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Category:CORRESPONDENCE-LETTERS
MONTHYEARML16341D1311999-10-15015 October 1999 Discusses Arrangements Made During 991013 Telephone Conversation for Administration of Licensing Exams at Diablo Canyon Power Plant Facility During Wks of 990410 & 990417. Requests Submittal of Ref Matls by Jan 15,2000 ML16341D1291999-10-14014 October 1999 Forwards Insp Repts 50-275/99-15 & 50-323/99-15 on 990920- 24.Two Severity Level 4 Violations Occurred & Being Treated as NCVs ML16342B9961999-10-0606 October 1999 Refers to OI Investigation 4-1998-029 in Response to Complaints from Shift Foreman of Alleged Retaliation for Reporting Safety Concerns.Allegations Not Substantiated ML16342A9081999-09-30030 September 1999 Informs That Staff Review of Util 980327 Response to GL 96-06, Degradation of SG Internals, Did Not Identify Any New Concerns & Concludes That Util Response to GL Provides Reasonable Assurance That Conditions of SG Compliant ML16342A9111999-09-29029 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & Pse&G Responses for Diablo Canyon NPP ,990701 & 990923.Informs That Staff Reviewed Responses & Concluded That All Requested Info Provided.Considers GL 98-01 Closed for Diablo Canyon IR 05000275/19990071999-09-29029 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/99-07 & 50-323/99-07 on 990727 ML16342A9091999-09-29029 September 1999 Forwards SER Granting Requests for Relief NDE-12.2R8, NDE-13-2R8,NDE-14.2R8,NDE-22.2R8 & NDE-25.2R8 Pursuant to 10CFR50.55a(g)(6)(i) for Second 10-year ISI Interval for Diablo Canyon,Unit 2 ML16342A8981999-09-20020 September 1999 Requests That PG&E Update ERDS Dpls Submitted in to Provide Missing Info ML16342B9901999-09-20020 September 1999 Forwards SE Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML16342A9011999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Diablo Canyon & Did Not Identify Any Areas in Which Performance Warranted Add Insp Effort Beyond Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next 7 Months ML20212B1681999-09-13013 September 1999 Forwards Insp Repts 50-275/99-12 & 50-323/99-12 on 990711- 08-21.Four Violations Being Treated as Noncited Violations ML16342A8881999-08-25025 August 1999 Forwards Insp Repts 50-275/99-13 & 50-323/99-13 on 990802- 06.No Violations Noted.Purpose of Insp,To Review Solid Radioactive Waste Mgt & Radioactive Matls Transportation Programs ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML16342C1331999-08-11011 August 1999 Ack Receipt of Transmitting Rev 3,change 18 to Diablo Canyon Nuclear Power Plant Emergency Plan ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML16342A8751999-07-30030 July 1999 Forwards Insp Repts 50-275/99-10 & 50-323/99-10 on 990529-0710.Four Violations Being Treated as Noncited Violations ML16342A8691999-07-29029 July 1999 Forwards Insp Repts 50-275/99-08 & 50-323/99-08 on 990628-0702.No Violations Noted.Radiological Environ & Meterological Monitoring Sys Were Effectively Implemented ML20210H6181999-07-27027 July 1999 Forwards Insp Repts 50-275/99-07 & 50-323/99-07 on 990503- 0714.Apparent Violations Being Considered for Escalated Enforcement Action ML16342A8661999-07-26026 July 1999 Advises That 981021 Application for Amends to Licenses DPR-80 & DPR-82 to Modify TS Re Voltage & Time Delay Setpoints for First Level Undervoltage Relays & Second Level Undervoltage Relays Being Treated as Withdrawn ML16342A8541999-07-15015 July 1999 Submits Summary of 990701 Meeting with Util in Region IV Ofc to Discuss Performance of Different Groups During Refueling Outage 1R9 & Plans for Continued Performance Improvement ML16342A8461999-06-30030 June 1999 Discusses Closeout of Responses to RAI Re GL 92-01,Rev 1, Suppl 1, Rv Structural Integrity, for Plant,Units 1 & 2 ML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address IR 05000275/19990061999-06-25025 June 1999 Forwards Insp Repts 50-275/99-06 & 50-323/99-06 on 990418-0529.Two Violations Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML16342A8381999-06-21021 June 1999 Forwards Corrected Pages (Page 2 of Transmittal Ltr,Pages 3, 7,8,11,12,21,25,28 & 29 of Safety Evaluation & Pages 2,3 & 4 of Table 1 Attached to SER) Re Util 981015 Second 10-year Interval Inservice Insp Program Plan DCL-99-081, Forwards Rev 15 to Diablo Canyon Power Plant,Units 1 & 2 IST Program Plan.Detailed Summary of Changes to IST Program Plan,Encl1999-06-18018 June 1999 Forwards Rev 15 to Diablo Canyon Power Plant,Units 1 & 2 IST Program Plan.Detailed Summary of Changes to IST Program Plan,Encl ML16342A8271999-06-16016 June 1999 Announces Corrective Action Program Insp at Plant,Units 2 & 2,reactor Facilities on 990726-30.Insp Will Evaluate Effectiveness of Activities for Identifying,Resolving & Preventing Issues That Degrade Quality of Plant Operations ML16342A8151999-06-0909 June 1999 Ack Receipt of Ltr Dtd 990312,which Transmitted Change 16, Rev 18 to Physical Security Plan for Diablo Canyon Under Provisions of 10CFR50.54(p).No NRC Approval Required ML16342A8081999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Diablo Canyon Power Plant Emergency Plan Implementing Procedures EP G-1,Emergency Classifications & EP Activation, Rev 27,under Provisions of 10CFR50,App E,Section V ML16342A8061999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Diablo Canyon NPP Er Plan Implementing Procedures,Ep G-1, Emergency Classification & Ep,Activation,Rev 28,under 10CFR50,App E,Section V Provisions.No NRC Approval Required ML16342C1221999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Diablo Canyon Power Plant Emergency Plan,Rev 3,Change 