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MONTHYEARML20134A2191985-10-31031 October 1985 Forwards Response to Request for Addl Info Re Conformance to Reg Guide 1.97.Util Will Widen Indicated Quench Tank Temp Range During Cycle 8 Refueling Outage to Include 50 F Lower Limit Project stage: Request ML20137H7851986-01-13013 January 1986 Forwards Followup Response to NRC Request for Addl Info Re Conformance to Reg Guide 1.97.Rev 3 to 840914 Reg Guide 1.97 Rept Also Encl Project stage: Request ML20153D6771986-02-11011 February 1986 Forwards Attachment II to Util 851031 Response to Request for Addl Info Re Reg Guide 1.97,inadvertently Omitted from Original Submittal Project stage: Request ML20154K9051986-03-0707 March 1986 Submits Revised Reg Guide 1.97 Implementation Schedule. Requirements,Including Upgrade of Spds,Will Be Completed by Cycle 8.Seismic Qualification of SPDS CRTs Cannot Be Qualified Until Cycle 9 Due to Procurement Problems Project stage: Other ML20210G2431986-09-15015 September 1986 Forwards Audit Plan for Safety Evaluation of Facility Action Plan for Performance Improvement of Control Room Design & Spds.Audit Should Be Conducted in Early Oct to Preclude Impact on Proposed Restart Date Project stage: Approval ML20214R5831987-03-31031 March 1987 Rev 2 to Conformance to Reg Guide 1.97,Rancho Seco, Informal Rept Project stage: Other ML20236N5901987-11-0909 November 1987 Discusses SPDS Safety Evaluation Issues Re Fire Protection, Software Validation & Verification & Electrical Isolation. Listing of Status of Each Issue & Comparison of Nonlinear Data Points in Final Acceptance Test Encl Project stage: Other 1986-03-07
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8851999-10-0808 October 1999 Informs of Staff Determination That Listed Calculations Should Be Withheld from Public Disclosure,Per 10CFR2.790, as Requested in 990909 Affidavit ML20211J7731999-08-31031 August 1999 Forwards Insp Rept 50-312/99-03 on 990802-06.No Violations Noted.Insp Included Decommissioning & Dismantlement Activities,Verification of Compliance with Selected TS & Review of Completed SEs ML20211H7481999-08-13013 August 1999 Forwards Amend 126 to License DPR-54 & Safety Evaluation. Amend Changes Permanently Defueled Technical Specification (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP Level Alarm Switches with Generic Ref 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20207E9181999-05-27027 May 1999 Informs That Effective 990328,NRR Underwent Reorganization. within Framework of Reorganization,Div of Licensing Project Mgt Created.Reorganization Chart Encl ML20206U7411999-05-18018 May 1999 Provides Summary of 990217-18 Visit to Rancho Seco Facility to Become Familar with Facility,Including Onsite ISFSI & Meeting with Representatives of Smud to Discuss Issues Re Revised Rancho Seco Ep,Submitted to NRC on 960429 ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204H6751999-03-19019 March 1999 Forwards Insp Rept 50-312/99-02 on 990309-11.No Violations Noted.Portions of Physical Security & Access Authorization Programs Were Inspected ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20207L1711999-03-10010 March 1999 Informs of Staff Determination That Supporting Calculations & Drawings Contained in Rev 2 of Sar, Should Be Withheld from Public Disclosure,Per 10CFR2.790 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20203D0761999-02-10010 February 1999 Ltr Contract:Task Order 37 Entitled, Technical Assistance in Review of New Safety Analysis Rept for Rancho Seco Spent Fuel Storage Facility, Under Contract NRC-02-95-003 ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A6031998-08-0707 August 1998 Forwards Insp Rept 50-312/98-03 on 980706-09.No Violations Noted ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236Q9461998-07-15015 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-02 ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20236E8211998-06-0303 June 1998 Forwards Insp Rept 50-312/98-02 on 980519-21 & NOV Re Failure to Review & Consider All Info Obtained During Background Investigation.Areas Examined During Insp Also Included Portions of Physical Security Program ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 IR 05000312/19980011998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-312/98-01 on 980205 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202C4641998-02-0505 February 1998 Forwards Insp Rept 50-312/98-01 on 980105-08 & Notice of Violation.Insp Included Decommissioning & Dismantlement Work Underway,Verification of Compliance W/Selected TS & Main & Surveillance Activities Associated W/Sfp ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20198K5391997-10-21021 October 1997 Forwards Insp Rept 50-312/97-04 on 970922-25 & Notice of Violation.Response Required & Will Be Used to Determine If Further Action Will Be Necessary ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20198G8141997-08-22022 August 1997 Forwards Amend 125 to License DPR-54 & Safety Evaluation. Amend Permits Smud to Change TS to Incorporate Revised 10CFR20.Amend Also Revises References from NRC Region V to NRC Region IV ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 ML20149E5031997-07-10010 July 1997 Second Partial Response to FOIA Request for Documents. Forwards Records Listed in App C Being Made Available in Pdr.Records in App D Already Available in PDR ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141A1721997-06-17017 June 1997 Forwards Insp Rept 50-312/97-03 on 970603-05.No Violations Noted.Areas Examined During Insp Included Portions of Physical Security Program 1999-08-31
