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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit 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 ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 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 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 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 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML18107A7011999-06-25025 June 1999 Requests Rev of NRC Records to Reflect Change of PG&E Address ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20205J3381999-04-0808 April 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision Expired. Commission Declined Any Review & Became Final Agency Action on 990406.With Certificate of Svc.Served on 990409 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) ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 DCL-99-033, Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl1999-03-12012 March 1999 Forwards Change 16 to Rev 18 of Diablo Canyon Power Plant Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Safeguards Effectiveness of Plan.Without Encl ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 DCL-99-010, Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld1999-01-26026 January 1999 Forwards Change 15 to Rev 18 of Dcnpp Physical Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan.Encl Withheld ML20202A9831999-01-18018 January 1999 Informs That Modesto Irrigation District No Longer Seeking Addl Interconnection with Pacific Gas & Electric Co at Pittsburg,Ca & Matters First Addressed in 980429 Comments in Opposition to Restructuring of Util Have Now Become Moot IR 05000275/19980121999-01-13013 January 1999 Informs That Insp Repts 50-275/98-12 & 50-323/98-12 Have Been Canceled DCL-98-163, Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld1998-11-24024 November 1998 Forwards Change 14 to Rev 18 of Physical Security Plan. Changes Do Not Decrease Safeguards Effectiveness of Plan & Submitted Pursuant to 10CFR50.54(p).Encl Withheld ML20195G5161998-11-16016 November 1998 Forwards Insp Repts 50-275/98-16 & 50-323/98-16 on 980913- 1024.No Violations Noted ML20155F7951998-11-0303 November 1998 Second Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App C ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util DCL-98-123, Submits Listed Address Changes for NRC Service Lists for Listed Individuals1998-09-0909 September 1998 Submits Listed Address Changes for NRC Service Lists for Listed Individuals DCL-98-108, Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year..1998-08-0707 August 1998 Submits 90-day Response to NRC GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants. Util Has Pursued & Continuing to Pursue Year 2000 Readiness Program Similar to That Outlined in Nei/Nusmg 97-07, Nuclear Util Year.. ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236T2931998-07-24024 July 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities for 5 Yrs.Order Being Issued Due to Falsification of Info on Application to Obtain Unescorted Access to PG&E Plant ML20236T3431998-07-22022 July 1998 Forwards Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.Apparent Violations Identified & Being Considered for Escalated Enforcement Action ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J2251998-07-0101 July 1998 Ltr Contract,Task Order 232 Entitled, Review of Callaway, Comanche,Diablo Canyon & Wolf Creek Applications for Conversion to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236G0691998-06-19019 June 1998 Forwards Endorsement 123 to Neila Policy NF-228,Endorsement 145 to Neila Policy NF-113,Endorsement 124 to Neila Policy NF-228 & Endorsement 89 to Maelu Policy MF-103 ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 1999-09-13
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058B5331990-10-22022 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 ML20059N3331990-10-0202 October 1990 Forwards Notice of Consideration of Issuance of Amend to OL & Proposed NSHC Re 900426 Application for Possession Only License ML20059M6871990-09-14014 September 1990 Forwards Notice of Consideration of Issuance of Amend & Proposed NSHC Re Plant Physical Security Plan for Long Term Defueled Condition ML20059G9421990-09-10010 September 1990 Forwards Amend 115 to License DPR-54 & Safety Evaluation. Amend Revises License Condition Re Fire Protection Plan,Adds Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocates Fire Protection Requirements ML20056B4621990-08-22022 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900724 Request for