ML20042G895

Forwards Summary of 900411 Meeting in Rockville,Md Re Restart Schedule & NRC Master Insp Plan to Support Restart. List of Attendees Encl

ML20042G895
Person / Time
Site:	Browns Ferry
Issue date:	05/02/1990
From:	Wilson B Office of Nuclear Reactor Regulation
To:	TENNESSEE VALLEY AUTHORITY
References
NUDOCS 9005160246
Download: ML20042G895 (37)

Text

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1 MAY t i 1990 L

t Docket Nos. 50-259, 50-260, 50-296 License Nos. DPR-33, DPR-52, DRPR-68 i

Mr. Oliver D. Kingsley, Jr.

Senior Vice President, Nuclear Power j

Tennessee Valley Authority L

6N 38A Lookout Place 1101 Market Street Chattanooga, Tn 37402-2801

SUBJECT:

MEETING

SUMMARY

- BROWNS FERRY PLANNING MEETING, APRIL 11, 1990, DOCKET NUMBER 50-260

Dear Mr. Kingsley:

A planning meeting was held April 11, 1990 in White Flint with members of your staff in attendance.

The current Browns ~ Ferry restart schedule was discussed.:

as well as the NRC Master Inspection Plan (MIP) to support Unit 2 restart.

A meeting summary, list of attendees, and a copy of the current MIP are enclosed.

In-accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.

Should you have any questions concerning these matters, please contact me.

Sincerely, i

(Original signed by L. Watson) f Bruce A. Wilson, Assistant Director for Inspection Programs TVA Projects Division Office of Nuclear Reacror Regulation

Enclosures:

1. Meeting Summary 1

2. Attendence List

3. Master Inspection Plan (Revision 4) cc w/encls:

(See page 2) 9005160246 900502

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M. Runyon, Chairman E. G. Wallace, Manager Tennessee Valley Authority Nuclear Licensing and

.ET 12A 7A Regulatory Affairs 400 West Summit Hill Drive Tennessee Valley Authority.

Kncxv111e. TN 37902 SN 1578 Lookout Place 4

Chattanooga, Tfl 37402-2801 C. H. Dean, Jr., Director-Tennessee Valley. Authority P. Carier, Site Licensing Manager ET 12A 11A Browns' Ferry-Nuclear Plant l

400 West Summit Hill Dr1ve Tennessee Valley Authority.

Knoxville, TN 37902 P. O. Box 2000

Decatur, AL 35602 J. D. Waters, Director Tennessee Valley Authority L. W. Myers, Plant Manager ET 12A 9A:

Browns Ferry Nuclear Plant 400 West Summit Hill Drive Tennessee Valley Authority Knoxville, TN 37902 P. O. Box 2000 i

Decatur, AL 36bO2 W. F. Willis Chief Operating Officer TVA Representative ET 12B 168 Rockville Office 400 West Summit Hill Drive 11921 Rockville Pike Knoxville. TN 37902 Suite 402 Rockville, MD 20952 D. Nunn, Vice President Nuclear EngiN ering.

General Counsel Tennessee Valley Author:ty Tennessee Valley Authority

>400 West Summit Hill Drive 400 West Summit Hill Drive WT.12A 12A ET llB 33H Knoxville TN 37902 Knoxville, YN 37902 Dr. M. O. Medford Claude Earl Fox, M.D.

Vice' President and Nuclear State Health Officer Technical Director-State Department of Public Health Tennessee Valley Authority State Office Building 6N 38A Lookout Place Montgomery, AL 36130 Chattanooga,.TN 37402-2801 State'of Alabama Chairman, Limestone County Commission Dr. Henry Myers, Science Advisor P. 0.' Box 188 Committee on Interior and e

Athens, AL 35611 Insular Affairs U. S. House of Representatives Washington, D. C.

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0. J. Zeringue, Site Director Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35602 bec w/encls:

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R. Bernhard, NRR/Ril' J.-Rutberg, OGC.

M. S.-Callahan, GPA/CA NRC Document Control Desk NRC Resident Inspector U.S. Nuclear. Regulatory Commission Route 12, Box 637 Athens, AL - 35611 RII/NRRt RII/NR h

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.o Docket Nos. 50-259, 50-260,- f;0-296 License _Nos. DPR-33, DPR-52, DRPR-68 Mr; Oliver D. Kingsley, Jr.

Senior Vice President, Nuclear Power Tennessee Valley Authority.

6N 38A Lookout Place 1

1101 Market Street Chattanooga, Tn 37402-2801

SUBJECT:

MEETING

SUMMARY

- BROWNS FERRY PLANNING MEETING, APRIL 11, 1990,.

- DOCKET NUMBER 50-260

Dear Mr. Kingsley:

A planning meeting was held April 11, 1990 in White Flint with members of your

' staff in attendance. The current Browns Ferry restart schedule was discussed, as well as the NRC Master Inspection Plan (MIP) to support Unit 2 restart.

A meeting sunnary, list-of attendees, and a copy of the current MIP are enclosed.

.In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2 Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in.the NRC Public Document Room.

Should you have any questions concerning these matters, please contact me.

Sincerely, Bruce A. Wilson, Assistant Director for Inspection Programs TVA Projects Division Office of Nuclear Reacror Regulation

Enclosures:

1. Meeting Summary 2, Attendence List.

3.MasterInspectionPlan(Revision 4) cc w/encls:

(Seepage 2)

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, 4 Tennessee Valley Authority 2

i cc w/ encl:

M. Runyon, Chairman E. G. Wallace, Manager Tennessee Valley Authority Nuclear Licensing and ET 12A 7A Regulatory Affairs 400 West Sumit Hill Drive Tennessee Valley Authority-Knoxville, TN 37902 SN 157B Lookout Place Chattanooga, TN 37402-2801 C. H, Dean, Jr., Director Tennessee Valley Authority P. Carier, Site Licensing Manager ET 12A 11A Browns Ferry Nuclear Plant 400 West Sumit Hill Drive Tennessee Valley Authority Knoxville,TN 37902 P. O. Box 2000

Decatur, AL 35602 J. B. Waters, Director Tennessee Valley Authority L. W. Myers, Plant Manager ET 12A 9A Browns Ferry Nuclear Plant 400 West Sumit Hill Drive Tennessee Valley Authority Knoxville,TN 37902 P. O. Box 2000

Decatur, AL 35602 W. F. Willis Chief Operating Officer TVA Representative ET 12B 16B Rockville Office 400 West Sumit Hill Drive 11921 Rockville Pike Knoxville, TN 37902 Suite 402 Rockville, MD 20852 D. Nunn, Vice President Nuclear Engineering General Counsel

- Tennessee Valley Authority Tennessee Valley Authority 400 West Summit Hill Drive 400 West Summit Hill Drive WT 12A 12A ET 11B 33H Knoxville, TN 37902 Knoxville, TN 37902 Dr. M. O. Medford Claude Earl Fox, M.D.

