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MONTHYEARPY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F3901999-10-14014 October 1999 Discusses Request That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:OUTGOING CORRESPONDENCE
MONTHYEARML20217F3901999-10-14014 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 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 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 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 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 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 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 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 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 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 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 ML20207G3921999-06-0808 June 1999 Forwards Notice of Consideration of Approval of Transfer of License DPR-58 & Issuance of Conforming Amend & Opportunity for Hearing Re 990505 Application ML20207B7341999-05-26026 May 1999 Forwards Correction of Typo in TS Table 3.3.6.1-1 for Plant, Unit 1 DD-99-08, Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 9905211999-05-20020 May 1999 Informs That to Extent That Union of Concerned Scientists Requests Commission Undertake Formal Review of DD-99-08 & Hold Meeting to Directly Receive View on Decision,Request Denied.With Certificate of Svc.Served on 990521 ML20207B1251999-05-20020 May 1999 Discusses Investigation Rept 3-98-007 on 981210 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000 IR 05000440/19980181999-05-14014 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-440/98-18 on 981110 ML20206Q5181999-05-14014 May 1999 Responds to to SL Hiatt Re Fee Exemption Granted to Firstenergy Nuclear Operating Co,Operator of Perry Nuclear Plant.Action Consistent with Longstanding Policy & Practice,As Well as Legal Requirements ML20196F8081999-05-12012 May 1999 Partially Deleted Ltr Referring to Investigation Case 3-1998-007 Re Determination Whether Recipient Discriminated Against Radiation Protection Supervisor at Perry for Providing Testimony as Witness in DOL Hearing ML20206Q0171999-05-12012 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created ML20206S5381999-05-12012 May 1999 Forwards Insp Rept 50-440/99-07 on 990412-16.No Violations Noted.Insp Consisted of Selective Exam of Procedures & Representative Records,Interviews with Personnel & Observation of Activities in Progress ML20206Q2111999-05-10010 May 1999 Discusses Investigation Rept 3-98-005,completed on 990129 & Forwards NOV & OI Rept Synopsis.Circumstances Surrounding Apparent Falsification of Training Records for Individuals Assigned Position in Er Organization Were Investigated ML20196A2961999-05-10010 May 1999 Discusses Investigation Rept 3-98-005 Conducted on 990129 Re Circumstances Surrounding Apparent Falsification of Training Records for Individuals Assigned Positions in Emergency Response Organization & Forwards NOV & Synopsis ML20206H3981999-05-0606 May 1999 Forwards Insp Rept 50-440/99-06 on 990303-04 & 0412-16.No Violations Noted.Inservice Insp Activities Effectively Implemented with Several Aspects Demonstrating Good Safety Focus ML20206N3161999-05-0606 May 1999 Responds to Ltr to NRC on Continued Events Re Transfer of Generation Assets Between Dl & Firstenergy.Info Will Be Considered as NRC Monitor Pending License Transfer Application of Bvps,Units 1 & 2 & Pnpp ML20206H6731999-05-0505 May 1999 Confirms Discussion Between Members of NRC & Recipient Re Meeting Scheduled for 990520 in Lisle,Il to Discuss Operational Issues & Related Topics of Interest to Licensed Operators at Nuclear Power Plants Located in Region III ML20206G6901999-05-0303 May 1999 Forwards Insp Rept 50-440/99-02 on 990225-0406.