ML20207T237

Forwards Summary of 870205-06 Mgt Meetings Re Restart Issues & Program Milestones/Schedules.Attendees List & Handout Matl Encl

ML20207T237
Person / Time
Site:	Sequoyah
Issue date:	03/04/1987
From:	Zech G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	White S TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8703230339
Download: ML20207T237 (160)

Text

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• h m . , m, Docket Nos. 50-327, 50-328 License Nos. DPR-77, DPR-79 TLnnessee Valley Authority

-(4 TIN: Mr. S. A. White Manager of Nuclear Power 6N 38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Gentlemen:

SUBJECT:

MEETING

SUMMARY

- SEQUOYAH, DOCKET NOS. 50-327 AND 50-328 This refers to the Management Meetings conducted at our request at the Sequoyah Site on February 5 and 6,1987. The meetings were held to discuss Sequoyah restart issues and program milestones / schedules. A summary of the meeting topics is provided in Enclosure 1 and a list of attendees is shown in Enclosures 2 and

3. Licensee handout material is included as Enclosure 4.

It is our opinion that these meetings were beneficial in that we feel they provided both the NRC and TVA a better understanding of the issues.

In accordance with Section 2.790 of 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, we will be pleased to discuss them.

Sincerely, .

ORfGINAL SKINED SV s GARY G. 2ECH Gary G. Zech, Assistant Director, Regional Inspections TVA Projects Division Office of Special Projects

Enclosures:

1. Meeting Summary

2. Meeting Attendees (2/5/87)

3. Meeting Attendees (2/6/87)

4. Licensee Handout Material cc w/encls: (See page 2) 8703230339 870304 7 DR ADOCK 0500

$['!5

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l Tennessee Valley Authority 2- i MAR 0 41997 cc y/encls:

, f.L.-Abercrombie,SiteDirector S quoyah Nuclear Plant W. Cantrell,' Acting Director

_Jiuclear Engineering LR. L. Gridley, Director fuclearSafetyandLicensing LM. - R. Harding, Site Licensing Manager bec w/encls:

J. N. Grace, RII

.tg G. Keppler, OSP 3 S- . Ebneter, OSP tJ A. Zwolinski, OSP D. Liaw, OSP

/R.Connelly,01A K. P. Barr, RII R. E. Carroll, RII

% Resident Inspector

. NRC Document Control Desk State of Tennessee 1

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e--e RII RII R ar :er KBarr 02g/87 02/2V/87 g/87

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m ENCLOSURE 1 MEETING

SUMMARY

- On February 5 and 6,1987, representatives of Tennessee Valley Authority (TVA) met with the NRC, at NRC's request, at the Sequoyah site. The topics of discus-sion were Sequoyah restart issues and program milestones / schedules.

TVA provided an overview of their intended restart program which included a presentation on their planned Sequoyah Operational Readiness Assessment. This assessment is to assure the completion of activities, programs, and commitments required for startup through the verification of. Volume II implementation, performance objectives and criteria, and the implementation of a start up check list. TVA also indicated that previously run surveillance instructions would not be reperformed prior to restart unless the surveillance instruction underwent a major technical revision, or its normal performance frequency came due. Additionally, as part of the restart program presentation, the licensee defined: (1) " Unit Heat-up" as entry into Mode 4, (2) " Pulling rods" as rod movement which is intended to bring the reactor critical and; (3) " Hold Points" as Mode 4 entry, Mode 2 entry, Mode 1 entry, and operation above 30 percent reactor power.

Subsequently, Region II provided a general overview of the NRC restart inspection organization, including NRC/TVA interfaces and required release authority for proceeding beyond established hold points. Also discussed was the desire for an additional hold point at 75 percent power, as well as the need for " operating familiarization plateaus" to assure operator efficiency. Consequently, TVA agreed to make a submittal addressing the discussed hold points, operating familiarization plateaus, and the use of a committee (such as PORC) to determine when the plant is ready to request NRC concurrence to move past a hold point.

During the meeting, TVA indicated that the TVA Operational Readiness Assessment Program was not verifying the validity of the Startup Activity list (SAL). TVA committed to evaluate the need to provide an overview assessment of the development of the SAL and inform the NRC of the results of that evaluation. On NRC request, TVA also agreed to submit their Sequoyah Operational Readiness

-Assessment Program. Additionally, before concurring with TVA's stated plans for limited surveillance testing performance prior to startup, NRC indicated that further evaluations of TVA's surveillance review program and post modification testing review would be necessary. Accordingly, TVA confirmed that they were still planning to submit their surveillance review program, and a summary report of the post modification testing review being conducted.

The remainder of the meetings involved status update of various critical path items addressed in the "Stello Plan." These items included ampacity, equipment qualification, surveillance instruction review, design base line verification program, maintenance program, quality assurance program, post modification testing, fuse replacement, employee concern program, and corporate activities.

TVA proposed modified schedules for NRC inspection activities and Safety Evalua-tion Report inputs for a number of the above items. NRC agreed to review the proposed schedule modifications, but cautioned TVA that they should not plan any substantial review or inspection efforts for the staff during the period of time of a few weeks (4-6) before their designed mode change date.

ENCLOSURE 2 MEETING ATTENDEES (FEBRUARY 5, 1987)

U. S. NUCLEAR REGULATORY COMMISSION G. G. Zech, Assistant Director, Regional Inspections, DTVA, OSP M. L. Ernst, Deputy Regional Administrator, RII C. A. Julian, Chief, Operations Branch, RII K. P. Barr, Branch Chief, TVA Projects, RII R. Wessman, TVA Project Staff, NRR R. L. Spessard, Deputy Division Director, IE F. R. McCoy, Section Chief (Sequoyah), RII P. E. Harmon, Resident Inspector M. W. Branch, Startup Coordinator (Sequoyah)

K. M. Jenison, Senior Resident Inspector R. E. Carroll, Project Engineer (Sequoyah), RII R. W. Cooper, II, Office of Inspection and Enforcement J. Holonich, Sequoyah Project Manager, NRR L. Kelly, TVA Project Staff, NRR TENNESSEE VALLEY AUTHORITY H. L. Abercrombie, Site Director, Sequoyah L. Nobles, Plant Manager, Sequoyah G. B. Kirk, Compliance Licensing Manager, Sequoyah M. R. Harding, SQN Site Licensing Manager T. A. Ippolito, Corporate Licensing L. E. Martin, Site Quality Manager C. Hansen, Division Nuclear Quality Assurance, Licensing Support C. L. Wilson, Nuclear Safety Review Board (NSRB) Technical Section, Sequoyah J. G. Wills, Site Licensing, Sequoyah B. S. Schofield, Site Licensing, Sequoyah D. F. Kunsemiller, ANSL- Stl. Closure Project Manager D. Motheny, Manager, Operational Readiness, Office of Nuclear Power (0NP)

T. Kurgut, Manager, Operational Readiness, Sequoyah R. H. Buchholz, Site Representative, ONP B. L. Willis, Power Plant Superintendent, Sequoyah C. H. Fox, Assistant Manager Nuclear Power-0NP A. Priest, Restart Manager, Sequoyah K. Jones, Sequoyah Operational Readiness Staff B. Vatter, Operational Readiness Manager ,

J. Baluken, Restart Test Program, Browns Ferry R. G. Cochran, Sequoyah Activities List Closure W. H. Hannum, Chairman, NSRB, ONP D. R. Bucci, Jr., Restart Test Program Manager, drowns Ferry M. He11ums, Project Manager, Sequoyah Licensing R. P. Denise, Project Manager, Procedures E. A. Putronen, Division of Nuclear Engineering, Project Controls Consultant

o ENCLOSURE 3 MEETING ATTENDEES (FEBRUARY 6, 1987)

U.S.-NUCLEAR REGULATORY COMMISSION R. L. Spessard, Deputy Division Director, IE R. Wessman, TVA Project Staff, NRR K. P. Barr, Branch Chief, TVA Projects, RII F. R. McCoy, Section Chief, (Sequoyah), RII C. A. Julian, Chief, Operations Branch, RII M. W. Branch, Startup Coordinator (Sequoyah)

K. M. Jenison, Senior Resident Inspector R. E. Carroll, Project Engineer (Sequoyah), RII L. Kelly, TVA Project Staff, NRR J. Holonich, Sequoyah Project Manager, NRR TENNESSEE VALLEY AUTHORITY M. R. Harding, Site Licensing Manager, Sequoyah B. S. Schofield, Site Licensing, Sequoyah G. B. Kirk, Compliance Licensing Manager, Sequoyah M. Hellums, Project Manager, Sequoyah Licensing J. A. Naik, Site Modifications, Sequoyah C. L. Wilson, Nuclear Safety Revision Board, Tech Section, Sequoyah J. G. Wills, Site Licensing, Sequoyah M. Burzynski, Licensing, Sequoyah M. Cooper, Licensing, Sequoyah G. Buchanan, Planning and Scheduling, Sequoyah P. R. Wallace, Assistant to Site Director D. W. Wilson, Project Engineer, Sequoyah T. A. Ippolito, Corporate Licensing D. L. Williams, Manager, Knoxville Licensing Staff E. Putkonen, Division of Nuclear Engineering, Project Controls Consultant I

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ENCLOSURE 4 i l

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LICENSEE HANDOUT MATERIAL l 1

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SEQUOYAH NUCLEAR PLANT UNIT 2 A

R SURVEILLANCE INSTRUCTION REVIEW AND REVISION NRC/TVA MEETING FEBRUARY 5-6, 1987

TECllNICAl, SPECIFICATION SilHVEll.l.ANCE INSTHilCTIONS tilSTORICAl, NRC Inspection Results - Spring 1986 TVA Special Subcommittee Progress to December 1986 SQ-CAR-86-050 Appendix F Revisions Training Revisions / Recycle Actions to Improve SCOPE OF PROGRAM Nuclear Performance Plan, Volume.2 Identify Documented Deficiencies Identify Revisions from Modifications and Walkdowns Identify Organization Responsibility and Authority Changes Make Necessary Revisions Complete Review / Revision of sis to Ensure Technical Specifications Satisfied Other Commitments .