Exemption to 10CFR50.47 ML20058N6461990-07-31031 July 1990 Forwards Insp Rept 50-312/90-11 on 900527-0706.No Violations Indentified IR 05000312/19900101990-07-0303 July 1990 Forwards Security Insp Rept 50-312/90-10 on 900611-22.No Violations Noted.Major Areas Inspected:Physical Protection. Rept Withheld (Ref 10CFR2.790 & 73.21) ML20055E5151990-07-0303 July 1990 Requests Listed Addl Info on Licensee 900606 Plans Re Diesel Generator Operation as Peaking Power Supplies to Assure That Generators Will Be Maintained in Nondegraded Status ML20055D5441990-06-28028 June 1990 Forwards Request for Addl Info Re 891129,900221 & 0327 Ltrs Concerning Computerized Commitment Tracking Sys,Long Range Scope List & Effluents & Water Mgt Project Action Plan Items Needing Deferral ML20059M9781990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20248D3411989-09-25025 September 1989 Forwards Amend 8 to Indemnity Agreement B-66,reflecting Changes to 10CFR140,effective 890701 ML20248G5731989-09-21021 September 1989 Forwards Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations or Deviations Noted.Concerns Raised Re Contamination Control Practices,Instrumentation Control & Informal Use of Vendor Data for Liquid Effluent Release ML20248G7031989-09-21021 September 1989 Forwards Enforcement Conference Rept 50-312/89-16 on 890915 ML20248G9731989-09-20020 September 1989 Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248B4131989-09-19019 September 1989 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 891004.Map of Area,List of Lodging in Immediate Area & Preliminary Instructions for Taking Exam Encl ML20247H6411989-09-12012 September 1989 Advises That 890816 Revisions to ATWS Mitigation Sys Acceptable W/Requirements of 10CFR50.62(c)(1) ML20248C8401989-09-11011 September 1989 Forwards Insp Rept 50-312/89-14 on 890828-0901.Concern Raised Re Apparent Decrease in Level of Emergency Preparedness.Enforcement Action Will Be Subj of Separate Correspondence ML20247K2231989-09-11011 September 1989 Forwards Amends 123 & 41 to Licenses DPR-61 & NPF-49, Respectively & Safety Evaluation.Amends Change Tech Specs 4.10.1.D.1.h & 4.4.5.4.a.8 to Allow Insp of Steam Generator Tubes by Insertion of Ultrasonic Test Probe ML20247E3371989-09-0707 September 1989 Forwards Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Change Tech Spec Sections 6.10.2.m & 6.10.3 Re Records Retention for Radiological Effluent Monitoring & ODCM ML20247B7561989-09-0606 September 1989 Advises That Response to Generic Ltr 88-17 Re Expeditious Actions for Loss of DHR Acceptable.Training Program Should State That Maint Personnel Included in Program & Daily Walkdowns of Tygon Tube Areas Should Be Performed ML20247C4931989-09-0606 September 1989 Informs That 890901 Insp Determined That Preparedness to Respond to Emergency Was Degraded.Violation Involved Failure to Assign Individuals Qualified Per EPIP to Critical Emergency Response Position IR 05000029/19890141989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246Q0121989-08-31031 August 1989 Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted ML20246K4721989-08-28028 August 1989 Advises That 880419 Rev 2 to Guard Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20246E5321989-08-22022 August 1989 Forward Summary of Sys Engineering/Design Engineering Initiatives & ...Quarterly Sys Status Rept,2nd Quarter 1989.... Rept Demonstrates Depth,Scope & Usefulness of Walkdown as Tool for Assessing Sys Status,Problems & Trends ML20246K4581989-08-18018 August 1989 Forwards Insp Rept 50-312/89-10 on 890603-0721.No Violations Noted ML20246C3941989-08-15015 August 1989 Forwards Safeguards Insp Repts 50-272/89-19,50-311/89-17 & 50-354/89-15 on 890710-14.No Violations Noted ML20246C8211989-08-11011 August 1989 Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891023 in Berlin,Ct.Schedule & General Discussion Groups Shown in Encl ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan ML20248C0561989-08-0303 August 1989 Forwards Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants.Nrc Requested to Be Notified Upon Completion of Human Factors Review ML20245H5331989-08-0202 August 1989 Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed IR 05000275/19890201989-07-31031 July 1989 Forwards Safeguards Insp Repts 50-275/89-20 & 50-323/89-20 on 890710-14.No Violations Noted ML20247H6891989-07-25025 July 1989 Requests Proposed Design Change to Containment Hydrogen Monitoring Sys,W/Schedule for Implementing Change or Justification for Existing Configuration ML20247H5551989-07-21021 July 1989 Advises That Util 890511 Response to SALP