Letter Sequence Other |
---|
|
Results
Other: ML20147C490, ML20149E859, ML20151B320, ML20155D675, ML20197B030, ML20199B161, ML20204F596, ML20210R060, ML20211B406, ML20211B442, ML20212H574, ML20212H582, ML20214E205, ML20214L960, ML20215H383, ML20215H397, ML20234F422, ML20235R405, ML20235R426, ML20236D305, ML20236D319, ML20236P920, ML20245E060, ML20245E067
|
MONTHYEARML20211B4421985-12-31031 December 1985 Annual Radiological Environ Operating Rept for 1985 Project stage: Other ML20155D6751985-12-31031 December 1985 Annual Nonradiological Environ Monitoring Rept,1985 Project stage: Other ML20210R0601986-02-24024 February 1986 Staff Assessment of Environ Radioactive Contamination in Vicinity of Rancho Seco Nuclear Power Plant Project stage: Other ML20214E2051986-03-0303 March 1986 Forwards Semiannual Radioactive Effluent Release Rept,Jul- Dec 1985. Changes to Offsite Dose Calculation Manual, Process Control Program & Rept Corrections Included. Operational & environmentally-related Events Discussed Project stage: Other ML20214L9801986-04-0101 April 1986 Summary of 860325 Meeting W/Epa Re Offsite Contamination Problems & Requirements of 40CFR190 Project stage: Meeting ML20197B0301986-04-30030 April 1986 Informs That Util Will Submit Completed 1985 Annual Radiological Environ Operating Rept by 860530.Delay Due to Difficulties in Completing Liquid Effluent Pathway Land Use Census Project stage: Other ML20211B4061986-05-27027 May 1986 Forwards 1985 Annual Radiological Environ Operating Rept, Including Parts I & II of Environ Radiological Studies Downstream from Rancho Seco Nuclear Power Generating Station - 1985 Project stage: Other ML20199B1611986-06-0505 June 1986 Special Rept 86-08 Re Max Hypothetically Exposed Individual Surpassing Numerical Guides for Design Objectives of 10CFR50,App I.More Appropriate Modeling Techniques Encl. Offsite Dose Calculation Manual Revised Project stage: Other ML20204F5961986-07-0303 July 1986 Responds to NRC Re Violation Noted in Insp Rept 50-312/86-15.Corrective Actions:Util Will Submit Amend to Tech Spec Table 4.21-1 Re Radioactive Liquid Waste Sampling Prior to Startup Project stage: Other ML20212G1351986-07-22022 July 1986 Advises That Changes to Radiological Effluent Tech Specs Should Be Proposed to Eliminate Possibility of Unacceptable Radiation Levels in Liquid Effluents.Evaluation of 860224 Rept Encl.Meeting Requested Project stage: Meeting ML20214L9601986-08-29029 August 1986 Forwards Documentation Summarizing NRC Actions to Close Out Offsite Contamination Issue,In Response to 860325 Request Project stage: Other ML20055C2251986-09-30030 September 1986 Responds to NRC 860718 Request for Addl Info Re Plant Liquid Effluents.Requested Info Will Be Provided by End of Nov 1986 Due to Magnitude of Effort Required Project stage: Request ML20245E0671986-12-0202 December 1986 Forwards Util Response to 860718 Inquiry Into Operations & Mgt of Plant Liquid Effluent Program.Util Considers That Discharge of Radioactive Matl in Liquid Effluents Allowable by Tech Specs within Limits of 10CFR20,App B Project stage: Other ML20245E0601987-01-0505 January 1987 Forwards Revs to Util 861202 Response to NRC Liquid Effluent Inquiry for Clarification,Per 861222 Discussion W/R Meeks Project stage: Other ML20212H5821987-01-12012 January 1987 Radiological Effluent Release & Radiological Environ Operating Repts for 1984,Rancho Seco Nuclear Generating Station, Technical Evaluation Rept Project stage: Other ML20212H5741987-01-16016 January 1987 Forwards TER-C5506-657, Radiological Effluent Release & Radiological Environ Monitoring Operating Repts for 1984, Rancho Seco Nuclear Generating Station, Technical Evaluation Rept Project stage: Other ML20245E0631987-02-19019 February 1987 Forwards Response to NRC 861224 Request for Addl Info Re Inquiry Into Operations & Mgt of Plant Liquid Effluent Program.Response Completes Util Efforts to