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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 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 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 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 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 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 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. 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 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 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, ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 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 ML20196G9111999-06-28028 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits 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 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 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment 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 ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage 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 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 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 ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co 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 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 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval DD-99-06, Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 9904281999-04-28028 April 1999 Informs That Time Provided by NRC within Which Commission May Act to Review Director'S Decision (DD-99-06) Has Expired.Decision Became Final Agency Action on 990423.With Certificate of Svc.Served on 990428 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 ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 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 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 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 ML18039A7931999-06-0101 June 1999 Provides Summary of Major Activities Performed at BFN During Scheduled Unit 2 Cycle 10 Refueling Outage 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 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 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 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 ML18039A7741999-04-30030 April 1999 Forwards Proposed Rev to BFN Unit 3 RPV Matl Surveillance Program,For NRC Approval 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 ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 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 ML20207C0501999-02-25025 February 1999 Submits Annual Rept Specifying Quantity of Each of Principal Radionuclides Released to Environment in Liquid & Gaseous Effluents,Per 10CFR72.44(d)(3).Effluent Release from ISFSI for CY98 Was Zero 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 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 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 1999-09-09
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l Tennessee Vaney Authority. Post Off:ce Box 2000. Decatur. Alabama 35609 May 14, 1998 10 CFR 50.90 U.S. Nuclear Regalatory Commission ATTN: Document Control Desk Washington, DC 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority ) E0-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 TECHNICAL SPECIFICATIONS (TS) CHANGE - 362 - IMPROVED TECHNICAL SPECIFICATIONS (ITS) SUPPLEMENT 19 - ITS SECTION 3.3 AND CLARIFICATION OF ITS PROVISIONS REGARDING ANALOG TRIP TESTING The Enclosure to this letter provides supplemental information in support of the TS-362 amendment request relating to Section 3.3, Instrumentation. TS-362 is TVA's conversion package from Current Technical Specifications (CTS) to ITS and was originally submitted to NRC on September 6, 1996. This supplement provides Revision 2 to Section 3.3. Revision 1 to Section 3.3 was submitted to the NRC on December 29, 1997.
This supplement makes several ITS/ITS Bases revisions and changes to supporting documentation in response to NRC comments provided in meetings on March 26, 1998, and April 14, 1998,.on Section 3.3 and in a follow-up teleconference on April 15, 1998. Several TVA initiated changes are also included as identified in the Enclosure.
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9905200134 990514 FM ADOCK 05000259 F PDR
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. U.S. Nucl' ear Regulatory Commission Page 2 Phy 14, 1998 The enclosed supplemental information does not alter the determination that the changes qualify ~for a categorical exclusion from environmental review pursuant to.the provisions of 10 CFR 51.22 (c) (9) . Additionally, in accordance with 10 CFR 50.91 (b) (1), TVA is sending a copy of this letter and enclosures to the Alabama State Department of Public Health.
TVA wauld also like to'use this letter to restate our position on testing of analog trip type instruments with
- . regard.to the transition from CTS to ITS. Specifically, in l
CTS there are several notes that apply to specification requirements for instrumentation for analog trip type devices that explicitly specify that a Channel Functional Test (CFT) consists of injection of a simulated signal into the electronic trip circuitry'or measurement channel in place of a system signal sensor to test the trip and alarm functions of the system. Examples of these are Note 7 to Table 4.1.A, Note 27 to Tables 4.2.A through 4.2.L, and footnote (1) to Table 4.7.A. These CTS notes are not being carried forth in
' the' proposed'BFN'ITS.
TVA's position is that the definition of CFT in Section 1.1 of the ITS' explicitly allows testing in the'same manner as CTS (use of a' simulated signal) and, hence, it is not necessary to incorporate the CTS notes in ITS. _
This issue was discussed with NRC staff to ensure that it was understood that'under ITS,~ testing.of analog trip type devices would continue in the same manner as currently employed under CTS and that ITS provisions were consistent with this approach.
NRC indicated that'it was accepted practice to perform analog trip-system testing in this manner and that the BFN ITS provisions supported this methodology.