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEAR3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held ML20210H9541999-07-0707 July 1999 Informs NRC of Change to Rancho Seco Decommissioning Schedule,As Described in Licensee Post Shutdown Decommissioning Activities Rept ML20209D2501999-06-24024 June 1999 Informs That Util Has Revised All Sections of Rancho Seco Emergency Plan (Rsep),Change 4,effective 990624 ML20196G0431999-06-22022 June 1999 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Smud Rancho Seco Nuclear Generating Station ML20195B8511999-05-27027 May 1999 Forwards Change 4 to Rancho Seco Emergency Plan, Incorporating Commitments Made to NRC as Outlined in NRC .Emergency Plan Includes Two Listed Supporting Documents ML20195D1851999-05-27027 May 1999 Forwards Rancho Seco Annual Rept, IAW Plant Permanently Defueled TS D6.9.4 & D6.9.6b.Rept Contains Shutdown Statistics,Narrative Summary of Shutdown Experience,Er Info & Tabulation of Facility Changes,Tests & Experiments ML20206M1611999-05-10010 May 1999 Forwards Listed Proprietary Calculations to Support Review of Rancho Seco ISFSI Sar.Proprietary Encls Withheld ML20206E8591999-04-12012 April 1999 Provides Info Re High Total Coliform Result in Plant Domestic Sewage Effluent Prior to Confluence with Combined Effluent.Cause of High Total Coliform Result Was Broken Flow Rate Instrument.Instrument Was Repaired on 990318 ML20204E4031999-03-16016 March 1999 Submits Rept of Status of Decommissioning Funding for Rancho Seco,As Required by 10CFR50.75(f)(1).Plant Is Currently in Safstor, with Operating License Scheduled to Expire in Oct 2008 ML20204E6441999-03-11011 March 1999 Forwards Individual Monitoring Repts for Personnel That Required Radiation Exposure Monitoring During 1998 ML20204E6661999-03-11011 March 1999 Forwards Rancho Seco Exposure Rept for Individuals That Received Greater than 100 Mrem During 1998,IAW TS D6.9.2.2 & NRC Regulatory Guide 1.16 NL-99-002, Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3)1999-03-10010 March 1999 Submits Info About Property Insurance for Rancho Seco Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20207D4431999-03-0101 March 1999 Forwards Annual Radioactive Effluent Release Rept, for Rancho Seco Nuclear Generating Station for 1998 ML20207H6181999-02-18018 February 1999 Provides Attached Metrix & Two Copies of Rancho Seco ISFSI Sar,Rev 2 on Compact Disc,As Requested in 990209 Meeting. First Rounds of RAIs Dealt Primarily with Use of Cask as Storage Cask.Without Compact Disc ML20155D4431998-10-27027 October 1998 Forwards Amend 3 to Rancho Seco Dsar,Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode.With Instructions & List of Effective Pages NL-98-032, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1998-09-30030 September 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20237A9481998-08-0303 August 1998 Forwards Smud 1997 Annual Rept, IAW 10CFR50.71(b),which Includes Certified Financial Statements ML20236J6331998-06-30030 June 1998 Forwards Response to Violations Noted in Insp Rept 50-312/98-02.Corrective Actions:Util Revised RSAP-1003 to Clarify District Security Staff Responsibilities Re Handling & Review of Criminal History Info ML20217G8391998-04-20020 April 1998 Forwards Copy of Rancho Seco Monthly Discharger Self-Monitoring Rept for Mar 1998 ML20217H0451998-03-18018 March 1998 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1997,per TS D6.9.2.2 & Guidance Contained in Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1997 ML20217F1891998-03-18018 March 1998 Forwards Signed Original & Amend 7 to Rancho Seco Long Term Defueled Condition Physical Security Plan & Rev 4 to Long Term Defueled Condition Training & Qualification Plan.Encls Withheld,Per 10CFR2.790 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation ML20216K1091998-03-11011 March 1998 Forwards NRC Form 5 Individual Monitoring Repts for Personnel Who Required Radiation Exposure Monitoring,Per 10CFR20.1502 During 1997.W/o Encl ML20217N9531998-03-0505 March 1998 Responds to Violations Noted in Insp Rept 50-312/98-01. Corrective Actions:Radiation Protection Group Wrote Potential Deviation from Quality (Pdq) 97-0082 & Assigned Radiation Protection Action to Determine Cause & CAs ML20203H7001998-02-25025 February 1998 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1997, IAW 10CFR50.36a(a)(2) & TS D6.9.3.Revs to Radiological Environ Monitoring Manual & off-site Dose Calculation Manual,Encl NL-98-006, Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3)1998-02-12012 February 1998 Submits Annual Rept of Property Insurance Levels for Rsngs, IAW 10CFR50.54(w)(3) ML20202G0131998-02-12012 February 1998 Forwards Certified Copies of Listed Nuclear Liability Endorsements & Master Worker Policy Certificate of Insurace for Facility ML20199A5881997-11-10010 November 1997 Responds to NRC Re Violations Noted in Insp Rept 50-312/97-01.Corrective Actions:Reviewed