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| {{#Wiki_filter:}} | | {{#Wiki_filter:- .. . _. . _ _ _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ . - |
| | Mr. J m:s Knubel |
| | . Chief Nuctur Officer Noyember 3, 1998 PowIr Authority cf tha Stata of |
| | . New York 123 Main Street 1 |
| | White Plains, NY 10601 ' |
| | |
| | ==SUBJECT:== |
| | JAMES A. FITZPATRICK NUCLEAR POWER PLANT- AUTHORIZATION OF ALTERNATIVE TO ASME CODE REQUIREMENTS FOR CONTROL ROD DRIVE BOLTING (TAC NO. MA1764) |
| | |
| | ==Dear Mr. Knubel:== |
| | i On May 8,1998, the Power Authority of the State of New York (also known as the New York Power Authority, or NYPA) requested relief from certain American Society of Mechanical Engineers (ASME) Code requirements at the James A. FitzPatrick Nuclear Power Plant. |
| | Specifically, NYPA requested relief from requirements for additional examinations of control rod drive (CRD) bolting when cracks are detected in the head-to-shank fillet area. Additional information regarding this request was provided on September 11,1998, in response to an NRC request dated August 31,1998. |
| | { |
| | ~ |
| | The NRC staff, with the assistance of its contractor, the Idaho National Engineering and Environmental Laberatory (INEEL), has concluded that NYPA's metallurgical and engineering analyses provide reasonable assurance of the continued inservice structuralintegrity of the CRD |
| | ' bolting at the FitzPatrick Nuclear Power Plant. Replacing all CRD bolting at one time, during the Code-required additional examinations, would result in hardship without a compensating increase 4 in the level of quality and safety. Therefore, the staff concluded that the licensee's proposed i |
| | attemative in Request for Relief No. RR-14 is authorized pursuant to 10 CFR 50.55a(a)(3)(ii). |
| | Details of the staff and INEEL assessment are provided in the enclosed safety evaluation and Technical Letter Report. |
| | If you have any questions regarding this matter, please contact Joe Williams at (301) 415-1470. |
| | Sincerely, ORIGINAL SIGNED BY: |
| | . S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-333 fh h gg {*{t, |
| | |
| | ==Enclosure:== |
| | Safety Evaluation w/ attachment cc w/ encl: See next page i DISTRIBUTION: |
| | Docket File S. Bajwa OGC B.McCabe - |
| | Q)l ' |
| | t g |
| | PUBLIC S. Little G. Hill (2 copies) C. Hehl, RI PDI-1 R/F J. Williams ACRS T. McLellan J. Zwolinski T. Harris (e-mail only to TLH3) |
| | DOCUMENT NAME: G:\FITZ\MA1764.LTR *See Previous Concurrence |
| | . To r:ceive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with j tttachment/ enclosure EN" = No copy I, |
| | OFFICE PM:PDI 1 [/)/ l LAIPDI1J() l DPOI1 M OGC* l l NAME JWil1 lams /r$f SLittle F S8ejus /puK yyg DATE 11/ 2 /96 / 11/ 1 /98 11/'4 /98 10/28/98 Official Record Copy PDR ADOCK 05000333 P PDR |
| | |
| | >n nag o *, UNITED STATES j |
| | I y j NUCLEAR REGULATORY COMMISSION g 2 WASHINGTON, D.C. 30a66-0001 b .,g 8 November 3, 1998 Mr. James Knubel Chief Nuclear Officer Power Authority of the State of New York 123 Main Street . |
| | White Plains, NY 10601 i |
| | |
| | ==SUBJECT:== |
| | JAMES A. FITZPATRICK NUCLEAR POWER PLANT- AUTHORIZATION OF ALTERNATIVE TO ASME CODE REQUIREMENTS FOR CONTROL ROD DRIVE BOLTING (TAC NO. MA1764) |
| | |
| | ==Dear Mr. Knubel:== |
| | |
| | 1 On May 8,1998, the Power Authority of the State of New York (also known as the New York Power Authority, or NYPA) requested relief from certain American Society of Mechanical Engineers (ASME) Code requirements at the James A. FitzPatrick Nuclear Power Plant. |
| | Specifically, NYPA requested relief from requirements for additional examinations of control rod drive (CRD) bolting when cracks are detected in the head-to-shank fillet area. Additional information regarding this request was provided on September 11,1998, in response to an NRC l request dated August 31,1998. |
