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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 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 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 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 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 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 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 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 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 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 ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration 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 NL-89-468, Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request1989-05-30030 May 1989 Submits Justification for Absence of Functional Testing Requirement in Proposed Tech Spec 4.14(f) Re Snubber Svc Life Monitoring,Per 890517 Request ML20247N2601989-05-25025 May 1989 Requests Guidance Re Whether NRC Concurs W/Arbitrator Order Concerning Employee Access to Plant 1990-09-06
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4 gSMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. o. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 l AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA l
i NOV 181987 GCA 87-755 J. B. Martin, Regional Administrator Region V Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, Ca 94596 i
DOCKET NO. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 SCHEDULES FOR PROCEDURES AND NRC OPEN ITEMS
Dear Mr. Martin:
In accordance with discussions between Mr. Roy Zimmerman, of your staff, and members of the District's Licensing staff, this letter transmits a status and schedule for completion of those procedures currently determined to be required for restart that are undergoing a revision process.
In addition, it should be noted that other procedures are undergoing a Technical Review / Biennial Review process as part of our preparation for restart. If, as a result of this review, a procedure revision is found to be necessary it will be added to the list. Based on this, we are 74% completed with our procedure revision process, not counting those procedures in the Technical Review or Biennial Review processes. Attachment I summarizes our Restart Procedure status.
Another item requested was our schedule for NRC Open Item closecuts. Attachment II is that schedule. This list is a moving schedule that displays those items in progress. Items-that have been closed are no longer retained on this list. It should also be noted that all justifications (those marked by a "J" in the right hand column) are completed and available for review. Of the remaining items, those that are deemed ready for closure are being assembled in review packages to facilitate review. Currently there are 30 items ready for closure.
g20ho P
\\
RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638-9799;(209)333 2935,
_ - _ . _. - _ _ _ _ ___S " (j.-
NOV 18 Mpf Martin GCA 87-755 The dates indicated on the NRC Open Item schedule are expected completion dates for those actions that remain open. A' completed package will be generated and internally reviewed within ten days-of completion of the last action. However, in progress packages will be kept current and available for NRC review prior to completion of corrective actions.
The progress of both the list of procedures and the NRC Open Items is reflected in a living schedule with responsibility and accountability covering the administrative process. This schedule is.available for review by members of your staff.
As a point of clarification, RSL statistics will be provided on a weekly basis. The detailed RSL is available'for inspector review at any time.
Please contact me if you have any questions. Members of your staff may contact Steve Crunk of my staff at (209) 333-2935, extension 4913.
Sincerely, G. Ca Mb #f sec And nini Chief Execu ive Officer, Nuclear cc w/ attachments G. K&lman, NRC Bethesda (2)
A. D'Angelo, NRC, Rancho Seco
I ATTACHMENT I RESTART PROCEDURE STATUS
SUMMARY
(NOVEMBER 10, 1987)
PROC.
TO BE TOTAL -APPROVED APPROVED CURRENT STATUS DEPARTMENT PROCEDURES TO DATE PRIOR TO TECH / BIENNIAL HEATUP IN DEV REVIEW Chemistry 98- 47 29 3 48 Cost Cntrl/ 6 5 0 0 1
-Office'Sves-Environmental 79 25 11 53 1 Protection
' Fire Protect 15 7 7 8 0 Info Sycs 1 1 0 0 0 Licansing 7 4 3 3 0 Maintenance 270 221 32 40 9 (Material Mgmt 20 20 0 0 0 NUC Engr 27 12 10 11 4 Oparations 317 150 98 9b 72 Proc Develop 7 4 0 3 0 Quality 9 9 0 0 0 red Protection 25 15 9 7 3
.Sys Rvw & 266 219 30 35 12 Tant
. TOTAL 1147 739 229 258 150
NRC OPEN ITEM CLOSURE SCHEDULE ATTACilMENT II NRCols ICCTS u lR;sp Dept l Due D-t? Des ription lJ 188701 ! . l IN REVEV (Thinning of pipe valls) j i i i i i GL8522 iT861106371 ! ENGR / MECH i 9/30/88 ilnsulation on RCS evaluation iJ i i
- : I !