SFP Water Temp & Instrument Calibr Records,Generated Otr 97-001 to Document out-of-tolerance Instrument & Generated Pdq 97-0064 ML20198R9501997-11-0505 November 1997 Requests Interpretation of or Rev to NUREG-1536, Std Review Plan for Dry Cask Storage Sys, Re Compliance W/ 10CFR72.236(e) & 10CFR72.122(h)(4) for Dry Fuel Storage Casks ML20217D3101997-09-25025 September 1997 Forwards Update of 1995 Decommissioning Evaluation, for Rancho Seco Nuclear Generation Station & Annual Review of Nuclear Decommissioning Trust Fund for Adequacy Re Assumptions for Inflation & Rate of Return ML20211F0991997-09-23023 September 1997 Forwards One Certified Copy of Mutual Atomic Energy Liability Underwriters Nuclear Energy Liability Insurance Endorsement 120 for Policy MF-0075 for Smud Rancho Seco Nuclear Facility ML20151L0281997-07-29029 July 1997 Provides Response to NRC Request for Addl Info Re TS Change,Relocating Administrative Controls Related to QA to Ufsar,Per NUREG-0737 NL-97-030, Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs1997-05-13013 May 1997 Forwards Endorsement 132 to Nelia Policy NF-0212 & Endorsement 118 to Maelu Policy MF-0075 for Smuds Rsngs ML20138F5321997-04-28028 April 1997 Forwards Response to RAI Re License Amend 192,updating Cask Drop Design Basis Analysis,Per NRC 960510 Request for Addl Info on 960318 Application NL-97-027, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-04-17017 April 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility ML20137W8091997-03-20020 March 1997 Forwards Biennial Update to Rancho Seco Post-Shutdown Decommissioning Activities Rept ML20137S3571997-03-19019 March 1997 Provides Notification of Use of Revised Quality Manual for Activities Re Rancho Seco ISFSI ML20137D0981997-03-18018 March 1997 Submits Rancho Seco Exposure Rept for Individuals Receiving Greater than 100 Mrem During 1996.Provided IAW TS D6.9.2.2 & Guidance Contained in NRC Reg Guide 1.16.No One Exposed to Greater than 100 Mrem in 1996 ML20137D1221997-03-18018 March 1997 Submits,Iaw 10CFR20.2206 & TS D6.9.2.1,1996 NRC Form 5 Individual Monitoring Repts for Personnel Requiring Radiation Exposure Monitoring Per 10CFR20.1502 During 1996. W/O Encl NL-97-012, Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3)1997-02-11011 February 1997 Submits Rept of Listed Current Levels of Property Insurance for Plant,Iaw 10CFR50.54(w)(3) ML20138L1091997-01-29029 January 1997 Informs of Schedule Change Re Decommissioning of Rancho Seco.Incremental Decommissioning Action Plan,Encl NL-97-005, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility1997-01-22022 January 1997 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Utility NL-96-056, Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util1996-12-16016 December 1996 Forwards Certified Copies of Listed Nuclear Liability Endorsements for Util ML20134E0041996-10-23023 October 1996 Forwards Response to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks ML18102B6871996-08-0606 August 1996 Informs That Util Will Revise Loading & Unloading Procedures & Operator Training as Necessary ML20149E4491994-05-16016 May 1994 Forwards 1993 Annual Rept of Sacramento Municipal Utility District,For Info ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List ML20059H6731994-01-20020 January 1994 Forwards Revised Rancho Seco Quality Manual, Reflecting Current Rancho Seco Pol Phase Nuclear Organization Changes ML20059E1221994-01-0303 January 1994 Forwards Amend 7 to Long Term Defueled Condition Physical Security Plan.Encl Withheld (Ref 10CFR73) ML20059C1681993-12-22022 December 1993 Forwards Suppl Info to Support Review & Approval of 930514 Proposed License Amend 186 Re Nuclear Organization Changes, Per NRC Request 1999-07-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L5431990-09-20020 September 1990 Requests Exemptions from Certain Requirements of 10CFR50.47(b) & 50,App E & Proposes New Emergency Plan That Specifically Applies to Long Term Defueled Condition ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 ML20059J9221990-09-13013 September 1990 Responds to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' No Vendor Interface Exists for Spent Fuel Pool Liner NL-90-442, Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-2121990-09-12012 September 1990 Forwards Endorsements 13 to Nelia Certificate N-49 & Maelu Certificate M-49,Endorsements 91 & 92 to Maelu Policy MF-75 & Endorsements 103 & 104 to Nelia Policy NF-212 ML20059G0791990-09-0606 September 1990 Forwards Supplemental Fitness for Duty Performance Data, Omitted from 900725 Rept Re Random Drug Testing Results ML20059E0031990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept,Jan- June 1990, Corrected Repts & Revs to ODCM ML20059C2491990-08-27027 August 1990 Advises That M Foster & B Rausch Leaving Util Effective on 900810 & 17,respectively & Will No Longer Require Active Operator Licenses ML20056B2591990-08-20020 August 1990 Forwards Long-Term Defueled Condition Security Training & Qualification Plan. Encl Withheld (Ref 10CFR2.790) ML20056B2961990-08-10010 August 1990 Discusses 900731 Meeting Re Future of Util & Closure & Decommissioning of Facility.Request for Possession Only License Pending Before Commission ML20058Q2811990-08-0909 August 1990 Forwards