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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 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 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 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 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 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 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 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 ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 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 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 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 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) 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 ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks 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 ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility 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 ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 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 1999-08-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F0799-22, 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 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 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 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 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 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 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 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 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 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 ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements 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 ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 NL-97-030, Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs1997-05-13013 May 1997 Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs ML20138F5321997-04-28028 April 1997 Forwards Response to RAI Re License Amend 192,updating Cask Drop Design Basis Analysis,Per NRC 960510 Request for Addl Info on 960318 Application NL-97-027, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-04-17017 April 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility ML20137W8091997-03-20020 March 1997 Forwards Biennial Update to Rancho Seco Post-Shutdown Decommissioning Activities Rept ML20137S3571997-03-19019 March 1997 Provides Notification of Use of Revised Quality Manual for Activities Re Rancho Seco ISFSI ML20137D0981997-03-18018 March 1997 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1996.Provided IAW TS D6.9.2.2 & Guidance Contained in NRC Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1996 ML20137D1221997-03-18018 March 1997 Submits,Iaw 10CFR20.2206 & TS D6.9.2.1,1996 NRC Form 5 Individual Monitoring Repts for Personnel Requiring Radiation Exposure Monitoring Per 10CFR20.1502 During 1996. W/O Encl NL-97-012, Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3)1997-02-11011 February 1997 Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3) ML20138L1091997-01-29029 January 1997 Informs of Schedule Change Re Decommissioning of Rancho Seco.Incremental Decommissioning Action Plan,Encl NL-97-005, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-01-22022 January 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility NL-96-056, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1996-12-16016 December 1996 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20134E0041996-10-23023 October 1996 Forwards Response to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks ML18102B6871996-08-0606 August 1996 Informs That Util Will Revise Loading & Unloading Procedures & Operator Training as Necessary ML20149E4491994-05-16016 May 1994 Forwards 1993 Annual Rept of Sacramento Municipal Utility District,For Info ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List ML20059H6731994-01-20020 January 1994 Forwards Revised Rancho Seco Quality Manual, Reflecting Current Rancho Seco Pol Phase Nuclear Organization Changes ML20059E1221994-01-0303 January 1994 Forwards Amend 7 to Long Term Defueled Condition Physical Security Plan.Encl Withheld (Ref 10CFR73) ML20059C1681993-12-22022 December 1993 Forwards Suppl Info to Support Review & Approval of 930514 Proposed License Amend 186 Re Nuclear Organization Changes, Per NRC Request 1999-07-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5431990-09-20020 September 1990 Requests Exemptions from Certain Requirements of 10CFR50.47(b) & 50,App E & Proposes New Emergency Plan That Specifically Applies to Long Term Defueled Condition ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 ML20059J9221990-09-13013 September 1990 Responds to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' No Vendor Interface Exists for Spent Fuel Pool Liner NL-90-442, Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-2121990-09-12012 