17, Under Provisions of 10CFR50,App E,Section V ML16342C1211999-06-0303 June 1999 Refers to 990602 Meeting with Util in Arlington,Tx Re Planned Electrical Configuration for Refueling Outage 2R9 During Midloop Operation.List of Attendees & Handouts Used by Util Encl ML16342A8021999-06-0303 June 1999 Ack Receipt of Ltr in Response to Request for Addl Info Contained in Ltr to Ruger ,which Forwarded NRC Insp Repts 50-275/98-201 & 50-323/98-201. Actions Described in Ltr Responsive to NRR Concerns ML13319B1431999-06-0202 June 1999 Responds to Comment Made by P Gunter at 990413 Reactor Decommissioning Public Meeting Re New Info Coming Out of Kobe & Northridge Earthquakes by Providing Info on Seismic Design,Procedures & Analyses Used by NRC & NPPs ML16342A7981999-05-27027 May 1999 Forwards Several Documents That Describe Recent NRC Policy Development in Oversight of Safety Cultures as Result of Millstone Experience Per Request ML16342A7951999-05-25025 May 1999 Informs of NRR Reorganization Effective 990328 & That as Part of Reorganization,Div of Licensing Project Mgt Was Created.Reorganization Chart Encl ML16342A7891999-05-14014 May 1999 Forwards Insp Repts 50-275/99-04 & 50-323/99-04 on 990307-0417.Four Violations Identified & Being Treated as non-cited Violations ML16342A7861999-05-14014 May 1999 Submits Summary of 990423 Meeting in San Luis Obispo,Ca to Discuss Results of Ppr,Completed on 990211.List of Attendees & NRC Presentation Slides Encl ML16342C1141999-05-0606 May 1999 Forwards Results of Gfes of Written Operator Licensing Exam, Administered on 990407 to Nominated Employees of Facility. Requests That Training Dept Forward Individual Answer Sheets & Results to Appropriate Individuals ML16340C2241999-05-0303 May 1999 Forwards Insp Repts 50-275/99-02 & 50-323/99-02 on 990405-09.No Violations Noted.Insp Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML16342A7681999-04-15015 April 1999 Ack Receipt of 990326 Response to NRC 990216 Request for Written Response to Explain Why Greater than 5 Percent Post Exam Changes to Test Questions Were Needed & What Actions Taken to Prevent Recurrence.Finds Reply Acceptable ML16342A7691999-04-14014 April 1999 Requests That First Page of Ltr Transmitting NRC Insp Repts 50-275/99-03 & 50-323/99-03 Be Replaced with Encl Page. Initial Transmittal Contained Minor Editorial Error ML16342A7571999-04-0808 April 1999 Forwards SER Accepting Util Emergency Core Cooling Sys Manual & Automatic Switchover from Refueling Water Storage Tank to Containment Sump for Diablo Canyon Power Plant ML20205J3381999-04-0808 April 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Directors Decision Expired. Commission Declined Any Review & Became Final Agency Action on 990406.With Certificate of Svc.Served on 990409 IR 05000275/19990031999-04-0505 April 1999 Corrected Ltr Forwarding Insp Repts 50-275/99-03 & 50-323/99-03 on 990124-0306.Minor Editorial Error Corrected on First Page ML16342C1101999-04-0505 April 1999 Forwards Copy of FEMA Final Rept for 981204 Diablo Canyon Power Plant Medical Drill.Rept Indicates That There Were No Deficiencies & Two Areas Requiring C/A Identified During Drill DCL-99-038, Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f)1999-03-31031 March 1999 Forwards Decommissioning Funding Repts for Diablo Canyon Power Plant,Units 1 & 2 & Humboldt Bay Power Plant,Unit 3, Per Requirements of 10CFR50.75(f) ML16342C1091999-03-30030 March 1999 Forwards Plant Issues Matrix That Was Inadvertently Omitted from PPR for Plant Facility.Encl 1 to PPR Requested to Be Replaced ML16342A7401999-03-25025 March 1999 Forwards Insp Repts 50-275/99-01 & 50-323/99-01 on 990215-26 at Diablo Canyon Npp.No Violations Noted.Purpose of Insp Was to Complete Evaluation of Welding & Welding Insp Program at Diablo Canyon NPP ML16342A7381999-03-23023 March 1999 Refers to PG&E SG 90-day Rept, 90-Day Rept for Voltage- Based Alternate Repair Criteria - Unit 2 Eighth Refueling Outage, Dtd 980628.Forwards SE Concluding PG&E Implemented voltage-based Criteria in Accordance with Licensing Basis ML16342C3241999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Plant PPR Completed on 990211 for Period 980510-990125,to Develop Integrated Understanding of Safety Performance.Historical Listing of Plant Issues & Details of Insp Plan Encl 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML16341F8831990-11-0909 November 1990 Forwards Insp Repts 50-275/90-23 & 50-323/90-23 on 900902- 1013.No Violations Noted ML16341F8871990-11-0808 November 1990 Forwards Mgt Meeting Repts 50-275/90-26 & 50-323/90-26 on 901105 ML16341F8721990-11-0808 November 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/90-16 & 50-323/90-16 ML16341F8661990-10-25025 October 1990 Forwards Insp Repts 50-275/90-24 & 50-323/90-24 on 900917-1005.No Violations or Deviations Noted.Some Maint Procedures Could Be Improved.Detail Examples in Encl Rept ML20058B5331990-10-22022 October 1990 Forwards Partially Withheld Safeguards Insp Repts 50-275/90-17 & 50-323/90-17 on 900924-28.Licensee Identified Violations Reviewed But Not Cited ML16341F8611990-10-19019 October 1990 Forwards Insp Repts 50-275/90-25 & 50-323/90-25 on 900917-1016.No Violations Noted ML16341F8501990-10-16016 October 1990 Advises That Rev 3,Change 10 to Emergency Plan Meets Stds in 10CFR50.47(b) & Requirements of 10CFR50,App E IR 05000323/19900131990-10-0202 October 1990 Ack Receipt of 900813 & 0919 Responses to Violations Noted in Insp Rept 50-323/90-13 Re Signature Responsibility ML16342B7011990-09-25025 September 1990 Advises That Presentation of Certificates to Licensed Operators Scheduled for 