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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:INCOMING CORRESPONDENCE
MONTHYEARL-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
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-99-151, 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
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
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-99-037, 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-99-012, 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-99-132, 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
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-99-111, 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-99-113, 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-99-112, 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
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
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-99-109, 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-99-104, 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
ML20196A6601999-06-16016 June 1999
Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1
ML20195H4651999-06-16016 June 1999
Forwards for Filing Answer of Firstenergy Corp in Opposition to Petition for Leave to Intervene of Local 29, Intl Brotherhood of Electrical Workers. Copies of Answer Have Been Served Upon Parties & Petitioner by e-mail
ML20195J5221999-06-16016 June 1999
Forwards Answer of Duquesne Light Co to Petition to Intervene of Local 29,International Brotherhood of Electrical Workers in Listed Matter.With Certificate of Svc
L-99-100, Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-1091999-06-15015 June 1999
Forwards Typed,Final TS Pages for LAR 109 Re Rcs.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages Is Provided in Attachment B-109
L-99-095, Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys1999-06-15015 June 1999
Provides Addl Info to Support LARs 262 & 135,in Response to NRC 990527 Verbal Request.Info Describes Performance of Unit 1 Rod Position Indication Sys & Provides Some Background Info Re Normal Operation of Sys
L-99-099, Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr1999-06-14014 June 1999
Requests Partial Withdrawal of LAR 120,which Requested Review of USQ Due to Increased Calculated Doses for Locked Rotor Event & Use of Unapproved Methodology for Evaluating Small Break LOCA Doses Involving W Natl Safety Advisory Ltr
ML20195H3731999-06-0303 June 1999
Forwards Petition to Intervene of Local 29,Intl Brotherhood of Electrical Workers in Matter of Firstenergy Nuclear Operating Co,For Filing
L-99-090, Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request1999-06-0202 June 1999
Forwards Summary Review Completed to Verify Adequacy of Design Basis Accident Thermal Overpressure Protection for BVPS Unit 2 Containment Penetrations,Per Request
L-99-086, Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 11999-05-28028 May 1999
Forwards Bvps,Unit 2 SG Exam Rept for Aug 1998.Rept Provided to Document Results of SG Eddy Current Exams Performed in Aug 1998.Summary of Insps Provided in Encl 1
L-99-089, Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)1999-05-28028 May 1999
Forwards Annual Financial Repts,Including Certified Financial Statements,Of Dqe,Firstenergy Corp,Ohio Edison Co,Pennsylvania Power Co,Cleveland Electric Illuminating Co & Toledo Edison Co,Iaw 10CFR50.71(b)
L-99-084, Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon1999-05-27027 May 1999
Forwards Revised marked-up TS & UFSAR Pages to 990303 LARs 259 & 131 Which Revised Qualifications for Operations Mgt & Incorporated Generic Position Titles in Ts.Encl Pages Incorporate NRC Requested Changes,Per Recent Telcon
L-99-082, Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS1999-05-17017 May 1999
Dockets Licensee Plan for Bvps,Unit 1,safety-related Small Bore Piping Evaluation Project Discussed in NRC 990311 Public Meeting at BVPS
L-99-071, Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS1999-05-12012 May 1999
Notifies of License Withdrawal for J Scott,License SOP-11481,due to Resignation from Employment at BVPS
1999-09-03
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059L4271990-09-0707 September 1990
Requests Approval for Use of Steam Generator Tube Plugs for Both Mechanical & Welded Applications
ML20059G0821990-09-0404 September 1990
Forwards Application for Amend to License DPR-66,consisting of License Change Request 180,changing Section 3.3.3.2 to Reduce Required Number of Operable Incore Detector Thimbles for Remainder of Cycle 8
ML20059F7551990-08-29029 August 1990
Responds to Unresolved Item 50-334/90-16-01 Noted in Insp Rept 50-334/90-16.Corrective Actions:Initial Training for Maint Group Personnel Responsible for Maintaining Supplied Air Respirators Will Be Supplemented W/Biennial Retraining
