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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-027, Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines1999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs L-99-024, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-027, Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines1999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-024, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 L-99-224, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments L-99-217, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F0621999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-022, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments L-99-021, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195C6941999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program L-99-020, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195F2101999-05-24024 May 1999 Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790 L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206F4321999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206C8021999-04-26026 April 1999 Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231 ML20205S9501999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 L-99-153, Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error1999-04-13013 April 1999 Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error L-99-125, Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z1999-03-19019 March 1999 Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z ML20205A2871999-03-19019 March 1999 Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z ML20205A1531999-03-19019 March 1999 Forwards Corrected Typed & marked-up Current TS Pages for Replacing Previous Pages Submitted on 990222,re CR, Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation L-99-012, Forwards 10CFR50.46 Annual Rept for 1998,re Effects of ECCS Evaluation Model Mod on Peak Cladding Temp Results Since 1997 Annual Rept & Most Recent PCT Error Rept Submitted 9809101999-03-19019 March 1999 Forwards 10CFR50.46 Annual Rept for 1998,re Effects of ECCS Evaluation Model Mod on Peak Cladding Temp Results Since 1997 Annual Rept & Most Recent PCT Error Rept Submitted 980910 L-99-010, Forwards ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jfnp,Unit 1, & Vols 1 & 2 to ISI Refueling 15,Interval 3, Period 1,Outage 1 for Jfnp,Unit 1. Summary of Results May Be Found in Tab B of Encl 21999-03-18018 March 1999 Forwards ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jfnp,Unit 1, & Vols 1 & 2 to ISI Refueling 15,Interval 3, Period 1,Outage 1 for Jfnp,Unit 1. Summary of Results May Be Found in Tab B of Encl 2 ML20205A7611999-03-18018 March 1999 Forwards Annual DG Reliability Data Rept for 1998,per Plant TS 6.9.1.12 & 10CFR50.36.Rept Provides Number of Tests (Valid or Invalid) & Number of Failures for DGs at Jm Farley Nuclear Plant.Ltr Contains No New Commitments ML20205H2741999-03-18018 March 1999 Forwards Info on Status of Decommissioning Funding for Jm Farley Nuclear Plant,Units 1 & 2,IAW 10CFR50.75(f)(i) ML20204D4281999-03-16016 March 1999 Forwards SG-99-03-001, Farley Unit-1 1999 Voltage-Based Repair Criteria 90-Day Rept, Per GL 95-05.Required Rept for Fall 1998 SG Insp Is Included in Rept ML20204E5841999-03-15015 March 1999 Submits Info on Current Levels & Sources of Insurance on Jm Farley Nuclear Plant,Units 1 & 2 1999-09-16
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7131990-09-17017 September 1990 Advises That Due to Reassignment,Jj Clark No Longer Needs to Maintain Senior Reactor Operator Licenses ML20059J2811990-09-14014 September 1990 Forwards List of Key Radiation Monitors Which Will Be Used as Inputs to Top Level Radioactivity Status Bar Re Spds.List Identifies Monitors Which Would Provide Concise & Meaningful Info About Radioactivity During Accidents ML20065D5961990-09-13013 September 1990 Responds to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19.Response Withheld ML20059J1661990-09-13013 September 1990 Forwards Monthly Operating Rept for Aug 1990 for Jm Farley Nuclear Plant & Rev 10 to ODCM ML20059L0751990-09-12012 September 1990 Forwards Revised Pages to Rev 3 to, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2911990-09-12012 September 1990 Forwards Operator Licensing Natl Exam Schedules for FY91 Through FY94,per Generic Ltr 90-07.Requalification Schedules & Estimated Number of Candidates Expected to Participate in Generic Fundamental Exam,Also Encl ML20064A7111990-09-12012 September 1990 Forwards