901012 ML16341F8411990-09-24024 September 1990 Forwards Insp Repts 50-275/90-19 & 50-323/90-19 on 900722- 0901.No Violations Noted.Mgt Meeting Will Be Scheduled ML16341F8361990-09-20020 September 1990 Forwards Insp Repts 50-275/90-18 & 50-323/90-18 on 900730-0817.No Violations Noted ML16341F8051990-09-0707 September 1990 Forwards Insp Repts 50-275/90-20 & 50-323/90-20 on 900813-17.No Violations Noted ML17083C3061990-08-31031 August 1990 Forwards Insp Repts 50-275/90-21 & 50-323/90-21 on 900813-17.One Noncited Violation Noted ML16341F8101990-08-28028 August 1990 Advises That Objectives & Scenario Manual Acceptable for 901003 Emergency Preparedness Exercise,Per 900702,03 & 05 Requests ML17083C2931990-08-13013 August 1990 Forwards Insp Repts 50-275/90-15 & 50-323/90-15 on 900610-0721.No Violations Noted.Weaknesses Identified ML16341F7781990-08-0202 August 1990 Discusses Generic Fundamentals Exam on 900606 & Forwards Exam Form W/Answers & Results ML16341F7771990-07-31031 July 1990 Discusses Investigation Case 5-89-012 Re Activities Under Licenses DPR-80 & DPR-82.Investigation Involved Concerns Associated W/Deficient Vendor Audits & Interview of Personnel.No Willful Violations Identified ML16341F7791990-07-30030 July 1990 Reviews 60-day Response to Generic Ltr 88-20 Re Individual Plant Exams for Diablo Canyon Units 1 & 2 ML16342B6921990-07-27027 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/90-01 & 50-323/90-01.Enforcement Item 275/90-01-01 Withdrawn Based on Addl Info Provided in IR 05000275/19900081990-07-13013 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/90-08 & 50-323/90-08 ML16341F7691990-07-13013 July 1990 Forwards Insp Repts 50-275/90-13 & 50-323/90-13 on 900422- 0609 & Notice of Violation ML17095A5601990-06-29029 June 1990 Forwards Ltr to Rc Mcdiarmid That Transmits Directors Decision DD-90-3 Issued on 900614,per 10CFR2.206.Notice of Issuance Also Encl.W/O Encls ML17083C2621990-06-14014 June 1990 Forwards Notice of Violation Re Antitrust License Conditions (6),7(a),7(d) & 9(a).Directors Decision Also Encl ML20059M9781990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML16341F7401990-06-12012 June 1990 Forwards Rept Re NRC Review of Plant long-term Seismic Program.Rept Describes Some Reanalysis Performed on Augmented Data Base ML16341F7361990-06-0707 June 1990 Grants Temporary Waiver of Compliance from Tech Spec 3.3.1 Requirement Re Reactor Coolant Pump Underfrequency Reactor Trip Instrumentation,Per 900601 Request IR 05000275/19900021990-06-0505 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/90-02 & 50-323/90-02.Actions Will Be Verified During Future Insp ML16342B6761990-05-25025 May 1990 Forwards SER Accepting Response to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML16341F7241990-05-25025 May 1990 Forwards Insp Repts 50-275/90-14 & 50-323/90-14 on 900430- 0504 & Notice of Violation ML20043C3631990-05-23023 May 1990 Forwards State of CA 1988 Environ Radiological Measurements Rept,Per Cooperative Agreement NRC-32-83-684.State Obtains & Analyzes Samples of Environ Media to Verify Adequacy of Environ Radiological Measurements ML16341F7311990-05-23023 May 1990 Forwards Insp Repts 50-275/90-11 & 50-323/90-11 on 900402-0504.Violation Noted But Not Cited ML16341F7041990-05-18018 May 1990 Advises That Response to Generic Ltr 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Matls & Impact on Plant Operations Acceptable,Based on Mods Approved Via Amends 54 & 53 to Licenses DPR-80 & DPR-82,respectively ML16342B6731990-05-18018 May 1990 Advises That 891113 Response to Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs, Satisfactory ML16341F6991990-05-16016 May 1990 Informs That Util Response to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latch Relays Mfg by GE Acceptable,Based on Confirmation That Subj Relays Not in Use in Class 1E Applications at Facility IR 05000275/19900051990-05-0909 May 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/90-05 & 50-323/90-05 ML16342B6701990-05-0808 May 1990 Provides Info Re Generic Fundamentals Exam Section of Operating Licensing Written Exam to Be Administered on 900606.List of Lodging in Immediate Area & Name & Phone Number of Regional Contact Encl IR 05000275/19890321990-05-0707 May 1990 Discusses Final SALP Repts 50-275/89-32 & 50-323/89-32 for Period Aug 1988 - Dec 1989 ML16341F6771990-04-27027 April 1990 Forwards Request for Addl Info Re Soil Structure Interaction at Plant Based on Questions Raised During 891102-03 Soil Structure Interaction Meeting in San Francisco.Response Requested by 900615 ML16341F6701990-04-26026 April 1990 Requests Addl Info Re NRC Review of long-term Seismic Program ML16341F6811990-04-23023 April 1990 Ack Receipt of Requesting Exemption from 10CFR26 on Behalf of Certain Employees at Plant ML20034B4981990-04-20020 April 1990 Forwards Insp Repts 50-275/90-02 & 50-323/90-02 on 900205-14 & Notice of Violation.Util Should Adhere to Procedures Re Method for Control of Personnel Access Into Vital Areas.Rept & Notice of Violation Withheld (Ref 10CFR73.21) ML16341F6781990-04-16016 April 1990 Forwards SALP Mgt Meeting Repts 50-275/90-12 & 50-323/90-12 on 900322.Comments Re Meeting May Be Provided within 30 Days of Ltr Date ML16341F6601990-04-12012 April 1990 Forwards Documents & Request for Addl Info Re NRC Review of long-term Seismic Program During 900430 & 0501 Ground Motion Meeting ML16341F6711990-04-0909 April 1990 Forwards Insp Repts 50-275/90-09 & 50-323/90-09 on 900321-23.No Violations or Deviations Noted ML16341F6511990-04-0909 April 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/89-34 & 50-323/89-34 