ML20059F1501990-08-29029 August 1990
Advises That Permanent Replacement Chosen for Plant Independent Safety Evaluation Group.Position Will Be Staffed Effective 900829
ML20028G8731990-08-29029 August 1990
Forwards fitness-for-duty Program Performance Data for Jan-June 1990,per 10CFR26.71
ML20059D3761990-08-24024 August 1990
Describes Cycle 3 Reload Design,Documents Util Review Per 10CFR50.59 & Provides Determination That No Tech Spec Changes or Unreviewed Safety Questions Involved.Reload Core Design Will Not Adversely Affect Safety of Plant
ML20028G8881990-08-24024 August 1990
Withdraws Operator License SOP-10731 (55-60749) Issued to K Gilbert,Who Resigned
05000412/LER-1990-007, Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued1990-08-23023 August 1990
Responds to NRC Re Deviation 50-412/90-12-01 Noted in Insp Rept 50-412/90-12.Corrective Actions:Procedure OM 2.20-4.I Revised to Require Removal of Flanges Following Drain Operations & LER 90-007-00 Issued
ML20058P7651990-08-14014 August 1990
Provides Info on Acceptability of Rescheduling Response to Reg Guide 1.97 Ser,Item 4b, Neutron Flux Monitoring Instrumentation. Rescheduling of Util Response Will Be Determined on or Shortly After Meeting W/Nrc
ML20059E0571990-08-10010 August 1990
Forwards Suppl 3 to Nonproprietary WCAP-12094 & Proprietary WCAP-12093, Evaluation of Pressurizer Surge Line Transients Exceeding 320 F for Beaver Valley Unit 2, for Review by 900901.Proprietary Rept Withheld (Ref 10CFR2.790(b)(4))
ML20059E7631990-08-0101 August 1990
Provides Results of Util Evaluation of Licensed Operator Requalification Exam Conducted During Wks of 900709 & 16. Crew That Failed to Meet Expected Performance Level Has Been Successfully Upgraded & re-evaluated to Be Satisfactory
ML20059B8141990-08-0101 August 1990
Requests Exemption from 10CFR26 Re Fitness for Duty Program & 10CFR73 Re Physical Protection of Plants & Matls Concerning Unescorted Access Requirements for Nuclear Generating Stations
ML20056A3471990-07-31031 July 1990
Responds to NRC Bulletin 90-001.Items 1 Through 5 of Requested Actions for Operating Reactors Completed
ML20056A1841990-07-27027 July 1990
Forwards Revised Methodology for Achieving Alternate Ac for Plant,Per 900720 Telcon
ML20055H2581990-07-25025 July 1990
Forwards Decommissioning Rept, Per 10CFR50.33(K) & 50.75(b)
ML20055F7061990-07-0909 July 1990
Responds to NRC Re Dcrdr Requirements as Specified in Suppl 1 to NUREG-0737.DCRDR Corrective Actions Implemented & Mods Determined to Be Operational Prior to Startup Following Seventh Plant Refueling Outage
ML20055D3871990-07-0202 July 1990
Provides Info Re long-term Solution to Action Item 3 of NRC Bulletin 88-008,per 890714 & s.Util Will Continue to Monitor Temp in Affected Lines & Evaluate Results
ML20058K5031990-06-29029 June 1990
Discusses Use of Emergency Diesel Generators as Alternate Ac Source at multi-unit Sites,Per Licensee .Emergency Diesel Generator Load Mgt Methodology Evaluated to Meet Listed Criteria
ML20044A3661990-06-21021 June 1990
Forwards Application for Amend to License NPF-73,consisting of Tech Spec Change Request 44,changing Stroke Time to 60 for Inside Containment Letdown Isolation Valves.Change Determined Safe & Involves No Unreviewed Safety Issue
ML20043G6811990-06-14014 June 1990
Forwards Application for Amends to Licenses DPR-66 & NPF-73, Revising Tech Specs Re Electrical Power Sys - Shutdown & Ac & Dc Distribution - Shutdown
ML20043H9341990-06-14014 June 1990
Forwards Issue 1 to Rev 4 to Inservice Testing Program for Pumps & Valves. Issue 1 Removes Relief Requests Requiring Prior NRC Approval & Adds Certain Program Changes Permitted by ASME XI & Generic Ltr 89-04
ML20043G5981990-06-12012 June 1990
Forwards Monthly Operating Repts for May 1990 for Beaver Valley Units 1 & 2 & Revised Rept for Apr 1990 for Beaver Valley Unit 1
ML20043G6851990-06-12012 June 1990
Forwards Application for Amend to License DPR-66,consisting of Proposed OL Change Request 176,revising Tech Specs to Replace Current Single Overpressure Protection Setpoint W/ Curve Based on Temp
ML20043G7941990-06-12012 June 1990
Responds to NRC 900524 Request for Addl Info Re Proposed Operating License Change Request 156.Clarification of Magnitude of Confidence Level of Westinghouse Setpoint Methodology,As Specified in WCAP-11419,encl
ML20043G8001990-06-11011 June 1990
Forwards Application for Amend to License NPF-73,consisting of Proposed Operating License Change Request 41.Amend Deletes Surveillance Requirement 4.4.9.3.1.d
ML20043H0291990-06-11011 June 1990
Forwards Application for Amend to License NPF-73,consisting of Proposed OL Change Request 40,modifying Heatup & Cooldown Curves Applicable to 10 EFPYs Per WCAP-12406 Re Analysis of Capsule U from Radiation Surveillance Program
ML20043F5251990-06-0707 June 1990