Updated Listing of Commitments & long-range Scope List Items Deferred or Closed by Commitment Mgt Review Group Since Last Update ML20058N0911990-08-0707 August 1990 Notifies of Minor Change in List of Tech Specs Applicable in Plant Defueled Condition.Determined That Surveillance Requirements Table 4.1-1,Item 63 Not Required to Be Included in List of Tech Specs Applicable in Defueled Condition ML20056A2041990-07-30030 July 1990 Provides Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. Pressure & Differential Pressure Transmitters 1153 & 1154 Do Not Perform Any safety-related Function in Current Plant Mode ML20056A1131990-07-30030 July 1990 Apprises of Status of Plans to Use 3 of 4 Emergency Diesel Generators as Peaking Power Supplies & Responds to Questions in .Util Obtained Authorization for Operation of Diesel Generators for No More than 90 Days Per Yr ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055H7561990-07-24024 July 1990 Requests Exemption from Performing Annual Exercise of Emergency Plan,Activation of Alert & Notification Sys & Distribution of Public Info Brochures,Per 10CFR50.12 Requirements ML20055H8081990-07-24024 July 1990 Forwards Decommissioning Financial Plan for Plant,Per 10CFR50.33(k)(2) & Requests Interim Exemption Re Requirement to Have Full Decommissioning Funding at Time of Termination of Operation,Per 10CFR50.12 ML20055F8421990-07-13013 July 1990 Forwards Application for Proposed Decommissioning of Plant. Util Needs Relief from Equipment Maint,Surveillance,Staffing & Other Requirements Not Necessary to Protect Public Health & Safety During Defueled Condition ML20055G9821990-07-12012 July 1990 Advises That Environ Exposure Controls Action Plan Will Be Provided by Sept 1990,per Insp Rept 50-312/90-02 ML20055E5111990-07-0606 July 1990 Notifies of Change in Operator/Senior Operator Status for D Rosenbaum & M Cooper,Effective 900622 & 29,respectively ML20055C3511990-02-14014 February 1990 Forwards Addl Info Re 900306 Response to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Util Will Replace Only Relays Found Not to Meet Insp Criteria ML20055C3541990-02-14014 February 1990 Forwards Updated Response to Insp Rept 50-312/88-30. Calculations for Liquid Effluent Monitors Completed & in Use & Rev to Reg Guide 4.15 in Procedure RSAP-1702 Scheduled to Be Completed & Implemented by Apr 1990 ML20248H2391989-10-0606 October 1989 Requests Exemption from Requirements of 10CFR26 Re Fitness for Duty Programs Based on Present & Future Operational Configuration ML20248H2571989-10-0606 October 1989 Responds to NRC Re Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54 Re Reactor Vessel Vent Valve Testing.No Testing of Reactor Vessel Vent Valves Will Be Performed ML20248A8271989-09-25025 September 1989 Requests Permission to Submit Next Amend to Updated FSAR W/Decommissioning Plan Submittal.Extension Will Allow District to Incorporate Plant Closure Status in SAR Update to Reflect Plant Conditions Accurately ML20248D4611989-09-13013 September 1989 Responds to 890906 Request for Assessment of Util Compliance W/Ol & Associated Programs & Commitments,Per 10CFR50.54(f). Staffing Requirements for Emergency Preparedness Will Not Be Violated & Future Shortfalls Will Be Remedied ML20247G1991989-09-11011 September 1989 Requests Extension for Time Period Equivalent to That of Current Shutdown.Extension Would Result in Revised Final Expiration Date of Not Earlier than 900318.Plant Would Not Be Brought Above Cold Shutdown W/O NRC Prior Concurrence ML20247H3551989-09-0707 September 1989 Informs That Util Stands by Commitments of 890621 & 0829 Re Implementation of Closure Plan in Safe & Deliberate Manner in Compliance W/License & W/All Applicable Laws & Regulations ML20247H5541989-09-0101 September 1989 Responds to Violations Noted in Insp Rept 50-312/89-14. Corrective Actions:Stop Order on Fuel Movement Issued & Action Plan Generated on 890908 to Address Broader Issues 05000312/LER-1988-010, Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys1989-08-23023 August 1989 Forwards Rev 1 to LER 88-010,due to Change in Commitment Date for re-evaluating Fire Zones.Date Changed to 901001. Zones re-evaluated in Conjunction W/Mods to Fire Detection Annunciator Sys ML20246A4011989-08-16016 August 1989 Forwards Rev 5 to Inservice Testing Program Plan. Changes Identified Consistent W/Guidance Provided by Generic Ltr 89-04 NL-89-593, Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request1989-08-15015 August 1989 Forwards Plant Closure Organizational Charts & Administrative Procedure RSAP-0101,per 890802 Request ML20245H4781989-08-10010 August 1989 Requests Exemption from Generic Ltr 89-07, Power Reactor Safeguards Contingency Planning for Surface Vehicle Bombs Because on 890607,util Board of Directors Ordered That Plant Cease Operation ML20245H1781989-08-0909 August 1989 Notifies of Change in Operator/Senior Operator Status. J Dailey & J Reynolds Terminated Employment on 890721 & 890802,respectively ML20245L1831989-08-0808 August 1989 Informs That Official Correspondence Must Be Directed to Listed Individuals Due to Reorganization of Util Following 890606 Election ML20247L9221989-07-26026 July 1989 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-312/88-33.Corrective Action:Portable