ML16341F6521990-04-0606 April 1990 Forwards Request for Addl Info Re NRC Review of Masonry Wall Issues at Plant.Each Issue in Encl Request Should Be Addressed by 900520 ML16341F6471990-04-0505 April 1990 Ack Receipt of & Payment of Civil Penalty in Amount of $50,000.Disagrees W/Util Conclusion That Opening Sump Access Hatches Did Not Render Containment Recirculation Sump Inoperable ML16341F6631990-04-0404 April 1990 Forwards Insp Repts 50-275/90-05 & 50-323/90-05 on 900128-0310 & Notice of Violation IR 05000275/19900011990-04-0202 April 1990 Forwards Insp Repts 50-275/90-01 & 50-323/90-01 on 900108-12 & 0122-0202 & Notice of Violation IR 05000275/19890291990-04-0202 April 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/89-29 & 50-323/89-29 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML16341D1311999-10-15015 October 1999 Discusses Arrangements Made During 991013 Telephone Conversation for Administration of Licensing Exams at Diablo Canyon Power Plant Facility During Wks of 990410 & 990417. Requests Submittal of Ref Matls by Jan 15,2000 ML16341D1291999-10-14014 October 1999 Forwards Insp Repts 50-275/99-15 & 50-323/99-15 on 990920- 24.Two Severity Level 4 Violations Occurred & Being Treated as NCVs ML16342B9961999-10-0606 October 1999 Refers to OI Investigation 4-1998-029 in Response to Complaints from Shift Foreman of Alleged Retaliation for Reporting Safety Concerns.Allegations Not Substantiated ML16342A9081999-09-30030 September 1999 Informs That Staff Review of Util 980327 Response to GL 96-06, Degradation of SG Internals, Did Not Identify Any New Concerns & Concludes That Util Response to GL Provides Reasonable Assurance That Conditions of SG Compliant IR 05000275/19990071999-09-29029 September 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-275/99-07 & 50-323/99-07 on 990727 ML16342A9111999-09-29029 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & Pse&G Responses for Diablo Canyon NPP ,990701 & 990923.Informs That Staff Reviewed Responses & Concluded That All Requested Info Provided.Considers GL 98-01 Closed for Diablo Canyon ML16342A9091999-09-29029 September 1999 Forwards SER Granting Requests for Relief NDE-12.2R8, NDE-13-2R8,NDE-14.2R8,NDE-22.2R8 & NDE-25.2R8 Pursuant to 10CFR50.55a(g)(6)(i) for Second 10-year ISI Interval for Diablo Canyon,Unit 2 ML16342A8981999-09-20020 September 1999 Requests That PG&E Update ERDS Dpls Submitted in to Provide Missing Info ML16342B9901999-09-20020 September 1999 Forwards SE Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML16342A9011999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of Diablo Canyon & Did Not Identify Any Areas in Which Performance Warranted Add Insp Effort Beyond Core Insp Program.Nrc Plan to Conduct Only Core Insps at Facility Over Next 7 Months ML20212B1681999-09-13013 September 1999 Forwards Insp Repts 50-275/99-12 & 50-323/99-12 on 990711- 08-21.Four Violations Being Treated as Noncited Violations ML16342A8881999-08-25025 August 1999 Forwards Insp Repts 50-275/99-13 & 50-323/99-13 on 990802- 06.No Violations Noted.Purpose of Insp,To Review Solid Radioactive Waste Mgt & Radioactive Matls Transportation Programs ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML16342C1331999-08-11011 August 1999 Ack Receipt of Transmitting Rev 3,change 18 to Diablo Canyon Nuclear Power Plant Emergency Plan ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML16342A8751999-07-30030 July 1999 Forwards Insp Repts 50-275/99-10 & 50-323/99-10 on 990529-0710.Four Violations Being Treated as Noncited Violations ML16342A8691999-07-29029 July 1999 Forwards Insp Repts 50-275/99-08 & 50-323/99-08 on 990628-0702.No Violations Noted.Radiological Environ & Meterological Monitoring Sys Were Effectively Implemented ML20210H6181999-07-27027 July 1999 Forwards Insp Repts 50-275/99-07 & 50-323/99-07 on 990503- 0714.Apparent Violations Being Considered for Escalated Enforcement Action ML16342A8661999-07-26026 July 1999 Advises That 981021 Application for Amends to Licenses DPR-80 & DPR-82 to Modify TS Re Voltage & Time Delay Setpoints for First Level Undervoltage Relays & Second Level Undervoltage Relays Being Treated as Withdrawn ML16342A8541999-07-15015 July 1999 Submits Summary of 990701 Meeting with Util in Region IV Ofc to Discuss Performance of Different Groups During Refueling Outage 1R9 & Plans for Continued Performance Improvement ML16342A8461999-06-30030 June 1999 Discusses Closeout of Responses to RAI Re GL 92-01,Rev 1, Suppl 1, Rv Structural Integrity, for Plant,Units 1 & 2 IR 05000275/19990061999-06-25025 June 1999 Forwards Insp Repts 50-275/99-06 & 50-323/99-06 on 990418-0529.Two Violations Occurred & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy ML16342A8381999-06-21021 June 1999 Forwards Corrected Pages (Page 2 of Transmittal Ltr,Pages 3, 7,8,11,12,21,25,28 & 29 of Safety Evaluation & Pages 2,3 & 4 of Table 1 Attached to SER) Re Util 981015 Second 10-year Interval Inservice Insp Program Plan ML16342A8271999-06-16016 June 1999 Announces Corrective Action Program Insp at Plant,Units 2 & 2,reactor Facilities on 990726-30.Insp Will Evaluate Effectiveness of Activities for Identifying,Resolving & Preventing Issues That Degrade Quality of Plant Operations ML16342A8151999-06-0909 June 1999 Ack Receipt of Ltr Dtd 990312,which Transmitted Change 16, Rev 18 to Physical Security Plan for Diablo Canyon Under Provisions of 10CFR50.54(p).No NRC Approval Required ML16342A8061999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Diablo Canyon NPP Er Plan Implementing Procedures,Ep G-1, Emergency Classification & Ep,Activation,Rev 28,under 10CFR50,App