Rev 1 to Relief Request RR-1, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2891990-09-12012 September 1990 Confirms Rescheduling of Response to Fitness for Duty Program Notice of Violation 90-18-02,per 900907 Telcon ML20065D6621990-09-12012 September 1990 Forwards NPDES Permit AL0024619 Effective 900901.Limits for Temp & Residual Chlorine Appealed & Stayed ML20064A3431990-08-28028 August 1990 Forwards Corrected Insertion Instructions to Rev 8 to Updated FSAR for Jm Farley Nuclear Plant ML20059D4711990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for Jan-June 1990 ML20059B5101990-08-22022 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990.No Changes to Process Control Program for First Semiannual Period of 1990 Exists ML20056B2751990-08-20020 August 1990 Forwards Relief Requests from Second 10-yr Interval Inservice Testing Program for Class 1,2 & 3 Pumps & Valves. Request Incorporates Commitments in 891222 Response to Notice of Violation ML20056B2741990-08-20020 August 1990 Forwards Rev 2 to Unit Inservice Testing Program,For Review & Approval.Rev Incorporates Commitments Addressed in Util 891222 Response to Notice of Violation & Other Editorial & Technical Changes ML20058Q1481990-08-15015 August 1990 Forwards Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components ML20058P6201990-08-15015 August 1990 Forwards Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components, Per 891207 & 900412 Responses to NRC Request for Addl Info ML20055G7701990-07-18018 July 1990 Updates 900713 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20055F7411990-07-11011 July 1990 Forwards Monthly Operating Rept for June 1990 & Corrected Monthly Operating Repts for Nov 1989 Through May 1990.Repts Revised to Correct Typo on Value of Cumulative Number of Hours Reactor Critical ML20055F3781990-07-10010 July 1990 Submits Final Response to Generic Ltr 83-28,Items 4.2.3 & 4.2.4.Util Position That Procedures Currently Utilized by Plant Constitute Acceptable Ongoing Life Testing Program for Reactor Trip Breakers & Components ML20055D4861990-07-0202 July 1990 Requests Authorization to Use Encl ASME Boiler & Pressure Vessel Code Case N-395 Re Laser Welding for Sleeving Process Described by Oct 1990,per 10CFR50.55a,footnote 6 ML20055D1001990-06-26026 June 1990 Responds to Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12 on 900411-0510.Corrective Actions:Electrolyte Level Raised in Lights Identified by Inspector to Have Low Electrolyte Level ML20044A6191990-06-26026 June 1990 Suppls 900530 Ltr Containing Results of SPDS Audit,Per Suppl 1 to NUREG-0737.One SPDS Console,Located in Control Room,Will Be Modified So That Only SPDS Info Can Be Displayed by Monitor.Console Will Be Reconfigured ML20043G4741990-06-11011 June 1990 Submits Addl Info Re 900219 Worker Respiratory Protection Apparatus Exemption Rev Request.Proposed Exemption Rev Involves Features Located Entirely within Restricted Area as Defined in 10CFR20 ML20043C1851990-05-29029 May 1990 Forwards Proposed Schedules for Submission & Requested Approval of Licensing Items ML20043B5941990-05-25025 May 1990 Provides Rept of Unsatisfactory Performance Testing,Per 10CFR26,App A.Error Caused by Olympus Analyzer Which Allowed Same Barcode to Be Assigned to Two Different Samples. Smithkline Taken Action to Prevent Recurrence of Scan Error ML20042G7461990-05-10010 May 1990 Certifies That Plant Licensed Operator Requalification Program Accredited & Based Upon Sys Approach to Training,Per Generic Ltr 87-07.Program in Effect Since 890109 ML20042F0831990-05-0101 May 1990 Forwards Rev 18 to Security Plan.Rev Withheld ML20042G3081990-04-25025 April 1990 Forwards Alabama Power Co Annual Rept 1989, Unaudited Financial Statements for Quarter Ending 900331 & Cash Flow Projections for 1990 ML20042E4121990-04-12012 April 1990 Provides Addl Info Re Review of Second 10-yr Inservice Insp Program,Per NRC 890803 Request.Relief Request RR-30 Requested Reduced Holding Time for Hydrostatically Testing Steam Generator Secondary Side ML20012E9571990-03-27027 March 1990 Forwards Annual Diesel Generator Reliability Data Rept,Per Tech Spec 6.9.1.12.Rept Provides Number of Tests (Valid or Invalid),Number of Failures for Each Diesel Generator at Plant for 1989 & Info Identified in Reg Guide 1.108 ML20012D9661990-03-22022 March 1990 Forwards Annual ECCS Evaluation Model Changes Rept,Per Revised 10CFR50.46.Info Includes Effect of ECCS Evaluation Model Mods on Peak Cladding Temp Results & Summary of Plant Change Safety Evaluations ML20012D8901990-03-20020 March 1990 