Ensure Technical Adequacy of sis Use of Qualified and Trained Personnel Incorporate (As Needed) Drawing Deviations, SYSTERS, s*nd SERs Follow on Revisions With Writer's Guide, Etc.

CURRENT SCOPE TVA has identified the sis that are required for startup, operation, and safe shutdown. The current review and revision program does not include all instructions encompassed by the license, but includes all instructions that i are expected to be utilized for restart and operation to the next refueling.

The remaining instructions, which are not to be utilized until after shutdown

'for refueling, will be reviewed for upgrading at a later date.

Those instructions that are not to be used during startup and operation to the next refueling, but have been performed to ensure plant adequacy, will be reviewed to confirm that the last performance was adequate, yielded valid results, and fulfilled technical specification requirements.

TVA will provide to NRC a submittal that describes this scope of effort, including justification.

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ILOWICAL SPECIFICATION SURVEILLANCE INSTRUCTIONS REVIEW AND REVISION

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Plant Manager L. M. Nobles Instruction Review Site Procedures ProjectManager --- Staff

. R. P. Denise B. W. Hanby

- Type

- Process Control

- Track 1

- Maintain Approved List i

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51te QA Responsible Independent Technica, Support L. E. Martin Sections Review Group R. W. Fortennerry J. M. McGriff

- Infonnel PORC - Produce - Verify App F - Trainine

- PORC Revisions - Sanple - Match SA/SI

- Audit - D.D. and - Sum of Parts

- Sanpling SYSTERS - Weekly Meetings

- Verify TAQ 4

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CAR 86-050 GENERA 1ED 11/18/86 IDENTIFIED INADEQUACIES WITH SI TECHNICAL REVIEW PROGRAM AND COMPLETED PROCEDURES. INADEQUACIES ARE:

1. SI-1 APPENDIX F CHECKLIST NOT ALWAYS PROPERLY UTILIZED

2. PROGRAM DEFICIENT IN FOLLOWING AREAS:

A. TRAINING .-

B. INSTRUCTIONS ISSUED IN SI TASK FORCE MEETINGS NOT INCORPORATED IN PROGRAM C. ASSURANCE THAT DESIGN BASELINE VERIFICATION FINDINGS ARE INCORPORATED INTO SI REVIEW PROGRAM ROOT CAUSES

1. INADEQUATE TRAINING OF REVIEWERS

2. PROCEDURE CONTINU0USLY CLARIFIED AND MISUSED

3. NOT EN0 UGH ATTENTION TO DETAIL

4. LACK 0F INDEPTH INDEPENDENT REVIEW i -

ACTIONS TO PREVENT RECURRENCE

1. DETAILED TECHNICAL TRAINING

2. SI-1 CHECKLIST REVISED AND REPERFORMED ON ALL INSTRUCTIONS

3. INDEPENDENT SI TECHNICAL REVIEW GROUP ESTABLISHED TO IDENTIFY AREAS OF WEAKNESS AND MAKE RECOMMENDATIONS FOR CORRECTIVE ACTIONS - PROGRAM GENERATED TO INCORPORATE DESIGN BASELINE VERIFICATION FINDINGS l 4. LONG-TERM ADMINISTRATIVE ENHANCEMENT WRITER'S GUIDE BEING t

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SEQUOYAH RESTART PROGRAM STARTUP CHECKLIST SQA191 STARTUP INSTRUCTIONS 9

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t STARTUP CHECKLIST , , ,

PREREQUISITES TESTING HOLD POINTS O

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STARTUP CHECKLIST PREREQUISITE CHECKLISTS The Prerequisite Checklist contains verification signatures by responsible . l supervisors and managers for all identified restart items and/or activities completion.

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l' Paso 35 SQA 191 Revisicn 0 '

ATTACHMENT H (continued) 5.0 ONSITE SUPPONT ..

5.1 Division of Nuclear Engineering (DNE) ,.

DNE has satisfied its restart commitnents and supports restart of

• unit 2. f t

D. W. Wilson. Project Engineer Date 5.2 Site Safety and Licensing Site I.lconalng has no known, einresolved items that would impact '

restart of unit 2. '

M. R. liarding. Site Licensing Staf f .

Date 5.3 Division of Nuclear Training All commitments for training, required prior to restart of unit 2, have boon complotod.

H. J. Johnuon, liitector of Nuclear Training Dato S.4 Site Quality Assurance Corrective Action Reports (CAR) and Doficiency Reports (DR) or portions of CARS and DRs that were identitled as unit 2 restart items have been tracked to completion and documented.

l.. E. Martin, Site Quality Manacor Date 9

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SQA 191 Rsvisicn 0 ATTACilMENT H (centinued) i

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5.5 Power System Operations .

I PS0 is ready with testing, calibration, and maintenance support for

! equipment needed for unit 2 startup. J. -

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l J. A. Dunlap Power System Operationn Supervisor Date I i

i S.6 Modifications Branch l

l The supports Modifications rustart ofBranch unit 2.has satisflod its restart commitments and

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I R. W. Olson, Modifications Manager Dato r

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l 5.7 Site Nuclear Security Branch (NSB)

The NSB is prepared to support restart and attests to physical  ;

security for unit 2 being in place and functioning properly.

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H. S. Kaplan, Hite Security Manar.or Date {

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L, . 0 SEQUOYAH SITE ONCANIZATIONS '

6.1 Site Servicen t 1

Sito Servlees han satisfied all identlflod prostartup ltoms and is t ready to support startup of unit 2.

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'/.. M. Xabirl. Site Services Mannter Date #

l 6,2 Proceduros Stutf I I I I

i 4 The Proceduros Staff has identified and successfully tracked the procedures implomentation.

needed for unit 2 restart through the review process to

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! l II . W. Hamby, Supervloor, l'rucedures Staff Date '

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cess .o SQA 191 R:vislen 0 ATTACHMENT H (continusd) 6.3 Planninr. & Scheduling -

t Planning & Scheduling has ensured a)) scheduled work required for restart is reported complete, all porlodic surveillance instructions are current, and is ready to support restart. '"'

G. N. Duchanan, PJanning & Scheduling Supervisor Date 6.4 Maintenance Planning Work request (WR) required to be complete for unit 2 startup to mode 4 hevo been tracked on the CT list to completion. In addition, a review of WR backlog and preventive maintenance packages required to ensure equipment operability for restart of unit 2 has been made for Electrical Maintenance.

W. R. Ramsey, Maintonance Planning Date 6.5 Work Hoquest Backlog The WR backlogs have boon rovlowed and at this time, all WHs identified on unit ? rentart items affecting equipment operability have been completed.

R. V. Pierce, Mechanical Maintenance Date Group Manar.er ~

11. D. Elkins, Jnstrument Maintenance Date Group Manager 6.6 Work Rogue 8t Work requent assif, nod to Electrical Maintenanco, required to ensure '

equipment operability issues for restart of unit 2 have boon '

comploted.

M. A. :'karzinski, Electrical Maintenanco Date 6

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SQA 191 R3visien 0 ATTACHMENT H (continued) s j 6.7 Proventive Maintenance Packages 't.

• 9 After revlow of Preventive Maintenance packages, we find no incomplete PMs that would impact operability of equipment needed for restart of unit 2. ..

R. V. Pierce, Mechanical Maintenance Date Group Manager

• i H. D. Elkins. Instrument Maintenance Date Group Manager ,

' 6.8 Proventive Maintenance Packages There are no outstanding Electrical Maintenance PMPs that would impact operability of egulpment needed for restart of unit 2.

M. A. Skarzinski. Electrical Maintenance Date Croup Manager I

6 ') Modifications of Egulpment i

l All identified and assigned modifications required to ensure operability of unit 2 equipment for restart have been completed.

I R. V. Plurce. Mechanical Maintenance Date Group Manager ,

H. D. Elkin8 Instrument Maintenance Date Group Manager M. A. Skardinski, Electrical Maintenanco Dato Group Manager

,, 11. J. Fisher. Modifications Group Manager Date

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M. H. Sedlacik. Electrical Maintenance Date Group Manager 1.. N. Alexander. Modifications Group Manager Date 7

- w. .v.

Rsvisien 0 ATTACHMENT ll (continued)

' 6.10. Environmental Qualificatlun Program Environmental Qualitication Program - Special projects has ensure ' -

proper Qualification Maintenanco Data Sheets (QMDS) documentation. .

storage. requirements, and EQUJS data base updates are complete to

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satisfy requirements of the SQN Environmental Qualification Progras' for restart of unit 2. i i

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D. H. Tullis, Special Projects (EQ & Mtn Trending Date . I Manager s

6.11 Radiological Control  :

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1 The Hadiolor.lcal Control section has satisfied all identified restart ltoms and is ready to support unit 2 restart.

