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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML20217E0711999-10-14014 October 1999 Grants Approval for Util to Submit Original,One Signed Paper Copy & Six CD-ROM Copies of Updates to FSAR as Listed,Per 10CFR50.4(c),in Response to ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML20217F7751999-10-0808 October 1999 Confirms 991006 Telcon Between T Abney of Licensee Staff & a Belisle of NRC Re Meeting to Be Conducted on 991109 in Atlanta,Ga to Discuss Various Maintenance Issues ML20217D3261999-10-0808 October 1999 Responds to Re Event Concerning Spent Fuel Pool Water Temperature Being Undetected for Approx Two Days at Browns Ferry Unit 3 ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212M1481999-09-28028 September 1999 Refers to Management Meeting Conducted on 990927 at Region II for Presentation of Recent Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML20212D3651999-09-20020 September 1999 Forwards SE Accepting Licensee 990430 Proposed Rev to Plant, Unit 3 Matl Surveillance Program ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20211G6491999-08-26026 August 1999 Confirms Telcon with T Abney on 990824 Re Mgt Meeting Which Has Been re-scheduled from 990830-0927.Purpose of Meeting to Discuss BFN Status & Performance ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML20210Q4421999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006. Authorized Representative of Facility Must Submit Ltr with List of Individuals to Take exam,30 Days Before Exam Date ML20210N1051999-08-0202 August 1999 Forwards SE Accepting Licensee 990326 Request for Relief from ASME B&PV Code,Section XI Requirements.Request for Relief 3-ISI-7,pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210G8991999-07-28028 July 1999 Discusses 990726 Open Mgt Meeting for Discussion on Plant Engineering Status & Performance.List of Attendees & Presentation Handout Encl ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML20210G8051999-07-22022 July 1999 Discusses DOL Case DC Smith Vs TVA Investigation.Oi Concluded That There Was Not Sufficient Evidence Developed During Investigation to Substantiate Discrimination.Nrc Providing Results of OI Investigation to Parties ML20209J0251999-07-16016 July 1999 Forwards SE Which Constitutes Staff Review & Approval of TVA Ampacity Derating Test & Analyses for Thermo-Lag Fire Barrier Configurations as Required in App K of Draft Temporary Instruction, Fpfi, ML20210B2671999-07-14014 July 1999 Confirms 990702 Telcon Between T Abney of Licensee Staff & Author Re Mgt Meeting Scheduled for 990830 at Licensee Request in Atlanta,Ga to Discuss Browns Ferry Nuclear Plant Status & Performance ML20209E5511999-07-0707 July 1999 Informs That as Result of NRC Review of Util Responses to GL 92-01,rev 1 & Suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes TACs MA1180,MA1181 & MA1179 ML20209E3421999-07-0707 July 1999 Confirms Arrangements Made During 990628 Telephone Conversation to Hold Meeting on 990726 in Atlanta,Ga to Discuss Plant Engineering Status & Performance ML20196J3531999-06-30030 June 1999 Responds to Re Boeing Rocket Booster Mfg Facility Being Constructed in Decatur,Al.Nrc Has No Unique Emergency Planning Concerns Re Proximity of Boeing Facility to BFN ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML20196F8741999-06-23023 June 1999 Forwards Safety Evaluation Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML20206G6611999-05-0404 May 1999 Forwards SE Accepting GL 88-20,submitted by TVA Re multi-unit Probabilistic Risk Assessement (Mupra) for Plant, Units 1,2 & 3 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18039A9021999-10-15015 October 1999 Forwards LER 99-010-00 Re Occurrence of Plant Reactor Scram Due to Main Turbine Trip Which Resulted in Main Steam Moisture Separator.All Plant Safety Systems Operated as Designed in Response to Event ML18039A8961999-10-14014 October 1999 Forwards LER 99-009-00,re Manual Reactor Scram on Unit 2 from 54% Power,Iaw 10CFR50.73(a)(2)(iv).All Plant