Letter Sequence RAI |
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MONTHYEARML20245D3081989-06-19019 June 1989 Forwards Request for Addl Info to Continue Review of Response to Generic Ltr 88-01, IGSCC Problems in BWR Austenitic Stainless Steel Piping. Response Should Also Be Submitted to Viking Sys Intl at Listed Address Project stage: RAI 1989-06-19
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20112E8911996-05-24024 May 1996 FOIA Request to Inspect & Copy Original OL Issued by Aec/Nrc for Util & EPP Issued as App B to Plant OL SNRC-2192, Forwards Both Copies,Signed by Util President Cv Giacomazzo, of Amend 7 to Indemnity Agreement B-87.Util Returning Copies Because Effective Date Left Blank1995-05-15015 May 1995 Forwards Both Copies,Signed by Util President Cv Giacomazzo, of Amend 7 to Indemnity Agreement B-87.Util Returning Copies Because Effective Date Left Blank ML20082B9131995-03-13013 March 1995 Submits Corrected Page for Insertion Into Final Rept Re Confirmatory Survey of RB & Phase 4 Systems at Plant ML20081A9321995-03-0707 March 1995 Forwards Final Rept Orise 95/B-81, Confirmatory Survey of Reactor Bldg & Phase 4 Sys Shoreham Nuclear Power Station Brookhaven,Ny ML20081A6531995-03-0707 March 1995 Forwards Final Rept Orise 95/B-80, Confirmatory Survey of Radwaste Bldg,Suppression Pool,Phase 2 Phase 3 Sys,Shoreham Nuclear Power Station,Brookhaven,Ny ML20081A6841995-02-21021 February 1995 Forwards Final Rept Confirmatory Survey of Radwaste Bldg, Suppression Pool,Phase 2 & Phase 3 Sys,Shoreham Nuclear Power Station,Brookhaven,Ny ML20081B5801995-02-21021 February 1995 Forwards Final Rept Confirmatory Survey of Reactor Bldg & Phase 4 Sys Shoreham Nuclear Power Station Brookhaven,Ny ML20081A7001995-01-30030 January 1995 Forwards Rev 1 to Draft Rept Confirmatory Survey of Radwaste Bldg,Suppression Pool,Phase 2 & Phase 3 Sys, Shoreham Nuclear Power Station,Brookhaven,Ny ML20081A7111995-01-30030 January 1995 Forwards Rev 1 to Draft Rept Confirmatory Survey of Reactor Bldg & Phase 4 Sys,Shoreham Nuclear Power Station, Brookhaven,Ny SNRC-2189, Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program,Annual Radiological Environ Operating Rept, Jan-June 19941995-01-20020 January 1995 Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program,Annual Radiological Environ Operating Rept, Jan-June 1994 SNRC-2188, Responds to NRC Request for Addl Info Re Certain Elevated Levels Found During Phase 4 Confirmatory Survey1995-01-20020 January 1995 Responds to NRC Request for Addl Info Re Certain Elevated Levels Found During Phase 4 Confirmatory Survey SNRC-2187, Forwards Snps Annual Man-Rem Rept, Including Individuals for Whom Personnel Monitoring Provided During CY94,per 10CFR20.407(a) & (B).Rept Also Includes Individuals Identified in 10CFR20.202(a),who Require Monioring1995-01-11011 January 1995 Forwards Snps Annual Man-Rem Rept, Including Individuals for Whom Personnel Monitoring Provided During CY94,per 10CFR20.407(a) & (B).Rept Also Includes Individuals Identified in 10CFR20.202(a),who Require Monioring SNRC-2182, Forwards Final Annual Radioactive Effluent Release Rept for Cy 1994, Including Last Revised Copies of ODCM & Pcp.Rept Prepared for Closeout Purposes as Part of Completion of Plant Decommissioning1994-11-0101 November 1994 Forwards Final Annual Radioactive Effluent Release Rept for Cy 1994, Including Last Revised Copies of ODCM & Pcp.Rept Prepared for Closeout Purposes as Part of Completion of Plant Decommissioning ML20077L3331994-10-25025 October 1994 Forwards Revised Proposed Confirmatory Survey Plan for Reactor Bldg Shoreham Nuclear Power Station Brookhaven,Ny ML20076K3881994-10-20020 October 1994 Forwards Proposed Confirmatory Survey Plan for Reactor Bldg, Shoreham Nuclear Power Station,Brookhaven,Ny,For Review & Comment ML20077M8351994-10-20020 October 1994 Forwards Draft Rept, Confirmatory Survey of Radwaste Bldg, Suppression Pool & Phase 2 Systems,Shoreham Nuclear Power Station,Brookhaven,Ny SNRC-2184, Forwards Shoreham Decommissioning Project Termination Survey Final Rept Phase 4. Portions Withheld1994-10-12012 October 1994 Forwards Shoreham Decommissioning Project Termination Survey Final Rept Phase 4. Portions Withheld SNRC-2185, Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl1994-10-0404 October 1994 Summarizes Results from Revised Exposure Pathway Analysis Using Corrected Dcf for External Exposure for Cs-137.Rev 1 to Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl ML20076F9251994-09-26026 September 1994 Forwards Final Rept Orise 94/I-80, Confirmatory Survey of Turbine Bldg,Site Grounds & Site Exteriors Shoreham Nuclear Power Station Brookhaven,Ny SNRC-2183, Forwards Amend 6 to Indemnity Agreement B-871994-09-23023 September 1994 Forwards Amend 6 to Indemnity Agreement B-87 SNRC-2181, Notifies of Equipment Changes to Shoreham Facility Which Have Occurred Subsequent to Rept on Phase I Final Survey Status,Provided in Util .Equipment Changes Described in Encl Table 11994-09-14014 September 1994 Notifies of Equipment Changes to Shoreham Facility Which Have Occurred Subsequent to Rept on Phase I Final Survey Status,Provided in Util .Equipment Changes Described in Encl Table 1 SNRC-2180, Forwards 940829 Memo Entitled, Technical Evaluation of Dusting from Concrete Blocks, Addressing Issue Discussed in Insp Rept 50-332/94-021994-09-0101 September 1994 Forwards 940829 Memo Entitled, Technical Evaluation of Dusting from Concrete Blocks, Addressing Issue Discussed in Insp Rept 50-332/94-02 SNRC-2179, Proposes That Release Criterion for Soil Be Applied to Certain Other Bulk Matls Which Will Remain at Plant Upon Completion of Decommissioning.Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl1994-09-0101 September 1994 Proposes That Release Criterion for Soil Be Applied to Certain Other Bulk Matls Which Will Remain at Plant Upon Completion of Decommissioning.Analysis of Bulk Matl Reconcentration Potential & Possible Exposure Pathways Encl SNRC-2178, Forwards Proprietary Response to NRC Concerns Re Survey Instruments Used for Termination Survey.Extensive Discussion Provided in Interest of Rapidly Bringing Outstanding Concerns to Close.Response Withheld (Ref 10CFR2.790(a)(4))1994-08-17017 August 1994 Forwards Proprietary Response to NRC Concerns Re Survey Instruments Used for Termination Survey.Extensive Discussion Provided in Interest of Rapidly Bringing Outstanding Concerns to Close.Response Withheld (Ref 10CFR2.790(a)(4)) ML20072P1591994-08-17017 August 1994 Forwards Revised, Confirmatory Survey Plan for Radwaste Bldg & Suppression Pool for Plant SNRC-2176, Informs of near-term Completion of Decommissioning of Shoreham Nuclear Power Station & Hereby Respectfully Requests Support in Achieving Timely Termination of Facility possession-only License NPF-821994-08-0404 August 1994 Informs of near-term Completion of Decommissioning of Shoreham Nuclear Power Station & Hereby Respectfully Requests Support in Achieving Timely Termination of Facility possession-only License NPF-82 SNRC-2177, Forwards Rev 3 to Shoreham Decommissioning Project Termination Survey Plan. Portions of Rept Withheld1994-08-0404 August 1994 Forwards Rev 3 to Shoreham Decommissioning Project Termination Survey Plan. Portions of Rept Withheld ML20071L8741994-07-29029 July 1994 Forwards Confirmatory Survey Plan for Radwaste Building & Suppression Pool for Review & Comment SNRC-2175, Provides Notification of Survey Location Changes to Shoreham Facility Which Have Occurred Subsequent to Repts on Phases 1,2 & 3 Final Survey Status Provided in Refs 1,2 & 3 Respectively1994-07-18018 July 1994 Provides Notification of Survey Location Changes to Shoreham Facility Which Have Occurred Subsequent to Repts on Phases 1,2 & 3 Final Survey Status Provided in Refs 1,2 & 3 Respectively SNRC-2173, Forwards Termination Survey Final Rept Phase 3. Proprietary Pages to Rept Also Encl.Proprietary Pages Withheld (Ref 10CFR2.790)1994-06-14014 June 1994 Forwards Termination Survey Final Rept Phase 3. Proprietary Pages to Rept Also Encl.Proprietary Pages Withheld (Ref 10CFR2.790) SNRC-2172, Certifies That All SNM as Irradiated Fuel Permanently Removed from Site & That Decommissioning/Decontamination Work on Biological Shield Wall Complete,In Accordance W/Nrc Approving Amend 11 to Pol NPF-821994-06-0707 June 1994 Certifies That All SNM as Irradiated Fuel Permanently Removed from Site & That Decommissioning/Decontamination Work on Biological Shield Wall Complete,In Accordance W/Nrc Approving Amend 11 to Pol NPF-82 SNRC-2171, Submits Resolution of Items Identified by NRC Region I Project Inspector,Pertaining to Planned Final Draindown & Discharge of Spent Fuel Storage Pool,Following Complete Removal of Irradiated Fuel1994-06-0202 June 1994 Submits Resolution of Items Identified by NRC Region I Project Inspector,Pertaining to Planned Final Draindown & Discharge of Spent Fuel Storage Pool,Following Complete Removal of Irradiated Fuel SNRC-2170, Requests Approval of Proposed Change to Shoreham Decommissioning Plan for Addl Remedial Decontamination of Shoreham Spent Fuel Storage Pool Beyond That Originally Specified in Decommissioning Plan1994-05-20020 May 1994 Requests Approval of Proposed Change to Shoreham Decommissioning Plan for Addl Remedial Decontamination of Shoreham Spent Fuel Storage Pool Beyond That Originally Specified in Decommissioning Plan SNRC-2168, Notification to NRC of Transfer of Device Containing 30 Uci Cs-137 Source.Device Transferred to JW Merkel,Terra Analytics,Inc1994-05-13013 May 1994 Notification to NRC of Transfer of Device Containing 30 Uci Cs-137 Source.Device Transferred to JW Merkel,Terra Analytics,Inc SNRC-2169, Advises of Listed Clarification to Util Re Resignation of Jc Brons from Position of Executive Vice President of Shoreham Decommissioning Project1994-05-11011 May 1994 Advises of Listed Clarification to Util Re Resignation of Jc Brons from Position of Executive Vice President of Shoreham Decommissioning Project ML20029E1731994-05-11011 May 1994 Informs That Based on Recent Discussions Between Officials, Licensee Decided to Retain Organizational Position at Least Until Fuel Removed from Site ML20029D1991994-04-29029 April 1994 Forwards Shoreham Nuclear Power Station Radiological Environ Monitoring Program Annual Radiological Environ Operating Rept Jan-Dec 1993. ML20029D2571994-04-28028 April 1994 Advises That Jc Brons Resigned to Pursue Employment W/ Another Util Co,Effective 940429 ML20029C7111994-04-22022 April 1994 Submits Technical Info on Biological Shield Wall Blocks to Be Surveyed SNRC-2163, Provides Notification of Equipment Changes to Facility Which Have Occurred Subsequent to Report on Phase I Final Survey Status Provided in Util1994-04-21021 April 1994 Provides Notification of Equipment Changes to Facility Which Have Occurred Subsequent to Report on Phase I Final Survey Status Provided in Util ML20065M3701994-04-20020 April 1994 Responds to NRC Verbal Request for Info Re Estimated Cost for Decommissioning SNRC-2161, Forwards 1994 Internal Cash Flow Projection for Shoreham Nuclear Power Station1994-03-30030 March 1994 Forwards 1994 Internal Cash Flow Projection for Shoreham Nuclear Power Station SNRC-2160, Forwards Financial Info Required by 10CFR50.71(b)1994-03-30030 March 1994 Forwards Financial Info Required by 10CFR50.71(b) SNRC-2148, Forwards Info Supporting Licensee Proposed Amend,Submitted on 941104.Specifically,info Supports Estimates & Conclusions Re Small Quantity of Remaining Radioactive Matl & Low Radiological Significance of Potential Accident Releases1994-03-0808 March 1994 Forwards Info Supporting Licensee Proposed Amend,Submitted on 941104.Specifically,info Supports Estimates & Conclusions Re Small Quantity of Remaining Radioactive Matl & Low Radiological Significance of Potential Accident Releases 1999-10-01