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' R. J. Prince, Superintendent, Radiolot.ical Date i

Control e t

! 6.12 Chemistry Program a

The Chemistry Control Pror, ram la in place and functioning with no  !

i unrosolved restart items. ,

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,i W. l. Williams, Chemistry Group Manar.er Date  !

3 6.13 Technleal Support I

The review of Technical Speelfications versus design criteria has i l boon completed and all descropanelos requirod for restart of unit ,

' t 2, have been resolved. '

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j R. W. Fortenberry, Supervisor, Technical Date j Support Group .

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' Pago 40 SQA 191 h: vision 0 ATTACHMEf!T H (continued)

C 6.14 Plant Operations Review Staff

Changes in the Plant Operations Review Committee (PORC) and Unresolved Safety Question Determination (USQD) progams have boon

• Implemented to support restart of unit.

J. H. Sullivan. Supervisor. Plant Dato' Operations Review Staff The Plant Operations Review Staff (PONS) has evaluated its assigned Conditions Adverse to Quality (CAQs) and Justification for Continuation of Operations (JCOs) exist to support restart and power operations of unit 2.

H. R. Rotors, Supervisur. Date Plant Reporting Section The compilation. review, and ovaluation of data concerning past equipment defielencion/fallures of safety.related equipment is completo and has been determined to havo no offect on safe operation of the plant.

M. E. Frye. Supervisor, PJant Date Assenemont Section 6.15 Instrumentation All Technleal Speelfication (Tech Spoes) lustrumentation callbratlons have been verlfled currunt and there are no known deficieneles that would impede restart of unit 2.

H. D. Elkinn. Instrumunt Date '

Maintenance Group Manater 9

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09/. 191 R3visicn 0 ATTACHTiENT H (continued) 6.16 Housekeepint Walkdown At ter an infortnal walkdown of key plant arean, we concur that these .

areas conform to housokoeping checklist in SQA66, attachment 1. and based on that checklist and our individual areas of expertise, we ..

fool safe restart of unit 2 may commence.

H. V. pierce, Mechanical Maintenance Date, Group Manager H. D. Elkins. Instrument Maintenance Dato Group Manager a

M. A. Skareinski. Electrical Maintenance Dato Group Manater f[. A. Craitto. Supervisor. Industrial Date Safety & Fire Protection Section M. R. Sedlacik. Modifications Group Manator Date L. D. Alosandor. Modifications Group Manator Date H. J. Finhor. Modifications Group Manager Dato J. M. Anthony. Operationn Group Mannt,er Date 8

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SQE191 ,

Esvision 0 ATTACHMENT !! (continued)

. 6.20 After reviewing my sections responsibilities. I concur with my managers that all items identified to be completed prior to restart , ,

of unit 2 and this section's responsibilities have been -

. satisfactorily resolved and I am ready to support restart of unit 2. i I i B. M. Patterson, Maintenance Suporintendent Date

8. S. Willis, Operations and Technical Support Superintendent Date r 6.21 Plant Mannt.or i

I concur with my managers that all identiflod items which would impact the restart of unit 2 havo been satisfactorily resolved and we are ready to rostart unit 2.

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L. M. Nobles, Plant Manager Date j ti . ? ? !Ilte Director Daned on the purposo and scope of this document. I concur with my  !

responsible manar, ors and staff on the closure of all identifled '

restart items / activities and recommond restart of unit 2. i j

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] 11. L. Abercromble Site Director

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. STARTUP Cl!ECKLIST

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Testing Checklist The Testing Checklist contains verification signatures by responsible supervisors and managers for all identified tests, other than normal tests, that must be completed prior to passing any specified hold point.

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TESTING CHECKLIST

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Note: This list is not complete at this ticie.

Testing Prior To Entering Mode 4 (Hold Point 1)

ESF Filter Testing -

Leak Test of RHR Spray Valves 72-40 and -41 (10CTR50 Appendix J)

Leak Test of UHI Valves 87-10 and -11 (10CFR50 Appendix J)

- ERCW Pump Testing All Valve Stroke Timing Tests According to ASME Section XI Auxiliary Building Vacuum Testing - modification to ABGTS pressure controllers ,

(ECN 6027) I Steam Valve Vault Temperature Survey periodic until next refueling outage H2 Analyzer Leak Tests Component Cooling Water Pumps Testing - Ampacity Leak Test Containment Cooler ERCW Containment Isolation Valves and Checkvalves Functional Test of Incore Detector System Retests as Required by DB and V Program 2A-A AFWP Cavitating Venturi Testing CVCS Sample Line Vibration 6.9 KU Shutdown Board Block Auto Transfer the Alternate Feeder Breaker SC PORV Controls DG Random Loads ,

ERCW Hotor Bearing Cooling Water Line Reroute 14

r TESTING C'IECKLIST L..

Note: This list is not. complete at this time.

'I j Testing Prior To Entering Mode 2 (Hold Point 2) 4 Main Steam Line. Safety Valves (SI-111) ,,

Retests as Required by DB and V Program 2A-A AFWP Cavitating Venturi Testing

. CVCS Sample Line Vibration

) Steam Valve Vault Temperature Survey periodic until next refueling outage 1

SC Blowdown System - Mode 3 up to 30 percent power l' Hain Steam Line Drain Dump Tank ,

SG PORV Controls i RCS RTD Cross Calibration (TI-60) i RCS Visual Leak Test (SI-146) 1/M Plot During Approach to Critical (dilute) i t

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TESTING CHECKLIST Note: This.is not complete at this time.

, Testing' Prior To Entering Mode 1 (Hold Point 3)

HFPT Overspeed Testing .

Steam Valve Vault Temperature Survey - periodic until next refueling outage Steam Generator Blowdown Testing k

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a TESTING CHECKLIST Testing Prior To Exceeding 30 Percent Power (Hold Point'4)

Main Turbine Overspeed Test lt Main Condenser Tube Leak Test Steam Generator Blowdown Testing Steam V,alve Vault Temperature Survey i- CVCS Sample Line Vibration Core Flux Map 4

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8 TESTING CHECKLIST ,

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Testing Between 30 - 100 Percent Power MSR Performance Testing ,

FW Heater Performance Testing Thermal Power Calculation Verification RCS Flow Calculation

. Flux Map /Incore/Excore Cross Calibration - if required Steam Valve Vault . Temperature Survey f

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. STARTUP CHECKLIST Hold Points The hold point section contains signature spaces for Sequoyah Nuclear Plant Site Director to indicate completion of requirements to pass a designated ,

hold point and documentation of NRC permission to pass designated hold .

Point (NRC to designate authority to release TVA from designated hold points).

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• TVA DEFINITIONS Unit Heat-up - TVA defines as entry into mode 4

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Pulling Rods - TVA defines as rod movement which is' intended to bring the -

reactor critical Hold Points - TVA designates the following hold points that requre NRC' approval' to pass: .

Hold Point 1 - Entry into mode 4 Hold Point 2 - Entry into mode 2

- Hold Point 3 - Entry into mode 1 Hold Point 4 - Exceeding 30 percent reactor power 4

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SQA 191 Revision 0

' ATTACHMENT H (continued) 7.0 Nuclear Regulatory Commission (NRC) hold points and Special Test .

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7.1 First hold point - just prior to entering Mode 4 The NRC Senior Resident has been notified that hold point #1 has been reached. -

Site Director Date.

NRC permission granted to resume startup to second hold point.

NRC Senior Resident Date 7.2 Second hold point - just prior to entering Mode 2 The NRC Senior Resident has been notified that hold point #2 has been reached.

Site Director . Date The following test must be signed off complete before entering Mode 2:

Pressurizer PORV stroke test under RCS no load Tave and under condition set in test is complete.

Date Test of 2 -FCV 1 -18 ~is complete.

Date Test of AFW pump 2AA venturi is complete.

Date ,

Permission has been granted by the Commission to resume startup to next hold point.

NRC Senior Resident Date 21

Page 45 SOA 192 Revisic:, O

• ATTACHMEf!T H (continued) e 7.3' 'L. '

Third hold. point - just prior to entering Mode 1 .

The NRC Senior Resident has been notified that hold point //3 has been reached. ...

Site Director Date NRC permission granted to resume startup to next hold point.

NRC Senior Resident Date.

7.4 Fourth hold point - just prior to achieving 30% thermal power The NRC Senior Resident has been notified that hold point //4 has been reached.

Site Director 4

Date NRC permission granted to resume normal plant startup.

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NRC Senior Resident Date 1.

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-STARTUP INSTRUCTIONS (G01)

Acoroximatelv Three Weeks From Scheduled Mode 4 Entev Start Precaration For Startuo o 1 System Alignment o Establish as Available Condensate and Feedwater Cleanup Turbine on turning gear Condenser vacuum CVCS charging and letdown from RHR

. RCP seal flow Pressure bubble Pressurize RCS to approximately 325 psig Run RCPs as needed 1

o When Permission to Enter Mode 4 Start G01-1 (hold point 1)

• G01-1 Performance o Prerequisites Holdup tank space available Primary makeup water available .,

MSIVs and bypasses closed RHR ',n service 4 -

All technical specifications requirements for mode 5 satisfied Onsite voltace requiremer.:s as specified in GOI-6G 23

- , . . - . . _ . - - , , - . - - - - - - - .- ~-

d-3 2

o ' Instructions _

1 -

Instrument Availability Checklist (G0I-lE)

Auxiliary Control Room Switch Alignment (SI-633) .