Safety Sys Operated as Designed in Response to Event ML18039A8881999-10-0808 October 1999 Provides Licensee Supplemental Response to NRC 980713 RAI Re GL 87-02,Suppl 1, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. ML18039A8931999-10-0808 October 1999 Forwards LER 99-008-00,concerning HPCI Sys Being Declared Inoperable,Iaw 10CFR50.73(a)(2)(v).There Are No Commitments Contained in Ltr ML20217B5481999-10-0101 October 1999 Requests Exception to 10CFR50.4(c) Requirement to Provide Total of Twelve Paper Copies When Submitting Revs to BFN UFSAR ML20212F7751999-09-22022 September 1999 Requests Operator & Senior Operator License Renewals for Listed Individuals and Licenses ML18039A8721999-09-10010 September 1999 Informs of Licensee Decision to Withdraw Proposed Plant risk-informed Inservice Insp Program,Originally Transmitted in Util 981023 Ltr.Licensee Expects to Resubmit Revised Program within Approx 6 Wks ML20211Q5731999-09-0909 September 1999 Submits Response to Administrative Ltr 99-03 Re Preparation & Scheduling of Operator Licensing Exams.Completed NRC Form 536,operator Licensing Exam Data,Which Provides Plant Current Schedules for Specific Info Requested Encl ML20210Q6931999-08-0909 August 1999 Forwards Updated Changes to Distribution Lists for Browns Ferry & Bellefonte Nuclear Plants ML18039A8371999-08-0606 August 1999 Forwards BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts, for NRC Review.Corrected Inservice Insp Summary Rept for Unit 3 Cycle 8 Operation,Included in Rept ML18039A8181999-07-26026 July 1999 Forwards LER 99-004-00 Re Inoperability of Two Divisions of Plant CSS Due to Personnel Error During Surveillance Testing.Event Reported Per 10CFR50.73(a)(2)(i)(B) ML20210F3031999-07-22022 July 1999 Submits Rept Re Impact of Changes or Errors in Methodology Used to Demonstrate Compliance with ECCS Requirements of 10CFR50.46.One Reportable non-significant Error Was Found During Time Period of 980601-990630 ML18039A8081999-06-28028 June 1999 Forwards LER 99-004-00 Re Esfas That Occurred When RPS Motor Generator Tripped.Rept Is Submitted IAW Provisions of 10CFR50.73(a)(2)(iv) as Event of Condition That Resulted in Automatic Actuation of ESF ML18039A8111999-06-25025 June 1999 Requests Permanent Relief from Inservice Insp Requirements of 10CFR50.55a(g) for Volumetric Exam of Bfn,Unit 3 Circumferential RPV Welds,Per GL 98-05 ML18039A8051999-06-22022 June 1999 Forwards LER 99-003-00,re Automatic Reactor Scram Due to Turbine Trip.Rept Numbered 99-001 Should Be Deleted & Replaced with Encl Rept as Result of Error Noted in 990614 Rept ML20196F8131999-06-22022 June 1999 Forwards Rev 24 to Security Personnel Training & Qualification Plan,Per 10CFR50.54(p).Rev Withheld ML18039A8031999-06-18018 June 1999 Responds to NRC Staff Verbal Request Re TS Change TS-376, Originally Submitted on 970312, & Proposed Changes to TS to Extend Current 7-day AOT for EDGs to 14 Days ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage ML20195D3321999-06-0101 June 1999 Informs That Cb Fisher,License OP-5525-4,can No Longer Maintain License at Plant Because of Physical Condition That Causes Licensee to Fail to Meet Requirements of 10CFR55.21 ML20195B9361999-05-24024 May 1999 Informs That Do Elkins,License SOP-3392-6,no Longer Needs to Maintain License as Position Does Not Require License ML18039A7891999-05-24024 May 1999 Informs That Oscillation Power Range Monitor Module Has Been Enabled for Current Cycle of Operation Following Unit 2 Cycle 10 Refueling Outage Which Was Completed on 990509 ML18039A7911999-05-24024 May 1999 Informs That by Meeting Test Criteria Established by Test Based on Ansi/Ans 3.5-1985 (License Amends 254 & 214) power- Uprate Simulation Acceptable for Operator Training ML20206U6551999-05-14014 May 1999 Informs That ML Meek & Wd Dawson Will No Longer Need to Maintain SRO Licenses at Plant,Due to Termination of Employment,Effective 990521 ML20206Q8421999-05-10010 May 1999 Forwards Medical Info on DM Olive,License SOP-20540-2,in Response to NRC 990428 Telcon.Encl