| | The NRC staff, with the assistance of its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), has concluded that NYPA's metallurgical and engineering analyses provide reasonable assurance of the continued inservice structuralintegrity of the CRD bolting at the FitzPatrick Nuclear Power Plant. Replacing all CRD bolting at one time, during the Code-required additional examinations, would result in hardship without a compensating increase in the level of quality and safety. Therefore, the staff concluded that the licensee's proposed alternative in Request for Relief No. RR 14 is authorized pursuant to 10 CFR 50.55a(a)(3)(ii). |
| | Details of the staff and INEEL assessment are provided in the enclosed safety evaluation and Technical Letter Report, if you have any questions regarding this matter, please contact Joe Williams at (301) 415-1470. |
| | Sincerely, S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects 1/ll Office of Nuclear Reactor Regulation Docket No. 50-333 |
| | |
| | ==Enclosure:== |
| | Safety Evaluation w/ attachment cc w/ encl: See next page |
| | |
| | " James Knubel James A. FitzPatrick Nuclear Power Authority of the State Power Plant of New York cc: , |
| | Mr. Gerald C. Goldstein Mr. F. William Valentino, President Assistant General Counsel New York State Energy, Research, Power Authority of the State and Development Authority of New York Corporate Plaza West 1633 Broadway 286 Washington Avenue Extension New York, NY 10019 Albany, NY 122034 399 Resident inspector's Office Mr. Richard L. Patch, Director U. S. Nuclear Regulatory Commission Quality Assurance P.O. Box 136 Power Authority of the State I Lycoming, NY 13093 of New York i 123 Main Street l Mr. Harry P. Salmon, Jr. White Plains, NY 10601 ! |
| | Vice President - Engineering l |
| | Power Authority of the State Mr. Gersid Goering l of New York 28112 Bayview Drive 123 Main Streat Red Wing, MN 55066 White Plains, NY 10601 Mr. James Gagliardo Ms. Charlene D. Faison Safety Review Committee Director Nuclear Licensing 708 Castlewood Avenue |
| | ^ |
| | Power Authority of the State Arlington,TX 76012 of New York 123 Main Street Mr. Arthur Zaremba, Licensing Manager White Plains, NY 10601 James A. FitzPatrick Nuclear l Power Plant Supervisor P.O. Box 41 Town of Scriba Lycoming, NY 13093 . |
| | Route 8, Box 382 Oswego, NY 13126 Mr. Paul Eddy New York State Dept. of Mr. Eugene W Zeltmann Public Service President and Chief Operating 3 Empire State Plaza,10th Floor Officer Albany, NY 12223 |
| | . Power Authority of the State of New York Michael J. Colomb 99 Washington Ave., Su;le No. 2005 Site Executive Officer Albany, NY 12210 2820 James A. FitzPatrick Nuclear Power Plant P.O. Box 41 |
| | ' Charles Donaldson, Esquire Lycoming, NY 13093 Assistant Attomey General |
| | . New York Department of Law l 120 Broadway New York, NY 10271 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road |
| | - King of Prussia, PA 19406 |
| | .. . - - . - - - - - . - - - - . . . . - - - , . - - - - . . -}} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M1851999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
JPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 11999-10-15015 October 1999
Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1
JPN-99-034, Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping1999-10-13013 October 1999
Forwards Proposed risk-informed ISI Program,Provided from NRC Review & Approval as Alternative to Current ASME Section XI Insp Requirements for Class 1 & 2 Piping
JPN-99-033, Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon1999-10-0808 October 1999
Provides Response to Questions Contained in 990712,facsimile from NRC Re Ja FitzPatrick USI A-46 Program.Questions Were Also Discussed Between Members of Util & NRC Staff During Telcon
JPN-99-030, Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days1999-09-29029 September 1999
Forwards Application for Amend to License DPR-59,proposing Change to TS 3.5.B.3 & Associated Bases to Extend LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days