Essential Instrumentation Operability Verification (SI-604)

. Verify system alignment (status files and configuration log)

Verify license requirements in accordance with GOI-1A pre-startup checklist

- Establish the following or verify.

Condensate and feedwater cleanup Turbine on turning gear CVCS charging and letdown RCP seal flow j Pressurizer bubble Pressurize RCS to approximately 325 psig

- Start RCPs as needed Withdraw all control and shutdown rods 5 steps or verify reactor trip breakers open Heat up to approximately 180 degrees fahrenheit Verify RCS chemistry prior to exceeding 180 degrees fahrenheit Containment spray operable

-Ice condenser lower door blocks removed Purge damper blocks installed Review hold orders Review TACFs l

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Review configuration log and statu., files Verify requirements of TI-77 satisfied  ;

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Air return fans operable Two CCPs operable  !

SIS unblocked t

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"

• T ' '- - Containment cleanliness inspection complete

- Remove RHR from' service ,

- Heat up to mode 4 approximately 205 degrees fahrenheit..(verify 74-1 agd.-2

. isolated prior to exceeding 212 degrees fahrenheit) .

- Continue heat up

- Perform FCV-74-1 and -2 leak test -

- Establish H2 blanket in VCT -

- Continue condensate and feedwater cleanup and deaeration

- Place steam lines in service

- Place CRDM fans in service prior to exceeding 350 degrees fahrenheit

- RCS will be pressurized according to heatup curves

- PAM instrument availability checklist G0I-lF completed

- Verify license requirements for mode 3 G01-1B checklist (UHI exceptions)

- Complete ECCS master checklist G0I-lD

!- - ERCW to AFW operable

- Verify following:

Hold orders TACFs

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Configuration log l

Status files

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- Heat up to mode 3

- Continue heatup to 547 degrees fahrenheit 7 - Perform SI-130.1 (terry turbine driven auxiliary feedwater f j- pump) at > 525 degrees and 842 psig main steam pressure l

- Perform SIS checkvalve leak test (SI-166.10) at > 900 psig RCS pressure 25 L

~

- Prior to 1000 psig RCS, place cold leg accumulators in service L.

- Perform UHI Check Valve Leak Test (SI-166.ll) and Hydraulic Isolation Valve Test (SI-196.2)

- Prior to 1900 psig RCS, place UHI accumulator in service

- At rated temperature and pressure ,,

Perform SI-146 RCS leak check visual Perform rod drops Perform RPI cals AFW pump 2A-A cavitating venturi tests Other required items G01-2 Performance o Prereouisites

- Permission to enter mode 2 (hold point 2)

- G01-2 checklist 2A (technical specification verification for mode 2) complete

- SI-93 complete (neutron instrumentation)

- RCS chemistry in limits

- Verify proper operation of MFW regulator valves and bypass valves o Instructions

- Verify SRM audio count rate channel in operation

- Withdraw shutdown banks if not already withdrawn

- Calculate ECC (we plan on diluting to critical using 1/M plot)

- Withdraw control rods to preselected position

- Begin dilution .

- At IRM 10-10 amps (P-6) remove SRM from service

- At IRM 10~0 amps obtain critical data 26

6 4-Increase' power to 1-4 percent control steam generator levels ,

.approximately 33 percent with AFW system

- Perform MFPT checks and overspeed tests Couple MFPTs to MFPs Start a feedwater pump supplying main feedwater to steam .

generators when feedwater chemistry in limits Maintain steam generator levels at approximately 33 percent with steam generator blowdown in service When steam generator blowdown chemistry is in limits reduce reactor power to approximately 1 percent until permission to enter mode 1 is received (hold point 3)

Increase reactor power to 10-20 percent on steam dump to condenser Verify generator contains hydrogen for cooling Roll main turbine to 1800 r/ min Synchronize main generator to electrical grid Increase load Establish automatic main feedwater level control Transfer station service Hold at 30 percent power Continue cleanup of condensate and feedwater system Continue steam generator blowdown to establish chemistry (

requirements for > 30 percent power After at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> remove turbogenerator from electrical grid 27

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- Perform main turbogenerator overspeed trip test Synchronize generator Return to 30 percent power Permission received to exceed 30 percent power (hold point 4)

When steam generator chemistry in limits increase power

- Place additional condensate and feedwater pumps in service as required Place heater drain system in service

- Place MSRs in service at approximately 35 percent power

- At 75 percent perform thermal power calculation verification, RCS flow calculation, and incore/excore cross calibration if required Increase power to 90 percent

- At 90 percent perform calorimetric calculation Increase power to 100 percent O

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iva u tos s m om e s.m

!' e i,Ni'iI:D .sT.\TI:s Govi: :N.tli:N r A02 861128 020 Memorandum TexNesses vacLev Aurnoniry 1 Those listed TO .

FROM  : C. C. Mason, Acting Manager of Nuclear Power, LP 6N 38A-C DATE  : Lvenber 23, 1986

SUBJECT:

CORPORATE REQUIREMENTS FOR OPERATIONAL READINESS FOR TVA PLANTS -

BROWNS FERRY, SEQUOYAll, AND WATTS BAR The attached subject requirements document is approved for issuance. The site directors and.the Operational Readiness Program Manager shall utilize this document in the development of the operational readiness program for the respective sites.

The Operational Readiness Program Manager is assigned the responsibility for the development of any needed corporate directives on this subject.

c oy h-.

II . L Abercombie, ONP Sequoyah R. A. Matheny, POTC-C H. P. Pomrehn, Browns Ferry G. Toto, ONP, Watts Bar VIC:CLB Attachment ec (Attachment):

HIMS, MR 4N 12A-C W. R. Brown, Jr., ONP, Watts Bar L. L. Jackson, LP 6N 38A-C W. R. Brown, Jr.,11-128 SB-K T. B. Jenkins, LP 6N 38A-C R. W. Cantrell, W12 A12 C-K R. J. Johnson, POTC-C W. T. Cottle, LP 6N 38A-C J. L. McAnally, LP SN 38A-C C. W. Crawford, MR SN 52A-C R. A. Pedde, ONP, Watts Bar J. P. Darling, ONP, Bellefonte C. G. Robertson, LP SS 83E-C C. II. Fox , Jr. , LP 6N 38A-C R. K. Seiberling, 716C EB-C R. L. Cridley, LP SN 1578-C E. K. Sliger, LP 2N 97B-C W. 11 . !! annum, BR IN 76B-C M. E. Taylor, LP 6N 38A-C 2 01'86 L - . * ~ -

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ATTACHMENT CORPORATE REQUIREMENTS FOR OPERATIONAL READINESS FOR TVA PLANTS SEQUOYAH, BROWNS FERRY, WATTS BAR t

i, A pp r es vi+d : . _ . , '.]~ ' IT'*f; _

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, CORPORATE REQUIREMENTS FOR OPERATIONAL READINESS TABLE OF CONTENTS F

1.0 -INTRODUCTION & PURPOSE 2.0 NUCLEAR PERFORMANCE PLAN IMPLEMENTATION.

3.0 PERFORMANCE OBJECTIVES EVALUATION 4.0 STARTUP PREREQUISITE VERIFICATION 5.0 REPORT REQUIREMENTS J

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Each sito will conduct an ovaluation of Operational Ratdiness prior i .' to plant heatup from cold shutdown. The purpose of Operational Readiness is to ensure that site organizations' and support

( organizations' procedures and programs are fully prepared for startup and in compliance with regulatory commitments and that plant systems are in the required state of readiness. This document provides a framework and minimum requirements to be used for the evaluation. It describes a structure to conduct and document

activities comprising three primary segments

o Nuclear Performance Plan Implementation o Performance Objective Evaluation o Startup Proroquisito Vorification Each site will supplement the minimum requirements by development and implementation of a site-specific program. Some variation in the sito-specific development and implementation is to be expected.

The manager of the Operational Readiness Program will provide independent oversight of the development and implementation of each of t ho sito-specific programs. lie will function in this capacity to

, assist thu sito diroctor in onsuring both the adequacy, offoetivonoas, and timolinoss of tho sito-specific program. He will also function to provido indopondant assessments and evaluations to tho Managor of Nucloar Powor. In particular, he shall assess whother curront corrective action plans have been addressed to the underlying causos of deficiencies or problem areas and shall ensure that additional correctivo actions for deficiencies identified during t he roviow are based on determination of the underlying cause.

7.0 NUCl. EAR PERFORMANCE Pl.AN IMPI.EMENTATION l

The implomontation of the Nuclear Performance Plan (NPP) is critical to unsuring Oporational Roadinoss. One objective of Operational l Rondinoss in to ostablish minimum standards and acceptable methods

for this task. Each plant may supplement these requirements with implomontation plans nocossary to satisfy plant-specific readiness requiremonts. Actions not required for restart aro boyond the scope of Oporational Roadinoss and will be addrossed by other site programs, llowevor, Operational Rondinoss will onsure that these actions aro enplurod by othar programs.

7.1 Iduntification of Rostart Roquiromonts Rostart roquiromonts havo boon idontifiod in the appropriate sito NPP (Volumns 1-4) commitmont lists, sito activity lists or intogratud P-? .chodulos. In addition to the restart roquiromonts idontiflod in omisting lists and schedulos, the NPP text will bo furthur roviowod to idontify actions or I

intentions that aro roquirod for rostart.

