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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 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 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 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 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 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 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 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 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 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 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 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 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
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SACRAMENTO MUMCIPAL UTiuTY DWTNCT U R O. Som 1583o, Sacramento CA 95852 1830, (916) 452 3211
, AN ELECTRIC SYSTEM SERVING THE HEART OF CAUFORNIA
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MPC&D 97157 November 5,1997 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555 Docket No. 72-11 Rancho Seco Independent Spent Fuel Storage Installation REQUEST FOR REVISION TO NUREG-1536 Attn.: Michael G. Raddatz Introduction The purpose of this letter is to request an interpretation of, or revision to, NUREG-1536
" Standard Review Plan for Dry Cask Storage Systems," regarding compliance with 10 CFR 72.236(c) and 10 CFR 72.122(h)(4) for dry fuel storage casks. As part of the requirements for spent fuel storage cask approval,10 CFR 72.236(c) requires redundant scaling of confinement systems, and 10 CFR 72.122(h)(4) requires that storage confmement systems have the. capability for continuous monitoring.
NUREG-1536 provides guidance for NRC staffin performing reviews oflicense applications for dry fuel storage systems. The principal purpose of NUREG-1536 is to establish a well-dermed basis from which NRC stafican conduct their review to ensure the quality and consistency of that review. NUREG-1536 is also open to interpretation and/or revision to allow for funher clarification regarding the acceptance criteria for designs that the NRC may not have considered prior to issuing the original NUREG.
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RANCHO SECO NUCLEAR GENERATING STATION Cl 14440 Twin Cities Road, Herald, CA 95038-9799;(209) 333-2935
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M. Raddat: MPC&D 97-1.52
'NUREG 1536, Chapter 7 "Confmement Evaluation," profides guidance to NRC staff for evaluating the confmement features and capabilities of a dry cask storage system. In its evaluation of the cask confinement system, the NRC seeks to ensure that:
- 1. Radiological releases to the c . ironment remain within regulatory requirements.
2.- Spent fuel cladding and fuel assemblies will be sufficiently protected during storage against degradation that could lead to gross ruptures.
NUREG 1536 currently recogrJzes as acceptable a system that monitors the pressurized region between a cask's bolted closure redundant seals. We believe that a system that monitors the redundant scaled cask volume is also acceptable, as outlined below.
Tvolcal Cask Confinement Bounderv Typically, a dry fuel storage cask confinement boundary consists of:
- 1. A cylindrical inner shell with welded closures.
- 2. A bolted top closure plate with redundant 0 ring seals.
- 3. Vent and drain port closure plates, also bolted with redundant 0 ring seals.
This confinement boundary, coupled with a system to monitor confinement integrity, provides a high level of confidence that licensees will be able to detect a breach in the confinement boundary, and take corrective actions to ensure that radiological releases to the environment remain within regulatory limits.
Tvolcal Confinement Bounderv Monitorina Systems Because of the high level of confidence in the inherent integrity of welded closures, the NRC has previously not required a monitoring system for welded closures.' Ilowever, due to the greater uncertainty associated with mechanical seals, the NRC has required some form of routine surveillance program and/or active instrumentation to meet the intent of" continuous monitoring," and show compliance with 10 CFR 72.122(h)(4).
For bolted closures with redundant 0-ring seals, the typical approach to monitoring confmement integrity has been to pressurize the region between the redundant seals, with a non reactive gas, to a pressure greater than the cask cavity and the atmosphere. A
' See NUREG 1536. Cluipter 7.Section IV.4.
l Af. Raddatz 3- AIPC&D 97-132 l
. i
' ecrease in pressure between the seals indicates that the gas is leaking either into the cask d ;
cavity or out to the atmosphere.