Requests Temporary Waiver of Compliance from Tech Spec Limiting Condition for Operation Re Operability of Containment Isolation Valves During Quarterly Slave Relay Testing.Evaluation to Support Request Encl
ML20043F1361990-06-0404 June 1990
Advises That Chemistry Manual Chapter 5P1, Enhanced Primary to Secondary Leakrate Monitoring Program for Unit 1,per 880328 Request to Recommit to Item C.1 of NRC Bulletin 88-002
ML20043B5971990-05-18018 May 1990
Advises of Delay in Hiring Independent Safety Evaluation Group Replacement to Maintain Five Permanent Personnel Onsite,Per Tech Spec 6.2.3.2.Replacement Will Be Provided within 30 Days of Retirement of Engineer on 900531
ML20043B0511990-05-15015 May 1990
Responds to Telcon Request for Addl Info Re Elimination of Snubbers on Primary Component Supports.Probability of Case B/G Event Extremely Small & Does Not Represent Realisitic Scenario
ML20043B1921990-05-11011 May 1990
Forwards Cycle 8 & Cycle 2 Core Operating Limits Rept,Per Tech Spec 6.9.1.14
ML20042G9761990-05-0808 May 1990
Responds to NRC 900226 Ltr Re Violations Noted in Insp Repts 50-334/89-80 & 50-412/89-80.Corrective Action:Maint Work Request Program Being Upgraded to Include Responsibilities of Nuclear Const Dept & Will Be Issued by 900601
ML20042G8541990-05-0303 May 1990
Forwards Technical Review,Audit Summary & Operability Assessments Re Potentially Invalid Leak Detection Tests Used as Alternative for Amse Section XI Hydrostatic Tests
ML20042G9071990-05-0101 May 1990
Forwards Annual Financial Repts for Duquense Light Co,Ohio Edison Co,Pennsylvania Power Co,Centerior Energy Corp & Toledo Edison Co,Per 10CFR50-71(b)
ML20042F1381990-04-30030 April 1990
Advises That Final SER for Implementation of USI A-46 Will Be Delayed Until Late 1990
ML20042F0991990-04-20020 April 1990
Forwards Response to Request for Addl Info Re Second 10 Yr ISI Program
ML20012F5951990-04-10010 April 1990
Forwards Monthly Operating Repts for Mar 1990 & Revised Operating Data Rept & Unit Shutdown & Power Reductions Sheets for Jan 1990
ML20042E1471990-04-0404 April 1990
Forwards Application for Amends to Licenses DPR-66 & NPF-73, Consisting of License Change Request 174/36,updating Staff Titles to Reflect Nuclear Group Organization
ML20012F6021990-03-30030 March 1990
Submits Supplemental Response to Station Blackout Rule for Plant,Per NUMARC 900104 Ltr.Summary of Changes to Condensate Inventory of Dhr,Effects of Loss of Ventilation, Control Room HVAC & Reactor Coolant Inventory Listed
ML20012E3091990-03-23023 March 1990
Forwards Response to 900308 Request for Addl Info on Reg Guide 1.97 Re Variable for Steam Generator wide-range Level Instrumentation
ML20012E3451990-03-23023 March 1990
Submits Addl Info for Exemption from General Design Criteria GDC-57,including Background Info Describing Sys Operation & Addl Bases for Exemption Request.Simplified Recirculation Spray Sys Drawings Encl
ML20012D6491990-03-19019 March 1990
Requests Retroactive NRC Approval of Temporary Waiver of Compliance Re Tech Spec Limiting Condition for Operation 3.8.2.1 on Ac Vital Bus Operability.Sts Will Be Followed When Inverters Not Providing Power to Vital Bus
ML20012E4091990-03-16016 March 1990
Forwards Inservice Insp 90-Day Rept,Beaver Valley Power Station Unit 1,Outage 7, for 880227-891221,per Section XI of ASME Boiler & Pressure Vessel Code 1983 Edition Through Summer 1983 Addenda,Section XI
ML20012D6181990-03-15015 March 1990
Responds to NRC 900215 Ltr Re Violations Noted in Insp Repts 50-334/89-23 & 50-412/89-22.Corrective Actions:Safety Injection Signal Reset & Plant Returned to Presafety Injection Conditions & Crew Members Counseled
ML20042D7401990-03-14014 March 1990
Forwards Corrected Annual Rept of Number of Personnel Receiving Greater than 100 Mrem & Associated Exposure by Work Function at Plant for CY89.
ML20012D5801990-03-13013 March 1990
Forwards Correction to First 10-yr Inservice Insp Program, Rev 2 to Relief Request BV2-C6.10-1 Re Recirculation Spray Pump - Pump Casing Welds & Relief Request Index
ML20012D6221990-03-13013 March 1990
Forwards Response to Generic Ltr 89-19, Resolution to USI A-47. Recommends All Westinghouse Plant Designs Provide Automatic Steam Generator Overfill Protection to Mitigate Main Feedwater Overfeed Events
ML20012C1791990-03-0909 March 1990
Responds to NRC 900207 Ltr Re Deviations Noted in Insp Repts 50-334/89-25 & 50-412/89-23.Corrective Actions:Written Request Initiated to Identify Unit 2 post-accident Monitoring Recorders in Control Room & Recorders Labeled
ML20012E0911990-03-0505 March 1990
Lists Max Primary Property Damage Insurance Coverages for Plant,Per 10CFR50.54(w)(2)
ML20012B7051990-03-0202 March 1990
Responds to NRC 900131 Ltr Re Violations Noted in Insp Repts 50-334/90-05 & 50-412/90-04.Requests Withdrawal of Violation Re Stated Transport Problem & Reclassification as Noncompliance,Per 10CFR2,App C,Section G
1990-09-07
[Table view] |
Text
_.
