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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M8771999-10-25025 October 1999 Requests That Industry Studies on long-term Spent Fuel Pool Cooling Be Provided to R Dudley at Listed Mail Stop ML20217M4331999-10-19019 October 1999 Submits Rept 17, Requal Tracking Rept from Operator Tracking Sys. Rept Was Used by NRC to Schedule Requalification Exams for Operators & Record Requal Pass Dates ML20217F5841999-10-13013 October 1999 Requests Revocation of License OP-11038-1 for GE Kingsley. Individual Has Been Reassigned to Position within Naesco ML20217F5811999-10-13013 October 1999 Forwards Insp Data & Naesco Evaluation of a EDG Exhaust Insp Conducted on 990407.Insp Ensured That Unacceptable Wall Thinning Will Not Occur During 40-year Design Lifetime of Sys ML20217C7321999-10-0808 October 1999 Forwards Copy of Seabrook Station Videotape Entitled, Completion of Seal Barrier Installation. Videotape Documents Process of Selecting,Designing & Installing Seal Deterrent Barrier to Preclude Entrapment of Seals ML20217B8621999-10-0505 October 1999 Forwards Rev 28,change 1 to EPIP Er 1.1, Classification & Emergencies, Per 10CFR50.54(q).Rev to Procedure Does Not Decrease Effectiveness of Seabrook Station Radiological Emergency Plan ML20217B7471999-10-0101 October 1999 Provides Notification of Change in PCT of More than 50 F,Per Requirements of 10CFR50.46(a)(3)(i),(ii).Tabulation of Large Break LOCA PCT Margin Utilization Applicable to Seabrook Station,Encl ML20212J8271999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Seabrook Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Info & to Plan for Insp Activities at Facility Over Next Six Months.Plant Issues Matrix & Insp Plan Encl ML20216J2381999-09-30030 September 1999 Responds to Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Nrc Expects All Licensees to Operate Nuclear Facilities Safety IAW NRC Regulations & Requirements ML20216J2421999-09-30030 September 1999 Responds to Card Received in Aug 1999,providing Comments on NRC Interim Enforcement Policy Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Informs That Naesc Reported Seabrook as Y2K Ready Prior to 990701 ML20216J2471999-09-30030 September 1999 Responds to Which Provided Comments on NRC Interim Enforcement Policy Re Enforcement Discretion for Nuclear Plants During Y2K Transition.Informs That Naesc Reported Seabrook as Y2K Ready Prior to 990701 ML20212K7921999-09-30030 September 1999 Confirms 990922 Telcon with J D'Antonio & T Grew Re Arrangements Made for NRC to Inspect Licensed Operator Requalification Program at Seabrook Facility ML20212J0301999-09-24024 September 1999 Forwards Insp Rept 50-443/99-10 on 990726-30 & 0809-13.No Violations Noted.Insp Discussed ML20212G5071999-09-21021 September 1999 Submits Complaint to NRC Re NRC Failure to Cite Seabrook Station NPP Operators for Failing to Periodically Calibrate & Establish Adequate Measures to Insure That Relay Equipment Met All Required Calibration Settings Prior to Installation ML20212C1881999-09-20020 September 1999 Ack Receipt of Which Raised Concerns Re NRC Enforcement Actions at Plant & Issuance of NCVs ML20212D1401999-09-17017 September 1999 Forwards SE Accepting Request to Use Proposed Alternative to Certain Weld Repair Requirements in ASME Boiling & Pressure Vessel Code ML20212B9511999-09-17017 September 1999 Forwards NRC Form 396 for MG Sketchley,License SOP-10685, Along with Supporting Medical Exam Info.Nrc Form 396 Has Been Superceded by Revised Version Dtd 971222,which Was Previously Submitted to NRC on 990812.Encl Withheld ML20212C3621999-09-15015 September 1999 Forwards Rev 34 to Seabrook Station Radiological Emergency Plan & Rev 85 to Seabrook Station Emergency Response Manual, Per 10CFR50,App E & 10CFR50.4 ML20212B5021999-09-14014 September 1999 Forwards Licensee Responses to EPA Questions Re Plant Seal Deterrent Barrier.Util Completed Installation of Subject Barriers on All Three Station Offshore Intake Structures on 990818.Barriers Will Preclude Entrapment of Seals ML20211Q8521999-09-0808 September 1999 Informs That Rl Couture,License SOP-11027,terminated Employment at Naesco on 990907.Revocation of License Requested ML20211N8781999-09-0303 September 1999 Forwards Response to 990820 RFI Re NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211J9291999-09-0303 September 1999 Forwards mark-ups & Retypes of Proposed Conforming License Changes Required in Connection with Transfers Being Sought in 990615 Application of Montaup Electric Co & New England Power Co for Transfer of Licenses & Ownership Interests ML20211M3221999-09-0202 September 1999 Responds to NRC Re Violations Noted in Insp of License NPF-86 & Proposed Imposition of Civil Penalty. Corrective Actions:Conducted Prompt Review of Layoff Decision to Determine Relevant Facts DD-99-10, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-10) Expired.Commission Declined Review & Decision Became Final on 990830.With Certificate of Svc.Served on 9909021999-09-0202 September 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-10) Expired.Commission Declined Review & Decision Became Final on 990830.With Certificate of Svc.Served on 990902 ML20211J8811999-09-0101 September 1999 Forwards Comments on Seabrook Station Review of Reactor Vessel Integrity Database (Rvid)(Version 2).Minor Discrepancies Were Noted.Proposed Changes Are Encl in Order to Correct Discrepancies ML20211J8411999-09-0101 September 1999 Forwards Updated NRC Form 396 for E Decosta,Nrc License OP-10655-1.Without Encl ML20211G9191999-08-27027 August 1999 Informs NRC That Name of New Company, Ref in Order Approving Application Re Corporate Merger Is Nstar Which Is Massachusetts Business Trust ML20211J0401999-08-26026 August 1999 Responds to 990819 Request,On Behalf of Gr Pageau & Williams Power Corp,For Addl Time in Which to Reply to Nov,Issued on 990803.Response Due to NRC by 991008 ML20211H0651999-08-25025 August 1999 Forwards Insp Rept 50-443/99-05 on 990621-0801.One Violation Re Failure to Include Multiple Components within Scope of ISI Test Program Was Identified & Being Treated as NCV, Consistent with App C of Enforcement Policy ML20211G7761999-08-24024 August 1999 Expresses Great Concern Re Lack of Enforcement Actions Against Seabrook Station Despite Citations NRC Has Issued for Violations of Seabrook Operating License ML20211J2171999-08-23023 August 1999 Expresses Disappointment with Lack of Enforcement Action Against Seabrook Station Despite Repeated Safety Violations ML20211J4971999-08-21021 August 1999 Submits Comments Re Violations Cited in Early Mar & 990509 Insps ML20211H8361999-08-19019 August 1999 Submits Concerns Re Violations at Seabrook Station ML20211F2681999-08-19019 August 1999 Discusses Former Chairman Jackson & 990602 Predecisional Enforcement Conference Re Findings of Ofc of Investigations Involving Allegations Raised by Contract Electrician.Determined That Allegations Not Supported ML20211J3241999-08-15015 August 1999 Expresses Disappointment in Apparent Failure of NRC to Cite Seabrook Station NPP for Recent Violations of Safety Regulations Uncovered During Recent Insps in Mar & May ML20211J1831999-08-15015 August 1999 Submits Concerns Over Serious Deficiencies at Seabrook Station That NRC Has Declined to Take Enforcement Actions Against ML20210T1601999-08-13013 August 1999 Informs That as Result of Staff Review of Licensee Responses to GL 92-01,rev,supp1 1, Reactor Vessel Structural Integrity, NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2 ML20211J2071999-08-13013 August 1999 Expresses Concerns Re Violations Occurring Recently at Seabrook Nuclear Power Station.Requests Effort to See That Measures Taken to Stop Flagrant,Continuing Violations That Hold Danger to Workers & Community ML20210S9611999-08-13013 August 1999 Informs That NRC Received Encl Ltr from Pb Johnston Expressing Concern About Certain Impacts on Shareholders of New England Electric Sys with Respect to Nees Proposed Merger with Natl Grid Group ML20210S9511999-08-13013 August 1999 Responds to to Collins Expressing Concerns with Certain Terms of Proposed Merger Between New England Electric Sys & National Grid Group.Nrc Has No Authority to Interject Itself in Nees Merger with National Grid Group ML20210S2001999-08-12012 August 1999 Forwards NRC Forms 398 & 396 in Support of Applications for Renewal of Operator Licenses for Individuals Listed Below. Without Encls ML20210R8401999-08-11011 August 1999 Forwards Response to NRC Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20210S7331999-08-11011 August 1999 Submits Third Suppl to 980423 Application to Renew NPDES Permit NH0020338 for Seabrook Station.Suppl Provides Addl Info on Input Streams & Requests Increased Permit Limit for Chemical Used in Makeup Water Treatment Sys ML20210R9581999-08-11011 August 1999 Forwards ISI Exam Rept of Seabrook Station, for RFO 6, Period 3,for Insps Conducted Prior to & During Sixth Refueling Outage Concluded on 990510 ML20210Q7441999-08-11011 August 1999 Forwards Order Approving Indirect Transfer of Control of Canal Interest in Seabrook Station Unit 1 as Requested in Application & SER ML20210R7931999-08-10010 August 1999 Forwards Cycle 7 Startup Rept for Seabrook Station, IAW Requirements of TS 6.8.1.1 ML20210N9421999-08-0505 August 1999 Informs That North Atlantic Suggests Listed Revisions to 990730 Draft Revisions to Committee Rept & Order.Further Revs Consistent with What North Atlantic Proposed at 990608 Hearing ML20210N5721999-08-0303 August 1999 Discusses Investigations Rept 1-98-005 Conducted by OI at Naesco,Seabrook Station & Forwards NOV & Proposed Imposition of Civil Penalty - $55,000.Violation Re Failure to Promptly Correct Incorrectly Terminated Cables of Control Bldg Air ML20210P3361999-08-0303 August 1999 Discusses Investigation Rept 1-98-005 Conducted by Region I OI at Naesco,Seabrook Station & Forwards Nov.Violations Re Electrical Wiring in Control Panel for Control Bldg Air Conditioning Sys ML20210P3161999-08-0303 August 1999 Discusses Investigation Rept 1-98-005,conducted Between 980129 & 0527 at Seabrook Station & Forwards Nov.Violation Re Discrimination of Williams Power Corp,Contractor of Naesco,Against Electrician for Raising Safety Issues 1999-09-08