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206G6401999-05-0303 May 1999 Forwards Safety Evaluation Authorizing Relief Requests IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp.Relief Requests IR-36 & IR-41 Withdrawn ML20206D4701999-04-30030 April 1999 Informs That on 990428,FirstEnergy Submitted Post Exam Results of Weld Overlay Repair for Feedwater Nozzle to safe-end Weld at Perry Nuclear Power Plant,Unit 1 (Pnpp) ML20206E2111999-04-29029 April 1999 Discusses Alternative Proposed by Licensee on 990325 & 990401 to ASME BPV Code,Section XI Repair Requirements Along with Separate Alternative to Ultrasonic Exam Acceptance Criteria.Forwards SE Approving Proposed Alternatives ML20205P4041999-04-15015 April 1999 Discusses GL 95-07 Issued by NRC on 950817 & Licensee Responses Submitted on 951016,960213 & 960624 for Perry NPP, Unit 1.Forwards Safety Evaluation Concluding That Licensee Adequately Addressed Actions Requested in GL 95-07 ML20205P0281999-04-12012 April 1999 Provides Individual Exam Results for Applicants Who Took Mar 1999 Initial License Exam.Information Considered Proprietary in Accordance with 10CFR2.790.Without Encls ML20205J5331999-04-0606 April 1999 Ack Receipt of Denying Request from NRC That Addl Info Be Provided Prior to Informal Public Hearing Held on 990222 Re River Bend Station & Perry Nuclear Power Plant 10CFR2.206 Petitions ML20205K5211999-04-0505 April 1999 Forwards Notice of Withdrawal of 970409 LAR on Refueling Interlocks,In Response to Util .Amend Request Will Be Replaced in Future by Similar Request,Based on Approved STS Change Traveler,Number TSTF-225 ML20196K8461999-04-0202 April 1999 Forwards Insp Rept 50-440/99-05 on 990301-05.No Violations Noted.Informs That Licensee Use of 10-Minute Rule & 4-Hour Rule Remains Under NRC Review.Expresses Re Practice Revising Unavailability Criteria on Recurrent Basis ML20205G3891999-03-31031 March 1999 Forwards Safety Evaluation Re Second ten-year Inservice Testing Program Relief Requests.Proposed Alternatives in Relief Requests VR-6,PR-3 & PR-6 May Be Authorized.Relief Request VR-8 Denied ML20205G0441999-03-26026 March 1999 Advises of Planned Insp Effort Resulting from Perry PPR Review,Which Was Completed on 990202.Overall,performance at Perry Was Acceptable ML20205F0011999-03-25025 March 1999 Responds to Re Safety of Perry Nuclear Power Plant & That Plant Operating with Limited Leaks in Three Fuel Rods for Several Months.Informal Public Hearing Re Leaks at Perry Facility Held in Rockville,Md on 990222 ML20205C1611999-03-25025 March 1999 Discusses GL 96-05 Issued on 960918 & Firstenergy 961118, 970317 & 980930 Responses to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verification at Perry Npp.Forwards RAI Re GL 96-05 Program ML20204D8891999-03-17017 March 1999 Forwards Insp Rept 50-440/99-04 on 990222-26.No Violations Noted.Insp Focused on Radiological Planning for Spring 1999 Refueling Outage,On Assessments of Radiation Protection Program & on Radiological Training for General Employees ML20204E7791999-03-17017 March 1999 Forwards Insp Rept 50-440/99-01 on 990113-0224.Non-cited Violation Was Identified ML20207H9921999-03-11011 March 1999 Informs That Requirements to Pay Fee Under 10CFR170 for Review of Pilot Plant Application for Use of Revised Accident Source Term Methodology for Perry Nuclear Power Plant Unit 1,waived for Reasons Stated ML20207K1991999-03-0404 March 1999 Forwards List of Names of Those Individuals & Their Organizational Affiliation as Appropriate,Who Spoke at Informal Public Hearing Re Petitions Filed Pursuant to 10CFR2.206 for River Bend & Perry Plants on 990222 ML20203F8501999-02-11011 February 1999 Forwards Fr Notice to Be Published on 990219 Re Informal 10CFR2.206 Public Hearing Including Video Teleconferencing 1999-09-09
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, . - . ~
4 g-
- y. December- 23, 1993 $
'Dockht No. 50-440-t Mr. Robert A. Stratman
'.Vice President Nuclear - Perry l
.Centerior Service Company i P.O. Box 97, S270 Perry, Ohio 44081 l
Dear Mr. Stratman:
SUBJECT:
REVISED REQUEST FOR ADDITIONAL'INFORMATION REGARDING GENERIC LETTER 92-08, "THERMO-LAG 330-1 FIRE BARRIERS," PURSUANT TO 10 CFR 50.54(F), PERRY NUCLEAR POWER PLANT, UNIT N0. 1 ;
The enclosure contains a revised request for information pursuant to 10-CFR, ,
Part 50.54(f) that was previously issued to you on December 20, 1993. The principal changes are located .in item I.B.2. of the request for additional ,
information. We apologize if this has caused y my nconvienience. Should you have any questions, please contact yot:r Project Manager, Robert Stransky at (301).504-1346. ,
Sincerely, Brian Grimes /for ,
L. J. Callan Acting Associate Director-for_ Projects Office of Nuclear Reactor Regulation :'
Enclosure:
Request for Additional Information cc w/ enclosure: t See next page DISTRIBUTION i Docket File CMcCracken MGamberoni RStransky .