Shield Walls Inspected Every 6 Months to Ensure All Safety Factors Met & Area Surveys Conducted on Weekly Basis ML20247M4121989-07-24024 July 1989 Requests Exemption from 10CFR50,App E,Section IV.F.2 to Allow Util Not to Perform Annual Emergency Plan Exercise for 1989.Request Results from Transitional Mode of Plant from Operating Plant to Plant Preparing for Decommissioning NL-89-541, Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 8912151989-07-14014 July 1989 Requests That Completion Date for Addl Training of Personnel Involved in Performing Work on Environ Qualified Equipment Be Extended from 890616 to 891215 ML20246P4011989-07-14014 July 1989 Informs That Evaluation of Contracts & Agreements Identified No Restrictions on Employee Ability to Provide Info About Potential Safety Issues to NRC NL-89-547, Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 1061989-07-0606 July 1989 Forwards Amend 110 to License DPR-54,issued on 890609, Identifying Discrepancy in Tech Spec Page X (Table of Contents) Which Does Not Reflect Changes Approved in Amend 106 ML20246A9751989-06-30030 June 1989 Advises That Concerns Addressed in Generic Ltr 89-08 Inapplicable,Since Util Intends to Defuel Reactor.Generic Ltr Will Be Reviewed Prior to Placing Facility in heatup-cooldown Operational Mode for Return to Power ML20246A5171989-06-30030 June 1989 Forwards Rancho Seco Closure Plan, Per 890621 Request for Addl Info Re Plan CEO-89-289, Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date1989-06-27027 June 1989 Notifies of Change in Operator/Senior Operator Status.Listed Operator/Senior Operator Terminated Employment on Listed Effective Date NL-89-526, Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl1989-06-22022 June 1989 Lists Discrepancies Noted in Amend 109 to License DPR-54,per 890615 Discussion W/S Reynolds.Tech Specs Encl ML20245H4181989-06-21021 June 1989 Discusses Util Plans Re Overall Closure of Plant,Per 890615 Meeting W/Nrc.Util Will Request Appropriate Changes to Tech Specs to Reflect Defueled Mode & Will Evaluate & Request Changes to Emergency Plan ML20245D9281989-06-21021 June 1989 Discusses Activities Underway Re Plan for Closure of Plant Discussed During 890615 Meeting W/Region V.Util Intends to Continue Use of Essential Programs,Such as Preventive Maint Program,For Sys within Scope of Closure Process ML20245A0981989-06-16016 June 1989 Responds to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs. No Westinghouse Plugs Used at Plant ML20248B5751989-06-0202 June 1989 Advises That Util Anticipates That Final Analysis of Thermal Striping Will Conservatively Support Surge Line Lifetime Significantly Longer than June 1994 Date,Per NRC Bulletin 88-011, Pressurizer Surge Line Thermal Stratification 1990-09-06
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SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, P.O. Box 15830, Sacramento, CA 95813; (016) 452-3211 RJR 85-521 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA October 31, 1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION UNIT NO 1 REGULATORY GUIDE 1.97 REQUEST FOR ADDITIONAL INFORMATION The District is enclosing in Attachment I, its response to the NRC's request for additional information concerning conformance to Reg. Guide 1.97. The NRC sent this request based on an interim report prepared by its contractor, INEL, who reviewed the District's various Reg. Guide 1.97 submittals. The District submitted these reports on September 14, 1983, July 13, 1984, September 14, 1984, and July 9,1985. The last two reports also contain implementation schedules. The District used its Living Schedule process to schedule the Reg. Guide 1.97 modifications.
To facilitate the review of the information in Attachment I, the District has included in Attachment II, revisions to its September 14, 1984 Reg.
Guide 1.97 report. Attachment II consists of replacement pages with revision change bars in the margin. Revisions include not only the District's revised positions, but also typographical and editorial changes. All scheduler revisions will follow the District's Living Schedule procedures.
If you have any questions, please contact Jerry Delezenski at Rancho Seco.
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R. J. RODRIGUEZ ASSISTANT GENERAL NAGER NUCLEAR Attachments (2) 000 I\sg 8511040281 851031 PDR ADOCK 05000312 F PDR
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8
'4 Attachment I RANCHO SECO CONFORMANCE TO REG GUIDE 1.97 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION
- 1. Neutron Flux Request:
" Neutron Flux - The licensee should identify the specific portion (s) of this instrumentation for which a deviation of Category 3 is being sought, justify these specific deviations and verify that the other portions are Category 1."
Response
The District has decided not to seek deviations from Category 1 requirements for any portions of the neutron flux instrumentation. Thus, the District will upgrade neutron flux instrument loops to Category 1 prior to Cycle 9 startup. The District Living Schedule will reflect this addition.
- 2. RCS Cold Leg Water Temperature Request:
"RCS cold leg water temperature--the licensee should provide justification for the deviation in the upper limit of the range."
