ML20217D215
| ML20217D215 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/24/1995 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20217D186 | List:
|
| References | |
| FOIA-97-252 NUDOCS 9710030083 | |
| Download: ML20217D215 (2) | |
Text
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UNITED STAf ts 6'
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101 MARitTTA STRt[T, N.W., sulTE 2000 ATLANTA, otoRotA 3GID4100
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February 24, 1995 s
Reaional Office Notice No. 0509 BROWNS FERRY UNIT 3 RESTART PANEL ESTABLISHMENT A.
Purcost:
% inform the staff of the establishment of the P.estart Panel for Browns h rry Uhtt 3.
B.
Disun:sion:
2 In 1985, all three Browns Ferry units were shut down and defueled due to poor perfonnance, significant enforcement actions, sevetal operational events, equipment failures, and the inability of management to identify knd correct problems.
In January 1991, the NRC published NUREG-1232, Volume 3, Supplement 2, as its final safety evaluation of the Browns Ferry Nuclear Performance Plan. Based on this and prior safety evalutt',on reports, the NRC concluded that TVA's connitments and correc;ive action programs for Unit 2 were acceptable. Unit 2 restarted on May 24, 1991.
TVA has since submitted its corrective action plan for returning Unit 3 to service.
By letter dated April 1,1992, NRR determined that TVA's plan was acceptable for returning Unit 3 to service.
On February 1, 1995, the Browns Ferry Unit 3 Restart Panel was established to perform an advisory role in accordance with NRC Manual Chapter 0350, Staff Guidelines for Restart Ap)roval. Mr. J. R. Johnson was ap)ointed as Chairperson and Mr. F. J. He > don as Vice Chairperson.
The otter members of the panel are J. F. Williams, M. S. Lesser, C. A. Casto, L. D. Wert, and W. E. Cline.
C.
6g11gn:
All staff members involved with Browns Ferry Unit 3 activities are expected to be familiar with the licensee's historical performance problems, specific to their inspection or oversight activities, and the related corrective action intended to resolve those problems. All inspectors need to closely plan and schedule their inspections with the Senior Resident inspector, L. D. Wert, and the DRP Acting Branch Chief, M. S. Lesser, as well as their imediate supervisor. These personnel are able to assist specialists in providing coordination with NRR as well as providing related Safety Evaluation references and other program acceptance criteria.
Staff and supervisors should plan inspections to focus the majority of inspection activity on those programs which have been modified from the Unit 2 program, while verifying with a sample that similar programs are being correctly implemented.
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9710030083 970929 4' 9 PDR FOIA
't, O'MEALI97-252 PDR
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Regional Office Notice No. 0509 2
D.
Contact:
Questions or coments regarding this Notice should be directed to Mr. J. R. Johnson, Deputy Director, Division of Reactor Projects.
E.
Cancellation Date:
This Notice is cancelled for record purposes on December 29, 1995.
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February 1, 1995 MEMORANDUM TO:
Jon R. Johnson, Deputy Director Division of Reactor Projects Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation Joseph F. Williams, Project Manager Project Directorate !!-4 Office of Nuclear Reactor Regulation Mark'Sr Lesser,, Acting Chief Reactor Projects, Branch 4A Division of Reactor Projects Charles A. Casto, Chief Engineering Branch Division of Reactor Safety Leonard D. Wert, Senior Resident inspector Reactor Projects, Section 4A Division of Reactor Projects William E. Cline, Chief Radiological Protection and Emergency Preparation Branch Division of Radiation Safety and Safeguards FROM:
Stewart D. Ebneter, Regional Administrator t/pW
SUBJECT:
BROWNS FERRY UNIT 3 RESTART PANEL AND ACTION PLAN I am pleased to inform you that you have been chosen as a member of the Browns Ferry Unit 3 Restart Panel.
Jon Johnson is hereby appointed as the Chairperson and Frederick Hebdon as the Vice Chairperson.
Panel members will be responsible for providing the necessary oversight of the Unit 3 restart project. As you are aware, Browns Ferry Unit 3 is a Category 3 plant requiring NRC Commission approval for restart.
In a:cordance with Manual Chapter 0350, Staff Guidelines for Restart Approval, the responsibilities of the Panel include the following and are further detailed in the attached Browns Ferry Unit 3 Restart Action Plan (and MC 0350 Checklist.
1.
Review available information related to the plant shutdown.
2.
Maintain the Restart Action Plan.