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2 2.2 Assignment of Restart Requirements k-The responsible manager for each restart requirement will be identified on attachment A forms. This. assignment may be accomplished by reference to and attachment of applicable portions of existing activities lists or P-2 schedules.

Rostart requirements identified in the NPP text and not already contained in an NPP list or restart schedule can be addressed in one of the following ways:

o Assignment of NPP sections to responsible individuals, o Assignment of specific actions or intentions directly to responsible individuals.

2.3 Closure of Rostart Requirements Closure of identified restart items shall be documented under the Operational Readiness by use of attachment A forms. These forms may ruforence closure under existing site project control methods.

Cortain rostart activitios and requirements reprosent major issuos or projotts that havo broad impact on other plant activitios. Examplos of thoso issuos and projects include dbaign basolino, Appendix R, onvironmontal qualification, soismic iscuos, survoillanco instruction review, electrical issuos, and wolding.

Tho sito diroctor will requiro documentation of resolving the principal problums; howuvor, he will also require that closure considor tho impacts of problem resolution on other activitios. Tho following are considerations that should be applied to impacted areas to ensure sufficient criteria are idontiflod for closure of major issues or projects:

o Calculations complete, documented, and cross-referenced as required.

o Dosign input and/or output process (or other process as appropriato) rovisod to procludo recurronce, o Drawing rovisions identiflod in a controlled procedural procons, primary drawings proporly marked in the main control room, o All intorfacos idontiflod and rosponsibility assumed:

FSAR updatos i Configuration control Procuduro rovision (internal /uxternal)

Storago roquiromunts.

o Excoptions to complotion idontified and schoduled.

o post-startup work requirod for complotion idontified and scheduled.

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• Attachment A will be used to identify, assign, and documsnt closure of all criteria, including criteria that address impacts on other activities.

3.0 PERFORMANCE OBJECTIVES EVALUATION Each site will establish performance objectives necessary for restart and shall conduct an assessment in the general format of an INPO evaluation for those objectives. The following documents will

be used as references for the establishment and the assessment of those performance objectives, o Performance Objectives and Criteria for Operating and Noar-Torm Operating License Plants INPO 85-001, Institute of Nuclear Power Operations, January 1985.

o Performance Objectivos and Criteria for Corporate Evaluations.

INPO 85-029, Institute of Nuclear Power Operations August 1985.

Each sito will onsuro tho assossmont of objectivos addresses the following:

o Staffing is adoquato to support safo and reliable operation of tho plant.

o Procuduros aro aduquato to support safe and reliable operation.

o Sup.orvisory_inyolvement in the activities of subordinates is sufficiont to onsuro satisfactory performance of work attivities, g' o Training and qualification have boon completed and are adoquato for personnol to perform assigned duties.

The purposo of the porformance objectives evaluation is to ensure tho sito organizations and support orfanizations function uffoetivoly and aro propared for plant startup.

Tho following functional areas will be assessed:

o Organizntion and Administration

, o Plant Operations

, o Maintenance

( o Technical Support l o Training and Qualifications o ' Radiological Controls o Chemistry o Emorgoney Preparedness o I.icensing o Modifications o Security l o Quality Assuranco I o Engincoring l o in-Sorvico Inspoetion o Surveillance o Contiguration Control 6

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4 Each sito should ensure all organizations that contribute to the j functions listed above are provided specific performance objectives essential for plant restart and that the organizations assess their readiness to achieve those objectives.

The evaluation for readiness will include the following general steps:

o Establishing performance objectivos and criteria that are appropriato, o Evaluating readiness against the established critoria.

o Assessing tho impact of deficiencies identified.

o Developing and implementing additional corrective action for deficienclos identified.

o Final vorification that the performance objective has been met and readinoss is assured.

4.0 STARTUP PREREQUISITE VERIFICATION Sito-spocific instructions and tracking programs are established to ensuro that hardwaro-related issues directly impacting system opornbility aro closod prior to modo changes. System operability prior to modo changos is veriflod by completion of applicable Genoral Oporating Instructions, System Oporating Instructions, and Startup or Rostart Instructions. In addition to those instructions, other tracking and schoduling means (P-2 schedule) may also be used to unsuro corroct system status prior to modo changos. To provido additional confidonco that thoso hardwaro issuos aro complete, site diroctors will implomont a spucific startup proroquisito chocklist prior to hoatup. Tho chucklist will sorvo to consolidate hardware operability issuos such as the following:

o Maintonanco or Work Roquests Backlog o Cloarancos Outstanding o Modification Status o Tomporary Attoration Control Forms (TACFs) Outstanding o Survoillanco Instructions o Provontivo Maintonanco Packagos outstanding o Instrumontation Availability o Nonconforming Conditions Conditions Advorso to Quality (CAQs)

Outstanding o Primary & Socondary Chemistry Controls This approach will provido a structurod completion signoff system by responsiblo managers The chocklist should idontify tho rosponsiblo manager or managers for each itom and provido a signature and dato attosting to satisfactory complotion of tho itom. Chocklist completion would then sorvo as tho basis for authorizing modo changes during plant startup.

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.5.0 REPORT REQUIREMENTS.

k' Operational Readiness reports will be provided in two phases as follows:

o The initial report will provide the following:

- Identification and assignment of NPP restart requirements

- Performance objectives and criteria to be evaluated A description of currently available startup prerequisite checklists o- A final report of Operational Readiness will be provided. This report will document Operational Readiness in those areas not closed in the initial report.

The Operational Readiness reports will have attachment A forms that address all restart requirements and attachment B and C forms that address all performance objectives and criteria. The final report will also include the site director's startup prerequisite checklist.

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RESTART REQUIREMENTS

, i' /

. Dzte Initiated:

' Restart Requirement I.D.:

Restart Item

Description:

Responsible Manager:

Criterlon Met, Cognizant Individual Documents on File Closure Criteria (Print Name) (Initials /Date)

I-Approval of Critoria: Concurrence:

Responsiblo Managor/Dato Principio Manager /Dato Excoptions and justification for restart with onceptions:

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Tho restart item adequately closed for plant startup: Concurronco:

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Responsible Manager /Date Principle Manager /Date l

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ATTACHMENT B

= .* PERFORMANCE OBJECTIVES

' Organization:

Responsible. Manager:

Performance Objectives (attach additional sheets as necessary):

9 Cuf f iciont porformanco objoctivos have boon identified for ovaluation:

Responsiblo Manager Date Ruviewod f. Concur:

Noxt liighor Level Manager Date

. Concurronco:

Operational Roadiness Manager Date l

l All.Portormanco Objoctivou and Rostart Roquiromonts have boon accomplished and this organization is ready to startup:

Responsiblo Managor i Date Next Hirhor I.ovol Managor

, -g Date l

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PERFORMANCE AND EVALUATION Organizction:

g .Hesponsible Manager:

Performanco Objective:

' Criterion:

Statement of how performance compared against critorion or how performance will be evaluated:

Preparod by /

i Rosponsiblo Managor Date Enceptions and Evaluation of Impact:

Correctivo Action to Rosolvo Exceptions:

chodulo f or Corroctivo Action Rostart? (Y/N) ,

In-Plant Schedulo (Y/N)

Critorion met: Roviow and Concurronco:

, Hesponsible Manager /Date Next liigher Level Manager /Date

~0perational Headiness Manager /Date

4 SEQUOYAH OPERATIONAL READINESS SQN Operational Readiness - Standard Practice SQA191 issued 1/2/87, Rev. 1 - 2/4/87 Scope / Purpose SQN Operational Readiness (OR) is complimented by:

1. The site program for closure of Sequoyah Activity List (SAL) items (SQA190).

2. Plant instructions to control approach to startup and power ascension -

General Operating Instructions 1, 2, and S.

3. The site quality manager's independent review in major project areas.

l Collectively, these processes will assure that site organizations, procedures.

l and programs are prepared for unit 2 startup; that regulatory commitments have been met; and that plant systems are in the required state of readiness.

• SQN OR is a structured line evaluation by onsite organizations which will .

provide the site director verification that activities, programs, and f

commitments required for startup are closed. This is being accomplished through:

1. Verification of Volume II implementation;

2. Verification of organizational readiness through evaluation of performance objectives and criteria; and Verification that hardware issues directly impacting system operability 3.

are closed prior to mode changes through implementation of a startup checklist.

! SON Nuclear performance plan Volume II Implementation

1. SAL Closure - The SQN OR report will contain documentation developed by the independent SAL closure effort.

2. Volume II Text Intention Closure for Restart - 75 potential intentions identified. For those determined to not duplicate a SAL item or be postrestart, SQN OR will require responsible managers to complete activities required for startup and develop documentation to verify the item is complete.

3. Major project / issues that have broad impact on other plant activities 3

will be required to meet additional closure criteria in addition to that

. required by the SAL closure process.

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The major projects and issues being addressed are:

. Appendix R . Heat code

. Environmental Qualification . Welding

. Design Baseline Verification . Procedures ,~

Program . Surveillance Instruction

. Alternate Analysis Review

. Superheat Issue . Component and Piece Part

. Employee Concerns Qualification

. Electrical Calculations (Low . Rachen Splices Voltage Ampacity, Sidewall . IE Bulletin 79-02 Pressure) . IE Bulletin 79-14 Closure criteria have been developed in conjunction with each assigned .

project manager. These criteria will provide the basis for a final project report which will address and document completion of each project for restart. Typically, the additional closure verification will address recurrence control, internal project documentation, internal / external identified findings in the project area, and control of postrestart actions.

