Similar Documents at Perry |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That Proprietary Document NEDE-32907P,DRF A22-0084-53, Safety Analysis Rept for Perry NPP 5% Power Uprate, Class III Dtd Sept 1999 Be Withheld.Determined Document Proprietary & Will Be Withheld ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2435, Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect1999-10-13013 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-440/99-13.Corrective Actions:Ts SRs with Incorrect Descriptions Were Annotated to Ensure That CR Operators Are Aware That ACs Are Effect ML20212K9271999-09-30030 September 1999 Refers to 990927 Meeting Conducted at Perry Nuclear Power Plant to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20212J1451999-09-30030 September 1999 Forwards Order,In Response to 990505 Application PY-CEI/NRR- 2394L.Order Approves Conforming License Amend Which Will Be Issued & Made Effective When Transfer Completed ML20217E7111999-09-30030 September 1999 Documents Telcon Conducted on 990929 Between M Underwood of Oh EPA & D Tizzan of Pnpp,Re Request to Operate Pnpp Sws,As Is,Until Resolution Can Be Obtained ML20212G4161999-09-24024 September 1999 Informs of Completion of Licensing Action for Generic Ltr 98-01, Y2K Readiness of Computer Systems at Nuclear Power Plants, for Perry Nuclear Power Plant ML20212G5811999-09-23023 September 1999 Informs That Licenses for Ta Lentz,License SOP-31449,PJ Arthur,License SOP-30921-1 & Dp Mott,License SOP-31500 Are Considered to Have Expired,Iaw 10CFR50.74(a),10CFR55.5 & 10CFR55.55 PY-CEI-NRR-2432, Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-21021 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, in Response to Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams PY-CEI-NRR-2428, Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions1999-09-16016 September 1999 Submits Resolution to Seventh Question Proposed within NRC 980615 RAI Relating to Cooling Water Sys That Serve Containment Air Coolers & Assessment,Post Accident,Of Potential Water Hammer & two-phase Flow Conditions ML20212D0151999-09-14014 September 1999 Requests Cancellation of NPDES Permit 3II00036.Permit Has Been Incorporated in Permit 3IB00016*ED.Discharge Point Sources & Associated Fees Currently Covered Under Permit 3IB00016*ED ML20212A8371999-09-13013 September 1999 Forwards Insp Rept 50-440/99-13 on 990712-30 & Notice of Violation.Insp Included Evaluation of Engineering Support, Design Change & Modification Activities,Internal Assessment Activities & Corrective Actions ML20217A8971999-09-0909 September 1999 Forwards Insp Rept 50-440/99-09 on 990709-0825.One Violation of NRC Requirements Occurred & Being Treated as NCV, Consistent with App C of Enforcement Policy PY-CEI-NRR-2431, Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages1999-09-0909 September 1999 Forwards Revised Emergency Plan for Perry NPP, IAW 10CFR50.54(q).Changes Constitute Revs,Temporary Changes or Reissued Pages ML20211Q6911999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Perry Operator License Applicants During Wks of 010108 & 15.Validation of Exam Will Occur at Station During Wk of 001218 IR 05000440/19990011999-08-31031 August 1999 Requests That Page Number 4, P2 Status of EP Facilities, Equipment & Resources, of Insp Rept 50-440/99-01 Be Replaced with Encl Rev PY-CEI-NRR-2425, Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.21999-08-26026 August 1999 Forwards Copy of Oh EPA Approval for Use of Nalco 7348 & Nalco 7468 at Pnpp,Iaw License NPF-58,App B,Epp,Section 3.2 PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20210Q8421999-08-13013 August 1999 First Final Response to FOIA Request for Documents.Records Listed in App a Being Released in Entirety & Records Listed in App B Being Withheld in Part (Ref FOIA Exempt 5) ML20210R7861999-08-12012 August 1999 Forwards Insp Rept 50-440/99-12 on 990712-16.No Violations Noted.New Emergency Preparedness Program Staff & Mgt Personnel Were Professional & Proactive ML20210S3961999-08-11011 August 1999 Requests That Ten Listed Individuals Be Registered to Take 991006 BWR Gfes of Written Operating Licensing Exam.Two Listed Personnel Will Have Access to Exams Before Exams Are Administered PY-CEI-NRR-2423, Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready1999-08-10010 August 1999 Provides Final Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Npps. Remediation of Meteorological Monitoring Sys Has Been Completed & Ppnp Facility Is Now Y2K Ready PY-CEI-NRR-2421, Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-9906301999-08-10010 August 1999 Forwards Semiannual fitness-for-duty Rept,Iaw 10CFR26.71(d) for Pnpp Covering Period of 990101-990630 ML20210Q7981999-08-10010 August 1999 Informs That Intention to Utilize Sulfuric Acid in Pnpp Circulating Water Sys to Lower Ph Is Anticipated to Be Completed in Nov ML20210Q5831999-08-10010 August 1999 Requests Permission to Chemically Treat CWS for Algae Due to Cooling Water Basin Becoming Infected with Algae of Various Types PY-CEI-NRR-2422, Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 9808261999-08-10010 August 1999 Forwards Addl Info Re ASME Section IX Relief Request (IR-023) for Inservice Examination Program at Pnpp,Submitted on 980826 ML20210K6331999-08-0404 August 1999 Submits Response to Requests for Addl Info to GL 92-01,Rev 1, Reactor Vessel Structural Integrity, for Perry Nuclear Plant,Unit 1 PY-CEI-NRR-2417, Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-60001999-08-0202 August 1999 Forwards NP0059-007, Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval, IAW ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,Article IWA-6000 ML20210G8411999-07-28028 July 1999 Informs That Based on Determination That Rev 14 Changes to Various Portions of Perry Nuclear Power Plant Emergency Plan Does Not Decrease Effectiveness of Licensee Emergency Plan & Meets Standard of 10CFR50.47(b),no NRC Approval Required ML20210E0661999-07-22022 July 1999 Forwards Insp Rept 50-440/99-08 on 990518-0708.No Violations Noted.Overall Conduct of Activities at Perry Facility, Conservative & Professional with Continuing Focus on Safety PY-CEI-NRR-2419, Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld1999-07-21021 July 1999 Forwards Four Copies of Rev 27 to Pnpp Security Plan,Per 10CFR50.54(p)(2).Changes Have Been Determined Not to Decrease Effectiveness of Security Plan.Rev Withheld PY-CEI-NRR-2415, Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-19019 July 1999 Submits Estimate of Number of Licensing Submittal for FY00 & 01,for Pnpp,Per Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates ML20210A6441999-07-15015 July 1999 Advises That Listed Operator Licenses for Company Personnel Have Expired,As of 990715,per 10CFR50.74(a) & 10CFR55.5. Individuals Listed Have Assumed Responsibilities at Pnpp That Do Not Require Operator Licenses ML20209E5951999-07-0909 July 1999 Ltr Contract:Task Order 46, Perry Engineering & Technical Support (E&Ts) Insp, Under Contract NRC-03-98-021 ML20209D5931999-07-0101 July 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Investigation Rept 3-98-005 Issued on 990510.Corrective Actions Will Be Examined During Future Inspections ML20211A3881999-06-30030 June 1999 Supplements Re NRC Incomprehensible Enforcement Inactions.Understands That NRC Claiming Hands Tied in Matter Re Discrimination Violation at Perry Npp.Requests That NRC Take Listed Two Actions PY-CEI-NRR-2410, Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant1999-06-29029 June 1999 Submits Response to NRC Request for Info Re GL 98-01, Y2K Readiness of Computer Sys at Npps. Attachment 1 Provides Y2K Readiness Disclosure for Plant PY-CEI-NRR-2413, Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 9907061999-06-29029 June 1999 Advises That Jk Wood Will Replace Lw Myers as Pnpp,Vice President - Nuclear,Effective 990706 PY-CEI-NRR-2403, Submits Response to RAI Re GL 96-05 Program at Plant1999-06-29029 June 1999 Submits Response to RAI Re GL 96-05 Program at Plant ML20196H9641999-06-29029 June 1999 Confirms 990615 Telcon Request with J Lieberman for Addl Time to Respond to Enforcement Action 99-012.FirstEnergy Has 60 Days to Respond to EA PY-CEI-NRR-2412, Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-19991999-06-28028 June 1999 Forwards Perry Nuclear Plant Simulator Four Yr Test Rept & NRC Form 474, Simulation Facility Certification, Which Describes Tests Conducted from June 1995-1999 ML20211A3991999-06-28028 June 1999 Submits Concerns Re Proposed Changes to Enforcement Policy. Believes That NRC Existing Regulations & Policies Provide Adequate Controls & That NRC Not Administering Consistent Enforcement Policies in Response to Discriminatory Actions ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 PY-CEI-NRR-2405, Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt1999-06-14014 June 1999 Informs NRC That Pnpp Staff Has Implemented Formal Industry Position on Severe Accident Mgt ML20195H9051999-06-10010 June 1999 Forwards Two License Renewal Applications Consisting of NRC Form 398 & NRC Form 396 for Bk Carrier,License OP-30997 & Jt Steward,License OP-30564-1 ML20212H5841999-06-10010 June 1999 Responds to NRC Notice of Level III Violation Received by K Wierman.Corrective Actions:K Wierman Has Been Dismissed from Position at Perry NPP PY-CEI-NRR-2408, Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval1999-06-10010 June 1999 Forwards Rev 4 to Pump & Valve Inservice Testing Program Plan, Incorporating Changes to Program to Implement Second Ten Yr Insp Interval ML20195G6741999-06-10010 June 1999 Forwards Insp Rept 50-440/99-03 on 990407-0517.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy PY-CEI-NRR-2407, Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records1999-06-0909 June 1999 Responds to NRC Re Violations Noted in Investigations Rept 3-98-005.Corrective Actions:Initiated Internal Investigation Into Matter to Discover Party Responsible for Falsification of Training Records 1999-09-09
