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| | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | page count = 7 | | | page count = 7 |
| | | project = TAC:M69428 |
| | | stage = RAI |
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| .Mr. | | .Mr. |
| Cross: | | Cross: |
| By: letter dated January 31, 1996, Duquesne Light Company (DLC) submitted the plant-specific summary report in response to the Unresolved Safety. Issue (USI) | | By: {{letter dated|date=January 31, 1996|text=letter dated January 31, 1996}}, Duquesne Light Company (DLC) submitted the plant-specific summary report in response to the Unresolved Safety. Issue (USI) |
| A-46 program at Beaver Valley Power Station, Unit No. 1 (BVPS-1). The.NRC staff..has reviewed the summary report and -has. determined that additional information is required to complete its review of DLC's USI A-46 program. The additional information we require to complete our review of DLC's USI A-46 program for BVPS-1 is described in the enclosed RAI. Please provide DLC's response to this RAI within 120 days of receipt of this -letter to enable us to complete our review in a timely manner. | | A-46 program at Beaver Valley Power Station, Unit No. 1 (BVPS-1). The.NRC staff..has reviewed the summary report and -has. determined that additional information is required to complete its review of DLC's USI A-46 program. The additional information we require to complete our review of DLC's USI A-46 program for BVPS-1 is described in the enclosed RAI. Please provide DLC's response to this RAI within 120 days of receipt of this -letter to enable us to complete our review in a timely manner. |
| Please contact me at (301) 415-1409 if you have any questions regarding this issue. | | Please contact me at (301) 415-1409 if you have any questions regarding this issue. |
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| ==Dear Mr. Cross:== | | ==Dear Mr. Cross:== |
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| By letter dated January 31, 1996, Duquesne Light Company (DLC) submitted the plant-specific summary report in response to the Unresolved Safety Issue (USI) | | By {{letter dated|date=January 31, 1996|text=letter dated January 31, 1996}}, Duquesne Light Company (DLC) submitted the plant-specific summary report in response to the Unresolved Safety Issue (USI) |
| A-46 program at Beaver Valley Power Station, Unit No.1 (BVPS-1). The NRC staff has reviewed the summary report and has determined that additional information is required to complete its review of DLC's USI A-46 program. The additional information we require to complete our review of DLC's USI A-46 program for BVPS-1 is described in the enclosed RAI. Please provide DLC's response to this RAI within 120 days of receipt of this letter to enable us to complete our review in a timely manner. | | A-46 program at Beaver Valley Power Station, Unit No.1 (BVPS-1). The NRC staff has reviewed the summary report and has determined that additional information is required to complete its review of DLC's USI A-46 program. The additional information we require to complete our review of DLC's USI A-46 program for BVPS-1 is described in the enclosed RAI. Please provide DLC's response to this RAI within 120 days of receipt of this letter to enable us to complete our review in a timely manner. |
| Please contact me at (301) 415-1409 if you have any questions regarding this issue. | | Please contact me at (301) 415-1409 if you have any questions regarding this issue. |
Letter Sequence RAI |
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MONTHYEARML20118B2831992-09-22022 September 1992 Responds to Suppl 1 to GL 87-02 Re SQUG Resolution of USI A-46.Util Commits to Utilize Methodology in Rev 2 to Generic Implementation Procedure for median-centered & Conservative Design in-structure Response Spectra Project stage: Other ML20127P1871992-11-20020 November 1992 Forwards Safety Evaluation Accepting Util Proposed Implementation Schedule to Use SQUG Commitments & Implementation Guidance Described in GIP-2 Project stage: Approval ML20097C8181996-01-31031 January 1996 Forwards USI A-46 Seismic Evaluation Rept for BVPS Unit 1 & USI A-46 Relay Evaluation Rept for BVPS Unit 1 for Resolution of USI A-46,in Response to GL 87-02 Project stage: Other ML20133G1641997-01-10010 January 1997 Forwards RAI Re NRC Review of Util plant-specific Summary Rept in Response to USI A-46 Program at Plant Project stage: RAI ML20141F2631997-05-16016 May 1997 Forwards Response to 970110 RAI Re Unresolved Safety Issue A-46 for Beaver Valley Unit 1.Calculations,also Encl Project stage: Other ML20216B2521998-03-0404 March 1998 Forwards RAI Re Summary Rept Concerning Verification of Seismic Adequacy of Mechanical & Electrical Equipment for