Performance Objectives and Criteria Performance objectives and criteria have been established which address the generic areas of procedures, staffing, supervisory involvement, internally / externally identified findings, housekeeping, and readiness of support organizations during startup. Additional performance objectives and criteria have been developed for the functional areas of organization and administration, document control, maintenance, training, licensing, engineering, and configuration control.

Under OR, performance objectives and criteria have been assigned to site organizations and detailed meetings held between the OR staff and responsible managers to convey these requirements and to assist the responsible managers in evaluating their organizational readiness. A total of 388 performance objectives / criteria - organization combinations are being evaluated.

The Interim OR Report will document each organization's evaluation of performance against the criteria to the point of identifying exceptions. The Final OR Report will document closure by the responsible site manager that criteria have been met or that exceptions are justified for restart.

Startuo checklist verification In addition to plant instructions (GOIs) and restart activity closure (P/2 schedule), a startup checklist (attachment to SQA191) will be used to provide additional verification that hardware issues directly impacting system i

l

operability are closed prior to mode changes. The checklist and signoff will i serve to consolidate hardware operability issues cuch as the following:

. TACFs and hold orders

. The review of past deficiencies and failures of safety-related equipmant

. Maintenance work request backlog and PM packages

. Testins and calibration of PSO equipment

. Technical specification review vs design criteria

. Modification status relative to equipment operability of safety-related systems

. Housekeeping of key plant areas

. General concurrence of site managers that identified hardware

• operability issues have been closed for restart

• Testing required during startup The startup checklist will provide a structured completion signoff by responsible managers for the above issues as well as identify and control operations relative to NRC holdpoints.

SON OR Evaluation and Report Schedule Interim OR Report - Week of 2/9/87 Final OR Report - March 31, 1987 A supplement to the final report may be prepared to address closure of any open items identified in the final report as well as closure of those SAL items and completion of those startup checklist items which are tied to conditions after entering mode 4.

0119H 2/4/87

a a TFNNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT STANDARD PRACTICE SOA191 EVALUATION OF OPERATIONAL READINESS PRIOR TO PLANT RESTART Revision 1 T. D. Knight PREPARED BY: .

- 'I RESPONSIBLE SECTION: Site Director's Staff APPROVED BY.: /M/

W 4 61te Quali nization V

/l1 SUBMITTED BY: )I" t ion Supervisor R e s p o n s i b l e' S e APPROVED BY: .

h T*} Sit""i'**

DATE APPROVED: Y 07

\

Reason for revision (inclijd- all Instruct ion Change Form Nos.):

General revision,to_incorpopote corrections;_ modtfy the scope of the startup.yreseouis,ite; checklist; and clarify responsibility of princlyaI'manacers for approval of assioned performance obiectives/ criteria. ,

The last page of this instruction is number: 34

. . .- _ .- = - - -

Page 3 SQA188' ,

Revision 0

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' Standard Practice ATTACHMDJT 1 SEQUOYAH NUCLEAR PLANT Interim procedure system coordination / documentation Rev Level 1 record for SOA191 Proca. dure Identity Number i

RESPONSIBLE SECTION:

Submitted By: M /' /

Date h -

Responsible _S4ctipnSpurvisor CONCURRENCE / APPROVAL:

,\ /r a W5* Y Date Engineering /~1*""

MJ h 2-4 97 Date

' nstruction 6 ~2nd

1. Saf ty and Licensi e -

2h/r1 Date-W /

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' /lthQuality'Assur e

='4 0 b Afl~ A/$/Pf Dste V Engineering'Als2rance 1

N/A Date Division of Nuclear Services sj w /W _o2 Al Date sonnel Staff

[ Nuclear P

- N/A

! Date 1

Planning and Financial Staff N/A - Sea Cover 9hoet Date Site Director

Reason for Interface

To document headquarters endorsement of existing site instruction in .

lieu of higher tier document number To document transfer of responsibility.

y To document concurrence of procedure interfaces.

02495/lsh

SEQUOYAH NUCLEAR PLANT PLANT INSTRUCTION REVISION LOG l

STANDARD PRACTICE SOA191 REVISION Date Pages REASON FOR REVISION (INCLUDE COMMIT-LEVEL Approved Affected MENTS AND ALL ICF FORM NUMBERS)

All New procedure.

0 General revision to incorporate correc-tions; modify the scope of the startup prerequisite checklist; and clarify responsibility of principal managers for approval of assigned performan'ce 1 All obiectives/ criteria.

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1079C/1dw

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ITO: Controlled Manual Holder FROM: Document Control / Records Management, SQN DATE:

SUBJECT:

TRNNSMITTAL OF SEQUOYAH INSTRUCTIONS Please sign below and return to acknowledge receipt of the following material and affirm'that it has been placed in the appropriate manuals, your table of contents has been updated, and the superseded

, instruction removed and discarded. Return this transmittal to Document Control within 10 days.

' STANDARD PRACTICE a

i SOA191 EVALUATION OF OPERATIONA'L READINESS PRIOR TO PLANT RESTART

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I4 Remove and destroy Insert PaQe Date Revision Pace Date Revision

'All 01/02/87 0 All 1 g

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Return to: Document Control / Records Management, Sequoyah Nuclear Plant- ,

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' Distribution of Standard Practice SQA191 q

-h Controlled Documents Uncontrolled Documents t

Plant. Master File Plant Manager, WBNP Plant Manager Chief, NUC Training Branch, ,

NMRG-710E EB-C i Site'QA Manager (2)

Site Director Site Licensing Supv ~

Mech Mtn Supervisor (2)

Elec Mtn Supervisor

-Asst Elect Mtn Supv Instr Mtn Supervisor ,) ,

Technical Support Supervisor ,

Mod Library Mech Mtn Engg #1 -

Systems Engg Supervisor ,

Electric Shop PSS Shift Supervisor Building' Services Supervisor "

Personnel Officer '

Operations Supervisor (2)

QA Surveillance Supv-

// Manager of Project Mgmt +

Radiological Control Supervisor Public Safety Supervisor (2)

Compliance and Regulatory Licensing Staffs

~

NUC PR Record Mgr Sect, LP 4S 160D-C (3)

Modifications Mgr SE Contr'ol Room DPSO Supervisor

, Industrial Safety Section

~ .' Project Enginher

' Chemistry Group Supervisor i Plant Operations Review Staff l Financial Planning Supervisor w._ Planning and Scheduling Group

^-s Procedures Staff' Site Services Supervisor

-Employee Concerns 1 Group Production Planners i- Systems Engineering l

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Page O SQA191 Revision 1 PUNCHLIST Attachment H, Startup Checklist, will be included at a later date.

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c- Paga 1 SQA191 Revision 1 TENNESSEE VALLW AUTHORITY SEQUOYAH NUCLEAR PLANT STANDARD PRACTICE SEQUOYAH OPERATIONAL READINESS 1.0 PURPOSE This standard practice delineates a method to be used to conduct an i evaluation of Operational Readiness prior to plant heatup from cold shutdown. The purpose of Operational Readiness is to assure that site organizations and support organizations, procedures, and programs are'

, fully prepared for startup and in compliance with regulatory. a conunitments and that plant systems are in the. required state of

~

readiness. This standard practice provides a' framework and requirements to be used for the evaluation. It describes a structure in which to conduct and document activities in three primary areas:

= Sequoyah Nuclear Performance Plan (SNPP) Implementation

• Performance Objective Evaluation

= Startup Checklist Verification

.2.0 SCOPE The requirements of this standard practice apply to onsite managers reporting either functionally or administratively to the site-director and to those ONP managers offsite who have responsibility for restart items identified in the SNPP. Managers are responsible for completing the requirements of this standard practice in accordance with a schedule to be established and prior to heatup of the first plant unit.

.An Operational Readiness Staff (ORS) has been formed to assist site directors and support managers in the timely and effective i

implementation of the reqvirements of this instruction (refer to Appendix A for a description of this staff).

3.0 REFERENCES

i 3.1 Corporate Requirements for Operational Readiness for TVA Plants Sequoyah, Browns Ferry, and Watts Bar, November 28, 1986 (A02 861128 020) 3.2 Performance Objectives and Criteria for Operating'and Near-Term Operating License Plants, INPO 85-001 0288S/v1c I

Paga 2 SQA191 ,

Revision 1 Standard Practice

3.0 REFERENCES

(continued) 3.3 Performance Objectives and Criteria for Corporate Evaluations,

.INPO 85-029 3.4 Memorandum to Those listed from H. L. Abercrombie dated October 27,'1986 (S06 861017 802) 3.5 Memorandum to Those listed from H. L. Abercrombie dated December 1, 1986 (S00 861126 801) 3.6 Standard Practice SQA190, Restart Issue Disposition

-4.0 DEFINITIONS 4.1 Performance Obiective-A goal stating an objective that prescribes an acceptable level of performance in an organizational or programmatic area.

4.2 Criteria A specific set of measurable attributes that define the acceptable levels used to meet a performance objective.

4.3 Site Director Orcanizations Organizations onsite who report directly to the site director.

4.4 Onsite Support Orcanizations Organizations onsite performing a supporting function to site director organizations and reporting administrative 1y to an offsite parent organization. These organizations include the Sequoyah Quality Manager's organization, Power Systems Operation, Licensing, SQN Project Engineer Organization, Modifications, POTC, Public Safety, and Power Stores.