NRC PDR PMadden RIngram, PMSB MRushbrook !
Local PDR CBerlinger JMartin, RIII GMulley (0IG)
JHannon RJenkins OGC EPawlik (RIII/01): 1 JRoe GMulley (0IG) ACRS (10) JZwolinski :
LCallano c[/ t 0FFICE LA:PD33h/n PM:PD33 PD:PD33 . AD/[// 1 NAME MRushbrook RStran'blik7 JHannobb J. ((LA[
DAT'E 12/ U /93 ll2M/93 12/0/93 12/7f/93 COPY- /fe/No /I$s)No [es/No Yes/No 0FFICIAL REGORD COPY -FILENAME: G:tPERRY\lHERMO.LT2 9401030277 931223 PDR ADOCK 05000440 ygn3 I h hf
o p oc ,I t UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055541001
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..... December 23, 1993 Docket No. 50-440 ,
Mr. Robert A. Stratman Vice President Nuclear - Perry Centerior Service Company P.O. Box 97, S270 Perry, Ohio 44081
Dear Mr. Stratman:
SUBAu f: REVISED REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER ,
92-08, " THERM 0-LAG 330-1 FIRE BARRIERS," PURSUANT 10 10 CFR 50.54(F), PERRY NUCLEAR POWER PLANT, UNIT NO. 1 The enclosure contains a revised request for information pursuant to 10 CFR, Part 50.54(f) that was previously issued to you on December 20, 1993. The principal changes are located in item I.B.2. of the request for additional information. We apologize if this has caused you any inconvienience. Should ,
you have any questions, please contact your Project Manager, Robert Stransky at (301) 504-1346.
7 S i,n.cprely, g ,,
i I A
/
# L. J. Callan '
, Acting Associate Director for Projects Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page t
Mr. Robert A. Stratman Perry Nuclear Power Plant Centerior Service Company Unit Nos. I and 2 cc:
Jay E. Silberg, Esq. Mr. James W. Harris, Director Shaw, Pittman, Potts & Trowbridge Division of Power Generation i 2300 N Street, N.W. Ohio Department of Industrial Relations !
Washington, D.C. 20037 P. O. Box S25 Columbus, Ohio 43216 Mary E. O'Reilly Centerior Energy Corporation The Honorable Lawrence Logan 300 Madison Avenue Mayor, Village of Perry Toledo, Ohio 43652 4203 Harper Street Perry, Ohio 44081 Resident Inspector's Office The Honorable Robert V. Orosz U.S. Nuclear Regulatory Commission Mayor, Village of Ncrth Perry Parmly at Center Road North Perry Village Hall Perry, Ohio 44081 4778 Lockwood Road North Perry Village, Ohio 44081 Regional Administrator, Region III r U.S. Nuclear Regulatory Commission Attorney General '
801 Warrenville Road Department of Attorney General '
Lisle, Illinois 60532-4351 30 East Broad Street Columbus, Ohio 43216 Lake County Prosecutor Lake County Administration Bldg. Radiological Health Program 105 Main Street Chio Department of Health Painesville, Ohio 44077 Post Office Box 118 Columbus, Ohio 43266-0118 Ms. Sue Hiatt OCRE Interim Representative Ohio Environmental Protection Agency 8275 Munson DERR--Compliance Unit Memtor, Ohio 44060 ATIN: Zack A. Clayton P. O. Box 1049 Terry J. Lodge, Esq. Columbus, Ohio 43266-0149 618 N. Michigan Street, Suite 105 Toledo, Ohio 43624 Mr. Thomas Haas, Chairman Perry Township Board of Trustees Ashtabula County Prosecutor 3750 Center Rd., Box 65 25 West Jefferson Street Perry, Ohio 44081 Jefferson, Ohio 44047 State of Ohio Mr. Kevin P. Donovan Public Utilities Commission Cleveland Electric Illuminating Company East Broad Street Perry Nuclear Power Plant Columbus, Ohio 43266-0573 P. O. Box 97, E-210 Perry, Ohio 44081 David P. Igyarto, General Manager Cleveland Electric Illuminating Company 6 James R. Williams, Chief of Staff Perry Nuclear Power Plant Ohio Emergency Management Agency P. O. Box 97, SB306 2825 West Granville Road Perry, Ohio 44081 Worthington, Ohio 43085
t ENCLOSURE REQUEST FOR ADDITIONAL'INFORMATION REGARDING GENERIC LETTER 92-08
" THERM 0-LAG 330-1 FIRE BARRIERS" PURSUANT TO 10 CFR 50.54(f) .;
I. Thermo-Lag Fire Barrier Configurations and Amounts A. Discussion Generic Letter (GL) 92-08,"Thermo-Lag 330-1 Fire Barriers," applied :
to all I-hour and all 3-hour Thermo-Lag 330-1 materials and barrier !