Plant,Unit 1.Response Requested within 90 Days of Receipt of Ltr Project stage: RAI L-98-109, Forwards Response to NRC 980304 RAI Re USI A-46 for Unit 1. Schedule for Completion of Future Actions Described in Encl Is by Completion of Unit 1 13th Refueling Outage,As Indicated in Util to NRC1998-06-0202 June 1998 Forwards Response to NRC 980304 RAI Re USI A-46 for Unit 1. Schedule for Completion of Future Actions Described in Encl Is by Completion of Unit 1 13th Refueling Outage,As Indicated in Util to NRC Project stage: Other ML20154M4501998-10-16016 October 1998 Informs That Encl RAI Was Transmitted by Facsimile on 981002 to F Ferri of Dlc for Use in Telcon on 981009.Memo & Attachment Do Not Convey Formal Request for Info or Represent NRC Staff Position Project stage: RAI ML20198A1301998-12-0909 December 1998 Forwards SE Re USI A-46 Program Implentation for Plant Unit 1.Staff Concludes Program Implementation Met Purpose & Intent of Criteria in Generic Implementation Procedure 2 & Suppl SER 2 for Resolution of USI A-46 Project stage: Approval 1997-05-16
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Category:CORRESPONDENCE-LETTERS
MONTHYEARIR 05000412/19990071999-10-21021 October 1999 Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System ML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates L-99-143, Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct1999-10-11011 October 1999 Informs That Subsequent Review of Approval Ltrs & SE for Relief Requests 1TYP-2-B5.40-1 (Rev 0),BV1-RV-AUG (Rev 1), BV2-RV-AUG (Rev 1),BV3-IWA-1 (Rev 1) & BV3-IWA-2 (Rev 1) Identified Erroneous Statements Which Dl Wishes to Correct L-99-152, Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections1999-10-11011 October 1999 Submits Relief Request BV3-N-533-1,rev 0,requesting Use of ASME Approved Code Case N-553-1, Alternative Requirements for VT-2 Visual Examination of Class 1,2 & 3 Insulated Pressure Retaining Bolted Connections ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr L-99-151, Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program1999-10-0707 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-412/99-07.Corrective Actions:Condition Repts Were Written for Listed Issues So That Repts Could Be Addressed Using BVPS Corrective Action Program ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified L-99-149, Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion1999-09-28028 September 1999 Informs NRC That Items Identified in 990629 Response to GL 98-01 Have Been Completed.Attached Table Submitted with Has Been Updated to Reflect Completion L-99-148, Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 9908171999-09-24024 September 1999 Notifies NRC of License Withdrawal of M Linch,License SOP-11478 IAW 10CFR50.74.M Linch Resigned from Employment at Bvps,Effective 990817 ML20212G0601999-09-23023 September 1999 Forwards Answer of Duquesne Light Co to Petition to Waive Time Limits & Suppl Comments of Local 29, Intl Brotherhood of Electrical Workers.Copies of Answer Have Been Served to Parties & Petitioner by e-mail or Facsimile ML20212C5521999-09-21021 September 1999 Forwards for Filing,Answer to Firstenergy Nuclear Operating Co & Pennsylvania Power Co in Opposition to Petition to Waive Time Limits & Suppl Comments of Local 29 Intl Brotherhood of Electrical Workers L-99-144, Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-031999-09-20020 September 1999 Forwards NRC Form 536 Which Addresses Util Proposed Operator Licensing Exam Schedule,In Response to Administrative Ltr 99-03 ML20212B3291999-09-16016 September 1999 Forwards for Filing,Petition to Waive Time Limits in 10CFR2.1305 & Supplemental Comments of Local 29,Intl Brotherhood of Electrical Workers Re Beaver Valley Power Station,Units 1 & 2 L-99-134, Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC1999-09-15015 September 1999 Provides Addl Info to Support 990617 LAR 127,proposing Mods to Heatup,Cooldown & Overpressure Protection Curves.Info Is Provided to Formally Docket Info Discussed During 990820 Telcon with NRC ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys L-99-138, Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d)1999-09-0303 September 1999 Forwards Rev 37 to Issue 4 for BVPS Physical Security Plan (PSP) (Base Plan,Safeguards Contingency Plan & Training & Qualification Plan).Changes to Plan Are Listed.Encls Withheld Per 10CFR2.790(d) L-99-136, Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls1999-09-0202 September 1999 Forwards Data Point Library (Dpl) Changes,Iaw Provisions of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6, Administrative Implementation Requirements. Ten Listed Dpls Have Specific Setpoint Values Removed,Per Unit 2 Dpls L-99-098, Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods1999-09-0202 