r-- ll- > - M
.. I
'Af Telephone (412) 393-6000 Nuclear Division
' P.O.Bor4 Shippingport, PA 15077-0004 December 6, 1984
' J. S. Nuclear Regulatory Comission
./ Attn: Thomas T. Martin, Director Division of Engineering and Technical Programs Region 1 631 Park Avenue King of Prussia, PA 19406
Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Inspection Report 84-21 Gentlemen:
On November 5,1984 we received the referenced inspection report which identified the results of an inspection of the Beaver Valley Unit 1 implementation of several NUREG-0737 task actions. No items of noncompliance were identified, however, certain activities were noted as requiring-improvement in order to be acceptable relative to NUREG-0737.
As requested, we have reviewed and addressed those items identified in the report. Attached is a listing of the items and our actions planned or taken to address each item.
This information is being provided prior to December 7,1984 per the discussion held by Mr. Steve Sovick with Mr. J. R. White of your staff on November 21, 1984.
If you have any questions concerning this reply, please contact my office.
Very tru y yours, J. J. Carey Vice President, Nuclear i
l l
8502060562 850128 PDR G ADOCK 05000334 PDR
L Liz . Beav:r Vall:y Power ~ Station, Unit N3.1
,,,- (Dock t- No. 50-334, Lic:nse No. DPR-66 Inspe'c tion Report 84-21 Page 2-cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport,-PA 15077
~
U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 Director, Safety Evaluation & Control-Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 o
I L
4
s .? ,
ATTACHMENT NRC Inspection 84-21 Open Items A. Post Accident Sampling System; NUREG-0737, Item II.B.3 It should be noted that the PASS has been out-of-service due to maintenance activities and Type C testing during the current refueling outage. Therefore, not ' all activities discussed at the exit meeting and identified in the inspection report can" be completed during the outage as anticipated. Some activities, as stated in this attachment, will be completed following station startup.
Inspector Follow Item (84-21-01)
Deficiencies to the specifications of NUREG-0737, II.B.3, Post Accident.
Sampling Capabilities were noted-relative to Reactor Coolant Sampling and the-following should be accomplished:
- 1. Demonstrate that a representative PASS sample can be collected from the RCS "B" hot leg at low RCS pressure.
Response
This activity will be completed prior to start-up from the current refueling outage. The sample collected at the PASS will be compared to a sample collected at the normal sample panel. Documentation demonstrating that a representative PASS sample was successfully collected will be available for NRC review during a subsequent inspection within one month following start-up from the current refueling outage.
- 2. Evaluate th PASS flow requirements and modify as necessary to assure -
that a representative sample will be collected by the system.
Response
We have completed our evaluation of the PASS sample flow and. have determined that sample flow inside the sample box is in the transition zone between laminar and turbulent flow. Flow will be somewhat turbulent but not fully turbulent. Based on our calculations, it is expected that
-the flow through , the . system is adequate for.providing a representative sample, therefore, no modifications are necessary.
- 3. . Perform an evaluation to demonstrate that system purge times .are suffi-cient to obtain a representative ' sample.
1 l-
' Attachment.
NRC Inspecticn 84-21 Open Items s 'sPage,2
Response
Purge time calculations will be performed using the information derived e from the above evaluation for the containment sump and reactor coolant samples. ^
sample from The calculations wili establish the time required to move a its sample point to the PASS box. The documentation supporting the adequacy of the system purge times will be compared with existing purge times and the necessary adjustments, if any, will be made to assure adequate purges are completed.
work will be available for NRC review during a subsequentDocumentation inspection s within one month following start-up from the current refueling outage.
4.
Complete the repair of the dissolved gas portion of the PASS.
Response
Parts have been ordered to repair the. dissolved gas portion of the PASS.
Installation the parts. and testing will occur within one month upon the receipt of Inspector Follow Item (84-21-02)
Deficiencies to the specifications of NUREG-0737, II.B.3 were noted relative to containment air sampling for the following reason:
The rotameters in the PASS are calibrated using a gas at STP, however, actual will affect flow. operating conditions result in varying backpressures on the rotameters 1.
function under post-accident conditions and reference representative of that gas expected to be mdasured.
_ Response:
Calibration f' actors for the containment air sample and reactor coolant system rotameters will be developed representative of the gas expected to be measured.and referenced to a gas that These calibration factors will be implemented in our procedures start-up from the current refueling outage.
within one month following Inspector Follow Item (84-21-03)
There is insufficient data to document the ability of the analytical tech-niques to meet the licensees commitments for accuracies and sensitivities.-
The following needs to be accomplished:
1.
Demonstrate PASS instrument accuracies when subjected to selected Stan-dard _ Test Matrix (STM) dilutions by developing a comprehensive set of data that and accuracy shows all samples can be analyzed within the expected degree of sensitivity.
i AttachmentL
- :NRC Ins Items
- Page 3'pectisn 84-21 Open
Response
The' PASS instruments will be checked at various points over their in-
' dicating range following startup from the current refueling outage using the Standard Test ' Matrix at selected dilutions to demonstrate that samples can be analyzed within the expected degree of accuracy and sensitivity. These checks will be complete and the documentation will be available for .NRC review in' a subsequent inspection within one month following station startup.