Clarifies 891130 Response to Generic Ltr 83-28,Item 2.2.1 Re Use of Q-List at Plant,Per NRC Request.Fnpims Data Base Utilized as Aid for Procurement,Maint,Operations & Daily Planning ML20012C4701990-03-15015 March 1990 Responds to NRC 900201 Ltr Re Emergency Planning Weaknesses Identified in Insp Repts 50-348/89-32 & 50-364/89-21. Corrective Actions:Cited Procedures Revised.Direct Line Network Notification to State Agencies Being Implemented ML20012C6241990-03-14014 March 1990 Informs of Resolution of USI A-47,per Generic Ltr 89-19 ML20012C4651990-03-13013 March 1990 Provides Verification of Nuclear Insurance Reporting Requirements Specified in 10CFR50.54 w(2) ML20012C2051990-03-0505 March 1990 Forwards SPDS Critical Function Status Trees,Per G West Request During 900206 SPDS Audit at Plant.W/O Encl ML20012A1621990-03-0202 March 1990 Forwards Addl Info Inadvertently Omitted from Jul-Dec 1989 Semiannual Radioactive Effluent Release Rept,Including Changes to Process Control Program ML20012A1301990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Encl ML20043A7481990-02-0202 February 1990 Forwards Util Exam Rept for Licensed Operator Requalification Written Exams on 900131 ML20006D2311990-01-31031 January 1990 Responds to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures Will Be Revised to Incorporate Guidance That Will Preclude Inadvertent Loss of Shutdown ML20006A9091990-01-23023 January 1990 Forwards Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Has Program to Perform Visual Insps & Cleanings of Plant Svc Water Intake Structure by Means of Scuba Divers ML20005E4931989-12-28028 December 1989 Provides Certification That fitness-for-duty Program Meets 10CFR26 Requirements.Testing Panel & cut-off Levels in Program Listed in Encl ML20005E3681989-12-28028 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-28 & 50-364/89-28 on 891002-06.Corrective Actions:All Piping Preparation for Inservice Insp Work in Containment Stopped & All Participants Assembled to Gather Facts on Incident ML20005E1971989-12-27027 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22 on 890911-1010.Corrective Actions:Steam Generator Atmospheric Relief Valve Closed & Core Operations Suspended.Shift Supervisor Involved in Event Counseled ML20011D5041989-12-22022 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-26 & 50-364/89-26.Corrective Actions:Personnel Involved in Preparation of Inservice Test Procedures Counseled. Violation B Re Opening of Pressurizer PORV Denied ML19332F2111989-12-0707 December 1989 Forwards Final Response to NRC 890803 Request for Addl Info Re Review of Updated Inservice Insp Program,Summarizing Results of Addl Reviews & Providing Exam Listing Info ML19332F0791989-12-0707 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22.Corrective Actions:All Managers Retrained on Intent of Overtime Procedures & Sys Established to Provide Independent Check of All Time Sheets Each Pay Period ML19332F1141989-12-0707 December 1989 Forwards Description of Instrumentation Sys Selected in Response to Generic Ltr 88-17, Loss of DHR, Per Licensee 890127 Commitment.Hardware Changes Will Be Implemented During Unit 1 Tenth & Unit 2 Seventh Refueling Outages ML19332F1241989-12-0707 December 1989 Forwards Response to NRC 890803 Request for Addl Info Re Review of Second 10-yr Inservice Insp Program,Per 891005 Ltr ML19353B0071989-12-0606 December 1989 Forwards Rev 1 to Safeguards Security Contingency Plan.Rev Withheld 1990-09-17
[Table view] |
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- 7. ,; . Allbama Power Company 600 North 16th Stre<st
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Birmingham, Alabama 352910400
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', R. P. Mcdonald Sentor Vice President Alabama Power o the soahem eutre sntem May 5, 1988 Docket Nos. 50-348 '
50-364 h
Director,.0ffice of Enforcement U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Vashington. D. C. 20555 Gentlemen:
Jopph M. Farley Nuclear Plant Inspections of May 11-22, June 1-5 and June 11-July 10, 1987 RE: Supplemental Response to Notice of Violation and Proposed Imposition of Civil Penalties Regarding Enforcement
- Action 87-142 On December 17, 1987 Alabama Power Company responded to the NRC Notice of Violation and Proposed Imposition of Civil Penalties (NOV), dated November
- 3. 1987, relating to the,Jaseph M. Farley Nuclear Plant Units 1 and 2 (E!.87-142). The NRC reported additional findings, asserted to relate to EA 87-142, in an Inspection Report issued by letter dated February 4, 1988.