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4 J. Johnson, et al 2
3.
Review the licensee's corrective action or improvement program and ensure that it addresses identified problems and weaknesses.
4.
Maintain an ongoing overview of licensee performance throughout the corrective action process to include periodic meetings among members of l
the panel.
l S.
Conduct periodic meetings with the licensee to discuss progress toward satisfactory completion of the program. Meetings with the licensee will typically be open to the public.
6.
Provide oversight of the NRC's followup activities.
Review NRC inspection and assessment plans and findings, and licensee performance.
Identify areas where NRC inspection and technical review are needed.
7.
Periodically provide assessment of licensee performance and corrective actions to NRC management.
8.
Based on the satisfactory com)1etion of the licensee's restart program, provide a recommendation to tle Regional Administrator and Director, NRR for approval to restart.
Attachment:
Browns Ferry Unit 3 Restart Action Plant (and MC 0350 Checklist) cc:
L. A. Reyes, Ril W. T. Russell, NRR S. A. Varga, NRR G. M. Tracy, OEDO R. P. Zimmerman, NRR J. A. Zwolinski, NRR E. W. Herschoff, Ril A. F. Gibson, Ril J. P. Stohr, Rll
~
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i BROWNS FERRY 3 RESTART ACTION PLAN The Browns Ferry 3 Restart Panel Jon R. Johnson, Region II, Chairman Frederick J. Hebdon, NRR, Vice Chairman Joseph F. Williams, NRR Mark S. Lesser, RII Charles Casto, RII Leonard D. Wert, SRI William E. Cline, RII l
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BROWNS FERRY 3 RESTART ACTION PLAN 1.
Purcose To provide a plan in accordance with NRC Hanual Chapter 0350, Staff Guidelines for Restart Approval, and assign responsibility for NRC activities related to restart of Browns Ferry Unit 3 Nuclear Power Plant.
2.
Backaround in March 1985, all three units were shut down and defueled due to poor performance, signif' cant enforcement actions, several operational events, equipment failures, and the inability of management to identify and correct problems. On September 17, 1985 the Executive Director for Operations issued a letter to the Chairman of the Board of TVA pursuant to 10 CFR 50.54(f) requesting information on the actions the licensee was taking to resolve the NRC's concerns about TVA's nuclear program.
TVA's Corporate Nuclear Performance Plan was prepared in response to the NRC letter and submitted on November 1,-1985.
During the October 1986 Senior Management Meeting (SMM), all Browns Ferry Nuclear (BFN) Plants were placed on the watch list as Category 3 plants.
In 1986, TVA provided a revised Corporate Nuclear Performance Plan.
That was followed by a Browns Ferry Nuclear Performanco Plan (BFNPP) to address site specific weaknesses identified in the previous Systematic Assessment of Licensee Performance (SALP) report and to resolve certain additional concerns raised by the staff in 10 CFR 50.54(f)-letter.
In January 1991, the stsff published NUREG-1232, Volume 3, Supplement 2, as its final safety evaluation (SE) of TVA's BFNPP.
Based on this and prior SE reports, the NRC concluded that TVA's commitments and corrective action programs for Unit 2 were acceptable.
Unit 2 restarted on May 24, 1991.
On June 30, 1992, the Category 3 status on Unit 2 was revised.
Units 1 and 3 remain on the watch list in a Category 3 status.
By letters cated January 9, and July 10, 1991, TVA submitted its Regulatory Framework plan for returning BFN Units 1 and 3 to service.
TVA began implementing this plan almost immediately for Unit 3.
By letter dated April 1,1992, NRR determined TVA's plan was acceptable for returning Units 1 and 3 to service. This letter concluded that those
)rograms similar to Unit 2 are acceptable for Units 1 and 3 and that TVA 1as supplied the information required by the 10 CFR 50.54(f) letter.
3.
Responsibilities 3.1 The Browns Ferry Unit 3 Restart panel will coordinate staff activities, monitor licensee activities, and keep the Regional Administrator informed regarding restart of the unit. The Panel will conduct periodic meetings with the licensee to discuss progress toward satisfactory completion of the corrective action program. The Panel will provide oversight of NPC inspection i
activities and pro"ide assessment of licensee performance and corrective actions to NRC management.
The Panel Chairman will provide periodic briefings to the Regional Administrator. Based on the satisfactory completion of the licensee's restart program the Panel will provide a recomendation to the Regional Administrator and Director of NRR for restart approval.
