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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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LER-2087-029, Forwards Proposed Alarm Sys Mods NFPA 72D Compliance, Ensuring That Plant Fire Protection & Detection Sys Meet NFPA Requirements,Per LER 87-29 Commitments.Corrective Actions Re Tech Spec Violation Also Encl |
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(")suun "5P SACRAMENTO MUNICIPAL UTILITY DISTRICT D 0201 S Street, P.O. Box 15830, Socramento NNOld Id30. (916) 452 3211 i
AN ELECTRIC SYSTEM SERVINEi THE HEART OF CALIF S J.iN -5 P D 01 -
January 2, 1988 GCA 87-912 U. S. Nuclear Regulatory Commission Attn: J. B. Martin, Regional Administrator Region V, Office of Inspection and Enforcement 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION LICENSE NO. DPR-54 i FIRE PROTECTION SYSTEM ENHANCEMENT PLAN
Dear Mr. Martin:
I In accordance with commitments aride in LER 87-29, and the exit meeting with the Commission on November 19, 1987, the enclosed documents detail the District's efforts to ensure fire protection and detection systems meet NFPA requirements.
District report ERPT M-0049 evaluated the current fire protection program for compliance with NFPA 12, 13, 14 (except containment),
15, 20, 24, and 72D. An evaluation of the manual firefighting capabilities in containment is currently underway and will be completed prior to restart. One condition involving testing of unsupervised circuits, as reported in LER 87-29, was identified as a violation of Technical Specifications. Compensatory measures were implemented and modifications installed and tested to correct this deficiency. None of the identified conditions degraded the station's ability to achieve and maintain safe shutdown. The deviations from the NFPA code and options for corrective actions to eliminate these deviations are identified in Attachment I, Table 3-1 from ERPT M-0049. This table also includes modification options for the fire detection and alarm systems. Attachment II contains a detailed evaluation of the proposed alarm system modifications. The forecast completion dates in Table 3-1 are tentative; a firm date for each item will be discussed with the NRC in the first quarter of 1988, when the Long Range Schedule Process is finalized.
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RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638 9799;(209) 333 2935
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~J.-B. Martin away 2, M88 GCA 87-912 Acceptance testing of the fire pumps as required to provide baseline data for future testing is scheduled for completion.by May 31, 1988. This satisfies the District's commitment made in our letter dated December 15, 1987, "Resolution of Fire Pump Open Items."
In summary, - the ' above evaluations verified the adequacy of the current fire- protection systems to ensure safe shutdown capability is maintained. Additionally, in order to improve reliability of the systems and meet applicable NFPA requirements, modifications have been identified and scheduled through the Long Range Schedule Process.
Please contact me if you have any questions. Members of your staff requiring further information or clarification may contact Steve Crunk or Dave Swank of my Licensing Staff at extension 4913.
Sincerely,
.J G. Carl Andog ni Chief Executive Officer, Nuclear cc with attachments:
C. Ramsey, NRC, Region V S. Stuart, NRC, Region V A. D'Angelo, Resident Inspector G. Kalman, NRC, Bethesda
ATTACHMENT I TABLE 3-1 DEVIATIONS TO BE CORRECTED i
i 3-1 1333z
TCCLE 3-1 DEDICTIONS 70 BE CORRECTED NFPA CODE NODIFICATION FORECAST CODE SECTIDW CORRECTIVE ACTIDs DOCUMENT COMPLETION DATE 12-1968 122 A warning bea m will be installed outside each CO2 protected New ECW 3/1/89 es.a is 4.n111ery Building. A warning horn will be provided or DCP in overheed ores of Zeae 11. Mezzanine Settery Room.
12-1968 1439 The push-buttor stations for Zones 36 and 39 will be labeled CCTS 12/10/88 to describe the area they protect. T871927101 12-1968 1644 As-built design calculations for the Aum111ery Building CO2 New Calc 2/1/89 zones will be developed and/or discherge test will be performed. or STP Perfore a full discherge test on Zone 38 after new calculatione prepered.