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217N4611999-10-22022 October 1999 Forwards Revised Pages 11,14 & 71 of Rept & Order Dtd 990608.Revs Are Textual Changes to Clarify & Confirm Action Taken by Nuclear Decommissioning Financing Committee ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20210K4141999-08-0404 August 1999 Forwards Signed Originals of DD Issued Under 10CFR2.206. Without Encl ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20206U9631999-05-18018 May 1999 Notification of Significant Licensee Meeting 99-27 with Util on 990602 to Discuss Predecisional Enforcement Conference - NRC Investigation ML20206R1691999-05-0707 May 1999 Rev 1 to Notification of 990602 Significant Licensee Meeting with Listed Attendees in King of Prussia,Pa Re Predecisional Enforcement Conference Concerning NRC Investigation.Rev Sighted Date Change ML20207G5681999-03-0808 March 1999 Informs That Commission Memorandum & Order (CLI-99-06), Issued on 990305,appointed TS Moore as Presiding Officer for Seabrook License Transfer Proceeding.With Certificate of Svc.Served on 990309 ML20197H1211998-12-0808 December 1998 Forwards Exam Rept with as Given Written Exam for Test Administered at Facility on 981019-23 ML20195C7641998-11-13013 November 1998 Forwards Pages That Were Faxed to J Peschel on 981113 in Preparation for Telcon That Will Be Scheduled Wk of 981116. Info in Attached Pages Based on Info Obtained from Licensee & Includes Specific Subjects to Be Discussed with Licensee ML20153E4211998-09-24024 September 1998 Informs That Ofc of Secretary Experienced Problems with Listed e-mail Address.Alternate Mailbox Has Been Created in Effort to Maintain Electronic Mailbox for Parties Filing by e-mail.With Certificate of Svc.Served on 980924 ML20153G0231998-09-24024 September 1998 Informs That Office of Secretary Experienced Problems with Dedicated e-mail Address.In Effort to Maintain Electronic Mailbox for Parties Filing by e-mail,alternate Mailbox Created.With Certificate of Svc.Served on 980924 ML20239A3361998-09-0404 September 1998 Forwards Request for Hearing & Submitted by RA Backus on Behalf of Seacoast Anti-Pollution League & New England Coalition on Nuclear Pollution Re Proposed License Amend for Seabrook Unit 1 ML20249A6691998-06-15015 June 1998 Forwards Request for Hearing, & Submitted by RA Backus on Behalf of Seacoast Anti-Pollution League. Petition Was Filed in Response to Notice of Proposed Determination by Staff ML20217M7161998-04-0303 April 1998 Notification of 980219 Meeting W/North Atlantic Energy Svc Corp in Rockville,Md to Discuss Great Power Corp Response to RAI Re Decommissioning Funding Assurance ML20216G5891998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-25 W/Util on 980324 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Rept 50-443/97-08 (EA-98-073) ML20198S4161998-02-26026 February 1998 Submits Impact of New Decommissioning Funding Rule on Great Bay.Staff Intends to Propose Some Addl Mechanisms That Appear to Offer Assurance Equivalent to What Existing Mechanisms Provide ML20203B9021998-02-0909 February 1998 Notification of 980219 Meeting W/North Atlantic Energy Service Corp in North Bethesda,Md to Discuss Proposed License Amends to Support Current Operating Cycle & Plans for Conversion to Improved Standard TSs ML20199E8881998-01-23023 January 1998 Notification of 980204 Mgt Meeting W/North Atlantic Energy Svc Corp in Rockville,Maryland to Discuss SALP for Period Covering 960505-971206 as Documented in SALP Rept 50-443/97-99 ML20198N0191998-01-0909 January 1998 Forwards Draft Rept, ,to Docket for Seabrook Station,Unit 1.Draft Rept Provides Licensee Preliminary Root Cause Analysis for Leaks in Piping of B Train of RHR System.Leakage Reported by Licensee on 971205 ML20203D2971997-12-0909 December 1997 Notification of 971216 Meeting W/Utils in Rockville,Md to Discuss Decommissioning Funding Assurance ML20211E7301997-09-23023 September 1997 Notification of 971028 Meeting W/North Atlantic Energy Service Corp in Rockville,Md to Discuss Approach for Extending Surveillances to 24-month Intervals ML20217B0471997-09-11011 September 1997 Notification of 970924 Meeting W/Eastern Utility Associates & North Atlantic Energy Service Corp in Rockville,Md to Discuss Proposed Electric Generating Asset Divestiture Plan ML20141D8191997-06-26026 June 1997 Forward 970624 Memo from P Milano to C Hehl Re Response to TIA Concerning Vantage 5H ZIRLO Fuel Problems at Plant,To Be Placed on Docket 50-443 & Made Publicly Available ML20141C9921997-06-24024 June 1997 Responds to 970605 TIA Re VANTAGE-5H ZIRLO Fuel Problems at Seabrook.Staff Has Not Identified Any Restart Concerns Re Reloading of VANTAGE-5H ZIRLO Fuel Used During Cycle 5 & W/Fresh VANTAGE-5H ZIRLO Fuel for Cycle 6 at Plant ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134H7931996-11-0606 November 1996 Partially Deleted Memo Re 950502 Meeting W/Northeast Utilities Re Listed Topics ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20129C0271996-10-11011 October 1996 Notification of 961030 Public Meeting of Nuclear Decommissioning Committee ML20129E2011996-09-25025 September 1996 Notification of 960930 Meeting W/Util in Rockville,Md to Discuss Status of Great Bay Power Corp as Electric Util ML20147J3281996-07-10010 July 1996 Discusses Staff Response to SRM M960612, Briefing on Part 100 Final Rule on Reactor Site Criteria. Staff Believes That Draft Final Rule Language May Be Misinterpreted as Implicity Overruling in Conflict W/Seabrook Decision ML20129D1831996-07-10010 July 1996 Informs of 960716 Visit W/B Patricelli,Cm Cleveland & Gw Davis of Northeast Utilities,Inc Re Introductions & Discussions of Millstone Point & Haddam Neck Issues ML20134B6681995-10-13013 October 1995 Forwards Briefing Package on Status of Listed Plant Units,As Background for Visit by Northeast Utils on 951018-19 ML20087B8531995-07-25025 July 1995 Forwards State of Nh Nuclear Decommissioning Finance Committee Third Supplemental Order Approving Revised Funding Schedule by North Atlantic Energy Svc Corp ML20134B5861995-06-0101 June 1995 Forwards Briefing Package on Status of Plants as Background for Util Visit on 950608 ML20134B5721995-04-26026 April 1995 Forwards Briefing Package on Status of Listed Plants,As Background for Visit by Util on 950502.Supporting Documentation Encl ML20078S9391994-12-23023 December 1994 Forwards State of Nh Nuclear Decommissioning Finance Committee (Ndfc) Ndfc 93-1, Brief of Nh Public Utilities Commission Staff NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B4931994-02-16016 February 1994 Forwards Updated Briefing Package for Visit by Util Officials W/Nrc Chairman,Commission,Edo,Director OI & Director Oe.Requests Replacement of Encls 1 & 2 in 940215 Package,Retaining Supporting Attachment 1 Documentation ML20059J8371994-01-0606 January 1994 Notification of Significant Licensee Meeting 94-05 W/Util Emergency Preparedness Mgt Working Group on 940210 ML20058L9281993-12-15015 December 1993 Notification of 931221 Meeting W/North Atlantic Energy Svc Corp,Yaec & Intl Tech Svcs,Inc in Rockville,Md to Discuss Application of YAEC-1856P Methodology to Plant ML20058C9681993-11-19019 November 1993 Notification of Significant Licensee Meeting 93-147 W/Util on 931208 Re SALP Mgt Meeting for Period of 920301-930828 ML20059J2321993-11-0505 November 1993 Forwards Safety Evaluation Accepting LAR 92-14,submitted Via for TS Changes to Allow Independent Fixed Incore Detector Sys at Facility to Be Used for Periodic in-core Power Distribution TS SRs ML20128K8601993-02-0202 February 1993 Notification of Significant Licensee Meeting 93-13 W/Util on 930210 to Discuss General Engineering Programs ML20126K1461993-01-0505 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Transfer of Control of Interest of Eua Power in Plant ML20126J6211992-12-24024 December 1992 Forwards LER 88-009-01 Issued on 921113,discussing Increased Thrust Bearing Loading for RHR Pumps When Pumps Run at Reduced Flows.Concern Raised That Inservice Testing May Not Detect Problem Soon Enough to Avoid Failure ML20125B4461992-11-30030 November 1992 Notification of 921203 Licensee Meeting in King of Prussia, PA to Discuss Auxiliary Operator re-licensing Plans ML20128C2131992-11-16016 November 1992 Notification of Postponement of 921124 Meeting W/Util in King of Prussia,Pa to Discuss Process for Reissuing Reactor Operator Licenses Terminated After Auxiliary Operator Performance Review ML20128C0271992-11-13013 November 1992 Notification of Significant Licensee Meeting 92-168 W/Util on 921124 to Discuss Process for Reissuing RO Licenses That Have Been Terminated After an AO Performance Review ML20097B5821992-05-27027 May 1992 Recommends That Methodology Specified in Order 20,475 Be Revised to Require Util to Include in Base Rates,Amounts Required by Nuclear Decommission Financing Committee 17th Supplemental Order 1999-09-16