September 1990 Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-212 ML20059G0791990-09-0606 September 1990 Forwards Supplemental Fitness for Duty Performance Data, Omitted from 900725 Rept Re Random Drug Testing Results ML20059E0031990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept,Jan- June 1990, Corrected Repts & Revs to ODCM ML20059C2491990-08-27027 August 1990 Advises That M Foster & B Rausch Leaving Util Effective on 900810 & 17,respectively & Will No Longer Require Active Operator Licenses ML20056B2591990-08-20020 August 1990 Forwards Long-Term Defueled Condition Security Training & Qualification Plan. Encl Withheld (Ref 10CFR2.790) ML20056B2961990-08-10010 August 1990 Discusses 900731 Meeting Re Future of Util & Closure & Decommissioning of Facility.Request for Possession Only License Pending Before Commission ML20058Q2811990-08-0909 August 1990 Forwards Updated Listing of Commitments & long-range Scope List Items Deferred or Closed by Commitment Mgt Review Group Since Last Update ML20058N0911990-08-0707 August 1990 Notifies of Minor Change in List of Tech Specs Applicable in Plant Defueled Condition.Determined That Surveillance Requirements Table 4.1-1,Item 63 Not Required to Be Included in List of Tech Specs Applicable in Defueled Condition ML20056A2041990-07-30030 July 1990 Provides Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. Pressure & Differential Pressure Transmitters 1153 & 1154 Do Not Perform Any safety-related Function in Current Plant Mode ML20056A1131990-07-30030 July 1990 Apprises of Status of Plans to Use 3 of 4 Emergency Diesel Generators as Peaking Power Supplies & Responds to Questions in .Util Obtained Authorization for Operation of Diesel Generators for No More than 90 Days Per Yr ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055H7561990-07-24024 July 1990 Requests Exemption from Performing Annual Exercise of Emergency Plan,Activation of Alert & Notification Sys & Distribution of Public Info Brochures,Per 10CFR50.12 Requirements ML20055H8081990-07-24024 July 1990 Forwards Decommissioning Financial Plan for Plant,Per 10CFR50.33(k)(2) & Requests Interim Exemption Re Requirement to Have Full Decommissioning Funding at Time of Termination of Operation,Per 10CFR50.12 ML20055F8421990-07-13013 July 1990 Forwards Application for Proposed Decommissioning of Plant. Util Needs Relief from Equipment Maint,Surveillance,Staffing & Other Requirements Not Necessary to Protect Public Health & Safety During Defueled Condition ML20055G9821990-07-12012 July 1990 Advises That Environ Exposure Controls Action Plan Will Be Provided by Sept 1990,per Insp Rept 50-312/90-02 ML20055E5111990-07-0606 July 1990 Notifies of Change in Operator/Senior Operator Status for D Rosenbaum & M Cooper,Effective 900622 & 29,respectively ML20055C3511990-02-14014 February 1990 Forwards Addl Info Re 900306 Response to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Util Will Replace Only Relays Found Not to Meet Insp Criteria ML20055C3541990-02-14014 February 1990 Forwards Updated Response to Insp Rept 50-312/88-30. Calculations for Liquid Effluent Monitors Completed & in Use & Rev to Reg Guide 4.15 in Procedure RSAP-1702 Scheduled to Be Completed & Implemented by Apr 1990 ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration ML20248H2571989-10-0606 October 1989 Responds to NRC Re Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54 Re Reactor Vessel Vent Valve Testing.No Testing of Reactor Vessel Vent Valves Will Be Performed ML20248A8271989-09-25025 September 1989 Requests Permission to Submit Next Amend to Updated FSAR W/Decommissioning Plan Submittal.Extension Will Allow District to Incorporate Plant Closure Status in SAR Update to Reflect Plant Conditions Accurately ML20248D4611989-09-13013 September 1989 Responds to 890906 Request for Assessment of Util Compliance W/Ol & Associated Programs & Commitments,Per 10CFR50.54(f). Staffing Requirements for Emergency Preparedness Will Not Be Violated & Future Shortfalls Will Be Remedied ML20247G1991989-09-11011 September 1989 Requests Extension for Time Period Equivalent to That of Current Shutdown.Extension Would Result in Revised Final Expiration Date of Not Earlier than 900318.Plant Would Not Be Brought Above Cold Shutdown W/O NRC Prior Concurrence ML20247H3551989-09-0707 September 1989 Informs That Util Stands by Commitments of 890621 & 0829 Re Implementation of Closure Plan in Safe & Deliberate Manner in Compliance W/License & W/All Applicable Laws & Regulations ML20247H5541989-09-0101 September 1989 Responds to Violations Noted in Insp Rept 50-312/89-14. Corrective Actions:Stop Order on Fuel Movement Issued & Action Plan Generated on 890908 to Address Broader Issues 05000312/LER-1988-010, Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys1989-08-23023 August 1989 Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys ML20246A4011989-08-16016 August 1989 Forwards Rev 5 to Inservice Testing Program Plan. Changes Identified Consistent W/Guidance Provided by Generic