Withheld from Public Disclosure IAW 10CFR2.790(a)(6) ML18039A7771999-05-0606 May 1999 Forwards LER 99-003-00,providing Details Re Plant HPCI Sys Being Declared Inoperable Due to Loose Electrical Connection.Ltr Contains No Commitments ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval ML20206H5901999-04-30030 April 1999 Forwards Notification of Revs to BFN Unit 2 Emergency Response Data Sys Data Point Library.Revs Were Implemented on 990413 ML18039A7681999-04-27027 April 1999 Requests Relief from Specified Inservice Insp Requirements in Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a(a)(3)(i).Relief Requests 2-ISI-8 & 3-ISI-8,encl for NRC Review & Approval ML18039A7651999-04-27027 April 1999 Forwards Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2,Cycle 11 Colr. ML18039A7591999-04-27027 April 1999 Forwards Annual Radiological Environ Operating Rept Browns Ferry Nuclear Plant 1998. Rept Includes Results of Land Use Censuses,Summarized & Tabulated Results of Radiological Environ Samples in Format of Reg Guide 4.8 & NUREG-1302 ML20206C8591999-04-23023 April 1999 Informs That Util Has Determined,Dr Bateman No Longer Needs to Maintain His License,Effective 990331,per Requirement of 10CFR55.55(a) ML18039A7581999-04-23023 April 1999 Responds to Item 4 of 981117 RAI Re TS Change Request 376 Re Extended EDG Allowed Outage Time,In Manner Consistent with Rgs 1.174 & 1.177 ML18039A7541999-04-23023 April 1999 Requests Approval of Bfnp Unit 3 Risk-Informed ISI (RI-ISI) Program,Per 10CFR50.55(a)(3)(i) & GL 88-01.Encl RI-ISI Program Is Alternative to Current ASME Section XI ISI Requirments for Code Class 1,2 & 3 Piping ML20206C1241999-04-21021 April 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998, IAW TS Section 5.6.1.Rept Reflects Radiation Exposure Data as Tracked by Electronic Dosimeters on Radiation Work Permits ML20205T0971999-04-15015 April 1999 Submits Change in Medical Status for DM Olive in Accordance with 10CFR55.25,effective 990315.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld,Per 10CFR2.790(a)(6) ML18039A7441999-04-0707 April 1999 Forwards LER 99-001-00,providing Details Re Inoperability of Two Trains of Standby Gas Treatment Due to Breaker Trip on One Train in Conjunction with Planned Maint Activities on Other.Ltr Contains No New Commitments ML18039A7431999-03-30030 March 1999 Responds to NRC 990112 RAI Re BFN Program,Per GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs. ML18039A7421999-03-30030 March 1999 Provides Results of Analysis of Design Basis Loca,As Required by License Condition Re Plants Power Uprate Operating License Amends 254 & 214 ML18039A7411999-03-30030 March 1999 Provides Partial Response to NRC 981117 RAI Re TS Change Request 376,proposing to Extend Current 7 Day AOT for EDG to 14 Days ML18039A7371999-03-26026 March 1999 Requests Relief from Specified ISI Requirements in Section XI of ASME Boiler & Pressure Vessel Code,1989 Edition.Encl Contains Request for Relief 3-ISI-7,for NRC Review & Approval ML18039A7331999-03-26026 March 1999 Forwards Rev 4 to TVA-COLR-BF2C10, Bnfp,Unit 2,Cycle 10 COLR, IAW Requirements of TS 5.6.5.d.COLR Was Revised to Extend Max Allowable Nodal Exposure for GE GE7B Fuel Bundles ML18039A7291999-03-22022 March 1999 Forwards Revised Epips,Including Index,Rev 26A to EPIP-1, Emergency Classification Procedure & Rev 26A to EPIP-5, General Emergency. Rev 26A Includes All Changes Made in Rev 26 as Well as Identified Errors ML20204G8471999-03-19019 March 1999 Reports Change in Medical Status for Ma Morrow,In Accordance with 10CFR55.25.Encl Medical Info & Certification of Medical Exam,Considered by Util to Be of Personal Nature & to Be Withheld from Pdr,Per 10CFR2.790(a)(6).Without Encl ML20207M0611999-03-11011 March 1999 Forwards Goals & Objectives for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3,radiological Emergency Plan Exercise.Plant Exercise Is Currently Scheduled for Wk of 990524 ML18039A6971999-02-22022 February 1999 Forwards Typed TS Pages,Reflecting NRC Approved TS Change 354 Requiring