Meeting Rept 50-312/88-39 Appropriate & No Changes to 890328 SALP Board Rept Deemed Necessary ML20247F0291989-07-20020 July 1989 Redistributed Forwarding Amend 112 to License DPR-54.Amend Revises Tech Specs Re Increasing Max Closure Time for Selected Containment Isolation Valves & Addition of 12 Valves to Table 3.6-1 ML20247B4031989-07-19019 July 1989 Forwards Errata to Amends 109,110 & 111 to License DPR-54, Correcting Omission of Language from Revised Pages ML20247B2961989-07-17017 July 1989 Forwards Amend 112 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Increase Max Closure Time for Selected Containment Isolation Valves & Add 12 Valves to Table 3.6-1 ML20247J0581989-07-12012 July 1989 Forwards Insp Rept 50-312/89-08 on 890422-0602.No Violations or Deviations Noted ML20246D5241989-07-0707 July 1989 Forwards Request for Addl Info Re 10-yr Internal Inservice Insp Program Plan.Response Requested within 45 Days of Ltr Receipt ML20247A0471989-07-0606 July 1989 Forwards Insp Rept 50-312/89-11 on 890629-30.No Items of Noncompliance Noted IR 05000312/19890011989-06-30030 June 1989 Ack Receipt of Responding to Violations Noted in Insp Rept 50-312/89-01.Reasons for Denial of Violations a & B.2 Will Be Reviewed During Future Insp ML20246A2951989-06-29029 June 1989 Forwards Request for Addl Info Re NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs ML20246B0911989-06-28028 June 1989 Forwards Exemption from Requirements of 10CFR20,App a, Footnote d-2(c) to Allow Use of Radioiodine Protection Factor of 50 for MSA GMR-I Canisters at Plant,Per 881117 Request.Notice of Environ Assessment Also Encl ML20246L2211989-06-26026 June 1989 Forwards Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21, DPR-65 & NPF-49,respectively & Safety Evaluation.Amends Revise Tech Specs by Removing Tech Spec Figures 6.2-1 & 6.2-2 Re Organizations Functional Requirements ML20245J3301989-06-22022 June 1989 Provides Background Info on Regulatory Analysis Supplementing NRC Proposed Backfit,Per 890413 Request.Util Expected to Provide Schedule for Implementation of Required Improvements ML20245F5731989-06-20020 June 1989 Advises That Senior Reactor Operator Licensing Writtem Exams & Operating Exams Scheduled for 890905 & 06-19,respectively. Encl Ref Matl Requested by 890710 in Order to Meet Schedule ML20245E0961989-06-20020 June 1989 Forwards Amend 111 to License DPR-54 & Safety Evaluation. Amend Revises Section 2.C.(4) of License Re Fire Doors & Dampers Based on Reevaluation of Fire Areas in Uitl 1985 Updated Fire Hazards Analysis ML20245F2691989-06-16016 June 1989 Forwards SER Accepting Licensee 850612 Response to Generic Ltr 83-28,Item 4.5.3 Re Trip Reliability & on-line Functional Testing of Trip Sys ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable 1990-09-14
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit 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 ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 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 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 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 ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20205J3381999-04-0808 April 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision Expired. Commission Declined Any Review & Became Final Agency Action on 990406.With Certificate of Svc.Served on 990409 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 IR 05000275/19980121999-01-13013 January 1999 Informs That Insp Repts 50-275/98-12 & 50-323/98-12 Have Been Canceled ML20195G5161998-11-16016 November 1998 Forwards Insp Repts 50-275/98-16 & 50-323/98-16 on 980913- 1024.No Violations Noted ML20155F7951998-11-0303 November 1998 Second Partial Response to FOIA Request for Documents. Records Subj to Request Encl & Identified in App C ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20236T2931998-07-24024 July 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities for 5 Yrs.Order Being Issued Due to Falsification of Info on Application to Obtain Unescorted Access to PG&E Plant ML20236T3431998-07-22022 July 1998 Forwards Insp Repts 50-275/98-11 & 50-323/98-11 on 980526-28.Apparent Violations Identified & Being Considered for Escalated Enforcement Action ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J2251998-07-0101 July 1998 Ltr Contract,Task Order 232 Entitled, Review of Callaway, Comanche,Diablo Canyon & Wolf Creek Applications for Conversion to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program IR 05000275/19980051998-04-17017 April 1998 Forwards Insp Repts 50-275/98-05 & 50-323/98-05 