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20212C0761999-09-15015 September 1999 Notification of 990930 Meeting with Firstenergy Nuclear Operating Co in Rockville,Md to Discuss Licensee Recent Submittal Requesting Five Percent Power Uprate ML20212J3201999-06-23023 June 1999 Forwards Proposed Change to STSs for Review & Comment.Change Would Remove TS Requirements for ESF Features to Be Operable After Sufficient Radioactive Decay Has Occurred to Ensure Off Site Doses Remain Below SRP Limits DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20205P6271999-04-14014 April 1999 Notification of 990428 Meeting with Util to Discuss Proposed Asset Transfer Between Duquesne Light Co & First Energy Nuclear Operating Co & Associated License Transfer of Beaver Valley Power Station Per 10CFR50.80 ML20205B8871999-03-26026 March 1999 Notification of 990415 Meeting with Utils in Knoxville,Tn to Visit Test Site & Discuss Test Program for ECCS Suppression Pool Suction Strainer.Context of Meeting Considered Entirely Proprietary ML20199L0511999-01-21021 January 1999 Notification of 990222 Meeting with Util in Rockville,Md for Ucs to Present Addl Info & Clarify Issues Raised in Two 10CFR2.206 Petitions Re River Bend Station & Perry Nuclear Power Plant ML20198R8831999-01-0707 January 1999 Forwards SER Accepting Licensee 971015 Request to Amend Perry Nuclear Power Plant TSs 5.2.2.e to Remove Reference to GL 82-12 & Require Administrative Controls Be Established Which Will Ensure Adequate Shift Coverage ML20196D9451998-11-30030 November 1998 Notification of 981204 Meeting with Centerior Svc Co in Rockville,Md to Discuss Proposed Revs to Licensing Basis for Feedwater Containment Isolation Valves ML20195B8551998-11-0909 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Proposed Revisions to Licensing Basis for Feedwater Containment Isolation Valves ML20238F8661998-09-0101 September 1998 Forwards Licensee Revs to Svc List for Placing in PDR ML20238F3341998-08-31031 August 1998 Notification of 980915 Meeting W/Centerior Service Co in Rockville,Md to Discuss Licensing Submittal Based Upon Revised Accident Source Term That Deletes MSIV Leakage Control Sys & Relaxes MSIV Leakage Limits ML20238F1861998-08-28028 August 1998 Notification of 980910 Meeting W/Centerior Service Co in Rockville,Md to Discuss Proposed Revs to Licensing Basis for Feedwater Containment Isolation Valves ML20238F5861998-08-28028 August 1998 Notification of 980909 Meeting w/BWR/6S:EOI & Listed Utils in Rockville,Md to Discuss W/Nrc Planned Applications by Licensees to Reduce Operability Requirements During Refueling Outages ML20248F4571998-06-0202 June 1998 Notification of 980625 Meeting W/Util in Rockville,Md to Discuss Analytical Testing Bases for Mark III ECCS Suction Strainer ML20216D8551998-04-14014 April 1998 Forwards Signed Original of Order Imposing Civil Monetary Penalty.Addl 5 Copies & Disk Encl,For Use.W/O Encl ML20217B8441998-03-0606 March 1998 Notification of Cancellation of 980331 Meeting in Rockville, MD to Discuss Proposed Testing Program for ECCS Suction Strainer ML20197B7831998-03-0606 March 1998 Notification of 980331 Meeting W/Ceic in Rockville,Md to Discuss Proposed Testing Program for ECCS Suction Strainer. (Proprietary Info Will Be Discussed) ML20199A3291997-11-13013 November 1997 Forwards NRC Operator Licensing Exam Rept 50-440/97-309OL on 970825-30 w/as-given Written Exam ML20199A3071997-11-13013 November 1997 Forwards NRC Operator Licensing Exam Rept (Included Completed & Graded Tests) for Tests Administered During Wk of 970825 ML20138D8451997-04-29029 April 1997 Notification of 970508 Meeting W/Clei in Rockville,Md to Discuss Priorities & Schedules of Licensing Issues for Plant ML20147J2271997-04-10010 April 1997 Forwards for Transmittal Notice of Proposed Merger for Perry Nuclear Power Plant,Unit 1 ML20136F9741997-03-13013 March 1997 Notification of 970324 Meeting W/Cleveland Electric Illuminating Co in Rockville,Md to Discuss Emergency Core Cooling Sys Suction Strainer 1/4 Scale Test Rept & to Discuss Acoustic Methodology Applied to Upper Lift Load ML20135E4781997-03-0505 March 1997 Notification of 970306 Meeting W/Cleveland Electric Illuminating Co in Rockville,Md to Review Emergency Core Cooling Sys Suction Strainer 1/4 Scale Test Rept.Meeting Cancelled ML20134Q1271997-02-25025 February 1997 Notification of 970306 Meeting W/Util in Rockville,Md to Review Emergency Core Cooling Sys Suction Strainer 1/4 Scale Test Rept & to Discuss Acoustic Methodology Applied to Upper Lift Load Reduction ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134P9011996-11-26026 November 1996 Notification of 961204 Meeting W/Clei & Teco in Rockville,Md to Discuss Potential Submittals Concerning Proposed Merger of Centerior Energy Co & Oec ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20149E8161994-08-0202 August 1994 Forwards Fr Notice of License Amend Requests Proposed Merger of Toledo Edison Co & Cleveland Electric Illumianting Co Antitrust Determination 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 ML20059E5031994-01-0606 January 1994 Forwards Results of on-site EQ Review of Related Info at Plant in Support of Staff Task Action to Identify & Address Existing EQ Issues & Concerns.Encl 1 Provides Results of Staff Review.Encl 2 Provides Draft Ltr to Transmit Info ML20058N4811993-12-15015 December 1993 Informs of Decision to Expand Senior Mgt Oversight of Selected Plants,Per Recent Meeting W/J Martin & H Miller. Lists Assignment of Managers,Effective Immediately ML20058M0351993-12-13013 