JPN-99-032, Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request1999-09-29029 September 1999
Forwards Info Re Potential Environ Effects of Alternatives to Proposed Expansion of FitzPatrick Spent Fuel Pool,In Response to NRC Project Manager Request
ML20212F8341999-09-22022 September 1999
Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted
JAFP-99-0262, Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl1999-09-16016 September 1999
Forwards Voluntary Response to Administrative Ltr 99-03, Re Preparation & Scheduling of Operator Licensing Exams. Completed NRC Form 536,containing Info Re Proposed Exam Preparation Schedule & Initial Operator License Exams,Encl
ML20212A8341999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20212A6951999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
05000333/LER-1998-015, Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete1999-09-0808 September 1999
Forwards LER 98-015-02 Re Logic Sys Functional Test Inadequacies,Per 10CFR50.73(A)(2)(i)(B).Rept Revised to Reflect Scheduled Completion Date for Corrective Action 3 of Jan 15, 2000 & Updates Status of Other C/As as Complete
ML20211N4301999-09-0808 September 1999
Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues
JAFP-99-0258, Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld1999-09-0808 September 1999
Forwards Operator License Restriction Change for Tj Pelton, License SOP-10090-3.License Is Requested to Be Reissued with Restriction for Corrective Lenses.Encl Withheld
JPN-99-028, Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity1999-08-30030 August 1999
Informs That Util Requires Extension from 990901 to 1015,to Complete Review of Rvid & Forward Comments to Nrc,Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity
JAFP-99-0247, Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 41999-08-26026 August 1999
Forwards JAFNPP Effluent & Waste Disposal Semi-Annual Rept for 990101-0630, IAW Amend 93,App B,Section 7.3.C of Plant Ts.Format Used for Rept Is Outlined in App B of Reg Guide 1.21,Rev 1.Distribution Is IAW Reg Guide 10.1,Rev 4
JAFP-99-0245, Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 19991999-08-19019 August 1999
Informs That Two Licensed Operators Have Returned to Site Upon Release for Normal Duties by Physician.R Korthas, License OP-11159,meets ANSI Std 3.4-1983 & R Sarkissian License SOP-10007-3,was Terminated in Mar 1999
ML20210U2621999-08-12012 August 1999
Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted
JPN-99-025, Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams1999-08-0505 August 1999
Forwards Relief Request 17 Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) for Reactor Pressure Vessel Circumferential Shell Weld Exams
JPN-99-026, Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds1999-08-0505 August 1999
Forwards Relief Requests 18 & 19 to Jaf ISI Program Re Proposed Alternatives IAW 10CFR50.55a(a)(3)(i) & Relief from ASME Section XI Code Re Insp of RPV Vertical Shell & Shell to Flange Welds
ML20216D9421999-07-28028 July 1999
Forwards Safety Evaluation Granting Requests for Relief from Requirements of ASME Code,Section XI for Second 10-year ISI Interval for James a FitzPatrick NPP
JAFP-99-0229, Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)1999-07-22022 July 1999
Forwards Three Sets of Corrected Summaries of Changes for Inclusion Into Security Plan for Ja FitzPatrick Nuclear Power Plant,Rev 19 & Security Contingency Plan,Rev 5.Encls Withheld Per 10CFR73.21 & 10CFR2.790)d)(1)
JAFP-99-0228, Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal1999-07-21021 July 1999
Forwards Rept Re Changes & Errors in ECCS Evaluation Models, Per 10CFR50.46(a)(3)(ii) for Period from 980701-990630.No Commitments Contained in Submittal
ML20210A7001999-07-16016 July 1999
Forwards Request for Addl Info to Supplement Response Provided for GL 97-05, Steam Generator Tube Insp Techniques
JAFP-99-0208, Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl1999-07-14014 July 1999