GL8605 .:T860910104 .!LIC/TS . I 11/29/87 .i Auto trip of RCP's
-+
i GLC605 jT870912001 jENGRh&C j 11/15/87 jAuto trip of RCP's i
- ! l 040102 iT861106 05 iMAINT 11/15/87 Yaste 0as Tank monitor in service i i i +
7 ~
- I :
841103 iT861031101 lEP i 6/15/88 ! Meteorological 1 instr. upgrade J 841103 iT861031102 iEP ! 10/21/87 ! Calibration for met. sensor 841103 IT861031103 !'EP i 10/21/87] Bearing change on met. instr. ~
841103 !T861031104 !EP ; 11/1/87 l Training for met. instr. tech. ,
!41103 jT861031105 jEP j 11/15/87 iQ A manual, met. maint/ mod & cal. J 841103 iT861031106 !EP 12/7/87 { Met. data editing program upgrade j i i :
- : s 842701 !T861104107 iSRTP .11/30/87 , Test Low leve1 Rad Yaste Storage facility j 842701 iT870306329 iTRNC i 3/31/88 Staff training, Rad Vaste storage facility {J i i I 850402 IT860428441 lLIC/TS !11/15/87 Design change & commitment review program
! i !
850501 iT861106334 !EP i 11/15/87 lEmerg Plan current j d $ d b 851401 !T860428303 l ENGR /ELECTi 3/31/88 lEQ Rockbestos cable J
. i i ;
.85t402 i ! l ilN REVIEY (irnplementation of EQ procedures)
^
{
- i l i 852602 ! lEP 3/1/88 10ff site improverfwot iterns EPIC 860179 ;J i
i i
!i 852808 jT861106426 ENGR /l&C { 7/1/89 iRx Bldg purge flow rate meter jJ i ! ! :
852811 i i i IN REVIEV (installation of R15017A & R150178)
- i. , .
C60602i I i !!N REVEV ( Annual corranand and control trainirg) t . -
i !
I !
860701 i !LIC ; itN PEVEV i
! ! l ! ;
860703 iT861106342 l ENGR /l&C 'i 11/1/87 iCalib.of essential filtration unit flow xmitter i i i~ l i Battery test 860805 }T861106344]SRTP,, ak
i ; i i i 861302 iT870616400 ! OPS i 12/5/87 ! Procedure / lineup change per AP.73 j i i ! ! !
861402 {T860916.002 lEP i 11/15/87 iFailure to maintain E. Plan & proc's per TS 6.8.11 j 861402 !T861222311 !EP i 3/1/88 iTurnoYer to EP Staff responsible for proc. {J_,.
i : ! !
861403 iT860916003 !EP ! 11/15/87 jEP training deficiencies ;
! i 4 i i j 8,6_1501 j '
j.
j jlN REVEV (Sury. procedures to implement 10CFR50 App.1) ;
i i i
"=L-- ---- -- - "^ c ' * "" "" ~ *c"*'s ' * ' A
a NRC OPE 3 ITEM CLOSURE SCHEDULE 14RCol' CCTS u (R:sp Dept Due ht) Derription J 861505 jEP 10/19/87 Need revised ODCM (F ailure to limit liq. efil. dose)
! i 861509 i IN REVIEY (Failure to implement and maintain liq. effl. proe's) j j i
861513i .. EP: l10/19/87 Need revised ODCM (Bioaccumulation factor F of cesium) -.
4 4 4 4 ;
861702{ j i jlN REVIEV (Prog. to calib. non Tech Spec safety-rel. inst's j I $ d k $
861807 jT870914001 { ENGR /MECHj 11/15/87 jReanalysis of drainage in TSC after FP actuation !
! i. '. i. .i i 863204j j j jlN REVEV (Monitoring for Red contamination) j i j i i !
? 4 BG3205 IT861203106 lEP ! 11/1/87 Insta11 card readers !
i i !
863206 i ;
~
IIN REVIEV (Revision of EPIP-5010) {
i-7 i ir i
i l
863701 iT861105117 !TRNG 863701 iT861106102 !MAINT 6/1/88 l PASS system operability
! 11/1/87 iPASS system operability j
}J 863701 iT870506100 iSRTP i *g ;P ASS system operability j
.' i 1
i 1
863702 iT870116105 iSRTP i 10/30/87 l Perform sury. on CR/TSC filtering system prior to restart ,
! ! i ! i j
863703} jlN REVIEY (Due date dependent on NRC approval of P A164) 1.