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058J0591990-11-19019 November 1990 Forwards NRC Public Notice of 901108 License Amend Request Re Shipment of Fuel Support Pieces to Low Level Radwaste Disposal Repository at Barnwell,Sc ML20058H8091990-11-14014 November 1990 Responds to Indicating Desire to Ship 137 Fuel Support Castings & 12 Peripheral Pieces to Low Level Radwaste Repository ML20062B6631990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20059M7901990-09-27027 September 1990 Advises That 880708 Response to NRC Bulletin 88-004 Re Potential safety-related Pump Loss Acceptable ML20059M4991990-09-20020 September 1990 Forwards Insp Rept 50-322/90-02 on 900606-0825.No Violations Noted ML20056B4481990-08-21021 August 1990 Forwards Exemption from fitness-for-duty Requirements Re 10CFR26,per .Exemption Requested to Limit Scope of Program to Persons W/Unescorted Access to Area Containing Equipment Necessary to Support & Maintain Storage of Fuel ML20059A6491990-08-16016 August 1990 Grants Waiver of Compliance from Limiting Condition for Operation 3.7.1.2.b.3 of Tech Spec on Plant Svc Water Sys, Per 900810 & 15 Ltrs.Waiver Allows Performance of Underwater Radiation Survey & Physical Insp of Selected Fuel Elements ML20059A6351990-08-15015 August 1990 Forwards Notice of Consideration of Issuance of Amend to License NPF-82 & Proposed NSHC Determination & Opportunity for Hearing Re 900105 Application ML20059A7151990-08-14014 August 1990 Expresses Appreciation for Remarks on Status & Schedules During drop-in Visit at Region I on 900731.Summary of Discussion Encl ML20058N8391990-08-13013 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900315 Request for Exemption from Full Scope of Fitness for Duty Requirements of 10CFR26 ML20058P1921990-08-0707 August 1990 Forwards Insp Rept 50-322/90-03 on 900710-13.No Violations Noted.One Unresolved Item Noted ML20058M5951990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Mgrs Forum to Foster Disciplined & Coordinated Approach to Initiatives ML20056A1971990-07-31031 July 1990 Forwards Amend 6 to License NPF-82,safety Evaluation,Notice of Issuance & Exemption Re Defueled Emergency Preparedness License Condition.Proposed Changes Would Allow Util to Cease Offsite Emergency Preparedness Activities ML20055G5691990-07-19019 July 1990 Grants Util 15-day Extension of 900619 Waiver of Compliance Re OL Paragraph 2.C.(13) Quarterly Drills License Condition. Extension Will Allow NRC to Complete Review of Associated Request to Cease Offsite Emergency Preparedness Activities ML20055D2911990-06-27027 June 1990 Forwards Review of Util 900105 Request to Amend Tech Specs to Reflect Plant Protracted Defueled Condition.Meeting Should Be Scheduled at Site on 900719 & 20 to Discuss Finalizing Plant Defueled Tech Specs ML20055E3591990-06-25025 June 1990 Forwards Amend 5 to License NPF-82 & Safety Evaluation.Amend Changes Administrative Section of Tech Specs & Moves Procedural Details Involving Radioactive Effluent Monitoring Instrumentation & Equipment Requirements to ODCM ML20055C8281990-06-19019 June 1990 Grants 900530 Request for Waiver of Compliance from License NPF-82,Paragraph 2.C.(13) Re Quarterly Drills License Condition,Pending NRC Action on 891215 Request to Cease Offsite Emergency Preparedness Activities ML20248C0531989-09-26026 September 1989 Forwards Amend 4 to Indemnity Agreement B-87,reflecting Changes to 10CFR140.Amend Reflect Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248G9331989-09-25025 September 1989 Forwards Safeguards Insp Rept 50-322/89-08 on 890821-24.No Violations Noted ML20247L3011989-09-15015 September 1989 Forwards J Mcgranery & L Bickwit 10CFR2.206 Petitions & Suppls & Requires,Under 10CFR50.54 (F) Provisions,That Licensee Address Each Concern Raised within 30 Days of Ltr Receipt ML20246K8301989-08-30030 August 1989 Requests to Provide NRC W/Written Commitment to Assure That Items Listed Satisfied for Extended Period & to Provide Info Re Processes Followed in Selecting Operating Status & in Determining Intended Staffing Changes,Per 890630 Commitment ML20246J3341989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purpose of Setting Occupational Exposure Limits.Regulation Specifies That Extremity Dose Limits Apply to Hands & Forearms,Feet & Ankles,Per Info Notice 81-26,Part 3 ML20245K3781989-08-0909 August 1989 Submits Guidelines to Be Used for Submittal & Review of Objectives & Scenario Packages Prior to Emergency Exercise & Provides List of Individuals to Receive Scenario in Lieu of Normal Distribution ML20247E4661989-07-24024 July 1989 Submits Response to Requesting Exemption from Payment of Annual License Fees for Plant.Util Failed to Demonstrate Under 10CFR171.11 an Adequate Basis to Support Exemption Request,Therefore,Request Denied ML20246J0901989-07-0707 July 1989 Denies Util 890522 Request for Exemption from 10CFR50.54(W) Re Required Amount of Onsite Insurance Coverage.Insurance Requirements of 10CFR50.54(W) Appropriate for Plants W/Full Power OLs ML20246E9611989-07-0606 July 1989 Forwards Ack Receipt of Petition Filed by Ecology Ctr of Southern California Under 2.206 ML20245D3081989-06-19019 June 1989 Forwards Request for Addl Info to Continue Review of Response to Generic Ltr 88-01, IGSCC Problems in BWR Austenitic Stainless Steel Piping. Response Should Also Be Submitted to Viking Sys Intl at Listed Address IR 05000322/19890041989-05-25025 May 1989 Forwards Insp Rept 50-322/89-04 on 890221-0505.No Violations Noted ML20244B8901989-05-25025 May 1989 Forwards Director'S Decision 89-03 & Fr Notice Re Hiatt 10CFR2.206 Petition Expressing Concern Re 880309 Power Oscillation Event at LaSalle Unit 2.Petition Denied. Request to Reopen Proceeding Re ATWS Treated Per 10CFR2.802 ML20247C3001989-05-18018 May 1989 Discusses Util 890221 Response to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Util Taking Correct & Positive Measures Towards Ensuring That Plant Does Not Experience Subj Problems ML20247A4641989-05-12012 May 1989 Grants 881118 Request for Exemption from Licensing Fees for 890422-0630.Prorated Invoice for Portion of Third Quarter of FY89 Encl ML20246J4531989-05-0404 May 1989 Advises That Financial Info for 1989 Submitted in Util Satisfies 10CFR140.21 Requirement That Licensee Maintain Approved Guarantee of Payment of Deferred Premiums for Each Operating Reactor Over 100 Mwe Owned ML20246E1591989-05-0404 May 1989 Requests That Util Proceed to Implement Conceptual Design for Core Spray Injection