Ltr 89-04 NL-89-593, Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request1989-08-15015 August 1989 Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request ML20245H4781989-08-10010 August 1989 Requests Exemption from Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs Because on 890607,util Board of Directors Ordered That Plant Cease Operation ML20245H1781989-08-0909 August 1989 Notifies of Change in Operator/Senior Operator Status. J Dailey & J Reynolds Terminated Employment on 890721 & 890802,respectively ML20245L1831989-08-0808 August 1989 Informs That Official Correspondence Must Be Directed to Listed Individuals Due to Reorganization of Util Following 890606 Election ML20247L9221989-07-26026 July 1989 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-312/88-33.Corrective Action:Portable Shield Walls Inspected Every 6 Months to Ensure All Safety Factors Met & Area Surveys Conducted on Weekly Basis ML20247M4121989-07-24024 July 1989 Requests Exemption from 10CFR50,App E,Section IV.F.2 to Allow Util Not to Perform Annual Emergency Plan Exercise for 1989.Request Results from Transitional Mode of Plant from Operating Plant to Plant Preparing for Decommissioning NL-89-541, Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 8912151989-07-14014 July 1989 Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 891215 ML20246P4011989-07-14014 July 1989 Informs That Evaluation of Contracts & Agreements Identified No Restrictions on Employee Ability to Provide Info About Potential Safety Issues to NRC NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 1061989-07-0606 July 1989 Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 ML20246A9751989-06-30030 June 1989 Advises That Concerns Addressed in Generic Ltr 89-08 Inapplicable,Since Util Intends to Defuel Reactor.Generic Ltr Will Be Reviewed Prior to Placing Facility in heatup-cooldown Operational Mode for Return to Power ML20246A5171989-06-30030 June 1989 Forwards Rancho Seco Closure Plan, Per 890621 Request for Addl Info Re Plan CEO-89-289, Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date1989-06-27027 June 1989 Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date NL-89-526, Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl1989-06-22022 June 1989 Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl ML20245H4181989-06-21021 June 1989 Discusses Util Plans Re Overall Closure of Plant,Per 890615 Meeting W/Nrc.Util Will Request Appropriate Changes to Tech Specs to Reflect Defueled Mode & Will Evaluate & Request Changes to Emergency Plan ML20245D9281989-06-21021 June 1989 Discusses Activities Underway Re Plan for Closure of Plant Discussed During 890615 Meeting W/Region V.Util Intends to Continue Use of Essential Programs,Such as Preventive Maint Program,For Sys within Scope of Closure Process ML20245A0981989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. No Westinghouse Plugs Used at Plant ML20248B5751989-06-0202 June 1989 Advises That Util Anticipates That Final Analysis of Thermal Striping Will Conservatively Support Surge Line Lifetime Significantly Longer than June 1994 Date,Per NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification 1990-09-06
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SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 15830, Sacramento CA 95852-183'),(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAUFORNIA h04Y 151987 GCA 87-046 James Partlow, Director Division of Reactor Inspection and Safeguards Office of Nuclear Reactor Regulation Washington, DC 20555 Docket 50-312 Rancho Seco Nuclear Generating Station Unit #1 AUGMENTED SYSTEMS REVIEW & TEST PROGRAM (ASRTP) INSPECTION
Dear Mr. Partlow:
The District is committed to the safe and reliable operation of Rancho Seco.
This commitment demands a careful self-examination following the recent ASRTP Inspection, looking beyond the specific Inspection findings to identify broader implications and, as necessary, programmatic improvements.
The District is pursuing the implications of the ASRTP Inspection. All ASRTP Inspection items have been processed into the Plant Performance and Management Improvement Program (PP&MIP) for validation, approval, implementation, and closure. All ASRTP Inspection items will be addressed in accordance with the existing PP&MIP mechanism which is the District's basis to delineate a phased approach to performance improvement and restart of Rancho Seco. The District will provide a detailed response to the ASRTP Inspection Report 50-312/86-41 in a complete, formal reply prior to the scheduled followup inspection visit.
The District recognizes the importance of establishing the specific listing of items the District will complete prior to restart. Revision 0 of the Restart Scope List was transmitted for J. B. Martin, RV Administrator, on April 17, 1987. This submittal provides a basis for discussion and concurrence by NRC staff on the District's plant for restart of the unit. ASRTP Inspection items will be integrated into the Restart Scope List.