December 1993 Notification of 931214 Meeting W/Licensee in Rockville,Md to Discuss Plant Fuel Failure Root Cause Analysis ML20057G3001993-10-15015 October 1993 Notification of 931028 Meeting W/Util in Rockville,Md to Discuss Plant Course of Action Plan to Improve Performance of Plant Over Next Several Yrs ML20057D5251993-09-0101 September 1993 Forwards 2.206 Petition Submitted by Capella,Wene & O'Connell Re Poor Performance of Plant.W/O Encl ML20056G0181993-08-26026 August 1993 Notification of 930902 Meeting W/Util in Rockville,Md to Discuss Facility IST ML20056E7141993-08-19019 August 1993 Notification of 930831 Meeting w/BWR-6 Owners Group in Rockville,Md to Discuss Pending Amend Submittals to Adopt Improved Standardized TS ML20062C2851990-10-18018 October 1990 Forwards Stipulation of Agreed Facts Between Licensee,Nrc Staff & Ohio Citizens for Responsible Energy, Signed by Three Parties.Original Stipulation Returned to Silberg. W/O Encl ML20059M0271990-09-17017 September 1990 Forwards Amend to Facility License,Removing cycle-specific Parameters from Tech Specs.W/O Encl ML20059H2091990-09-0505 September 1990 Provides Recipients & Hiatt W/Util Proposed Amend to Delete Values of cycle-specific Parameters of Each Core from Tech Specs ML20056A3641990-07-24024 July 1990 Requests Addition of Listed Name to Svc List for Plant Proceeding.W/Certificate of Svc.Served on 900726 ML20248D1391989-09-25025 September 1989 Forwards AEOD/T915, Ground Fault Detection & Trip Circuit at Perry Unit 1, Technical Review Rept.No Further AEOD Action Recommended,Based on Merits of Alarm Scheme for Resolution of Issue ML20248B5631989-06-0606 June 1989 Forwards,For Info,Aeod Diagnostic Evaluation Team Rept for Plant.Evaluation Initiated Following Discussions Held During Senior Managers Meeting in Dec 1988 ML20247E5711989-05-22022 May 1989 Notification of 890531 Meeting W/Util in Rockville,Md to Discuss Monthly Performance Rept ML20246L2701989-05-0909 May 1989 Forwards SALP Inputs for SALP 9 Rept,Including Info Obtained During Exams Reported in Exam Repts 50-440/OL-88-01 & 50-440/OL-88-02.Deficiencies Noted Re Failure to Provide Training on Auxiliary & Emergency Sys ML20246A2771989-05-0303 May 1989 Forwards SALP Input for May 1988 - May 1989,in Accordance W/ 890401 Memo ML20236E3261989-03-20020 March 1989 Forwards Assessment & Tech Spec Clarification Re 881212 Loss of 5-volt Dc Power Supply & Loss of Rod Display & Operator Control Modules.Restoration of Normal Rod Position Indication,Rather than rod-by-rod Indication,Proper ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20206C6041988-11-0808 November 1988 Discusses Review of 870227 Significant Precursor Event Re Two Inoperable Diesel Generators,Per R Dudley 881013 Note. Util Corrective Actions Appear Thorough & Comprehensive ML20205T5821988-11-0707 November 1988 Notification of 881115 Meeting W/Devonrue & Util in Rockville,Md to Discuss Proposed Std Alternate AC Design to Meet Station Blackout Rule ML20155J3931988-10-20020 October 1988 Notification of 881102 Meeting W/Util in Rockville,Md to Discuss Unit 1 Operating Performance.Proposed Agenda Encl 1999-09-15
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20212C0761999-09-15015 September 1999 Notification of 990930 Meeting with Firstenergy Nuclear Operating Co in Rockville,Md to Discuss Licensee Recent Submittal Requesting Five Percent Power Uprate ML20212J3201999-06-23023 June 1999 Forwards Proposed Change to STSs for Review & Comment.Change Would Remove TS Requirements for ESF Features to Be Operable After Sufficient Radioactive Decay Has Occurred to Ensure Off Site Doses Remain Below SRP Limits DD-99-05, Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action1999-04-20020 April 1999 Forwards Monthly Rept on Status of 10CFR2.206 Petition as of 990331.During March,Director'S Decision (DD-99-06) on Browns Ferry & DD on Army Corps of Engineers Was Issued & (DD-99-05) on Diablo Canyon Became Final Agency Action ML20205P6271999-04-14014 April 1999 Notification of 990428 Meeting with Util to Discuss Proposed Asset Transfer Between Duquesne Light Co & First Energy Nuclear Operating Co & Associated License Transfer of Beaver Valley Power Station Per 10CFR50.80 ML20205B8871999-03-26026 March 1999 Notification of 990415 Meeting with Utils in Knoxville,Tn to Visit Test Site & Discuss Test Program for ECCS Suppression Pool Suction Strainer.Context of Meeting Considered Entirely Proprietary ML20199L0511999-01-21021 January 1999 Notification of 990222 Meeting with Util in Rockville,Md for Ucs to Present Addl Info & Clarify Issues Raised in Two 10CFR2.206 Petitions Re River Bend Station & Perry Nuclear Power Plant ML20198R8831999-01-0707 January 1999 Forwards SER Accepting Licensee 971015 Request to Amend Perry Nuclear Power Plant TSs 5.2.2.e to Remove Reference to GL 82-12 & Require Administrative Controls Be Established Which Will Ensure Adequate Shift Coverage ML20196D9451998-11-30030 November 1998 Notification of 981204 Meeting with Centerior Svc Co in Rockville,Md to Discuss Proposed Revs to Licensing Basis for Feedwater Containment Isolation Valves ML20195B8551998-11-0909 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Proposed