3.2 The Reaional Administrator will coordinate with the Deputy Executive Director for Nuclear Reactor Regulation Regional Operations and Research, and with the Director of Nuclear Reactor Regulation (NRR) in implimenting the Restart Action Plan. Browns Ferry Unit 3 is a Category 3 plant and requires NRC Comissioner approval to restart. The Regional Administrator will keep the Director of NRR informed of staff and licensee restart actions.
3.3 The Associate Director For Pro.iects. NRR will assure that the l
Comission is kept informed of staff and licensee restart actions through Comission papers, EDO highlights, or communications with the EDO.
Based on these interactions between the staff and the Comission, the need for Comission briefings will be determined by the circumstances and the Comission's wishes.
4.
Action Plan Contents The Task Checklist for the restart process is provided as Ap)endix A.
The Issues checklist will identify all issues which need to )e resolved prior to unit restart.
The checklists will be maintained current and revised as appropriate by the Restart Panel.
Sumaries of the licensee programs and issuet being upgraded and the scope of planned major inspections shall also be maintained by the Restart Panel.
5.
Records All documents relating to the restart process will be included in the docket file and, to the extent permitted by 10 CFR 2.790, made public in accordance with NRC policy. Such records include:
a)
Minutes of Restart Panel meetings b)-
Minutes of meetings with licensee c)
Other government actions comunicated to the NRC d)
Comission papers e)
Documents approving restart f)
Inspection reports g)
Safety evaluations
t..
Appendix A BRCANS FERRY 3 TASK CHECKLIST TASK RESP.
DATE STATUS Establish Restart Panel Ril NRR
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Develop Restart Action Plan Ril, NRR Regional Administrator Approves Plan Ril NRR Associate Director Approves Plan NRR Notification Restart Panel established Ri!
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Review licensee generated restart Panel issues Independent NRC identification of Panel restart items (consider external
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NRC/ Licensee agreement on restart Panel issues Obtain public comments NRR Obtain comments from State and Local Ril Officials Obtain coments from applicable Federal RIl agencies Evaluate licensee's readiness self Ril assessment Conduct Operational Readiness NRR Assessment Team Inspection (ORAT),
Restart issues closed Panel Issue augmented restart coverage ROI RII Obtain staff comments on restart RII Re-review HC 0350 generic restart Panel checklist
l 1
Prepare restart recomendation document Ril and basis for restart to Regional Administrator Restart meeting with licensee Licensee Restart Panel recomends restart Panel Regional Administrator concurs in RII restart recommendation NRR Associate Director concurs in NRR restart recommendation EDO Concurs, in restart recomendation NRR ACRS briefing NRR Submit Commission paper NRR Comission briefing NRR Comission restart authorization Com Notify Congressional Affairs of restart NRR I
Notify ACRS of restart NRR Notify FEMA of restart Ril Notify OSHA of restart RII Notify Public Affairs of restart RII Notify State and Locals of restart RII Honitor restart RII i
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AppeTidix B BROWNS FERRY 3 ISSUES CIIECKLIST Date Printed: February 14, 1995 ISS* E DESCRIPil001 WRC (EAli IR/SI R tlCENSIT STAitf5 WRC ACTION CIWWFNTS STATtf5
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Deder st 5/27/67 94-33 Corrective Actions TAC M74613; PPA F076 II.8.3.3 PASS - ProcedJres Cecker SE 5/27/87; 2/22/95 15 ammeruf T AC MT4614; MPA FOTT; 6/21/94 MS3122 11.8.3.4 Pass Modifications Deck er st 5/27/57 Design conplete; 50% implement 12/94 TAC M44425; MPA 7012 75% imtement &/95 ll.E.4.1.2 Dedicated Hydregen SRI st 5/23/88 Corplete; ready f or stMs ready for closure closure Penetrations - Review eruf Revise H2 Control Proc TAC R00003 II.E.4.1.3 Dedicated Hydrogen SRI SE 12/22/81 Conplete; ree 4y f or SIMS shows ready for closure closure Penetratim - Instati T AC M44763; MPA 7018 II.E.4.2.1-4 Contelnment Isolation
$RI SE 1/6/95 TVA to provide completion status Deperdebility - Diverse 8/95 Isotation TAC MT1615; MPA 7078