Part 72 Statements of Consideration In the Part 72 Statements of Consideration for General Licensing Provisions, Comment 35 expressed a concern regarding the potential for corrosion of fuel cladding if the inert atmosphere inside a storage cask is not maintained. In their response, the NRC stated that,
" Cask atmospheres will be required to befd!ed with an inert gas andprovided with snonitoring systems to detret leaks in the <nsk sealing system. "
The NRC further stated that, "If the redundant seals and the monitoring systemfail, oxidation of thefuel cladding could occur...But, there would not be any sigmfcant increase in radioactivity because any release of radioactiw particlesfrom thefuel nxis would remain confined within the cask. If the r edundant scalsfall, and the monitoring system does notfail, the monitoring system would detect thefailure and the seals would be promptly repaired. "
In the Part 72 Statements of Consideration for the Certification of the TN-24 cask, Comment I stated that bolted closures with metal 0 rings have shown poor operating characteristics, and that all closures should be double seal welds. In their response, the NRC stated that, "Several casks with metallic 0-rings have been in operationfor at least seven years. Licensees are required tofileformal nymrts ofproblems with 0-rings occur. The NRC has not receivedam nymrts concerning 0-ringproblems. "
"The metallic O-ring seals may not necessarily last the 20 par term of the Certificate of Compliance. Ihat is why double seals are used with a higher pressure between the 0-rings with pressure monitoring equipment to quickly detect a sealfailure. Failed seals can be readily replaced. "
~ __ . __ __. .. _ _ _ _ _ . _ _ _ . _._ _ _ _ _ _
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MIGtD 97-1M Anarnatha Cannnarnent Boundary Monitorina Svstem
' Although the NRC has accepted conAnement monitoring systems that simply monitor the . l integrity of the redundant 0 ring seals, some cask designs may not allow for this j approach. For example, with the design of some storage casks, this approach to !
confinement monitoring may not be possible because some seals may not accessible for the typical confinement monitoring system described above. In the case where some O ring .
i seals may not be accessible, the typical methods for maintaining redundant seals and i
providing continuous seal monitoring may be mutually exclusive.
~~
- As an altemative to meeting the intent of the continuous monitoring requirements in 10 CFR 72.122(h)(4), and the redundant sealing requirements in 10 CFR 72.236(e), a dry i storage cask could use a system that monitors the helium pressure in the cask interior. Or, ,
for a seal welded canister stored in a cask, a system that monitors the annulus between the !
canister and the cask inner shell. Providing direct and continuous monitoring of the +
- helium atmosphere inside the cask, or canister / cask annulus, would monitor the integrity of the entire confinement boundary, as opposed to monitoring only the integrity of the ,
mechanical seals.. ,
In the unlikely event of cask confmement leakage through a path other than the mechanical seals, the alternative system would deter isuch leakage, and is superior to a between the-seal monitoring system that would not detect the leakage. The proposed l system would be consistent with the Statement of Considerations noted above, j
'llf the redurukmt sealsfall, arut the monitoring system does notfall, the mcmitoring system would detect thefailure arul the seals would be promptly repaired. "
Although there may be only a single seal boundary on the pressure transmitter associated with this type of monitoring system, the size of the seal would be small, and not as susceptible to failure as the larger diameter 0 rings used on the cask cover plates. There' ;
would likely be a short mn of piping, with a few small fittings; however, the system would ,
operate at very low pressure, and any leak path would be very small. ' The system would ;
. monitor the cask interior continuously and directly, and could provide a port to sample the. ,
cask atmosphere,if needed.
Based on the ad0antages of monitoring the integrity of the entire cask confinement boundary SMUD believes that this alternative provides an acceptable level of confidence in confinement integrity, and s alves the dichotomy between the requirements for providing redundar;t seals and continuous monitoring for certain types of storage cask.
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M. Rad &nz $- MPC&D 97-132 Use of an Alternative Confinement Boundary Monitorina Systern Some licensees plan on using a canister based dry fuel storage system The canister-based storage system could include a cask licensed for storage in the event of a breached canister at the ISFSt.