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U.S. Nuclear Regulatory Commission Page 3 May 14, 1998 There are no commitments contained in this letter. If you have any questions, please contact me at (256) 729-2636.
Si/ cerely, j T. E. Abney Manager of Lice oing and Industry ffai s Subscribed and sw n o before me on is 14th day May iggg, C
Notary Public dd/d k t /4/ O My Commission expires -% CC'"'" W @ ** I E " {
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U.S. Nuclear Regulatory Commission Page 4 May 14, 1998 Enclosure cc (Enclosure) :
Chairman Limestone County Commission 310 West Washington Street Athens, Alabama 35611 Mr. A. W. De Agazio, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Harold O. Christensen, 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 Dr. Donald E. Williamson State Health Officer Alabama State Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-3017 I
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SUMMARY
DESCRIPTION of ITS/ BASES CHANGES ITS SECTION 3.3 - INSTRUMENTATION TVA is submitting a proposed supplement to TS-362 for ITS Section 3.3, INSTRUMENTATION. This supplement makes several changes associated with NRC comments on Section 3.3, and incorporates changes resulting from internal TVA reviews. A synopsis of the ITS and ITS BASES changes is provided below. i l
SECTION 3.3.1.1, RPS INSTRUMENTATION SURVEILLANCE REQUIREMENTS AND CORRESPONDING BASES In response to TVA reviews, changed frequency on SR j 3.3.1.1.7 from 1000 effective full power hours to 1000 MWD /T I average core exposure to be consistent with NUREG-1433.
TABLE 3.3.1.1-1 AND CORRESPONDING SAFETY ANALYSIS, LCO, AND APPLICABILITY BASES )
i In response to TVA reviews, deleted applicability of MODE l 5and associated SR FUNCTIONS 2.a, Average Power Range l Monitors Neutron Flux - High Setdown, and 2.e, Average Power !
Range Monitors Neutron Inop. This change is made to be l
consistent with NUREG-1433. l BASES, BACKGROUND In response to TVA reviews, made editorial changes to agree with previously submitted NUREG mark-up.
BASES, ACTIONS In response to an NRC comment, clarified details for Function C.1 to better define when Functions lose trip capability due to multiple inoperable /untripped channels.
SECTION 3.3.2.1, CONTROL ROD BLOCK INSTRUMENTATION TABLE 3.3.2.1-1 AND CORRESPONDING APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY BASES In response to TVA reviews, changed footnotes (a) and (b)
Minimum Critical Power Ratio (MCPR) values to agree with TS change 35351 and Amendment No. 249.
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SUMMARY
DESCRIPTION ofITS/ BASES CHANGES j l
l ITS SECTION 3.3 - INSTRUMENTATION l SECTION 3.3.2.2, FEEDWATER AND MAIN TURBINE HIGH WATER LEVEL TRIP l l
INSTRUMENTATION SURVEILLANCE REQUIREMENTS In response to internal TVA reviews, changed Allowable Value for SR 3.3.2.2.3 from 588 inches above vessel zero to 586 I inches above vessel zero to agree with change previously made to the NUREG mark-up.
SECTION 3.3.3.1, POST ACCIDENT MONITORING (PAM) INSTRUMENTATION SURVEILLANCE REQUIREMENTS In response to an NRC comment, made editorial changes to be ;
consistent with NUREG format. '
SECTION 3.3.3.2, BACKUP CONTROL SYSTEM SURVEILLANCE REQUIREMENTS AND CORRESPONDING BASES In response to internal TVA reviews, modified SR 3.3.3.2.2 calibration frequency for Unit 3 to agree with engineering analysis.
BASES, TABLE B 3.3.3.2-1 In response to internal TVA reviews, modified Table 3.3.3.2-1 (Backup Control System Instrumentation and Controls) to delete extraneous note from Unit 1 and 2 tables, and deleted from the Unit 3 table the required number of components for parameter 9.
SECTION 3.3.4.1, END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)
INSTRUMENTATION SURVEILLANCE REQUIREMENTS In response to internal TVA reviews, changed 2 10% to s 10%
for turbine stcp valve closure allowable value to agree with plant design.