Response
The District's RCS Cold Leg Water Temperature range of 500F to 6500F provides the capability to measure in excess of 15% of the saturation temperature for the steam generator. The saturation temperature is less than 5600F (based on 1102.5 psig, the highest main steam safety valve setting). An upper range of 6500F for the RCS Cold Leg Water Temperature instrumentation provides 16% margin over the saturation temperature. In addition, widening the range would reduce the sensitivity of the indication. Therefore the District maintains this range is adequate.
(This is consistent with the B&WOG Reg. Guide 1.97 task force's generic position. )
- 3. RHR (Decay Heat) Heat Exchanger Outlet Temperature Request:
"RHR heat exchanger outlet temperature--the licensee should upgrade this instrumentation to Category 2."
i Page 1 RG 1.97 J
7 e
Response
The District will upgrade this variable to Category 2. Temperature loops
-TE-26043 & TE-26044 will be : upgraded- for cycle 9 startup. The District's
-Living Schedule will reflect this addition.
- 4. Pressurizer Level Request:
" Pressurizer level--the licensee should supply additional a . sis to support the deviations from the recommended range."
Response
The District, in concert with the B&W Owners Group, is developing a generic response to this item. The District will submit its position to the NRC by January 6,1986.
- 5. Pressurizer Heater Status Pressurizer heater status--the licensee should provide the instrumentation recommended by Reg. Guide 1.97.
Response
The District, in concert with the B&W Owners Group, will develop a generic
- response to this item. A submittal is planned by January 6,1986.
- 6. 2'ench Tank Temperature Request:
" Quench tank temperature--the licensee should either show that instrumentation will remain on scale or provide 500F lower limit of range."
Response
The District will widen the indicated range during the cycle 8 refueling outage to include the lower limit of 500F. The District's living schedule will include this addition.
- 7. Containment Spray Flow Request:
" Containment spray flow - the licensee should identify the specific deviation from Category 2 instrumentation and either justify or correct the deviation."
Page 2 RG 1.97 o _ _ __s
Response
Reg. Guide 1.97. defines. the purpose of containment spray flow to be for monitoring operation of the containment cooling system.
At Rancho Seco, the Reactor. Building (RB) spray system consists of two separate spray trains of equal capacity, each including:
. RB spray pump
. Spray header
. Spray additive tank
. Spray additive eductor
. Isolation valves and the necessary piping
. Instrumentation and controls The safety features signal on'high RB pressure automatically initiates the RB Spray System operation. Hence, for. this mode of operation, RB pressure is the primary variable to indicate cooling system operation.
Therefore, RB spray flow indication is a backup variable. At Rancho Seco RB pressure is a' Reg. Guide 1.97_ Category 1 variable.
- All RB spray piping is Rancho Seco QA Class 1 and seismic category 1.
All- piping inside the RB is designed to ANSI B31.1. All remaining piping and connections to the spray system are in accordance with ANSI B31.7. The controls for the pumps and all valves which are not locked open are Class 1 with indication in the main Control Room. The District has performed single failure analysis on all active components of the RB spray' system to show that the failure of any single active component will not prevent the fulfilling of the design function following a LOCA. Each train of the RB spray system also includes a.
unqualified flow' transmitter which provides indication in the Control Room.
The primary indication of the adequacy of the containment cooling
- systems are building pressure and temperature. At Rancho Seco RB pressure is Category 1 and RB temperature will be upgraded to Category
- 2. The Class 1 pump and valve control monitors indicate RB spray
! system actuation. In conclusion, the District maintains that
! indication of RB spray flN is a backup variable and therefore should be Category 3.
- 8. Containment Atmosphere Temperature Request:
(; " Containment Atmosphere Temperature - the licensee should upgrade this l instrument to Category 2."
Response
The District will upgrade temperature loops TE-52010 & TE-52015 to Category 2 prior to Cycle 9 Startup. The District's Living Schedule will reflect this addition.
Page 3 RG 1.97 D
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- 9. Containment Sump Water Temperature ;
Request:
" Containment ' sump water temperature--the licensee should provide category 2-instrumentation with the recommended range or identify alternate instrumentation."
Response
According to Reg. Guide 1.97 Revision 3, the purpose for Containment Sump Water Temperature is to monitor operation of the Containment Cooling Systems.
At Rancho Seco Containment Sump Water Temperature would only be useful following a high energy line break in containment. While containment sump water temperature trends may be indicative of leaking high energy fluid and containment cooling it would be slower & less effective than other available indications. Reactor Building pressure and temperature provide more direct indication. Currently, Rancho Seco does not indicate or record Reactor Building sump water temperature because it is not required to mitigate the consequences of a design basis accident on a B&W designed plant. The operator is not required to take action based on this variable. However, indication of- the Decay Heat / Reactor Building Spray flow suction lines temperaturs is available with a range of 0-3000F.
Reactor Building spray flow provides additional information concerning core cooling. Back up variables are Reactor Building fan breaker status and the flow rate of cooling water to the cooling units. The
' District believes this instrumentation is sufficient for monitoring the operation of the containment cooling systems. (This is consistent with the B&WOG Reg. Guide 1.97 task force's generic position.)
- 10. Component Cooling Water Temperature to ESF System Request:
" Component cooling water temperature to ESF system--the licensee should provide Category 2 instrumentation for the NSCW temperature, and further justification for the deviation to Category 3 instrumentation for the NSRW temperature (Section 3.3.24)."