on 980202-06 & 23-27 & 0302-18.No Violations Noted.Insp Focused on Resolution of Previous NRC Insp Findings & Included Review of Issues Identified During Architect/Engineering Insp Rept IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20203G0371998-02-25025 February 1998 Forwards Revised Copy of NRC Form 398, Personal Qualification Statement - Licensee, (10/97) Encl 1,which Has Been Revised to Reflect Current Operator Licensing Policy ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199H6691998-02-0202 February 1998 Ack Receipt of ,Transmitting Rev 18,change 11, to Plant Physical Security Plan,Submitted Under Provisions of 10CFR50.54(p).Role of Video Capture Audible Alarm Sys Needs to Be Addressed in Security Plan,Per 980123 Telcon IR 05000275/19970181997-10-31031 October 1997 Forwards Insp Repts 50-275/97-18 & 50-323/97-18 on 971006- 10.Insp Verified That Liquid & Gaseous Radioactive Waste Effluent Mgt Program Was Properly Implemented.No Violations Noted ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program ML20140G6341997-05-0707 May 1997 Forwards ERDS Implementation Documents Including Data Point Library Updates for McGuire Number 224,WNP2 Number 225, Beaver Valley Number 226 & Calvert Cliffs Number 227. W/O Encl ML20140E6911997-04-25025 April 1997 Forwards Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted ML20137N1591997-03-31031 March 1997 Informs That Licensee Facility Scheduled to Administer NRC GFE on 970409.Sonalsts,Inc Authorized Under Contract to Support NRC Administration of GFE Activities ML20137C7211997-03-21021 March 1997 Forwards Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted ML20134H6271997-02-10010 February 1997 Fifth Partial Response to FOIA Request for Documents.Records in App I Encl & Available in Pdr.App J Records Withheld in Part (Ref FOIA Exemption 5) & App K Records Completely Withheld (Ref FOIA Exemption 5) ML20134K3421997-02-0606 February 1997 Conveys Results & Conclusions of Operational Safeguards Response Evaluation Conducted by NRR at Plant,Units 1 & 2, on 960909-12.W/o Encl ML20129J4001996-10-18018 October 1996 Forwards Order Approving Corporate Restructuring by Establishment of Holding Company & Safety Evaluation ML20129G7431996-09-27027 September 1996 Forwards Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Observed ML20129G6121996-09-24024 September 1996 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App C,E,F & G.Documents Available in Pdr.App E,F & G Documents Partially Withheld Ref FOIA Exemptions 4 & 6.App D Record Listed as Copyright ML20149H8171994-12-23023 December 1994 Advises That 941010 & 1102 Changes 4 & 5 to Rev 18 of Physical Security Plan,Respectively Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20059L5031994-01-28028 January 1994 Extends Invitation to Participate in Workshop Re Emergency Preparedness & Incident Response on 940222 in Arlington,Tx ML20059J9771994-01-14014 January 1994 Informs That Document Rancho Seco ISFSI Sar,Vol Iv,Drawings & Calculations Submitted on 931027,w/Pacific Nuclear Fuel Services Group Affidavit of 931006 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5),as Requested ML20058D6291993-11-19019 November 1993 Forwards Exemption from Requirements of 10CFR140.11(a)(4) to Extent That Primary Financial Protection in Stated Amount Shall Be Maintained ML20058A1211993-11-16016 November 1993 Forwards Safeguards Info Referenced in Preliminary Draft Guide Re Proposed Rule for Protection Against Manevolent Use of Vehicles at Nuclear Power Plants.Encl Withheld ML20058C9721993-11-0202 November 1993 Ack Receipt of Transmitting Rev 6 of Section 5 to Plant Emergency Plan.Advises Revised Emergency Plan Continues to Meet Planning Stds in 10CFR50.47(b) & Requirements of 10CFR50 App E ML20057D1841993-09-27027 September 1993 Grants Exemption from Requirements in 10CFR50.120 to Establish,Implement,& Maintain Training Programs,Using Sys Approach to Training,For Categories of Personnel Listed in 10CFR50.120.Exemption Effective 931122 & Encl IR 05000312/19930031993-09-24024 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/93-03 1999-09-13
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, i 2 2 MAY 1987 Mr. G. Carl Andognini Chief Executive Office, Nuclear Sacramento Municipal Utilities District 14440 Twin Cities Road Herald, California 95638-9799
Dear Mr. Andognini:
SUBJECT:
INFORMATION RELATIVE TO RHR DURING MID-LOOP OPERATIONS Diablo Canyon lost RHR while in mid-loop operation on April 10, 1987, and it was 8 G inuths before RHR was restarted. During more than half of this time, the core was cooled by boiling.