-2. ' Provide data which demonstrates that back-up grab samples can also be obtained and analyzed within a stated degree of accuracy.
Response
Back-up grab samples _which are collected for analysis in the Chemistry Lab are obtained at the PASS box. The laboratory instruments will be checked at various points over their indicating range prior to start-up from the current refueling outage using the Standard Test' Matrix at-selected dilutions to demonstrate that samples can be analyzed within the expected degree of accuracy and sensitivity. The documentation demonstrating acceptability will be available for . NRC review in a subsequent inspection within one month following station startup.
Inspector Follow Item (84-21-04)
Deficiencies to the specifications of NUREG-0737, II.B.3 were noted relative to chloride and boron analysis and the following should be accomplished:
- 1. Develop operating procedures for the in-line chloride' and boron analyzers
, in the PASS.
Response
These procedures have been drafted and will be tested following start-up from the current refueling outage when the PASS has been returned to service. Procedure implementation will be complete within one month following station startup.
- 2. Include a statement in the chloride analyzer operating procedure concern-ing the potential for iodine interference with the in-line chloride analyzer.
Response
A statement reflecting this concern has been included in the draft procedure referenced in. item 1 above.
- 3. Provide detailed information concerning the off-site laboratory analysis program, including shipping procedures and arrangements for' analysis.
. . Attachment
., ',NRC Inspection 84-21 Open Items Page 4
Response
Following _ this inspection, we contacted the Bettis Atomic Power
-e Laboratory with whom arrangements had been made to perform a chloride analysis on undiluted samples-in the event it became necessary. However, Bettis would not agree to renew their agreement to provide this service.
As such,- we are in the process of making new arrangements for the same service. In addition, we must also make different arrangements for the transport of the grab sample. This involves procuring or arranging _ for the use of the appropriate packaging for the transport of a sample.
Upon selecting the packagin'g for shipment, the existing shipping procedures will be reviewed and revised if necessary. We will provide a description of our approach- to provide for this off-site laboratory analysis within one month following start-up from our current refueling outage.
Inspector Follow Item (84-21-05)
Deficiencies to the specification of NUREG-0737, II.B.3 were noted relative to pH analysis and the following should be accomplished:
- 1. Revise the chemistry manual to include provisions for the collection and analysis of grab samples for pH.
Response
A new pH electrode which requires significantly less sample volume has been procured and placed in operation. Ttie use of this new electrode removes the personnel exposure problem which existed when handling a 4cc sample. Procedures ' addressing the collection and analysis of grab samples for pH will be implemented within one month following station startup.
- 2. Indicate the actual range capability for pH, consistent with the require-ments of NUREG-0737.
Response
The indicated range of the PASS in-line pH analyzer is as stated in our letter dated August 31, 1982 f rom J. J. Carey to S. A. Varga. The station Operating Manual incorrectly identifies the pH analyzer range.
This will be corrected during a subsequent Operating Manual revision.
- 3. Evaluate the effect of temperature on pH results and make provisions accordingly.
Response
The PASS in-line pH analyzer is equipped with temperature compensation over the range of expected temperatures. The effect of temperature on the analytical results, if any, will be evaluated following start-up from
Attachment
.NRC Inspectirn 84-21 Open Items "Page 5 the current refueling outage when the PASS has been returned to service.
Documentation supporting our findings and procedure changes, if any, will be available ' for NRC review during a subsequent inspection .within one month following station startup.
- 4. - Determine the basis for the varying response of the in-line pH analyzer and adjust and/or correct the instrument as required.
Response
When analyzing the PASS sample utilizing the in-line pH analyzer, it is possible to draw too much vacuum across the pH electrode which can cause the electrode to become uncovered which results in . erroneous- readings.
Through analytical testing, the Chemistry Department has duplicated this operational anomaly. As a result the Chemistry Manual will be revised to warn PASS operators of this condition. Procedure revision will be completed within one month following startup from the current refueling outage.
Inspector Follow Item (84-21'06)
Additional problems were noted ir. regard to the Post Accident Sampling System (PASS) which were not included in the previously identified inspector follow items.
The following should be accomplished:
1.
Complete the calibration and maintenance program of the PASS system and the spare parts list.
Response
The calibration and maintenance program for the PASS is near completion.
Procedures will be reviewed and ready for implementation within one month following start-up from the current refueling outage. The spare parts I list has been developed and parts are on order.
2.
Revise the Chemistry manual to reference routine procedures used in performing the chemical analysis of post-accident grab samples.
Response
Revisions to the Chemistry Manual to reference routine procedures used in performing the chemical analysis of post-accident grab samples will be implemented within one month following station startup from the current refueling outage.
3.
The routine procedures for the chemical analysis of grab samples need to include sufficient radiological precautions and control measures that should be exercised during the analysis of highly radioactive samples.