Valve Low Pressure Permissive Logic & Setpoint Before Startup After First Refueling Outage,Per 830218 Commitment NUREG-1357, Forwards Tech Specs (NUREG-1357) & Sser 10.W/o Encls1989-05-0303 May 1989 Forwards Tech Specs (NUREG-1357) & Sser 10.W/o Encls ML20247A7481989-05-0303 May 1989 Extends Invitation to Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Meeting Agenda Encl ML20245B8851989-04-21021 April 1989 Forwards License NPF-82,nonradiological Environ Protection Plan,Notice of Issuance of Ol,Amend 3 to Indemnity Agreement B-87 & Sser 10.W/o Sser 10 ML20244D2371989-04-11011 April 1989 Forwards Environ Assessment & Finding of No Significant Impact Re 860327 & 850619 Requests for Exemption from 10CFR50.44(c)(3)(i) to Permit Reactor to Operate for 120 EFPD Before Containment Atmosphere Must Be Inerted ML20248G7131989-04-0404 April 1989 Forwards Operational Readiness Assessment Team Insp Rept 50-322/89-80 on 890311-27.Listed Items Require Resolution W/Nrc Prior to Operation Above 5% Power ML20248J5481989-03-31031 March 1989 Forwards Safety Insp Rept 50-322/89-05 on 890314-17.No Violations Noted ML20247L3781989-03-29029 March 1989 Discusses FEMA Review of Rev 10 to Offsite Emergency Plan & FEMA Exercise Assessment.Fema Continues to Support Overall Finding of Reasonable Assurance Transmitted to NRC on 880909 ML20247E2991989-03-28028 March 1989 Ack Receipt & Review of Changes to Jan 1989 Rev 9 to Emergency Preparedness Plan.Changes Consistent W/ Requirements of 10CFR50.54(q) & Acceptable ML20236B9471989-03-13013 March 1989 Forwards Safety Insp Rept 50-322/89-02 on 890109-13.No Violations Noted ML20236B9331989-03-13013 March 1989 Forwards Safeguards Insp Rept 50-322/89-03 on 890213-16.No Violations Noted ML20236E1731989-03-10010 March 1989 Requests Review of Encl camera-ready Tech Specs to Document & Certify Accuracy W/Facility Usar,Per 890301 Meeting ML20235Y9391989-03-0202 March 1989 Forwards Insp Rept 50-322/89-01 on 890104-0220.No Violations Noted.Matter Noted in Rept Detail 4.1 Re Specific Recurrent Failure of Valve to Seat Properly Will Be Evaluated Further by NRC as Measure of Licensee Performance ML20235S2741989-02-17017 February 1989 Forwards Exam Rept 50-322/88-12OL of Exam Administered During Wk of 881212 ML20235M1811989-02-0808 February 1989 Forwards SER Accepting Util 880909 & 1221 Responses to NRC Bulletin 88-005, Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co at Williamstown,Nj. Issue Considered Resolved ML20196E5641988-11-30030 November 1988 Forwards Amend 10 to License NPF-36 & Safety Evaluation. Amend Changes Definition of Core Alteration in Tech Specs to Include Certain Exceptions & Changes Footnotes in Tech Specs to Be Consistent W/New Definition ML20196B6581988-11-30030 November 1988 Forwards Amend 9 to License NPF-36 & Safety Evaluation.Amend Revises Attachment 3 to Plant License Re Maint & Surveillance for Tdi Emergency Diesel Generators ML20206J4981988-11-23023 November 1988 Forwards Radiological Safety Insp Rept 50-322/88-09 on 881017-21.No Violations Noted 1990-09-27
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212L2081999-10-0101 October 1999 Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance ML20212L1831999-10-0101 October 1999 Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health ML20212L2171999-10-0101 October 1999 Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island ML20212L1971999-10-0101 October 1999 Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety ML20212K1241999-10-0101 October 1999 Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected ML20212J9991999-10-0101 October 1999 Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected ML20059J8101994-01-26026 January 1994 Responds to 930701 & 16 Ltrs Re Changes to Shoreham Nuclear Power Station Revised Security Plan for Long Term Defueled Condition,Fuel Storage in Spent Fuel Identified as Rev 2. Changes Acceptable ML20058P2831993-12-0808 December 1993 Advises That Rev 2 to Security Plan for Long Term Defueled Condition,Fuel Storage in Spent Fuel Pool Consistent W/ Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan W/Encl Exceptions.Exceptions Withheld Per 10CFR73.21 ML20058D1971993-11-22022 November 1993 Forwards Insp Rept 50-322/93-03 on 930801-1008.No Violations Noted.Weaknesses Were Identified in Initial Fuel Shipment at Shoreham Station ML20058K7301993-11-16016 November 1993 Informs That Case 93-4269,State of Nj Vs Long Island Power Authority Filed on 930921,seeking to Prevent Barge Shipments of Slightly Spent Fuel from Defunct Shoreham Nuclear Power Plant to Limerick Plant Dismissed on 931021 ML20062J7981993-11-0505 November 1993 Forwards EA & Finding of No Significant Impact in Response to 930706 Request for Exemption from Revised Requirements of 10CFR20 for Unit 1.Schedular Exemption Granted ML20059B2231993-10-22022 October 1993 Ack Receipt of 931008 Petition Filed W/Edo,Requesting That Commission Take Immediate Action to Halt Ongoing Shipments of Fuel ML20057F2071993-09-30030 September 1993 Forwards Exemption from Emergency Preparedness Requirements of 10CFR50.54(q),per 930126 Request & SER ML20057B7201993-09-14014 September 1993 Forwards EA & Finding of No Significant Impact in Response to 930126 Request for Exemption from Emergency Preparedness Requirements of 10CFR50.54(q).Informs That After EA & Fonsi Published in Fr,Exemption Can Be Granted ML20057D8981993-09-13013 September 1993 Forwards Enclosure (8) to SECY-93-166 Re Proposed Characteristics of Design Basis Vehicle.W/O Encl ML20056H1991993-08-26026 August 1993 Responds to Re Changes to Shoreham Nuclear Power Station Guard Training & Qualification Plan Identified as Rev 6.Rev Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan ML20056H5131993-08-26026 August 1993 Accepts Changes to Safeguards Contingency Plan Identified as Rev 6.Changes Consistent w/10CFR50.54(p) IR 05000322/19930021993-08-16016 August 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-322/93-02 ML20056C7151993-07-14014 July 1993 Forwards Amend 10 to License NPF-82 & Se.Amend Revises Defueled TS by Deleting Requirement That Radioactive