Vice President and Nuclear State Health Officer Technical Director State Department of Public Health Tennessee Valley Authority State Office Building 6N 38A Lookout Place Montgomery, AL 36130 Chattanooga, TN 37402-2801 State of Alabama Chairman, Limestone County Comission Dr. Henry Myers, Science Advisor P. O. Box 188 Committee on Interior and Athens, AL 35611 Insular Affairs U. S. House of Representatives Washington, D. C.

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0. J. Zeringue, Site Director Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35602 bec w/encls:

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T. R.)ss, NRR.

D. Moran, NRR:

W.- S. Little.- NRR/RIl

.R..Bernhard,NRR/RII J. Rutberg, OGC-

-i M. S. Callahan,:GPA/CA NRC Document Control Desk NRC Resident Inspector U.S. Nuclear Regulatory Commission Route-12, Box 637 Athens, AL_ 35611

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ENCLOSURE 1 Meeting Summary Browns Ferry Planning Meeting White Flint April 11, 1990 TVA discussed the current progress in work supporting startup of Unit 2.

Mr.

Weber stated that bulk work appeared to be approximately one to two weeks behind-schedule, but this was not expected to affect the scheduled startup date.

The bulk work consists primarily of hanger and-pipe support modifications and electrical cable testing and replacement.

ILRT and Hydro schedule. dates could be firmed up by April 30, 1990 to allow the NRC to set inspection dates for these ' activities.

The remaining major milestones, as specified in TVA's March 28, 1990 letter were on schedule.

The NRC Staff discussed the Master Inspection Plan, explaining revisions made-since the last MIP, and additional prerequisites required for-restart inspections.

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1 ENCLOSURE 2 Browns Ferry Planning Meeting r

White Flint April.11.1990

.NRC Attend'ees:

l S. Black, Assistant Director for TVA Projects B. Wilson, Assistant Director for Inspection Programs T.'Ross, Project Manager-W. Little Section Chief R. Bernhard, Project Engineer D. Carpanter, NRC Site Manager, Browns Ferry l'

i TVA Employees.

P. Carter, Site Licensing Manager it. Crisler, Manager of Projects P.'Salas, Compliance Supervisor H. Weber, Engineering and Restart Manager i

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ENCLOSURE 3 BFNP RESTART MASTER INSPECTION PLAN REVISION 4 (APRIL 1990)

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'1 INDEX 1

I. INSPECTIONS PLANNED-4 A.

- SITE MANAGEMENT AND ORGANIZATION B.'

QUALITY ASSURANCE C..

SEISMIC ISSUES ~

D.

FIRE PROTECTION E.

ENVIRONMENTAL QUALIFICATION r

F.

-TECHNICAL SPECIFICATIONS G.

PROCUREMENT AND PIECE PARTS (Postponed)

H.

RESTART TEST PROGRAM I.-

OPERATIONAL READINESS FOR RESTART J.

ELECTRICAL DESIGN ISSUES K.

ROUTINE ONSITE INSPECTIONS

.L.

REGION II SUPPORT INSPECTIONS i

M..

ALLEGATION /0 PEN ITEM REVIEW FOR RESTART N.

PROCEDURE UPGRADES 3

0.

ANTICIPATED TRANSIENTS WITHOUT SCRAM P.

REFUELING II. INSPECTIONS COMPLETED A.

' DESIGN BASELINE VERFICATION PROGRAM AND DESIGN CALCULATION REVIEWS-8.

FUEL LOAD (JAN. 1989)

C.

WELDING D.

INTERGRANNULAR STRESS CORROSION CRACKING I-E.

EMPLOYEE CONCERNS PROGRAM F.

VERTICAL SLICE TEAM INSPECTION

.G.

MAINTENANCE-H.

OPERATOR TRAINING i

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INSPECTIONS PLANNED A.

SITE MANAGEMENT AND ORGANIZATION Issue The NRC's 50.54(f) letter of September 17, 1985, requested specific information regarding actions taken or planned by TVA to improve management oversight, direction, and support of BFN activities.

In response to the 50.54(f) letter, TVA submitted the Browns Ferry Nuclear Performance Plan (NPP, Volume 3).

In Sections !! and IV of this plan, TVA described corrective actions to strengthen management and organization such as: 1) restructuring the BFN site organization to be compatible with changes to the corporate structure; 2) preparing position descriptions which delineate areas of responsibility and-authority for site management, L

including reporting channels and interfaces; 3) defining training E

activities, such as. shift technical advisor (STA) training or senior reactor operator (SRO) license training for managers; and 4) establishing specific site improvements, such as a site licensing group.

Inspections Conducted and Status The following inspections have been conducted:

Organizational changes: 85-36 Management qualifications:

87-33

" War Room" activities: 87-46 PORC: 85-28, 87-02, 88-05, 88-21 Management. training:

89-12 Important management changes continue to be made which could have a significant impact on the plant as it. transitions from a 5 year outage to an operating plant. Due to the outage and the staff reorganizations that were required, the NRC must review the current staff organization and its preparedness for restart.

Inspections Planned 1.

Assess Site Management and Organization Effectiveness RI-staff Prerequisites:

None Scheduled:

Ongoing (Weekly assessment, reported in monthly resident report beginning January 1989 and continuing through restart) a.

Ability to plan, schedule and successfully carry out major activities required for restart without significant delay, and with a minimum of problems b.

Performance based review of ability to provide integrated team effort

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On site review committees effectiveness (MC 40700) d.

Plant activity meeting effectiveness e..

Coordination and-timeliness of problem resolution f.

LER review with emphasis on root cause analysis g.

Effectiveness of information flow up the. management chain h.

Feedback of causal events to lower staff levels 1.

Effectiveness of feedback of operating experience J.

Effectiveness of standing orders and night orders k.

Site functional interface with corporate activities 1.

Operational and management staffing / qualifications from.

MC 36301/ ANSI 18.1 m.

Operational processes - tagouts, logs, TS interpretations, caution orders, and TACFs n.

Turnover impacts o.

ACRS concerns 2.

Management Evaluation During Operational Readiness Inspaction (Included in 1.1.)

NRR, DRIS MC 40500; 36800 (include tech. staff and mgr. training)

Scheduled: August 1990 B.

QUALITY ASSURANCE (QA)

-Issue The NRC's 50.54(f) letter referred to a number of instances of poor performance in the QA area including three successive SALP periods with -

ratings of "3" in QA at both Sequoyah and BFN.

In response to the 50.54(f) letter, TVA revised its QA topical report with a number of changes, including:

1) restructurin.g the nuclear.QA organization to include a representative at each site' reporting to the new Director of Nuclear Quality Assurance; 2) consolidating all nuclear QA and quality ' control- (QC) functions under the Director of Nuclear Quality Assurance; and 3)-increasing emphasis on corrective action and root cause analysis. programs.

NPP, Volume III, Sect. II.2.6 and Attachment IV-2 documents TVA's commitments to strengthen QA at BFN.

' On March 30, 1989 TVA submitted. a new Nuclear Quality Assurance Plan.