In that letter, the NRC requested that Alabama Power Company "provide [its]
corrective actions for these additional examples in a supplemental i response" to the NOV. As requested, Alabama Power Company describes below the corrective actions taken with respect to these items.
PROCUREMENT OF COMMERCIAL GRADE COMPONENTS FOR EQ APPLICATIONS (50-348, 364/87-30-01)
General In the February 4, 1988 Inspection Report, six examples of conditions considered to reflect adversely on Alabama Pover Company's procurement process were noted. Four of these items were self-identified by Alabama ,'
Power Company. As requested, corrective measures related to those findings are described below. Some of these actions are included in our December 17, 1987 response.
'C805090054 880505
.O PDR ADOCK 05000:348 DCD ll
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- Director, Office of Enforcement ' Hay 5, 1988 U. S. Nv:1 car Regulatory Commission Page 2
- s On June 4, 1987, prior to completion of the vendor inspection audit on which the November 3, 1987 NOV vas based, plant procedures were revised to require written evaluation and approval of code C parts prior-to their use in safety related functions. This action was an interim measure until a dedication program was approved.
Procedures were revised on November 13, 1987 requiring engineering ceview of Code C parts prior to installation in safety related components. If the commercial grade part does not perform a safety function, a basis for acceptance is provided. Procedures have also been revised to incorporate a parts dedication program which provides clear guidance for procurement and dedication of commercial grade items (except for parts procured as Code D) for use in performance of safety related functicas.
As noted in Alabama Power Company's December 17, 1987 response, Alabama Power Company intends to continue actively working with the NRC and industry committees in an effort to improve the process for dedication of commercial grade items for use in the performance of safety related functions.
Alabama Power Company vill further revise its procedures as follows:
- 1. EQ components and parts that perform a safety function vill be procured as safety related or they vill be procured as non-safety related and dedicated. If the parts serve no safety related function and are not required to function to satisfy the environmental qualification of the component, they may be purchased as non-safety related.
- 2. Procurement procedures vill be revised to require that items that are procured as non-safety related for dedication for safety related use in EQ applications vill undergo an engineering review to determine that the items are the same as the items included in the original qualification test (s) or that any deviations which could affect the quellfication status have been satisfactorily addressed.
- 3. Procurement procedures vill be revised as necessary to allow the dedication of Code D (non-safety related) items to be used in safety related functions. This dedication, including a commitment of Alabama Power Company to accept 10CFR21 reporting responsibility, may be a formal dedication plan or it may be a documented engineering reviev showing the adequacy of the part.
The second paragraph on page 11 of the Inspection Report states in part, "Review of the quality implementing procedure FNP-0-AP-9, Revision 12, revealed that measures had not been established to assure that applicable I regulatory requirements are met, and design bases are preserved during the procurement and use of 0A Review Code C (Non-safety-Related) and QA reviev
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Director, Office of Enforcement May 5, 1988 U. S. Nuclear Regulatory Commission Page 3 Code D (Non-safety-Related) items in E0 applications." Alabama Power Company does not agree with the portion of this conclusion regarding Code D items. FNP-0-AP-9, paragraph 9.2.1, states that Code D assemblies, parts or materials and services vill be assigned QA requirements per the criteria contained in paragraph 9.2.1.1. Specifically, this paragraph states that design, code, or license requirements shall be included in the procurement documents. This ensures that the design bases are preserved during the procurement of Code D items, including items in E0 applications.