864101 IT870424104 SRTP 3/1/88 Quick restart of AFYPT evaluation J 864106- T870424112 SRTP i 6/1/88 Procedures to verify backup bottle air pressure d i !. !
j 864107 !T870424115 iSRTP ! 11/20/87 l Faulty MFP lovejoy control response j 864107 iT870424117 10PS ! 12/5/87 !C.26 erAancements !
C64107 !T870623101 ! OPS i 11/15/87 iMFP contro1 transfer circuitry j
- i i i i 864108 iT870424121 !MAINT 12/7/87 .EQ of excess flow check valves in EFIC sensing lines j i i ! ; !
864109 iT870424123 l0PS l 12/5/87) Eval. of training / proc's for response to EFIC sens line failures j 864111 iT870424125 ! OPS I 12/7/87 A.61 enhancements I l4 i
4 4 i _. 4 i
864112 {T870424133 jENGR/ASTRij 12/7/87 [S, tudy of120V breaker indication j
! ! ! ! I l
l 864113jT870424134 jENGR/ASTPJJ 12/7/87 ! study need for alarm for loss of 480v at MCC level j
! 864113jT870424136 { ENGR /ASTRij 12/7/87 jlocalindication of certain Westinghouse 480V breakers j 864113 !T870623102 ! OPS i 12/7/87 A.59 enhancements i 7 r
- [.
864114 !T870424141 !ENOR/ASTRfi 12/7/87 iProc. enhancements for moritoring DC cntri pwr for 4160VAC j
! i i ! ! i 864122] j j jlN REVIEV (Eval. need for thermal overload protection for MOV's) j_
.k k 864125 ,T870623111 jENGR/ASTRij 10/1/88 l Remove obsolete engineering calculations jJ j
! I i ! I
)
//)/19WT PAGE 2 Situnhy, f&wnhv- 14, ?997 )
. NRC OPEll ITEM CLOSURE SCHEDULE ,
MtC0ls CCTS u R2sp Dept Dee Dits Description J 864128:T870424153 SLRV 12/5/87 : Procedure for calib of CST 1evelinstrument i
864130 !T870424155 'SURV : 12/5/87 Revise SP.210.01 A 864130 iT870424156 .SURV 12/5/87 Revise SP.210.01 A and SP.210.01B !-
]
864130 {T870424157 jSURV 12/5/87 ,, Revise proc's to specify alert and action ranges for pumps 864131,,,T870623117 ,MANT 12/1/87 Review adequacy of elect. maint1 surveillance procedures . ,
864133 ;T870424161,0PS -j 11/15/87 ,Procedura1 response for P-318 overspeed alarm ,,
864133 T870424162 ' OPS j 11/15/87 : Establish AFY Pump motor start time limits C64134 T870424163j0PS 12/1/87 Eval. adequacy of oper. proc's/trng for AFV pump runout response i I !
f 864136 T870424165 MANT i 12/1/87 : Establish proc's for air operated valve maintenance (M.165) 864139 !T870623122 QA 12/7/87 Procedural changes in Q A surveillance program (re-opened)
J . _
864142 !T870424169 S&O j_ ,0riginal concern addressed. Avaiting ASTRP reinspection report.
I
.f.
870201 T870309301 fEP 1 11/15/87 EP training concerns , ,,,,,,
870202 JT870421201 .SECURfiY j 12/7/87 Security contigency plan trai.4 870202 i el REVEV ,
870301 T870603302 LIC/lRO 12/7/87 Revise response to N0187-03-01 _ ,
870302 ,
! IN REVEV (Findings of B&V report in response to 87-03-02) 870303] ,, ,N REVEV (Findings of B&Y report, N0187-03-03) ,
! ! I l ~
870304 T871031001 iPLNT PERF 1/1/88 iRevise M.308 .J i I l ilN REVEV (Management attention to Rad. Environ. Q A program) 870501 {T870401302 ! ,
! ! l ! !