. 12-1968 1714 Incorporate vendor maintenance itees from 514.23-INS 3 into CCTS 4/1/88 plant procedures as needed. T871119301 12-1968 172 newtee aP.3e to include maintenning systee operability for CCTS 12/10/88 routine entry into CO2 zones per LER 87-13 response. T871827101 l
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TABLE 3-1 CEVIAT!DNS TO BE CORRECTED NFPA CODE CODE NODIFICATION P0 RECAST SECTION CORRECTIVE ACTION DOCURENT CORPLETION DATE 12-1968 2212 Install e deeper in the ve.atilation panel in Zone 19 which to New ECM 3/1/89 interlocked with the CO2 syntes. or DCP 12-1980 1-6.2 Install e verning beecon outside each Q32 protected area on New ECM 3/1/89 the Turbine deck, or DCP 12-1960 1-7.2 Create as-built design calculations for the Turbine zones and New Calc 2/1/89 the NSEB and/or perfore discherge teste. or STP '
12-1960 1-8.3.3 Replace the push-button statione on the Turbine deck with New ECN 3/1/89 weatherproof devices or protect in piece.
12-1999 1-8.3.8 Create new Turbine zone design calculatione and/or perfore New Cole 2/1/89 e discharge test. or STP 12-1980 1-9.1 Create new Turbine zone desige calculatione and/or perfore New Calc 2/1/89 e discharge teet. or STP 12-19ee 1-10.4 Clean the entended discharge nozzles in .'.one 32 to remove corrosion.
Perfore eyeten discharge test on Zone 76 per NCR S-6987. STP 2/1/89 12-1988 1-10.5.2 Create new Turbine zone design calculatione and/or perfore New Cole 2/1/89 discharge teste. or STP 12-1988 1-11.3 Rewtoe procedure AP.38 to retain systee operability for CCTS 3/1/89 routine entry per LER 87-15 responer. Procedure will be T871821181 revloed after hardware fines are completed.
12-199t 2-5.3.3 Perform a full discharge test for Turbine zone 51. STP 2/1/89 1QZ 3-3 r , -- - w a
3 TABLE 3-1 LEY 1AT10NS TO BE CORRECTE)
NFPA CODE CODE SECTION N001FICAT10N FORECAST CORRECTIVE ACTION DOCURENT COMPLETION DATE 12-1988 3-3.1 Create new Turbine zone calculatione and/or perfore discharge New Calc 2/1/89 tests. or STP 13-1971 2119 A hydraulic calculation of the as-built Turbine Eu11 ding wet- New Calc 9/1/88 pipe eyotes will be performed to verify the adequacy of the eyetre.
13-1971 3872 The home station et the northwest corner of the Turbine New ECM 3/1/89 Building, grade level, will be modified no that it is or DCP supplied by 2-1/2 inch or larger piping.
13-1971 3151 An evaluation and analyste of the ability of the piping to New Calc 6/1/89 withetend a solemic event will be performed, or et the or ECM locatzone indicated below, one to two inches of clearance will be provided around the c m seine which are grouted to well penetrationes the penetrations will be oesied with a flexible fire rated meterial.
Il Crees Mein #11 et grade level of the Aum111ery Building Basement penetrates the corridor well et S & 18.3.
- 2) Crose Main #13 Grade level at N-P & 19.3.
33 Crose Main #11 supplying the grade elevetion at E & 9.7.
- 4) Cross Mein #1 evpplying the turbine elevation et E & 18.6.
33 The 4 anch crose sein supplying suppreselon Zone 7 on the Turbane Deck level penetrates the wall at R-S & 10.6.
6? Crose Mein #1 eupplying supprecoloe Zone 5 on the Turbine Deck level penetrates the well et S & lt.3-10.6.
13-1971 316e Earthquake bracing will be installed on the leed-in piping New ECN 6/1/89 from the fare loop to the Amm111ery Building wystems where or DCP the lead-in exits the ground in the Tonk Fere.