Effluent Release Rept Be Submitted on Semiannual Basis & Eliminates Requirements for Ac Sources ML20056G0041993-06-25025 June 1993 Submits Info Re Implementation of Training Rule 10CFR50.120 for Licensees of Plant in Decommissioning Process ML20058M0361993-04-12012 April 1993 Partial Response to FOIA Request for Documents.Forwards Records in App L Which Are Being Withheld Partially for Listed Reasons,(Ref FOIA Exemptions 5) ML20128G6271993-02-0202 February 1993 Forwards Insp Rept 50-322/92-05 on 921013-1231.No Violations Noted.One Unresolved Item Described.Decommissioning Activities Generally Well Managed ML20128H2951993-01-29029 January 1993 Informs That NRC Has Reviewed & Approved Licensees Ltr LSNRC-2019 Dtd 921230,requesting Change to Shoreham Decommissioning Plan in Accordance W/Condition 4 for Decommissioning Order ML20126G9351992-12-22022 December 1992 Submits Results of Review of 921204 & 14 Requests for Approval of Changes to Decommissioning Plan Covering Decommissioning of Existing Liquid Radwaste Redundant Sys. Removal of Redundant Sys Approved ML20126F9431992-12-16016 December 1992 Provides Interim Response to Re Transnuclear Inc Application for License to Export Irradiated Fuel from Facility in New York to Cogema in France ML20126G9231992-12-16016 December 1992 Forwards Comments Per Review of Rev 0 to Decommissioning Project Termination Survey Plan,Submitted Via . Addl Info Needed to Complete Review of Proposal to Exclude Fe-55 from Consideration W/Surface Contamination Limits ML20128E1061992-12-0202 December 1992 Forwards Insp Rept 50-322/92-04 on 920627-1012 & Notice of Violation ML20133N0981991-08-27027 August 1991 Forwards Viewgraphs Used by Long Island Lighting Power Assoc During Meeting W/Nrc on 910816 ML20058J0591990-11-19019 November 1990 Forwards NRC Public Notice of 901108 License Amend Request Re Shipment of Fuel Support Pieces to Low Level Radwaste Disposal Repository at Barnwell,Sc ML20058H8091990-11-14014 November 1990 Responds to Indicating Desire to Ship 137 Fuel Support Castings & 12 Peripheral Pieces to Low Level Radwaste Repository ML20062F4301990-11-0808 November 1990 Advises That Ofc of General Counsel Designated to Review & Resolve Six Petitions Filed by Scientists & Engineers for Secure Energy & Stated School District Re Amends to Ol. W/Certificate of Svc.Served on 901109 ML20062C1901990-10-24024 October 1990 Advises That Commissioner Jr Curtiss Will Visit Plant on 901113 to Tour Facility & Meet W/Lilco Mgt & Operating Personnel to Review General Status of Activities at Plant. W/Certificate of Svc.Served on 901024 ML20058G4471990-10-18018 October 1990 Forwards Sept 1990 Rept to Commission on Implementation of TMI Action Plan Items,Per 900320 Commitment.W/O Encl.Review Concluded for All But Two Units ML20062B6631990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support ML20059M7901990-09-27027 September 1990 Advises That 880708 Response to NRC Bulletin 88-004 Re Potential safety-related Pump Loss Acceptable ML20059M4991990-09-20020 September 1990 Forwards Insp Rept 50-322/90-02 on 900606-0825.No Violations Noted ML20056B4481990-08-21021 August 1990 Forwards Exemption from fitness-for-duty Requirements Re 10CFR26,per .Exemption Requested to Limit Scope of Program to Persons W/Unescorted Access to Area Containing Equipment Necessary to Support & Maintain Storage of Fuel ML20059A6491990-08-16016 August 1990 Grants Waiver of Compliance from Limiting Condition for Operation 3.7.1.2.b.3 of Tech Spec on Plant Svc Water Sys, Per 900810 & 15 Ltrs.Waiver Allows Performance of Underwater Radiation Survey & Physical Insp of Selected Fuel Elements ML20059A6351990-08-15015 August 1990 Forwards Notice of Consideration of Issuance of Amend to License NPF-82 & Proposed NSHC Determination & Opportunity for Hearing Re 900105 Application ML20059A7151990-08-14014 August 1990 Expresses Appreciation for Remarks on Status & Schedules During drop-in Visit at Region I on 900731.Summary of Discussion Encl ML20058N8391990-08-13013 August 1990 Forwards Environ Assessment & Finding of No Significant Impact Re 900315 Request for Exemption from Full Scope of Fitness for Duty Requirements of 10CFR26 ML20058P1921990-08-0707 August 1990 Forwards Insp Rept 50-322/90-03 on 900710-13.No Violations Noted.One Unresolved Item Noted ML20058M5951990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Mgrs Forum to Foster Disciplined & Coordinated Approach to Initiatives ML20056A1971990-07-31031 July 1990 Forwards Amend 6 to License NPF-82,safety Evaluation,Notice of Issuance & Exemption Re Defueled Emergency Preparedness License Condition.Proposed Changes Would Allow Util to Cease Offsite Emergency Preparedness Activities ML20055G5691990-07-19019 July 1990 Grants Util 15-day Extension of 900619 Waiver of Compliance Re OL Paragraph 2.C.(13) Quarterly Drills License Condition. Extension Will Allow NRC to Complete Review of Associated Request to Cease Offsite Emergency Preparedness Activities ML20055D2911990-06-27027 June 1990 Forwards Review of Util 900105 Request to Amend Tech Specs to Reflect Plant Protracted Defueled Condition.Meeting Should Be Scheduled at Site on 900719 & 20 to Discuss Finalizing Plant Defueled Tech Specs ML20055E3591990-06-25025 June 1990 Forwards Amend 5 to License NPF-82 & Safety Evaluation.Amend Changes Administrative Section of Tech Specs & Moves Procedural Details Involving Radioactive Effluent Monitoring Instrumentation & Equipment Requirements to ODCM ML20055C8281990-06-19019 June 1990 Grants 900530 Request for Waiver of Compliance from License NPF-82,Paragraph 2.C.(13) Re Quarterly Drills License Condition,Pending NRC Action on 891215 Request to Cease Offsite Emergency Preparedness Activities ML20248C0531989-09-26026 September 1989 Forwards Amend 4 to Indemnity Agreement B-87,reflecting Changes to 10CFR140.Amend Reflect Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248G9331989-09-25025 September 1989 Forwards Safeguards Insp Rept 50-322/89-08 on 890821-24.No Violations Noted 1999-10-01
[Table view] |
Text
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June 19, 1989:
O O.