September 1999 Forwards Proposed Changes to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Change Would Reduce Operations QA Program Description Commitments by Limiting Required Onsite Safety Committee Reviews of Mods L-99-137, Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 31999-08-31031 August 1999 Forwards Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing Program for Pumps & Valves. Encl 1 Provides Summary of IST Program Changes Which Have Been Incorporated Into Issue 3, Rev 3 L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl1999-08-31031 August 1999 Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl L-99-012, Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2,operations QA Program Description,Per 10CFR50.54(a)(3)(ii),including Description of Proposed Change,Reason for Change & Basis for Concluding Revised Program Satisfy 10CFR50,App B L-99-037, Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change1999-08-30030 August 1999 Forwards Proposed Change to Bvps,Units 1 & 2 Operations QA Program Description,Iaw 10CFR50.54(a)(3)(ii).Attachment 1 Further Describes Proposed Change & Identifies Reason for Change L-99-132, Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 21999-08-26026 August 1999 Forwards fitness-for-duty Program Six Month Rept for 990101-990630 for Bvps,Units 1 & 2 05000412/LER-1999-007, Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info1999-08-19019 August 1999 Forwards LER 99-007-00, Forced Shutdown Due to Inoperable EDG, Per 10CFR50.73(a)(2)(i).Rept Is Delayed Due to Util Needing Addl Three Days to Address Event Issues on Reportability & Provide Addl Safety Implications Info ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement L-99-127, Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel1999-08-17017 August 1999 Provides Response to NRC Ltr Requesting Review & Comment of NRC Reactor Vessel Structural Integrity Database by 990901.Inconsistencies Noted in Way Data Characterizes Condition of Reactor Vessel L-99-124, Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached1999-07-30030 July 1999 Requests Withdrawal of Editorial Changes That Do Not Pertain to Transfer of Operating Authority or Plant Ownership That Are Proposed in LARs 269 & 144.Revised mark-up License Pages Reflecting Changes,Attached L-99-121, Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements1999-07-28028 July 1999 Submits Data Point Library (Dpl) Changes,Iaw Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,rev 1,Section 3.6, Administrative Implementation Reqiurements L-99-118, Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 20011999-07-25025 July 1999 Forwards Response to NRC AL 99-02,request for Info Re Estimate of Number of New Licensing Actions Expected to Be Submitted in Fy 2000 & 2001 L-99-120, Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations1999-07-22022 July 1999 Forwards Annual Rept of Facility Changes,Tests & Experiments for BVPS Unit 1,IAW 10CFR50.59.Rept Provides Brief Description of Each Facility & Procedure Change & Summary of Safety Evaluations L-99-119, Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 9901221999-07-20020 July 1999 Forwards Rev 17 to UFSAR for Beaver Power Station,Unit 1. Submittal Reflects Changes to Facility & Procedures as Described in UFSAR That Were Completed During Annual Reporting Period Endinig 990122 L-99-113, Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by1999-07-15015 July 1999 Forwards Final,Typed TS Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by L-99-111, Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes1999-07-15015 July 1999 Forwards Revised Final Typed Pages for LARs 109 & 115, Previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115.With Summary of Editorial Changes L-99-112, Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl1999-07-14014 July 1999 Responds to NRC Questions Made During 990518 Meeting with Util Re LARs 220 & 88,for Bvps,Units 1 & 2.Copy of Ltr DLC-99-743,which Is non-proprietary Version of DLC-96-310 & Westinghouse Technical Bulletin ESBU-TB-96-07-R0 Also Encl L-99-110, Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.61999-07-14014 July 1999 Forwards Changes to ERDS for Unit 1,IAW Requirements of 10CFR50,App E,Section VI.3.a & NUREG-1394,Rev 1,Section 3.6 ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed L-99-105, Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves1999-07-0808 July 1999 Forwards Response to NRC 990420 RAI Re Previous Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective L-99-109, Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-62301999-07-0707 July 1999 Forwards Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999, IAW ASME Boiler & Pressure Vessel Code,Section Xi,Article IWA-6230 