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u-- STATUS CIpstNTS sutC LEAD IR/Ste LIGNSFE STATUS WRC ACfitut ISSHE DESCRIPTION 'e. I P 5 f! ' I PROGRANS IIS4DENTE3 Ig arrrunagm utTg 13lly 2 PREMBENT numEG 1232 v3 52 reviewed > 50% Iglement progree and NRC ttr of Cable Aspecity $hymf ock 751 leptement 4/95 6/23/93 reviewed folto.ap cceptete 5/95 Itene Cable Trey stgports stake SER 12/1T/91 TVA ttr 3/27/91; >90% laptement M 80684 cryptete 2/95 Program has changed; Conponent and Piece Parts Blake SER 12/7/93 possibly perform module 38703 on procurement ot:ellfleetion M 83828 IFI 94-18-02 g ned to Conteirmer! Costings $RI 94-01 94-09 track repelre to U3 94-18 94-27 CRD insert and Ulthdrawat Sleke Piping Design Calc Review Casto 11 2515/076 closed 92-03 <75% laptement j shystock EQ TAC M42482; MPA 8060 flexible Conduite Blake $hystock SER 13.6 93-Fuses 02 93 08 state SER 10/24/89 50% implement 2/95 Inspect es part of open 7/16/92 la conptete 5/95 Item closure WVAC Duct Stpporte TAC a00300, M82127 INbbfhbkbIk$-b ikk' 93-201 D$hk [iI$Y k.d$MhIM*$MI$s iggsEgyhaped.r9ewie w e @. w ps % @k*%M h)!
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1 STATW r WRC LEAD IR/SER LIE NSEE STATUS sec ACTION 058tWTS ISSIE DE$talPflGU Licensee ethmittet NRt to write SER by fire Protect {on; Agp R. Casto of 12/20/94, status 7/95 1AC M85254 > 50% isplement 751 laplement 4/95 Long ters deelen criterie Lower Drywel1 Platforlas Blake SER 7/26/88 TVA 6/12/91 leptemente 1978 Alst spec 10/24/89 >901 leptement ord Misc steet TAC M80620 203303 '/19/52 crg tete 1/95 4/20/94 IR94-15, 93-201 PeacIUses usetETED ON Att TNEEE (AltfS NURUG 1232 V3 51 eec 2.3 Heat Code freceability stake sER 5/31/90 and NRC SEE of Mey 31, 1990 reviewed progree for ett 3 mits. Program evetuoted by Aprlt Secondary Contalrunent Stske SER 4/11/88 11, 1988 eddressed ett 3 mite Penetrations Wetding concerne 4 tely stake SER 5/31/90 addressed per NUCEG Welding Progree 1232,v3,St SER eddressed ett 3 mite Pipe Well Thiming Blake SER 8/31/88 (GL 87-01) Sources for issues include: IFS, SIMS, WISP, NUREG 1435 (Status of Safety Issues at Licensed Power Plants), BFNPP, NUREG 1232 (SER for Browns Ferry NPP) 14
s o STRUCTURAL ISSUES
Contact:
J. Lenahan SRI for Instrument Sensing Lines Backaround Cable tray supports - concerns were raised about the cable tray overfill, seismic support qualification and excessive application of fire-retardant material (Flamemastic). Program resolved in SSER 1, 2.2.2.7 and to implemented IAW unit 2 precedents. CRD Insert and Withdrawal Piping - concern raised about the adequacy of the~ control rod drive insert and withdrawal piping supports to sustain design basis loads; some Unistrut space frame supports for the CRD tube bundles would be overstressed under design basis earthquake loads. Program resolved in SSER 1 and 2, 2.2.3.2 and to be implemented IAW unit 2 precedent. HVAC duct supports - IR 88-38 identified concerns in the design area of HVAC supports. Program resolved in SSER 2, 2.2.2.4 and to be implemented IAW unit 2 precedent. Large bore piping and supports - IEB 79-02 was issued as a result of concerns with the installation and evaluation of concrete expansion anchor bolts in pipe support base plates. IEB 79-14 was issued as a result of concerns with the adequacy of the input information (as-built configuration) that had been used in the 7 seismic analysis of piping systems. Program resolved in SSER 1 and 2, 2.2.3.1 to be implemented IAW unit 2 precedent. Miscellaneous steel frames - reactor building framing has various safety related features attached such as pipe supports; seismic design concerns. Program resolved in SSER 2, 2.2.2.6 and to be implemented IAW unit 2 precedent. Platform thermal growth - concerna related to thermal growth of structural platforms outside the drywell, Program resolved in SSER 2, 2.4 to be implemented IAW unit 2 precedent. Seismic class II/I - concern identified with the interaction of seismic Class II (NSR) systems on Class I (SR). Phase 1 program associated with water spray affects resolved in SSER 1 and 2, 2.2.4.2 and to be implemented IAW unit 2 precedent. Phase 2 program associated with evaluation of seismic induced spacial affects to be resolved in conjunction with USIs A-17 and A-46. Conduit support - issues regarding support rod hangers and Conduit with Unistrut support; field routing not in accordance with applicable specs and criteria. Program resolved in SSER 1 and 2, 2.2.2.3. Unit 3 program decarta from unit 2 implementation precedent as described in TVA ltr 5/6/91. SE of 3/20/92 approves program that all conduit other than rod-hung conduit will be evaluated IAW unit 2 program. Rod-hung conduit NV J