Provide Requested Info Project stage: Request ML20205S8181987-02-25025 February 1987 Notification of 870303 Meeting W/Util in Bethesda,Md to Review Discrepancies in Plant Liquid Effluent Program & to Discuss Changes to Tech Specs & Offsite Dose Calculation Manual to Correct Identified Discrepancies Project stage: Meeting ML20197D4831987-04-0707 April 1987 Summary of 870303 Meeting W/Util in Bethesda,Md Re Problems Identified W/Facility Liquid Effluent Program & Proposed Corrective Actions.Attendance List Encl Project stage: Meeting ML20215H3831987-04-15015 April 1987 Forwards Rev 1 to Procedure R-0775, Facility Change Safety Analysis. Design Bases of Current Mod to Secondary Waste Water Sys Not Intended to Be Equivalent to Evaporation Ponds Described in Submittal Project stage: Other ML20215H3971987-04-15015 April 1987 Rev 1 to Procedure R-0775, Facility Change Safety Analysis Project stage: Other ML20209C7401987-04-20020 April 1987 Confirms Commitments Made During 870303 Meeting W/Nrc in Bethesda,Md Re Radiological Liquid Effluent Matters.Dose Based Surveillance Std Appropriate for Ensuring Compliance w/10CFR50,App I Regulation.List of Commitments Encl Project stage: Meeting ML20235F7541987-06-30030 June 1987 Application for Amend to License DPR-54,consisting of Amend 155,revising Tech Specs Re Radiological Effluents to Ensure Compliance W/Regulatory Requirements Concerning Effluent Monitoring & Nearby Land Use Identification.Fee Paid Project stage: Request ML20235R4261987-10-0303 October 1987 Proposed Radiological Effluent Tech Specs,Incorporating Clarifications & Correcting Editorial Errors Project stage: Other ML20235R4051987-10-0303 October 1987 Rev 1 to Proposed Amend 155,revising Radiological Effluent Tech Specs to Incorporate Clarifications & Correct Editorial Errors Project stage: Other ML20236D3191987-10-0707 October 1987 Rev 0 to Radiological Environ Monitoring Program Manual Project stage: Other ML20236D3051987-10-20020 October 1987 Forwards Rev 0 to Radiological Environ Monitoring Program Manual, for Review in Support Evaluation of Proposed Amend 155 to License DPR-54 Project stage: Other ML20236P9201987-11-12012 November 1987 Forwards Radioactive Liquid Effluent Sys Description Including P&Id,Design Criteria,Instrumentation & Control Measures to Support Evaluation of Proposed Amend 155 Project stage: Other ML20149E8591987-12-22022 December 1987 Proposed Tech Specs,Establishing New Set Lower Limits of Detection for Prebatch Release & Composite post-release Analyses Project stage: Other ML20149E8521987-12-23023 December 1987 Supplemental Application for Amend to License DPR-54, Consisting of Rev 2 to Proposed Amend 155,establishing New Set of Lower Limits of Detection for Prebatch Release & Composite post-release Analyses Project stage: Supplement ML20234F4221987-12-27027 December 1987 Forwards Rev 5 to AP.310, Offsite Dose Calculation Manual, for Review to Support Evaluation of Proposed Amend 155, Rev 2.Rev Incorporates Results of Verification & Validation as Well as NRC & Internal Reviews Project stage: Other ML20147C4901988-01-0505 January 1988 Forwards Fr Notice of Consideration of Issuance of Amend to License DPR-54 & Proposed NSHC & Opportunity for Hearing on 870630 Request Re Revs to Radiological Effluent Tech Specs Project stage: Other ML20149E2561988-01-0707 January 1988 Forwards Supplemental Info to Radioactive Liquid Effluent Sys Description Provided Via Ltr Gca 87-763 Dtd 871112,to Support Evaluation of Rev 2 to Proposed Amend 155.Concerns Raised Re Radioactive Liquid Effluent Sys Listed Project stage: Supplement ML20148J8111988-03-17017 March 1988 Forwards Amend 98 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs,Reducing Lower Limits of Detection for Liquid Radioactive Effluents & Changing Requirements to Address Hardware Changes in Effluent Sys Project stage: Approval ML20151B3201988-03-30030 March 1988 Forwards Errata to Amends 97 & 98 to License DPR-54, Correcting Inadvertent Errors in Tech Specs Project stage: Other 1987-10-20