870504l l ! 'IN REVEY (Trng of radiation tech's and QC inspectors) {
I i 870605 ! N REVEY (Violation, control of stored materials) l I $
870607 {T870601402 LIC/TS 11/11/87 ,RS AP 1301 j 870607 lT870820002 LIC/lRO ,
3/1/88 Root cause analysis on R 87-07 jJ i
870608 lT870409307 N REVEV (Safety analysis, CRTS self checking program) ,
870701 'T870506301 SAFETY l Improvements to vital area exit doors (exit buttons) ,J, 870702 T870506302 jSE_CURITY j 12/7/87 ,jPosting of area locations and door numbers in vital areas
~
l 870703 T870506303 IMS ,,,
Telephones not located by doors in vital areas ,,,,, J i !
870704I i i ilN REVEY (Qualifications trng for security compliance auditor) !
AWKPM PA0E 3 Sahn14, AOwhv 1f 1%7
~
,' NRC OPEN ITEM CLOSURE SCHEDULE HRColo CCTS u Rasp Dept l Due Dzts Description J i
870705 iT870506305 iSECURITY ,j 3/31/88 jComplete relocation of security antenna
,J I
870706 T870506306 lSECURITY 6/1/88 : Complete security work on DC b1dg trior to restart J l !
870707 T870506307 ENGR
- jComplete work on site lighting improvements J l
870709 T870506309 iENGR* i ! Upgrade barriers in vital areas 9,10,12,13,14 J l !
870710 !T870506310 ! ENGR
- i Alarm system on Tank Farm fence jJ I i 1 870712:T870506312 jENGR* Locking bolt on vital area doors J 870713 {T870506313 , ENGR
- j CAS/SAS mods to reduce noise
!J i i 870714 IT870506314 ! ENGR * , Exposed viring in vehicle search area ,J I ! l 870715 jT870506315 ' ENGR * { Alarm info lost during dual computer failures J_
870716 T870506316 fENGR* , Allow C AS to open maingate in emerg condition J i I !
870717 IT870506317 iENGR* Insta111ocalized intelligence units in vital areas
!J i !
870718 T870506318 ENGR
- j ! Electronic system to detect badges leavirq site J j
870719 T870303300 ENGRf Alarm system on new security fence J 870720 T870506320 ENGR
- Strobe and alarm on new feree J 870802 T870916347fCHEM[12/7/87 Implement chemical control program 871101 T870522300 SURV 10/16/87 Review and revise sury. proc's to document instr cal data 871501 {T870616103 ! ENGR / MECH i i2/7/87 ! Eval. of design discrepancies in fire alarm annunc. -
i t t t t i i i i I 871502 jT870616103 ENGR / MECH 12/7/87 l Eval. of design discrepancies in fire alarm annunc. ,,,,,
I i ! .-
871503i ! IN REVEY (Fire protection staffing)
{
l i 871504 !!N REVEY (Deportability of 15 deficiencies) ,,,j i l I 871801 I l ,1N REVEY (install covers on toggle switch) i l I l 871803 i ! IN REVIEY (Input supervisory data into security computer) i i 4
I 871901 ' j j ,jfN REVEY (Response to Q A on open item from audit 87-022) i i i !
j 872001 T870925021 ' ENGR 12/15/87 , Lack of root cause determ. for engine vibration
! ! l !
872002 iT870925022 ! ENGR I
- l Electrical cable separation i N]/AYMT PAGE 4 Safunf39, Nnwntw-If 1997
, , NRC OPE 3 ITEM CLOSURE SCHEDULE NRC0la CCTS u lR2sp Dept i Due Data Description J 872003 lT870925023 iENGR/CONFif 12/1/87 Outstanding drawing change notices l .
872004 ,j N REVEY(TDIbuilding work concerns)
I 4
872005 T871028010 ISRTP 11/1/87 Resize terminal box and rework cables 872006 lT871114001 ENGR x Analysis to support the design of the raceway system
! l 872007 iT870925026 ! ENGR X ! Qual of records Siltex and fiberfrax tape
} l }
872008 ji871028012 MAHT j 1/1/88 !
Revise M.300 i !
- i. -
872101 i N REVEV (Failure to perform cable routing inspections) i i 872102 !T870805051 ! ENGR / ELECT 2/15/88 iConfirm adequacy of cable ampacity in overfilled raceways J
! l .