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NRC Inspection 84-21 Open Items Page 6 Response:
- Revisions to the Chemistry Manual incorporating radiological precautions and control measures when handling highly radioactive samples will be implemented within one month following station startup from the current refueling outage.
- 4. The licensee's time and motion studies, designed to establish compliance with the GDC-19 criteria did not clearly demonstrate that sampling and analysis could be conducted within these limits for both samples collect-ed at the PASS and_ other grab samples. The licensee should conduct a detailed and comprehensive evaluation of expected personnel exposure, using the appropriate source terms for all samples which could be col-lected.
Response
A time and motion study was performed by observing and timing the collection and analysis of samples. Information has been gathered and is attached to this submittal which demonstrates that the primary method of sample collection and analysis is within the criteria defined in NUREG-0737 item II.B.3. This included sample collection and analysis at the PASS box using in-line analyzers and performing the isotopic analysis in the Chemistry Hot Lab. See TABLE 1. Grab samples were also analyzed to demonstrate that whole body and extremity doses were within the GDC-19 requirements. See TABLE 2. The dose rates used in this study assume letdown from the Reactor Coolant System becomes isolated upon initiation of safety injection which is consistent with our plant review performed under the guidance of NUREG-0737 item II.B.2.
NUREG-0737 item II.B.2, Design Review of Plant Shielding, identified the need to evaluate plant spaces to determine radiation exposure rates in areas requiring personnel access. During NRC Inspection 82-24, this item was reviewed. The post-accident source term and radiation levels in the plant were reviewed to determine the acceptability of our design. It is suggested this information, including information provided to the NRC .
subsequent to Inspection 82-24, be reviewed as this serves as the basis for radiation levels in the plant.
The overall times and exposures are higher than originally provided in our August 31, 1982 due in part to additional time being necessary to purge the PASS before collecting the sample. Initial times and exposures were developed during the early days of the PASS operation and since that time additional information has been gained as a result of operating experience. It should be noted that personnel radiation exposures are still within the GDC-19 requirements.
In order to further evaluate the potential for changing radiation levels in the area of the PASS box, a task force has been established to determine potential changes during the course of an accident. Work will commence on this project within one month following start-up from the current outage. The information collected and the conclusions made will be available for review during a future inspection.
~ .. . ~ Attachment 3RC Inspection 84-21 Open Items Page 7 5 '. Develop an activation procedure for the Emergency Response Facility (ERF) laboratory.
Response
An activation procedure for.the ERF laboratory will be implemented within one.montn following startup from the current refueling outage.
B. Noble Gas Effluent Monitor; NUREG-0737 item II.F.1-1 We wish to clarify several statements made in Section 5.2.1 of the inspection report..
On Page 10 of the inspection report, the staff noted that "...The licensee has Laccepted Eberline's primary systems calibration, without independent
. verification..." This comment implies that no calibration was done. This is not the case. Following installation, and prior to declaring the system operational, Duquesne Light did perform and document (in Design Change Package files) a transfer calibration using sources used by the vendor during factory-calibration. This transfer calibration is re-performed periodically.
The report further states, "All_ Radcon technicians are trained to make routine changes of particulate and charcoal filters and to -collect grab samples of noble gas. To date, their training has been informal". A subsequent review of training records has produced documentation of formal training for all but a few Rad Techs. Formal training for these Rad Techs will be completed prior to station startup from the current refueling outage.
Inspector Follow Item (84-21-07)
The Noble Gas Effluent Monitoring System as reviewed appears to generally meet
-the guidance of NUREG-0737, Attachment II.F.1-1, but the following item needs to be accomplished:
- 1. Develop a procedure for obtaining a grab sample from the SPING-4 systems under emergency conditions.
Response
A procedure, RE0P 1.2, has been draf ted which will provide direction in obtaining a grab sample from the SPING-4 systems under emergency con-ditions. This procedure is currently undergoing review and will be implemented within one month following startup from the current refueling outage.
I C. Sampling and Analysis of Plant Effluents; NUREG-0737 Item II.F.1-2 l l
Inspector Follow Item (84-21-08)
The systems for Sampling and Analysis of Plant Effluents does not meet the guidance given in NUREG-0737, II.F.1-2 for the following reasons:
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., f.NRC Inspection 84-21 Open Items Page 8
- 1. The SPING-4 and SA9/SA10 sample systems have not been designed to meet the source term requirements of NUREG-0737 Table II.F.1-2. The maximum measurement limit of the SPING-4 is 28.9 pCi whereas the sample collect-ed, based on the NUREG-0737 iodine air concentration, would yield a -
source term of 'approximately 195 C1. The shielding design of the SA9/SA10 and SPING-4 provides minimal shielding for personnel who would collect these samples or take grab samples at these locations. Further-more, there are no procedures to collect or analyze these high level samples.