[Table View] |
|
---|
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 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 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 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 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) 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 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 IR 05000312/19980021998-07-15015 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 ML20217G6661998-03-18018 March 1998 Forwards Discharge Self Monitoring Rept for Feb 1998, Which Makes Note of One Wastewater Discharge Permit Violation 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 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 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 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 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 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 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 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 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) 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 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 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 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 ML20029E4601994-05-12012 May 1994 Forwards Response to NRC Bulletin 94-001, Potential Fuel Pool Drain-Down Caused by Inadequate Maint Practices at Dresden Unit 1. Util Plans to Move Spent Fuel Into Proposed Rancho Seco ISFSI by 1998 ML20149E3971994-05-10010 May 1994 Forwards Re Updated Decommissioning Cost Estimate for Rancho Seco & Attached Rept by Tlg Engineering,Inc. W/Svc List NL-94-008, Forwards Endorsement 118 to Nelia Policy NF-0212 & Endorsement 106 to Maelu Policy MF-00751994-04-28028 April 1994 Forwards Endorsement 118 to Nelia Policy NF-0212 & Endorsement 106 to Maelu Policy MF-0075 ML20029D3531994-04-28028 April 1994 Forwards Documents S11-25-003, Update of 1991 Decommissioning for Rancho Seco Nuclear Generating Station 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 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 ML20059J9161990-09-13013 September 1990 Notification of Change in Operator/Senior Operator Status for R Groehler,Effective 900907 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 ML20055J0331990-07-25025 July 1990 Notifies of Change in Operator/Senior Operator Status. Operators Terminating Employment & No Longer Require License ML20055J0311990-07-25025 July 1990 Forwards fitness-for-duty Performance Data for Facility from 900103-0630 ML20055H8081990-07-24024 July 1990 Forwards Decommissioning Financial Plan for Plant,Per 10CFR50.33(k)(2) & Requests Interim Exemption Re Requirement to Have Full Decommissioning Funding at Time of Termination of Operation,Per 10CFR50.12 ML20055H7561990-07-24024 July 1990 Requests Exemption from Performing Annual Exercise of Emergency Plan,Activation of Alert & Notification Sys & Distribution of Public Info Brochures,Per 10CFR50.12 Requirements ML20055F8421990-07-13013 July 1990 Forwards Application for Proposed Decommissioning of Plant. Util Needs Relief from Equipment Maint,Surveillance,Staffing & Other Requirements Not Necessary to Protect Public Health & Safety During Defueled Condition ML20055G9821990-07-12012 July 1990 Advises That Environ Exposure Controls Action Plan Will Be Provided by Sept 1990,per Insp Rept 50-312/90-02 ML20055E5111990-07-0606 July 1990 Notifies of Change in Operator/Senior Operator Status for D Rosenbaum & M Cooper,Effective 900622 & 29,respectively ML20043G5701990-06-12012 June 1990 Forwards NSHC for long-term Defueled Condition of Plant for Security Plan,Per Util .As Discussed W/Nrc During Telcon,Determination