2 In the even; a cask is used as a storage cask , the licensee would place the breached canister la the cask, seal the cask with the bolted closure plates, evacuate the cask cavity, and backfill the cavity with helium. Ilackfilling the annulus between the canister and the cask inner shell with helium provides a non reactive environment to protect the fuel assemblics against fuel cladding degradation.
When used as a storage cask, the licentee would record the cask pressure as part of a routine surveillance program. If the cask pressure monitoring indicates the requirement to re test and replace the cask or monitoring system seals, the licensee would take actions to repair or replace the faulty seals, in accordance with approved plant procedures.
Another advantage of a system that monitors the cask volume directly is the reduced potential for unnecessarily removing the cask lid to replace seals that may not be faulty.
Minimizing the potential for unnecessary cask lid removal also minimizes the potential for a release while conducting an unnecessary 0 ring replacement operation.
When using the typical approach to monitoring con 6nement integrity, a decrease in pressure between the sals indicates that either the inner seal, the outer seal, or both seals, may be leaking if the licensee determines that the cask outer seal is leaking, the integrity of the inner seal remains indeterminate because there is no way to individually assess its status. The licensee would need to remove the cask closure plate, and replace both seals even if the inner seal is intact.
A decrease in pressure using the alternative system indicates that seal replacement is clearly required, thus avoiding unwarranted cask lid removal operations. If the leak is from the instrument seal, the licensee could easily replace that seal, without the need to unnecessarily remove the cask closure plate. Also, the alternative system would allow the licensee to sample the cask atmosphere directly, to determine the level of activity in the cask inteiior.
A routine surveillance program, along with continuous instmment monitoring of the cask helium atmosphere, would provide confidence not only in the performance of the 0 ring seals, it would provide confidence in the integrity of the entite cask con 6nement boundary, including the welded closures. This alternative monitoring system, along with operating procedures to readily replace faulty seals, would enhance protection to the environment by ensuring a non-reactive environment to protect the fuel assemblies against cladding 8 The licensec puld use the cask as a storage overpack to isolate a breached canister from the environment, if the spent fuel pool is not available.
1 M. Raddat: MPC&D 97-132
' ' ' ' degradation during storage, and ensuring that radiological releases to the environment will be within regulatory requirements.
Reauested Action Dased on the advantages of monitoring the integrity of the entire cask confinement boundary, SMUD believes that this alternative provides an acceptable level of confidence in confinement imegrity, and meets the intent of 10 CFR 72.236(e) and 10 CFR 72.122(h)(4). Accordingly, SMUD requests that the NRC consider the alternative monitoring approach described, and determine if the alternative system meets the intent of the regulatory requirements, and provides adequate assurance that radiological releases to the environment will be within regulatory requirements.
If the NRC determines that the alternative confinement monitoring system meets the intent of 10 CFR 72.236(e) and 10 CFR 72.122(h)(4), SMUD requests that the NRC clarify the acceptance criteria in NUREG-1536, Chapter 7,Section IV, by stating that storage cask confinement monitoring systems that monitor the integrity of the entire cask confinement boundary meet the intent of 10 CFR 72.236(c). For example:
Storage cask confinement monitoring systems that monitor the integrity of the entire cask confinement boundary are acceptable. Although this type of monitoring hyStem may have smallfittings, connectors, or instruments using single seals, the admntages of this methodprovide an acceptable lewl of confidence in confinement integrity, andprovide a high level of confidence that licensees will be able to take corrective actions to ensure that radiological releases to the environment remain within regida!ary lituits. Accordingly, systems that monitor the integrity of the entire cask confinement boundary meet the intcnt of10 CFR 72.236(e) and 10 CFR 72.122(h)(4).
If you, or members of your stafT, have questions requiring additional information or clarification, please contact Bob Jones at (916)452-3211, extension 4676.
Sincerely, 1 tl .4 Steve Redeker Manager, Plant Closure and Decommissioning