872201lT870916010 TRNG 12/7/87] Initiate pre packaged AL ARA trainirs manual 872201 T870916011 EP 12/7/87 Revise ALARA manual 872201 T870916012lEP 2/28/88 -Field sury. of AL ARA program 1J 372202 T870819002 EP 12/1/87] Tabulated limits for air particles 872203 N REVEY (Eval. of anamo19 e/ TLD program)
RP J 572204 fT870319004 6/30/88 ,TLD System capability to accurately measure non penetrating radiation 872401 1 M REVEY (DG spare jacket cooling water pump concerns)
{
- +
t- iJ 872402 j,T871022002 SRTP Ree::ote shutdown panel testing i .
8316L2 (T861204109 ! ENGR /ELECTI 6/30/89 l Software verification program for CRTS v/ periodic audits J 8516L2 !T870930010 !LIC/IIRG 4/1/88 IIRG investigation /LER suppkment J l i I 8610LO i i i ilN REVEV(CRTS vork) I i3,,,,,,, i. i. i. i.
8616L1 jT861210207 'SRTP j 12/7/87,jModify DC vital power supply j 8616L1 T861210208 LIC/flRG i 11/30/87 ! Supplement LER vith root cause
! i !
8617LO T861112103 ! ENGR / ELECT 12/7/87 ! Complete testing EDG, I for each of 4 safety buses I C617LO T861112106 iENGR/ ELECT 12/7/87 iReview sample of elect. design cale to determire error pattern ,,,
8617LO iT861112107 ' ENGR / ELECT: 12/7/87 !!ssue report on design calc j 1
. l l
8621L3 T861030101 ISURV i 12/7/87 IST of RCS isolation chk vivs in accord. v/ Stolz to Rodrigue z C621L3 T861105118 !!SI l 7/15/88 ! Submit 10 year ISI Plan to the NRC (6 months after s/u) ,J 8621L3 iT870119203 !SURV i 12/7/87 jDHS-059, PLS-045 check valve testing j
- 8621L3 jT870119205 jSURV j12/7/87 . Ensure sury. proc's consistent with Tech Spec's j 8621L3 {T870610100 ! ENGR / MECH
- 12/5/87 Develop supporting celes as req'd by TS 4.5.1.1.B.4 note (a) l
{_
8621L3 jT870610101 jSURV ,12/4/87 JRevise SP.203.11, stabihzation of downstream press < CFT press j '
C621L3 iT870610102 iSURV i 12/1/87 ! ASME Sect. XI relief request on valve leakage trending AC/130%RT PAGE 5 S3tw1137, h%mbv- 14,196'7
e-
. . I
, NRC OPEJ ITEM CLOSURE SCHEDULE NRC0l* lCCTS
- Resp Dept Due Dr.t? De:.iription J t
I l 8622L1 iT870505001 ! OPS l 12/7/87 TNeed management direction - AP.73 on rad monitors j l 8622L1 'T870505002 jENGR/l&C j 11/15/87 Upgrade rad detector monit system via AP.73 valkdown j 8622L1 T870505003 ENGR /l&C j 8/1/88 Eval. des,gn of rad monitor annunciator panels jJ
. b-. b 8624LO jT861229208 l ENGR / ELECT, 11/30/87 AC vital power buses modification, new NSEB ins erter j 8624LO !T861229209 10PS 12/5/87 Revise C.157 i t- -t +
$ l d b 8625L1 iT861229200 l ENGR /NUC 6/1/89 iSpent fuel pool leakage drain path modification jJ 8625L1 jT861229202 PLNT PERF 2/28/88 Procedures / trending for spent fuel poolleakage J 8626LO iT861212303 !LIC/IIRG ! 4/1/88 ilncident analysis, tripping bistable error jJ 8626LO iT861212305 iSRTP i 1/1/89 lSF AS tripping bistable error assumptions reviev jJ 8626LO iT861212304 jMAINT 1/1/88 jAdjust SF AS instr. string prior to 1600 psi j
- d 8628L1 ;T870106202 jENGR/l&C 11/15/87 l Replace Victoreen rad monitors i ! :
8629L2 T870116101 LIC/IIRG
- 11/30/87 ! Root cause analysis of LER ' l*
i i i i .