Made That NSHC Needed to Be Processed in Support of Security Plan ML20043G9521990-06-12012 June 1990 Notifies of Organizational Changes.Svc List Should Be Revised as Listed ML20043E8191990-06-0606 June 1990 Requests Withdrawal of 900510 Request for Exemption from GDC 17, Electric Power Sys. Util Understands That Formal Exemption Not Required,Based on Discussions W/Nrc.Info on Plans Re Diesel Generator Operation Also Provided ML20043E1691990-05-25025 May 1990 Forwards Refinement List of Tech Specs Applicable in Defueled Condition,Per .Unless NRC Differs W/ Approach,Conduct of Activities in Defueled Condition Will Proceed Until Amend 182,Rev 1 Approved 05000312/LER-1990-001, Forwards Errata to LER 90-001-00,re Inoperable Radioactive Gaseous Effluent Monitoring Instrumentation Not Reported in Semiannual Radioactive Effluent Release Rept Due to Procedural Deficiencies,To Include Rept Date1990-05-0202 May 1990 Forwards Errata to LER 90-001-00,re Inoperable Radioactive Gaseous Effluent Monitoring Instrumentation Not Reported in Semiannual Radioactive Effluent Release Rept Due to Procedural Deficiencies,To Include Rept Date ML20042F3421990-04-26026 April 1990 Forwards Long Term Defueled Condition Security Plan.Plan Withheld (Ref 10CFR2.790) ML20042F6121990-04-26026 April 1990 Forwards Rancho Seco Emergency Plan Change 4 Long-Term Defueled Condition. New Plan Includes Provisions Necessary for Protection of Onsite Personnel & for Protection of Public Via Communication W/Offsite Agencies ML20034C4081990-04-24024 April 1990 Forwards Rev 5 to Sections 1 & 8 of Plant Emergency Plan,Per NRC Requesting Two Changes NL-90-143, Responds to Generic Ltr 89-13 Re Svc Water Problems Affecting safety-related Equipment.Routine Sys Walkdowns Performed by Operations Personnel to Ensure Sys Parameters within Required Range1990-04-17017 April 1990 Responds to Generic Ltr 89-13 Re Svc Water Problems Affecting safety-related Equipment.Routine Sys Walkdowns Performed by Operations Personnel to Ensure Sys Parameters within Required Range ML20034B6701990-04-13013 April 1990 Forwards Quarterly Update of Emergency Response Telephone Directory.Directory Withheld ML20042E0941990-04-10010 April 1990 Advises That Util Intends to Submit EIS Associated W/Plant Decommissioning After Submittal of Decommissioning Plan ML20033G5981990-03-30030 March 1990 Forwards Mods to Plant Operator Training Program Submitted on 891228,in Response to Requesting Addl Info ML20012D7711990-03-28028 March 1990 Responds to NRC 900205 Comments on Util Discussing Tech Specs Applicable to Defueled Condition.Util Intends to Keep Area Radiation Monitor R15028 Functional at All Times.Spent Fuel Pool Bulk Temp Maintained at 80 F ML20012E2211990-03-23023 March 1990 Forwards Amend 18 to Physical Security Plan.Encl Withheld (Ref 10CFR73.21) ML20012B8731990-03-0909 March 1990 Provides Status of Inservice Insp & Inservice Testing Programs.Util Does Not Intend to Continue Normal Test Schedule for Pumps & Valves in Sys Not Required by Tech Specs to Be Operable NL-90-030, Forwards Endorsements 94,95 & 96 to Nelia Policy NF-212, Endorsements 82,83 & 84 to Maelu Policy MF-75,Endorsements 10 & 11 to Nelia Certificate N-49 & Maelu Certificate M-49, Respectively & Endorsements 5,6,14 & 15 to Master Policy 11990-02-21021 February 1990 Forwards Endorsements 94,95 & 96 to Nelia Policy NF-212, Endorsements 82,83 & 84 to Maelu Policy MF-75,Endorsements 10 & 11 to Nelia Certificate N-49 & Maelu Certificate M-49, Respectively & Endorsements 5,6,14 & 15 to Master Policy 1 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 ML20033F1661990-02-14014 February 1990 Forwards Revised Pages to Sections 1-8 of Rev 4 to Emergency Plan,Per NRC 900206 Telcon Request.Summary of Changes Listed,Including Deletion of Ref to Accidents Not Exceeding Alert Classification 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 