1333Z 3-4
TABLE 3-1 DEVIATIONS 70 SE CORRECTED NFPA CODE NODIFICATION FORECAST CODE SECTION CORRECTIVE ACTION DOCUMENT COMPLETION DATE 13-1971 3490 Stone will be installed on sprinkler syntes control valves work Request 8/1/88 indicatang the systema controlled by each valve.
13-1971 3528 The paping being supported by branch line 95 in the Turbine Work Request 12/31/88 Building will be repaired so that it le not supported by branch line 95.
13-1971 3568 Miaming and broken hengers will be replaced in the areas work Request 12/31/88 indicated belows AUIILIARY BUILDING 13 No henger le provided on branch line #24 (Turbine Level) between the 4th and the 7th sprinklere from the end of this branch line.
29 No henger le provided near the end beed on branch line 877 (Tusbine Levell.
- 3) Branch line #47 (Turbine Levell between column lines K and L is not provided with pipe hengers.
- 4) Branch li p #33 EMezzanine Level) closest to crose sein N-9 hee no henger supporting it.
33 Branch line all (Grade Leve13 closest to crose main N-11 hoe had the henger removed. The pipe Ce uneupported.
63 Branch line #15 (Grade' Level) et the east end has had a henger removed. The pipe et this location to not supported.
79 Branch line ele (Grade Level) et the first tee from crose sein #13 hee had a henger removed. The pipe et this location is not supported.
83 The branch line along the south well of the meia corridor Grade Level hee a henger removed at the weet end. The pipe et this location is not supported.
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TABLE 3-1 DEVIATIONS TO BE CORRECTED NFPA CODE NODIFICATION FotECAST CODC SECTION CORRECTIVE ACTION DOCUWENT CONPLETION DATE 13-1971 3610 The oprinkler heed that is out of position le the Auxiliary New ECN 6/1/89 Su11 dang (bronch line 34, zone 20) will be removed from its or DCP branch line end the piping will be capped where the heed is removed. The sprinkler heeds listed below will be repositioned to their correct positions:
TURBINE BUILDING Work Request 7/1/88
- 1) On line 64 9 03, grade level, the sprinkler heed to installed approximately 45 degrees out of its designed position.
23 On line 81 0 08, grade level, the sprinkler heed is installed approximately 45 degrees out of its designed position.
- 3) On line 77 between E & G, grade level, e pondent heed le installed in en opreght position.
- 4) On line 95 between E E G 9 11.8, grade level, the upright head is turned down.
13-1971 3679 AUIILIaRT BUILDING Work Request 12/31/88 Comoged oprinkler heede will be replaced at the following locationet
- 1) Cheetcal Storage telecay 23 Nein Corridor hezzonine Elevation
- 3) Nein Corridor Turbine Deck Elevation 1333Z 3-7 P
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TABLE 3-1 DEVICTIONS TO DE CORRECTLD NFPA CODE CODE SECT 10m IIODIFICATION FORECAST COR2ECTIVE ACTION DOCUWENT ConPLETICE DATE 13-1971 3678 EContinued) TURBINE BUILDIEG Guards wall be repelred or replaced at the following locationes
- 1) Line 95 e D11.6
- 2) Line 74 9 DS.2
- 3) Line E3 9 D2.G
- 4) Line 76 9 E5.6
- 5) Line el # D7.6
- 6) Line 82 9 DS.2 (this bood not shown om drawing N31.01-124)
- 7) Line 111 betroen C & D
- 8) Line 111 9 54.4
- 9) Line 111 # C4.4
- 18) Line 66 9 A2
- 11) Line 64 9 32
- 12) Line 68 9 C2
- 13) Lane 116 9 512.2 Befflee will be repelred or replaced et the locatione indicated belows
- 1) Seifles t29) hewe been removed iron the outdoor breach lines located at the edge of the Turbine Cock.