Oscillation PRM to Be Integrated Into Approved Power uprate,24-month Operating Cycle & Single Recirculation Loop Operation ML18039A6961999-02-19019 February 1999 Provides Util Response to GL 95-07 Re RCIC Sys Injection Valves (2/3-FCV-71-39) for BFN Units 2 & 3.Previous Responses,Dtd 951215,1016 & 960730,0315 & 0213,supplemented ML18039A6911999-02-19019 February 1999 Forwards Rev 3 to Unit 2 Cycle 10 & Rev 1 to Unit 3 Cycle 9, Colr.Colrs for Each Unit Were Revised to Include OLs Consistent with Single Recirculation Loop Operation ML20203B6031999-02-0404 February 1999 Requests Temporary Partial Exemption from Requirements of 10CFR50.65,maint Rule for Unit 1.Util Requesting Exemption to Resolve Issue Initially Raised in NRC Insp Repts 50-259/97-04,50-260/97-04 & 50-296/97-04,dtd 970521 ML18039A6741999-01-21021 January 1999 Responds to NRC 981209 Ltr Re Violations Noted in Insp Repts 50-259/98-07,50-260/98-07 & 50-296/98-07,respectively. Corrective Actions:Will Revise Procedure NEPD-8 Re Vendor Nonconformance Documentation Submission to TVA ML20199F6951999-01-0808 January 1999 Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months 1999-09-09
[Table view] |
Text
- _ _ _ _ - - _ _ _
t 1
Tennseees Valley Authority, Post offce Box 2000, Decatur, Alabama 35609-2000 Karl W. Singer i
Ves President, Browns Ferry Nuclear Plant February 4, 1999 10 CFR 50.12 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk f
Washington, D.C. 20555 Gentlemen:
q In the Matter of
)
Docket No. 50-259 Tennessee Valley Authority
)
BROWNS FERRY NUCLEAR PIANT (BFN) - UNIT 1 - REQUEST FOR A TEMPORARY EXEMPTION FROM THE REQUIREMENTS OF 10 CFR 50.65, MAINTENANCE RULE Pursuant to the provisions of 10 CFR 50.12 (a), TVA requests a temporary partial exemption from the requirements of 10 CFR 50.65, Maintenance Rule, for BFN Unit 1.
The exemption, if granted, is requested to remain effective until TVA returns l
Unit 1 to operation.
TVA is requesting this exemption to resolve an issue which was initially raised in NRC Inspection Report 50-259/97-04, 50-260/97-04, and 50-296/97-04, dated May 21, 1997.
In the report NRC concluded that, although the BFN Maintenance Rule program was comprehensive and was being effectively
\\
implemented, the scope of the program was inconsistent with h
the requirements of the rule.
The NRC staff concurred with this conclusion in a letter dated July 19, 1997.
If NRC approves this request, TVA will continue to implement the current BFN Maintenance Rule program that includes scoping and monitoring of Unit 1 systems, structures and components (SSCs) in a manner appropriate to Unit l's l
shutdown and defueled status.
This program contains two key elements: 1) an alternative scoping methodology utilized for n.y
.n 9902100360 990204 A
PDR ADOCK 05000259 1 a
PDR,L e - -.,
j
U.S.LNuclear1 Regulatory Commission Page 2-FEB 0 s 1999 l
l
'the Unit l'SCCs and 2) an explicit' program requirement to re-I evaluate'the' scoping of the Unit 1 SCCs if the status of Unit I changes.- Both of these existing Maintenance Rule program
. elements were described in a September 29, 1997, letter to NRC.
l The enclosure to this letter provides the background and the l
justification for seeking this. exemption.
1 i
If you have'any questions regarding this exemption request, please contact Tim Abney, Manager of Licensing and Industry l
Affairs, at (256) 729-2636.
i i
Sincerely,
-ew L-KarlSingd$I)
Enclosure cc (Enclosure):
Mr. Paul E. Fredrickson, Branch Chief U.S. Nuclear Regulatory Commission Region II 61 Forsyth Street, S. W.
Suite 23T85
' Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr. L. Raghavan, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 4
i I
i
ENCLOSURE' TENNESSEE VALLEY AUTHORITY-j BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 REQUEST FOR AN EXEMPTION IN ACCORDANCE WITH 10 CFR 50.12
(
FROM THE REQUIREMENTS OF 10 CFR 50.65, MAINTENANCE RULE Pursuant-to 10 CFR 50.12, TVA is requesting a temporary,-partial exemption from the requirements of 10 CFR 50.65, Maintenance j
Rule, for BFN Unit 1.