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217N4611999-10-22022 October 1999 Forwards Revised Pages 11,14 & 71 of Rept & Order Dtd 990608.Revs Are Textual Changes to Clarify & Confirm Action Taken by Nuclear Decommissioning Financing Committee ML20217J8951999-10-21021 October 1999 Staff Requirements Memo Re Affirmation Session on 991021, Rockville,Md (Open to Public Attendance) ML20216F5061999-09-16016 September 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petitions as of 990831.During August,Director'S Decision (DD-99-10) on Seabrook Issued & Petition Closed.Six Petitions Open,Five in NRR & One in Nmss.Attachment 2 Withheld ML20210K4141999-08-0404 August 1999 Forwards Signed Originals of DD Issued Under 10CFR2.206. Without Encl ML20210C1631999-07-19019 July 1999 Forwards Monthly Rept Which Gives Status of 10CFR2.206 Petitions as of 990630.Six Open NRR,1 OE & 2 NMSS Petitions Available.Attachment 2 Withheld ML20206U9631999-05-18018 May 1999 Notification of Significant Licensee Meeting 99-27 with Util on 990602 to Discuss Predecisional Enforcement Conference - NRC Investigation ML20206R1691999-05-0707 May 1999 Rev 1 to Notification of 990602 Significant Licensee Meeting with Listed Attendees in King of Prussia,Pa Re Predecisional Enforcement Conference Concerning NRC Investigation.Rev Sighted Date Change ML20207G5681999-03-0808 March 1999 Informs That Commission Memorandum & Order (CLI-99-06), Issued on 990305,appointed TS Moore as Presiding Officer for Seabrook License Transfer Proceeding.With Certificate of Svc.Served on 990309 ML20207F5021999-03-0505 March 1999 Staff Requirements Memo Re 990305 Affirmation Session, Rockville,Md (Open to Public Attendance).Commission Approved Memo & Order Which Granted Util Intervention Petition & Request for Hearing ML20197H1211998-12-0808 December 1998 Forwards Exam Rept with as Given Written Exam for Test Administered at Facility on 981019-23 ML20195C7641998-11-13013 November 1998 Forwards Pages That Were Faxed to J Peschel on 981113 in Preparation for Telcon That Will Be Scheduled Wk of 981116. Info in Attached Pages Based on Info Obtained from Licensee & Includes Specific Subjects to Be Discussed with Licensee ML20153G0231998-09-24024 September 1998 Informs That Office of Secretary Experienced Problems with Dedicated e-mail Address.In Effort to Maintain Electronic Mailbox for Parties Filing by e-mail,alternate Mailbox Created.With Certificate of Svc.Served on 980924 ML20153E4211998-09-24024 September 1998 Informs That Ofc of Secretary Experienced Problems with Listed e-mail Address.Alternate Mailbox Has Been Created in Effort to Maintain Electronic Mailbox for Parties Filing by e-mail.With Certificate of Svc.Served on 980924 ML20239A3361998-09-0404 September 1998 Forwards Request for Hearing & Submitted by RA Backus on Behalf of Seacoast Anti-Pollution League & New England Coalition on Nuclear Pollution Re Proposed License Amend for Seabrook Unit 1 ML20249A6691998-06-15015 June 1998 Forwards Request for Hearing, & Submitted by RA Backus on Behalf of Seacoast Anti-Pollution League. Petition Was Filed in Response to Notice of Proposed Determination by Staff ML20217M7161998-04-0303 April 1998 Notification of 980219 Meeting W/North Atlantic Energy Svc Corp in Rockville,Md to Discuss Great Power Corp Response to RAI Re Decommissioning Funding Assurance ML20216G5891998-03-0606 March 1998 Notification of Significant Licensee Meeting 98-25 W/Util on 980324 Predecisional Enforcement Conference to Discuss Apparent Violation in Insp Rept 50-443/97-08 (EA-98-073) ML20198S4161998-02-26026 February 1998 Submits Impact of New Decommissioning Funding Rule on Great Bay.Staff Intends to Propose Some Addl Mechanisms That Appear to Offer Assurance Equivalent to What Existing Mechanisms Provide ML20203B9021998-02-0909 February 1998 Notification of 980219 Meeting W/North Atlantic Energy Service Corp in North Bethesda,Md to Discuss Proposed License Amends to Support Current Operating Cycle & Plans for Conversion to Improved Standard TSs ML20199E8881998-01-23023 January 1998 Notification of 980204 Mgt Meeting W/North Atlantic Energy Svc Corp in Rockville,Maryland to Discuss SALP for Period Covering 960505-971206 as Documented in SALP Rept 50-443/97-99 ML20198N0191998-01-0909 January 1998 Forwards Draft Rept, ,to Docket for Seabrook Station,Unit 1.Draft Rept Provides Licensee Preliminary Root Cause Analysis for Leaks in Piping of B Train of RHR System.Leakage Reported by Licensee on 971205 ML20203D2971997-12-0909 December 1997 Notification of 971216 Meeting W/Utils in Rockville,Md to Discuss Decommissioning Funding Assurance ML20211E7301997-09-23023 September 1997 Notification of 971028 Meeting W/North Atlantic Energy Service Corp in Rockville,Md to Discuss Approach for Extending Surveillances to 24-month Intervals ML20217B0471997-09-11011 September 1997 Notification of 970924 Meeting W/Eastern Utility Associates & North Atlantic Energy Service Corp in Rockville,Md to Discuss Proposed Electric Generating Asset Divestiture Plan ML20141D8191997-06-26026 June 1997 Forward 970624 Memo from P Milano to C Hehl Re Response to TIA Concerning Vantage 5H ZIRLO Fuel Problems at Plant,To Be Placed on Docket 50-443 & Made Publicly Available ML20141C9921997-06-24024 June 1997 Responds to 970605 TIA Re VANTAGE-5H ZIRLO Fuel Problems at Seabrook.Staff Has Not Identified Any Restart Concerns Re Reloading of VANTAGE-5H ZIRLO Fuel Used During Cycle 5 & W/Fresh VANTAGE-5H ZIRLO Fuel for Cycle 6 at Plant ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20134H7931996-11-0606 November 1996 Partially Deleted Memo Re 950502 Meeting W/Northeast Utilities Re Listed Topics ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20129C0271996-10-11011 October 1996 Notification of 961030 Public Meeting of Nuclear Decommissioning Committee ML20129E2011996-09-25025 September 1996 Notification of 960930 Meeting W/Util in Rockville,Md to Discuss Status of Great Bay Power Corp as Electric Util ML20147J3281996-07-10010 July 1996 Discusses Staff Response to SRM M960612, Briefing on Part 100 Final Rule on Reactor Site Criteria. Staff Believes That Draft Final Rule Language May Be Misinterpreted as Implicity Overruling in Conflict W/Seabrook Decision ML20129D1831996-07-10010 July 1996 Informs of 960716 Visit W/B Patricelli,Cm Cleveland & Gw Davis of Northeast Utilities,Inc Re Introductions & Discussions of Millstone Point & Haddam Neck Issues ML20134B6681995-10-13013 October 1995 Forwards Briefing Package on Status of Listed Plant Units,As Background for Visit by Northeast Utils on 951018-19 ML20087B8531995-07-25025 July 1995 Forwards State of Nh Nuclear Decommissioning Finance Committee Third Supplemental Order Approving Revised Funding Schedule by North Atlantic Energy Svc Corp ML20134B5861995-06-0101 June 1995 Forwards Briefing Package on Status of Plants as Background for Util Visit on 950608 ML20134B5721995-04-26026 April 1995 Forwards Briefing Package on Status of Listed Plants,As Background for Visit by Util on 950502.Supporting Documentation Encl ML20078S9391994-12-23023 December 1994 Forwards State of Nh Nuclear Decommissioning Finance Committee (Ndfc) Ndfc 93-1, Brief of Nh Public Utilities Commission Staff NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20134B4931994-02-16016 February 1994 Forwards Updated Briefing Package for Visit by Util Officials W/Nrc Chairman,Commission,Edo,Director OI & Director Oe.Requests Replacement of Encls 1 & 2 in 940215 Package,Retaining Supporting Attachment 1 Documentation ML20059J8371994-01-0606 January 1994 Notification of Significant Licensee Meeting 94-05 W/Util Emergency Preparedness Mgt Working Group on 940210 ML20058L9281993-12-15015 December 1993 Notification of 931221 Meeting W/North Atlantic Energy Svc Corp,Yaec & Intl Tech Svcs,Inc