As committed to Joe Callan, NRC ASRTP Inspection Team Leader, this letter forwards the attached summary of ASRTP Inspection items for which the District plans to provide a resolution prior to restart.
The District would like to express its appreciation for your Inspection efforts. The review was thorough, the findings relevant, and the interaction constructive. More particularly, the inspection has been a helpful course check on the District's road to restarting Rancho Seco. It has helped the 8705270450 870515 t PDR ADOCK 05000312 G PDR 2 fp
'l(
RANCHO SECO NUCLEAR GENERATING STATION fJ 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
~ James Partlow -2_: 404Y 151987 GCA 87-046 Nuclear,0rganization maintain its focus on quality implementation and attention to_datail. The District realizes that quality of operational performance is absolutely essential for public trust and confidence, and that credibility rests on promises kept.
Sincerely,_
$. df.a:4I Carl And nini l
Chief Executive Officer, Nuclear-Attachment ec: J. Callan, NRC, Bethesda A. D'Angelo, NRC, Rancho Seco J. Dyer, NRC, Bethesda G. Kalman, NRC, Bethesda (2)
J. B. Martin, NRC, Walnut Creek T. O. Martin, NRC, Bethesda
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ASRTP Inspection Response Items Committed for Resolution Prior to Restart ASRTP'IR; Item f
_ . Associated QTS #
^(ASRTP Report Reference). Summary Item Description .(QCI-12 Priority)
' Item 86-41-01 Resolve P-318 motor overspeed concerns 26.1069-f(Section'3.1.1(1)) (AFW SSR Problem #61). (1)
Item 86-41-01 Perform appropriate testing to 26.0608 (Section 3.1~.1(2)) evaluate need for procedura1' caution (1) against quick restarting of AFWPT (AFW SSR Problem #31).
Item 86-41-02 Install flow limiting verturis to
- 26.0957 (Section 3.1.1(3)) prevent excessive AFW flow to'OTSGs (1)
(AFW SSR: Problem #54, ECN f R-1672A).
Item 86-41-03. Modify AFW Full Flow Test Line to
- 26.0120 (Section 3.1.1(4)) provide _for accurate surveillance (1)-
testing (AFW SSR Problem 3, ECN #
R-1188).
Item 86-41-04 Evaluate AFW Pump Runout effects due 15.0282 (Section'3.1.1(5))- 12/26/85 event-(AFW SSR Problem #43). - (1)-
-Item 86-41-04 Evaluate the effects of cumulative 26.1064 (Section 3.1.1(5)) AFW Pump runout (AFW SSR Problem #56). (2R)
Item 86-41-04 Evaluate the potential for AFW Pump 26.1081
-(Section 3.1.1(5)) runout following installation of EFIC (2R) and flow limiting venturis (AFW SSR Problen #66).
Item 86-41-05 __
Verify accuracy of AFW Pump Per- 26.1084 (Section 3.1.1(6)) formance Calculation Z-FWS-M2081 (1)-
(AFW SSR Problem f55).
Item 86-41-06 Assure adequate overpressure pro- 26.1087 (Section 3.1.2(1)) tection for main and startup feed- (2R) water control valve actuators.
Item 86-41-06 Document seismic qualification of 26.1088 (Section 3.1.2(2))- safety related valves in backup air (1) supplies for EFIC modifications.
~ Item 86-41-06 Replace excess flow check valves in 26.1089 (Section 3.1.2(3a&b))- backup air supplies. (1)
- Committed to in 2/12/87 ASRTP Inspection Exit Interview
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ASRTP Inspection Response-Items Committed for Resolution Prior to Restart ASRTP-IR' Item # Associated QTS f (ASRTP Report Reference) Summary Item Description (OCI-12 Priority)
_ Item 86-41-06 . Establish operating procedures to moni- 26.1090 (Section 3.1.2(3c)) tor backup bottle pressure and initiate (2R) appropriate actions if leakage is indi-cated.
Item 86-41-06 Establish periodic test procedures to _26.1091 (Section 3.1.2(3d)) functionally verify the bottle backup (2R).
air systems.
- Item 86-41-06 Resolve concerns that pressure' control 26.1092 (Section 3.1.2(4))- valves'for EFIC backup air system may (2R) not be appropriate design application.