L-99-108, Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC1999-07-0707 July 1999 Requests Withdrawal of Change Proposed for TS Bases Page B 3/4 2-2 from LARs 1A-262 & 2A-135,originally Submitted by Licensee to NRC L-99-104, Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl1999-06-29029 June 1999 Responds to GL 98-01,Suppl 1, Y2K Readiness at Nuclear Power Plants. Disclosure Rept Encl L-99-093, Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.51999-06-25025 June 1999 Provides Response to RAI on Proposed Change to Operations QA Program Description.Attachment 2 Provides Revised Markup for Proposed Changes to Affected UFSAR Section 17.2.5 L-99-102, Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl1999-06-22022 June 1999 Forwards Typed,Final TS Pages for LARs 259 & 131.Summary of Description of Plant Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages,Encl L-99-101, Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal1999-06-22022 June 1999 Submits Response to NRC Oral RAI Concerning Qualifications for Senior Nuclear Executive Ref in 10CFR50.80 Submittal L-99-062, Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages1999-06-17017 June 1999 Forwards Final TS Pages for LARs 262 & 135,including Summary Description of Plants Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARIR 05000412/19990071999-10-21021 October 1999 Refers to Special Team Insp 50-412/99-07 Conducted from 990720-29 & Forwards Nov.Two Violations Identified.First Violation Involved Failure to Implement C/A to Prevent Biofouling of Service Water System ML20217M1591999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217C6741999-10-0808 October 1999 Forwards RAI Re Licensee 970128 Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, . Response Requested within 60 Days of Receipt of Ltr ML20217E0301999-10-0707 October 1999 Forwards Insp Repts 50-334/99-06 & 50-412/99-06 on 990809-13 & 990823-27.Violation Noted Involving Failure to Correctly Translate Design Change Re Pertinent Operating Logs & Plant Equipment Labeling ML20212K8071999-09-30030 September 1999 Informs That on 990916,NRC Staff Completed mid-cycle Plant Performance Review (PPR) of Facility.Staff Conducted Reviews of All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility ML20216J9621999-09-30030 September 1999 Forwards Insp Repts 50-334/99-05 & 50-412/99-05 on 990725-0904.Two Violations Noted & Being Treated as Ncvs.One Violation Re Failure to Follow Operation Manual Procedure Associated with Configuration Control Identified ML20212M2661999-09-30030 September 1999 Forwards Order Approving Transfer of Licenses for Beaver Valley from Dlc to Pennsylvania Power Co & Approving Conforming Amends in Response to 990505 Application ML20211Q3431999-09-0808 September 1999 Informs That During 990903 Telcon Between L Briggs & T Kuhar,Arrangements Were Made for NRC to Inspect Licensed Operator Requalification Program at Plant,Unit 1.Insp Planned for Wk of 991115 ML20211Q5601999-09-0707 September 1999 Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys ML20211A5111999-08-18018 August 1999 Forwards Insp Repts 50-334/99-04 & 50-412/99-04 on 990613- 990724.One Violation Noted & Treated as Non-Cited Violation Involved Failure to Maintain Containment Equipment Hatch Closed During Fuel Movement ML20209G5701999-07-12012 July 1999 Discusses Closure of TACs MA0525 & MA0526 Re Response to RAI Concerning GL 92-0,Rev 1,Suppl 1, Rv Structural Integrity. Info in Rvid Revised & Released as Ver 2 as Result of Review of Response ML20207H6621999-07-0808 July 1999 Forwards RAI Re Util 981112 Response to IPEEE Evaluations for Plant,Units 1 & 2.RAI Was Discussed During 990628 Telcon in Order to Ensure Clear Consistent Understanding by All Parties of Info Needed ML20209D8191999-07-0707 July 1999 Forwards Insp Repts 50-334/99-03 & 50-412/99-03 on 990502- 0612.No Violations Noted.Program for Maintaining Occupational Exposures as Low as Reasonably Achievable (ALARA) & for Training Personnel,Generally Effective ML20207G2611999-06-0707 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart IR 05000412/19980091999-05-26026 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-412/98-09 ML20195C4461999-05-21021 May 1999 Forwards Insp Repts 50-334/99-02 & 50-412/99-02 on 990321-0501.No Violations Were Identified.Licensee Conduct of Activities at Beaver Valley Power Station Characterized by Safe Conduct of Activities During Refueling Outage ML20206P1241999-05-14014 May 1999 Refers to Proposed Changes Submitted by Dl on 990316 to BVPS QA Program Described in BVPS-2 Ufsar,Chapter 17.2.Forwards RAI Re Proposed QA Program Changes ML20206N3161999-05-0606 May 1999 Responds to Ltr to NRC on Continued Events Re Transfer of Generation Assets Between Dl & Firstenergy.Info Will Be Considered as NRC Monitor Pending License Transfer Application of Bvps,Units 1 & 2 & Pnpp ML20206H7931999-04-30030 April 1999 Ack Receipt of 990426 Request for Enforcement Discretion & 990427 Withdrawal of Request for Enforcement Discretion. Resolution Documented.Enforcement Discretion Not Necessary ML20206B2751999-04-22022 April 1999 Forwards Insp Repts 50-334/99-01 & 50-412/99-01 on 990207- 0320.