in Rockville,Md to Discuss Application of YAEC-1856P Methodology to Plant ML20058C9681993-11-19019 November 1993 Notification of Significant Licensee Meeting 93-147 W/Util on 931208 Re SALP Mgt Meeting for Period of 920301-930828 ML20059J2321993-11-0505 November 1993 Forwards Safety Evaluation Accepting LAR 92-14,submitted Via for TS Changes to Allow Independent Fixed Incore Detector Sys at Facility to Be Used for Periodic in-core Power Distribution TS SRs ML20128K8601993-02-0202 February 1993 Notification of Significant Licensee Meeting 93-13 W/Util on 930210 to Discuss General Engineering Programs ML20126K1461993-01-0505 January 1993 Notification of 930106 Meeting W/Util in Rockville,Md to Discuss Transfer of Control of Interest of Eua Power in Plant ML20126J6211992-12-24024 December 1992 Forwards LER 88-009-01 Issued on 921113,discussing Increased Thrust Bearing Loading for RHR Pumps When Pumps Run at Reduced Flows.Concern Raised That Inservice Testing May Not Detect Problem Soon Enough to Avoid Failure ML20125B4461992-11-30030 November 1992 Notification of 921203 Licensee Meeting in King of Prussia, PA to Discuss Auxiliary Operator re-licensing Plans ML20128C2131992-11-16016 November 1992 Notification of Postponement of 921124 Meeting W/Util in King of Prussia,Pa to Discuss Process for Reissuing Reactor Operator Licenses Terminated After Auxiliary Operator Performance Review 1999-09-16
[Table view] Category:NRC TO ASLP
MONTHYEARML20059B0341990-08-21021 August 1990 Advises That Time for Commission to Review Decision ALAB-934 Expired.Commission Declined Review.Decision Became Final Agency Action on 900820.W/Certificate Os Svc.Served on 900821 ML20056B1771990-08-0606 August 1990 Forwards Fj Congel to D Kwiatkowski of FEMA Re Mc Sinclair ,Served on Parties to Proceeding ML20055D9041990-06-22022 June 1990 Forwards FEMA Addressing Training Program for Decisionmakers for Radiological Emergencies at Plant,Per ASLB 900605 Prehearing Conference ML20248D2201989-09-28028 September 1989 Advises That NRC Does Not Intend to File Response to Commonwealth of Ma 890911 Motion for Leave to File Reply to Certain Applicant Responses to Proposed Findings ML20247M1621989-09-15015 September 1989 Forwards ACRS Providing Views Concerning Adequacy of Emergency Planning for Facility ML20247L5601989-09-11011 September 1989 Forwards Corrected Pages 36-37 of NRC Staff Supplemental Proposed Findings of Fact & Conclusions of Law W/Respect to Spmc & Exercise Contentions ML20247A2171989-09-0505 September 1989 Forwards NRC Supplemental Proposed Findings of Fact & Conclusions of Law Re Spmc & Exercise Contentions in Disk Form.W/O Encl ML20246N3991989-09-0101 September 1989 Requests That ASLB Find Town of Amesbury & Salisbury & City of Newburyport 890831 Proposed Findings in Default & Findings Disregarded Due to NRC Not Receiving Copy & Findings Not Being Properly Served,Per 10CFR2.701(a) ML20246F7831989-08-28028 August 1989 Forwards NRC Staff Proposed Findings of Fact & Conclusions of Law W/Respect to Spmc & Exercise Contentions in Disk Form.W/O Encl IR 05000443/19890811989-08-21021 August 1989 Forwards Ba Boger & Encl Team Insp Rept 50-443/89-81 on 890612-23 Re Insp of Util Low Power Startup Test Program,Per Informing Board of Event During 860622 Natural Circulation Test ML20248D8291989-08-0303 August 1989 Alab.* Advises That Time for Commission to Review ALAB-917 Expired.Commission Declined Review.Decision Became Final Agency Action on 890726.W/Certificate of Svc.Served on 890804 ML20247B4171989-07-19019 July 1989 ALAB-916.* Advises That Time Provided by NRC for Commission to Review ALAB-916 Expired.Commission Declined Review. Decision Became Final Agency Action on 890718.Certificate of Svc Encl.Served on 890719 ML20245J5101989-06-26026 June 1989 Forwards Confirmatory Action Ltr 89-11 Re Facility 890622 Manual Scram Due to Difficulties During Natural Circulation Startup Test.Licensee Investigating Circumstances of Event & NRC Sending Augmented Insp Team to Investigate ML20236D6101989-03-17017 March 1989 Forwards Documents,Dtd Oct 1981 - Oct 1987,w/relevant Statements Re Proceeding & Other Documents on Denial of Senator G Humphrey Petition to Participate Under 10CFR2.715(c).W/o Stated Encls ML20236D2401989-03-0707 March 1989 ALAB-909.* Advises That Time in Which Commission May Act to Review ALAB-909 Has Expired.Commission Declined Review. Decision Became Final Agency Action on 890227.Certificate of Svc Encl.Served on 890307 ML20205N3151988-11-0101 November 1988 ALAB-899.* Advises That Time for Commission to Review Decision ALAB-899 Expired.Commission Declined Review & Decision Became Final Agency Action on 881027.Served on 881027.Served on 881101 ML20204G2661988-10-18018 October 1988 Forwards Disc Containing NRC Response to Intervenors Contentions on Graded Exercise Filed on 881013.W/o Encl ML20204G1801988-10-18018 October 1988 Forwards FEMA Review & Evaluation of Seabrook Plan for Commonwealth of Ma Communities.W/O Encl ML20204G2281988-10-18018 October 1988 Forwards FEMA Review & Evaluation of Seabrook Plan for Commonwealth of Ma Communities.Fema Regards Applicant Means for Providing Prompt Notification to EPZ Residents Inadequate.W/O Encl ML20204G0351988-10-14014 October 1988 Forwards Page 6 to NRC Motion to Compel Answers to Interrogatories & Production of Documents by Town of Amesbury Filed on 881011 Due to Page Not Being Photocopied as Part of Document ML20204G6651988-10-12012 October 1988 Forwards 880628-29 Exercise Rept for Plant Issued by FEMA on 880901,per 881012 Request.W/O Encl ML20154L1311988-09-19019 September 1988 Forwards Stipulation to Seabrook Plan on Commonwealth of Ma Communities,Consolidating & Clarifying Applicant,Intervenors & NRC Contentions Admitted by ASLB in 880722 & 0819 Memoranda & Orders.Contentions J17 & J18 Not Included ML20154B7291988-09-0909 September 1988 Forwards Decision by Us First Circuit Court of Appeals Denying Various Petitions for Review of Commission Incorporation of Realism Doctrine in Emergency Planning Regulations Where Govts Decline to Participate in Planning ML20154B7461988-09-0808 September 1988 Forwards Floppy Disk Containing NRC Proposed Findings of Fact & Conclusions of Law Re Sheltering Issues.W/O Disk ML20153H6711988-08-26026 August 1988 Forwards NRC Proposed Findings of Fact & Conclusions of Law Re Sheltering Issues,Per 2-day Extension of Time Granted by ASLB ML20153D0571988-08-25025 August 1988 Informs That Time Provided for Commission to Review ALAB-896 Expired.Commission Declined Review & Decision Became Final Agency Action on 880824.Served on 880825 ML20151W5531988-08-23023 August 1988 Submits Corrections to Errors in NRC 880822 Response to Applicant Motion for Referral & Intervenors Cross Motion in Alternative NUREG/CR-4873, Forwards NUREG/CR-4873, Benchmark Study of I-DYNEV Evacuation Time Estimate Computer Code & NUREG/CR-4874, Sensitivity Study of Evacuation Time Estimates to Changes in Input Parameters for I-DYNEV Computer Code. W/O Encls1988-08-22022 August 1988 Forwards NUREG/CR-4873, Benchmark Study of I-DYNEV Evacuation Time Estimate Computer Code & NUREG/CR-4874, Sensitivity Study of Evacuation Time Estimates to Changes in Input Parameters for I-DYNEV Computer Code. W/O Encls ML20151W6501988-08-22022 August 1988 Informs That NRC Will Not Move for Summary Disposition of Remanded New England Coalition on Nuclear Pollution Contention I.B.2,per Board 880623 Order ML20151W6681988-08-18018 August 1988 Forwards Disc Containing NRC Proposed Findings of Fact & Conclusions of Law Filed on 880701.W/o Encl ML20151P4581988-08-0404 August 1988 Informs That NRC Does Not Plan to Respond to Applicant 880802 Revised Motion to Compel Discovery for Commonwealth of Ma Atty General Re Amended Contention on Emergency Notification Sys ML20155C2531988-05-31031 May 1988 Forwards Table of Contents for NRC Response to Contentions Filed by Towns of Amesbury,Newbury,Salisbury & West Newbury, Cities of Havervill & Newburyport & Commonwealth of Ma Atty General,New England Coalition on Nuclear Pollution ML20155B9311988-05-24024 May 1988 Forwards Documents NYN-88025 & NYN-88042,per 880524 Request. Encl Map of Commonwealth of Ma Portion of Seabrook EPZ Could Not Copied Due to Size.W/O Encls ML20154F0041988-05-0303 May 1988 Notifies That Time Provided for Commission to Review ASLAP Decision ALAB-889 Expired.Decision Became Final Agency Action on 880427.Served on 880505 ML20151Y8051988-04-29029 April 1988 Forwards Revised Page 4 to NRC 880428 Response to Intervenors Applications for Subpoenas of Named NRC & FEMA Employees,Correcting Citations in Footnotes.Related Correspondence ML20151Y7131988-04-28028 April 1988 Advises That ASLB Should Issue Order Dismissing Contentions I.V & IV Based on New England Coalition on Nuclear Pollution 880422 Written Decision Not to Litigate Contentions Further ML20245J4081988-04-27027 April 1988 Forwards Page 5 of Testimony of F Kantor Re Basis A.5 of Commonwealth of Ma Atty General Amended Alert Notification Sys Contention,Filed on 890425 & FEMA .W/ Certificate of Svc.Related Correspondence ML20151P0031988-04-20020 April 1988 Advises That Time for Commission to Review Aslab Decision ALAB-886 Expired.Commission Declined Review.Decision Became Final Agency Action on 880404.Served on 880420 ML20148G1681988-03-24024 March 1988 Informs That NRC Does Not Intend to Formally Respond to New England Coalition for Nuclear Pollution (Necnp) Motion to Compel Applicants to Respond to Necnp Third Set of Interrogatories ML20149L8891988-02-22022 February 1988 Advises That,In Light of FEMA Supplemental Testimony,Nrc Will Not File Testimony on Beach Shelter Issues Independent of FEMA ML20149L9881988-02-22022 February 1988 Onsite Emergency Planning & Safety Issues.