Response
The District will provide Category 2 instrumentation for Nuclear Service Cooling Water ~ (NSCW) temperature by upgrading TI-48003 and TI-48004 during the cycle 9 refueling outage. The District's Living Schedule will reflect this addition.
Page 4 RG 1.97 J
4 Heat from the NSCW is transferred to the Nuclear Service Raw Water
. . (NSRW) system in the heat exchangers. From there it is transferred to the Rancho Seco ultimate heat sink (atmosphere) via spray ponds which form a part of the NSRW. Design outlet temperature from the NSRW spray ponds is 950F. That is, components which are directly cooled by the NSRW are designed to accept inlet temperatures as high as 950F and function normally. In a standby mode with no flow in the NSRW, and consequently no pond spray, the bulk spray pond temperature will be approximately the median of the. daily maximum and minimum dry-bulb temperatures. For the hottest month of record ( August 1958), the
, ' estimated maximum. initial pond temperature would be 86.50F (see Rancho
- Seco U.S. A.R. Section 9.4, page 20). After the operators start NSRW L flow (and pond spray), the pond temperature will approach the wet-bulb
- -temperature. Figure 9.4-9 of the Rancho Seco U.S. A.R. shows that for i
the hottest month of record ( August 1958), the average wet-bulb
' temperature never exceeded 790F.
L
, Since the spray ponds provide an assured source of sufficiently low i temperature coolant, temperature of the NSRW system is not a vital feetack indication of system operation. Thus, the NSRW cooling water temperature indications meet the District's understanding of the provisions of Reg. Guide 1.97 as a Category 3 parameter.
[ 11. Category 1 Indicators:
i Request:
" Category 1 indicators--the licensee should provide additional
! information on the CRT displays."
b L Response:
l
References:
1 SMUD letter, R. J. Rodriguez to J. F. Stolz, dated i L September 14,1984, NUREG 0737 Supplement 1 -
l Regulatory Guide 1.97,-Revision 1,Section II
! Instrument System Description 2 SMUD letter, R. J. Rodriguez to J. F. Stolz dated July .
28, 1983, SPDS Safety Analysis and Implementation Plan,Section III.C.2 and III.D
- Why can't dedicated recorders be used?
Reference 1 provided the following reason for using the SPDS instead of recorders: "This approach is necessary due to space limitations in the
,~
control room and provides the opportunity to incorporate favorable human factors into the presentation." A copy of this section is duplicated.in Appendix 1 for your review.
- Address the readability of the variables displayed (human factors) l
. Proper human factors criteria as determined by the CRDR process will L apply to the display of all Category 1 variables. The District will l
modified SPDS in accordance with the Living Schedule.
I Page 5
, RG 1.97 i
~* Are the displays redundant?
Reference 2 provided the.following information:
"a. For: improved reliability and readability, two identical channels of display are provided. Each display can monitor either the A or B loops of the plant.
- b. All parameters and graphics are displayed on two' (2) color video monitors. The size of the video monitors is nineteen (19) inches."
The District has seismically qualified all equipment except for the CRT's and control panel cabling. Although the system is partially redundant, power is not Class 1.
The District will-modify SPDS to provide:
- Full redundancy (2 channels)- y Class 1 Power
- Necessary seismic qualification
. . Indication of all Category 1 variables The District believes that use of the SPDS for the display of RG 1.97
' Category 1 variables, will result in improved human factors and an y- integrated approach to post accident monitoring and recovery at Rancho.
Seco.
- Are the displays dedicated to the real-time display of Category 1 variables?
In Reference 2, Section 5.0 the SPDS Functional Description. states:
"All Category 1 variables will be implemented on the post-trip ATOG display of the SPDS" either in real time or alerts. All category 1 variables'will also be available on the first page of the alphanumeric displ Ay as -described below. .
Also Section 2.0 states. "When a reactor trip occurs, the display i
shall switch to the post-trip "ATOG" display with history trace
- initialized. "
This does not disable the system's "... flexibility of displays that
- allows ~ the operator to select the most appropriate display for the L
,5 existing plant condition." Therefore, trending is " continuously available" on reactor' trip or operator request. ,
i How many displays are there?
The primary RG 1.97 Category 1 display is the post-trip AT0G display.
The first page of the alphanumeric display will also list all category 1 variables including the average of the 5 highest incore temperatures and an alert for isolation valves. Individual incore temperatures will
~ be available on the Core Map display and individual isolation valve
! positions will be available on addition alphanumeric displays. The R.G.1.97 displays use primarily category 1 variables. The remaining
[ SPDS displays also use the category 1 variables.
Page 6 RG 1.97 s
- How many variables are displayed per display?
The displays are still under development. The District anticipates that the primary RG 1.97 displays will be as follows:
POST-TRIP ATOG DISPLAY Graph:
T-Cold, T-Hotl 'or T-Incorel vs. RPS Pressurel Secondary Sys;;em. Saturation Temperature Percent Poweg
- Percent F1ow' Steam Generator Levell (operate and startup)
Alerts:
Containment Sump Level l Steam Generator Prespurel Reactor Vessel Level' Containment Isolation Valypsl Containment Area Radiation' Containment H2 Concentrationi Pressurizer Levell Auxiliary Feedwater Flowl
! Condensate Storage Tank Levell j ALPHANIMERIC DISPLAY Alpha Numeric Page 1 will include:
i-T-Hotl T-Incore (avprage of 5 highest)l' RPS Pressure' Steam Generator Levell Containment Sump Level l Steam Generator Prespurel Reactor Vessel Level' Containment Isolation Valyys (alert)I Containment Area Radiation Containment H2 Concentrationl Pressurizer Level' Auxiliary Feedwater Flowl Condensate Storage Tank Levell 1.