! i i 8630LO 1870108219 iOPS l 12/1/87 ! Revise A.58 8630LO T870108221 lENGR/ELECTI 1/31/89 l Review of autoclose interlocks for HV-20001, HV-20002 iJ i i i I 8706L2 T870222204 jENGR/P&V j 12/7/87 , Valve configuration contro1 program 8706L2 'T870428106 l ENGR /PSV l 1/14/88 iMOV Final Report - as found configuration ,
i ; i i 8709L1 jT870219301 jSURV j 12/1/87 jRevise proc's associ ted with RCS leak detection j 8709L1 iT870219302 ! OPS 12/5/87 ! Revise OPS procedures associated with RCS leak detection j
! I 8710LO]T870222205]ENOR/ELECTj 11/1/87 'Modify current elect. design of RCS high pt. vents j i . I 8712L1 iT870218303 LIC/IIRG 11/20/87 iSupplement LER with root cause findings j 0712L1 {T870218304 ,LIC/TS j,11/11/87 issue RS AP 1301 i 3712L1 iT870218306 iSURV i 12/1/87 Complete procedure AP.303.01
- i ; . i 8713L0 '
i 'IN REVIEV (Redundant instr cables in same fire area) i i
u I.
8714LO iT870310100 ilS1 12/7/87 ! Modify SP.214.02 {
8714LO iT870310101 !!Si i 12/7/87 iModify SP.210.10, SP210.11 A, SP213.01 }
- i i i i i : j 8715LO iT871027101 OPS i 12/10/88jRevise AP.30 (due date by 11/11) {J 8715LO jT871027102 , ENGR ;12/31/88 jinsta11 Fire Prot. emerg. abort switches jJ l 8715LO iT871027103 !TRNG i 6/30/88 ! Training on revised AP.30 (due date by 11/11) jJ l I l ! ! ;
l 8716LO IT870312102 S&O l 12/7/87 ! Note in AP.44, scheduling VR's for cable work l l 8716LO T870312103 iMAINT i 11/15/87 : Revise EM.145 and EM.163 te reference AP.90 !
i ; I 8717LO iT870312106 10PS ' 11/24/87 ! Revise CCV casually proc. and annunciator proc's f l l 8717LO lT870529301 lPLNT PERF 12/5/87 ! Perform LLRT or get exemption for valves hsted in LER j l
87,17LQjT870529303 JPLNT PEPJ 12/5/87 j00antify and document as found data for hsted penetrations i j 8717LO iT870529304 lLIC/TS i 7/23/88 iRevise US AR to eliminate discrep. v/10CFR50 App. J jJ
_megwr e AGE 6 sitoevsy, annew 11, in7
NRC OPDI ITEM CLOSURE SCHEDULE IIRC01s lCCTS
- R:sp Dept Due Data Description J 8721LO i !N REVIEV(PZR heater damage)
! i' 4 4 .
8723L1 l l l lN REVIEY (8&Y tot nuetron pwr RPS signal not isolated) ,
i 1 ! . -
I 8724LO 'T870402300 jENGR/ELECTj 12/7/87 Finalize cable tray weight cales 8724LO T870402302 JENGR/ ELECT f_
11/30/87 ,Make necessary physical corr ections 8724LO !T870402304 ENGR /CIVL 12/31/87'ReYise NEP5203.9 8724LD iT870402307 ENGR / ELECT 4/1/88 Add modules to CRTS prog. to recale weight of raceway ,,j J i I l 8725LO iT870610104 iLIC/lRG ! 2/1/88 . Root cause analysis J
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t i l i 8726LO T870710401 ! ENGR / ELECT! 12/1/87jEvaluate cause & safety consequences of cable intermixing ,,,,,,j 8726LO ,T870710403 . ENGR / ELECT 11/15/87 ' Ana19 ze intermixed cable and reroute if safety impacted j 8'726LO LT870710404 -LIC/TS 7/31/88 Include in US AR update exceptions to Section 8.2.2.11.H.5 jJ I
8727LO ~T870604303 ! OPS 12/1/87 ReYise B.4 step 5.17
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8729LO ;T870616102 ENGR / MECH 3/13/88 : Install alarm circuit lJ 8729t07T870616103 8729LO ENGR / MECH 12/7/87 Eval. of design discrepancies in fire alarm annunc. ]
T870616104 , ENGR / MECH 3/13/88 ;Sn.oke detectors installed in 480V switchgear rooms jJ 8729LO T870616105 ENGR / MECH 3/13/88 Install alarm circuits (see V0# 108532) iJ 8729L0 jT870616106 ENGR /MECHj12/7/87 Plan for long term upgrade _
8729t0 {T870616107 jENGR/MECHj 3/13/88 ; Replace controller elect. fire pump J 8729LO iT870616110 iLIC/lRG } 11/20/87 !Reeise LER to remove adding a deportability determination in 0C1-12
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'8730LO IT870706001 iTRNG i 3/31/88 fTraining of Ops Dept. Planners l
]J !