systems constructed by any assembly method, such as by joining preformed panels and conduit preshapes, and trowel, spray, and :
brush-on applications. This includes all fire barriers, all i barriers to achieve physical independence of electrical systems, radiant energy heat shields, and barriers installed to enclose intervening combustibles.
B. Required Information
- 1. Describe the Thermo-Lag 330-1 barriers installed in the plant to
- a. meet 10 CFR 50.48 or Appendix R to 10 CFR Part 50,
- b. support an exemption from Appendix R,
- c. achieve physical independence of electrical systems, <
- d. meet a condition of the plant operating license, ,
- e. satisfy licensing commitments.
The descriptions should include the following information: ,
the intended purpose and fire rating of the barrier (for -
example, 3-hour fire barrier,1-hour fire barrier, radiant energy heat shield), and the type and dimension of the ,
barrier (for example, 8-ft by 10-ft wall, 4-ft by 3-ft by i 2-ft equipment enclosure, 36-inch-wide cable tray, or 3-inch-diameter conduit). ;
- 2. For the total population of Thermo-Lag fire barriers described under Item I.B.1, submit an approximation of: ;
- a. For cable tray barriers: the total linear feet and square feet of 1-hour barriers and the total linear feet and square feet of '-hour barriers.
- b. For conduit barriers: the total linear feet of 1-hour <
barriers and the total linear feet of 3-hour barriers.
- c. For all other fire barriers: the total square feet of 1-hour barriers and the . total square feet of 3-hour ;
barriers.
- d. For all other barriers and radiant energy heat I shields: the total linear or square feet of 1-hour barriers and the total linear or square feet of 3-hour barriers, as appropriate for the barrier configuration. '
or type.
- l II. Important Barrier Parameters A. Discussion In a letter of July 29, 1993, from A. Marion, NUMARC, to C. McCracken, NRC, NUMARC stated: " Relative to bounded configurations, ... (i]t will be the utilities' responsibility to verify their baseline installations are bounded." Furthermore, i NUMARC stated that the parameters of importance fcr utility use of data from the industry Thermo-Lag fire barrier test program are:
- 1. Raceway orientation (horizontal, vertical, radial bends)
- 2. Conduit
- 3. Junction boxes and lateral bends
- 4. Ladder-back cable tray with single layer cable fill
- 5. Cable tray with T-Section
- 6. Raceway material (aluminum, steel)
- 7. Support protection, thermal shorts (penetrating elements)
- 8. Air drops Baseline fire barrier panel thickness 9.
- 10. Preformed conduit panels
- 11. Panel rib orientation (parallel or perpendicular to the raceway)
- 12. Unsupported spans l'
- 13. Stress skin orientation (inside or outside)
- 14. Stress skin over joints or no stress skin over joints
- 15. Stress skin ties or no stress skin ties
- 16. Dry-fit, post-buttered joints or prebuttered joints !
- 17. Joint gap width -!