Docket No. 50-322 y DIS"RIBUTION w/ enclosure: ,
idDocket111egf SBrown l Mr. . Johh D. Leonard, Jr. NRC PDR & Local-PDR' -CShiraki Vice President-Nuclear Operation PDI-2 Reading . 0GC Long Island Lighting Company SVarga EJordan Shoreham Nuclear Power Station ~BBoger BGrimes P.O. Box 618, North Country Road WButler ACRS (10)
Wading River, NY 11792 'M0'Brien CCheng, DEST ASmith
Dear Mr. Leonard:
SUBJECT:
INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) PROBLEMS'IN BWR AUSTENITIC STAINLESS STEEL PIPING (TAC NO. M69157) j RE: SHOREHAM NUCLEAR POWER STATION' 'I The NRC is evaluating LILCo's response to Generic Letter 88-01. Enclosed arei questions that address additional information that is required to complete the review. .A formal response is requested to these questions within sixty dyas of receipt of this request. To expedite the review process, please include in the-distribution of your response, a copy. to the NRC's contractor at the following address:
Dr. Armand A. Lakner, Director Safety & Reliability Viking Systems International 101 Chestnut Street Gaithersburg, MD 20877 Sincerely,
./s/
Stewart W. Brown, Project Manager' Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear' Reactor Regulation t
Enclosure:
As-stated cc w/ enclosure:
See next page-
[LEONARDLTR] , ,
PDI-2 PDI-2/D f d SBrow : WButler O l
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Docket No. 50-322 I Mr. John D. Leonard, Jr. 4 Vice President-Nuclear Operation Long Island Lighting Company Shoreham fluclear Power Station 1 P.O. Box 618, North Country Road ;
Wading River, NY 11792 ;
Dear Mr. Leonard:
j
SUBJECT:
INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) PROBLEMS IN BWR AUSTENITIC STAINLESS STEEL PIPING (TAC NO. M69157)
RE: SH0REHAM NUCLEAR POWER STATION j The NRC is evaluating LILCo's response to Generic Letter 88-01. Enclosed are questions that address additional information that is required to complete the ,
review. A formal response is requested to these questicns within sixty days of I receipt of this request. To expedite the review process, please include in the '
distribution of your response, a copy to the NRC's contractor at the following address:
3 Dr. Armand A. Lakner, Director Safety & Reliability Viking Systems International 101 Chestnut Street Gaithersburg, MD 20877 Sincerely, h Mw Stewart W. Brown, Project Manager Project Directorate I-2 Division of Reactor Projects I/II-Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page
i O O Mr. John D. Leonard, Jr. Shoreham Nuclear Powtr Station Long Island Lighting Company 1
CC:
Victor A. Staffieri, Esq. Supervisor 4 General Counsel Town of Brookhaven Long Island Lighting Company 205 S. Ocean Ave.
175 East Old County Road Patchogue, New York 11772 Hicksville, New York 11801 l Town Attorney l W. Taylor Reveley, III, Esq. Town of Brookhaven Hunton & Williams 3232, Route 112 )
1 Post Office Box.1535 Medford, NY 11763 I 707 East Main Street !
Richmond, Virginia 23212 MHB Technical Associates 1723 Hamilton Avenue Mr. Lawrence Britt Suite K i' Shoreham Nuclear Power Station San Jose, California 95125 Post Office Box 618 Wading River, New York 11792 Richard M. Kessel Chairman & Executive Director -
Mr. John Scalice New York State Consumer Protection Plant Manager Board i Shoreham Nuclear Power Station Room 1725 Post Office Box 628 250 Broadway I Wading River, New York 11792 New York, NY 10007 .
Resident Inspector Jonathan D. Feinberg, Esq. i Shoreham NPS New York State Department }
U.S. Nuclear Regulatory Comission of Public Service Post Office Box B Three Empire State Plaza Rocky Point, New York 11778 Albany, New York 12223 Regional Administrator, Region I Gerald C. Crotty, Esq.
U.S. Nuclear Regulatory Commission Ben Wiles, Esq.
475 Allendale Road Counsel to the Governor-King of Prussia, Pennsylvania 19406 Executive Chamber ;
State Capitol .;
Ms. Donna Ross Albany, New York 12224 New York State Energy Office Agency Building 2 Herbert H. Brown, Esq.
Empire State Plaza Lawrence Coe Lanpher, Esq.
Albany, New York 12223 Karla J. Letsche, Esq.
! Kirkpatrick & Lockhart ;
- l. South Lobby - 9th Floor l 1800 M Street, N.W.
Washington, D.C. 20036-5891 ,
l ;
b l
I j
o o 1 Long Island Lighting Company Shoreham(1) i
)
cc: )
Dr. Monroe Schneider I North Shore Committee Post Office Box 231 )
Wading River, NY 11792 i Fabian G. Palomino, Esq.
Special Counsel to the Governor l Executive Chamber - State Capitol' j Albany, NY 12224 I Martin Bradley Ashare, Esq. i
~
Suffolk County Attorney H. Lee Dennison Building Veteran's Memorial Highway l J
Hauppauge NY 11788 i Robert Abrams, Esq.
Attorney General of the State l of New York I ATTN:- John Corwin, Esq.