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML20206A8381999-04-20020 April 1999 Forwards Reactor Operator Initial Exam Rept 50-412/99-301 on 990322-25.All Three Reactor Operator Applicants Passed. Initial Written Exam Submittal Was Determined Not to Meet NRC Guidelines in Certain Instances ML20205R9071999-04-20020 April 1999 Forwards Second Request for Addl Info Re Response to GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves, for Beaver Valley Power Station,Units 1 & 2 ML20205Q8311999-04-14014 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-334/98-11 & 50-412/98-11 Issued on 990225.Actions Will Be Examined During Future Insp of Licensed Program ML20205L0341999-04-0909 April 1999 Forwards SER Accepting Util 971209 & 980729 Submittal of Second 10-year Interval ISI Program Plan & Associated Relief Requests for Beaver Valley Power Station,Unit 2.TER Also Encl ML20205P2431999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Ltr Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival ML20205K0901999-04-0505 April 1999 Informs of Individual Exam Result on Initial Retake Exam Conducted on 990322-25 at Licensee Facility.Three Individuals Were Administered Exam & All Three Passed. Forwards Encl Re Exam.Without Encl ML20205R1791999-03-30030 March 1999 Responds to Issue Re Generic Implication of part-length Control Rod Drive Mechanism Housing Leak at Praire Island, Unit 2 & Beaver Valley Power Station,Units 1 & 2 ML20205C0301999-03-26026 March 1999 Informs That Util Responses to GL 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling & Containment Heat Removal Pumps Acceptable ML20204D7371999-03-16016 March 1999 Advises That RW Lindsey Authorized to Administer Initial Written Exams to Sh Cencic,Tf Lardin & Ta Pittas on 990322. Region I Operator Licensing Staff Will Administer Operating Tests ML20207E0201999-02-25025 February 1999 Forwards Insp Repts 50-334/98-11 & 50-412/98-11 on 981227- 990206 & Forwards Notice of Violations Re Uncontrolled Reduction of Main Condenser Vacuum ML20203D0691999-02-10010 February 1999 Forwards SE Accepting Approval of Proposed Revs to Plant QA Program Description in Chapter 17.2 of Updated Fsar,Per Util 981224 Submittal ML20206U3011999-02-0505 February 1999 Forwards Insp Repts 50-334/98-09 & 50-412/98-09 on 981116-1217 & Nov.Violation Identified Re Inadequate Design Control in Unit 2 Dc Voltage Drop Calculation ML20203A0811999-02-0404 February 1999 Forwards Request for Addl Info Re Review of Beaver Valley Power Station,Unit 1 License Amend to Allow one-time Extension of Steam Generator Insp Interval ML20199E6681999-01-14014 January 1999 Forwards RAI Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, for Plant,Units 1 & 2 ML20199F1961999-01-13013 January 1999 Forwards Insp Repts 50-334/98-10 & 50-412/98-10 on 981115-1226.No Violations Noted.Informs That Overall Fire Protection Program Functioning Well ML20199F5101998-12-29029 December 1998 Discusses Third 10-year Interval ISI Program Plan & Associated Relief Requests for BVPS-1 Submitted by Dlc on 970917 & 980618.Informs That NRC Has Adopted Ineel Recommendations in TER INEEL-98-00893.Forwards SE & TER ML20198K5911998-12-24024 December 1998 Forwards Emergency Response Data Sys Implementation Documents Which Include Data Point Library Updates for Fermi (Number 268),Peach Bottom (Number 269) & Beaver Valley (Number 270).Without Encls ML20198K8251998-12-21021 December 1998 Forwards SER Granting Licensee 980611,as Suppl 981015 Pump Relief Request PRR-5 for Third 10-year IST Interval for Beaver Valley Power Station,Unit 1 Pursuant 10CFR50.55(a)(f)(6)(i) ML20198B1301998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Beaver Valley Power Station mid-year Insp Resource Planning Meeting Held on 981110.Historical Listing of Plant Issues & Details of Insp Plan for Next 6 Months Encl ML20198A1301998-12-0909 December 1998 Forwards SE Re USI A-46 Program Implentation for Plant Unit 1.Staff Concludes Program Implementation Met Purpose & Intent of Criteria in Generic Implementation Procedure 2 & Suppl SER 2 for Resolution of USI A-46 ML20196J2761998-12-0404 December 1998 Forwards Corrected Pages 17 & 18 of NRC Integrated Insp Repts 50-334/98-06 & 50-412/98-06 for Exercise of Enforcement Discretion ML20196H3051998-12-0202 December 1998 Forwards Insp Repts 50-334/98-06 & 50-412/98-06 on 981004-1114.No Violations Noted.Conduct of