* Informs That NRC Does Not Intend to Respond to New England Coalition on Nuclear Pollution (Necnp) Motion to Compel Applicants to Respond to Necnp Second Set of Interrogatories ML20149K9411988-02-17017 February 1988 Advises That NRC Does Not Indicate Whether Copy Was Transmitted to Each of Addressees on Svc List.Author Has Telefaxed Copy of Subj Ltr to Commonwealth of Ma Atty General Ofc ML20149L0481988-02-17017 February 1988 Informs of NRC Staff Plan Not to File Response to New England Coalition on Nuclear Pollution (Necnp) Motion for Leave to File Reply to Applicant Response to Necnp Motion to Compel Discovery Against Applicant Re Necnp Contention IV ML20149F1221988-02-0808 February 1988 Informs That NRC Does Not Plan to File Response to New England Coalition on Nuclear Pollution Motion to Compel Discovery Against Applicant Re Contentions I.V & IV ML20148D0831988-01-14014 January 1988 Requests That Encl Corrected Pages 6 & 7 to NRC 880112 Response to Licensing Board Order of 871127 Be Substituted for Same Pages Due to Typos ML20147B8501988-01-0707 January 1988 Notifies of Encl Util Press Release Re Util Offer to Give Siren Poles to Towns.Press Release May Have Relevance to Matters Before Aslp,Including 871113 Motion to Reopen Records & Admit Contentions Involving Newburyport,Ma Sirens ML20237B6741987-11-30030 November 1987 Requests That Parties Be Advised of Unavailability of Plant Documents During 871202-17,due to Relocation of Lpdr.Served on 871209 ML20236H3331987-10-27027 October 1987 Requests That Parties to Proceeding Be Informed of Exeter Public Library,Exeter,Nh Move to New Bldg in Late Nov or Early Dec.Lpdr Matl Will Not Be Available to Public During Move.Author Will Notify of Exact Dates for Move When Known ML20236H3371987-10-26026 October 1987 Informs That NRC Does Not Oppose Applicant 871023 Motion for 1-wk Extension to File Supplemental Memorandum Re Merrimac Sirens Required by Appeal Board 871014 Order ML20235B3401987-09-14014 September 1987 Forwards Flexible Disk Containing Testimony of T Urbanik on Behalf of NRC Staff on Town of Hampton Contention III & Seacoast Anti-Pollution League Contentions 18,31,34 & 37, Per .W/O Encl.Related Correspondence 1990-08-06
[Table view] |
Text
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/ k~g UNITED STATES 8' o NUCLEAR REGULATORY COMMISSION MJ%' -
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WASHINGTON, D. C. 20555 ~-
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id Sheldon J. Wolfe, Esq. , Chairman Dr. Jerry Harbour /
Administrative Judge Administrative Judge Atomic Safety and Licensing Atomic Safety and Licensing Board Panel Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Washington, D.C. 20555 Dr. Emmeth A. Luebke Administrative Judge Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 in the Matter of PUBLIC SERVICE COMPANY OF NEW HAMPSIIIRE, et al. --
(Seabrook Station, Units 1 and 2)
Docket Nos. 50-443 OL and 50-444 OL
Dear Administrative Judges:
In the Staff's Fifth Monthly Status Report submitted to the Board on June 4, 1986, the Staff notified the Board that it would be providing its review of Applicants' environmental qualification program as soon as that review was complete. The Staff review of this area is now final; that review will be published in Supplement 5 to the Staff's Safety Evaluation Report for the Seabrook facility. I have enclosed a copy of the completed environmental qualification review as it will appear in Supplement 5.
Sincerely, h l R'obert G. Perlis Counsel for NRC Staff Enc: As stated cc w/ enc: see next page h
G
f cc: Patrick J. McKeon Roberta C. Pevear .
Sandra Gavutis Edward L. Cross, Jr. , Esq. -
Jo Ann Shotwell Beverly Hollingworth ~_~
Nicholas J. Costello Docketing and Service Section Robert A. Backus, Esq. Letty Hett Brian P. Cassidy Dr. Mauray Tye Thomas G. Dignan, Jr. , Esq. Anne Verge, Chairperson Atomic Safety and Licensing Atomic Safety and Licensing Appeal Panel Board Panel Jane Doughty Division of Consumer Counsel William S. Jordan, III, Esq. Diane Curran, Esq.
Phillip Ahrens, Esq. Donald L. Herzberger, MD Sen. Robert L. Preston John F. Doherty Letty Hett Senator Gordon J. Humphrey Calvin A. Canney, City Manager Mr. Robert J. Harrison George Dana Bisbee, Esq. Mr. Maynard B. Pearson Town of North flampton R. K. Gad III, Esq.
Edward Meany John H. McEachern, Esq.
Gary W. Ifolmes Carol S. Sneider, Esq.
Diana P. Randall Owen B. Durgin Mr. Angie Machiros Donald E. Chick Alfred Sargent Mr. Mendall Clark Richard Hampe, Esq.
l l
l - -- -
O Safety Evaluation Report Office of Nuclear Reactor Regulation Electrical Instrumentation and Control Systems Bran:h Docket No. 50-443 _
3.11 EnvironTmental Qualification of Electrical Equipment Important to Safety --
and Safety-Related Mechanical Equipment 3.11.1 Introduction Equipment that is use'd to perform a necessary safety function must be demon-strated capable of maintaining functional operability under all service conditions postulated to occur during its installed life for the time it is required to operate. This requirement- which is embodied in General Design Criteria (GDC) I and 4 of Appendix A and Sections III, XI, and XVII of Appen-dix B to 10 CFR 50--is applicable to equipment located inside as well as out-side containment. More detailed requirements and guidance relating to the methods and procedures for demonstrating this capability for electrical equip-ment have been set forth in 10 CFR 50.49, " Environmental Qualification of Elec-tric Equipment Important to Safety for Nuclear Power Plants"; NUREG-0588,
" Interim Staff Position on Environmental Qualification of Safety-Related Elec-trical Equipment," which supplements the Institute of Electrical and Electron-ics Engineers (IEEE) Standard 323; and various NRC regulatory guides (RGs) and industry standards.
l l
3.11.2 Background i
l NUREG-0588 was issued in December 1979 to promote a more orderly and systematic l implementation of equipment qualification programs by industry and to provide
( guidance to the NRC staff for its use in ongoing licensing reviews.
l l
l The positions contained in that report provide guidance on (1) how to establish environmenta] service conditions, (2) how to select methods that are considered appropriate for qualifying equipment in different areas of the plant, and (3) other areas such as margin, aging, and documentation. In February 1980, the NRC asked certain near-term operating license '(OL) applicants to review 06/09/86 1 SEABROOK 1 SSER 5 SEC 3.11 l
and evaluate the environmental qualification documentation for each item of safety-related electrical equipment and to identify the degree to which their_
qualification programs were in compliance with the staff positions discussed in NUREG-Q588. -_~
IE Bulletin 79-01B, " Environmental Qualification of Class IE Equipment," issued by the NRC Office of Inspection and Enforcement (IE) on January 14, 1980, es-tablished environmental qualification requirements for operating reactors.
This bulletin and its supplements were provided to applicants for considera-tion in their reviews.
A final rule on environmental qualification of electrical equipment important to safety for nuclear power plants became effective on February 22, 1983. This rule, 10 CFR 50.49, specifies the requirements to be met for demonstrating the environmental qualification of electrical equipment important to safety located in a harsh environment. In conformance with 10 CFR 50.49, electrical equipment for Seabrook Unit 1 may be qualified according to the criteria specified in Category I of NUREG-0588.
The qtralification requirements for mechanical equipment are principally con-tained in Appendices A and B to 10 CFR 50. The qualification methods defined in NUREG-0588 can also be applied to mechanical equipment.
To document the degree to which the environmental qualification program com-plies with the NRC environmental qualification requirements and criteria, the applicant provided equipment qualification information by letters dated August 12, 1983, September 7, 1984, October 31, 1985, April 3, 1986, April 10, 1986, April 16, 1986, April 30, 1986, May 6, 1986, May 7, 1986, June 5, 1986, and June 6, 1986 to supplement the information in FSAR Section 3.11.