E,Section V Provisions.No NRC Approval Required ML16342A8081999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Diablo Canyon Power Plant Emergency Plan Implementing Procedures EP G-1,Emergency Classifications & EP Activation, Rev 27,under Provisions of 10CFR50,App E,Section V ML16342C1221999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Diablo Canyon Power Plant Emergency Plan,Rev 3,Change 17, Under Provisions of 10CFR50,App E,Section V ML16342C1211999-06-0303 June 1999 Refers to 990602 Meeting with Util in Arlington,Tx Re Planned Electrical Configuration for Refueling Outage 2R9 During Midloop Operation.List of Attendees & Handouts Used by Util Encl ML16342A8021999-06-0303 June 1999 Ack Receipt of Ltr in Response to Request for Addl Info Contained in Ltr to Ruger ,which Forwarded NRC Insp Repts 50-275/98-201 & 50-323/98-201. Actions Described in Ltr Responsive to NRR Concerns ML13319B1431999-06-0202 June 1999 Responds to Comment Made by P Gunter at 990413 Reactor Decommissioning Public Meeting Re New Info Coming Out of Kobe & Northridge Earthquakes by Providing Info on Seismic Design,Procedures & Analyses Used by NRC & NPPs ML16342A7981999-05-27027 May 1999 Forwards Several Documents That Describe Recent NRC Policy Development in Oversight of Safety Cultures as Result of Millstone Experience Per Request ML16342A7951999-05-25025 May 1999 Informs of NRR Reorganization Effective 990328 & That as Part of Reorganization,Div of Licensing Project Mgt Was Created.Reorganization Chart Encl ML16342A7891999-05-14014 May 1999 Forwards Insp Repts 50-275/99-04 & 50-323/99-04 on 990307-0417.Four Violations Identified & Being Treated as non-cited Violations ML16342A7861999-05-14014 May 1999 Submits Summary of 990423 Meeting in San Luis Obispo,Ca to Discuss Results of Ppr,Completed on 990211.List of Attendees & NRC Presentation Slides Encl ML16342C1141999-05-0606 May 1999 Forwards Results of Gfes of Written Operator Licensing Exam, Administered on 990407 to Nominated Employees of Facility. Requests That Training Dept Forward Individual Answer Sheets & Results to Appropriate Individuals ML16340C2241999-05-0303 May 1999 Forwards Insp Repts 50-275/99-02 & 50-323/99-02 on 990405-09.No Violations Noted.Insp Used Annual Licensed Operator Requalification Exams to Assess Licensed Operator Performance ML16342A7681999-04-15015 April 1999 Ack Receipt of 990326 Response to NRC 990216 Request for Written Response to Explain Why Greater than 5 Percent Post Exam Changes to Test Questions Were Needed & What Actions Taken to Prevent Recurrence.Finds Reply Acceptable ML16342A7691999-04-14014 April 1999 Requests That First Page of Ltr Transmitting NRC Insp Repts 50-275/99-03 & 50-323/99-03 Be Replaced with Encl Page. Initial Transmittal Contained Minor Editorial Error ML20205J3381999-04-0808 April 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Directors Decision Expired. Commission Declined Any Review & Became Final Agency Action on 990406.With Certificate of Svc.Served on 990409 ML16342A7571999-04-0808 April 1999 Forwards SER Accepting Util Emergency Core Cooling Sys Manual & Automatic Switchover from Refueling Water Storage Tank to Containment Sump for Diablo Canyon Power Plant IR 05000275/19990031999-04-0505 April 1999 Corrected Ltr Forwarding Insp Repts 50-275/99-03 & 50-323/99-03 on 990124-0306.Minor Editorial Error Corrected on First Page ML16342C1101999-04-0505 April 1999 Forwards Copy of FEMA Final Rept for 981204 Diablo Canyon Power Plant Medical Drill.Rept Indicates That There Were No Deficiencies & Two Areas Requiring C/A Identified During Drill ML16342C1091999-03-30030 March 1999 Forwards Plant Issues Matrix That Was Inadvertently Omitted from PPR for Plant Facility.Encl 1 to PPR Requested to Be Replaced ML16342A7401999-03-25025 March 1999 Forwards Insp Repts 50-275/99-01 & 50-323/99-01 on 990215-26 at Diablo Canyon Npp.No Violations Noted.Purpose of Insp Was to Complete Evaluation of Welding & Welding Insp Program at Diablo Canyon NPP ML16342A7381999-03-23023 March 1999 Refers to PG&E SG 90-day Rept, 90-Day Rept for Voltage- Based Alternate Repair Criteria - Unit 2 Eighth Refueling Outage, Dtd 980628.Forwards SE Concluding PG&E Implemented voltage-based Criteria in Accordance with Licensing Basis ML16342C3241999-03-19019 March 1999 Advises of NRC Planned Insp Effort Resulting from Plant PPR Completed on 990211 for Period 980510-990125,to Develop Integrated Understanding of Safety Performance.Historical Listing of Plant Issues & Details of Insp Plan Encl ML16342A7341999-03-18018 March 1999 Forwards FEMA Final Rept for 981104,emergency Preparedness Exercise.Rept Indicates No Deficiencies During Exercise, However 7 Areas Requiring Corrective Action Identified ML16342A7291999-03-12012 March 1999 Responds to Petition Requesting That NRC Modify Operating Licenses for Diablo Canyon Nuclear Power Plant to Require That Owner Have Independent Contractor Evaluate Plant Safety Culture ML16342A7281999-03-0404 March 1999 Forwards Draft SE on Proposed Conversion of CTSs for Plant, Units 1 & 2 to Itss.Provides Draft SE for Review to Verify Accuracy & to Prepare Certified ITSs for Plant to Be Submitted for Issuance in Conversion Amend 1999-09-30
[Table view] |
See also: IR 05000275/1988002
Text
ACCELE RATED
DISCI'MBU'EON
DEMONSTRATION
SYSTEM
REGULATORY"INFORMATION"DISTRIBUTION SYSTEM (RIDS)
<<ACCESSION
NBR: 8811030085
DOC ~ DATE: 88/10/21
NOTARIZED:
NO
DOCKET
CIL:50-275 Diablo Canyon Nuclear
Power Plant, Unit 1, Pacific
Ga
05000275
50-323 Diablo Canyon Nuclear
Power Plant, Unit 2, Pacific
Ga
05000323
UTH.NAME
AUTHOR AFFILIATION
CHAFFEE,A.E.