Detailed Discussion of NRC Identified Examples EXAMPLE 1:
"P.O. No. OP-1481 (OA Review Code D) vas issued for the procurement of States type ZVM terminal blocks. The controlling procedure for this procurement was FNP-0-AP-9, revision 12 (Issue Date September 2, 1986).
This procedure defined Code D as a non-safety-related procurement of an item where current license requirements are applicable to the part, or special vendor documentation and verification of vendor's OA program is deemed necessary. The requirements of 10 CFR 21 vere not imposed on this purchase order. teceptance of the items by the licensee was by receipt inspection with a Jertificate of Conformance that noted the terminal blocks had been manufactured using vendor's standard QA/0C procedures for Class 1E terminal blocks. However, specific supplemental documentation, such as material certificates or reports of tests, was not requested in the l
purchase order nor vere they provided by the vendor.d Admission or Denial Alabama Power Company admits that specific supplemental documentation
- vas not requested in the purchase order nor was it provided by the vendor.
( Evaluation of Violation i
Although specific supplemental documentation was not requested nor received in the subject purchase order, subsequent evaluation by the vendor (Multi-amp letter dated May 3, 1988) has demonstrated that the l
States type ZVM terminal blocks procured Code D vere of the same l
design, materials and manufacturing processes as those tested (Wyle l !aboratories Test Report NE044354-1 dated March 8, 1979). Therefore i Alabama Power Company concludeF the subject terminal blocks are l
acceptable for safety related E0 applications. The States type ZVM l terminal blocks were procured Code D under the States Quality Assurance l Program, Revision 3, that had been approved by Alabama Power Company prior to procurement. Receiot inspection was done by Alabama Power Company as required by FNP-0-AP-20, which is the same procedure used to document receipt inspection for safety related items. This procedure ensures proper inspection of the items as well as verification that the documentation required by the procurement documer.ts has been received.
e Director, Office of Enforcement May 5, 1988 L U. S. Nuclear Regulatory Commission Page 4 In addition, the traceability of the Code D items of this purchase order was maintained per FNP-0-AP-21. These steps, combined with the knowledge of Alabama Pover Company that it had previously had Vyle Laboratories perform the necessary E0 testing on this type terminal block, adequately constituted the dedication of the terminal blocks for safety related E0 applications. Further, these steps are equivalent to a dedication of the items under a formal plan. No additional action for 10CFR21 compliance is deemed necessary.
Corrective Action Taken and Results Achieved No further action required.
Corrective Steps Taken to Avoid Further Violations Procurement procedures vill be revised as necessary to allow the dedication of Code D (non-safety related) items to be used in safety related functions. This de61 cation, including a commitment of Alabama Power Company to accept 10CFR21 reporting responsibility, may be a formal dedication plan or it may be a documented engineering review showing the adequacy of the part.
Date of Full Compliance Applicable Farley Nuclear Plant procedures vill be revised by June 2, 1988.
EXAMPLE 2:
"The reactive inspection the week of September 14-18, 1987, for follovup of licensee identified unqualified taped splices revealed the use of commercially procured tapes for E0 applications. Purchase Order No. B4541 (OA Review Code C) was issued on September 30, 1986 for procurement of ,
miscellaneous electrical supplies including Okonite T-95 insulating tape and No. 35 overlay tape. An engineering determination of the items critical attributes, ability to function in the intended safety-related application, and the acceptance parameters for verification of those critical attributes were never performed by the licensee. An assessment of the impact on E0 status pursuant to receipt of Okonite's letter to Mr.
Robert Culp, dated November 11, 1986 [ sic], was never performed. This letter gave a qualified shelf life for T-95 tape as 18 months, and for No.