We believe problems associated with this event are generic tt PWR's equipped with "U" tube steam generators, with some a]plicability to P6Rs with once through steam generators. These problems s1ould be addresseo prior to mid-loop operation in any PWR. Enclosure I summarizes the concerns an.f provides recom-mended actions. Enclosure 2 describes the short term Diablo (anyon response to the event, and was implemented prior to our completion of Enclosure 1.
Although we are not aware of any near term plans to conduct mid-loop operations at Rancho Seco, this information is being forwarded to provide guidance for any operating procedure rewriting which may be in progress and for incorporation into your operator training program. Additional NRC correspondence (Information Notice) regarding this matter will be forthcoming.
Sincerely, 9tlelmet slynd by George Kalman, Project Manager Project Directorate V Division of Reactor Projects - Ill/IV/V
& Special Projects
Enclosure:
As stated cc:
See next page DRJhDV DRj /d:POV GKalman:cd GWKni gh ton 5//.!,, /87 5[fM87 0FFICIAL RECORD COPY 0706040320 070gyg f
- ,' D R ADOCK 00000a75 r> vn
Mr. G. Carl Andognini Rancho Seco Nuclear Generating Chief Executive Officer, Nuclear Station Sacramento Municipal Utility District CC' Mr. David S. Kaplan, Secretary Mr. John Bartus and General Counsel Ms. JoAnne Scott Sacramento Municipal Utility Federal Energy Regulatory Commission District 825 North Capitol Street, N. E.
6201 S Street Washington, D.C. 20426 P. O. Box 15830 Sacramento, California 95813 Thomas A. Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Washington, D.C. 20037 Mr. John V. Vinguist Acting Manager, Nuclear Licensing Sacramento Municipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident inspector / Rancho Seco c/o U. S. N. R. C.
14440 Twin Cities Road Herald, California 95638 Regional Administrator, Region V U.S. Nuclear Regulatory Comission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. Joseph 0. Ward, Chief Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 Sacramento County Board of Supervisors 827 7th Street, Room 424 Sacramento, California 95814 Ms. Helen Hubbard P. O. Box 63 Sunol, California 94586
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DISTRIBUTION Uoctet F11e.
hRC/ Local POR P05 Reading OMCrutchfield CMHolahan JLee GKalman 0GC-Dethesda EJordan JPartlow ACRS(10) 1
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ENCLOSURE I LOSS OF RESIOUAL HEAT REMOVAL SYSTEMS, LOWERED LOOP OPERATIONS, UNRECOGNIZED PHENOMENA, AND LEVEL INSTRUMENTATION ERRORS APPLICABILITY: PWR Operations involving Lowered Water Level CONCERNS Diablo Canyon lost RHR while in mid-loop operation on April 10, 1987, and it was 85 minutes before RHR was restarted. During more than half of this time, the core was cooled by boiling.
We believe problems associated with this event are generic, and the following are of concern should be discussed with the appropriate licensees' staff and the resident inspectors at these facilities.
(1) RCS water level instrumentation "drif t" in all measurements. Higher water level is indicated at the RHR suction nozzle than is actually the case.
(2) Change in RCS inventory when the RCS and RHR systems are interconnected but otherwise isolated. Air appears to rove from the RCS to the RHR system (or the reverse), and displaces RHR water which moves to the RCS.
This has misled operators into taking actions contributing to RHR loss.
(3) Vortexing at the same level as is required to drain steam generator tubes, or at a level higher than that to which operators are instructed to control level. Such vortexing and air entrainment may not affect RHR pump current and flow rate until the pumps become air-bound and continued RHR operation is jeopardized.
(4) Flow dynamics which affects all_ level instrumentation. Of concern are:
(a) Water level difference between RHR injection and suction locations.
The former may be the level indicated by instrumentation.
(b) Level perturbation due to injection water momentum. Water level toward the Reactor Coolant Pump can ba higher than toward the vessel because the former is static, while the latter is a flow region. The former may be the level sensed by level instrumentation.
(c) Pressure increase on the cold leg side of the reactor vessel relative to the hot leg. Air entrained from the hot leg can be pumped to the cold legs, with return flow to the hot leg restricted to core bypass flow from the upper reactor vessel. Instrumentation may reflect the cold leg pressure increase as a level increase.
(5) Level instrumentation design and installation may contribute to erroneous level readings and instrument response delays due to long, small diameter tubing runs with high and low elevation regions. High points trap air, and low points water, both of which can affect level indications.