The major changes in this plan were:

the Integration of quality Programs, the expansion of coverage to include quality related activity-

.as well as. safety-related activities, incorporation of a graded approach to QA verification, and update of commitments to ANSI standards and Regulatory Guides.

This plan replaced the topical report and has been approved by the NRC.

Inspections Conducted and Status g

The NRC must develop confidence that the changes are properly implemented and have a positive impact on the site performance indicators. The NRC.

must concur with the licensee's selection of these performance indicators 4

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On site review committees effectiveness (MC 40700) d Plant activity meeting effectiveness o

Coordination and timeliness of problem resolution T.

LER review with emphasis on root cause analysis g.

Effectiveness of information flow up the management chain

-h.

Feedback of causal events to lower staff levels 1.

Effectiveness of feedback of operating experience J.

Effectiveness of standing orders and night orders k.

Site functional interface with corporate activities l.

Operational and management staffing / qualifications from MC 36301/ ANSI 18.1 L

m.

Operational processes - tagouts, logs, TS interpretations.

-caution orders, and TACFs n.

Turnover impacts o.

ACRS concerns 2.

Management Evaluation During Operational Readiness Inspection (IncludedinI.1.)

NRR, DRIS i

MC 40500; 36800 (include tech, staff and mgr. training)

Scheduled: August 1990 l

B.

QUALITY ASSURANCE (QA)

Issue g

p The NRC's 50.54(f) letter referred to' a number of instances of poor performance in the QA area including three successive SALP periods. with ratings of "3' in QA at both Sequoyah and BFN.

I In response to the 50.54(f) letter, TVA revised its QA topical report with-l-

a number of. changes, including:

1) restructuring ' the. nuclear QA 1

.-organization to include a representative at each site reporting to the new Director. of Nuclear Quality Assynce; 2) consolidating all nuclear QA and quality control (QC) functions 'under the Director of - Nuclear Quality-Assurance; and 3) increasing emphasis on corrective action and root cause analysis programs.

NPP,. Volume III, Sect. II.2.6 and Attachment IV-2 documents TVA's commitments to strengthen QA at BFN.

On March -30, 1989 TVA submitted a new Nuclear Quality' Assurance Plan.

The major changes in this plan were:

the integration of quality Programs, the. expansion of coverage to include quality related activity g.J as well: as safety-related activities, incorporation of a graded approach to QA verification, and update of commitments to ANSI standards and i

Regulatory Guides. This plan replaced the topical report and has been l

approved by the NRC.

Inspections Conducted and Status The NRC must develop confidence that the changes are properly implemented l

and have a positive impact on the site performance indicators.

The NRC must concur with the licensee's selection of these performance indicators

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and established goals for restart.

Since the new component level Q-List development is a phased approach, the NRC must concur with the scope of the short term activities and then agree to the licensee's schedule for the long term Q-List. As a final activity, the NRC must determine that the. site QA program and implementation of the program appropriately include all those planned and systematic actions necessary to provide adequate confidence that a structure, system, or component that is important to safety will perform satisfactorily in service per 10 CFR 50, Appendix S.

The following inspections have been conducted:

QA program: 86-08, 87-02, 87-20 QA organization / administration:

85-38, 85-48, 86-12, 87-24 Audits: 85-38, 88-18 Corrective action program: 86-36, 86-43, 87-24, 87-37, 87-41, 88-21 Q-List: 87-37, 88-05, 88-10, 88-16 Offsite support staff:

85-47 Engineering Assurance:

87-37 QA surveillance reports: 88-04 QC inspection activities: 86-15 Document control / records: 85-56, 86-08, 87-37 QA training for craftsmen:

88-05 Engineering training:

89-12 Inspections Conducted 1989 1.

Quality Verification Team Inspection - MC 35702 - IR 89-12 Jenison, Team Leader Completed: May 8, 1989 Inspections Planned 1.

Programmatic Team Inspection - MC 35701, 36100 Jenison, Team Leader Prerequisites:

TVA Letter of January 10, 1990 meets prerequisites Scheduled: May 29 - June 1 and June 11-15, 1990 a.

Topical Implementation (MC 35502,35001) b.

Q-list /CSSC effectiveness c.

CAQR resolution process including generic reviews, timeliness,-

root'cause analysis, and effectiveness d.

QA oversight of engineering e.

QA training adequacy f.

Other (MC 35750,39701,39702,40702,40703,40704) 2.

Assess Offsite Review Committee - MC 40701 Carpenter /RI staff Prerequisites:

None Scheduled: Ongoing (To be completed in May 1990)

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SEISMIC ISSUES Issue Deficiencies were identified for the torus, piping and piping-supports, cable tray supports, conduit supports,. HVAC ductwork, drywell steel platforms, miscellaneous steel, lower class over Class I-features, secondary containment penetrations, and miscellaneous civil issues.

The NRC's 50.54(f) letter requested information regarding the programs being used sto evaluate the seismic adequacy of some of these. issues,

~1n response to the 50.54(f) letter, TVA submitted program descriptions in the August 1986 - NPP, which was subsequently revised in June 1987, and a separate April 1987 submittal.

A program summary and review meeting was held with the NRC in September 1987.

A continuing dialogue between TVA and NRC staff on seismic issues was established.

TVA will perform comprehensive review of these issues and demonstrate acceptability for operation prior to restart.

Inspections Conducted and Status TVA identified a range of seismic issues in Volume 3 of the NPP. Selected resolution of these issues has been submitted to the NRC for review and approval. Additional resolution of outstanding items. is still required.

The staff has issued an SER for cable tray supports. Several programs are still_ in the discovery stage. Corrective action may need to be augmented after further staff review and observation of TVA performance.

Partial inspections and reviews have been conducted on several programs.

The following inspections have been conducted:

Orywell platform steel: 86-14, 86-30 Seismic anchorage concerns:

87-27 Cable trays: 85-41, 85-51, 86-02, 86-36, 87-07, 87-19 Pipe supports and restraints:

85-26, 85-30, 85-51, 86-02, 86-19, 87-19 IEBs 79-02 and 79-14:

85-21, 85-26, 85-30, 85-41, 86-19, 86-30, 87-07, 87-19, 87-26, 88-12, 88-19, 89-57 Conduit and supports: 85-51, 87-07, 87-19 CRD piping: 86-06, 87-07, 87-08, 87-19 HVAC concerns:. 86-06, 87-07, 87-14, 87-19 Torus modifications: 85-26, 86-35, 87-07, 88-18 Torus attached piping: 87-07 Small bore piping:

86-02, 87-07 Secondary containment penetrations: 85-57 Seismic design programs: 88-38, 88-39, 89-31, 89-39 l

1

_7 The fc11owing areas are considered to be resolved for restart without further inspection:

a.

Cable Trays b.

Torus Modifications Inspections Conducted in 1989 1.

Follow-up Inspection For Closure of IEB 79-02 and 79-14 Based On SER Output.

IR 89-15.

John Fair, Team Leader Prerequisites:

90% of design complete supporting 79-02 and 79-14.

Conducted: January 23 - February 3, 1989 2.