ML20006F1451990-02-13013 February 1990 Revises 891212 Exemption Request Re Requirements for Simulation Facility Training & Testing.Requested Exemptions Commensurate W/Nuclear Safety Requirements W/Plant in Defueled Condition ML20033E3471990-02-12012 February 1990 Advises of Change in Operator/Senior Operator Status for H Coomes,Effective 900205 ML20006D6771990-02-0808 February 1990 Requests Limited Scope Exemption from Requirements of 10CFR26 Fitness for Duty Programs.Util Currently Implementing Program in Accordance W/Enforcement Discretion Granted in Commission NL-90-023, Forwards Endorsements 95 & 83 to Nelia Policy NF-212 & Maelu Policy MF-75,respectively,Endorsements 10 & 11 to Certificates N-49 & M-49 & Endorsements 5,6,14 & 15 to Maelu Policy 11990-02-0707 February 1990 Forwards Endorsements 95 & 83 to Nelia Policy NF-212 & Maelu Policy MF-75,respectively,Endorsements 10 & 11 to Certificates N-49 & M-49 & Endorsements 5,6,14 & 15 to Maelu Policy 1 ML20006D0201990-02-0202 February 1990 Requests Exemption from Simulator Training & Testing Requirements of 10CFR55.11 While Plant in Defueled Mode.In Present Defueled Condition,Use of Simulator to Ensure Skills & Abilities Re Plant Operations Irrelevant ML20011E1711990-01-30030 January 1990 Forwards Rev 0 to NDP-039, Sys Required to Support Defueled Mode, & Rev 1 to TSAP-4124, Sys Layup Program. Sys Categories at Facility Include,Operable,Available,Prudent to Operate & Layup ML19354E4441990-01-22022 January 1990 Advises That Actions Requested by NRC Bulletin 89-003 Not Applicable to Station Since Station Currently in Defueled Shutdown Condition.Util Took Action to Disallow Temporary Storage of Fuel Assemblies W/O Approval of Reactor Engineer ML20005G2571990-01-12012 January 1990 Responds to NRC Re Violations Noted in Insp Rept 50-312/89-18.Violation a Denied & Violation B Ack.Corrective Actions:Controls for Environ Pollution Reanalyzed I-131 in Water Sample Using Correct Efficiency Factor for Instrument ML20005F1791990-01-0808 January 1990 Responds to NRC Re Violations Noted in Insp Rept 50-312/89-15.Util Denies Alleged Violations on Basis That Removing Auxiliary Fuel Handling Bldg to Facilitate Testing Performed Considered Consistent W/Plant Work Practices ML20005F0351990-01-0303 January 1990 Certifies Implementation of fitness-for-duty Rule,Per 10CFR26 ML20005E4121989-12-27027 December 1989 Suppls NRC Summary of Util Plans to Close & Decommission Facility & Identifies Subjs Needing Further Discussion.Four Phases Listed,Including First Phase Re Relief from Existing Commitments 1990-09-06
[Table view] |
Text
.
c esuu.
SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.O. Box 15830. Sacramento CA 95852-!830.(916)452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-169
- gW 1* T July 3, 1986
'S v,
J B MARTIN REGIONAL ADMINISTRATOR
%,)
f,
{
REGION V 0FFICE OF INSPECTION AND ENFORCEMENT c-U S NUCLEAR REGULATORY COMMISSION S
1450 MARIA LANE SUITE 210 WALNUT CREEK CA 94596 DOCKET N0. 50-312 LICENSE N0. DPR-54 NRC INSPECTION REPORT 86-15 The Sacramento Municipal Utility District has thoroughly reviewed and has com-pleted or is in the process of correcting all items of concern stated in your letter dated June 6, 1986.
l l
In response to your audit conducted April 1, 2, 29 and May 15, 1986, and the Enforcement Conference of June 20, 1986, the District voluntarily submits the following clarification and corrective actions to address your concerns:
Apparent Violation, 86-15-01:
(Summary reprinted in part from NRC Inspection Report 86-15)
"As of April 1, 1986, since the Radiation Protection Superintendent apparently believed that the LLD values presented in T.S. Table 4.21-1 were adequate to meet Appendix I, no other appropriate monitoring pro-gram had been established to provide data on quantities of radioactive material released in liquid effluents to assure the dose criteria of Appendix I were met.