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SUMMARY
DESCRIPTION ofITS/ BASES CHANGES ITS SECTION 3.3 - INSTRUMENTATION :
SECTION 3.3.4.2, ANTICIPATED TRANSIENT WITHOUT SCRAM
{ CIRCULATION PUMP TRIP (ATWS-RPT) INSTRUMENTATION l LCO In response to an NRC comment, changed water level nomenclature to be consistent other parts of the ITS.
l SURVEILLANCE REQUIREMENTS In response to an NRC comment, modified SR 3.3.4.2.1 water level nomenclature for consistency.
BASES, BACKGROUND, APPLICABLE SAFETY ANALYSES, LCO, AND APPLICABILITY In response to an NRC comment, changed water level nomenclature to be consistent with other parts of the ITS.
I SECTION 3.3.5.1, EMERGENCY CORE COOLING SYSTEM (ECCS)
INSTRUMENTATION ACTIONS AND CORRESPONDING BASES In response to an NRC comment, revised Completion Time descriptive information for Required Actions B.1, C .1, and ;
E.1 to be more consistent with NUREG terminology. j BACKGROUND, APPLICABLE SAFETY ANALYSES, LCO, APPLICABILITY, j AND ACTIONS BASES In response to internal TVA reviews, made editorial changes to agree with changes made in the previously submitted 1."J.'1EG mark-up and added clarification regarding the effect of the minimum flow bypass valve on High Pressure Coolant Injection System operation.
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SUMMARY
DESCRIPTION ofITS/ BASES CHANGES l ITS SECTION 3.3 - INSTRUMENTATION SECTION 3.3.6.1, PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION ACTIONS AND CORRESPONDING BASES In response to an NRC comment, revised the Required Actions.
Note A.1 was revised to more clearly delineate the applicability (changed "15 of 16 Channels OPERABLE" to "two or more Channels inoperable"). Required Action D.1 was )
changed from " Isolate the affected penetration flow path (s)"
to original NUREG text, " Isolate associated Main Steam Line (MSL)". Deleted Required Action G.1 and associated Note !
because Action was redundant to Actions in ITS Section 3.6.1.3, " Primary Containment Isolation Valves".
TABLE 3.3.6.1-1 In response to internal TVA reviews, corrected Functions 2.a and 2.b "Cenditions Referenced" from H to G in the NUREG mark-up to agree with changes previously made in identification of Required Actions.
In response to internal TVA reviews, changed Functions 3.a and 4.a " Allowable Value" from 150% rated steam flow for each function to 90 psi for Function 3.a and 450" H O for 2
Function 4.a to match corresponding CTS numeric values and supporting analysis.
In response to an NRC comment, revised footnote b to more closely match the NUREG text.
SECTION 3.3.6.2, SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS In response to an NRC comment, revised Note 3 to clarify that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Allowed Outage Time (AOT) is applicable only for channel calibration or maintenance.
SECTION 3.3.7.1,~ CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION ACTIONS In response to an NRC comment, revised the Required Actions and Completion Time description for D.1 and D.2 to be consistent with the NUREG.
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SUMMARY
DESCRIPTION ofITS/ BASES CHANGES l ITS SECTION 3.3 - INSTRUMENTATION l SURVEILLANCE REQUIREMENTS AND CORRESPONDING BASES In response to an NRC comment, revised Note 3 to clarify that the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AOT is applicable only for channel calibration or maintenance.
SECTION 3.3.8.1, LOSS OF POWER (LOP) INSTRUMENTATION ACTIONS AND CORRESPONDING BASES In response to NRC comments, changed the terminology from the relay logic being a channel to a relay being a channel.
Revised Required Actions A.1, A.2, B .1, B.2, C.1, C.2, D.1 and D.2 to accommodate the changing of relays to channels.
TABLE 3.3.8.1-1 In response to NRC comments, revised the number of required channels per board for the LOP Functions.
BACKGROUND, APDLICABLE SAFETY ANALYSES, LCO, AND l
APPLICABILITY BASES I l
1 In response to NRC comments, changed the terminology from !
the relay logic being a channel to a relay being a channel.
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