- 2) Baffles 83) removed from line 111 9 B-C4.6 33 5efflee (2) removed from line 111 9 C-D4.6 49 Baffle removed from line 82 9 G8.2 1333Z 3-8
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TABLE 3-1 DEVILTIONS TO SC COREECTED BFPA CODE NODIFICATION FORECAST CODE SECTION CORRECTIVE ACTION DOCUMENT CONPLETIOE DATE 13-1971 3678 (Continued) 268 Out of position on line 111 9 C-04
- 27) Out of position on line til 9 54.8 288 Out of position on line 68 9 C-D2 13-1971 3688 TURSINE BUILDING Work Request 12/31/88 The two pointed oprinkler heads will be replaced. These heeds are located at branch line 81 et D7.6 and branch line 82 et D8.2.
13-1971 4268 AUEILIARY BUILDING Ilev ECM 5/1/C.'
or DCP The sprinkler heads in ibe Chemical Storage Room will be repositioned so that they are within 16 inches of the ceiling.
13-1971 4329 A baffle will be instelled between the two sprinklers closer New ECN 5/1/89 than eau feet sport on branch line 24, 40 foot elevation, in or DCP the Aum111ery Building. A beffle will be instelled between oprinklers on breach line 72, between coluene D5 and E3, on the 28 foot elevation of the Turbine Buildine-13332 3-18
TABLE 3-1 DEVICTIONS TO DE CORRECTED NFPA CODE NODIFICATION Fneer g CODE SECTION CORRECTIVE ACTION DOCUMENT ConPLETION DATE 13-1998 3-9 Rodify the inspectors test connections on the NSES pre-action New ECE 6/1/89 systeme and the DG Building systee so that they will provide or DCP e flow equivalent to one oprinkler heed.
13-1968 3-19.3.3 An eveleetion and enelyste of the ability of the piping to New Calc 6/1/89 withetend e seismic event will be performed, or et the or ECM locations listed below earthquake backing will be provided:
Earthquake bracing will be provided at the top of the TSC systes riser.
Earthquake bracing will be provided ehere the TSC system cross mela changes direction et R & 11.7.
Earthqbake bracing will be provided on the third floor of the NSE8 where the crose sein changes direction before penetrating the well et coluna lines N & 14.2.
Earthquake bracing will be installed on the third floor of the NSEB et the end of the crose meio et colmen lines M & 14.
o Earthquake bracing et the top of the riser for the NSEN room 362 systes will be reinotelled correctly.
Earthquake bracing will be installed on the end of the cromo sein an room 362 of the NSEE.
Earthquake bracing will be installed on the end cf the crose mein in race 363 of the NSEB.
Earthqvake bracing r.111 be insta!!ed at the top of the riser et coluen linee P.6 & 23 of the DG Deilding.
Earthquake bracing will be provided on the end of the crose sein an the east mezzontee area of the DG Sullding.
Earthquake bracing will be anstalled on the end of the croom sete in the weet control rooo of the DG building.
13-1999 3-13.3 The oprinkler head on the 29 foot elevation, et colmen linee New ECM 9/30/89 5 & 15, is the NSEB will be repositioned so that its or DCP pattern le not obstructed.
13-1980 3-15.7 See section 3-18.3.5 of NFPA 13-1999. New Calc 6/1/89 or ECE 13-1990 3-16.2 The oprinkler heed on the grade elevation, et column lines Nork Nequest 12/31/88 M & 15, an the RSES will be reinste!!ed to its correct position.
1333Z 3-11
TABLE 3-1 LETIITIOes TO BE CORRECTED NFPA CODE NODIFICATION FORECAST CODE SECTION CostECTIVE ACTION DOCUWEET CORPLETIOE DATE 13-1980 4-3.1 The sprankler beiede located above the false ceiling in the New ECM 6/1/89 TSC will be relocated to within 16 inches of the ceiling. or DCP The four oprinkler heeds sorth of colmen line 16.7 in the hallway of the 21 foot elevetion of the NSEE will be relocated within 16 inches of the ceiling. The three sprinkler heede east of colmen 11 ass R & 13.2 on the 21 foot elevation of the NSEE will be relocated within 16 inches of the ceiling. The sprinkler heed et E & 15.3 on the 21 foot elevation of the RSEE will be repoettioned to within 16 taches of the ceiling.