Activities at Beaver Valley Power Station Facilities Characterized by Safe Plant Operations ML20196H2781998-12-0202 December 1998 Forwards Insp Repts 50-334/98-08 & 50-412/98-08 on 981026- 30.No Violations Noted.Plant Operations Witnessed by Team Were Conducted in Safe & Controlled Manner ML20196G9921998-12-0101 December 1998 Forwards Ltrs from Fk Koob, to JW Pack & CF Wynne Re Plant Deficiencies Assessed During 981006 Exercise Against Hancock County,Wv & Beaver County,Pa,Respectively ML20196D4371998-11-25025 November 1998 Discusses Concerns Re Announced Asset Transfer Between Firstenergy Corp & Duquesne Light Co ML20196A7101998-11-24024 November 1998 Forwards Notice of Withdrawal of Amend to License NPF-73. Proposed Change Would Have Extended on one-time Only Basis, Surveillance Interval for TSs 4.8.1.1.1.b & 4.8.1.2 Until First Entry Into Mode 4 Following Seventh Refueling Outage ML20195K3331998-11-18018 November 1998 Informs That Effective 981214,DS Collins Will Become Project Manager for Beaver Valley Power Station,Units 1 & 2 IR 05000334/19980041998-11-13013 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-334/98-04 & 50-412/98-04 Issued on 980915.C/As Will Be Examined During Future Insp of Licensed Program ML20195J2941998-11-12012 November 1998 Forwards Safety Evaluation Re First & Second 10-year Interval Inservice Insp Request for Relief ML20155K4041998-11-0505 November 1998 Forwards Insp Repts 50-334/98-07 & 50-412/98-07 on 981006- 07.No Violations Noted.Overall Performance of Emergency Response Organization Was Good 1999-09-08
[Table view] |
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-January 10, 1997 l Mr! J. E. Cross t
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SUBJECT:
fREQUESTFORADDITIONALINFORMATION(RAI)-BEAVERVALLEYPOWER .
..f * , , ' STATION,* UNIT NO.1, UNRESOLVED SAFETY ISSUE A-46 (TAC NO. M69428) '
Dear,
.Mr.
Cross:
By: letter dated January 31, 1996, Duquesne Light Company (DLC) submitted the plant-specific summary report in response to the Unresolved Safety. Issue (USI)
A-46 program at Beaver Valley Power Station, Unit No. 1 (BVPS-1). The.NRC staff..has reviewed the summary report and -has. determined that additional information is required to complete its review of DLC's USI A-46 program. The additional information we require to complete our review of DLC's USI A-46 program for BVPS-1 is described in the enclosed RAI. Please provide DLC's response to this RAI within 120 days of receipt of this -letter to enable us to complete our review in a timely manner.
Please contact me at (301) 415-1409 if you have any questions regarding this issue.
Sincerely,
/S/
Donald S. Brinkman, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
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..... January 10, 1997 Mr. J. E. Cross President - Generation Group i Duquesne Light Company
. Post Office Box 4 Shippingport, PA 15077 i
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) - BEAVER VALLEY POWER a STATION, UNIT NO. 1, UNRESOLVED SAFETY ISSUE A-46 (TAC NO. M69428)
Dear Mr. Cross:
By letter dated January 31, 1996, Duquesne Light Company (DLC) submitted the plant-specific summary report in response to the Unresolved Safety Issue (USI)
A-46 program at Beaver Valley Power Station, Unit No.1 (BVPS-1). The NRC staff has reviewed the summary report and has determined that additional information is required to complete its review of DLC's USI A-46 program. The additional information we require to complete our review of DLC's USI A-46 program for BVPS-1 is described in the enclosed RAI. Please provide DLC's response to this RAI within 120 days of receipt of this letter to enable us to complete our review in a timely manner.
Please contact me at (301) 415-1409 if you have any questions regarding this issue.
Sincerely,
.h .
Donald S. Brinkman, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-334
Enclosure:
RAI cc w/ enc 1: See next page
l a
l J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2 cc:
Jay E. Silberg, Esquire Bureau of Radiation Protection 1 Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street, NW. Environmental Resources Washington, DC 20037 ATTN: R. Barkanic Post Office Box 2063 R. K. Brosi, Manager Harrisburg, PA 17120 Nuclear Safety Department (BV-A)
Duquesne Light Company _ i Beaver Valley Power Station Mayor of the Borrough of PO Box 4 Shippingport Shippingport, PA 15077 Post Office Box 3 Shippingport, PA 15077 ,
Commissioner Roy M. Smith 1 West Virginia Department of Labor Regional Administrator, Region I Building 3, Room 319 U.S. Nuclear Regulatory Commission Capitol Complex 475 Allendale Road Charleston, WVA 25305 King of Prussia, PA 19406 John D. Borrows Resident Inspector Director, Utilities Department U.S. Nuclear Regulatory Commission !
Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport, PA 15077 Columbus, OH 43266-0573 Director, Pennsylvania Emergency Duquesne Light Company Management Agency Beaver Valley Power Station Post Office Box 3321 PO Box 4 Harrisburg, PA 17105-3321 Shippingport, PA 15077 ATTN: S. C. Jain, Vice President i Ohio EPA-DERR Nuclear Services (BV-A)
ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 l Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 ,
1 -
- Reauest For Additional Information Reaardina Unresolved Safety Issue A-46 '
j Beaver Valley Power Station. Unit No. 1 j Docket No. 50-334 i
I i'
Reference:
Letter (and attachments) from Duquesne Light Company to USNRC,
] " Summary Report for Resolution of USI A-46," January 31, 1996 i 1. On page 20 of your submittal, you state that "The length of all Hilti
! Kwik-bolts.is known by virtue of controlled procurement." Indicate whether the demand force in an anchor was compared against the bolt i
strength specified in Generic Implementation Procedure, Revision 2, (GIP-2) Table C.2-1, or the bolt strength corresponding to the actual bolt length from the Hilti catalog. If the Hilti Catalog allowable bolt loads were used, provide the basis for not using the GIP-2 allowable j '
l bolt loads.
I 2. You stated that thirty-one (31) tanks and heat exchangers were reviewed I and twenty-seven (27) were outliers, and most of the outliers were
! caused by anchorage problems. However, you did not state whether you -
i had reviewed the adequacy of the tanks and heat exchangers themselves
- assuming the anchorage was properly designed and installed. Provide i information regarding the adequacy of the tanks and heat exchangers
~i themselves in accordance with the criteria delineated in Chapter 7 of GIP-2.
4
- 3. Based.on the information provided by DLC, it is unclear as to how some l equipment were determined to meet the intent of the stated caveat. The i following questions pertain to Table 5.2 on meeting the intent of l caveats as described in Appendix B of GIP-2.
4 l a. For equipment FE-CDL-1A, FE-CDL-1B, PCC-FE-1A, and PCC-FE-18, you
- stated that the anchorage calculation is not yet complete but that
- the anchorage was adequate. State your basis for this conclusion.
- b. Transmitters FT-CH-124, FT-CH-127, and FT-CH-130 were mounted to j block walls with expansion anchors. You stated that you performed j analyses for these anchors and found them acceptable. Provide the criteria that you used for expansion anchors embedded in block walls and submit anchorage calculations for these three transmitters.
- c. For BAT-BKR-1, -2, -3, -4 and BAT-CHG-1, -2, -3, -4 provide a calculation for each type of equipment to demonstrate the seismic
- adequacy of these cabinets.
}
j Enclosure
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- d. For valves FCV-RC-455C1, C2, D1, and D2, discuss how these valves are equivalent in ruggedness to the check valves with regard to design adequacy during a seismic event.
- e. For flow indicators FI-CH-122A,124,127,130, and 150, FI-FW-100A/B/C, level recorders FR-MS-478, 488, and 498, LI-FW-474, 475, 476, 484, 485, and 486, discuss in detail how these components were qualified by the " rule of the box."
- f. For flow indicator FI-CH-122, provide the basis for concluding that the collapse of a lighting fixture located above this equipment will not adversely affect its function.
- g. For motor-operated valves MOV-106A and 114A, provide the basis for concludingithat the failure of the 1-inch steel pipe above the valves will not damage the valves.
- h. Discuss how the solenoid-operated valves SOV-MS-101A, B, and C were qualified by the " rule of box" with panels PNL-MS-101A, B and C respectively.
- i. For solenoid-operated valves S0V-RC-455C1, C2, D1 and 02, the clearance from the valve housing is approximately 1/16-inch to the adjacent PCV-RC-455C valve actuator. Provide additional informati:m to demonstrate that the S0Vs and the valve actuator would not respond out of phase and impact each other during an earthquake, as-described in the Bounding Spectrum Caveat 3 of Appendix B to GIP-2.
- j. Provide an analysis or a calculation to demonstrate the seismic adequacy of the cast-iron valve yokes for valves TV-MS-111A, B, and C.
- k. For control room air intake vent damper VS-D-40-1F, provide the basis for the statement that poor weld quality is judged to be structurally adequate.
- 4. In Table 5-3, it appears that the brief discussion and resolution of the outliers do not provide adequate information in characterizing the deficiencies and for evaluating acceptability of the proposed or implemented modifications. This observation is applicable to over 200 caveats -listed in Table 5.3. It is expected that, as GIP-2 specifies, the deficiencies and modifications have been thoroughly documented to allow an independent review. Provide documentation regarding the resolution of the outliers for equipment BAT-1, FCV-RC-455C1, FR-MS-478, HCV-CH-389, INV-VITBUS-1, PCV-RC-456, PNL-AMSAC, PNL-PR-HTR-A, RK-VS-E567, TRANS-1-8-N1, TV-CH-200A, VS-AD-9, VS-AFD-5, VS-D-4-8A, VS-F-57A, and WR-P-1A.