Item 86-41-06 Verify accuracy of fabrication drawings '
26.1093 (Section 3.1.2(5)) for EFIC backup air supplies. (1)
Item 86-41-07 Resolve FWS SSR Problem #6 relating to 20.0043
. (Section 3.1.3) faulty MFF Lovejoy Control Response (2R)
- (Implement ECN #R-0717).
Item 86-41-07 Resolve FWS SSR Problem #12 relating to 20.0188 (Section 3.l.3) MFW control valve positioning during (2R) transients.
Item 86-41-07 Resolve FWS SSR Problem #18 relating to 22.0330 (Section 3.1.3) Casualty Procedure C.26 enhancements. (2R)
Item 86-41-07 Resolve FWS SSR Problem #19 relating to 22.0453 (Section 3.1.3) Casualty Procedure C.10 enhancements. (2R)
" Item 86-41-07 Resolve FWS SSR Problem #22 updating 22.0688 (Section 3.1.3) P&ID M-580, Sheet 1. (2R)
Item 86-41-07 Resolve FWS SSR Problem f45 relating to 26.0518 (Section 3.1.3) MFP governor response (Implement ECN (2R)
R-0717).
Item 86-41-08 Docunent environmental qualification of 26.1086 (Section 3.1.4(1)) excess flow check valves installed in- (1)
EFIC sensing lines.
i I
- Committed to in 2/12/87 ASRTP Inspection Exit Interview 3
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ASRTP: Inspection Response j-0 Items Committed'for Resolution' Prior to Restart (Y
0 \
fASRIP IR Item #L .
. Associated-QTS #
(ASRTP Report Reference) Summary Item Description (QCI-12 Priority)
Item 86-41-09 . Revise and resubmit EFIC. Safety Analys'is 25.1061 (Section 3.1.4(2)) to more clearly reflect EFIC sensing (1)
,g , line design.
f" (Item.86-41-09.. Document evaluation of acceptability 26.1085 (Section 3.1.4(2)) of operational procedures and training (2R)
-for response to EFIC sensing line failures.
Item 86-41-10 Incorporate appropriate-provisions to 26.1098 (Section 3.1.4(3)) - fully test the EFIC maintenance bypass. (1) feature.
~
, /
Item 86-41-11' ft Resolve 125 VDC System SSR Problem #8
- 26.0218 (Section.3.1.5(1))~' relating to Procedure A.61 enhancements. (2R)
Item 86-41 Resolve:125 VDC System SSR Problem #9
- 26.0219 (Section 3.1.5(2)) . relatin8 to maintaining battery room (2R)
'b . temperatures within design temperature limits.
i Item 86-41-11 ' Resolve.125 VDC System SSR Problem #20
- 26.0987 (Section 3.1.5(3)) relating to refurbishment of six AB (2R) j< battery chargers.
K ,;
N Item 86-41-11 .
Resolve 125 VDC System SSR Problem #22
- 26.0989 h ' relating to open NCRs on deformed (Section 3.1.5(4)) (2R) battery terminal posts.
ii[ Item 86-41-12 .
Resolve 120 VAC System SSR Problem #7 .
'(Section 3.1.6(1))' updating the IEB 79-27 study to include (1) all changes to the 120 VAC vital buses, i ,
. Implement the recommendations of the IEB
! . ,;, z. , 79-27 study.
9 ..
"i -Item 86-41-12 Address 120 VAC System SSR Problem #2
- 22.0384 (Section 3.1.6(1)) ,
relating to CR annunciation of feeder (3R) s ,'
breaker trips. An overview study will be done to provide a resolution of identified concerns.
1 0 ' Committed to in 2/12/87 ASRTP Inspection Exit Interview
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'ASRTP Inspection Response -
Items Committed for Resolution Prior to Restart ASRTP-IR Item =f ' Associated QTS #
~(ASRTP Report Reference) Summary Item Description (QCI-12 Priority)
. Item 86-41-12 -
Resolve 120 VAC System SSR Problem #5
-(Section 3.1.6(1)) relating to casualty procedures for (2R) loss of 120 VAC vital buses.