13-1990 7-3.3 Nydraulic celeslations of the ee-boilt sprinkler systems in New Calc 9/1/86 the ESEB eill be performed.
13-1998 7-4.3 Mydraulic calculatione of the as-boilt sprinkler eyetees in New Calc 9/1/88 the ItSES will be performed.
13332 3-12
TABLE 3-1 CEVIATIONS TO BE CORRECTED .
t NFPA CODE IIODIFICATION FORELAST CODE SECTION COREECTIVE AC DC3AENT CC4fPt.ETIDIE DATE 14-1998 5-6 The sign indicating the systes supplied by the fire kork Request 4/1/88 department connection on the T & R Building vill be cher: J to read "Steedpipe Systee'.
14-1928 7-4 An evaluation and analysis of the ability of the piping New Calc 6/1/89 to withetend a seismic ewsnt will be performed or, or ECM four-way evay brace will be installed at the top of the
, riser in the Auxiliary Building stairwell.
14-1992 7-4 thpointed piping on the systes riser will be pointed. Work Request 7/1/89 L
9 f
1333Z 3-13
TABLE 3-1 DEVI4TIONS TO DE CORRECTED NFPA CODE CODE SECTION NODIFICATION FORECAST CORRECTIVE ACTION DOCUNENT COMPLETION DATE 15-1 % 9 6812 Revise surveillance procedures to include flushing of CCTS 3/31/88 atrainers on the Transformer Yard and Turbie Pu11 ding veter TL71119301 apray systeam.
15-1 % 9 8058 R2 vise surve111snce procedurse to include verifying that the CCTS 3/31,38 actuation detectors on the Transformer Yard and Turbine 78711193e1 Building water spray systems operate within 44 seconds when a standard heat source is applied to the detecters.
15-1 % 9 NFPA-13 Frovide clearance around the riser piping that penetrates the New ECM 6/1/89 3-19-3 foundation of the Transformer Yard Valve Nouse. or DCP i
i 13332 3-14
TABLE 3-1 Di',IATIONS '60 SE CORRECTED NFPA CODE MODIFICATICN FPr*rAST CODE SECTION CORRECTIVE ACTION DOCUMENT CCfdt.ETION DATE 15-1979 3-2 Hydroclac calcalatione, for the as-built water spray systems hew Calc 9/1/88 in the NSER, will be performed to verify the adequacy of the ayatems.
15-1979 4-8.1 The obetructed nozzle et hydraulic reference point 18, off New ECN 6/1/89 of branch 11he 84, et the (-)11 foot elevation, in tunnel or DCP (s61 of the NSE8 v111 be repositioned so that it is not obstructed.
15-1979 6-2.2 Revise surveillance pr redures to include fluehang of CCTS 3/31/88 strainere on the NSEB water oprey systems. T871119301 O
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4 TABLE 3-1 DEVIATIONS TO BE CORRECTED
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NFPA CODE NODIFICATION FORECAST CODE SECTION CORRECTIVE ACTION DOCUMENT CONPLETION DATE 21-1978 4 General arrangement drawings of P-440 vill be made. New Drawing 7/1/8e i
28-197e 143 Clearance will be provided around the supply piping to P-996 New ECM 12/31/68 where the piping penetrates the foundation. or DCP 20-1978 233 The 3/4 inch air release valve on P-449 vill be replaced with New ECM 12/31/88 a 1-1/2 anch air release valve. or DCP 1
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20-1970 314 Provide separate annunciation for pump running and loss of New ECM 6/1/89 power alares from P-440. or DCP L
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TABLE 3-1 CEVIATIONS TO BE CORRECTED NFPA CODE NODIFICATION FORECAST CODE SECTION CORRECTIVE ACTION DOCUMENT COMPLETION DATE 24-1978 11, 12 brewing C-182 will be revised to correct the deviatione cited Drawing Change 6/1/88 below
- 1) Poet Indicator Valwee (P1Vs) Nos. 33 (FPW 485),
35 (FPW 963), and 48 (FPW 998) are not shown.