Seismic Design Program - irs 89-21, 89-29, 89-31, 89-39 Thomas Cheng, Team Leader Prerequisites: None Conducted: January 23, 24; February 20-24; April 26-28; August 16-18, 1989 3.

Civil Calculation Program Thomas Cheng, Team Leader Prerequisites: None Conducted: March 13-24, 1989, IR 89-30 June 6 - August 18, 1989, IR 89-32 4.

Small Bore Piping and Tubing HQ - John Fair Conducted August 29 - September 1, 1989, IR 89-36 5.

Pre-Restart 79-02 and 79-14 (Large Bore)

John Fair, Team Leader (3)

Prerequisites: 90% of design complete Scheduled: October 16-27, 1989 6.

Followup Civil Calculation / Seismic Design Program Thomas Cheng, Team Leader (2)

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Prerequisites: All required restart evaluation to be completed Scheduled: November 27 - December 1,1989 (at Browns Ferry) 7.

Field Inspection of Seismic Modifications (79-02/14 pipe supports)

RII, MPS

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Completed:

Inspection of. pipe supports (~10% installed, IR 89-57,' and - 35% installed, IR 90-09)

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Inspections Planned 1.

Field Inspection of Seismic Modifications (MC 50090)

RII, MPS (1 or 2)

Prerequisite:

79-02/14 mods in progress Schedule:

Closeout inspection Junr 11-15, 1990 2.

Seismic Program Followup

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John Fair Team Leader Schedule: April 23-27 1990 D.

FIRE PROTECTION Issue Final NRC concurrence on the Appendix R compliance program is-required for the restart of Unit 2.

A BFN plan to implement the requirements of 4

Appendix R was developed by TVA and submitted ' for NRC approval on -.

January 31, 1986. Additional information, supplementing the January 1986 program submittal, was sent to the NRC on November 21, 1986.

Five exemptions from Appendix R requirements have been requested by TVA and approved by the staff. ' Modifications to comply with Appendix R will be =

completed prior to Unit 2 restart. Additionally, BFN has undergone major fire protection upgrades' that should be evaluated.

Inspections Conducted and Status The NRC staff. is ' presently reviewing the BFN Appendix R compliance program. The staff has found that the program will meet NRC requirements.

. An-SER on post-fire safe shutdown was issued on April 14, 1989.

The'following inspections have been conducted:

Fire protection program: 86-09, 87-21 Appendix R modifications:

87-37 Inspections Conducted in 1989 1.-

. Appendix R Team Inspection post-fire safe shutdown systems and procedures)

OSP PSB/NRR Team Conducted:

May 1 - 5, 1989 l

IR 89-13 s

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Appendix R Team Inspection-(fire protection systems and procedures)

ADSP Team Conducted July 17 - 21, 1989

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IR-89-28 3.

Fire Protection Program - MC 64704 R II i

Prerequisites:

Fire protection mods complete (schedule completion by February 28, 1990) r Scheduled: Conducted February 26 - March 2, 1990 (IR 90-06)

Inspections Planned 1.

Appendix R Closeout R. Wescott, ADSP & J. Harris, Region II Prerequisites:

IR 89-13, 89-28 Ols and IFIs ready for closure.

Schedule: April 16-20, 1990 E.

ENVIRONMENTAL QUALIFICATION (EQ)

Issue Insufficient documentation. existed to demonstrate that electrical equipment at the plant was environmentally qualified as required by

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10 CFR 50.49.

TVA has developed an upgraded EQ program to identify equipment, specify environments, verify equipment in the field, document qualification.

specify maintenance requirements, maintain EQ binders, and replace 4

cnqualified equipment if necessary. The necessory documentation is being L

completed and field verified.

Any required modifications will.be L

completed before restart.

Recent TVA program assessments indicate that the EQ Program is a major factor in the Unit 2 restart schedule.

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Inspections Conducted and Status

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An in-depth NRC team 11nspection was conducted in May 1988.

Equipment 1

i specific deficiencies were found in eight EQ binders.

The program in l

general was judged acceptable; however, the Qualification Maintenance l

Program was still in-its infancy and could not be properly evaluated.

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The following inspections have been conducted:

EQ: 87-26, 87-33, 87-37' L

EQ team inspection:

88-11 l

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i Inspections Planned 1.

EQ Follow-up Team Inspection - tis 2515/75, 2515/76 NRR, Team Leader (5 including 1 from RII)

Prerequisites:

TVA E0 readiness letter 2 weeks prior to inspeciton (90% of packages, 75% of mods & MRs complete)

Scheduled: June 25-29, 1990 1

F.

TECHNICAL SPECIFICATIONS Issue TVA and the NRC have identified and agreed upon a list of 30 TS changes requiring approval by the NRC before BFN can enter the startup mode.

I-These changes involve clarifications, corrections, modifications, and organization and regulatory changes.

1 I

Inspections Conducted and Status l

Due to a loss of-configuration control the licensee has submitted a number of TS changes to support the plant modifications, TVA has submitted a number of the required TS changes for staff review.

i The other. changes are scheduled to be submitted to allow time for NRC review and TVA implementation prior to restart.

The staff expects to issue' the' last restart TS amendment 90- days - following submittal by the licensee. Additional TS change requests are expected from TVA prior to restart; however, their approval and implementation have' not been established as a restart item.

TVA has completed a TS assessment-program to verify compliance with plant hardware, design basis and NRC safety evaluation. NRC inspections are planned to verify that the TS reflect plant configuration along with training for the changes.

i-1.

Inspection For TS Adequacy - MC 71301 Patterson(ADSP)-

Prerequisites:- TVA verification of TS complete, DBVP discovery andidesign complete, and all TS changes identified.

Conducted: September 25-29, 1989, IR 89-47 issued (October-21, 1989) 1 Inspections Planned 1.

TS Implementation and Adequacy Patterson(ADSP)

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11 Prerequi_ sites: TS activities implemented for restart, training conducted on TS changes, procedures issued, outstanding items ready for closure Scheduled - TBD (July / August 1990)

'G.

PROCUREMENT / PIECE PARTS (CANCELLED)

Issues From TVA NSRS reports issued between 1983 and 1985 and during - an inspection in November 1986, the NRC determined that TVA had procured replacement parts for safety-related equipment without appropriate procurement controls to ensure that replacement items were-tested or qualif.ied for their: safety-related applications.

Inspections Conducted and-Status TVA has undertaken an extensive program to review and evaluate past and present procurement of replacement items.

TVA is establishing the qualification' of, items or replacing items on equipment required for restart on a priority basis.

The NRC is reviewing TVA's programmatic approach. The staff SE is yet to be issued. ' BFN'.s approach is very similar to the approved Sequoyah approach.

The NRC is currently reexamining its position with regard to procurement.

These inspections will be postponed.

The following inspections have been conducted:

87-08, 87-09 l

Inspections Planned (Postponed until after restart, except for d. below) l ;-

1.

Team Inspection NRR(5) l Prerequisites:

I

.1.

Review of installed 50.49 equipment essentially complete-and all required replacements identified.