35 tape as 24 months. The controlling procedure for this procurement FNP-0-AP-9, revision 12, did not establish requirements for dedication of commercially procured items prior to use in E0 applications."
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'g Director, Office of Enforcement May 5, 1988 U. S.' Nuclear Regulatory Commission Page.5 "
Admission or Denial Alabana Power Company, admits that requirements for dedication of commercially procured items prior to use in EQ applications were not
- established.
Evaluation of Violation Inadequate pro:edural guidance resulted in inadequate documentation of the suitability of these commercial grade items prior to their installation in safety related components. To confirm previous verbal informs. tion, a letter was obtained from The Okonite Company on June 11, 1987 stating that Okonite T-95 and Okonite #35 tapes are commercial materials manufactured under a commercial QC Program. The tapes have
, been qualified for use in a nuclear environment (see Report NORN-3 Rev.
2, 2/16/84). Stock material is run and distributed to varehouses.
These stock tapes are the same quality as vould be.provided if identified for nuclear plant use and traceability requirements imposed in the procurement documents. In addition, a shelf life program was implemented in 1986. An inspection of tape removed as a result of the V-t'epe splice tape replacement program was performed and the tape was in good condition. On this basis, the use of these tapes is accoptable and hence no significant safety issue is involved.
Corrective Actior. Taken and Resulta Achieved No further action required. Evaluations affirmed that the tapes are acceptable.
Corrective Steps Taken to Avoid Further Violations EQ components and parts that perform a safety function vill be procured as safety related or they vill be procured as non-safety related and dedicated. If the parts serve no safety related function and are not required to function to satisfy the environmental qualification of the component, they may be purchased as non-safety related.
Date of Full Compliance Applicable Tarley Nuclear Plant procedures vere revised on November 13, 1987. Okonite tape has been procured as safety related since September 23, 1987.
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i Director, Office of Enforcement May 5, 1988 U. S. Nuclear Regulatory Commission Page 6 EXAMPLE 3: ,
"Installation of unqualified limit switch and torque switches in motor operated valves discovered during valkdown in response to IEN 86-03.
(Procured Code C)."
Admission or Denial Alabama Power Company admits that the installed limit switch and torque switches were procured without environmental qualification supporting documentation.
Evaluation of Violation Inadequate procedural guidance resulted in an inadequate evaluation of the suitability of commercial grade parts prior to their installation in safety related components. An investigation was initiated which determined that the non-metallic portions of the torque switch and limit switches installed had a whitish-gray color and appeared to be identical to the qualified replacement parts. According to Limitorque, whitish-gray is the sas.e color material they utilize for Code A, safety related, environmentally qualified applications. Code C items, however, are normally red in color. Frem this review, it was determined that the limit switch and torque switches vould have performed their intended function and hence no significant safety issue was involved. Therefore, the extent of the deficiency is limited to a lack of documentation supporting environmental qualification.
Corrective Action Taken and Results Achieved The torque switch and limit switches vere replaced with parts procured as Code A.
Corrective Steps Taken to Avoid,Further Violations E0 components and parts that perform a safety function vill be procured as safety related or they vill be procured as non-safety related and dedicated. If the parts serve no safety related function and are not required to function to satisfy the environmental qualification of the component, they may be purchased as non-safety related.
Date of Full Compliance Applicable Farley Nuclear Plant procedures were revised on November 13, 1987. Replacement of all subject components was completed on November 25, 1987.
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' y, Director, Office of Enforcement May 5,.1988
-U. S. Nuclear Regulatory Commission Page 7 t
i EXAMPLE 4t.
"Installation of Raychem Breakout kits in NANCO Limit Switches for Chico Seal (Procured Code D vithout supporting documentation)."-
Admission or Denial Alabama Power Company denies that the Raychem breakout kits were procured without supporting documentation. Alabama Power Company admits that the reporting requirements of 10CFR Part 21 vere not addressed.