Item 86-41 Resolve 120 VAC System SSR Problem #6
- 22.0345 (Section-3.1.6(2)) . relating to Operating Procedure A.62 (2R) enhancements.
Item 86-41-12 -
Address 120 VAC System SSR Problem #12
- 26.0356' (Section 3.1.6(3)) . relating to local indication of 120 VAC (2R) breaker status. An overview study will be done to provide a resolution of identified concerns.
Item 86-41-13 Address 480 VAC System SSR Problem #10-
- 22.0037 (Section 3.1.7(1)) relating to study of need for alarming (2R) loss of power at the MCC level. An overview study will be done to provide-a resolution of identified concerns.
~
Item 86-41-13 Resolve 480 VAC System SSR Problem #11
- 26.0298 (Section 3.1.7(2)). relating to casualty procedures (2R) enhancements.
Item 86-41-13 . Address 480 VAC System SSR Problem #16
- 26.0300 (Section 3.1.7(3)) relating to poor local indication of l(2R) certain Westinghouse MCCs. An over-view study will be done to provide a resolution of identified concerns.
Item 86-41-13 Resolve 480 VAC System SSR Problem #46
- 22.0700 (Section 3.1.7(5)) relating to a discrepancy identified in (2R) drawing E-108, Sheet 30.
Item l86-41-13~ Address 480 VAC-System SSR Problem #26
- 26.0521 (Section 3.1.7(6)) providing local indication monitoring (3R) control power on all applicable 480 V switchgear breakers. An overview study will be done to provide a resolution of identified concerns.
- Committed to in 2/12/87 ASRTP Inspection Exit Interview
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, ASRTP Inspection Response Items Committed for Resolution' Prior to Restart-
- ASRTP 1R Ites # Associated QTS i (ASRTP Report Reference) Summary Item Description (QCI-12 Priority)
~
Item 86-41-13 _
Address 480 VAC System SSR Problem #19:
- 26.0338 (Section 3.1.7(7)) relating to. review.and documentation of- -(2R) 480 VAC System breaker annunciation.
~
An.
overview study will be done to provide a.
resolution of identified concerns.
' Item 86-41-14 Resolve 4160 VAC System SSR Problem #8
- 21.0248' t(Section 3.1.8(1)) relating to slotting of protective (2R) relays in the switchgear.
Item.86-41-14 Resolve 4160 VAC System SSR Problem #25'
- 22.0387 (Section 3.1.8(2)). relating to procedural enhancements for (2R)J
. monitoring DC control power to switchgear-
-breakers.
Item 86-41-14 kesolve 4160 VAC System SSR Problem #32
- 26.0965 (Saction 3.1.8(3)) relating to Operating' Procedure A.54 (2R) enhancements.
Item 86-41-14' Resolve 4160 VAC System SSR Problem #33
'(Section 3.1.8(4)) ' relating to Casualty Procedure C.143 (2R)
. enhancements.
. Item 86-41-15 Document assurance that CST relief valve 26.1083 (Section 3.2.1(2a)) .setpoints are appropriate to maintain'the (1) structural integrity of the tank (AFW SSR Problem #68).-
Item 86-41-15 Document assurance that CST vacuum. 26.1065
- (Section 3.2.1(2b)) breaker protection is apprcpriate to- (1)-
maintain the structural integrity of the tank (AFW SSR Problem'#57).
Item 86-41-23 Issue revised procedure governing the 25.0162
-(Section 3.3.2) performance of safety evaluations. ~(2R)
Item 86-41-24 Issue revised procedures for site 25.0163 (Section'3.3.3)_ drawing control. (1)
. Item 86-41-24 Conduct QA audit of SDC activities to 25.0164
, (Section 3.3.3) assure compliance with approved (2R) procedures.
' # Committed to in 2/12/87 ASRTP Inspection Exit Interview
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iSRTP Inspection Response Items Committed for Resolution Prior to Restart
-ASRTP IR Item i Associated QTS f (ASRTP Report Reference) Summary Item Description, (QCI-12 Priority)
)
item 86-41-25 Submit to an evaluation of engineering 25.0092 (Section 3.3.4) . calculation practices by an independent (2R) calculation review team.