Majority of replacements completed.

2.

More than 20 dedication packages performed under new program available for review.

3.

More than 20 items receipt inspected under inspection criteria established under new program.

4.

Sample of close-out packages for equipment with critical characteristics vei'i fied by post-installation testing available for review.

i

i 12 5.

50.49 equipment warehouse inventory essentially complets.

Scheduled:

Postponed a.

Procurement program (MC 38701,38702) b.

Replacement parts, including sampling in-plant parts and conditions in the warehouse.

c.

Commercial grade item dedication programs and processes (MC 38703) d.

Close IEB 88 Resident Inspectors will do in April 1990 inspection H.

RESTART TEST PROGRAM (RTP)

Issue Due. to the prolonged ' plant shutdown and extensive modifications, a comprehensive RTP is required to ensure plant systems are capable of meeting their safe shutdown requirements.

Inspections Conducted and_ Status A RTP has been developed which includes individual and integrated system testing, a backup control test, and criticality and power ascention -

testing. The DBVP developed the system test requirements necessary to satisfy. the safe shutdown analysis. The program involves developing test procedures and, where possible, utilizes existing operation.and surveillance' instructions.

A summary description of the program was

. submitted on July 13, 1987. To date, TVA has not completed all of the detailed test procedures.

The staff is in general agreement with the intent of TVA's program and has issued an SER.

The fol_ lowing inspections have been conducted:

RTP: 12, 87-27, 87-30, 87-33, 87-42, 87-46, 88-02, 88-04, 88-05, 88-10,-88-16, 88-21, 88-24, 88-28, 88-32, 88-33, 88-35, 89-03', 89-08, 89-11, 89-19, 89-20, monthly Resident Inspection Reports.

Restart Review Board: 87-14, 87-30, 87-37 Special tests: 86-28, 87-33, 87-42 Inspections Conducted 1.

Phase I Restart Test Review Christnot Prerequisites: None

(

Completed: December 1988 Review five fuel load systems (test results and test exception resolution) (MC 70329) i o-

rm.

y, a,

to 33-I i

i Inspections Planned l

1.

Phase II Restart Test Review (post fuel load)

Christnot, RI, Prerequisites:

Final review and approval of 75% of restart tests, excluding power ascension tests Scheduled:

In progress a.

Three non fuel load systems (procedures, observations, results, exceptions) y b.

Overall summary based on Phase I, Phase _II, test exceptions,-and SP0C review.

j 1

2,

. Initial Criticality and Power Ascension Testing Program Per MC 2514 j

Patterson, lead (ADSP/RII) l i

Prerequisites:

TVA to develop detailed plan,- including hold i

points.

Procedures approved and issued 30 days prior to restart t

Scheduled: August 1, 1990 3.

Review'and observation of' primary plant hydro, LLRT and ILRT -

1 MC 61720, 70307, 70313, 70323 j

Hydro and LLRT to be inspected by RI and Region 11 staff.

ILRT to be inspected by RII.

L Prerequisites: None f

l

-Scheduled:

ILRT, August 7, 1990.

Hydro, August 10, 1990.

.l LLRT, TBD

,n l

d I.

OPERATIONAL READINESS FOR RESTART l

I

. Issue L

)

A comprehensive effort to assess BFN material condition and personne1' readiness to support safe plant restart and operation is required due to' the current extended -outage, changes in the site and support j

organizations, realignment of. responsibilities, and implementation of new' j

programs to correct past problems.

TVA has established programmatic l

guidance for_ operational readiness verification.

TVA is ' currently l

documenting commitments and test statements of intention from the BFN NPP i

to be-used to verify adequate NPP implementation. -TVA is also defining

- performance objectives, criteria, and evaluation plans to ensure that site organizations -function effectively and are prepared for-plant restart and operation. On-June 16, 1989 TVA issued the report on the first of a

-two phase operational ~ readiness review conducted in May 1989.

A second Report was issued March 9,1990, ba upon additional reviews.

Another independent review will be performed after fuel load to complete the Volume 3 commitment.

J

o' 14 Inspections Conducted and Status The NRC will independently assess TVA's readiness for restart. The NRC is currently reviewing TVA' plans for the operational readiness program as described in the BFN NPP.

Inspections planned 1.

Operational Readiness Assessment Team Inspection NRR, Team Leader (8), DRIS Prerequisites: TVA final report on operational readiness issued, all modificiations complete and scaffolding removed, all surveillace tests required for startup, and pre-startup quiet time established.

Scheduled: August 6-27, 1990 a.

Corporate oversight b.

Implementation of lessons learned from SQN restart c.

Corporate SER open items d.

Assess senior management in place at the time of restart (MC 36800)-

e.

Assess maintenance backlog and MTI OIs f.

Follow-up on - the resolution of Site Hanagement Effectiveness

. concerns. and areas of limited coverage (using Murley criteria) 9 Procedure adequacy h.

Control room professionalism-1.

Review TVA's operational readiness self assessment j.

Offsite support staff (MC 40703) k.

Follow-up on outstand'Ing QA issues and evaluate QA effectiveness.

1.

Tech. staff and management training m.

System Alignment n.

Observation of Crew performance on BF simulator J.

ELECTRICAL DESIGN ISSUES Issue Employee concerns, INPO findings, and various other audits and reviews detected significant deficiencies which have been categorized as

" Electrical Issues."

Corrective action consists of those activities necessary to establish, through analysis or modifications, that the plant configuration is consistent with requirements of electrical design standards and specifications.

Issues involved are AC/DC calculation deficiencies, cable pulling issues, flexible conduit, cable ampacity, cable separation, thermal overloads, cable splices, fuses, cable and bus protection, DG component rating, standby DG loading, and instrument accuracy.

1 7

15 Inspections Conducted and Status Programs have been established for each of the specific issues including walkdowns of the installed configuration, qualification tests of

- representative configurations, calculations, replacement, and rework.

Review of the remaining issues will be documented in the Volume 3 SER.

The following inspections have been conducted:

86-24.

Discussions between TVA and the NRC staff are continuing-with regard to identification and resolution of each of these-issues.

Inspections completed 1.

Instrumentation Adequacy Assessment Johnson, Team Leader Prerequisites:

Fuel reload and 10 safety related system SP0Cs completed.

IR 89-06, Inspection conducted January 30 - March 10, 1989, a.

Instrument accuracy b.-

Setpoint scaling c.

Material condition d.

. Frequency of out-of-tolerance conditions

-e.

Sense line slope (installation) f.

Operational parameter verification

'2.

Electrical Design Issue Closeout Audit / Inspection Marinos, Team Leader (3)

Prerequisites: - Final-ampacity calculations complete Completed:

December 4-8, 1989;.IR 89-59 a.

Cable ampacity b.

' Diesel generator loading c.

Cable separation d.

Flex conduit e.

Thermal overloads (SSFI identified problems) f.

Cable splices 9

Fuses h.

Cable and bus program (pending Watts Bar problem resolution) 1.

OC component rating j.