Provides Clarification of Info Re Proposed Its, & 0601.Table Reconciling Differences,Encl
ML20209D5511999-07-0606 July 1999
Informs That as Result of NRC Review of Licensee Response to GL 92-01,rev 1,suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
ML20210C9031999-06-30030 June 1999
Summarizes Impact of Changes & Errors in Methodology Used by GE to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.Summary of Changes & Errors Provided in Attached Table
JPN-99-021, Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend1999-06-22022 June 1999
Forwards Application for Amend to License DPR-59,changing to Pressure Temp Limits.Pressure Temp Curves & Associated LCO & Bases Changes Included in Proposed Amend
JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept1999-06-21021 June 1999
Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept
ML20196G2981999-06-18018 June 1999
Forwards Insp Rept 50-333/99-04 on 990412 to 0529.Violations Being Treated as non-cited Violations
ML20212J0541999-06-17017 June 1999
Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First
JPN-99-019, Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant1999-06-15015 June 1999
Withdraws Recent Exemption Request Re 10CFR50,App R, Use of Core Spray to Achieve Safe Shutdown. Exemption Dealt with Use of Core Spray for Reactor Coolant Makeup to Achieve Safe Shutdown in One Fire Area at Plant
ML20196L1451999-06-0707 June 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Ja Fitzpatrick & Indian Point NPPs
JPN-99-018, Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1)1999-06-0101 June 1999
Forwards Revised Application,Previously Submitted,For Amend to Plant TS for Converting CTS to ITS Consistent with Improved Std TS (NUREG-1433,Rev 1)
ML20207D9191999-05-27027 May 1999
Informs That on 990521 NRC Staff Held Planning Meeting to Identify Insp Activities at Facility Over Next Six Months
JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr1999-05-20020 May 1999
Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr
JPN-99-016, Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl1999-05-19019 May 1999
Forwards Application for Amend to License DPR-59,requesting 14 Day AOT for EDG Sys.Commitment Made by Util,Encl
ML20207A6751999-05-17017 May 1999
Forwards RAI Re 960626 Submittal & Suppl Related to IPEEEs for Plant.Licensee Committed to Revise Plant Fire IPEEE to Reflect Issues Associated with EPRI Fire PRA Implementation Guide within 120 Days of Issues Resolution
JAFP-99-0168, Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls1999-05-13013 May 1999
Forwards Eight Operator License Renewal Applications for Listed Individuals.Without Encls
ML20206N0721999-05-11011 May 1999
Forwards Insp Rept 50-333/99-03 on 990301-0411.Four Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy
JAFP-99-0160, Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 41999-04-30030 April 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Ja FitzPatrick Nuclear Power Plant. Distribution for Rept Is IAW Reg Guide 10.1,Rev 4
ML20206C8551999-04-27027 April 1999
Informs That Util 990406 Submittal, Licensing Rept for Reracking of Ja FitzPatrick Spent Fuel Pool,Rev 7, Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b)
ML20205T1141999-04-22022 April 1999
Provides Comments from Technical Review of Draft Info Notice Re Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station,Unit 2,ANO,Unit 2 & JAFNPP
JPN-99-012, Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached1999-04-16016 April 1999
Informs That Authority Identified Typographical Error on Page 3 of Attachment 3 of 990331 Response to NRC RAI Re App R.Corrected Response to NRC Question 3 Is Attached
ML20205P4641999-04-15015 April 1999
Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP
ML20205P1991999-04-0909 April 1999
Discusses 990224 PPR & Forwards Plant Issues Matrix & Insp Plan.Advises of Planned Insp Effort Resulting from Plant PPR Review
JAFP-99-0129, Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick1999-04-0909 April 1999