I l
(I RG 1.97 ' Category 1 variable)
Page 7 RG 1.97
l A
Appendix 1 Section II. Instrument Systems Description from SMUD letter, R. J. Rodriguez to J. F. Stolz, dated September 14, 1984, NUREG 0737 Supplement 1 -- Regulatory Guide 1.97, Revision 1 i
RG 1.97
-II. INSTRlMENT SYSTEMS DESCRIPTION In addition to existing hardvired indicators and recorders, the District will utilize computer driven displays and other means to present Reg. Guide 1.97. variables to the operator. This approach is necessary due to space limitations in the control room and provides the opportunity to incorporate favorable human factors into the presentation. The location and exact content of these displays will be developed as a part of the CRDR process.
The computer systems of interest to Reg. Guide 1.97 are the Safety Parameter Display System (SPDS), Interin Data Acquisition and Display System (IDADS), and Digital Radiation Monitoring System (DRMS). The SPDS, a seismically qualified 1 variables. IDADS will be used to provide diverse displays (e.g., to resolve ambiguities),
while DRMS provides the operator access to data from a number of the radiation monitors installed as required by NUREG 0737.
Following is a description of each of these systems.
' A. SPDS The District contracted with Babcock and Wilcox (B&W) to design and deliver an SPDS to meet the appropriate requirement of NUREG 0696, Reg. Guide 1.97, NUREG 0737, and Supplement 1 to NUREG 0737. The SPDS was designed as a diagnostic tool compatible with the Abnormal Transient Operating Guidelines (AT0G) and -the Emergency Operating Procedures (EOP's). The SPDS has been designed, constructed, vendor tested, and installed. The - SPDS is currently in a test phase for operator familiari7ation and evaluation. Testing, modification (as required), Et v revision, and training will be complete prior to Cycle 7 start-up. The.
SPDS will then be operational .
Future enhancements will be made to the SPDS in accordance with the District's Living Schedule. These enhancements include:
- Continuing human factors engineering during the test phase. As part of the test phase, the control room -
operators will evaluate the SPDS and suggest near-term L improvements and/or enhancements to the system.
- Seismic qualification and dual-channel redundancy will be completed to provide the display functions for Reg.
Guide 1.97, Category 1 variables.
- The SPDS will be verified and validated according to the District's V8V plan.
t i
Page 9 RG 1.97 J
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B. IDADS' The main purpose of IDADS is to provide CRT displays for the Emergency Response Facilities (ERF) as required by NUREG 0696, and Supplement 1 to NUREG 0737. As a secondary objective, IDADS will provide enhanced operator functions not currently available in the Control Room.
IDADS consists of a central computer system located in the Computer-Room. It has various types of input multiplexing equipment, display terminals and hardcopy equipment in the Control Room, TSC, and EOF, and display equipment at the assembly points. Plant inputs enter the system from the following sources: the Bailey Multiplexer, the MODCOMP .
Multiplexer, and the Anatec Remote Multiplexer (REMUX) System.
The following general features are to be provided:
A. Data Acquisition B. Man-Machine Interface C. Alarm Annunication D. Radioactive Release Monitoring E. Reactivity Calculations F. On-line Trending G.-- . Data Link to EOF Future enhancements will be made to the IDADS in accordance with the District's Living Schedule. These enhancements include:
- A data link with the GA Technologies' DRMS Computer so that radiation data will be available on IDADS
- A long term history storage and retrieval option for later interrogation of data.
- Alphanumeric group trending.
- Calculated values using predefined equations which can be alarmed or trended.
C. ~DRMS The District contracted with GA Technologies (GA) to design and deliver a Digital Radiation Monitoring System (DRMS) to meet the appropriate requirements of-NUREG 0737. The DRMS provides on-line information concerning radiation levels of selected radioisotopic concentrations within the plant processes and dose rate information for various areas within the plant facility.
Process measurements provide . diagnostic or status information for a particular portion of the p1 ant operation, and monitor releases of radioactive material from the plant environment.
Page 10 RG 1.97
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~
N DRMS consists of subsystem elements including:
- R'4-ll central control and display system
- Gaseous process monitors
- Liquid process monitors
- Wide range gas monitor (WRGM) control cabinet
- Strip chart recorders RM-23 portable control and display. units
. High range in containment area monitor '
Main steam line radiation monitors l
The RM-11 computer communicates with all the monitors using three loops of redundant communications lines. Communications between each monitor and the RM-23' module are accomplished over a single dedicated line separate from the RM-ll' loops.
The DRMS design incorporates the following features:
Distributed data processing Expansion capability
- Centralization of control and display
- Redundancy and reliability Independence of safety related monitors Trending 4
4 3
Page 11 RG 1.97
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