. 2 (6) If an RHR pump fails due to vortexing, it is likely that starting another will result in its immediate failure for the same reason. Yet operators may persist in attempting to start pumps before increasing level.
(7) RHR system characteristics may differ due to different pipe lengths and plant specific analysis may be necessary to determine acceptable RHR flow / level relationships to preclude vortexing.
(8) Upper vessel thermocouples may have been disconnected, and other tempera-ture indications are usually meaningless when RHR pumps are idle. As a result, operators may be unable to monitor RCS heatup rate following RHR failure. This can lead to inappropriate mitigative actions and failure to comply with technical specifications.
(9) Procedures may not address mid-loop operation and event classification guidance may be inadequate due to failure to consider the unique plant state and the implications of accidental loss of RHR as contrasted to a planned RHR shutdown.
(10) Many operations may be in progress during mid-loop operation. Some operations have the potential to reduce RCS inventory. Others may jeopar-dize containment integrity. Both situations can occur at a time when systems and operators are challenged by unique RCS conditions. Of partic-ular concern are impacts to RCS inventory and the equipment hatch. The fomer can initiate loss of RHR. An open equipment hatch may be incapable of being closed quickly, which could result in an offsite release if an accident occurs.
The licensees should be encouraged to consider the following:
(1) Consider air sucked into RHR System which may affect level indication and give a false reading. Evaluate all level instrumentation with respect to flow phenomena within the combined RCS/RHR systems. Fully consider two component (air /H,0) behavior and RCS/RHR regions which may trap and later release air, thus pemitting water to be displaced from one or more locations to another. Consider additional fully independent instrumentation and display of level in the control room, as appropriate.
(2) Reevaluate vortexing behavior to assure consistency between operations and inventory needed to prevent vortexing associated problems. Consider reduction of RHR flow rate as a means for achieving additional margin.
(3) Postpone removal of key instrumentation, such as several vessel themoccuples, until after mid-loop operation has been completed and RCS water level has been raised.
(4) Review operating and emergency (abnomall procedures and operator training applicable to mid-loop operation. Include appropriate corrective actions following loss of an 1HR pump.
(5) Postpone plant maintenance, test, and related operations which may influence the RCS so they are not conducted during mid-loop operation.
3 (6) Reevaluate containment isolation status during mid-loop operation which closely follows power operation. Consider having containment reasonably isolated or readily isolable under these conditions.
(7) Postpone operations which may negatively influence containment isolation capability so they are not conducted during mid-loop operation.
(8) Minimize time spent in mid-loop operation.
(9) Provide immediate operator access to technical personnel intimately familiar with mid-loop operation and potential problems which may occur while in this condition, or assign such personnal to the control room during mid-loop operation. -7 1
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. . ENCLOSURE 2 FACIFIC GRAS AND E LE C T RI C C O M PANY
. (415)781 4211 . Twx 910-372 6587 FOW3 l 77 BEALE STREET . S AN FRANCISCC. C AUFORNIA 94106
~?, U,"I" May 4, 1987 PGandE Letter No.: DCL-87-099 Mr. John B. Martin, Re'gional Administrator U. S. Nuclear Regulatory Commission, Region V 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596-5368 Re: Docket No. 50-323, OL-DPR-82 Diablo Canyon Unit 2
- April 10, 1987 Interruption of RHR Flow Event
Dear Mr. Martin:
PGandE is' submitting the enclosed information regarding actions to beThese completed prior to resumption of mid-loop operation on DCPP while the plant is in mid-loop operation and to improve definition of corrective action and emergency reporting in the unlikely event of an interruption of RHR flow.
PGandE estimates a resumption of Unit 2 mid-loop operation as early as May 18, 1987, to restore the primary system to its normal operating configuration (removal of steam generator nozzle dams and reinsta11ation of steam generator primary manway covers).
The proposed and completed actions described in the enclosure resulted from PGandE's investigation and discussions with the NRC Augmented Inspection Team PGandE will work with your staff to during the weeks of April 13 and 20.
effect long term resolutions of mid-loop operation issues prior to the next DCPP Unit i refueling outage, presently scheduled for March 1988.
Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it in the enclosed addressed envelope.