Submits Comments on Technical Review of Draft Info Notice Describing Unanticipated Reactor Water Draindown at Quad Cities Unit 2,ANO & FitzPatrick
JAFP-99-0127, Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld1999-04-0808 April 1999
Forwards Affidavit Signed by Holtec Which Describes Proprietary Nature of Licensing Rept & Addresses Considerations Listed in 10CFR2.790.Attachment 4 in Util Re Design Features Should Be Withheld
JAFP-99-0124, Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999
Forwards Rev 19 to JAFNPP Security Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Safeguards Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)
ML20205M8941999-04-0707 April 1999
Forwards Rev 21 to App C of JAFNPP Emergency Plan & Rev 1 to EAP-32, Recovery Support Group Manager
JAFP-99-0125, Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)1999-04-0707 April 1999
Forwards Rev 5 to JAFNPP Security Contingency Plan,Which Enhances Requirements of 10CFR73.55.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld IAW 10CFR73.21 & 2.790(d)(1)
1999-09-09
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M1851999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20212F8341999-09-22022 September 1999
Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted
ML20212A6951999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20212A8341999-09-0909 September 1999
Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics
ML20211N4301999-09-0808 September 1999
Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues
ML20210U2621999-08-12012 August 1999
Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted
ML20216D9421999-07-28028 July 1999
Forwards Safety Evaluation Granting Requests for Relief from Requirements of ASME Code,Section XI for Second 10-year ISI Interval for James a FitzPatrick NPP
ML20210A7001999-07-16016 July 1999
Forwards Request for Addl Info to Supplement Response Provided for GL 97-05, Steam Generator Tube Insp Techniques
ML20209D5511999-07-0606 July 1999
Informs That as Result of NRC Review of Licensee Response to GL 92-01,rev 1,suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
ML20196G2981999-06-18018 June 1999
Forwards Insp Rept 50-333/99-04 on 990412 to 0529.Violations Being Treated as non-cited Violations
ML20212J0541999-06-17017 June 1999
Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First
ML20196L1451999-06-0707 June 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Ja Fitzpatrick & Indian Point NPPs
ML20207D9191999-05-27027 May 1999
Informs That on 990521 NRC Staff Held Planning Meeting to Identify Insp Activities at Facility Over Next Six Months
ML20207A6751999-05-17017 May 1999
Forwards RAI Re 960626 Submittal & Suppl Related to IPEEEs for Plant.Licensee Committed to Revise Plant Fire IPEEE to Reflect Issues Associated with EPRI Fire PRA Implementation Guide within 120 Days of Issues Resolution
ML20206N0721999-05-11011 May 1999
Forwards Insp Rept 50-333/99-03 on 990301-0411.Four Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy
ML20206C8551999-04-27027 April 1999
Informs That Util 990406 Submittal, Licensing Rept for Reracking of Ja FitzPatrick Spent Fuel Pool,Rev 7, Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b)
ML20205P4641999-04-15015 April 1999
Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP
ML20205P1991999-04-0909 April 1999
Discusses 990224 PPR & Forwards Plant Issues Matrix & Insp Plan.Advises of Planned Insp Effort Resulting from Plant PPR Review
ML20205F8031999-04-0202 April 1999
Forwards Draft Info Notice Describing Unanticipated Reactor Water Draindown of Listed Plants
ML20205C1041999-03-26026 March 1999
Forwards Insp Rept 50-333/99-02 on 990125-0209.No Violations Noted.Insp Evaluated Results of Investigation Into Causes of 990114 Hydrogen Fire Event & Licensee Response to Event. Licensee Overall Response to Event,Acceptable
ML20204J3791999-03-23023 March 1999
Forwards Insp Rept 50-333/99-01 on 990111-0228.No Violations Noted.Security Program Was Effectively Implemented