, Reason for Denial J
Alabama Power Company purchased the material for Class lE use inside containment in accordance with 0A Requirements for Safety Related Commodities. Raychem provided the requested documentation as well as a Certificate of Compliance. The Certificate of Compliance certf.fied that the material was equivaler t to that tested by test reports EDR-5015, EDP-5009, and Vyle Report 58442-3. Even though the purchase
,, order stated that the material was classified as Code D, safety grade documentation requirements were specified and the vendor supplied proper documentation for safety related or EQ use of the material.
This material is therefore acceptable for its installed application.
While all documentation supporting safety grade material was supplied by the vendor, the requirements of 10CFR Part 21 vere not imposed on this purchase order. Alabama Power Company did, however, handle receipt inspection and issuance per FNP-0-AP-21, which provides the necessary traceability to meet 10CFR Part 21.
Corrective Action Taken and Results Achieved No further action required.
Corrective Action Taken to Avoid Future Violations Procurement procedures vill be revised as necessary to allow the dedication of Code D (non-safety related) items to be used in safety related functions. This dedication, including a commitment of Alabama Power Company to accept 10CFR Part 21 reporting responsibility, may be a formal dedication plan or it may be a documented engineering review shoving the adequacy of the part.
Date of Full Compliance Applicable Farley Nuclear Plant procedures vill be revised by June 2, 1908.
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Dir'ector, Office of' Enforcement May 5,' 1988 U. S. Nuclear Regulatory Commission Page 8 w
e EXAMPLE 5:
."Installation of. G.E. O rings in penetrations (Procured Code C, r.ot upgraded for EQ applicable)."
Admission or Denial Vhile Alabama Power Company admits that the G.3. O rings were procured Code C, we deny that upgrading for EQ applicability is required since the 0 ring does not affect the environmental qualification of the
. module.
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Evaluation of Violation Inadenua procedural gaidance resulted in an inadegaate evaluation of the suittoility of commercial grade parts prior to installation in safety related components. This issue vas reviewed and it was
~~termined that the material was purchased for use inside Containment on the Electrical Penetration Assemblies supplied by General Electric vnder P.O. FNP-241. The subject 0 rings are metallic and serve to seal individual penetration modules for containment leakage aiderations. These parts are commercial quality items whose iformance is demonstrated by periodic Local Leak Rate Testing of each penetration. General Electric supplied a Product Quality Certification for these parts certifying that the items were supplied in accordance l vith applicable codes and specifications. From this review it was determined that the seals vould have performed their intended function and hence no significant safety issue was involved.
Corrective Action Taken and Results Achieved No further corrective action necessary.
Corrective Steps Taken to Avoid Further Violations Components and parts that perform a safety function vill be procured as safety related or they vill be procured as non-safety related and
,, dedicated.
Date of Full Compliance Applicable Farley Nuclear Plant procedures were revised on November 13, 1987.
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Director, Office of Enforcement May 5, 1988 U. S. Nuclear Regulatory. Commission; Page 9.
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EXAlfP1Ji 6:
, , "Installation of metal 0 rings in Conax Penetration (Procured Code C)."
Admission or Denial Alabama Power Company denien that the violation occurred as described
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above.
Reason for Denial The subject containment penetrations were manufactured by General Electric. The General Electric penetrations contain General Electric and/or Conax modules. No metallic 0 rings have been installed on Conax modules; however, Alabama Power Company admits that General Electric 0 rings were procured as Code C and installed on four blank plugs supplied by General Electric. Refer to Example 5, Evaluation of Violation, regarding commercially supplied 0 rings by General Electric.
Action Takren to Reinforce Continued Compliance Refer to Example 5, above.
UPGRADING E0 EQUIPMENT DURING PROCUREMENT (50-348, 364/87-30-02)
General In the February 4, 1988 Report the NRC Staff describes an alleged deficiency (concerning upgrading of equipment) related to the procurement of certain limit switches as an additional example of a previously cited violation.
Detailed Discussion of NRC Identified Examplo EXAMPLE:
"An example of failure to upgrade during procurement is the purchase of Snap-Lock limit switches. P.O. No. OP-1164 (OA Review Code A) van issued for the procurement of environmentally qualified Snap-Lock limit switches on September 8, 1986. The switches were procured as safety-related equipment, and the provisions of 10 CFR 21 vere imposed on the purchase order, however, the P.O. specified that the Certificate of Compliance should certify. compliance with ACHE-Cleveland Development Report llo.