TVA plans to fully implement the l
Maintenance Rule upon restart of Unit 1..
i I'
BACKGROUND l
Unit 1 status Browns Ferry Unit 1 was shut down by TVA in March 1985.
It was defueled in late 1985 and put on administrative hold to resolve regulatory concerns.
The unit has remained in a defueled condition, and there is. currently no defined schedule for l
restart.
The Unit 1 systems that perform a required function in l
the defueled-condition or that directly support Unit 2 or Unit 3
' operation are being operated and maintained under applicable l
. Technical Specifications and plant ~ programs. 'The Unit 1 systems and components that are-not required to be operational have been placed in lay-up under a formal lay-up program.
In its current long-term defueled and administrative hold status, most of the Unit 1 systems are not required to perform the functions required to be monitored by 10 CFR 50.65(b) and cannot perform these functions due to the' lay-up status of the unit.
l NRC conducted an inspection of the implementation of the Maintenance Rule at Browns Ferry on April 14-18, 1997.
The results of the inspection were (scumented in NRC Inspection Report 50-259/97-04, 50-260/97-04, and 50-296/97-04, dated May 21, 1997.
The inspection report concluded that the BFN i
Maintenance Rule program was comprehensive and was being effectively implemented.
The inspection team also reviewed the actions to implement the Maintenance Rule on Unit 1 and concluded i
that the actions were technically adequate; however, the team i
identified one Unresolved Item (URI) which concerned the i
application of the Maintenance Rule for Unit 1.
Subsequently, in l
a letter to TVA dated July 30,1997 (Reference 1): the staff i
i
,,e y -
m.
,-w,-, -
r
i-ENCLOSURE e
TENNESSEE VALLEY AUTHORITY l
BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 l
REQUEST FOR AN EXEMPTION IN ACCORDANCE WITH 10 CFR 50.12 FROM THE REQUIREMENTS OF 10 CFR 50.65, MAINTENANCE RULE l
concluded that the scope of the BEN Maintenance Rule Program for
[
j Unit 1 was not consistent with the requirements of the rule.
This letter further stated that TVA had three apparent l
alternatives:
i
- 1. Revise the scope of the Maintenance Rule monitoring j
program for Unit 1 to-include structures, systems, and components as specified in paragraph (b) of the rule, or l
2.
Submit a written certification to the NRC as specified in 10 CFR 50.82 (a) (1) that TVA has determined to l
permanently cease BFN Unit 1 operations, or
- 3. Petition the NRC for an exemption from the requirements of the rule that are not currently being met.
l The staff requested TVA to describe which of the three l
alternatives it considers to be applicable, or propose another course of action and discuss why that option was consistent with regulatory requirements.
TVA replied by letter dated September 29, 1997 (Reference 2),
stating that it did not believe that the selection of any of the above-enumerated alternatives was warranted since TVA's existing program to implement the Maintenance Rule for Unit 1 met the requirements of 10 CFR 50.65.
On January 26, 1998 (Reference 3), TVA met with the staff to further discuss TVA's position regarding this issue.
As a result l
of this meeting, the staff requested TVA to submit its alternate plan for the Unit 1 Maintenance Rule program.
On April 3,
- 1998, (Reference 4), TVA submitted an alternative plan which would have j
scoped the Unit 1 SSCs in a manner analogous to Units 2 and 3.
This plan, however, would ultimately have led to the placing of a l
large number of Unit 1 SSCs in "a(1)" status, since many of the systems cannot be monitored to prove that they can perform their-design function in their current lay-up condition.
E-2
i ENCLOSURE TENNESSEE VALLEY-AUTHORITY DROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 I
REQUEST FOR'AN EXEMPTION IN ACCORDANCE WITH 10 CFR 50.12 FROM THE REQUIREMENTS OF 10 CFR 50.65, MAINTENANCE RULE l
While TVA still believes that the current program meets the requirements of the Maintenance Rule, TVA is submitting this l
petition for an exemption as proposed by NRC in the July 30, 1997, letter to expeditiously resolve this issue.
j l
The following justification and safety impact assessment are l
provided in support of this
) quest.
JUSTIFICATION l
10 CFR 50.12 authorizes the Commission to grant exemptions from the requirements of the regulations provided that:
The exemption is authorized by law; l
The exemption does not present an undue risk to the public health and safety; e ~ The requested exemption will not endanger the common defense and security; Special circumstances are present as defined in e
j 10 CFR 50.12 (a) (2).