Response
. Based on NUREG-0737 Clarification, the SPING-4 has been designed to provide continuous sampling to collect plant gaseous effluents. It is not a design function of the SPING-4 to be able to provide a readout of radioiodine in a post accident sample. Once the sample 'is collected, a separate analysis is performed. A review of the SPING-4 shielding design has been completed. It has been verified that the shielding design is adequate to protect personnel when assuming the source term provided in TABLE II.F.1-2. A procedure for collecting and analyzing grab samples (RE0P 1.2) is drafted and under review and will be implemented within one month following startup from the current refueling outage. Upon implementation of the - procedure, the SPING-4 system will become the sample collection point for post accident samples. The SA 9/SA 10 sample systems will not be used.to collect the post accident samples when high activity levels are expected.
- 2. The SPING-4 or SA9/SA10 units of all the effluent pathways have not been equipped to monitor the pressure drop at each sampling point on the unit.
The procedures which are used to compute effluent flow have not incor-porated any change in flow due to pressure differential. Since the SA9/SA10 is used for both routine and emergency situations, provisions should be made for pressure drop measurements and flow' corrections at these sampling locations.
Response: -
The SPING-4 system is being modified as part of DCP-400. Completion of this DCP during this refueling outage will satisfy the inspectors con-cerns for this instrument. Modifications to install pressure gauges on the SA9/SA10 units have been completed. Procedures have been revised to allow for flow corrections based on the pressure drop ~ at sampling lo-cations.
- 3. It was. documented in a previous inspection (83-30-05) that insufficient data exists to determine if a representative sample can be collected for monitoring airborne radioactivity released from the plant. The utility is addressing this issue and will issue a final report on the study by
. December 31, 1984.
Response
Based on the previous commitment (83-30-05), we will provide a report by December 31, 1984.
.' . Attachment
., 'sNRC_ Inspection 84-21 Open Items
'Page 9 Inspector Follow Item (84-21-09) I l
The following are specific ~ inspector recommendations which are to be addressed in the response to this Inspection Report.
- 1. The SPING-4 controller will read out in pCI/cm3 vise cpm following completion of DCP-400.
Response
The station has evaluated this recommendation and although there is merit in this recommendation, the station has decided not to change the current units from cpm to pCi/cm3 The .SPING unit must comunicate with other computer equipment that expects to receive units of cpm.
There are existing procedures in the RCM and EPP which provide for converting the reading in cpm to pCi/cc and to C1/sec. If the SPING were
-to read out in pCi/cc, corrections for different source terms and/or decay in these source terms would not be possible. These procedures provide for different source terms. The ARERAS computer, which obtains an input from the SPING, uses similar source terms and corrects for decay. -The ARERAS computer was installed to meet NUREG-0737 requirements and will be operational by the end of the current refueling outage.
- 2. BVPS-RCM Chapter 4. RIP 2.10 quotes Table 3.3.6 of the Technical Speci-fications incorrectly.
Response
The Radiation Control Manual has been revised to incorporate the NRC's Concerns.
- 3. Resolve the inconsistency which exists in the primary calibration data supplied by Eberline.
Response
The review of the Eberline primary calibration data has been completed.
The identified unit inconsistency has been resolved, therefore, an inconsistency no longer exists.
- 4. Procedure / manual revisions to account for iodine channel gain calibration in MSPs 43.58, 43.59 and 43.60 and the CT-1 terminal manual.
Response
Current revisions (Issue 1 Rev. 2 Effective 5/14/84) of the MSPs do account for iodine channel ' gain calibration. It was determined that it is not necessary to include this information at the CT-1 terminal manual.
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'.,NRC. Inspection 84-21 Open. Items ;
'Page 10-
- 5. For the II.F.1-2 monitors, consider the filters as source terms when determing exposure rates. '
e Response:
-We will be using the SPING-4 as the primary device for accident sample collection following this outage when the procedures are implemented.
The source term resulting from the filters has been taken into account when using this monitor.
- 6. Update BVPS-RCM Chapter 3, RIP 7.3 to reflect use of current instrumenta-tion. Clarify action levels if handling accident samples.
Response
The manual has been updated to reflect the use of current instrumentation and will be revised to clarify action levels' when handling accident samples. This will be accomplished when RE0P 1.2 is implemented.
- 7. BVPS-RCM, Chapter 4, RIP 2.10 needs to be modified (4 specific recomen-dations).
Response: -
BVPS-RCM Chapter 4, RIP 2.10 items 5.3, 5.4 and 5.7 have been revised to incorporate the inspectors recommendations identified in the Inspection Report. Figure 4.2.10.2 is a vendor sketch flow diagram showing system layout for general knowledge only and does not need changed.
- 8. Develop a detailed Emergency Operation Manual for the SPING-4.
Response
This is covered under REOP 1.2 which is currently in draft form undergo-ing review and will be implemented within one month following startup from this refueling outage.
D. In-Containment High Radiation Monitors; NUREG-0737 Item II.F.1-3 Inspector Follow Item (84-21-10)
NUREG-0737 Item II.F.1-3, requires the installation of two in-containment radiation monitors with a maximum range of 107 R/hr (gamma). The monitors shall be operated to view a large portion of containment, and developed and qualified to function in an accident environment.