Region
5, Ofc of the Director
RECIP.NAME
RECIPIENT AFFILIATION
SHIFFER,J.D.
Pacific Gas
8 Electric Co.
SUBJECT:
Ack receipt of 880527 ltr informing NRC of steps
to correct
violations noted in Insp Repts
50-275/88-02
6 50-323/88-02.
DISTRIBUTION CODE:
IE01D
COPIES
RECEIVED:LTR
/
ENCL J
SIZE:
TITLE: General
(50 Dkt)-Insp Rept/Notice of Violation Response
NOTES:
RECIPIENT..
-
.
COPIES
ID CODE/NAME
LTTR ENCL
PD5
PD
1
1
RECIPIENT
ID CODE/NAME
ROODgH
-.COPIES
LTTR ENCL
1
1
INTERNAL: ACRS
DEDRO
NRR/DLPQ/PEB
11
NRR/DOEA DIR ll
NRR/DREP/RPB
10
NRR/PMAS/ILRB12
O~IEQERMANiJ
EG FTD
02
RGN
F LE
01
EXTERNAL: LPDR
NSIC
2
2
1,
1
1
-
1-
1
1,
2
2
1
1
1
1
1
1
1. -...1 -.
2
2
1'
AEOD
NRR MORISSEAU,D
NRR/DLPQ/QAB 10
NRR/DREP/EPB
10
NRR/DRIS DIR 9A
NUDOCS-ABSTRACT
OGC/HDS2
RES/DSR
DEPY
NRC
PDR
RESL MARTIN,D
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
D
S
TOTAL NUMBER OF COPIES
REQUIRED:
LTTR
26
ENCL
26
Docket Nos. 50-275
and 50-323,
OCT 2
1 l988
Pacific
Gas
and Electric Company
77 Beale Street,
Room 1451
San Francisco,
CA
94106
Attention:
Mr. J.
D. Shiffer, Vice President
Nuclear Power Generation
Gentlemen:
Thank you for your letter dated
May 27,
1988, in response
to our Notice of
Violation and Inspection
Report No. 88-02, dated April 27,
1988, informing us
of the steps
you have taken to correct the items which we brought to your
attention.
Your corrective actions will be verified during
a future
inspection.
In your response
to the Notice of Deviation, you stated your position that
PGIEE does
not believe that there
was
a deviation of the Redundancy
Requirements
of Regulatory
Guide 1.97.
Your response
to the Notice of
Deviation is being forwarded to the Office of Nuclear Reactor Regulation for
review.
Your cooperation with us is appreciated.
Sincerely,
bcc w/copy of'etter 5/27/88:
'ocket
file
State of California
A. Johnson
G.
Cook
B. Faulkenberry
J. Martin
Resident
Inspector
Project Inspector
J. Zollicoffer
M. Smith
A. E. Chaffee,
Deputy Director
Division of Reactor Safety
and Projects
REGION
V
JNel fi
10/~i/88
SRic ards
RJPate
10/9/88
10/0 /88
AJohnson
AChaffee
10
/88
10/
/88
t( (
R
U ST
C
P
EQU ST
RE/VEST
Y
/
NO
YES /
NO
YES /
N
@sf>030085
8~>
PDR
ADOCK O>00
G
UES
C
PY
RE/
S
P
YES /
NO
YES /
NO
DR
YES /
NO
e
~( ~D/
t
P":ific Ga. aa: 'tectri."'. mpany
o410t,
.26iS7
'I
I
May 27,
1988
PGIEE Letter No. DCL-88-141
U.S. Nuclear Regulatory Commission
ATTN:
Document Control
Desk
Hashington,
D.C.
20555
r
Re:
Docket No. 50-275,
OL-DPR-80
Docket No. 50-323,
OL-DPR-82
Diablo Canyon Units
1 and
2
Reply to Notice of Violation and Notice of Deviation,
and Three
Unresolved
Items. Regarding Regulatory Guide
1..97
Implementation,
in NRC Inspection
Report 50-275/88-02
and
50-323/88-02
Gentlemen:
NRC Inspection
Report 50-275/88-02
and 50-323/88-02 (Inspection
Report),
dated April 27,
1988, forwarded
a Notice of Violation and
a
Notice of Deviation regarding calibration intervals of certain
instruments
and the redundancy of steam generator
wide range level
instrumentation.
The Inspection
Report also identified three
unresolved
items regarding neutron flux monitoring, isolation of
certain, instrumentation,
and the frequency for testing the status of
standby
power which require additional
NRC staff review.
Enclosure
1 provides
PG&E's response
to the Notice of Violation and
the Notice of Deviation.
Enclosure
2 provides
PGIItE's response
to
the three unresolved
items identified in the Inspection Report.
Based
on conversations
with the
NRC and Region
V Staffs, it is
PGIEE's understanding
that, in addition to review of the three
unresolved
items discussed
in Enclosure
2, the method for powering
the steam generator
wide range level instrumentation will also
be
reviewed for acceptability.
Kindly acknowledge receipt of this material
on the enclosed
copy of
this letter and return it in the enclosed
addressed
envelope.
cerely,
D. Shi
r
cc:
J.
B. Hartin
H. M. Hendonca
P.
P. Narbut
B. Norton
H. Rood
B. H. Vogler
CPUC
Diablo Distribution
Enclosures
2094S/0059K/THL/2059
SS0527
PDR
ADOCK 05000275
~ fP
Q
DCD
W)gr
t
)
5r- ls.~
PGhE Let'. ~ ": Ho. D,L-i"- . 4 i
ENCLOSURE
1
REPLY TO NOTICE OF VIOLATION AND NOTICE OF DEVIATION IN NRC
INSPECTION
REPORT
NOS. 50-275/88-02
AND 50-323/88-02
In NRC Inspection
Reports
50-275/88-02
and 50-323/88-02
(Inspection
Report)
dated April 27.
1988,
NRC Region
V issued
a Notice of Violation citing one
Severity Level IV violation and a Notice of Deviation for Diablo Canyon
Power
Plant
(DCPP).