Sincerely, J. . hiffer Enclosure .
cc: L. J. Chandler B. Norton J. L. Crews C. M. Trammell G. H. Knighton CPUC M. M. Mendonca Diablo Distribution
- ,;7 g j y g o g P. P. Narbut 14225/0050K/THL/1515 ,
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PGandE Letter No.: DCL-87-099 ENCLOSURE
, DIABLO CANYON POWER PLANT UNIT 2 q APRIL 10, 1987, INTERRUPTION OF RHR FLOW EVENT N -
This submittal provides a summary of proposed and completed actions taken by PGandE to address conditions associated with the April 10, 1987, Unit 2 interruption of RHR flow event. These actions are based on the results of PGandE's investigation to date and discussions with the NRC Augmented Inspection Team (AIT). These actions are categorized as
- Actions completed during previous mid-loop operation (April 10-18, 1987) s
- Actions to be completed prior to resumption of mid-loop operation
- Long term actions which involve Westinghouse, the NRC, and PGandE A detailed report of the event including causes and PGandE actions will be submitted at a later date.
' Actions Comoleted Durina Previous Mid-Loon Ooeration (Aoril 10-18. 1987)
- 1. Evaluation of Reactor Vessel Refueling Level Indication System
--(RVRLIS)
An evaluation of the RVRLIS performance during the interruption of RHR flow event was conducted. This evaluation identified that vortexing occurs at slightly higher RCS water levels than previously
- anticipated. Air entrainment resulting from vortexing caused a reduction in level indication accuracy which escalates as a function of the degree of air entrainment.
!' 2. Capability for' Containment Closure i
The major pathways to the envircnment were closed.
. 3. Enhancement of Procedures On April 12, 1987, an on-the-spot change was made to Operating Procedure A-2:II, " Reactor Vessel-Draining the Reactor Coolant System," to include a step for placing the narrow range RVRLIS in
- service. This on-the-spot change was revised on April 14, 1987, with another on-the-spot change to give detailed instruction for placing the nar(ow range RVRLIS annunciator in service. The final on-the-spot change to Operating Procedure A-2
- II was written April 20, 1987, to retype the procedure for clarity. It
- incorporates all the previous on-the-spot changes.
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4 On April 12, 1987, an on-the-spot change was made to AP-16
" Malfunction of RHR System," to include a specific section on system malfunction or interruption of RHR during mid-loop operation.
Previously, the procedure addressed mid-loop operation in a general panner and not in a specific section. On April 13, 1987, a second review of INPO SOER 85-04 and IEIN 86-101 was completed to ensure that all potential immediate corrective actions pe.rtaining to this event were identified. The review concluded that no further imediate procedural revisions were required.
- 4. Installation of Reactor Coolant System Temperature Indication Two core exit thermocouples were reconnected. Those selected for reconnection were near the top center of the core and on opposite trains. Except for a short period required to facilitate a conoseal removal, they remained connected to the thermocouple monitoring system panels in the control room. The thermocouples were disconnected when the RCS level was raised in preparation for vessel head removal.
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- 5. Improved Work Planning and Control
' The scope of outage work to be performed on systems connected to'the RCS while in mid-loop operation was restricted to those items which did not (1) communicate between containment and the environment or (2) have the potential to reduce RCS inventory.
- 6. . Additional Training On-shift operating crews were briefed on the interruption of RHR flow event, including potential causes and procedure changes which were made as an immediate response to this event.
Actions Comoleted or to Be Comoleted Prior to Resumotion of Mid-Loon Ooerittinn Based on the condition of Unit 2 during the forthcoming mid-loop operation, and the actions which have or will be completed to enhance the safety of mid-loop operation, the following information is provided.
PGandE estimates resumption of Unit 2 mid-loop operation on May 18, 1987, at which time the core heat load will be approximately 1.45 MHt (as opposed to 7.5 MHt at the time of the event). At this heat load a loss of decay heat removal would result in the coolant temperature increasing from 90*F to boiling in a minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. This calculation does not consider any effect of metal heatup or natural circulation.
The following is a summary of those actions which PGandE has completed or will complete prior to the resumption of mid-loop operation to preclude an interruption in RHR flow and to provide for effective emergency action if required. -
1A99Cinocov 9
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- 1. RVRLIS Modifications for Use During Mid-Loop Operation The RVRLIS will be modified. This modification will provide for an additional channel of indication.
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- a. A narrow range level transmitter will be installed to sense the loop 3 hot leg level, referenced to the reactor vessel head.
This will be indicated in the control room through accumulator 2-3 level indication with high and low alarm capabilities.