The staff.has reviewed the adequacy of the Seabrook environmental qualification program for electrical equipment important to safety as defined in 10 CFR 50.49 and the program for safety-related mechanical equipment. The scope of this report includes an evaluation of (1) the completeness of the list of systems and equipment to be qualified, (2) the criteria they must meet, (3) the en-vironments in which they must function, and (4) the qualification documentation 06/11/86 2 SEABROOK SSER 5 SEC 3.11
and evaluate the environmental qualification documentation for each item of safety-related electrical equipment and to identify the degree to which their qualification programs were in compliance with the staff positions discussed in NUREG-0588.
~
IE Bulletin 79-01B, " Environmental Qualification of Class IE Equipment," issued by the NRC Office of Inspection and Enforcement (IE) on January 14, 1980, es-tablished environmental qualification requirements for operating reactors.
This bulletin and its supplements were provided to applicants for considera-tion in their reviews.
A final rule on environmental qualification of electrical equipment important to safety for fuelear power plants became effective on February 22, 1983. This rule, 10 CFR 53.49, specifies the requirements to be met for demonstrating the environmertal qualification of electrical equipment important to safety located in a tarsh environment. In conformance with 10 CFR 50.49, electrical equipment for Seabrook Unit 1 may be qualified according to the criteria specified in Category I of NUREG-0588.
The qualification requirements for mechanical equipment are principally con-tained in Appendices A and B to 10 CFR 50. The qualification methods defined in NUREG-0588 can also be applied to mechanical equipment.
To document the degree to which the environmental qualification program com-plies with the NRC environmental qualification requirements and criteria, the applicant provided equipment qualification information by letters dated August 12, 1983, September 7, 1984, October 31, 1985, and April 3, 1986, to supplement the information in FSAR Section 3.11.
The staff has reviewed the adequacy of the Seabrook environmental qualification program for electrical equipment important to safety as defined in 10 CFR 50.49 and the program for safety-related mechanical equipment. The scope of this report includes an evaluation of (1) the completeness of the list of systems and equipment to be qualified, (2) the criteria they must meet, (3) the en-vironments in which they must function, and (4) the qualification documentation 06/09/86 2 SEABROOK 1 SSER 5 SEC 3.11
- for the equipment. It is limited to electrical equipment important to safety within the scope of 10 CFR 50.49 and safety-related mechanical equipment.
3.11.3 Staff Evaluation .
~- -
The staff e luation included an onsite examination of some equipment, an audit of qualification documentation, and a review of the applicant's submittals for completeness and acceptability of systems and components, qualification meth-ods, and accident environments. The criteria in SRP Section 3.11 (NUREG-0800),
Revision 2, and in NUREG-0588, Category I, and the requirements in 10 CFR 50.49 form the bases for the staff evaluation.
The staff performed an audit of the applicant's qualification documentation and installed electrical equipment on February 25, February 26, and February 27, 1986. The audit consisted of a review of 12 files containing information re-garding equipment qualification. The staff's findings from the audit are dis-cussed in Section 3.11.4 of this supplement.
3.11.3.1 Completeness of Equipment Important to Safety 10 CFR 50.49 identifies three categories of electrical equipment that must be qualified in accordance with the provisions of the rule:
(1) safety-related electrical equipment whose failure under the postulated environmental conditions could prevent satisfactory accomplishment of the safety functions by the safety-related equipment (2) non-safety-related electrical equipment whose failure under the postulated environmental conditions could prevent satisfactory accomplishment of the safety functions by the safety-related equipment (3) certain,postaccident monitoring equipment (RG 1.97, Category 1 and 2 postaccident monitoring equipment).
06/09/86 3 SEABROOK 1 SSER 5 SEC 3.11
The applicant has provided information addressing compliance with this require-ment of 10 CFR 50.49.
To demonstrate compliance with 10 CFR 50.49(b)(1), the applicant provided a list of syst, ems a'nd their components required to mitigate the consequences of - _~
loss-of-cooiant accidents (LOCAs) or high-energy line breaks (HELBs). The systems identified by the applicant for the environmental qualification program as being required to function to mitigate the consequences of LOCAs or HELBs that have components located in a harsh environment are listed below. This list was reviewed and found acceptable by the staff.
System (1) auxiliary steam (2) containment air handling (3) containment air purge (4) control building air handling (5) containment building spray (6) component cooling water primary (7) combustible gas control (8) containment on-line purge (9) rod control and position (10) chemical and volume control (11) diesel generator air handling (12) drains--floor (13) diesel generator (14) containment enclosure air handling (15) electrical distribution (16) electrical distribution--emergency (17) emergency feedwater pump house air handling (18) fuel storage building air handling (19) feedwater (20) heat tracing (21) in-core instruments (22) miscellaneous equipment (23) main steam (24) main steam drain (25) nitrogen gas (26) nuclear instrumentation (27) primary auxiliary building air handling (28) reactor coolant (29) residual heat removal (30) radiation monitoring (31) reactor makeup water (32) steam generator blowdown (33) spent fuel pool cooling ,
(34) safety injection 06/09/86 4 SEABROOK 1 SSER 5 SEC 3.11
O (35) sampling (36) service water (37) service water pumphouse air handling (38) vibration monitoring -
, (39) vents (40)wastep[ocessing--liouidDrains 2 --
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To demonstrate compliance with 10 CFR 50.49(b)(2) concerning non-safety-related equipment whose failure under postulated accident conditions could prevent the satisfactory accomplishment of safety functions, the' applicant included all such equipment in the equipment Qualification program. In addition, the appli-cant has committed to conform with RG 1.75 and will submit his analysis support-ing conformance for staff review. The staff will confirm that the applicant conforms to RG 1.75 prior to fuel load. The applicant also performed a review in response to the concerns addressed by the staff in IE Information Notice 79-22,
" Qualification of Control Systems," dated September 14, 1979. The staff found the applicant's response to the concerns in IE Information Notice 79-22 accept-able. On the basis of the above, the staff concludes that the applicant's com-pliance with 10 .CFR 50.49(b)(2) is acceptable.
10 CFR 50.49(b)(3) requires that certain post accident monitoring instrumenta-tion that is located in a harsh environment be included in the equipment environmental qualification program. Guidance as to the matters to be covered is contained in R.G. 1.97. R.G. 1.97 identifies parameters to be provided unless adequate justification is given. The applicant has indicated that 10 CFR 50.49(b)(3) equipment is included in the qualification program; however, in addressing conformance with RG 1.97, the applicant identified 10 variables listed in Category 1 or 2 (which specify environmental qualification) of the guide as not requiring monitoring during an accident. That is, the emergency response procedures do not require the plant cperating crew to monitor these i
variables in order to provide a basis for operator actions for mitigating the consequences of an accident.
The staff evaluation of all identified deviations from RG 1.97 is included in Section 7.5.2.4 of this supplement. From the evaluation the staff concludes that sufficient justification has been provided to support the classification of these 10 variables as not being required for accident i monitoring. Therefore, these 10 variables, given below, do not fall within the scope of 10 CFR 50.49(b)(3).
06/11/86 5 SEABROOK SSER 5 SEC 3.11
(1) primary coolant radiation 1evel
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(2) narrow range sump water level (3) heat removal by containment fan heat removal system (4) containment sump water temperature -
(5) makeup flow-in -
(6) makeup fiow-out 2 (7) volume @ntrol tank level -
(8) boric aEid charging flow (9) accumulator. tank pressure (10) accumulator tank level Instruments for monitoring variables (1) through (4) are not being installed at Seabrook; although instruments for monitoring variables (5) through (10) are being installed, they will not be qualified for the harsh environment. The staff position is that an instrument to monitor the containment sump water temperature (variable 4) should be provided and that it should be environmen-tally qualified. In addition, an environmentally qualified instrument should be provided for monitoring either accumulator tank pressure (variable 9) or accumulator tank level (variable 10) although implementation of this position can be deferred to the first refueling without jeopardizing the public health and safety. The basis for this staff position is provided below.
The requirements for accident monitoring instrumentatior. were issued as Item II.F of NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident."
(Revision 2 was issued in August 1980.) NUREG-0737, Supplement 1, " Clarification of TMI Action Plan Requirements," which was issued in January 1983, provides de-tailed implementation guidance. This supplement, which invokes RG 1.97 as well as other emergency response capabilitie;, states that it is not intended that the guidance documents referred to (in this instance, RG 1.97) are to be used as requirements, but rather that they are to be used as sources of guidance for NRC staff and licensees regarding acceptable means for meeting the basic re-quirements. Similarly, footnote 4 to 10 CFR 50.49(b)(3) states that specific guidance concerning the types of variables to be monitored is provided in Revision 2 of RG 1.97. Engineering judgment is required in the application of this guidance. Equipment qualification for instrumentation identified on a plant-specific basis as not required for accident monitoring would not fall under the provisions of 10 CFR 50.49(b)(3) but rather under the provisisons of RG 1.97 relating to other instrumentation.
06/11/86 6 SEABROOK SSER 5 SEC 3.11 i
.,-,w
Revision 2 of RG 1.97 identifies three basic types of equipment: accident moni-toring instrumentation, systems operation monitoring instrumentation, and effluent release monitoring instrumentation. Additionally, the guide identifies variables, types A through E, to distinguish the types of parameters and to provide a gen- '
eral ranking.of their importance. "ccident monitoring instrumentation provides~ _~
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information on vital parameters cla nified as type A, B, and C variables in Table 2 of the regulatory guide.