- 18. Butt joints or grooved and scored joints
- 19. Steel bands or tie wires
- 20. Band / wire spacing
- 21. Band / wire distance to joints
- 22. No internal bands in trays -
- 23. No additional trowel material over sections and joints or :
additional trowel material applied '
- 24. No edge guards or edge guards Each NUMARC cable tray fire test specimen includes 15 percent cable i fills (i.e., a single layer of cables uniformly distributed across i the bottom of the cable tray). This approach requires consideration ;
of plant-specific cable information during the assessments of tested i configurations and test results in relation to plant-specific ;
Thermo-Lag configurations; for example, cable trays with less '
thermal mass (cable fill) than the NUMARC test specimens, different ,
cable types, and the proximity of the cables to the Thermo-Lag (e.g., cables may be installed in contact with the unexposed surface of the Thermo-Leg or may come into contact during a fire if the .
Thermo-Lag material sags). In its letter of July 29, 1993, NUMARC i stated: " Utilities using the results of the NUMARC testing will ,
need to evaluate their installed cable fill and ensure that it is bounded by the tested cable fill." NUMARC is not conducting any ,
cable functionality tests or evaluations and stated that cable !
functionality evaluations will be performed by utilities using data l from the generic program.
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The' parameters of importance concerning cables protected by fire barriers are:
- 1. Cable size and type (power, control, or instrumentation). l
- 2. Cable jacket type (thermoplastic, thermoset) and materials.
- 3. Cable conductor insulation type (thermoplastic, thermoset plastic) and materials. .
- 4. Cable fill and distribution of cables within the protected f conduit or cable tray. ,
- 5. Proximity of cables to the unexposed (inside) surfaces of I the fire barrier.
- 6. Presence of materials between the cables and the unexposed !
side of the fire barrier material (for example, Sealtemp cloth, which is used in the NUMARC test specimens).
- 7. Cable operating temperature. !
Temperatures at which the cables can no longer perform their 8.
intended function when energized at rated voltage and .
current.
Other parameters that are unique to particular barriers, such as interfaces between Thermo-Lag materials and other fire barrier materials or building features (walls, etc.) and internal supports, ;
are also important. In addition, because of questions about the ;
uniformity of the Thermo-Lag fire barrier materials produced over time, NUMARC stated in its letter of July 29, 1993, that "[c]hemical analysis of Thermo-lag materials provided for the program, as well as samples from utility stock, will be performed, and a test report prepared comparing the chemical composition of the respective samples." The results of the chemical analyses may indicate that ,
variations in the' chemical properties of Thermo-Lag are significant '
and may require additional plant-specific information in the future.
B. Required Information !
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- 1. State whether or not you have obtained and verified each of !
the aforementioned parameters for each Thermo-Lag barrier installed in the plant. If not, discuss the parameters you have not obtained or verified. Retain detailed information on site for NRC audit where the aforementioned parameters .
are known.
- 2. For any parameur that is not known or has not been verified, describe how you will evaluate the in-plant barrier for acceptability. .
- 3. To evaluate NUMARC's application guidance, an understanding of the types and extent of the unknown parameters is needed.
Describe.the type and extent of the unknown parameters at 1 your plant in this context.
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, III. Thermo-Lag Fire Barriers Outside the Scope of the NUMARC Program A. Discussion In your response to GL 92-08, you indicated that actions necessary to restore the operability of these barriers would be based on the results of the NUMARC test program. During recent meetings with the NRC staff, the Executive Director for Operations and the Conaission, NUMARC descriv' ed the scope of its Thermo-l.ag fire barrier program, the results of the Phase I fire tests, ar.d planned Phase 2 tests, The program is limited to certain 1-hour and 3-hour conduit and cable tray fire barrier configurations and the development of guidance for applying the test results to plant-specific fire barrier configurations. However, NUMARC's program is not intended to bound all in-plant Thermo-Lag fire barrier configurations. In view of the scope of the NUMARC program and the limited success of the Phase 1 tests, it is clear that the NUMARC program will not be sufficient to resolve all Thermo-Lag fire barrier issues identified in GL 92-08. Thcrefore, licensees may need to take additional actions to address fire endurance and ampacity derating concerns with in-plant Thermo-Lag barriers.
B. Required information
- 1. Describe the barriers discussed under Item I.B.1 that you have determined will not be bounded by the NUMARC test program.
- 2. Describe the plant-specific corrective action program or plan you expect to use to evaluate the fire barrier configurations particular to the plant. This description should include a discussion of the evaluations and tests being considered to resolve the fire barrier issues identified in GL 92-08 and to demonstrate the adequacy of existing in-plant barriers.