Breaker trip settings (subcategory Rpt. 26500, paragraph 4.2.7) 45 k

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l 16 Inspections Planned 1.

Electrical' Followup, Cab 1<e Insulation

- Marinos

- Scheduled:

April 23-27, 1990 K.

ROUTINE UNSITE INSPECTIONS Issue Inspections were commenced in September 1988 to resume the routine 2515 inspection program at BFN. This is consistent with the reestablishment-of the SALP process which began with the licensee's fuel load date of January-1, 1989. and closes on March 31, 1990. 'In order to lessen the TS requirements and, therefore, allow modifications to procede faster, Unit 2 was defueled in January 1990.

Inspections of the routine operations modules will be minimal until Unit 2 refueling occurs (scheduled for July 1990).

Inspections Planned Carpenter /RI staff 1.~

MC 71707.: Operational Safety Verification 2.

MC 71710:'ESF Walkdown 3.

MC 61726. Monthly Surveillance Observation

[

4.

MC 62703: Monthly Maintenance Observation 5.

MC 71500: Balance of Plant 6.

MCs 92.s0, 92701, 92702: LERs, Followup, and Violations /0eviations 7..

MC 93702: Onsite Followup of Events at Operating Power Reactors L.

REGION II SUPPORT INSPECTIONS l'

The following routine inspections have been. conducted:

HP program:

85-27, 85-42, 85-55, 86-10, 86-16, 86-18, 86-26, 86-29, 86-41, 87-28, 87-34, 88-10, 88-14, 88-23, 89-22, 89-52, 90-02 EP program:

85-23, 86-01, 86-36, 87-18, 87-31, 88-26, 89-14 EP.exerci se/ organization: 85-52, 85-53, 86-32, 86-33, 87-39, 88-30, 88-34, 89-25 Security:

85-37, 85-46, 85-54, 86-13, 86-21, 86-31, 86-37, 86-44, 87-23, 87-35, 87-44, 88-01, 88-03, 88-20, 88-29, 89-09, 89-23 Security / regulatory effectiveness review team:

87-05, 87-23, 88-03 Security /NPP improvements:

87-17

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.-, _ y

'"'_,y-p 17 SNM: 89-01, 89-55 IEB 80-11, Snobber Surveillance:

89-02 i

ISI: 89-05, 89-34 Inspections Planned 1.

Routine 2515 Modules Recommend appropriate RII DRS or DRSS sec+1on.

Prerequisites:

None

-Scheduled: Ongoing / Unannounced a.

Health physics b.

Emergency preparedness i

c.

Security d.

Chemistry 2.

Integrated Leak Rate Test Region II Staff l

Prerequisites: hotification of plant readiness two weeks prior to test.

Scheduled:

August 7, 1990 3.

Hydrostatic Test of. Primary System Region II Staff Prerequisites: Notification of plant readiness two weeks prior to test Scheduled:

Augt.st 10, 1990 M.

ALLEGATION /0 PEN ITEM REVIEW FOR RESTART ADSP Staff L

i -

Prerequisites:

None-Scheduled:

Ongoing (Refer to Browns Ferry 2 " Status of Restart l

Readiness" memorandum, to be issued)

N.

PROCEDURE UPGRADES Issue Audits and inspections identified a number of deficiencies and weaknesses in procedures. A procedure upgrade program was implemented to address l

these problems. The near-term portion of the program focused on resolving l

deficiencies in the procedures which affect the safe restart, operation, I

and shutdown of the plant. Procedures that are not required for restart, 1

s L

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.. =,

18 operation, and shutdown will be upgraded as part of the long-term program.

The program requires a review of procedures for technical content, administrative controls, regulatory requirements, and performability.

The NRC must develop confidence that the new procedures are appropriate to the circumstances, contain appropriate quantitative or qualitative acceptance criteria for determining that the activity was satisfactorily accomplished, and that activities can be. accomplished in accordance with the instructions. The NRC must also concur with the scope of procedures selected for restart and agree to a schedule for the long-term program.

The NRC will additionally assess the potential adverse impact on plant operations created - by the large number of changes over the relatively short time period.

Inspections Conducted and Status

-The NRC has concurred with the scope of procedures included in the upgrade program.

The MTI rated the maintenance procedures as good.

A team inspection of the Emergency Operating Instructions (E01s) was conducted in August 1988.

The Vertical Slice Team Inspection reviewed maintenance, surveillance, operating and alarm procedures; and reviewed the programs controlling writing and reviewing procedures.

Surveillance and-operating procedures were reviewed for technical adequacy. Minor problems were identified and comments were given to TVA.

The following inspections-have been conducted:

Ol's: 87-09, 87-27, 89-16 SI's: 86-14, 87-14, 87-30, 88-02, 88-24, 89-16

^

E01's: 87-46,88-200, OL-90-01 A01's: 87-27, 89-16 Inspections planned 1..

Procedure Adequacy (Except E01s)

Programmatic closeout by letter dated January 3,1989.

Final team inspection is required, as stated in NRR letter to TVA, January 3, 1989. Since the MTI and VSI evaluated procedures the scope of this inspection will be modified to close open procedure concerns and to determine that station procedure are ready for startup.

NRR Prerequisites: TVA certification that procedures are ready for startup.

Schedule: August 6 17, 1990 (component of the Operational Readiness Team)

\\.

"* 5, 19 a.

System engineer concept b.

SI validations c.

SI verification d.

Procedural compliance e.

Station Procedures 0.

ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) psue 10 CFR 50.62 ( ATWS Rule) was issued in July 1984 and includes modifica-tions in three areas: 1) recirculation pump trip (RPT), 2) standby liquid control (SLC), and 3) alternate rod insertion (ARI). In October 1985, TVA submitted to the NRC its proposed solution and schedule for BFN. The TVA NPP Volume 3, in August 1986, committed BFN to implement the ATWS rule before Unit 2 restart.

Inspections Conducted and Status TVA - submitted the detailed plant specific design criteria on July 15, 1988, following submittals on conceptual design and several working level meetings between the TVA and NRC staffs.

The staff's review was documented in letters to TVA dated January 22 and April 19, 1989.

Modifications of Unit 2 are in progress.

The ATWS rule implementation was inspected during the Design Verification Team Inspection (IR 89-17 issued August 10. -1989).

Inspections planned ATWS Closecut Inspection NRR, H. L1 Prerequisites:

Completion of restart ATWS modifications and the preoperational test of the modifications; IR 89-17 concerns and open items ready for closure Schedule: TBD P.

REFUELING Issue Unit 2 was defueled in January 1990 to reduce TS requirements to allow

~

modification work to proceed faster. Reload will occur after all restart modifications are complete and after systems required by TS for refuel are-operational.

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20 Inspections Planned Refueling Readiness and Refueling Operations Resident Staff Prerequisites:

Restart mods complete, refuel systems SP00s complete and refuel procedures ready Scheduled:

Prior to and during refuel (July 12,1990) e.

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{s El II. INSPECTIONS COMPLETED A.