The statements
of violation and deviation
and
PGEE's
responses
are
as follows:
A.
TAT H NT
F V
A
N
Duririg an
NRC inspection
conducted
during the period of
February 29,
1988 through Harch 4,
1988,
and in accordance
with the "General
Statement of Policy and Procedure for NRC
Enforcement Actions," 10
CFR Part 2, Appendix
C (1987), the
following violation was identified.
'
Technical Specification 6.8.1 requires that written
procedures
shall
be established,
implemented
and
maintained
covering the activities referenced
in that
Technical Specification.
One of the activities
referenced
is-the applicable procedure- recommended
in
Appendix A of Regulatory Guide 1.33, Revision 2,
February
1978.
Section
8 in Appendix A of Regulatory Guide 1.33,
Revision
2 states
in part:
"Procedures
of a type
appropriate to the circumstances
should
be provided to
ensure that tools, gauges,
instruments,
controls,
and
other measuring
and testing devices
are properly
controlled, calibrated,
and ad]usted at specified
periods to maintain accuracy.
Specific examples of
such equipment to be calibrated
and tested
are readout
instruments, ..."
2094S/0059K
1-1
Diablo Canyon administrative
procedure
AP C-450,
"Instrument
and Controls Department Preventative
Haintenance
Program"
and the Diablo Canyon Recurring
Task Scheduler
(RTS) specify calibration requirements
for Regulatory Guide 1.97 instrumentation.
The
Condensate
Storage
Tank (CST) level instruments
and
the containment
spray flow instruments
are required
by
the
RTS to be calibrated
on
18 month intervals.
Contrary to the above, at the time of the inspection,
the following Regulatory Guide 1.97 instruments
were
not calibrated within the interval established
by the
RTS.
Unit
1
CST level transmitter LT-44, work order--
number R0014267,
was
due for calibration
on
November 15,
1986.
This instrument
was
approximately
15 months overdue.
2.
3.
Unit 2 CST level transmitter
LT-44, work order
number R0016724,
was
due for calibration on
November
15,
1986.
This instrument
was
approximately
15 months overdue.
Unit 2 containment
spray flow transmitted
FT-932,
work order number R0015973,
was
due for
calibration
on April 27,
1987.
This instrument
was approximately
10 months overdue.
This is a Severity Level IV violation.
A NFRV
A
H
PGLE acknowledges
that the violation occurred
as described
in the Inspection
Report.
The periodic testing requirements of Regulatory Guide 1.97 for the
Units
1 and
2 condensate
storage
tank (CST) level transmitters
LT-44 and
Unit 2 containment
spray flow transmitter
FT-932 were incorporated into the
Recurring Task Scheduler
(RTS) computer program with a priority level which
2094S/0059K
1-2
~
~
did not require plant management
revie~ and approval if the scheduled activity
date
was exceeded.
The calibrations
had
been
rescheduled
without plant
management
review due to the inappropriate priorttization.
RR
T
P
A
H
The
CST level transmitters
LT-44 and containment
spray flow transmitter
FT-932
have
been assigned
an appropriate-RTS priori-ty:"The-above violation was
discussed
with all appropriate
IhC and Electrical Haintenance
personnel
to
ensure that they understand
the need to complete Regulatory Guide 1.97
instrumentation calibration -in a timely manner. "- ---.
RR
T
A
N
The transmitters
CT-44 and FT-932 will be recalibrated
by June
15,
1988.
The.
RTS will be reviewed to ensure that testing priority information for
Regulatory Guide 1.97 instruments
has
been correctly. entered.
Any
discrepancies
found during the
RTS review will be promptly corrected.
PG&E
believes that these corrective actions are sufficient to avoid any further
violations.
T
HH
The
RTS review will be completed prior to July 1,
1988 and any discrepancies
will be promptly resolved in accordance
with DCPP procedures.
2094S/0059K
1-3
Pgg,
E4
P
B.
TAT H NT
F
V AT
N
As a result of the inspection
conducted
during the period
of February
29 through Harch 4,
1988,
a deviation from your
commitments to the
NRC was 1dentified.
In accordance
with
the General
Statement of Policy and Procedure for NRC
Enforcement Actions, l0 CFR Part 2, Append1x
C (1987), the
following deviation
was 1dentified:
The D1ablo Canyon
FSAR, Section 7.5.l.ll - Compliance
to Regulatory Guide 1.97 states:
"Table 7.5-6
summarizes
the compl1ance of Diablo Canyon
Power Plant
w1th Regulatory
Gu1de 1.97";
Table 7.5-6 +lassifies-
the Wide Range
Steam Generator
Level instrumentation
as category
1 1nstrumentation
with redundancy.
Table
1 of Regulatory Guide 1.97, Revision
3 states
that for Category l instrumentation,
"Redundant or
d1verse
channels
should
be electrically. independent
.
and physically separated
from each other and from
equ1pment
not classif1ed
1mportant to safety in
accordance
with Regulatory Guide 1.75, "Physical
Independence
of Electrical Systems,"
up to and
1ncluding any 1solation device."
Contrary to the above, at the time of the 1nspection,
the Wide Range
Steam Generator
Level instrumentation
d1d not meet the redundancy criter1a
1n that all four
of the Wide Range
Steam Generator
Level instruments
were powered
from one power supply.
This is a Deviation.
A
NFRTK
VA
N
As stated
1n the notice of dev1ation,
the wide range
steam generator
level
instrumentation is powered
from one power supply (protection set IV). Kowever,
PG&E does not believe there is a deviation from the redundancy
requ1rements
of
Regulatory Guide 1.97, Revision 3.
In the implementation of post THI
requirements,
PGLE as
a member of the West1nghouse
Owners
Group
(WOG)
2094S/0059K
1-4
worked to develop
an integrated
approach to the various requirements.
The
following discussion
describes
how PG&E meets
Regulatory Guide 1.97,
Revision 3, for secondary
heat sink mon1tor1ng
and the specif1c
steps that
PG8E will take to more clearly. document this compliance.
