |
| * 10 CFR 20.1703(a)(2) Authorization Request for Additional Information | | * 10 CFR 20.1703(a)(2) Authorization Request for Additional Information |
| : 1. In the March 27-, 1997 request letter for the 1O CFR 20.1703(a)(2) authorization, Virginia Electric and Power Company requested to " .. make allowance for protection factors as specified for Pressure Demand Self-Contained Breathing Apparatus (SCBA) in 10 CFR 20, Appendix A (i.e., 10,000 or greater) during normal and emergency use." In reference to the numerical value of the SCBA protection factor (PF) 10,000 or greater, please confirm that you are requesting to use protection factors greater than 10,000. Since 10 CFR 20 Appendix A requires prior authorization to use PFs greater than 10,000, please provide additional test data for PFs greater than 10,000 tcrjustify use of such PFs. * | | : 1. In the March 27-, 1997 request letter for the 10 CFR 20.1703(a)(2) authorization, Virginia Electric and Power Company requested to " .. make allowance for protection factors as specified for Pressure Demand Self-Contained Breathing Apparatus (SCBA) in 10 CFR 20, Appendix A (i.e., 10,000 or greater) during normal and emergency use." In reference to the numerical value of the SCBA protection factor (PF) 10,000 or greater, please confirm that you are requesting to use protection factors greater than 10,000. Since 10 CFR 20 Appendix A requires prior authorization to use PFs greater than 10,000, please provide additional test data for PFs greater than 10,000 tcrjustify use of such PFs. * |
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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
VIRGINIA ELECTRIC AND PowER CoMPANY RICHMOND, VIRGINIA 23261
- July 28, 1997 United States Nuclear Regulatory Commission Serial No. 97-092A Attention: Document Control Desk NL&OS/DAS RO Washington, D.C. -20555 Docket Nos. 50-280/281 50-338/339 License Nos. DPR-32/37 NPF-4/7
Dear Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION 10 CFR 20.1703(a)(2) EQUIPMENT AUTHORIZATION In a March 27, 1997 letter (Serial No.97-092) Virginia Electric and Power Company requested specific authorization to use respiratory protection equipment for equipment which has not been tested and certified by NIOSH/MSHA for the specific application at both Surry and North Anna Power Stations. In a June 26, 1997 letter, the staff . i I
requested additional information. The attachment provides information requested by the Staff, to support the review of the equipment authorization.
Should you have any questions regarding the authorization request, please do not hesitate to contact us.
Very truly yours, James P. O'Hanlon Senior Vice President - Nuclear Attachment Commitments made by this letter:
None
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- U.S. Nuclear Regulatory Commission e
Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station Mr. M. J. Morgan NRC Senior Resident Inspector North Anna Power Station
- Attachment 10 CFR 20.1703(a)(2) Authorization Request for Additional Information Virginia Electric and Power Company Surry and North Anna Power Stations
- Virginia Electric and Power Company
- 1. In the March 27-, 1997 request letter for the 10 CFR 20.1703(a)(2) authorization, Virginia Electric and Power Company requested to " .. make allowance for protection factors as specified for Pressure Demand Self-Contained Breathing Apparatus (SCBA) in 10 CFR 20, Appendix A (i.e., 10,000 or greater) during normal and emergency use." In reference to the numerical value of the SCBA protection factor (PF) 10,000 or greater, please confirm that you are requesting to use protection factors greater than 10,000. Since 10 CFR 20 Appendix A requires prior authorization to use PFs greater than 10,000, please provide additional test data for PFs greater than 10,000 tcrjustify use of such PFs. *
Response
Virginia Electric and Power Company (Virginia Power) does not -require the use of protection factors greater than 10,000 in conjunction with our containment use only (CUO) Pressure-Demand Self-Contained Breathing Apparatus (SCBA).
- 2. In Attachment 1 of the submittal, the SCBA maintenance program for the "containment-use only" (CUO) units is described mainly in general terms. The staff needs more details about CUO SCBA maintenance.