Failure to establish appropriate surveillance and monitoring procedures represents an apparent violation of 10 CFR 50, Appendix I."
DISTRICT RESPONSE:
Procedure AP 306 V-13, Lower Limit of Detection Count Time Determination, has been revised to specify a minimum count time of 2000 seconds for RHUT liquid effluent releases.
This has been shown to be sufficient to detect Cs-137 at a concentration that is consistent with T.S. Table 3.22-2, Reporting Levels for Radioactivity Concentrations in Environmental Samples.
Procedure AP.305-13, Environmental Releases of Liquid Radioactivity, is currently being revised to provide better documentation on quantities of radioactive material released in liquid effluent.
The proposed changes include:
- sampling and analysis of every RHUT volume transfer
- composite of all regenerant holdup tank (RHUT) volumes transferred to the retention basins
- placing a complete set of documentation for each RHUT release to the retention basin in a folder for routing and signature approval 8608040243 860703 gDR ADOCK 0500 2
gf RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935
4 J B MARTIN retaining a copy of the complete set of documcatation while the origi-nal is being routed for signature
- specifying sampling and analysis of batch volumes of liquid transferred to the RHUT.
The District will submit an amendment to T.S. prior to startup which will in-clude a change to T.S. Table 4.21-1, Radioactive Liquid Waste Sampling and Analysis Program, lowering the Cs-137 LLD for radioactive liquid waste to the value specified in T.S. Table 3.22-2.
These LLD values are the reporting levels for radioactivity concentrations in environmental water samples.
Apparent Violation, 86-15-03:
(Summary reprinted in part from NRC Inspection Report 86-15)
" Failure to report positive results for Cs-137 activity which was identified and measured on June 4, 6 and 17, 1985, in liquid effluent releases 85-98, 85-99 and 85-110 in the Semiannual Radioactive Effluent Release Report dated September 26, 1985, is considered an apparent viola-tion of. T.S. 4.21."
DISTRICT RESPONSE: Procedure AP.305-13, Environmental Releases of Liquid Radio-activity, is being revised and AP.306 V-13, Lower Limit of Detection Count Time Determination, has been revised to better identify and report quantities of radioactive material in liquid effluent discharged to the environment. Please see the response to item 86-15-01 for additional actions.
The District submittal, Special Report 86-08 dated June 5, 1986 (JEW 86-087),
provides a best estimate of the quantity of radioactive material in liquid effluent discharged to the environment during 1985.
This information will be included in the next Semiannual Radioactive Effluent Release Report as a revision to the 1985 reports.
The District will submit an amendment to T.S. prior to startup which will include a change to T.S. Table 4.21-1, Radioactive Liquid Waste Sampling and Analysis Program, lowering the Cs-137 LLD to the value specified in T.S.
Tabic 3.22-2, Reporting Levels for Radioactivity Concentrations in Environ-mental Samples.
The District will review its y detection equipment to allow for the necessary y analysis to be done onsite.
Apparent Violation, 86-15-05:
(Summarized from NRC Inspection Report 86-15)
"The estimated quantity of radioactive material in liquid effluents discharged to the environment in 1985 appears to result in a calculated dose that is an apparent violation of T.S. 3.17.2.
It is reasonable to expect that no real member of the public actually received a dose greater than this value as a result of the liquid releases made during 1985."
DISTRICT RESPONSE:
In the District transmittal to the NRC dated June 5, 1986 (JEW 86-087), Special Report 86-08, the District acknowledges that the best estimate of the radioactive material in liquid effluent discharged to the environment in 1985 resulted in a calculated dose to the maximum hypothetically
J B MARTIN exposed individual that was in excess of the values specified in T.S. 3.17.2, Liquid Effluents, Dose.