Revisions to Licensing Basis for Feedwater Containment Isolation Valves ML20238F8661998-09-0101 September 1998 Forwards Licensee Revs to Svc List for Placing in PDR ML20238F3341998-08-31031 August 1998 Notification of 980915 Meeting W/Centerior Service Co in Rockville,Md to Discuss Licensing Submittal Based Upon Revised Accident Source Term That Deletes MSIV Leakage Control Sys & Relaxes MSIV Leakage Limits ML20238F1861998-08-28028 August 1998 Notification of 980910 Meeting W/Centerior Service Co in Rockville,Md to Discuss Proposed Revs to Licensing Basis for Feedwater Containment Isolation Valves ML20238F5861998-08-28028 August 1998 Notification of 980909 Meeting w/BWR/6S:EOI & Listed Utils in Rockville,Md to Discuss W/Nrc Planned Applications by Licensees to Reduce Operability Requirements During Refueling Outages ML20248F4571998-06-0202 June 1998 Notification of 980625 Meeting W/Util in Rockville,Md to Discuss Analytical Testing Bases for Mark III ECCS Suction Strainer ML20216D8551998-04-14014 April 1998 Forwards Signed Original of Order Imposing Civil Monetary Penalty.Addl 5 Copies & Disk Encl,For Use.W/O Encl ML20217B8441998-03-0606 March 1998 Notification of Cancellation of 980331 Meeting in Rockville, MD to Discuss Proposed Testing Program for ECCS Suction Strainer ML20197B7831998-03-0606 March 1998 Notification of 980331 Meeting W/Ceic in Rockville,Md to Discuss Proposed Testing Program for ECCS Suction Strainer. (Proprietary Info Will Be Discussed) ML20199A3071997-11-13013 November 1997 Forwards NRC Operator Licensing Exam Rept (Included Completed & Graded Tests) for Tests Administered During Wk of 970825 ML20199A3291997-11-13013 November 1997 Forwards NRC Operator Licensing Exam Rept 50-440/97-309OL on 970825-30 w/as-given Written Exam ML20138D8451997-04-29029 April 1997 Notification of 970508 Meeting W/Clei in Rockville,Md to Discuss Priorities & Schedules of Licensing Issues for Plant ML20147J2271997-04-10010 April 1997 Forwards for Transmittal Notice of Proposed Merger for Perry Nuclear Power Plant,Unit 1 ML20136F9741997-03-13013 March 1997 Notification of 970324 Meeting W/Cleveland Electric Illuminating Co in Rockville,Md to Discuss Emergency Core Cooling Sys Suction Strainer 1/4 Scale Test Rept & to Discuss Acoustic Methodology Applied to Upper Lift Load ML20135E4781997-03-0505 March 1997 Notification of 970306 Meeting W/Cleveland Electric Illuminating Co in Rockville,Md to Review Emergency Core Cooling Sys Suction Strainer 1/4 Scale Test Rept.Meeting Cancelled ML20134Q1271997-02-25025 February 1997 Notification of 970306 Meeting W/Util in Rockville,Md to Review Emergency Core Cooling Sys Suction Strainer 1/4 Scale Test Rept & to Discuss Acoustic Methodology Applied to Upper Lift Load Reduction ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134P9011996-11-26026 November 1996 Notification of 961204 Meeting W/Clei & Teco in Rockville,Md to Discuss Potential Submittals Concerning Proposed Merger of Centerior Energy Co & Oec ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20149E8161994-08-0202 August 1994 Forwards Fr Notice of License Amend Requests Proposed Merger of Toledo Edison Co & Cleveland Electric Illumianting Co Antitrust Determination 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 ML20059E5031994-01-0606 January 1994 Forwards Results of on-site EQ Review of Related Info at Plant in Support of Staff Task Action to Identify & Address Existing EQ Issues & Concerns.Encl 1 Provides Results of Staff Review.Encl 2 Provides Draft Ltr to Transmit Info ML20058N4811993-12-15015 December 1993 Informs of Decision to Expand Senior Mgt Oversight of Selected Plants,Per Recent Meeting W/J Martin & H Miller. Lists Assignment of Managers,Effective Immediately ML20058M0351993-12-13013 December 1993 Notification of 931214 Meeting W/Licensee in Rockville,Md to Discuss Plant Fuel Failure Root Cause Analysis ML20057G3001993-10-15015 October 1993 Notification of 931028 Meeting W/Util in Rockville,Md to Discuss Plant Course of Action Plan to Improve Performance of Plant Over Next Several Yrs ML20057D5251993-09-0101 September 1993 Forwards 2.206 Petition Submitted by Capella,Wene & O'Connell Re Poor Performance of Plant.W/O Encl ML20056G0181993-08-26026 August 1993 Notification of 930902 Meeting W/Util in Rockville,Md to Discuss Facility IST ML20056E7141993-08-19019 August 1993 Notification of 930831 Meeting w/BWR-6 Owners Group in Rockville,Md to Discuss Pending Amend Submittals to Adopt Improved Standardized TS ML20062C2851990-10-18018 October 1990 Forwards Stipulation of Agreed Facts Between Licensee,Nrc Staff & Ohio Citizens for Responsible Energy, Signed by Three Parties.Original Stipulation Returned to Silberg. W/O Encl ML20059M0271990-09-17017 September 1990 Forwards Amend to Facility License,Removing cycle-specific Parameters from Tech Specs.W/O Encl ML20059H2091990-09-0505 September 1990 Provides Recipients & Hiatt W/Util Proposed Amend to Delete Values of cycle-specific Parameters of Each Core from Tech Specs ML20056A3641990-07-24024 July 1990 Requests Addition of Listed Name to Svc List for Plant Proceeding.W/Certificate of Svc.Served on 900726 ML20248D1391989-09-25025 