I.
The Requested Exemption is Authorized By Law The Commission is authorized by law to grant this exemption.
II.
The Requested Exemption Does Not Present an Undue Risk to the Public Health and Safety l
BFN Unit 1 systems that perform a required function while the unit is in a defueled condition, or which directly support Unit 2 or Unit 3 operations, are currently being operated and maintained under applicable technical specifications and plant programs, including the 4
Maintenance Rule.
Appropriate scoping of Unit 1 systems, E-3
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A ENCLOSURE TENNESSEE VALLEY' AUTHORITY BROWNS FERRY NUCLEAR PIANT (BFN) l UNIT 1 REQUEST FOR AN EXEMPTION IN ACCORDANCE WITH 10 CFR 50.12 FROM THE REQUIREMENTS OF 10 CFR 50.65, MAINTENANCE RULE structures, and components (SSCs) into the Maintenance Rule has been performed based on current plant conditions (Unit 1 defueled and in lay-up, Units 2 and 3 in operation). As a result, Unit 1 systems, or appropriate portions thereof, such as Fuel Pool Cooling and Cleanup, Raw Cooling Water, Fire Protection, Reactor and Refuel Zone Ventilation, Radiation Monitoring, Residual Heat Removal, and Reactor Building Closed Cooling Water have been adequately scoped into the BFN Maintenance Rule program.
Unit 1 systems and components that are-not required to be operational have been drained, de-energized, disassembled, and placed in dry lay-up under a formal lay-up program as appropriate. Both safety and non-safety-related plant systems are included in this lay-up program which is designed to protect and preserve equipment until Unit 1 is returned to service.
The lay-up program is described in l
plant procedures and includes periodic monitoring of equipment condition and provisions for corrective actions when lay-up criteria are not met.
I The current BFN Maintenance Rule Program requires that if Unit 1 conditions change, the affected.SSCs will be re-evaluated for 10CFR50.65 applicability.
Based on the foregoing, the current maintenance programs in place for i
BFN Unit 1 maintain and monitor the unit in a manner that fully assures the safety of the unit and appropriately consider the non-operational status of Unit 1.
Therefore, approval of the requested exemption will not present an undue risk to the public health and safety.
I III. The Requested Exemption Will Not Endanger the Common Defense l
and Security The proposed exemption is consistent with common defense and security and is otherwise in the public interest.
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ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 REQUEST FOR AN~ EXEMPTION IN ACCORDANCE WITH 10 CFR 50.12 FROM THE REQUIREMENTS OF 10 CFR 50.65, MAINTENANCE RULE i
IV.
Special Circumstances are Present Which Necessitate the Request for an Exemption to the Regulations of 10 CFR 50.65 j
TVA believes that special circumstances are prerent in this instance to wartint exemption from the regulatory requirements of 10 Ctn 50.65.
Specifically, Sections (ii), (iii), and (v) of 10 CFR 50.12 (a) (2) state, (ii)
" Application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the role; The underlying purpose of the Maintenance Rule is to ensure that structures, systems, and components of nuclear power plants be maintained so that the plant SSCs will perform their intended function when required.
Due to the status of Unit 1, defueled and in long-term lay-up, the safety function of many of the systems is not required.
Since these systems' safety functions will not be required until restart of the unit, no legitimate purpose would be served in maintaining any present ability to perform their intended function.
Indeed, the very status of those SCCs precludes any present ability to perform the.r intended function.
TVA will implement the Maintenance Rule for Unit 1 systems not currently under the scope of the rule at restart.
(iii) " Compliance would result in undue hardship or other costs that are significantly in excess of those contemplated when the regulation was adopted, or that are significantly in excess of those incurred by others similarly situated;....."
Strict compliance with the 10 CFR 50.65 (a) (1) (b) requirement of the rule for timely corrective action would result in unnecessary expenditure of considerable funds and resources to bring equipment r
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. ENCLOSURE i
TENNESSEE VA112Y AUTHORITY l
l BROWNS FERRY NUCLEAR PIANT (BFN)
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UNIT 1 REQUEST FOR AN EXEMPTION IN ACCORDANCE WITH 10 CFR 50.12 l
FROM.THE REQUIREMENTS OF 10 CFR 50.65, MAINTENANCE RULE into conformance with goals related to the intended safety functions of Unit 1 SSCs..