New York State Department of Law Consumer Protection Bureau 3 120 Broadway j 3rd Floor New York, NY 10271 ]
Honorable Peter Cohalan i Suffolk County Executive l County Executive / Legislative Building i Veteran's Memorial Highway l Hauppauge, NY 11788 l
f 1
1
O O ATTACHMENT A )
GENERAL QUESTIONS / REQUESTS j 1
i Reviews of several licensee submittals has shown that most (although not
- all) of the submittals commonly lack certain information that is needed for evaluation of the submittale. Thus, this general list of questions and l requests has been prepared for submission to each of the licensees. For i those portions of this attachment for which the requested information was supplied (in the detail requested herein) in the original submittal, the utilities may reference the relevant pages or tables in the original submittal and supply only the requested information that was not provided. . Please 1 certify that you comply with NRC Staff positions in Generic Letter 88-01, '
or identify and justify any deviations taken.
1 Item 1. Position or. NRC Staff Positions l Generic I4tter 88-01 states on page 3:
I
" Pursuant to 10 CFR 50.54(f), you, as a BWR operating reactor !
licensee or construction permit holder, are requested to furnish, i under oath or affirmation, your current plans relating to piping replacement, inspection, repair, and leakage detection. Your response should indicate whether you intend to follow the staff positions included in this letter, or propose alternative j measures." j
'Ihe staff positions outid.ned in Generic Letter 88-01 includ,e positions on: (1) Materials. (2) Processes. (3) Water Chemistry. (4) Weld j Overlay. (5) Partial Replacement. (6) Stress Improvement of Cracked i Weldments. (7) Clamping Dev;tces. (8) Crack Evaluation and Repair !
Criteria. (9) Inspection Method and Personnel. (10) Inspection 1 Schedules. (11) Sample Expansion. (12) Leak Detection.- (13)
Reporting Requirements.
Please supply information concerning whether the licensees (1) endorses these positions, (2) proposes alternate positions, exceptions, or provisions, and (3) is considering or planning to apply them in the future. Please describe any alternate positions, exceptions, or provisions that are proposed.
~
Please supply this information using a table such as that illustrated in the example shown in Table 1.
9 A-1 ,
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I O o !
Table 1 Responses to NRC Staff Positions l
Licensee Response
Accept Requests {
with Alternate Applied Consider for j Staff Position Accept Provisions Position in Past Future Use
- 1. Materials
- 2. Processes
(
- 3. Water Chemistry
- 4. Weld Overlay 1
- 5. Partial Replacement
{a
- 6. Stress Improvement of f Cracked Weldments
- 7. Clamping Devices
- 8. Crack Evaluation and I j
Repair Criteria 1 l
- 9. Inspection Method and Personnel
- 10. Inspection Schedules
- 11. Sample Expansion
- 12. Leak Detection
- 13. Reporting Requirements Answer with "yes", " check mark" or "X" in appropriate column for each of the 13 NRC Staff Positions. List and explain each provision and/or alternate position (or reference original submittal if it contains the listing and explanation). Use separate page(s) if needed.
- Answer with "yes" or "no", as appropriate, in each column for each of 13 NRC Staff Positions. '
l A-2 9
9
____._________m _ _ . _ _ _ _
O O ATTACHMENT A (continued)
Item 2. Inservice Inspection Pronram Generic Letter 88-01 requests on page 3:
"Your current plans regarding pipe replacement and/or other measures taken or to be taken to mitigate IGSOC and provide assurance of continued long-term integrity and reliability."
"An Inservice Inspection Program to be implemented at the next refueling outage for austenitic stainless steel piping covered under the scope of this letter that conforms to the staff positions on inspection schedules methods and personnel, and sample expansion included in this letter."
The information pertaining to the pipe replacement and other mitigating actions as well as the Inservice Inspection Program provided in most of the licensee submittals were either incomplete or did not provide the background data that is needed to evaluate the ISI Program such as (1) reasons / justification for IGSOC classification of welds, (2) methods, personnel qualification, schedules and identities of welds inspected, and (3) results of previous inspections, and/or identities of welds to be inspected during future inspections.
Thus, the following information is requested:
- 1. A listing of all welds by system, pipe size, configuration (e.g., pipe to elbow, pipe to valve, etc.), drawing number (piping ISO with weld I.D.), location (i.e., inside or outside of containment, etc.), weld I.D. number, and IGSOC classification (i.e. IGSCC Category A, B, C, D, E, F and G).
- 2. Reason / justification for the classification of each weld, using such information as (a) weld history such as heat sink welding (HSW), (b) pipe and weld metal compositions or material identities to show either conforming material or non-conforming material, (c) mitigating treatment (s) applied such as solution ;
heat treating (SHT), stress improvement (IHSI or MSIP).
- 3. Identity of welds to be inspected during past and future refueling outage. Include (a) dates and results of previous inspections, (b) flaw characteristics including orientation (axial or circumferential), maximum length, maximum depth, repairs and/or mitigating treatments applied.
Please supply this information in tabular form using formats such as that illustrated in Tables 2 and 3.
\
A-3 l
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. Table 2 ,
History of Welds and Prior Mitigating Actions / Treatments
IGSCC Weld Dia. Casting Treatment *** j Caten System Number Configuration Inch Foraina. Pipe Weld SHT HWS CRC jg[ 0.L. i
)
Notes:
List each weld separately, using one or more lines as required.
- For materfs1: identify as non-conforming or conforming as appropriate concerning whether it conforms with the NRC Staff 1 position on resistant materials. If conforming, identify the f material type (e.g., Type 316 NG). j 1
- For treatment: list "X" under appropriate column (s) if weld was treated using indicated technique, i.e., solution heat treated (SHT), heat sink welded (HSW), corrosion resistant clad (CRC),
stress improved (SI), or overlayed (0.L.). For SI, add )'
explanation of method used, i.e., whether by induction heating or mechanical, whether pre and/or post treatment inspection was ,
applied using methods and personnel qualified under NRC/EPRI/BWROG !
coordination plan, and whether treatment was applied within two l years of service date. Also add explanation and justification i of any overlays that were not standard (per NRC Staff position). 1 l
l l
s A-4 I
Y
l O O i
. Table 3 )
Inspection Schedules Inspected /To Be Inspected / Flaws Found ICSCC Weld Dia. Past Future Caten System No. Inch. Configuration R.O.dX-2 R.O.fX-1 Flaw R.O.fX R.O.fX+1
']
i
)
Instructions:
- 1. Under the heading, " Inspected /To BE Inspected," use as many columns as required to describe the followings (a) All previous inspections that were conducted (per NUREG ,
0313. Revision 2, page 5.2) using methods and personnel l qualified under NRC/EPRI/BWROG coordination plan as i upgraded in September,1985. j plus (b) A sufficient number of future inspections to demonstrate that the schedules will follow the NRC Staff positions as given in Table 1 in Generic b tter 88-01,
- 2. Replace R.O.i (X-2, X-1, X, X+1) with actual refueling outage numbers. Indicate dates inspections were/will be performed.