September 1989 Forwards AEOD/T915, Ground Fault Detection & Trip Circuit at Perry Unit 1, Technical Review Rept.No Further AEOD Action Recommended,Based on Merits of Alarm Scheme for Resolution of Issue ML20248B5631989-06-0606 June 1989 Forwards,For Info,Aeod Diagnostic Evaluation Team Rept for Plant.Evaluation Initiated Following Discussions Held During Senior Managers Meeting in Dec 1988 ML20247E5711989-05-22022 May 1989 Notification of 890531 Meeting W/Util in Rockville,Md to Discuss Monthly Performance Rept ML20246L2701989-05-0909 May 1989 Forwards SALP Inputs for SALP 9 Rept,Including Info Obtained During Exams Reported in Exam Repts 50-440/OL-88-01 & 50-440/OL-88-02.Deficiencies Noted Re Failure to Provide Training on Auxiliary & Emergency Sys ML20246A2771989-05-0303 May 1989 Forwards SALP Input for May 1988 - May 1989,in Accordance W/ 890401 Memo ML20236E3261989-03-20020 March 1989 Forwards Assessment & Tech Spec Clarification Re 881212 Loss of 5-volt Dc Power Supply & Loss of Rod Display & Operator Control Modules.Restoration of Normal Rod Position Indication,Rather than rod-by-rod Indication,Proper ML20235S6271989-02-28028 February 1989 Notification of 890307 Meeting W/Bwr Owners Group in Rockville,Md to Discuss Items of Current Interest.Agenda Encl ML20206C6041988-11-0808 November 1988 Discusses Review of 870227 Significant Precursor Event Re Two Inoperable Diesel Generators,Per R Dudley 881013 Note. Util Corrective Actions Appear Thorough & Comprehensive ML20205T5821988-11-0707 November 1988 Notification of 881115 Meeting W/Devonrue & Util in Rockville,Md to Discuss Proposed Std Alternate AC Design to Meet Station Blackout Rule ML20155J3931988-10-20020 October 1988 Notification of 881102 Meeting W/Util in Rockville,Md to Discuss Unit 1 Operating Performance.Proposed Agenda Encl 1999-09-15
[Table view] Category:NRC TO ASLP
MONTHYEARML20210J5121986-09-30030 September 1986 Advises That Time for Commission Toreview Decisions ALAB-841 & ALAB-844 Expired.Commission Declined Review.Decisions Became Final Agency Action on 860929.Served on 860930 ML20203L9891986-08-28028 August 1986 Requests That Participants Confirm Intentions to Appear at Commission 860905 Meeting to Consider Full Power OL by C.O.B. on 860903.Served on 860829 ML20137U0781985-12-0505 December 1985 Informs That Time Provided by NRC Regulations for Commission to Act to Review ALAB-820 Expired.Commission Declined Review.Decision Became Final Agency Action on 851203.Served on 851205 ML20133H8621985-10-15015 October 1985 Informs of Palladino 851029 Site Tour.One Representative of Each Party Will Be Permitted to Join Tour.Participant Should Notify Pj Polk or J Grobe & Licensee Re Attendance by 851022 ML20134H3171985-08-21021 August 1985 Forwards MR Edelman Re Preoperational Testing of Tdi Diesel Generators.Related Correspondence ML20134C7771985-08-13013 August 1985 Forwards Correspondence Re Util Agreement to Fully Comply W/ Commission Response to Remand by Us Court of Appeals in Guard Vs Nrc.Related Correspondence ML20128Q1471985-07-24024 July 1985 Forwards Recent Correspondence Re post-100 H Insps & Tests of Tdi Diesel Generators at Plant.Ltr Previously Forwarded to Parties.Related Correspondence ML20128M4451985-07-23023 July 1985 Informs That Hiatt 850710 Request Directing Applicants to File Rept of Proposed Merger Unrelated to Issues Pending Before Aslb.Assumption That Proposed Merger Will Escape Review Incorrect.Related Correspondence ML20129K0781985-07-19019 July 1985 Forwards Util Correspondence Re Compliance W/Requirements Described in Sser 6 Concerning Tdi Diesel Generators.Related Correspondence ML20132G9421985-07-17017 July 1985 Forwards Util Re Applicability of Recent 10CFR21 Notifications by Tdi to Diesel Generators at Plant.Related Correspondence ML20127M9381985-06-21021 June 1985 Forwards Util to NRC Indicating Anticipated Fuel Load Readiness Date for Plant Changed from June 1985 to Sept 1985,as Suppl to Silberg .Related Correspondence ML20128P0361985-05-31031 May 1985 Advises That Time for Commission to Review ALAB-805 Expired. Commission Declined Review.Decision Became Final Agency Action on 850520.Served on 850531 ML20128G4301985-05-22022 May 1985 Forwards Commission Policy Statement Re Effect of Guard Decision 1 on Adequacy of Medical Svcs Required by 10CFR50.47(b)(12).W/o Statement.Related Correspondence ML20058H6631982-08-0505 August 1982 Advises That NRC Will File No Response to Sunflower Alliance 820621 Motion to Compel Discovery from Applicant 1986-09-30
[Table view] |
Text
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y Ig UNITED STATES
, 3 ' p, NUCLEAR REGULATORY COMMISSION 00Cyc7 h[,'e.( /. j WASHINGTON,0. C. 20555 U$hhC
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July 19,1985
'65 gd 22 g 3RR in y James P.'Gleasoi, Chairman Dr. Jerry R. Kline N.$7{A$CS BR T Administrative Judge -
Administrative Judge 513 Gilmoure Drive Atomic Safety and Licensing Board Silver Spring, MD 20901 U.S. Nuclear Regulatory Comission Washington, DC 20555 Mr. Glenn 0. Bright Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, DC 20555 In the Matter of CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.