will be evaluated to determine if systems are enveloped by the unit 2 bounding calculations. Flexible conduits - construction specs did not adequately address requirements for minimum and maximum flexible conduit lengths to all for thermal and seismic movemant. Program resolved SSER 2, 3.12. and to be implemented IAW vnit 2 precedent, however since this was interim criteria, NRR wl:.1 issue SE for long term criteria. Instrument sensing lines - employee concerns raised regarding physical separation, sensing line slope, fabrication to quality standards. Program resolved in SSER 2, 3.4. Unit 3 program deoarts from unit 2 implementation precedent as described in TVA ltr 2/13/91 and 11/8/91. SE of 12/10/92 approves unit 3 program in that it will be similar to unit 2 however based on lessons learned, TVA will not perform a drawing review of the instrumentation layout no further review of quality classification is needed. Long term torus integrity - generic concerns on Mark I containment regarding torus dynamic loads not originally considered; discrepancies between design drawings and modifications to attached piping supports. Program resolved in SSER 1 and 2, 2.2.4.4. Unit 3 program departs from unit 2 implementation precedent as follows:
- 1) torus attached piping support discrepancies will be resolved with modifications IAW Unit 2 precedence, 2) Inspection of safety related torus and related structures will exclude 4 attributes which did not need modifications on Unit 2 (dimensions of std structural shapes, correct materials, grout dimensions, attachments to concrete mounted baseplates), 3) No inspections of non-safety related valve access platforms and limited inspections of non-safety related catwalks.
Small-bore piping, instrument tubing - adequacy of piping supports for seismic Class I small bore piping (<2 1/2 inch) and lack of design criteria for supports of capillary tubing and for addressing thermally induced stresses in tubing. Unit 2 program resolved in SSER 1 and 2, 2.2.3.3 - 4. Unit 3 program departs from the unit 2 implementation precedent. The unit 3 program combines the small bore piping and instrument tubing efforts. As-built walkdowns of installations will be performed. A rigorous analysis of a sample will be performed. The sample will be used to identify adverse attributes not identified during unit 2 walkdowns. Interim operability criteria will not be used. Lower drywell steel platforms - unanalyzed attachments to drywell access platforms. Unit 2 program resolved in SSER 1 and 2, 2.2.2.5. Unit 3 program deoarts from unit 2 criteria precedent. Operability criteria for seismic qualification of drywell steel platforms (interim), misc steel (interim), electrical conduit supports, HVAC ductwork and supports in the NRC SE of 7/26/88. The licensee proposed long term design criteria regarding lower
. - ~ ~ - - _. - - - - f w t [ 'drywell steel platforms in TVA ltr 6/12/91.- The' original FSAR l-used the 1963 AISC specs but the proposed design. criteria utilizes the 1978 AISC spec for live and seismic loads, allowable + stresses, etc. -The NRC staff has concerns with.the licensee's ) application of ductility ratios when considering load combinations on steel structures constrained from expansion. (NRC ltr 3/19/92). Issue reso1ved in SE 4/20/94, ~ i Secondary containment penetrations - FSAR stated that penetrations through secondary containment are Class I seismic. j' FSAR also indicated that the containment must perform its safety j function following a design basis earthquake and design basie accident. Although the possibility of a DBE and DBA occurring j-simultaneously are extremely low, the licensee has taken a very i conservative approach and implemented a program to upgrade its i penetration seals in order to conform to the FSAR. Program resolved in SSER 1 and 2, 2.2.2.8 and has been completed on all units. InsDections Comoleted to dates 93-201 Structural Steel platforms, HVAC duct support 94-04 Pipe support cales, shallow undercut achors, wedge i anchor i 94 Long term Torus Integrity Program 94-15 Platform Steel.and