8731LO !T870612001 iLIC/lRO 4/1/88 ! Root Cause, update lER if appropriate J 873)LO iT870612002 !SURY j 12/7/87 Revise SP201.08 if P A158 not approved before restart 8733LO ; T870706206 OPS 12/7/87 Establish fire watch peo1 {,,,
! l l 8734LO iT870707002 l ENGR / MECH! 4/30/89 Verify info in MEL, post restart i J t*'~
i
! 1 i 8735L0 :T870727020 illC/lRG i 3/1/88 IRG inYestigaton, missed continous fire watch jJ
! ! ! i ! ,
l 8736LO jT870713001 jsRTP } 10/28/87 jinspection of brng coolers serviced by NSRV for fouling 8736LO T870713002 jMAINT 12/1/87 jPM procedure for pump brng cooler water supply & return lines ,
8736LO T870713003 ! ENGR 6/1/89 Alternatives for soil stabilization around NRY spray ponds [J i
i 4/1/88 8737LO iT870729001 'LIC/lRG 1RG investigation, MUT ievel violation J
! I - +
8702LO T870218308 ! OPS l 12/5/87 ReYise C.13 A and C.138 l 8702LO T870218309 iOPS 9/1/88 Procedures for fire in entri room during cold s/d jJ 8718LO i l llN REVIEY (Vaste Gas 02 concent. sury. not performed) i 7 i ! i i 1918698 : T861212307 lEP ! 11/15/8710ffsite Med serYice !
! i I ht1/ROWT P AGE 7 Satant>y, &nmkv 11,1%7
', ,, NRC OPE 3 ITEM CLCSURE SCHEDULE IIRCCle lCCTS u R:sp Dept Dee Det? Description lJ 588708 j- ,
H REVEV (Degraded motor leads, Limitorque DC oper's) l 8513P TT861106388 ENGR / ELECT,12/7/87 Review for applicability, Engine Generator Control Panel ,
8514P T870212317 -ENGR /P&V ,12/7/87 , Valve actuator weights _,
i i I 8323P lT8611%243 MAINT i 12/1/87 2ero shift due to process pressure for Rosemont j,_,,
I 8614P T861106289 ,0PS 12/10/88 , Auto sprinkler Model C deluge valve fails open ,
J
! l I
8620P ,,
M REVEV (EOL susceptibility of Foxboro instruments)
J N REVEY (Thrust bearings in MSIV's)
L_ i 8623PJ {
l I 8628P T870211302 ?SRTP 11/15/87 ManualContromatics jackscrew l
8703P !T870316205 ! ENGR / ELECT 12/7/87 :Batterg Oround Detector ITE 278 relay problem j
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I 3708P jT871103010 !MANT $ GE HF A relay armature binding, failed contact operation
! l 0709P T870416300 ' SRTP 12/7/87 Square D Co. general purpose relay failed to open _,
I 8714P T871102002 ENGR / MECH -NEY REPORT (Potentia 1 defect in DelaYal DO air press. regululator)
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l 1-l' Tl1573 iT870428106 ENOR/P&V 12/7/87 LER 87-06 MOV safety consequences _
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8026TO jT861106210 ~LIC/TC j 12/1/87 ,0ffsite Dose following OTSG tube leak ,
j 8201X0 N REVEV l l ^ ^ ^
l 1 l 8309X0i IN REVEV (Thermal shields in H2 monit. system hangers) i l
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- DATE TBD PRIOR TO RESTART AC/M7 TWT P AGE 8 $3h.nf>y, NnwnW 14,1997.