- 2) PIV No. 5, as shown on the diagram, does not exist.
l
- 3) Fire hydrant FH No. is not labeled and its secociated home house is not shown.
- e Fire hydrants FN Nos. 4, 9, 16, and 21 do not have home houses se shown on the drawing.
Si The home houses for fire hydrants FH Nos. 23 and 26 are not indictted.
6! The connw tion to the diesel fire pump P-996 from the yard earn loop is not shown.
In addition, the fire hydrant near the PAP Security Building
. is not identified.
24-1978 55 Fire hydrants and home hovmes will be labeled with work Pequest 3/31/88 identification numbers.
24-1970 62 Eurveillance procedures will be revised to include an annual CCTS 4/1/88 service test of all fire home in home houses. T871119301 l
24-1978 64 Surveillance procedures will be revised to include ensuring CCTS 4/1/88 that fire home in home houses is refolded at different pointe T871119341 or rolled up after vee.
13332 3-17 L____ __
TABLE 3-1 PEVIATIONS TO BE CORRCCTED NFPO- CODE CODE SECTION NODIFICATION FORECAST CORRECTIVE ACTION DOCUMENT COMPLETION DATE 72D-1%7 2032 Replace the Control Room annunciation system (H3FPA & H3FP8) New ECM 5/30/89 with a systes meeting NFPA 72D or demonstrated equivalents. or DCN 72D-1%7 2422 . Tie general fire alare circuits to Control Room annunciation (ECNe R-1993A & B).
New ECN 9/30/89 or DCP Upgrade Control Room annunciation. New ECN 9/30/89 or DCP 72D-1%7 2423 Upgrade Control Room annunciation. New ECM 9/30/89 or DCP 72D-1%7 3335 T1e general fire alarm circuits (ECNR-1993A & 8). New ECN 5/30/89 or DCP Upgrade Control Room annunciation. New ECN 9/30/89 or DCP 72D-1%7 4042 Upgrade Control Room annunciation. New ECN 9/30/89 or DCP 72D-1%7 4e98 Upgree Control Roos annunciation.
! New ECN 9/30/89 or M7 1333Z 3-18
TAGLE 3-1 DEVIATIONS TO BE CORRECTED NFPA CODE 4. 'IFICAT1:4 FORECAST CODE SECTION CORRECTIVE ACTION DOCUMENT COMPLETION DATE 72D-1980 2-2.2 Replace IDADS annunciation ayotes with a syntes complying with New ECN 9/30/89 the requirements of NFPA 72D or demonstrated equivalents, or DCN 72D-1988 2-6.2.3 Perform at.alysis of backup power supplies for all fire panels New ECN 9/30/89 or provide internal battery units complying with NFPA 72D. or DCN 720-1980 2-7.1 Tie the general fire alarm signal from each local panel to New ECN 9/30/89 Control Room annunciation (ECN N-1993A & B). or DCN UNrade roatrol Roc,a annunciation.
723 1980 3-6.3 Separate tha detection zone circuits from the devices which New ECN 9/30/89 indicate water flow ffee suppreaston syntese. or DCN 72D-1384 3-9.3 Separatt, preesure ev.16,%1gh and valve position dwite.h for New ECN 9/30/P9 zones 81 ano 52, or DCN 72D-1984 3-14.1 Upgrade Cchtrol Rn annunciation. New ECN 9/30/89 or DCN CD-1953 4-J.2 Upgrade Control Room annunciatloa. New ECE 9/30/89 or DCN 72D-196J 4-3.3.4 Sepe: ate pressure switch high and valve position evi + Ier New ECM 9/30/89 z.,nes 81 and 82. or DCN 72D-1988 4-b Lewise IDADS point E-80e3 to describe general panel trouble New ECM 9/30/89 (interial. or DCN 1333Z 3-19
TABLE 3-1 CEVICTIONS TO BE CORRECTED RFPQ CODE CODE SECTION MODIFICATION FORECAST CORRECTIVE ACTION DOCDnENT CONPLETION DATE 72E-1976 4-3.2 Replace the suspended ce111mg that has been removed from Work Request 6/1/88 Computer Room 338.