ML20203E9231999-02-10010 February 1999
Forwards Insp Rept 50-333/98-08 on 981123-990110.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices
ML20203B9001999-02-0808 February 1999
First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6)
ML20202J0571999-02-0303 February 1999
Forwards Safety Evaluation Authorizing Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant
ML20202C1871999-01-26026 January 1999
Forwards Request for Addl Info Re Util 971014 Request for Changes to James a Fitzpatrick Nuclear Power Plant TSs to Increase Capacity of Sf Pool.Response Requested within 30 Days of Date of Ltr
ML20203H8941999-01-21021 January 1999
Forwards Notice of Withdrawal of Application for Amend to License DPR-59.Amend Would Have Modified TS Re Inservice Leak & Hydrostatic Testing Operations
ML20199G7161999-01-19019 January 1999
Informs That NRC Review of Relief Requests Submitted on 980126 for James a FitzPatrick Nuclear Power Plant, Considered Complete
ML20198L4041998-12-17017 December 1998
Forwards Insp Rept 50-333/98-07 on 981005-1122 & NOV Re Design Deficiency That Resulted in Main Steam Safety Relief Valve Pilot Solenoid Cables Not Being Installed in Conduit
ML20198C2331998-12-15015 December 1998
Ltr Contract:Task Order 236, Review & Evaluation of Fitzpatrick Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026
ML20198B4531998-12-10010 December 1998
Advises of Planned Insp Effort Resulting from Insp Resource Planning Meeting on 981110.Historical Listing of Plant Issues Encl
ML20198F9861998-12-0404 December 1998
Forwards Assessment Re Util 980916 Info Re NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwr. NRC Agrees with Util Conclusion That Plant Remains within Licensing Basis
ML20196J3431998-12-0404 December 1998
Forwards SER Accepting Util Program for Periodic Verification of MOV design-basis Capability at FitzPatrick in Response to GL 96-05
ML20196F9181998-11-25025 November 1998
Forwards Safety Evaluation Re Third 10-year Interval Inservice Insp Program Relief Requests for Plant
ML20195K3631998-11-17017 November 1998
Forwards SE Authorizing IST Program Relief Request VRR-05, Per 10CFR50.55a(a)(3)(i) & Relief Requests PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04,per 10CFR50.55a(a)(3)(ii)
ML20195D9711998-11-13013 November 1998
Forwards SE Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817
ML20195B7331998-11-0505 November 1998
Submits Request for Addl Info Re Proposed Extension of Emergency Diesel Generator Allowed Outage Time
ML20155H5251998-11-0303 November 1998
Forwards SE Authorizing Licensee 980508 Request for Relief from Certain ASME Code Requirements at Ja FitzPatrick Npp. Licensee Requested Relief from Requirements for Addl Exams of CRD Bolting When Cracks Detected in head-to-shank Area
ML20155H5751998-11-0303 November 1998
Forwards SE Authorizing Proposed Alternative to RPV Shell Weld Exam Requirements of Both ASME BPV Code,Section XI,1989 Edition & Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) for Ja FitzPatrick NPP
ML20155B5681998-10-27027 October 1998
Informs That GE Rept GENE-187-30-0598,DRF B13-01920-30, CRD Bolting Flaw Evaluation for Ja FitzPatrick Np, Rev 0,dtd May 1998,submitted by 980507 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20154Q9251998-10-19019 October 1998
Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20154Q5111998-10-16016 October 1998
Responds to Re Concerns on Use of Reactor Building Crane to Move Sf with Fuel Pool at Jafnpp.Regrets That Did Not Address Concerns in Satisfactory Manner & Provides Addl Info Re Concerns
ML20154L6381998-10-14014 October 1998
Forwards SE Accepting Licensee 980126 Submittal of ISI Program & Relief Requests for Third 10-year Interval for Plant
ML20154M0951998-10-14014 October 1998
Forwards Insp Rept 50-333/98-06 on 980824-1004.No Violations Noted.Testing & Control Room Operations Were Conducted Appropriately with Formal Communications
ML20154L2371998-10-13013 October 1998