- b. The existing visual standpipe level system and narrow and wide range level transmitters which provide indication and alarm in the control room will remain as installed except for minor installation enhancements.
Note: PGandE plans to further upgrade the RVRLIS, including the addition of wide range indication sensing of the loop 2 crossover leg level, referenced to the pressurizer vapor space. This will be indicated in the control room through accumulator 2-2 level indication with high and low alarm capabilities. This channel will be installed for mid-loop operation of Unit I during its second refueling outage. ,
- 2. Enhancement to Procedures Regarding Containment Closure Changes will be made in procedures governing mid-loop operation and in abnormal procedures governing actions to be taken on interruption "of RHR flow to require major pathways which communicate between the containment atmosphere and the outside atmosphere either to be closed (in the case of equipment hatch and steam generator secondary ride isolation) or to have the capability of being closed (e.g.,
airlock door) in a timely manner, less than 30 minutes.
- 3. Enhancements to Operating Procedure AP-16 The abnormal operating procedure governing the loss of decay heat removal capability, AP-16, will be revised to include:
- a. Requirements for not starting the second RHR pump if the first pump cavitates or becomes airbound until proper RHR pump suction is reestablished and verified.
- b. Recovery actions to be taken in the event that RCS level decreases belaw acceptable values.
- 4. Enhancements to Operating Procedure A-2:II Operating Procedure A-2:II will be revised to provide the following:
- a. Precautions'to specify minimum reactor vessel water level as a function of RHR flow and RCS level conditions to preclude significant air entrainment due to vortex formation.
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- b. Checklists that include proper alignment of the reactor head l and RVRLIS vent systems.
- c. RHR flow reduction to a value to be determined with g
Hestinghouse consistent with adequate decay heat removal and other considerations.
- 5. Enhancement of Emergency Classifications The following clarifies which circumstances would require emergency plan entry and/or notification:
- a. A prompt report in accordance with 10 CFR 50.72 if there is any unplanned interruption of RHR flow to the vessel.
- b. An Unusual Event if the RHR flow is not restored within 10 minutes,
- c. An Alert if RCS temperature exceeds 200*F based on core exit
> thermocouples or the results from a conservatively calculated table indicating the time to reach 200*F. In addition, an Alert will be declared if RHR flow is not restored within 1 -
hour.
- 6. Emphasis on Procedure Compliance PGandE's policy regarding compliance and adherence to procedures
. will be reemphasized.
- 7. Instrumentation in Service l A prerequisite for entering mid-loop operation will be that RHR temperature and flow instruments and recorders be available. A minimum of two RCS core exit thermocouples will be in service when the reactor vessel head is in place, except when preparing for removal or replacement of the vessel head. A minimum of one loop's RCS wide range (Th and Tc) temperature monitors and recorders will also be in service.
- 8. Additional Training Training will be conducted for operating crews on mid-loop operation as described in procedures A-2:II and AP-16. The training will also cover RCS venting and RHR system venting (pumps and piping).
l Note: Training for this mode of operation will be included in the
' formal operator training program.
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B I WbEfdi1iH(sN _
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- 9. Control of Work Activities Work activities will be controlled to ensure that:
- j. No potential RCS inventory loss path from the reactor coolant system, residual heat removal, or charging system will be l
created. .
- b. Effective communication is implemented between the control room and critical work areas.
- c. During mid-loop operation, all work activities will be planned so that the time duration in this configuration is minimized (estimated time approximately 5 days). The presently planned activities are (1) to verify proper RHR system operation with installed instrumentation at the specified minimum operating level (2) nozzle dam removal, and (3) steam generator primary manway installation.
- d. An engineer or manager knowledgeable with respect to the requirements of mid-loop operation will be present during this period.
Lona Term Actions PGandE, in conjunction with Hestinghouse, intends to resolve mid-loop operation with NRR and Region V prior to the next Unit I refueling outage, presently ~ scheduled for March 1988, or develop all actions to a point where there is no longer a concern or safety issue.
Summary As part of its ongoing investigation efforts, PGandE studied and reviewed the event and its implications. Actions have been agressively taken, and all short term actions will be completed prior to resumption of mid-loop operation. Based upon its investigation to date PGandE has concluded that resumption of mid-loop operation on May 18, 1987, presents no undue risk to public health and safety.
14225/0050K _ _ _ _ _ _ ___