DESIGN BASELINE VERIFICATION PROO!!AM '00VT) AMO 0 l; ION CALCULATIONS REVIEWS Issue Questions were raised during a review conducted for TVA by Gilbert Commonwealth in 1985 regarding the adequacy of the existing TVA design control process.

Examples included missing calculations, incomplete design documentation, and failure to update as-built drawings to reflect plant configuration.

TVA developed the DBVP to reestablish the design baseline for BFN.

This program includes:

1) establishing the plant cohfiguration; 2) reconstructing the design basis; 3) reviewing and evaluating modifications; 4) defining and performing required tests to verify functionality of DBVP systems; and 5) performing modifications developed from this program.

TVA instituted a rev'iew of essential design calculations to verify that the calculations existed and were adequate to support the design of BFN.

As a result of the calculation reviews, TVA estimated that a large number of calculations would not be retrievable.

TVA initiated a review of the engineering calculations in the electrical, nuclear, mechanical, and civil areas.

Inspections Conducted and Status The staff conducted a major team inspection in October 1987 during which both programmatic and specific deficiencies were identified. The licensee responded to these concerns in April 1988. These responses were reviewed by an NRC team inspection.

The DBVP is considered to contain the essential elements needed to achieve its intended goals and objectives.

The design calculation inspections have been integrsted with those of the DBVP.

The staff evaluation of the DBVP is complete.

Sampling of program implementation was performed during a Vertical Slice Inspection (IR 89-16) performed in November and December of 1989.

The following inspections have been conducted:

DBVP/CCM: 86-25, 86-32, 87-02, 87-09, 87-14, 87-20, 87-37 DBVP team inspections: 87-36, 88-07, 89-07 Design control: 87-08, 88-04 Drawing control system training: 86-22 r

i

(

e J

..e o

)

22

)

' Inspections Conducted in 1989 1.

Followup DBVP Team Inspection 1

l Georgiev, Team Leader l

Prerequisites:

TVA readiness certification letter that calculations are 80'4-90% complete for each class and type.

Calculation cross reference system 20%-30*4 complete.

Conducted: March 10, 1989 (IR 89-07 issued June 30,1989) a.

DBVP final inspection b.

AC/DC calculation deficiencies c.

DC component rating i

d.

Unverified assumptions for procedure / operator actions e.

Mechanical calculations f.

Nuclear calculations g.

Civil / structural calculations h.

Sample of Control Drawings 1.

Sample ECNs 2.

Design Control Inspection Branch, Tmia Leader Prerequisise.s:

Fuel load complete, (ECN closeout), drawing control improvements in place, fuel load systems drawings L

complete, committed design control process fully implemented, and EA audit complete.

Conducted:

May 22 - 26, 1989 (IR 89-17 issued August 10,1989) a.

Assess design control process (HC 37700,37701,37702) b.

ECN backlog c.

FSAR condition d.

ATWS modifications (TI 2500/20) l e.

Control room drawings l

l-B.

FUEL LOAD (JAN. 1989)

Issue The licensee loaded fuel in January 1989: The major objective was to exercise operations personnel in establishing and maintaining system operability in order to begin the process of establishing the requisite operational attentiveness following an extended shutdown.

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23 t

Inspections Conducted and Status Completed.

IR 88-36. 89-03, 89-04 89-18.

l 2

Inspections Completed l

1.

SPOC Review Carpenter /RI Staff Prerequisites: None 2.

Allegation /Open Item Review OSP staff Prerequisites:

None i

3.

Operational Capability Assessment for Fuel Load - MC 60705

[

r Carpenter /RI Staff Prerequisites: None 4.

Fuel Load Inspections - MC 60710, 71715 RI staff /OSP Staff Prerequisites:

Fuel load C.-

WELDING Issue Concerns were raised at the Watts Bar site regarding TVA's inspection practice and welding rod control program.

These concerns implicated the l

quality of weldments and the ability of the welds to perform their function at BFN. TVA conducted a welding reassessment program at BFN in two basic phases.

Phase.I was a review of the TVA weldin documents (i.e., design documents, policies, and procedures)g program to ensure that the welding program correctly reflects TVA's licensing commitments and regulatory requirements.

Phase II was the actual reinspection of selected welds and weld records.

The results of the inspection effort were used to evaluate the implementation of the written welding program.

The reinspection results of the sample welds also were used to determine whether TVA's welding-activities in the field meet the applicable code requirements and whether the welds are adequate for service. During both of these phases, TVA identified and categorized deficiencies in the existing welding program, corrected the problems, and implemented changes to prevent recurrence.

!O 1

i i

1 k

1 1

??!Y

+1 24 i

Inspections Conducted and Status P

The welding programs at TVA are administered by a commer, project group.

The NRC has reviewed the Sequoyah program and found it acceptable. Both Phase I and Phase II of the welding program have been submitted for BFN and were reviewed by the NRC staff.

An inspection of Phase I was performed in April 1987(87-17) and determined that the necessary elements existed to translate welding commitments into specifications and drawings.

An inspection was performed of Phase II in May and June 1988 (88-13) and determined that welding was adequately implemented and the corrective actions that resulted from the welding program evaluation appear adequate and, if properly implemented, should provide reasonable assurance that the quality of the welds at BFN would be adequately determined.

The following inspections have been conducted:

Welding team inspections:

87-19, 88-13 Welding program reviews: 86-27, 86-03, 87-14 U2 recire. safe-ends & pipe replace.: 86-39, 87-01, 87-04, 87-11 U2 reactor vessel shroud access covers:

88-06, 88-15 NDE B6-03, 87-15, 87-16 Reactor vessel nozzle welding: 86-23 U2 torus modifications:

86-34 U2 RCS pipe welding:

85-33 HPCI welding problems:

85-57 Inspections Planned Some aspects of welding were addressed in the Vertical Slice Team Inspection. No additional inspections are considered necessary.

j D.

INTERGRANNULAR STRESS CORROSION CRACKING (IGSCC)

Issue i

IGSCC is evident to some degree in all three units. The IGSCC mitigation options are primarily replacement weld overlay, induction heating stress improvements (IHSI), and/or hydrogen water chemistry. IE bulletins 82-03 and 83-02 and generic letters 84-11 and 88-01 were issued by the NRC to address this problem.

Inspections Conducted and Status TVA submitted a response to GL 88-01 on August 1,1988. TVA performed.

inspections of 100 percent of all accessible / susceptible welds in the recirculation, core spray, reactor water cleanup, and residual heat removal (RHR) systems for requirements of IEB 83-02 in 1983. Unit 2 was inspected to the requirements of GL 84-11 in 1985 (TI 2515/89).

IGSCC mitigation and repair measures on the recirculation and RHR piping implemented on Unit 2 include weld overlay, weld replacement, and welds

'l

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e o 25

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j with shallow cracks mitigated by _ IHSI.

IHSI was implemented on all susceptible welds that could be successfully treated. TVA has replaced all 10 recirculation inlet safe ends and 2 jet pumn inn n m atetion safe ends on Unit 2.