- a. The site maintenance procedures and SCBA maintenance worker training program are "in accordance with MSA's [Mine Safety Appliances] training, and preventive maintenance and repair procedures." Please confirm if these vendor procedures are generic to open-circuit SCBAs, or are they specific for the CUO units. Also please describe aspects of the maintenance procedures and training programs which are specific to the CUO units and which differ from the generic MSA maintenance procedures and training program. This description should include different techniques (e.g., how to keep a hydrocarbon-free environment), routine inspection frequencies (e.g., 0-rings for regulator, steel cylinder hydrostatic tests}, or other routine maintenance activities.
Response
MSA and Virginia Power procedures require that all repairs to SCBA be made exclusively in accordance with "model specific" MSA guidance and by factory trained and authorized personnel. These procedures make it unacceptable for Virginia Power to maintain any SCBA equipment, including the containment-use only (CUO) units in question, in any manner other than as specified by MSA (e.g., all MSA SCBA are repaired in a hydrocarbon free environment). However, in the context of your question, MSA maintenance requirements are considered generic (applicable to all models) since specific maintenance procedures have not been developed for SCBA charged with 35% oxygen/65% nitrogen.
Page 1 of 4
..
- As stated in our initial authorization request, Virginia Power procedures do contain some directions specific to CUO SCBA (e.g., charging cylinders with 35% oxygen/65% nitrogen), however, these differences are necessitated by operational requirements (i.e., use of a dedicated compressor or cascade system), not by manufacturer guidance.
- b. Do the maintenance surveillance activities for SCBA units differ depending on whether brass or aluminum alloy components are used? If not, justify why not and provide a detailed maintenance/surveillance/inspection summary of any experience with CUO SCBAs (using enriched oxygen) with non-brass parts. The test data submitted in Attachments 2 and 3 of your March 27, 1997 request focused on *catastrophic SCBA failures, while this question is directed at a program for assessing chronic degradation (e.g., accelerated corrosion) of aluminum alloy parts and material used in an enriched oxygen environment.
Response
MSA does not direct that maintenance surveillance activities differ for SCBA units based upon whether brass or aluminum alloy components are used.
Virginia Power believes, and MSA agrees, that: 1.) the current inspection and maintenance frequencies specified are adequate to monitor SCBA material condition, and 2.) that the percentage increase of oxygen from 21 to 35 percent should not cause any significant increased rate of degradation in either brass, aluminum, or SCBA softgoods components.
Virginia Power currently does not allow the use of 35% oxygen/65% nitrogen charged SCBA which contain aluminum parts, therefore no experience history can be provided for aluminum components. Chronic degradation (e.g.,
accelerated corrosion) due to substitution of aluminum parts for brass, as stated above, is not anticipated. All degradation (chronic or abrupt) will continue to be monitored by the inspection, maintenance, and problem reporting programs mandated by Virginia Power procedures.
- 3. Relative to the requirements of 10 CFR 20.1703(a)(3)(v) (medical fitness evaluation), describe any special, additional information provided to the medical doctor for an evaluation of a worker who enters containment using an SCBA. If no special distinction is made among SCBA users, then justify why not, given the challenging containment environment. Have any site workers been approved for routine SCBA use, but not for in-containment use? If so, give the percentage of rejected versus approved workers.
Response
Virginia Power requires annual respiratory physicals be performed under the direct supervision of a licensed physician. The first step in this process is the completion of a detailed medical history form. The information on this form, in conjunction with follow-up questions and the actual physical examination, Page 2 of 4
- supply the information necessary for the physician to make decisions concerning each employee's ability to enter containment. If temporary or permanent containment access restriction is indicated, then a Medical Testing Form is completed and forwarded to the employee in question and appropriate supervision.
Restriction from containment entry due to inability to wear SCBA for medical reasons is rare (i.e., < 1%). It is more common for employees to be excluded from entering containment due to overall health conditions that would be aggravated by the containment environment itself (i.e., high temperature, subatmospheric pressure, confined spaces). Examples of these restricting health conditions include inner ear problems, heart conditions, and muscular injuries.