(Perry Nuclear Power Plant, Units 1 and 2)
Docket Nos. 50-440 OL, 50-441 0L
Dear Administrative Judges:
For your information I am forwarding to you recent correspondence from Cleveland Electric Illuminating Company concerning compliance with certain requirements described in SSER 6 concerning the Transamerica Delaval, Inc.
diesel generstors at the Perry plant.
Sincerely, .
Colleen P. Woodhead Counsel for NRC Staff
Enclosure:
As stated cc w/ enclosure: Mr. Silberg Ms. Hiatt Mr. Lodge cc w/o enclosure: Rest of service list 850723036585g49 PDR ADOCK 05 PDR. [
50
1 PO BOX $000 - CLEVELAND. oHlo 44101 - TELEPHONE (216) 622-9600 - ILLUMINATING BLOG - 55 PUsLICSQUARE
. Serving The Best Location in the Nation MURRAY R. EDELMAN VICE MESIDENT NUC LE A R ,
' June 28, 1985 PY-CEI/NRR-0277 L Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing ~
U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 SER Confirmatory Issue 63 TDI Diesel Generator Reliability
Dear Mr. Youngblood:
Attached is our response to the seven (7) questions, regarding TDI Diesel Generator Reliability, constituting Confirmatory Issue 63 as requested in Safety Evaluation Report Supplement 6 (Attachment 1). An additional item, conformance with the testing guidelines of Regulatory Guide 1.108, is also addressed (Attachment 2).
If you have any questions, please feel f ree to call.
Very truly ours d W Murray R. Edelman Vice President Nuclear Group MRE:njc Attachments cc: Jay Silberg, Esq.
John Stefano (2)
J. Grobe b I l R 850628-----
E $aCK05000440 -
PDR L )
F Attcchment 1 PY-CEI/NRR-0277 L s
Question 1:
Submit the maintenance and surveillance program that CEI intends to use on the Perry enginea for staff approval. The staff will review this program to the same extent it has those on other engines (e.g., Comanche Peak, Grand Gulf, and Catawba). .
Response: -
PNPP will utilize the maintenance and surveillance program developed by the TDI Owners Group. This program is included as Appendix II to the Design Review and Quality Revalidation (DR/QR) report which was submitted to the staff on January 17, 1985 (PY-CEI/NRR-0156 L) and revised March 18, 1985 (PY-CEI/NRR-0203 L).
Question 2:
Perform a torsiograph test that includes both variable speed tests and variable load tests and a subsequent stress analysis that confirms that stresses in the crankshaft are acceptable.
Response
A torsiograph testing program which included variable speed and variable load tests was performed on each Unit 1 engine. The test report, submitted to the staff on June 14, 1985, concludes that the crankshafts are adequate for their intended use at Perry.
Questions 3:
Address the effects of engine imbalance on crankshaft adequacy as part of the torsiograph test report to be submitted to the staff.
Response
A special imbalance torsiograph test was conducted on each Unit 1 engine. The test results are addressed in the addendum to the torsiograph test report submitted on June 14, 1985.
Question 4:
Confirm that Owners Group recommendations have been followed regarding:
(a) random sample testing of pushrods (b) proper torquing of the jacket water pump shafts
Response
(a) Destructive random sample testing to verify the weld quality of future friction welded pushrods is recommended by the TDI Owners Group. Tais will be done. The pushrods that are presently installed have been subjected to the inspections required by the DR/QR including:
I
Q Attachment 1 3 PY-CEI/NRR-0277 L
._- Verification that the main and connector p.ushrods are friction welded.
Performance of a liquid penetrant test on all friction welded main and connector pushrods, or, as an alternative, visual inspection. No surface cracks were found along the bond line
- between the rod end and the tube.
- b. The Owners Group recommen'ds torquing the castle nut on the engine drive jacket water pump shaft to a value between 120 and 660 ft-lbs.
The Division 2 pump was dissassembled and reassembled onsite with the castle nut torqued to 120 ft-lbs. A rebuilt jacket water pump assembled at the factory, was installed on the Division i engine.
Castle nut torque was not verified during the Division 1 engine revalidation effort. It will be verified during the post operation (approx. 100 hrs.) inspection.
Question 5:
Demonstrate the adequacy of control panel assembly / panel system.
Response
The control panel assembly / panel system for PNPP has been found to be acceptable per the requirements of the DR/QR. Inspection results were submitted to the staf f by letter PY-CEI/NRR-0188L dated February 8,1985.
Inspections were performed in* accordance with the Component Quality Revalidation Checklist prepared for Perry by the Owners Group. Original issue of the PNPP DR/QR contained the Component Design Review Checklist for the Vogtle Plant. This was in error. Subsequent revision to the DR/QR on March 18,1985 (PY-CEI/NRR-0203L) corrected this error.
Question 6:
Demonstrate the adequacy of the bearing stresses on the chock plates.