Review of the rule
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and the Statements of Consideration indicate that the l
application of the rule to a plant in an extended i
lay-up period was not contemplated.
(v)
"The exemption would provide only temporary relief I
from the applicable regulation and the licensee or applicant has made a good faith effort to comply with t h e r e g u l a t i o n ;...... "
The requested exemption would provide only temporary l
relief from the rule.
This exemption is being requested to allow maintenance of BFN Unit 1 under l
the current programs described above until such time TVA may decide to restart Unit 1.
TVA has implemented a program that is designed to i
l comply with the purpose and intent of the Maintenance Rule for Unit 1.
This program, which was described to NRC by letter dated September 29, 1997 (Reference 2), utilizes a scoping methodology which is slightly different than the methodology endorsed by the staff l
in NRC Regulatory Guide 1.160, " Monitoring the l
-Effectiveness of Maintenance at Nuclear Power l
Plants."
For BFN Unit 1 in its current defueled status, most of the Unit 1 SSCs are not required to perform the functions required to be monitored by 10 CFR 50.65 (b) and cannot perform these functions due to the lay-up status of the unit.
The Unit 1 systems that perform a required safety function in the defueled condition or that directly support Unit 2 or Unit 3 operation are included in the Maintenance Rule i
Program as appropriate.
The lay-up status of Unit 1 l
was appropriately recognized and factored into the l
scoping of Unit 1 SSCs for the Maintenance Rule Program.
As stated above, the current Maintenance j
Rule program also explicitly requires that the scoping of Unit 1 SSCs be re-evaluated if the status of Unit 1 changes.
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l ENCLOSURE t
TENNESSEE VALLEY AUTHORITY l
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' BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 REQUEST FOR AN EXEMPTION IN ACCORDANCE WITH 10 CFR 50.12 FROM THE REQUIR3MENTS OF 10 CFR 50.65, MAINTENANCE RULE
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i ASSESSMENT OF THE SAFETY IMPACT The approval of this exemption request does not impact the probability of occurrence of any accident.
The requested temporary exemption from the Maintenance Rule does not impact any event precursors or event initiators.
The exemption does not create the possibility of a new or different kind of accident from those previously analyzed.
The exemption request is administrative in nature. The proposed exemption does not add any new equipment or require any existing equipment to be operated in a' manner different from the present design.
Plant SSCs will continue to be operated consistent with the SAR analysis for design basis accidents.
No operation outside of the existing design basis is introduced by the proposed exemption.
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The Maintenance Rule exemption will not physically modify any i
equipment, setpoints, equipment initiation sequences or safety
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system redundancy.
Therefore, approval of the requested exemption will not involve a significant reduction in the margin of safety.
l CONCLUSION l
Approval of the exemption request will resolve the open issue associated with the implementation of the Maintenance Rule for Unit 1.
The current maintenance programs in place for BFN Unit 1 l
maintain and monitor the unit in a mannar that fully assures the safety of the unit and appropriately considers the non-operational status of Unit 1.
These programs continue to meet the full letter and intent of the rule.
The proposed exemption poses no risk to the health and safety of the public.
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ENCLOSURE l
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TENNESSEE VALLEY AUTHORITI BROWN 3 FERRY NUCLEAR PLANT (BFN)
UNIT 1 REQUEST'FOR AN EXEMPTION IN.ACCORDANCE WITH 10 CFR 50.12 FROM THE REQUIREMENTS OF 10 CFR'50.65, MAINTENANCE RULE REFERENCES
- 1. NRC letter to TVA dated July 30, 1997, Implementation of.the Maintenance Rule, 10 CFR'50 65, For Browns Ferry Nuclear Plant, Unit 1
- 2. TVA. letter _ to NRC dated September 29, 1997, Browns Ferry Nuclear Plant - Unit 1 - Response to NRC Request Regarding Implementation of Maintenance Rule, 10 CFR 50.65 (URI 50-259/97-04-01)
- 3. NRC-meeting summary dated February 6, 1998, Summary of Meeting With. Tennessee Valley Authority on Implementation of 10 CFR
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50.65 - Meeting of January 26, 1998
- 4. TVA letter to NRC dated April 3, 1998, Browns Ferry Nuclear Plant - Unit 1 - Revised Response to'NRC Request Regarding Implementation of Maintenance. Rule,' 10 CFR 50.65 (URI 50-259/97-04-01) i I
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