Discussions with Company medical personnel indicate that there are currently
- -only two individuals at North Anna and Surry Power Stations who are approved to wear SCBA outside of containment (for emergency purposes), but are not allowed to make subatmospheric containment entries (wearing GUO SCBA).
One individual has insulin dependent diabetes, a condition that can result in the onset of insulin shock, especially under high stress conditions (e.g., containment heat and humidity). The other individual has advanced problems from sarcoidosis. Again, it is not the SCBA that is the limiting factor. Rather it is the concern that in the event of a medical emergency, help would be delayed due to restricted access I egress.
- 4. Relative to the user fit testing requirements, what pass-fail criteria is used to ascertain an acceptable fit? The NRC staff finds the guidance in 288.2-1992 acceptable -- for a positive-pressure, tight-fitting respirator, a fit factor of at least 100 should be obtained. What percentage of fit-testers for SCBA use have failed the existing site's fit testing criteria?
Response
Virginia Power fit testing procedures specify a minimum fit factor of 1000 (i.e., a safety factor of 20 applied to a full facepiece negative pressure respirator).
Additionally, Virginia Power does follow the guidance of ANSI 288.2-1992 in requiring fit tests for all tight-fitting respirators worn regardless of mode (e.g.,
individuals are required to obtain a satisfactory fit test even if the only tight-fitting respirator they may wear is a positive pressure device such as SCBA).
Virginia Power uses the MSA Ultravue facepiece available in both hycar rubber and silicone in small, medium, and large sizes. This combination has proven itself extremely successful in fitting a wide variety of potential employees (i.e.,
100%).
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5.
- The CUO SCBAs are intended to be available for "emergency use." Does this include in-containment firefighting? If so, what prevents the temperature "limit" of 135 degrees Fahrenhl:lit (to prevent possible 0-ring failures during initial regulator startup) from being exceeded in containment?
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Response
Virginia Power intends, pending NRC approval, to allow the use of MSA Ultralite or Custom 4500 SCBA charged with 35% oxygen/65% nitrogen for containment firefighting. We intend to procedurally restrict Model 401 CUO SCBA to routine and emergency uses exclusive of fire fighting. The reason for this is NFPA 1981 (1992 Edition) which contains a performance *requirement in Appendix A (Heat and Flame Test). This stipulation increases the required regulator supplied flow rate from 40 Umin. to 100 Umin. The MSA Model 401 SCBA was designed before this requirement came into being. The MSA Ultralite and Custom 4500 do meet the-100 Umin. flow requirement.
Virginia Power believes the 135 degrees Fahrenheit "limit" (to prevent possible 0-ring failures during initial regulator startup) is not a problem for the following reasons:
- CUO SCBA are staged outside of containment in a room temperature environment. In the event of a fire in containment under vacuum, CUO SCBA use would be initiated before ambient temperatures exceeded 135 degrees Fahrenheit.
- 135 degrees Fahrenheit, as used by NASA in their Test Report, was not a failure temperature. It was the temperature that they did not test beyond, therefore conservatively limiting their approval to 135 degrees Fahrenheit.
- NASA, during their Compressive Heating Tests, used a method of rapidly pressurizing the test components (an impact valve) that significantly exceeded the speed at which a human can open the SCBA handwheel (i.e.,
140 versus 480 milliseconds). This test conservatism was introduced to explore worst case scenario situations, but was not meant to simulate a real world activity.
- Pre-tes~ temperatures of test articles (i.e., SCBA components) actually reached temperatures as high as 154 degrees Fahrenheit (with no failure evident). NASA post-test inspections revealed "no signs of ignition" (emphasis added) on 0-rings or flexhose.
- The Lawrence Livermore National Laboratory engineering staff evaluated the potential for incident (safety concern from fire/explosion, etc.) before performing flame testing of the MSA SCBA in question and concluded that
there is no significant hazard increase because of the change from 20% to 35% oxygen."
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