- 3. If a plant-specific fire endurance test program is anticipated, describe the following:
- a. Anticipated test specimens.
- b. Test methodology and acceptance criteria including cable functionality.
IV. Ampacity Derating A. Discussion NUMARC has informed the staff that it intends to use the Texas Utilities (TV) Electric Company and Tennessee Valley Authority (TVA) ampacity derating test results to develop an electrical raceway component model for the industry. Additional information is needed to determine whether or not your Thermo-Lag barrier configurations (to protect the safe-shutdown capability from fire or to achieve physical independence of electrical systems) are within the scope of
i k
. i the NUMARC program and, if not, how the in-plant barriers will be i evaluated for the ampacity derating concerns identified in GL 92-08. !
B. Required Information
- 1. For the barriers described under Item I.B.1, describe those '
that you have determined will fall within the scope of the NUMARC program for ampacity derating, those that will not be ;
bounded by the NUMARC program, and those for which ampacity derating does not apply. *
- 2. For the barriers you have determined fall within the scope }
of the NUMARC program, describe what additional testing or ,
evaluation you will need to perform to derive valid ampacity '
derating factors. >
- 3. For the barrier configurations that you have determined will not be bounded by the NUMARC test program, describe your plan for evaluating whether or not the ampacity derating tests relied upon for the ampacity derating factors used for ,
those electrical components protected by Thermo-Lag 330-1 '
(for protecting the safe-shutdown capability from fire or to achieve physical independence of electrical systems) are ;
correct and applicable to the plant design. Describe all corrective actions needed and submit the schedule for .
completing such actions. 1
- 4. In the event that the NUMARC fire barrier tests indicate the need to upgrade existing in-plant barriers or-to replace existing Thermo-Lag barriers with another fire barrier l system, describe the alternative actions you will take (and '
the schedule for performing those actions) to confirm that the ampacity derating factors were derived by valid tests '
and are applicable to the modified plant design.
Your response to Section IV.B may depend on unknown specifics of the NUMARC ampacity derating test program (for example, the final barrier upgrades). However, your response should be as complete as ,
possible. In addition, your response should be updated as i additional information becomes available on the NUMARC program.
i V. Alternatives .
A. Discussion On the basis of testing of Thermo-Lag fire barriers to date, it is '
not clear that generic upgrades (using additional Thermo-Lag materials) can be developed for many 3-hour barrier configurations '
or for some 1-hour barriers (for example,1-hour barriers on wide ,
cable trays, with post-buttered joints and no internal supports). ,
Moreover, some upgrades that rely on additional thicknesses of .
Thermo-Lag material (or other fire barrier materials) may not be practical due to the effects of ampacity derating or clearance problems. !
I l !
B. Required Information Describe the specific alternatives available to you for achie'ving compliance with NRC fire protection requirements in plant areas that contain Thermo-Lag fire barriers. Examples' of possible alternatives to Thermo-Lag-based upgrades include the following:
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- 1. Upgrade existing in-plant barriers using other materials.
- 2. Replace Thermo-Lag barriers with other fire barrier materials or systems.
- 3. Reroute cables or relocate other protected components. !
- 4. Qualify 3-hour barriers as 1-hour barriers and install detection and suppression systems to satisfy NRC fire protection requirements.
VI. Schedules A. Discussion The staff expects the licensees to resolve the Thermo-Lag fire barrier issues identified in GL 92-08 or to propose alternative fire :
protection measures to be implemented to bring plants into ,
compliance with NRC fire protection requirements. Specifically, as i test data becomes available, licensees should begin upgrades for ,
Thermo-Lag barrier configurations bounded by the test results. -
B. Required Information Submit an integrated schedule that addresses the overall corrective action schedule for the plant. At a minimum, the schedule should address the following aspects for the plant:
- 1. implementation and completion of corrective actions and fire barrier upgrades for fire barrier configurations within the ;
scope of the NUMARC program,
- 2. implementation and completion of plant-specific analyses,-
testing, or alternative actions for fire barriers outside the scope of the NUMARC program.
VII.- Sources and Correctness of Information Describe the sources of the information provided in response to this request for information (for example, from plant drawings, quality assurance documentation, walk downs or inspections) and how the accuracy and validity of the information was verified.}}