Type D variables provide information to (1) indicate operation of individual safety systems and other sys'tems important to safety and (2) help the operator make appropriate decisions in mitigating the consequences of an accident. Of the 10 variables identified above, 9 are Type D. The staff's position is that these 9 variables are not required to perform either of these functions. The remaining variable, narrow range sump water level, is type B. However, a fully qualified wide range sump level instrument is installed to provide this variable; there-fore, a narrow range instrument is not considered necessary and need not be provided.
However, sump water temperature is a parameter, along with sump level and con-tainment pressure, that influences net positive suction head (NPSH) for safety system pumps during the recirculation mode. Furthermore, knowledge of sump water temperature is useful in performing postaccident energy balance calcu-lations. RG 1.97 identifies containment sump water temperature instrumentation as equipment that should be environmentally qualified. Thus, even though this variable is not required for the performance of the two function attributes of type D variables, the information it provides is deemed of sufficient usefulness following an accident that a fully qualified instrument should be provided.
The accumulator tank level and pressure provide direct indication of function-ing of the accumulators (first-line safety equipment) during an accident.
Either pressure or level indication would be sufficient to indicate discharge of the accumulators. It is recognized that the accumulators are passive sys-tems; that the operator could take no meaningful action to restore an inoper-able accumulator other than to open a closed (inadvertently). isolation valve for which qualified status information is provided; and that other variables 06/09/86 7 SEABROOK 1 SSER 5 SEC 3.11
(e.g., reactor system pressure, reactor vessel level and core temperature) are available from which operation of the accumulators can be inferred. However, even though accumulator pressure or level are not required for performance of the function attributes of type D variables, the direct indication of accumu-lator operapion is deemed of sufficient usefulness that a fully qualified pres ~ .~
sure or level instrument should be provided.
In summary, the staff's position is that environmentally qualified instrumenta-tion for monitoring accumulator pressure (or level) and containment sump water temperature should be installed before startup from the first refueling since this is not a required post accident monitoring instrumentation. This is not inconsistent with 10 CFR 50.49(b)(3). The staff discussed this position with the applicant. The applicant agrees with the staff position and, by letter dated June 6, 1986, the applicant committed to meet it.
3.11.3.2 Qualification Methods 3.11.3.2.1 Electrical Equipment in a Harsh Environment Detailed criteria for qualifying safety-related electrical equipment in a harsh environment are defined in NUREG-0588. The criteria in NUREG-0588 are also ap-plicable to the other equipment important to safety defined in 10 CFR 50.49.
The staff has reviewed the methods used by the applicant to demonstrate quali-fication and concluded that they are in compliance with the requirements of NUREG-C588, Category I.
3.11.3.2.2 Safety-Related Mechanical Equipment in a Harsh Environment Although there are no detailed requirements for mechanical equipment, GDC 1,
" Quality Standards and Records," and 4, " Environmental and Missile Design Bases,"
and Appendix B to 10 CFR 50, " Quality Assurance criteria for Nuclear Power Plants and Fuel Reprocessing Plants" (Section III, " Design Control," and XVII, 06/11/86 8 SEABROOK SSER 5 SEC 3.11 )
" Quality Assurance Records"), contain the following requirements related to equipment qualification:
- Components shall be designed to be compatible with the postulated environ- -
mental conditions, including those associated with LOCAs. _"
- Measures shall be established for the selection and review for suitability of application of materials, parts, and equipment that are essential to safety-related functions.
- Design control measures shall be established for verifying the adequacy of design.
- Equipment qualification records shall be maintained and shall include the results of tests and materials analyses.
The results of the safety-related mechanical equipment qualification program have been submitted to the staff for review. In addition, qualification documentation for three items of safety-related mechanical equipmer.t has been submitted by the applicant and has been reviewed by the staff. The staff review has verified that the requirements for environmental qualification of safety-related mechanical equipment have been adequately addressed.
3.11.3.3 Service Conditions NUREG-0588 defines the metheds to be used for determining 'the environmental conditions associated with LOCA> or HELBs, inside or outside of containment.
The review and evaluation of the adequacy of these env',ronmental conditions are described below. The staff has reviewed the qualif', cation documentation to ensure that the qualification conditions envelop the environmental conditions established by the applicant.
In December 1984, the NRC issued IE Information Notice 84-90 regarding a poten-tial problem pertaining to plant analysis and equipment qualification with respect to a postulated main steamline break (MSLB') with release of superheated 06/03/86 9 SEABROOK 1 SSER S SEC 3.11
steam. It was discovered during the NRC staff's review cf the Westinghouse methodology for computing, mass and energy releases for a postulated MSLB that the heat transfer from the uncovered portion of the steam generator tube bundle was not included. In the FSAR, the applicant used this Westinghouse steam
- generator blewdown model (i.e., the Westinghouse methodology of computing mass ~~ _~
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and energy releases) for calculating equipment qualification temperature inside (
containment. By letter of April 10, 1986, the applicant reported its evaluation of the inpact of the superheated steam blowcown on the equipment qualification ,
temperature previously calculated for both inside and outside centainment.
The applicant's evaluation for equipment inside containment was based on Wes-tingnouse Topical Report WCAp-8822, Supplement 2, in which it was found that the impact of steam superheatirg is not significant for large dry contain-ments. In Supplement 2 of WCAp-8822, a snodified LOFTRAN code, accounting for ,
heat transfer to the steam during steam generator tube uncovery, yas used to ,
calculate mass and ener.gy release rates following an MSLB. The rnedification >
was described in Supplement 1 of WCAP-8822. The staff has reviewed both Sup-piements 1 and 2 of WCAP-8822 and found therg acceptable.
Furthermore, the applicant stated that *he results of WCAp-8822, Supplereent 2, are applicable to the Seabrobk Model F steam generatpr. On the basis of the above evaluation, the staf f concludes th.t the environmental qualification -
pressure and temperature inside containment, estatif shed previously in the FS,AR, are still valid.
3.11.3 3.1 Temperature, Pressure, and Humidity Conditions Inside Centatnnent t
The applicant provided the LOCA/MSLB profiles used for equipment qualification program submittals. The peak values resulting from these profiles are as follows: l
. Maximum Mp in.ufn Temperature Pressure Humidj,ty LOCA/MSLB 370.0*F 34.5 psig 100*4 06/09/86 10 SEABROOK 1 SSER S SEC 3.11
t
- The staff has reviewed these profiles and finds them acceptable for use in equipment qualification; that is, there is reasonable assurance that the actual pressures and temperatures will not exceed these profiles anywhere within the '
specified environmental zone (except in the break zone). .
3.11.3.3.2 kemperature, Pressure,andHumidityConditionsOutsidePrimary Containment The applicant has provided, in the FSAR, the temperature, pressure, and humidity conditions resulting from HELBs in various compartments outside containment. The criteria used to define the location of the HELBs are described in the FSAR Section 3.6. As a result of the superheated steam issue described in Sec-tion 3.11.3.3, the applicant determined that the new mass and energy releases ,
into the two main steam and feedwater pipe chase areas are greater than the previously postulated releases. Therefore, the maximum temperature in the faulted pipe chase is expected to be higher than the previously prescribed temperature for environmental qualification of equipment in the pipe chase.
In letters dated April 10, 1986, and June 5, 1986, the applicant stated that despite any postulated superheated temperature in the faulted pipe chase, the Seabrook plant can achieve a safe shutdown. Seabrook has two separated main steam and feedwater pipe chase areas on the east and west sides of contain-ment. Each pipe chase houses the feedwater and main steam piping for two of the four steam generators. The pipe chase also houses the main steam and feed-water isolation valves, steam safety relief valves, atmospheric dump valves, and main steam supply valves to the emergency feed pump turbine.
Given an HELB in one of the pipe chase areas, the applicant stated that the main steam isolation valves and the other electrical equipment in the faulted pipe chase will perform the intended safety functions before the tubes in the faulted steam generator are uncovered and superheated steam is generated. The applicant al,so evaluated all of the electrical equipment in the faulted pipe chase and determined that its consequential failure could not affect the ability to safely shut down Seabrook with the equipment in the other pipe chase. The 06/09/86 11 SEABROOK 1 $$ER 5 SEC 3.11
.r,
staf f finds this approach acceptable because only two steam generators are required to safely shut down the Seabrook plant.
However, if the superheatd steam should cause the main steam isolation valves tofailinthfaultedpipechase,twosteamgeneratorswouldblowdown. This T
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event was not previously evaluated in FSAR Chapter 15. The applicant provided the results of a scoping analysis for a two-steam generator blowdown event.
The FSAR Chapter 15 steamline break analysis is based on a minimum assumed shut-down margin of 1.31. a'nd is performed at conditions epresentative of end of life (EOL). A Westinghouse steamline break topical report (WCAp-9226, Rev. 1) provides sensitivity studies as a function of the moderator coefficient for the steamline break event which demonstrate that as the temperature coefficient becomes less negative, the accident becomes much less limiting. Since at begina ning of life (BOL) the temperature coefficient is less negative, the BOL case is significantly less limiting than the point at which the analyses are per-formed. The amount of reactivity added by the consequential opening of both main steam isolation valves (MSIVs) is very small and would have a negligible effect on the BOL transient as compared with the FSAR (EOL) transient. On this basis, it is Westinghouse's conclusion that the departure from nucleate boiling (DNB) design basis for the plant would be maintained at BOL assuming a shutdown margin of 1.3?;.