OTR/105 Revision 4, dated January 8, 1984. This report establishes y
Director, Office of Enforcement May 5, 1988 U. S. Nuclear Regulatory Commission Page 10 environmental qualification (EQ) to NUREG-0588 Category II. Contrary to the requirements of 10 CFR 50.49(1) the equipment was not upgraded to 10 CFR 50.49 and reasons to the contrary for not doing so vere never documented. The controlling procedure for procurement activities, FNP-0-AP-9, revision 12, did not establish requirements for procurement of upgraded items. This failure of the liceauce procurement program to establish measures that ensure upgrade of equipment in accordance with requirements of 10CFR50.49(1) is identified as a violation..."
Admission or Denial Alabama Power Company admits that replacement equipment, as interpreted by the NRC, was not upgraded to 10CFR50.49 or "sound reasons to the contrary" documented.
Evaluation of Violation On January 11, 1984, a meeting with NaC staff in Bethesda, Maryland was held to discuss Alabama Power Company position on maintaining equipment
, qualification. On February 29, 1984, Alabama Power Company documented, via letter to the NRC, minutes of the January 11, 1984 meeting in which Alabama Power Company's position on procurement of replacement equipment was described. Specifically, Alabama Power Company stated that it vould procure "identical components" as replacements unlesc -
identical components cannot be obtained. On December 13, 1984, NRC issued an SER specifically referencing the February 29, 1984 Alabama Power Company letter and concluding that Alabama Power Company's EQ program is in accordance with the requirements of 10CFR50.49.
As shown above, Alabama Power Company informed the NRC through a meeting and by letter of its intended actions on maintaining qualification of equipment; specifically, replacement equipment. It was Alabama Power Company's understanding that the NRC SER documented that Alabama Power Company's EQ program, including Alabama Power Company's interpretation of replacement equipment, was in compliance with 10CFR50.49 requirements. During an EQ inspection conducted during the period of September 14-18, 1987, a concern was identified that the requirements of 10CFR50.49(1) were not being properly implemented. To resolve ongoing NRC concerns, Alabama Power Company revised procedures on Novemer 16. 1987 to require that replacement equipment be upgraded to 10CFR50.49 or "sound reasons to the contrary" be documented.
Corrective Action Taken and Results Achieved All E0 components replaced since February 1983 have been reviewed. It has been determined that all items vere qualified to 10CFR50.49 requirements or "sound reasons to the contrary" have been documented.
In addition, a review of store-room inventories was conducted to determine the level of qualification of all E0 components in inventory. '
Any components not qualified to 10CFR50.49 vere removed from the EQ t inventory.
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Director, Office of Enforcement May 5, 1988 U. S. Nuclear Regulatory Commission Page 11 Corrective Steps Taken to Avoid Further Violations on November 16, 1987, Alabama Power Company revised procedures requiring replacement equipment to be upgraded to 10CFR50.49 or "sound reasons to the contrary" be documented.
Date of Full Compliance Review of storeroom inventories and repla,ement EQ equipment including the disposition of the results of this reviev was completed on May 2, 1988.
CONCLUSION Alabama Power Company believes that the actions described above fully respond to the conditions identified in the original NOV and to the conditions identified above, many of which vere in fact identified through Alabama Power Company's efforts. In addition, as noted, each of the examples referenced by the NRC in the February 4, 1988 Inspection Report have been evaluated and found to be acceptable for use in EQ applications.
Thus, none of these findings represent conditions of adverce safety significance.
In view of the above, Alabama Power Company maintains that the positions taken in the December 17, 1987 response to the NOV remain valid and we reassert those here.
If you have any questions, plesse advise.
Respectfully submitted, AJAy^ POV.R COKPANY /
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R. P. Mcdonald RPN/JARedst-D1V8.21 cci Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. V. H. Bradford i
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