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- 5. Section 5.3.1.5 of the reference report states that the BVPS-1 air supply system is not seismically qualified for functionality. The resolution provided in Table 5.3.1.5 shows that there are seven air-operated valves (i.e., FCV-CH-122, FCV-FW-103A and B, HCV-MS-104, PCV-MS-101A, B and C) that require operator actions for use in the SQUG safe shutdown. Clarify how these operator actions could be performed within the allowable time frame and in a hazardous or unfamiliar environment.
- 6. Section 8 of the reference report states that "the unresolved outliers will be prioritized as to their safety significance and scope. If modifications are required, the implementation of modification and replacements will be scheduled during one of the next three BVPS-1 refueling outages." Discuss how the unresolved outliers will be ranked considering their safety significance and scope. Provide the results of the prioritization analysis, an actual schedule for completion of the outlier resolution and an assessment of the impact on plant safety in consideration of the proposed schedule for resolution.
- 7. In reference to Sections 2.2.1.5 and 2.3 of Attachment 2 to the reference report, the essential relays in the fire protection systems that are neither seismically qualified, nor included in the Seismic Qualification Utility Group (SQUG) database are listed in Table 2.1-1, as " FIRE PROT. - NO QTR." The report mentioned that these relays /contactors may be qualified by using a database other than the SQUG database. If so, identify the database, and the nature and the extent of the deviation from the GIP-2 and provide justification that the. database is acceptable for such applications.
- 8. In Section 2.2, the bad actor relays Westinghouse COM-5, and SG relays and General Electric HGA relays used at BVPS-1 are identified as outliers because of low seismic ruggedness chatter (in accordance with GIP-2 guidance). The section indicated that these relays are used as normally open contacts and, therefore, their seismic capacities exceed the demand level of relays used in that configuration. Provide the seismic qualification data for these relays to demonstrate that these relays have seismic capacity exceeding the seismic demand.
- 9. Referring to the in-structure response spectra provided in your 120-day response to the NRC's request in Supplement No. 1 to Generic letter 87-02, dated May 22, 1992, provide the following information:
- a. Identify structure (s) that have in-structure response spectra (5 percent critical damping) for elevations within 40 feet above the effective grade, which are higher in amplitude than 1.5 times the SQUG bounding spectrum.
. . . l e !
l
- b. With respect to the comparison of equipment seismic capacity and seismic demand, indicate which method in Table 4-1 of GIP-2 was used i
to evaluate the seismic adequacy for equipment installed on the i
corresponding floors in the structure (s) identified in Item (a) above. If you have elected to use method A in Table 4-1 of GIP-2, provide a technical justification for not using the in-structure response spectra provided in your 120-day response. It appears that
- some USI A-46 licensees are making an incorrect comparison between their plant's safe shutdown earthquake (SSE) ground motion response spectrum and the SQUG bounding spectrum. The SSE ground motion a
response spectrum for most nuclear power plants is defined at the plant foundation level. The SQUG bounding spectrum is defined at the free-field ground surface. For plants located at deep soil or rock sites, there may not be a significant difference between the ground motion amplitudes at the foundation level and those at the ground surface. However, for sites where a structure is founded on shallow soil, the amplification of the ground motion from the foundation level to the ground surface may be significant.
- c. For the structure (s) identified in Item (a) above, provide the in-structure response spectra designated according to the height
- above the effective grade. If the in-structure response spectra l 3
identified in the 120-day response to Supplement No. I to Generic '
Letter 87-02 were not used, provide the response spectra that were i actually used to verify the seismic adequacy of equipment within the i structures identified in Item (a) above. Also, provide a comparison of these spectra to 1.5 times the bounding spectrum.
i 2
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4 4
, . . ' ' ', O O -CO /9333Of - 3fo[
Page 2 December 20, 1996 U.S. Nuclear Regulatory Commission y j47g I
Element & Isotope: .See Attached Schedule
! Mode of Shipment: Truck, Closed Van, Exclusive Use Routing: US 23 to US 1181 Estimated Time and Date of Departure and Arrival:
See Attached Schedule A total of sixteen shipments are necessary to complete this project. The attached schedule identifies the first seven shipments currently scheduled. The remaining shipments and dates will be identified at a later date when scheduling arrangements have been determined. l I
Please contact me at (423) 743-9141, Ext. 1154 if you have questions or comments.
Sincerely, NUCLEAR FUEL SERVICES, INC. 1
,, >)
\
oseph Pugh Transportation & Waste Manager
/ka Enclosure I
I invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Arlington, Texas this 26th day of December 1996 l
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