Replaced safe ends have received IHSI. In the course of i

material replacement, approximately 90 percent of the susceptible piping welds have been eliminated. Mitigation steps will be taken for Units 1 and 3 prior to restart from their current respective outages.

TVA recognized the importance of hydrogen water che'nistry to mitigate the IGSCC problem and interface connections area being installed on Unit 2 this outage to allow mid-cycle introduction of hydrogen wster chemistry.

The NRC staff performed an onsite review of BFN's IGSCC mitigation program and was favorably impressed. The staff has concluded that TVA is ade-quately addressing IGSCC at BFN. Weld inspections performed subsequent to the post-replacemnt IHSI of the Unit 2 safe ends are complete.

TVA is preparing a final response to GL 84-11 and GL 88-01.

The staff has

+

provided its analysis by letters dated December 8 and 30,1988. Based on additional cracks found in Unit 2, TVA is updating their response to GL 84-11 and 88-01.

On September 28, 1988 TVA submitted the Browns Ferry Microbiological 1y Induced Corrosion (MIC) Program. MIC has been detected at Browns Ferry with small random leaks occurring in high pressure fire protection and raw service water carbon steel piping, and with MIC indications in EECW piping. The indications in the EECW piping were considered acceptable by l

TVA for restart.

NRC is evaluating TVA's position and program for monitoring this problem.

The following inspections have been conducted:

IEB 83-02:

86-03 Facility modifications: 87-30 1

MIC:

87-32, 87-33, 87-45 GL 88-01:

89-05 E.

EMPLOYEE CONCERNS PROGRAM (ECP)

Issue Under the employee concern programs initiated at Watts Bar in 1985 more than 5800 employee concerns were identified.

Approximately 700 safety-related and non safety-related concerns identified in the original ECP were applicable to BFN by direct reference or generic applicability.

TVA divided the Watts Bar concerns into 9 categories:

construction, engineering, operations, material control, welding, QA industrial safety, management and personnel, and harassment and intimidation (H&I).

Investigations and corrective ections for BFN are being documented and submitted by sub-category reports.

H&I concerns are being addressed separately by the TVA Inspector General.

Both the Watts Bar program and the new ECPs were thoroughly evaluated and judged to be acceptable as part of the Sequoyah Unit 2 restart effort.

s i

1, c. *.

26 Inspection Conducted and Status Inspection activities on the new ECP have bm complated. The most recent inspection of the new ECP concluded that the program was adequately established and implemented on-site and acceptable for restart.

Additional sampling of the Watts Bar generic concerns is needed in order to assure that the corrective actions have achieved the desired impact.

The following inspections have been conducted:

ECP: 86-40, 87-26,.87-30, 88-04 ECP team inspection:

88-22 Each subcategory report for the special Employee Concerns Task Group program will be assessed in an SER.

F.

VERTICAL SLICE TEAM INSPECTION Branch, Team Leader (12)

Prerequisites: Five identified systems fully returned to service for restart (90% of modifications complete).

Completed:

Weeks of November 27 and December 11, 1989 (IR 89-16 issued 3/9/90 Confirmatory inspection to ensure that TVA's improvement programs are being effectively implemented.

1.

Engineering review 2.

Construction quality 3.

Program implementation a.

System turnover b.

Maintenance /Q List / Piece Parts /EQ c.

Training / Procedures d.

Contractor recommendations e.

ECN control / drawings f.

Restart tests G.

MAINTENANCE Issue Programmatic problems in site maintenance were previously identified in SALP and inspection reports. This area received three SALP category "3" ratings. The problems were attributed to such factors as poor supervision l

of work activities, inadequate planning, ineffective root cause analysis, inadequate training, and poor coordination between different organizations to support maintenance activities.

+

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27 c

Inspections Conducted and Status BFN has developed and is implementing a comprehensive maintenance improvement program (MIP) that identifies several essential improvements.

The problem encompasses TVA's own assessment of needed improvements and those identified by INPO evaluations / recommendations and NRC aeficiencies.

Program elements being improved include:

programmatic aspects of maintenance, preventive failure analysis, maintenance procedures upgrade, training, personnel certification qualifications, and facilities for the conduct of maintenance. To ensure success, BFN committed resources and established a staff of senior line managers with authority to develop and implement the MIP.

The Maintenance Team Inspection in January 1990 concluded that the program and its implementation were satisfactory.

however, the ability of parts of the program to support operation could not be evaluated in the plants current shutdown condition.

Increased emphasis is needed by both TVA and the NRC as the maintenance request backlog work-off-rate has increased as restart milestones are approached.

The following inspections have been conducted:

Maintenance program: 86-32 MIP: 87-27, 88-02 VMCP: 67-26, 87-27 M&TE: 85-36, 87-33 Calibration:

85-53, 86-05 Preventive Maintenance: 88-24, 88-28, 88-32, 88-33, 88-35, 89-03, 89-08, 89-11, 89-19, 89-20 Inspections Conducted: 89 & 90 1.

Performance Based Maintenance Team Inspection (TI 2515/97)

Region II Prerequis n es: Programmatic issues resolved and program in place

& implementation demonstrated IR-89-17 concerns ready for closure.

TVA letter confirming I

readiness for the inspection.

l Conducted: December 10, 1989 l

January 8 and 22,1990.

IR 89-06 issued H.

TRAINING Issue From results of NRC requalification examinations, the NRC determined that the TVA operator training program had several programmatic weaknesses.

Inspections Conducted and Status TVA has undertaken a comprehensive one-time training program to upgrade all licensed operators.

Beginning in 1987, TVA increased its annual requalification training for licensed operators from four to at least six

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4 28 weeks.

The TVA BFN simulator was moved to the BFN site to improve operator access to the simulator and to allow for more effective overall training.

The licemed operator training program achieved INPO accreditation in March 1986. TVA's programmatic approach is acceptable to the staff.

Inspection of the reactor operator training program is complete. Pass rates on the NRC administered requalification examinations for TVA operators to complete the upgrade course were greatly improved.

The overall pass rate was 80 percent or better. NRC requalification testing of TVA operators has been completed.

Due to a change in the methodology of evaluating the final group, some restrictions have been imposed on those operators pending an evaluation using the " pilot program" techniques.

The following inspections have been conducted:

86-14, 86-32, 87-26, 88-08, 89-12.

The requalification program was re-evaluted by the NRC examination process in January and February 1990 and is now judged satisfactory. All twenty candidates examined at that time passed.

Inspections Completed in 1989 and 1990 1.

Group IV Operator Reexamination and Assessment of the Requalification Program Via Requalification Examinations Brockman (RII)

Prerequisites:

TVA notification that Group IV operators are ready for the exams.

Conducted July 10-21, 1989 2.

Overall Staff Training l

RII Team (5) 1 Prerequisites:

None I

Completed:

December 18-22, 1989;.IR 89-58 i

MC 41500 j

3.

Operator Requalification Program Verification Casto, Region II Prerequisites:

Adequate sample of individuals ready for requal exams. All attribures of CAL 86-01 ready for closure Conducted: January 22-26 and February 5-9,.1990 1

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