- 3. List each weld within the scope of Generic Letter 88-01.
- 4. Place an "X" or other appropriate symbol under the appropriate column for each refueling outage for which that weld was inspected or will be inspected.
- 5. Indicate with'"yes" under column marked " flaw" if a flaw indication was found. Attach a statement for each flawed weld giving the orientation (altial or circumferential), the dimensions (maximum length and depth), and describing any repairs made.
A-5
O- O ATTACHMENT A (continued)
Ites 3. Welds covered in Licensee Submittal Generic Intter 88-01 (on page 2) states:
"This Generic 14tter applies to all BWR piping ande of sustenitic stainless steel that is four inches or larger in nominal diameter and contains reactor coolant at a temperature above 200*F during power operation regardless of Code classification. It also applies to reactor vessel attachments and appurtenances such as jet pump instrumentation penetration assemblies and head spray and vent components."
Were any welds that fall within this defined scope excluded from the licensee submittal (for example, welds in the RWCU outboard of the isolation valves)? If previously excluded, pleaue list identity of such welds and plans for mitigation and inspections in Tables 2 and 3 or provide alternative proposal. If ICSCC susceptible welds were excluded from the licensee submittal based on temperature considerations please identify the welds and describe in detail the method of temperature measurements.
Ites 4. Welds that Are Not UT Inspectable Generic Letter 88-01 (in Table 1) states: " Welds that are not UT inspectable should be replaced, " sleeved", or local leak detection applied. RT examination or visual inspection for leakage may also be considered."
Does the licensee submittal include discussions and plans fort (a) All welds that are inaccessible for ITT ir.spections?
(b) All welds that are only partis 11y accessible for Iff inspections?
(c) Welds that cannot be ITT inspected because of geometrical constraints or other reasons.
If not, please list these welds and plans for mitigation / inspection.
Item 5. Leakene Detection Generic I4tter 88-01 states on page 3: .
" Confirmation of you plans to ensure that the Technical A-6
O O ATtACIMENT A (continued)
Specification related to leakage detection will be in conformance with the staff position on leak detection included in this letter."
)
The staff position is outlined on pages 5 and 6 of Generic Letter i 88-01 and include the followiag items:
l
- 1. Leakage detection should be in conformance with Position C of Regulatory Guide 1.45 " Reactor Coolant Pressure Boundary Leakage Detection Systems," or as otherwise approved by the NRC.
- 2. Plant shutdown should be initiated for corrective action when:
(a) within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period any leakage detection system indicates an increase of unidentified leakage in excess of 2 spa or its equivalent, or i (b) the total unidentified leakage attains a rate of 5 gpa or equivalent.
- 3. Leakage should be monitored (or determined from flow measurements if flow is continuously monitored) at approximately f four hour intervals or less. ,
l
- 4. Unidentified leakage should ir.clude all leakage other than i (a) leakage into closed systems, or l j
i (b) leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with operations of monitoring systems or not to be from a throughwall crack.
- 5. For plants operating with any IGSCC Category D, E', F, or G welds, at least one of the leakage measurement instruments ;
associated with each sump shall be operable, and the outage time for inoperable instruments shall be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> i or immediately initiate an orderly shutdown.
Although most licensee submittels describe'the intention of meeting some or all of these requirements or offer alternative measures, it is not always clear whether these requirements are contained in '
the Technical Specifications. Thus it is requested that this information should be provided by each licensee. For clarity and completeness, please use a checklist such as that illustrated in Table 4 A-7 .
V
i
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Table 4 Licensee Positions on Leakage Detection i 1
Already TS will be Alternate Contained Changed Position i Position in TS to Include Proposed l 1
- 1. Conforms with Position C of a Regulatory Guide 1.45 1
- 2. Plant shutdown should be I initiated when:
(a) within any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l or less, an increase is 1 indicated in the rate of !
unidentified leakage in excess of 2 gpm, or ,
(b) the total unidentified leakage attains a rate of 5 sps.
- 3. Leakage monitored at four hour intervals or less.
- 4. Unidentified leakage includes all except:
(a) leakage into closed systems, or (b) leakage into the containment atmosphere from sources that are located, do not interfere i with monitoring systems, or not from throughwall crack.
- 5. Provisions for shutdown within 24 ;
hours due to inoperable measurement instruments in plants with Category D, E. F, or G welds.
Instructions:
Place "X" or "yes" under appropriate column for each item. Provide description and justification for alternative positions if not already provided.
i O
9 A-8
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. ATTACSGDIT B REQUEST FOR ADDITIONAL INFORMATION PERTAINING 10 SHOREHAM, UNIT 1 Ites 1. Inservice Inspection and Mitimatian Treatments In responding to Item 2 of Attachment A:
I (a) Please note that the tables listing of~ welds in the IGSOC ,,
ISI plan which were previously submitted do not contain=
piping or weld compositions. Please include these.in your reply.
(b) Please supply justification for the IGSCC Category B classifiestions applied to welds that were treated with IHSI in terms of the dates of application of the IHSI treatmente (recalling that the treatements must be applied within two years of operation to be classisifed as IGSCC Category B) and the limited number (17) of post-IHSI inspections (recalling that all IHSI-treated welds must -
be inspected to be classified as IGSCC Category B unless
~ the treatments were applied prior to operation).
l (c) Please note that specific refueling outages when welds are to be inspected were not included in the submittal. Nor were plans included for IGSCC Category B welds after the first refueling outage.
(d) Please justify the "not applicable" assignments to welds containing Inconel, noting that all Inconal alloys are I specifically covered in Generic Intter 88-01 and that only - '
Inconel 82 is considered resistant. Also please include I
page B - 1 i i
1r
O O ATTAC} MENT B (continued) i inspection plans for these welds.
Item 2. Uninspectable Welds In responding to Item 4 of Attachment A, recall that expected UT i inspectability of several welds was less than 100%. In particular expected per cent ITT coverage for some of the welds was about 65%
of less. Please list plans, other that UT inspection of these welds or provide justification for limiting the inspections to UT.
S l _
1 1
page B - 2 i