Item 86-41-25 Review study files to assure formal 25.0093 (Section 3.3.4) calculations have been prepared where (1) appropriate.
Item 86-41-26 Submit revised IST program for NRC 25.0119 ,
(Section 3.4.1(1))
approval. (1)
Item 86-41-28' Document basis for AFW minimum recircu-
- 26.1095 (Section 3.4.2(la)) lation flow valve of 60 gpm. (1)
Item 86-41-28 Establish procedure for calibration of 26.1082 (Section 3.4.2(1b)) CST level instrument LIT 35803. (1)
Item 86-41-29 Reestablish acceptable criteria for 26.1080 (Section 3.4.2(2)) stroke times of AFW control valves in (2R) accordance with ASME Section XI Article IWV requirements.
Item 86-41-30 Revise SP 210.01A to check the backseat 26.1079 (Section 3.4.2(3a)) of AFW pump discharge check valve (1)
FWS-048 (AFW SSR Problem #64).
Item 86-41-30 Revise SP 210.01A and 210.01B 26.1097 (Section 3.4.2(3b)) to specify fixed locations for (1) bearing temperature measurements of the AFW pumps.
Item 86-41-30 Revise Surveillance Procedures to 25.0180 (Section 3.4.2(3c)) specify ALERT and ACTION ranges for (2R) differential pressures and pump flows.
Item 86-41-31 Evaluate adequacy of ventilaston design 25.0106 (Section 3.4.4(1)) to maintain NSEB and AB batteries within (2R) the required design temperature ranges.
Item 86-41-31 Revise battery surveillance procedures 25.0130 (Section 3.4.4(2)) to adequately address electrolyte level, (1) specific gravity and room ambient temperature.
- Committed to in 2/12/87 ASRTP Inspection Exit Interview
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w 4
.ec ASRTP Inspection Response 1 Items Committed for Resolution Prior to Restart.
ASRTP.IR Item;f. Associated QTS #
(ASRTP Report Reference)- Summary Item Description (QCI-12 Priority)
' Item 86-41-32: Implement policy emphasizing operator 25.0165
- (Section 3.5.1) attention to detail. -(2R)
- Item _86-41-33 .
Provide appropriate procedural response 25.0178 4
(Section 3.5.2(1)) ' for P-318 turbine overspeed alarm. (2R)
Item 86-41 Establish AFW pump motor' start time 26.0067-(Section 3.5.2(2)) limitations (AFW SSR Problem #20). (1)
' Item 86-41 Evaluate the. adequacy of operator 26.1066 (Section.3.5.3) procedures and training for. AFW . (2R) pump runout alarm response.
Item 86-41-36 Issue' Procedure M.115 for Dings brake 25.0132
- (SectionL3.6.2(1)) -maintenance. (1)
Item 86-41-36 Establish Procedures for Air Operated 25.0131 (Section 3.6.2(2))- Valve Maintenance. (1) r Item 86-41-40 .
. Issue procedure for compliance with 25.0138
- (Section 3.7.3(1))' 10 CFR 50, Appendix B, Criterion XVI. -(1)~
Item.86-41-40 Enhance NRC Commitment Tracking per- 25.0008 (Section 3.7.3(3)) formance (See Action Plan Section 4B.11, (2R)
Commitment Management).
Item 86-41-41. Evaluate integration of LRS Management 25.0172
, - (Section'3.8.1(1)) Appraisal Report items into QCI-12 (2R) process.
. Item 86-41-42 Document measures to revalidate the 25.0173 r (Section 3.8.1(2)) adequacy of QCI-12 reviews. (2R)
Item 86-41-43. Establish controlling procedures for 25.0174 l-(Section 3.8.1(3)) '
SSR documents. Verify acceptability (2R) with NRC.
. Item 86-41-44 Implement final nuclear. organization 25.0175
' (Section 3.8.4(1)&(2)) and fill management position vacancies (1) with District employees, j
'* -Committed-to-in 2/12/87 ASRTP Inspection Exit Interview
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