The steam generator
wide range level 1nstrumentation
provides
one of the
means
to monitor secondary
heat s1nk.. The
WOG emergency
response
guidelines
(ERGs)
used for 'development
o'f the emergency operating
procedures
monitor the
following variables to determine if safety in)ection (SI) flow can
be reduced:
'
'CS Subcooling
~
Secondary
Heat Sink [Total Auxiliary Feedwater
(AFW) Flow or Narrow
Range
Steam Generator
(SG) Water Level3
RCS Pressure
~
Pres'surizer
Level
The basis.4'or-specifying-two
alternate
indications .for monitoring
secondary'eat
sink is that the steam generator
water level generally shrinks out of the
narrow range
span following a safety in)ection actuation.
Hence,
1nstrumentation
other than narrow range
steam generator
level must
be used to
monitor process
variables to verify that a secondary
heat sink is available,
or the operator must walt until water level
1s restored within the narrow
range
span
i.n order to reduce safety 1n)ection flow.
The key variable
used
by
the operators
1f steam generator
water level is below the narrow range
span is
the auxiliary feedwater flow in each loop.'t each of the
DCPP units there is
2094S/0059K
1-5
I
I
one auxi'~iary feedwater flow instrument per loop, 'v
powered
by protection
set I and the other two powered
by protection set III.
Since only one flow
instrument
1s installed per loop, the diverse variable
used to verify
secondary
heat
s1nk is wide range
steam generator level.
There
1s one wide
range level instruaent
per loop at DCPP, all of which are
powered
from
protection set IV.
The redundancy of steam generator
1nstrumentation
is
1ndicated
below by the table of the protection set
power supply wh1ch powers
each instrument for narrow- range
steam generator
water level, auxiliary
feedwater flow, and wide range
steam generator.
PROTECTION
SET
POWER
SUPPLY
Wide Range
Level
Narrow Range
Level
Aux. Feed
Flow
X
X
X
'
X
Wide Range
Level
Narrow Range
Level
Aux. Feed
Flow
m
r
Wide Range
Level
Narrow Range
Level
Aux. Feed
Flow
r
W1de Range
Level
Narrow Range
Level
Aux. Feed
Flow
X
PGEE has identified narrow range
steam generator
water level
as the
key
variable for monitoring secondary
heat sink at
DCPP 1f the water level is
2094S/0059K
1-6
0
with1n the narrow range
span.
As such,
narrow range level will be classified
as
a Regulatory Guide 1.97, Revision
3 Category l variable
and will be added
to Table 7.5-6 of the Diablo Canyon
FSAR Update.
Narrow range
steam generator
level is not listed
1n Regulatory
Gu1de 1.97,
Revis1on 3, and therefore,
was
not listed by PG&E in 1ts submittal.
As shown in the above table,
the narrow
range
steam generator
water level channels
meet the regulatory guide
redundancy
requirements.
If the water level is below the bottom tap of the
narrow range. span,
auxi.liary feedwater flow 1-s-des1gnated
as the key variable-
for monitoring secondary
heat s1nk.
Presently,
Table 7.5-6 of the 01ablo
Canyon
FSAR Update class1fies auxiliary feedwater flow as
a Category
2
variable.
PG&E 11sts auxil.iary feedwater flow as
a Category
2 variable
s1nce
Table
3 of Regulatory Guide 1.97, Revision 3, lists it as
a Category
2
variable.
Except for the redundancy
requirement
per steam generator,
the
auxiliary feedwater flow meets
the Category
1 .variable criteria;
"-
As stated
1n the Regulatory Guide 1.97, Revision 3,
Hhere failure of one accident-monitoring
channel results
tn
1nformation amb1guity (that is, the redundant
displays
disagree)
that could lead operators
to defeat or fail to
accomplish
a required safety funct1on, additional
1nformat1on
should
be provided to allow the operators
to
deduce
the actual
cond1tions in the plant.
This may be
accompl1shed
by prov1ding additional
1ndependent
channels
of 1nformation of the
same variable (addition of an
identical channel) or by providing an independent
channel
to monitor a d1fferent variable that bears
a known
relationship to the mult1ple channels
(addition of a
diverse channel).
Redundant or diverse channels
should
be
electrically independent
and phys1cally separated
from each
other and from equipment not classified important to safety
in accordance
with Regulatory Guide 1.75,
"Phys1cal
Independence
of Electric Systems,"
up to and including any
2094S/0059K
1-7
I
I
~
\\
lI ~
~
~
~
~
~
~
isolation device.
Hithin each
redundant division of a
safety system,
redundant
mon1toring channels
are not needed
except for steam generator
level instrumentation in
two-loop plants.
To meet the redundancy
requirement for mon1toring secondary
heat sink, wide
range
steam generator
water level
was considered
by PG&E as
a diverse variable
to auxiliary feedwater flow.
The power supply arrangement
to the wide range
level instruments
1s powered from vital busses different from those that
power'he
auxiliary .feedwater.flow channels.--.----
T
M T
AK N
To clarify the intended utilization of wide range
steam generator
water level,
Table 7.5-6 of the Diablo Canyon
FSAR Update will be expanded
to show both
narrow and wide. range
steam generator
water l.evel variables.
As stated
abo~e.,-
the narrow range water level will be identified as
a Category
1 variable which
meets the redundancy
requirements.
Hide range
steam generator
water level
w1ll be identified as
a Category l variable except for meeting the redundancy
requirements.
A note will be added to Table 7.5-6 of the Diablo Canyon
FSAR
Update to indicate that wide range
steam generator
water level is considered
a
d1verse variable to auxil1ary feedwater flow to meet the Regulatory Guide
1.97,
Rev1sion 3, Category l redundancy
requirements.
As noted
1n the
previous
Table of instrumentation
powered by the protection set power
supplies,
the actual
DCPP power supply arrangement
meets
the regulatory guide
redundancy
power requirements.
2094S/0059K
AT
NH
N A T
P
T
The plant variables that are used to monitor secondary
heat sink are narrow
range
steam generator water level, auxiliary feedwater flow, and wide range
steam generatoriwater
level.
All three variables will be identified as
Regulatory Guide 1:97, Revision
3 Category
1 variables in Table 7.5-6 of the
Diablo Canyon
FSAR Update with a note added to explain the relationship
between the variables..
This will be included in the next
FSAR Update
l
scheduled for September,
1988.
-
2094S/0059K
1-9
lj
t