4.5 Offsite Support Organizations Organizations located offsite who perform support functions to site director or onsite support organizations and having no onsite support organization. These organizations are within Nuclear Services and DNE and located at the corporate office such as Radiological Control, Chemistry, Fuels Branch, Containment Leak Testing, and Inservice Inspection.

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l P:ga 3 ]

SQA191 j Revision 1 Standard Practice 4.0 DEFINITIONS (continued) 4.6 Operational Readiness Staff (ORS)

The temporary staff established by the SQN site director to develop a Sequoyah Operational Readiness program, consistent with corporate guidelines (reference 3.1), to assist onsite organizations in their evaluation of operational readiness, and to assemble the reviewed and approved results into a final report. Refer to appendix A for a description of the ORS.

4.7 Proiect Manacer An individual assigned with overall coordination responsibilities to ensure that a major work issue is accomplished in accordance with all applicable requirements and in compliance with a defined schedule.

5.0 INSTRUCTIONS ,

The first two phases of the operational readiness assessment, SNPP implementation, and performance objective evaluation will be completed i in parallel beginning with the issuance of this standard practice. The third phase of operational readiness, the startup prerequisite verification, will be completed just prior to restart of the first plant unit. The closure of restart items will result in a set of completed documentation providing an adequate basis and referencing associated closure documentation. As new restart items are identified in the future, the same closure mechanism described in section 5.1 will be used to document completion. An initial review of performance objectives will be conducted in accordance with the requirements of section 5.2. Updates will be processed in accordance with the instructions given in section 5.2 for the attachment E forms.

Applicable parts of the startup checklist will be signed off just prior to entering designated modes. Any required updates will be accomplished by signing and dating the appropriate item on the checklist.

5.1 Sequovah Nuclear Performance Plan (SNPP) Implementation Responsible supervisors and managers will verify that restart activities, restart SNPP text statements of intention, and major projects are closed for restart. This section provides the instructions and documentation requirements to meet this objective under Operational Readiness.

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P:g2 4

. SQA191 Revision 1 Standard Practice 5.0 INSTRUCTIONS (continued) s A. Restart Items Identified in the Sequoyah Activities List (SAL) Schedule Verification of closure of restart items shall be documented under Operational Readiness. This effort will address restart items which have been identified in the SAL.

The requirements for closure documentation of SAL restart items are defined in standard practice SQA190. The closure i

documentation and approvals generated by performance of .

SQA190 shall be incorporated into the Operational Readiness Report. ,,

4 B. SNPP Text Statements of Intention d

The SNPP text will be reviewed by the ORS to identify statements of intention which were not identified as a '

4 commitment or restart item in the SAL. Statements of intention which are identified by the Operational Readiness Staff and the responsible supervisor will be documented on-

. Attachment A forms. Under Operational Readiness, I

responsible managers will verify that these items are

completed to fully carryout the SNPP.

1. Operational Readiness Staff (ORS) l (a) Provide update / closure forms (see attachment A) l listing intentions to the responsible supervisors.

j (b) Evaluate completed update / closure forms and any

l exceptions taken. Review exceptions with the site i, director / task force as necessary.

(c) Incorporate documentation into the Operational

Readiness Report.

4 r

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P:g3 5 SQA191 Revision 1 Standard Practice 5.0 INSTRUCTIONS (continued)

2. Responsible Supervisor / Manager

' (a) Ensure that work is complete and documentation

maintained to fully carry out the SNPP. - To document completion of work required for restart, the responsible supervisor / manager will complete the " Criteria and Justification for Closure" and the " Exceptions and Justification for Restart with Exceptions" portions of the form in attachment A.

(b) Return the signed update / closure form to ORS signifying that the item,is closed for restart.

• t C. Closure of Maior Issues or Proiects Certain restart activities and requirements represent major issues or projects that have broad impact on other plant

' activities. These issues and projects are defined as follows:

• Appendix R Environmental Qualification

• Design Baseline Verification Program a Alternate Analysis

• Superheat Issues

• Employee Concerns

• Electrical Calculations (Low Voltage, Ampacity, Sidewall Pressure)

• Heat Code

• Welding

• Procedures

'

• Surveillance Instruction Review

• Component and Piece Part Qualification (Seismic

and Environmental)

• Raychem Splices

• IE Bulletin 79-02

'

• IE Bulletin 79-14 j 028ES/vic

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Page 6 SQA191 Revision 1 Standard Practice 5.0 INSTRUCTIONS (continued)

Individual items requiring completion to close these projects / issues are identified in the SAL and are closed in accordance with the requirements of SQA190 and section 5.1.A of this Standard Practice *. However, since these projects /

issues have significant impact on plant activities, additional closure documentation will be required. The purpose of this additional documentation is to ensure that restart activities have been identified, adequate recurrence control has been established, internal documentation is being properly managed, and that all restart items associated with the project / issue have been completed.

Since each major project / issue varies in scope, impact on plant activities, and necessary programmatic requirements, the closure criteria needed to assure operational readiness will also vary with each project / issue. In order to establish project / issue specific criteria, the ORS will meet ,

with each assigned project manager to define the criteria necessary for project closure. Specific criteria will be developed by considering the following objectives:

• Required restart activities (by any organication) have been entered in P/2 and closed in accordance with the criteria of section 5.1.A.

• Actions to identify and prevent recurrence have been completed, if the action is required for restart.

• Internal project documentation required for restart is complete, retrievable, and maintained by an approved management system.

• Post-restart actions have been identified, responsibility assigned, scheduled, and placed in an appropriate management tracking system.

• NOTE: Surveillance instruction revisions and other procedure revisions are tracked and closed on the site procedures tracking system.

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L Page 7 SQA191 Revision 1 Standard Practico 5.0 INSTRUCTIONS (continued)

The project / issue specific criteria will then be documented on attachment G along with the principal manager's approval of the established specific criteria. Following the principal manager's approval, the assigned project manager will begin the evaluation and closure process for each established criteria.

Following completion of the criteria evaluations for each major project / issue, the responsible project manager documents on attachment G that all associated TVA actions -

with restart applicability are complete. The project manager then obtains review and concurrence from his supervisor and transmits the completed documentation to the ORS.

5.2 Performance Obiectives and Criteria A. Identification of Performance Objectives Performance objectives and asrociated criteria essential for

. the safe, efficient restart of the plant have been developed and are listed in attachment B. These performance objectives are grouped under the two major headings of generic and major functional areas. The generic criteria were generated to address almost universal programmatic and personnel related issues applying to site director and support organizations. The functional area performance objectives and criteria were developed by reviewing the information contained in INPO Report 85-001 (reference 3.2) for applicability to Sequoyah programs based on known and identified problem areas. A matrix has been developed (attachment C) to identify specific performance objectives and criteria that must be addressed by each organization.

This matrix defines assignments down to individual group levels for the site director organizations.

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Page 8 SQA191 Revision 1 Standard Practice 5.0 INSTRUCTIONS (continued)

In addition to the performance objectives and criteria listed in attachment B, managers and supervisors should determine if any additional performance objectives and criteria are needed to ensure operational readiness for their particular area of responsibility. For the additional performance objectives and criteria identified, the organizational manager should identify these to the ORS who in turn will prepare attachments D.1 and E forum and return them to the manager / supervisor for his evaluation. .

In some casec, a particular generic criteria may not be directly applicable to an evaluating organization. When these cases are identified, the responsible supervisor may develop alternate criteria tailored to his organization to implement the assigned performance objective. The alternate criteria should be established by working with the ORS to ensure consistency and integrity of the evaluation process.

The ORS will then issue a new attachment E to the supervisor reflecting the new criteria for evaluation. The basis for establishing the new criteria will be documented by the ORS >

on the superseded attachment E form containing the originally assigned criteria.

For both site director and onsite support organizations, the evaluation of performance objectives must also include those areas of support which they receive from ONP organizations offsite. Site director and onsite support organizations will review those interfaces based on past experience and present known capabilities. In those cases in which the site director or ensite support organizations can determine that the working interface is well established and that the offsite group satisfactorily meets performance objective number 5, this should be documented on attachment E by the onsite group. Areas of offsite support for which the onsite organization cannot determine that performance objective number 5 is met shall be identified to the ORS. In the areas identified, the ORS will work with the offsite group and onsite group in addressing performance objective number 5.

Attachment D is the form to be used to assign performance objectives to responsible supervisors and to ultimately certify that all performance objectives for that supervisor's organization have adequately been met for restart.

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, e:

P g2 9 SQA191 Revision 1 Standard Practice 5.0 . INSTRUCTIONS (ccntinued)

Group supervisors must determine the level of review and 4 documentation necessary within their organization to provide

'themselves with adequate confidence to complete assigned performance objective reviews and evaluations.

~

B. Performance Obiective Evaluation Performance objectives are met by evaluating current organizations or programs against the defined criteria.

Successful completion of the criteria may be judged in some ,

cases by measurable attributes. In other cases, a supervisor must rely on subjective, judgments in lieu of quantifiable measurements. However, these subjective judgments may be minimized through proper techniques such as an effective sampling program. As an example, personnel commitment to follow instructions may be determined by questioning randomly selected employees concerning certain aspects of a complex work assignment. The evaluating supervisor must examine and document sufficient attributes to ensure that the criteria either has been met or an accurate listing of exceptions developed for each assigned criteria. Supporting documentation need not be attached to the criteria evaluation form (attachment E) but should be referenced on the form and retained by the responsible supervisor. An example of a properly evaluated and completed performance criteria is given in attachment F.