The system components were verified to be environmentally qualified to design bases accident conditions, with the exception of.the containment penetration i
. . Attachment
, :NRC Inspection 84-21 Open Items Page 11 cable connectors. The licensee has commissioned environmental testing of a similar connector -configured in the same manner by an independent testing laboratory. Such testing was ongoing at the time of the inspection.
While the licensee expects that the results of the test will confirm that the penetration connectors will meet or exceed the acceptance criteria for the accident environment, each certification was not available at the time of the inspection. The licensee ~ agreed to provide certification of environmental qualifications as soon as the testing program is completed.
Response
The containment penetration cable connectors are qualified and the documentation is maintained in the BV-1 EQ files. The conduit seal on the conduit housing the Radiation monitors cable was undergoing testing at the time of.the inspection. The tests have successfully demonstrated
. the ability of the conduit seal to survive design basis accident conditions. The test results are -documented in Test Report No. 46880-1 and is maintained in the DLC BV-1 EQ file.
E. In-Plant Radioiodine Instrumentation; NUREG-0737 Item III.D.3.3 Inspection Follow Item (84-21-11)
NUREG-0737 " Clarification of TMI Action Plant Requirements", Item III.D.3.3.
requires that each licensee shall provide equipment and associated training and procedures for accurately determining the airborne iodine concentration in areas within the facility where plant personnel may be present during an accident.
None of the procedures reviewed contained requirements for purging noble gases.
from the sampling media, therefore, the following should be accomplished:
- 1. Revise appropriate procedures to make provisions for purging noble gases as necessary from radioiodine sampling modes as specified in NUREG-0737, Item III.D.3.3.
Response
In order to determine radiciodine concentrations in plant areas, silver zeolite cartridges are utilized. A characteristic of the- silver zeolite cartridge is such that noble gas retention is negligible (5 x 10 6 percent) therefore making it unnecessary to purge them in order to obtain an accurate indication of the radiciodine present.
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Table 1 3
, s c i Time / Motion Study for Sample Collection and Analysis at the PASS Box and Hot Lab TASK TIME (min) EXPOSURE RATE EXPOSURE (mR)
Pfe-sample briefing, Anti-C -
dressing- 30 * *
. hlk from PAB door to PASS box -
1 5 R/hr 83.3 Start-up activity
' Li gid systen start-up 12 550 mR/hr 110.0 Containment air system start-up 2 18.3 Ni system start-up 6 55.0 i Analyzer start-up 2 18.3 Sampling Systen alignment for a containment sump sample -or (liquid coolant sample) 10 (4+) 91.7 (36.7+)-
! - Purge, sump sample collection, and readings or (purge, lipid coolant
- sample collection and readings) 30 (10+) 275.0(91.7+)
Undiluted pressurized liquid and gas
- sample from RCS (0.5 cc sample) 10 91.7 Diluted depressurized liquid sample 12 110.0
- Containment atmosphere sample 12 'I 110.0 System shutdown hlk from PASS box to PAB door 1 5 R/hr 83.3 Chemistry Hot Lab Isotopic Analysis **
hlk from PAB door to hot lab 2 611 mR/hr 20.4
! Isotopic counting of liquid samples 30 sec 9240 mR/hr 77 extremity j
I (1 cm from sample) i 5 50.1 601 mR/hr l Data reduction 20 .* *
! Total 155 min 1117.1 mR whole body 4
77 mR extrenity
+ Liquid sample will be either coolant or containment sump. Containment sump i sample time is most conservative, l
- Perfonned in low background area.
- Based on background at hot laboratory at one hour after accident (601 mR/hr) .
Table 2 Grab Sample Analysis
' Exposure Activity Time trip to ERF lab- 10 min 100 mR from containment shine (6 min) and 1 mR from diluted sample 15 min 24 mR to get undiluted sample (in cask) to truck bay 15 min 24 mR to get sample from ERF truck bay to lab low level boron analysis
-(diluted sample)
(contact 1,540 mR extremity (1 cm from sample) 10 min /
2 mR whole body (1ft 60 min ----
remotely monitor hydrogen analysis (diluted sample) contact 77 mR extremity (1 cm from sample) 30 sec 1 ft -----
4.5 nin ----- remotely monitor lipid isotopic analysis (diluted sample)
, contact 77 mR extremity (1 cm from sample) 30 sec 1 ft -----
4.5 min ----- remotely monitor Containment air isotopic i
analysis contact 2.5 mR extremity (1 cm from sample) 30 sec 1 ft -----
4.5 min ----- remotely monitor l ph analysis (undiluted sample 3 sec contact 2,740 mR extremity in order to connect in sample cask) and open valve on sample line (1.5 inches from sample) 30 sec 1 ft 130 mR whole body (sample set up) l
l Table 2 (cont'd.)
return to plant 10 min 100 mR from containment shine (6 min) and 1 mR dose from diluted sample
, 15 min 24 mR to get undiluted sample from l ERF lab to truck bay 1 15 min 24 mR to get sample from plant truck bay to PASS box 15 min 137 mR to place samples in box 285 mR
-total exposure including trip to and from the ERF and all analysis: 565 mR whole body 4,436.5 mR extremity I
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