Large bore Pipe Supports 94-24 Instrument Sensing Lines i. 94-32 Core Spray Support Mod i 94-29 Pipe support calc program and pipe supports, Bechtal QA f audits, PERs, Drywell platform structural steel, 95-03 Pipe supports, hangers, CRD insert and withdrawal pipe and stress cales, large and small bore pipe, spring can j 95-15 Structural steel frames and platforms, conduit support, wedge achors 95-16 Hilti bolt base plate torquing J-95-33 Rad monitor inst line slope, heat tracing } 95-38 RERSW pipe replacement 95-41 Cover plates, drywell platforms 95-52 BWR scram system piping, HVAC supports, large bore pipe i supports, cable tray and conduit supports 95 Cable tray and conduit support, Seismic II/I, j Instrument tubing, Small bore pipe, steel platforms i V
.+ DESIGN BASIS ISSUES
Contact:
C. Casto Hapkground ~ No design policy existed that would provide a reference basis for deciding how to judge the design requirements and thus no explicit set of baseline design documents existed. Design Baseline and Verification Program (DBPV) was established to resolve the identifed problems related to design control including:
- 1) The original design control program allowed an as-built set of drawings maintained by operations and an as-designed set of drawings to be maintained by engineering.
- 2) The plant configuration was not reconciled with the design basis because the plant design basis was scattered among many documents, thus making it not readily usable.
- 2) External reviews and studies indicated weaknesses in plant modifications.
The program was reviewed in SER, 2.1. Design Calculations Review is IAW Unit 2 precedent. Configuration Management / Design Baseline deoarts from the Unit 2 implementation precedent. The program on Unit 2 was implemented in 2 phases; Phase I completed prior to startup and Phase II delayed until the first refueling outage. Unit 3 will consolidate the phases and complete them prior to startup. It will also address the operation of Units 2 and 3 combined. The program will not evaluate and reconcile differences between as-built and as-designed drawings as was done on Unit 2. Walkdown data will be used togenerate verified as-built drawings, which will be evaluated against the design basis. Inspections: 94-07 DBVP (EECW) 94-20 Drawing Deviation controls 94-31 DBVP vertical slice of RHR, HPCI design criteria, BTRD, Cales, QA audits of program 95-36 Drawing controls 95-50 Design related CATDs 95-51 Assessment of drawing issues
PROCUREMENT AND QUALIFICATION ISSUES
Contact:
MacDonald
Background
Component and Piece Parts' Qualification - Deficiencies is TVAs practices for procurement and control of SR replacement items were identified. Program established to verify equipment certified previously as EQ or seismic had not been degraded through inadequate replacement practices. Program resolved in SSER 2, 3.3. Equipment Qualification - In Aug 1985 TVA, assisted by Westec Services, conducted a management review of EQ activities and concluded that qualification documentation had not been established for the large majority of equipment reviewed. Problems resulted from an unstructured program, lack of guidance, and an inconsistent appr'.ch taken by the fragmented organization. Program waA resolved in SER and SSER2, 3.2. Q-List-Program resolved in SSER 2, 3.15 These programs are to be implemented IAW the Unit 2 precendent. Inspections 94-06 EQ Cabling 94-27 EQ aspecte of Recirc Pump disch motor 94-35 EQ program, folders, Beta shield tape, raychem splice 95-43 Q list 95-56 EQ program and emergent issues 95-60 Piece Parts program
o 1 FIRE PROTECTION; APPENDIX R GL 92-04/IEB 92-01 (Thermolag) CONTACT: C. Casto. j. .Backaround ^~ 1 Appendix R issues remain open at Browns Ferry. DRS will review l the opeaiitems and conduct u Fire Protection review. The Fire Protection and Appendix R program deoarts from the Unit 2 criteria precedent. Thermo-Lag is an Agency concern that is undergoing an Agency j evaluation. NRR has an action plan that the Region will follow. i Inspections: 4 94-27 Appendix R compensatory measures NCV r 95-04 Fire suppression system design flow cales, system l walkdown, drawings, mods. 95-07 Fire detection and suppression mods Jz .95-36 Outside Security Lighting calc 95-37 App R. team inspection 95-38 ~Thermolag installation 95-43 Fire brigade 95-50 CO2. fire protection mods-95-51 App R. Safe Shutdown Instruction simulation i 95-60 SSI simulation, emergency lighting-95-64 Fire Protection comp measures d 1