Response
Minimum load surfaces for the chock plates used on the PNPP engines have been calculated, and in all cases, the actual field measurements of the bearing surfaces exceed the calculated minimum requirements. Additionally, hot and cold crankshaft deflection measurements have also been taken. These measurements show that deflection is well within she acceptable limits established by the manufacturer. This indicates that the engine is properly supported.
Question 7: ,
Replace the 4R cylinder head with one that does not contain a through-wall weld repair where the repair was performed from one side only, or demonstrate that the present cylinder head does not contain such a repair.
k
t Attachment 1 s
PY-CEI/NRR-0277 L Response: ,
Cylinder head 4R (serial #A76) does not contain a through-wall weld repair performed from one side only. Details were provided to the staff by letter dated February 21, 1985 (PY-CEI/NRR-0198 L). Transcripts from the ASLB hearing on the P,NPP diesel generators (Issue 16), also address this issue (pages 2428 and 2429). .
All PNPP TDI engine cylinder heads were returned to Transamerica Delaval, Inc.
(TDI) to be reconditioned in accordance with the latest recommendations established by the TDI Owners Group. This included reworking the valve seats, water discharge ports, steam vent hole, and injector hole. Additionally each head was stress relieved and pickled. Upon completion of the rework, cyclinder head 4R (serial IA76) was inspected by a CEI representative and rejected because of combustioa face (fire deck wall) pitting and weld indications.
These indications were excavated (not through wall), and built up with weld .
material per accepted procedures. The CEI representative reinspected the head and found it acceptable.
l l
l
)
e Attachment 2 PY-CEI/NRR-0277 L Conformance with the Testing Guidelines of Regulatory Guide 1.108 CEI responded to NRC Safety Review question 430.94 in Amendment 8 to the FSAR (August, 1982) by stating that testing would be performed in accordance with R.G. 1.108 except for the provisions in position C.2.a.(3). Position C.2.a.(3) states: , ,
C.2.a. (3) Demonstrate full-load-carrying capability for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, of which 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> should be at a load equivalent to the continuous ~ rating of the diesel generator and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at a load equivalent to the 2-hour rating of the diesel generator. Verify that voltage and frequency requirements are maintained. The test should also verify that the cooling system functions within design limits.
We agreed in our 1982 response to " demonstrate full-load-carrying capability _
for an interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a load equivalent to the continuous rating of the diesel generator" (7000KW), but took exception to testing for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at a load equivalent to the 2-hour rating of the diesel generator. Our position was based upon the f act that the maximum continuous load on the Division 2 diesel generator is only 5634 KW, and Division 1 only 4668 KW. The diesel generators are not expected to operate above the 5634(4668) KW maximum continuous calculated load and therefore testing at the continuous load rating of the diesel generators, (7000 KW = 24% above 5634 KW) is more than adequate to demonstrate their ability to reliably perform their intended safety function. Testing at the 2-hour rating (7700KW) for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> would appear to be unnecessary in this application since the maximum continuous load is so much lower than the rating of the diesel generators (i.e., the diesel generators were purchased oversized so that they would not be forced to operate near their limits).
An additional consideration in taking exception to testing at the 2-hour rating was to limit operating time at or near maximum rated conditions, since operating under these conditions may lead to shortened diesel generator life.
This f act has been borne out in other industrial diesel generator applications.
Therefore, since it appeared to serve no useful purpose (maximum load much less than the rated load) and in consideration of the above stated industrial experience, we took exception to verbatim compliance with position C.2.a.(3) of R.G. 1.108. Table 1.8 of the FSAR was revised in Amendment 12 (July, 1983) to reflect this exception to R.G. 1.108.
NRC endorsed this exception in Safety Evaluation Report Supplement (SSER) #4 (February,1984) and subsequently suspended their endorsement in SSER #5 (February, 1985) due to TDI Diesel Generator concerns raised in early 1984, pending review of the TDI Diesel Generator Owners Group recommendations.
SSER #6 (Apri1 1985) summarizes actions taken to date with respect to the TDI Diesel Generators and concludes:
With respect to the TDI diesel generators at Perry Unit 1, the staff concludes that actions already taken by the applicant, and those proposed to be performed before licensing, are adequate to ensure that the TDI diesel generators at Perry Unit I can reliably generate emergency onsite power.
o
I ,
Attechnent 2 PY-CEI/NRR-0277 L 6
This conclusion is based on (1) the TDI Owners Group program and staff review of that program; (2) preliminary findings by PNL on the 16 Phase 1 generic co*mponents; (3) staff review of the adequacy of the Phase 1 components at Perry Unit 1, including the results of the recent teardown and inspection; (4) the Phase 2 DR/QR review conducted thus far by PNL for Comanche Peak Unit i diesel generators and the similarity of the Perry diesel, generators to those at Comanche Peak; (5) previous staff conclusions on similar engines at Comanche Peak, Grand Gulf, and Catawba; (6) the proposed preoperational testing program at Perry; and (7) the applicant's commitment not to use any cylinder heads that have had throughwall weld repairs where the repair was performed from one side only.
Preoperational testing, Item 6 of this conclusion, has been completed with the exception of the Loss of Offsite Power Test. We have performed a continuous rating test for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 7000 KW. We still believe it prudent to not test the diesel generators at the 2-hour rating (7700KW) and are proceeding on the -
assumption that NRC will maintain their conclusions made in SSER #6.
The FSAR, Table 1.8-1 will be further clarified in a future amendment to reflect the above discussion.
..