At EOL, the consequential opening of both MSIVs could potentially result in a transient more severe than that in the present FSAR analysis. However, the Seabrook Cycle 1 nuclear design calculated shutdown margin at EOL is greater than 3.8*; after taking into account uncertainties. This value includes the assumption that all rods are fully inserted except for the stuck rod. WCAp-8226 presents the results of sensitivity studies that show that the transient is less limiting as the initial shutdown margin increases. Representative calcu-lations incorporating consequential MSIV failures due to superheated steam show that the amount of reactivity added by tha consequential opening of the MSIVs is negligible when compared with the negative reactivity available by the in-clusion of the Cycle 1 shutdown margin of more than 3.8?; in the analysis.
06/09/86 12 SEABROOK 1 SSER 5 SEC 3.11
- Therefore, the DNB design basis would be met at EOL when credit is taken for !
the Cycle 1 specific value of shutdown margin.
In Section 15.6.4 of the SER, the staff reviewed the radiological consequences .
l ofamainstjamlinefailureoutsidecontainment. This analysis was based on - - -
the blowdowf of one steam generated. its staff has performed an independent calculation of the radiological consequences of a main steamline failure as described in Section 15.6.4 of the SER, assuming a second steam generator also blows down outside containment with an additional iodine inventory loss to the atmosphere of about 5 curies within the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the accident. This release will increase the exclusion areas boundary dose to the thyroid by about 0.6 rem with no noticeable increase in the whole-body dose. Even with this increase, the calculated dose for a two-steam generator blowdown accident would be a small fraction of the 10 CFR 100.11 dose guidelines.
Th6refore, an the basis of the above discussion, the staff concludes that the Seabrook plant can safely shut down following an HELB in either pipe chase. In addition, the Seabrook plant meets the requirements of GDC 28 of Appendix A to 10 CFR 50 and the guidelines of 10 CFR 100.J1 provided that the Seabrook Techni-cal Specifications require a 3.8% AK/k shutdown margin for operating modes 1, 2, and 3. In a letter dated June 5,1986, the applicant committed to modify the Ceabrook Technical Specifications to require a 3.8% AK/k shutdown margir in operating modes 1, 2, and 3. The staff finds this acceptable.
3.11.3.3.3 Submergence The submergence potential has been determined by the applicant to be below
(-)20 ft 8 in. inside the containment and at various elevations in buildings outside the contair.nent building. The applicant has taken appropriate corree-tive actions to either justify submerged operation, or to relocate or qualify the affected equipment.
3.11.3.3.4 Chemical Spray 06/09/86 13 SEABROOK 1 $$ER 5 SEC 3.11
T A chemical spray inside containment may be used to mitigate the effects of an accident. The applicant has appropriately included this parameter in the evaluation of equipment located inside containment. -
3.11.3.3.5 3ging -
The aging program requirements for Seabrook electrical equipment are defined in Category I of NUREG-0588. All degrading influences must be considered and included in the aging program. Justification for excluding preaging of equip- .
ment in type testing must be established on the basis of equipment design and application, or on state-of-the-art aging techniques. A qualified life is to be established f6r each equipment item.
! In addition to the above, a maintenance / surveillance program must be implemented to identify and prevent significant age-related degradation of electrical and mechanical equipnent. The applicant committed to follow the recommendations in RG 1.33, Revision 2, " Quality Assurance Program Requirements (Operation)," which endorses American Nuclear Society /American National Standards Institute Standard ANS-3.2/ ANSI N18.1976, " Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants." This standard defines the scope and content of a maintenance / surveillance program for safety-related equipment.
Provisions for preventing or detecting age-related degradation in safety grade equipment are specified and include (1) utilizing experience with similar equip-ment, (2) revising and updating the program as experience is gained with the equipment during the life of the plant, (3) reviewing and evaluating malfunc-tioning equipment and obtaining adequate replacement components, and (4) estab-lishing surveillance tests and inspections based on reliability analyses, frequency and type of service, or age of the items, as appropriate.
l The staff found that the applicant has adequately described a program that in-corporates the above guidelines. In addition, the applicant has stated that the maintenance / surveillance program is in effect at Seabeook.
l 3.11.3.3.6 Radiation (Inside and Outside Containment) 06/11/86 14 SEABROOK SSER 5 SEC 3.11 l
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The applicant has provided values for the radiation levels postulated to exist following a LOCA. The application and methodology to determine these values were presented to the applicant in NUREG-0588 and NUREG-0737. The staff review-determined that the values to which equipment was qualified enveloped the re-
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quirementsifentifiedbytheapplicant. -
The maximum value specified by the applicant for use in equipment qualification inside containment, and in areas outside containment exposed to post-LOCA recir-culating fluid environments, is 2.0 x 10' rads (gamma plus beta). This value is acceptable for use in the qualification of equipment.
3.11.3.4 Outstanding Equipment The Seabrook qualification program has a total cf 112 item groups. The applicant originally committed to qualify all equipment for a postaccident operability time of 1 year. Subsequently, the applicant discovered that there are 12 '. tem types (i.e., 12 item types out of the 112 item groups) that cannot be qurfified for a postaccident operating time of 1 year. The.. staff typically requires quali-fication for a period of 100 days after an accident, and in some insi.ances the regulations allow for postaccident qualification periods substantially less than 100 days. Table 3.1 lists the 12 item types and their postaccid1nt quali-fication periods as provided by the applicant.
The staff reviewed the qualification information prosided by the applicant for the 12 item types listed in Table 3.1 in which the. applicant indicated that 5 of the 12 item types met the staff requirement of.100 days and the remaining 7 meet the postaccident tin.E margin requirements specified in Position C.4 of Revision 1 nf RG 1.89. Therefore, t'he staff finds this acceptable.
x 3.11.4 Environmental Qualification Audit On February 25, February 26, and February 27, 1986, the staf f, with assistance from EG&G Idaho, Inc., conducted an audit of the applicant's qualification files and equipment installed at the plant. Twelve file,s were audited to determine
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06/11/86 -
15 SEABROOK SSER 5 SEC 3.11
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9 if the documents in the qualification files supported the qualification status determined by the applicant.
The files se.lected for audit were ;
(1) Okonite Cable (File No. 113-03-01)
(2) Transamerica Level Transmitter (File No. 174-15-01)
(3) Brandrex Cable (File No. 113-06-01)
(4) Reliance Motor (File No. 236-11-06)
(5) Limitorque Motor Operator (File No. 248-37-01)
(6) ASCO Solenoid Valve (File No. NSSS-220-02)
(7) ITT-Suprenoit Cable (File No. 113-19-01)
(8) Conax Conduit Seal Assembly (File No. 118-03-01)
(9) Rotork Motor Operator (File No. 173-05-02)
(10) Barton Transmitter (File No. 252-16-02)
(11) Endevco Accelerometer and Charge Converter (File No. 252-30-01)
(12) Weidmiller Terminal Block (File No. 600-02-01)
Several deficiencies were noted and discussed with the applicant at the time of l
the audit and transmitted to the applicant by letter dated April 10, 1986.
l The applicant proposed acceptable corrective measures in the form of additional l information and file revision to eliminate the deficiencies cited.
i As part of the audit, the equipment as actually installed was inspected during a plant walkdown. The purpose of the walkdown was to verify that the manufac-turer, model number, location, and installation are consistent with qualification documents. The applicant proposed acceptable corrective measures for the defi-ciencies that were found and committed to correct all deficiencies by fuel load.
3.11.5 Conclusions The staff ha's reviewed the Seabrook program for the environmental qualification of electrical equipment important to safety and safety-related mechanical equipment. The purpose of the review was to determine the adequacy and scope 06/09/86 16 SEABROOK 1 SSER 5 SEC 3.11 i
of the qualification program and to verify that the methods used to demonstrate qualification are in compliance with applicable regulations and standards.
On the basis of the results of its review and subject to confirmation that all audit deficiencies.have been corrected, the staff concludes that the applicant has ~ I' demonstrated compliance with the requirements for environmental qualification as outlined in 10 CFR 50.49, the relevant parts of GDC 1 and 4, and Sections III, XI, and XVII of Appendix B to 10 CFR 50, and with the criteria as specified in NUREG-0588.
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Table 3.1 Equipment item types and thier postaccident qualification periods Qualified Time '
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post- required accident to perform - - -
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EQ file ." operating safety Number of number Description time function items 174-00-01 Foxboro transmitters 100 days 90 days 13 252-3E-01 ASCO temperature switches 160 days 30 days 4 600-01-04 Raychem 8-kV motor connector kits 100 days 30 days 13 173-05-03 Maisoneilan E/P converter 204 days 100 days 4 248-36-01 Borg-Warner feedwater 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Approxi- 4 isolation valves mately 1 minute 600-06-01 NAMC0 EC 210 series conduit seals 318 days 30 days 16 113-03-01 Okonite 600-V power cable
- 30 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 113-17-01 Anaconda 600-V control cable
- 30 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 113-18-01 Anaconda 300-V instrumentation 30 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cable
- 113-20-01 ITT Suprenant 300-V instrumen- 30 days 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tation cable
- 172-01-01 General Atomic Radiation 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Approxi- 1 Monitors and Detectors mately (annulus) 2 minutes 172-01-01 General Atomic Radiation 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Approxi- 2 Monitors and Detectors (inside mately containment) 2 minutes
- 0nly the cable that is subject to submergence is limited to 30 days' qualifica-tion. This applies to all cable listed here.
06/11/86 18 - SEABROOK SSER 5 SEC 3.11