- - ~ -. - -. ~ _ _, _ - - - ~ - -. -. - - --...- - v. 4 != -RESTART' TEST PROGRAM
Contact:
SRI MacDonald Backaround-3 Because of the prolonged plant shutdown and extensive modifications, a comprehensive-restart test program is required to ensure that plant systens are capable of meeting-their safe shutdown requirements under transient and accident conditions. On Unit 2, the DBVP developed the System Test Specifications 4 necessary to satisfy safe shutdown requirements as described in SER, 4.6. The unit 3 program deoarts from the Unit 2 precedent. l The Unit 3 RTP integrates all testing needed to return a system to service 11nto the System Test Specifications, including post modification-and post maintenance tests. This-will reduce duplication efforts. Turbine _ Trip Test, Feedwater Pump Trip Test and Backup Control System Test will not be performed due to ' acceptable testing during; initial startup and no significant i-modifications. Backup control testing is included in the individual system tests. LOP /LOCA test is not planned because i -Unit 2 testing demonstrated-electrical system operation'for all 3 units. 18M TS surveillances on EDG, simulhting LOP _will be J -performed. [ Inspections 93-36 Joint Test Group 95-07 Restart-test program review 95-08 Containment leak rate testing; RHR, CS, HPCI penetrations 95-26 SLC System review of BTRD' implementation into test procedures 95-31 EECW flow test / BTRD 95-38 SLC. phase 2-test 95-43 Hydrotest RHR, LPCI mods; RPS instrument calibrations 95-51 Core Spray testing, RHRSW testing, Control and Service Air testing,. Common Accident Signal logic test review, Degraded grid voltage relay testing 95-56' RHR flow test, HPCI test, control air test, RCIC test, MSIV test 95-60 ILRT, Restart testing w. e e
s, = OPERATIONAL READINESS
Contact:
Lesser i .Backaround ~ -Aspects of Site Management and Organization, Independent Oversight,-Quality Assurance, corrective action, self assessment were: reviewed during unit 2 restart and in SALP, Inspections vf. ' effectiveness have been essentially continuous and will continue .to be conducted to assess readiness for multi-unit operation. Inspections 93-36 Procedure upgrade, Ops, Mnt, Sur; CCW SPOC 93 CCW SPOC; separation boundary 93-44 Minor systems SPOC 93-45 Raw Water SPOC 94-01= CCW SPOC 94-06 Raw Water SPOC 94-07 QA Audit of DBVP 94-09 Raw Water SPOC; New corrective action process; Layup process 94-20 Problem Resolution 94 Corrective Actions; PER process 94-36: Organization; SLC SPOC 95-10 QA organization and U3 restart plan 4kV Electrical and EECW system _walkdowns 95-16 EECW and 4kV walkdowns; Core Spray, RHRSW pipe replacement 95-31 RWCU SPOC, Operator perf issues, NSRB review 95-38 PORC review, Service Air phase 1 SPOC, CAD phase 1 SPOC, multiunit event response coordination 95-43 CRD phase 1 SPOC, HCOs 95-47 CREVS review 95-51 SPOC phase 1 for: HPCI, RCIC, Main Steam, Drywell control air. Flood protection, Review of INPO Restart Assist visit. 95-56 Multi-unit sensitivity, SPOC-Sequence of events recordor,-annunciators, Main Steam SPOC 1, RWCU walkdown, Unit Separation program 95-62 _ -Service Water team inspection 95-210 ORAT 95-64 Power Ascension
1 RADIATION PROTECTION READINESS Contactr W. Rankin Backcround' ~ No,significant problem areas were previously identified other than excessive reliance on the use of contractors. _IDsDections 95-11 RP organization, U3 RP-punchlist 95-33 Rad monitors, controls 95-42 Area rad monitors installation and calibration, Restart survey procedures, training on new instrumentation, equipment readiness 95 Chemistry inline monitors for RWCU, Cond and FW; Liquid radwaste, SBGT, offgas system 4 95-55. RP Punchlist, Survey plans 95-60 PASS, water chemistry, Liquid Radwaste, CREVS 95-65 HP' surveys, exposure controls O 4 4' 1 5 4 4 6 4 4 r ~
-___ ___ _ __ __ =__ ____ _ 4 4'.' 1 d ],- EMERGENCY PRLPAREDNESS READINESS i:
Contact:
'.<.IBarr Bac'korounf-Specific concerns in this area were resolved for Unit 2 startup. ) Program reviewed-in SER, 4.9. Insp3ctions 95 Response facility, evacuation warning, CREVs, accident assessment, communications 95_38 EP exercise observation 95-46 Organization,. training, Accident Assessment equipment and communication, equipment, meteorology equip. i -. j s 4 4 i