Responds to Util Re NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, Which Addressed Issues Discussed in 980521 Meeting. Request to Defer Completion of Actions Acceptable
ML20154B3951998-09-29029 September 1998
Provides Addl Info Re Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20154B3421998-09-28028 September 1998
Advises That Info Contained in 980803 Application Re cycle-specific Safety Limit Min Critical Power Ratio for Cycle 14,will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20154B8201998-09-28028 September 1998
Forwards Insp Rept 50-333/98-05 on 980727-0814 & NOV Re Failure to Analyze Effects of LOCA Plus LOOP on Containment Penetration Protection
ML20153F8791998-09-22022 September 1998
Forwards RAI Re Licensee Response to GL 96-05 for Plant & Indicating Intent to Implement Provisions of JOG Program on motor-operated Valve Periodic Verification
ML20153D2551998-09-21021 September 1998
Forwards SE Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement
ML20153B3341998-09-14014 September 1998
Advises That Matl Marked as Proprietary in from Pasn & 980625 Affidavit from Holtec Intl Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended
1999-09-09
[Table view] |
Text
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Mr. J m:s Knubel
. Chief Nuctur Officer Noyember 3, 1998 PowIr Authority cf tha Stata of
. New York 123 Main Street 1
White Plains, NY 10601 '
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT- AUTHORIZATION OF ALTERNATIVE TO ASME CODE REQUIREMENTS FOR CONTROL ROD DRIVE BOLTING (TAC NO. MA1764)
Dear Mr. Knubel:
i On May 8,1998, the Power Authority of the State of New York (also known as the New York Power Authority, or NYPA) requested relief from certain American Society of Mechanical Engineers (ASME) Code requirements at the James A. FitzPatrick Nuclear Power Plant.
Specifically, NYPA requested relief from requirements for additional examinations of control rod drive (CRD) bolting when cracks are detected in the head-to-shank fillet area. Additional information regarding this request was provided on September 11,1998, in response to an NRC request dated August 31,1998.
{
~
The NRC staff, with the assistance of its contractor, the Idaho National Engineering and Environmental Laberatory (INEEL), has concluded that NYPA's metallurgical and engineering analyses provide reasonable assurance of the continued inservice structuralintegrity of the CRD
' bolting at the FitzPatrick Nuclear Power Plant. Replacing all CRD bolting at one time, during the Code-required additional examinations, would result in hardship without a compensating increase 4 in the level of quality and safety. Therefore, the staff concluded that the licensee's proposed i
attemative in Request for Relief No. RR-14 is authorized pursuant to 10 CFR 50.55a(a)(3)(ii).
Details of the staff and INEEL assessment are provided in the enclosed safety evaluation and Technical Letter Report.
If you have any questions regarding this matter, please contact Joe Williams at (301) 415-1470.
Sincerely, ORIGINAL SIGNED BY:
. S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-333 fh h gg {*{t,
Enclosure:
Safety Evaluation w/ attachment cc w/ encl: See next page i DISTRIBUTION:
Docket File S. Bajwa OGC B.McCabe -
Q)l '
t g
PUBLIC S. Little G. Hill (2 copies) C. Hehl, RI PDI-1 R/F J. Williams ACRS T. McLellan J. Zwolinski T. Harris (e-mail only to TLH3)
DOCUMENT NAME: G:\FITZ\MA1764.LTR *See Previous Concurrence
. To r:ceive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with j tttachment/ enclosure EN" = No copy I,
OFFICE PM:PDI 1 [/)/ l LAIPDI1J() l DPOI1 M OGC* l l NAME JWil1 lams /r$f SLittle F S8ejus /puK yyg DATE 11/ 2 /96 / 11/ 1 /98 11/'4 /98 10/28/98 Official Record Copy PDR ADOCK 05000333 P PDR
>n nag o *, UNITED STATES j
I y j NUCLEAR REGULATORY COMMISSION g 2 WASHINGTON, D.C. 30a66-0001 b .,g 8 November 3, 1998 Mr. James Knubel Chief Nuclear Officer Power Authority of the State of New York 123 Main Street .