L Cocate the detectore in NSE8 roome 146, 147, 234, 235, 236, New ECN 9/30/89 237, .. and 363 to e ceiling mounted configuration. or DCP 72E-1978 4-3.7.2 Additional detectors will be installed and/or relocated in New ECM 9/30/89 order to enhance the reliability of the detector in the 488 or DCP i volt and 4168 volt switchgear rooms.
b 72E-1978 4-3.7.3 Detection will be provided above- roome 232, 233, 358 and New ECW 9/30/89 359 in the NSEB. or DCP 72E-1978 4-4.1 Relocate the ISD in room 361 of the NSEB. New ECN 9/30/89 or DCP 1
13332 3-20
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05000312/LER-1987-006, Forwards LER 87-006-03.Rev Incorporates Commitment to Address Assessment of Safety Consequences for motor-operated Valve as-found Configuration.Final Rept Will Be Submitted within 60 Days or by 880114 | Forwards LER 87-006-03.Rev Incorporates Commitment to Address Assessment of Safety Consequences for motor-operated Valve as-found Configuration.Final Rept Will Be Submitted within 60 Days or by 880114 | | 05000312/LER-1987-009, Forwards LER 87-009-01.W/o Encl | Forwards LER 87-009-01.W/o Encl | | 05000312/LER-1987-029, Forwards Proposed Alarm Sys Mods NFPA 72D Compliance, Ensuring That Plant Fire Protection & Detection Sys Meet NFPA Requirements,Per LER 87-29 Commitments.Corrective Actions Re Tech Spec Violation Also Encl | Forwards Proposed Alarm Sys Mods NFPA 72D Compliance, Ensuring That Plant Fire Protection & Detection Sys Meet NFPA Requirements,Per LER 87-29 Commitments.Corrective Actions Re Tech Spec Violation Also Encl | | 05000312/LER-1987-031, Forwards Rev 1 to LER 87-031,stating That Proposed Tech Spec Amend 158 Will Provide Controls for Hydrogen Recombiner Sys & Surveillance Procedures SP.45A & SP.45B Will Replace Procedure SP.201.08 | Forwards Rev 1 to LER 87-031,stating That Proposed Tech Spec Amend 158 Will Provide Controls for Hydrogen Recombiner Sys & Surveillance Procedures SP.45A & SP.45B Will Replace Procedure SP.201.08 | | 05000312/LER-1987-035, Corrected Page 1 to LER 87-035-00:on 870625,during Startup Test Procedure 199 Continuous Fire Watch Abandoned from Monitoring Alarm Panel H4FCP5 for 3 H.Caused by Uncontrolled Discharges of Carbon Dioxide Exposing Personnel to | Corrected Page 1 to LER 87-035-00:on 870625,during Startup Test Procedure 199 Continuous Fire Watch Abandoned from Monitoring Alarm Panel H4FCP5 for 3 H.Caused by Uncontrolled Discharges of Carbon Dioxide Exposing Personnel to Risk | | 05000312/LER-1987-036, Errata to LER 87-036-01:on 870608,discovered That Pipe Supplying Water for Bearing Cooling for Reactor Bldg Spray Pump Blocked.Preventive Maint Procedure for Pump Bearing Cooling Water Supply & Return Lines Instituted | Errata to LER 87-036-01:on 870608,discovered That Pipe Supplying Water for Bearing Cooling for Reactor Bldg Spray Pump Blocked.Preventive Maint Procedure for Pump Bearing Cooling Water Supply & Return Lines Instituted | |
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