EMPLOYEE CONCERNS
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SRI Backaround In June 1986, NRC notifie~d the licensee that TVA employees had raised a number of significant safety concerns to the NRC. Included in the expressions of concerns to the NRC were the employees' fear of reprisal by TVA managers if employees raised their views on safety issues within TVA. The NRC expressed its disapproval to the licensee that the TVA policy and program for handling employee issues did not involve a feedback to managers of types of issues that employees had raised. Further the NRC believed the potential existed that other nuclear safety issues would remain unexpressed because employees feared reprisal from TVA managers. There were indications that the licensee's programs and policies were not being fully implemented and that the legal and policy protection against reprisal had not gained the full confidence of all TVA employees. In response to the recognition that existing programs to identify and resolve concerns of employees were not fully effective, TVA awarded Quality Technology Company (QTC) a contract in May 1985 to develop and implement a program for conducting confidential interviews of all TVA employees associated with the Watts Bar Nuclear Plant. QTC also solicited concerns from TVA employees at the licensee's other nuclear sites. This program generated more than 5800 employee concerns. Approximately 710 were applicable to Browns Ferry by direct reference or generic applicability. These concerns are addressed by an Employee Concerns Program for which the staff has issued a seperate safety evaluation. All employee concerns received on anc after Feb 1, 1986 are handled by the new Concerns Resolution Program. Insnections 93-43 Licensee and Contractor Employee Concerns Prog.ams 94-10 Employee Concerns 94-20 Concerns Resolution Program 94-29 Employee concerns regarding pipe support cales 95-10 Rollover process; TI 2515/074 Employee Concerns 95-20 Electrical CATDs 95-21 Electrical CATDs 95-36 Drawing CATDs 95-56 Review of CATD closure letter
Or l-A= A. l L Date Printed:' January 26, 1996 ELECTRICAL ISSUES
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S. Rudisail, G.-MacDonald Backcround Cable Ampacity --INPO identified lack of design calculations to-show adequacy of cable ampacities; design standards were incomplete and did not properly account for effects of environment. Program resolved SSER 2, 3.11.3.1 and to be = implemented IAW unit 2 precedent. Fuses insufficient evidence that installed fuses would provide electrical equipment with adequate overload protection and would not prevent equipment from performing its safety function. Program resolved SER, 3.11.2 and to be implemented IAW unit 2 precedent. Splices _~ _IN 86-53:regarding improper installation'of heat-- shrinkable tubing over electrical splices and terminations and an employee concern regarding existing site procedures for installing electrical splices. Program resolved SSER 2, 3.13 and-to be implemented IAW unit 2 precedent. Thernal Overloads -' drawings for-480VAC and 250VDC MCCs did not specify therral overload _ ratings; no evidence thnt overloads as installed were' selected or reviewed by qualified engineering personnel. Program resolved SSER 2, 3.11.1 and to be implemented IAW unit 2: precedent. Cable installation, including cable separation - employee concerns rugarding inadequate cable installation may have caused damage to' cables. Inaccuracies of the cable and' conduit schedule, questionablenraceway-routing, routing without circuit protection. Program resolved in SSER 2,-3.11.4 5. Program decarts from unit 2 precedent; enhancements made to program described in-letter 5/10/91 and NRC SE 4/8/92. l l
~~ .y. .-- Inspections: 93-34 Cable Separation 93-35 Electrical Calcs 93-201 Electrical desi~gn changes i + 94-27 Electrical Cable 94-35 Cable ampacity and cales,_ cable tray walkdown, -ble pull, conduit fill 94-36 Battery replacement 95-01 Battery replacement 95-02 Fuse Control program 95-14 Cable' splice deficiencies 95-20 Cable separation, CATDs, Cable splice 95-21 CATDs, diesel turbocharger 95-25 Thermal overloads, CATD, Cable pull tension, Flamastic cable coating 95-34 SBO 95-31 EQ _95-39 CATDs cables 95 Fuses, separation, cable and conduit CATDs, cable raceway fill: 95-56 -Flexible conduit 4 I t 0}}