White Plains, NY 10601 i
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT- AUTHORIZATION OF ALTERNATIVE TO ASME CODE REQUIREMENTS FOR CONTROL ROD DRIVE BOLTING (TAC NO. MA1764)
Dear Mr. Knubel:
1 On May 8,1998, the Power Authority of the State of New York (also known as the New York Power Authority, or NYPA) requested relief from certain American Society of Mechanical Engineers (ASME) Code requirements at the James A. FitzPatrick Nuclear Power Plant.
Specifically, NYPA requested relief from requirements for additional examinations of control rod drive (CRD) bolting when cracks are detected in the head-to-shank fillet area. Additional information regarding this request was provided on September 11,1998, in response to an NRC l request dated August 31,1998.
The NRC staff, with the assistance of its contractor, the Idaho National Engineering and Environmental Laboratory (INEEL), has concluded that NYPA's metallurgical and engineering analyses provide reasonable assurance of the continued inservice structuralintegrity of the CRD bolting at the FitzPatrick Nuclear Power Plant. Replacing all CRD bolting at one time, during the Code-required additional examinations, would result in hardship without a compensating increase in the level of quality and safety. Therefore, the staff concluded that the licensee's proposed alternative in Request for Relief No. RR 14 is authorized pursuant to 10 CFR 50.55a(a)(3)(ii).
Details of the staff and INEEL assessment are provided in the enclosed safety evaluation and Technical Letter Report, if you have any questions regarding this matter, please contact Joe Williams at (301) 415-1470.
Sincerely, S. Singh Bajwa, Director Project Directorate 1-1 Division of Reactor Projects 1/ll Office of Nuclear Reactor Regulation Docket No. 50-333
Enclosure:
Safety Evaluation w/ attachment cc w/ encl: See next page
" James Knubel James A. FitzPatrick Nuclear Power Authority of the State Power Plant of New York cc: ,
Mr. Gerald C. Goldstein Mr. F. William Valentino, President Assistant General Counsel New York State Energy, Research, Power Authority of the State and Development Authority of New York Corporate Plaza West 1633 Broadway 286 Washington Avenue Extension New York, NY 10019 Albany, NY 122034 399 Resident inspector's Office Mr. Richard L. Patch, Director U. S. Nuclear Regulatory Commission Quality Assurance P.O. Box 136 Power Authority of the State I Lycoming, NY 13093 of New York i 123 Main Street l Mr. Harry P. Salmon, Jr. White Plains, NY 10601 !
Vice President - Engineering l
Power Authority of the State Mr. Gersid Goering l of New York 28112 Bayview Drive 123 Main Streat Red Wing, MN 55066 White Plains, NY 10601 Mr. James Gagliardo Ms. Charlene D. Faison Safety Review Committee Director Nuclear Licensing 708 Castlewood Avenue
^
Power Authority of the State Arlington,TX 76012 of New York 123 Main Street Mr. Arthur Zaremba, Licensing Manager White Plains, NY 10601 James A. FitzPatrick Nuclear l Power Plant Supervisor P.O. Box 41 Town of Scriba Lycoming, NY 13093 .
Route 8, Box 382 Oswego, NY 13126 Mr. Paul Eddy New York State Dept. of Mr. Eugene W Zeltmann Public Service President and Chief Operating 3 Empire State Plaza,10th Floor Officer Albany, NY 12223
. Power Authority of the State of New York Michael J. Colomb 99 Washington Ave., Su;le No. 2005 Site Executive Officer Albany, NY 12210 2820 James A. FitzPatrick Nuclear Power Plant P.O. Box 41
' Charles Donaldson, Esquire Lycoming, NY 13093 Assistant Attomey General
. New York Department of Law l 120 Broadway New York, NY 10271 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road
- King of Prussia, PA 19406
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