The District will make changes to the ODCM implementing procedures to include the RHUT composite sample analysis results into the 30 day dose projection cal-culations.
The 1985 Annual Radiological Environmental Operating Report included an en-vironmental assessment and estimated a maximum potential exposure of 2 mrem to a member of the public during 1985.
Apparent Violation 86-15-07:
(Reprinted from the NRC Inspection Report 86-15)
"The installation of a piping system specifically intended to transfer water from the liquid radioactive treatment system to the RHUTs for release to the environment without first performing a safety evaluation is con-sidered an apparent violation of 10 CFR 50.59."
, DISTRICT RESPONSE: The temporary piping in question was removed in April 1986 and its re-installation would not be allowed without proper 10 CFR 50.59 evaluations in accordance with procedures which are currently in effect.
At the time the temporary piping was installed, the AP.26, Abnormal Tag Pro-cedure, pertained only to electrical equipment, not to mechanical.
It was, therefore, necessary to use the temporary change provisions of AP.2, Review, Approval and Maintenance of Procedures, which at the time did not require a 50.59 determination.
Both AP.2 and AP.26 have been revised to require a 50.59 determination for all temporary changes to procedures and temporary modifica-tions to plant systems.
Apparent Violation, 86-15-09: Apparent Violation of T.S. 6.8 (reprinted in part from NRC Inspection Report 86-15).
" Based on review of the Procedural Change Approval Form and Discussions with the Principle Regulatory Compliance Engineer, it appears that on January 6, 1986, a temporary change to Procedure A.10, Demineralized Reactor Coolant Storage System, was approved and implemented which allowed pumping water from T-621 to T-950 A and B for offsite release without review by the Plant Review Committee (PRC).
From January 6, 1986 to March 6, 1986, the licensee estimates that about 350,000 gallons of water were transferred.
In addition, the inspector noted that AP.2, Revision 21, Review, Approval and Maintenance of Procedures, had not been developed consistent with this T.S. in that it does not require temporary changes to be reviewed by the PRC.
The Principle Regulatory Compliance Engineer informed the inspector on May 21, 1986, that this issue had been previously addressed by the PRC and that they believed the previous NRC Senior Resident had agreed that the review of non intent changes to procedures could be delegated to a Group Supervisor, reviewed by the PRC Chairman and approved by the Plant Superintendent.
The inspector commented that if T.S. 6.8.3.c were revised, their technique would be considered acceptable.
In any case, the inspector considered the revision to A.10 to be an intent change in view of the FSAR information.
r 1
J B MARTIN Failure to implement and maintain procedures is considered an apparent violation of T.S. 6.8.
The establishment, implementation, and maintenance of procedures is a management function It is the inspector's conclusion that the proper establishment of these procedures considering the guidance provided in IE Circular No. 80-18:
10 CFR 50.59, Safety Evaluations for Changes to Radioactive Waste Treatment Systems, could have resulted in recognition of the need to perform a 50.59 review, update the FSAR, and assure proper sampling of T-621 prior to transfer such that compliance with T.S. 3.17.2 could have been achieved."
DISTRICT RESPONSE: The District will reevaluate the guidance in IE Circular No. 80-18.
Procedure AP.2 and T.S. 6.8 will be reviewed in light of the above discussion and revised as necessary. The approval process of having a PRC Chairman screen procedures was discussed with the NRC in 1984 and found appropriate according to the Technical Specification requirements.
Training will review the guidance in IE Circular No. 80-18, AP.2, and T.S. 6.8, and current training modules pertaining to 50.59 determinations.
Improvements to the 50.59 training will then be made as necessary and training provided to Distrij,tstaffperforming50.59determinationspriortostartup.
~
J
. WARD ASSISTANT GENERAL MANAGER, NUCLEAR (ACTING) i l
l l
l
_ _ - - - _ _.