C. Performance Obiective Documentation When a criteria is determined to be met by the evaluation of current programs and personnel, the completed attachment E is processed through a review and approval cycle prior to becoming a part of the completed Operational Readiness documentation. The responsible manager's imediate supervisor will review attachment E and approve the results, performance objectives and criteria applicable to the major onsite matrixed organizations (Licensing, Modifications. Quality Assurance, Project Engineering) are assigned at the principal manager level. At his discretion, he may reassagn the " responsible manager" responsibilities to managers who report directly to him. In these cases, the principal manager would signify his review and concurrence by signature as the next higher level manager on the completed Attachment E form. Attachment E is then transmitted to the Operational Readiness Manager for concurrence and retention.

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P g3 10 SQA191 Revision 1 Standard Practice 5.0 INSTRUCTIONS (continued)

When criteria are evaluated and exceptions identified, corrective actions must be determined to resolve these exceptions. Each supervisor should then evaluate any exceptions against the restart criteria contained in reference 3.5. If the exception is determined not to be required for restart, the attachment E form is completed with appropriate justifiestion, reviewed, approved, and forwarded to the ORS. The responsible supervisor should retain a copy and disposition any exceptions not required ,

for startup in accordance with standard site procedures and practices.

If the supervisor determines that an exception must be addressed prior to restart, he then determines if the item should be added to the P/2 restart schedule. If the determination is made not to add the item to p/2 (can be completed in a relatively short duration with min,imum impact on other site activities), the supervisor transmits a copy of the partially completed attachment E to the ORS. The responsible supervisor retains the original attachment E until the exception is resolved. The attachment E is then completed, reviewed, and approved as previously described.

If the supervisor determines that an exception should be added to p/2 (because of significant scope, resources, or affect on other organizations), he should complete the required P/2 input sheets and note on the sheet that the item is from an ORS review. Planning and Scheduling (P&S) will then add the item to P/2 in a zone or range of zones specifically designated for ORS review. The supervisor should thtn send the partially completed original attachment E to the 0,'S. When the ORS verifies that the item has been added to p/2, the attachment E will then be closed.

When all performance objectives have been met for an organization or exceptions justified as not impacting restart, the ORS will contact the responsible organization manager for completion of attachment D. This attachment will serve as final documentation attesting that each site organization adequately meets performance objectives for restart.

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Pcg3 11 SQA191 Revision 1 Standard Practice 5.0 INSTRUCTIONS (continued) 5.3 Startup Checklist Plant instructions (GOIs, SOIs, etc.) and tracking systems (P/2 schedule) have been established to ensure that hardware issues directly impacting system operability are closed prior to mode changes. To provide additional confidence that these hardware issues are complete, a startup checklist will be developed and required items completed prior to heatup as a part of the Operational Readiness program. This checklist will be developed by the ORS and will serve to consolidate hardware operability 1 issues such as the following: -

• Maintenance or work requests backlog

• Outstanding clearances

• Modification status

• Temporary Alteration Control Forms (TACFs) outstanding

• Preventive maintenance packages outstanding

• Instrumentation availability

• Outstanding hardware related PROS and SCRs

• Special Tests During Startup The rtartup checklist will provide a structured completion signoff system by responsible managers for the above hardware issues and for specific NRC holdpoints. This checklist will serve as a part of the basis for entry into mode 4 and other designated milestones.

The ORS will develop a checklist and ensure that copies are distributed to affected managers and comments resolved. Dated signatures by responsible managers will be obtained directly in the checklist. When all signatures have been obtained on the checklist, the checklist will become a part of a supplement to the final operaitonal Readiness report. The checklist is to be included in Attachment H of SQA191.

6.0 OPERATIONAL READINESS REPORT FORMAT The corporate requirements document (reference 3.1) requires comprehensive reports in two phases. The initial report will be prepared when the following conditions are mett

• Performance criteria have been evaluated by responsible managers and exceptions identified.

• Major project / issue closure criteria have been developed and appreved by the site director.

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P:ga 12 SQA191 Revision 1 Standard Practice 6.0 OPERATIONAL READINESS REPORT FORMAT (continued)

This initial report will be comprised of the following information:

• A closure form for each SAL item closed at the time of issuance of the initial report.

• A completed attachment A form for each restart intention closed at the time of issuance of the initial report.

• A listing of SAL items and restart intentions with assigned

• responsible supervisors. ,

• Attachment G forms with closure criteria approved by the principal manager for each defined' major project / issue.

• Attachment E forms for performance criteria evaluations completed to the extent necessary to identify exceptions.

• A copy of the current startup checklist.

The final report will be prepared following completion of the operational readiness review. The final report will be comprised of the following information:

• The closure forms for completed SAL items. Additionally, supporting forms listing the initiating and implementing documents supporting principal manager signatures will be included.

• Completed attachment A forms for each restart intention.

• Completed attachment G forms for each defined major project / issue.

• Completed attachments D and E forms for all assigned performance objectives and criteria.

• The current startup checklist.

Since closure of some SAL items and completion of the startup checklist is tied to conditions after entering mode 4, a supplement to the final report may be prepared to include this information.

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P g2 13 SQA191 Revision 1 Standard Practice 6.0 OPDtATIONAL READINESS REPORT FORMAT (continued)

In addition to the comprehensiva corporate reports, progress reports

'will.be provided to the site director. These progress reports should be given every two weeks following issuance of this standard practice until issuance of the final corporate report. These biweekly reports may be presented in the site director's staff meeting. The biweekly progress report will contain the following information:

• Percentage completion rates for SAL, restart intentions, and major project / issue closure. ,

• A listing of major projects / issues closed under operational readiness requirements. ,

• Percentage completion rates for performance criteria (site encompassing and by organisations).

• A listing of organisations that have completed all assigned performance objectives'and criteria.

• A listing of areas of concern identified in evaluation activities.

• Progress made in startup prerequisite verification activities..

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P:93 14 SQA191 Revision 1 ATTACHMENT A RESTART INTENTION CLOSURE Date Initiated:

Intention ID No. Volume II Reference (Section, Page):

Intention description:=

Responsible Manager:

Criteria and Justification for Closure:

Exceptions and Justification for Restart with Exceptions:

Restart Intention adequately Review and Concurrence closed and documented for startup:

Responsible Manager /Date Next Higher Level Manager /Date Concurrence:

Operational Readiness Manager /Date C2885/vle

P ga 15 SQA191 Revision 1 ATTACHMENT B Page 1 of 7 GENERIC PERFORMANCE OBJECTIVES

1. Performance objective: Procedures or instructions not specifically

. addressed by a SAL item are adequate and are properly implemented to support restart.

Criteria

• A. Assigned instructions required for restart, as identified on the procedures tracking system printout, have been completed. .

• B. Instructions on the procedure tracking system printout required for restart have been revised or supplemented to reflect organizational changes.

C. First-line supervisors as well as foremen personally observe and discuss the performance of four or more instructions being used by their employees to verify the following. -

• Latest controlled copy being used.

• Personnel are following all instruction requirements.

• Personnel observed know when and how to initiate instruction changes.

• Personnel understand technical requirements of the instruction as evidenced in correct work performance.

• Personnel follow or are knowledgeable of applicable work practices and requirements in the areas of industrial safety, radiological controls, security, and quality assurance.

NOTE: DNE should use their established tracking system / process for evaluating criteria.

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Pag 3_16 SQA191 Revision 1 ANACHMENT B Page 2 of 7

2. Performance objective: Staffing and supervisory involvement are adequate to support restart.

Criteria A. Vacant positions critical to your organization for restart have been identified and filled.

B. Supervisors will obsecve, on a daily basis, a specific assigned '

work activity being performed by their personnel. '

C. A meeting with group personnel is held and documented to ensure responsibilities and interfaces are clearly understood, to review the impact of startup on section activities, and to ensure that proper work ethics are understood (work time, breaks, lunch, leave, etc.).

3. NRC violations, CARS, and INPO findings have been properly evaluated for impact on restart.

A. NRC violations, CARS, and INPO findings identified since issuance of the SNPP Vol. II have corrective actions identified.

B. Corrective actions for NRC violations, CARS, and INPO findings identified in A above have been evaluated for impact on restart and required restart actions completed.

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i pig 3 17 SQA191 Revision 1

, ATTACHMENT B Page 3 of 7

4. Performance objective: Assigned plant areas are maintained in a clean and orderly condition.

A. SQA 66 shall be rigidly adhered to.

B. Periodic safety inspections are performed and corrective actions completed as necessary.

C. Appropriate steps are taken to minimize C-zone areas required in'- .

the plant. These steps include minimizing fluid leaks, preplanning activities to minimize the spread of contamination, and implementation of an effective decontamination program to stabilize and reduce affected areas.

5. Performance objective: Support organization management controls and resources are adequate to support restart.

Criteria l-A. The support needed for startup has been identified to the

appropriate support organization.

B. Points of contact have been established between the organizations involved.

C. Reviews have been performed by the interfacing organizations to detenmine that procedures are correct and the working interface is understood for startup.

D. Support organizations are prepared to provide the identified support required for startup.

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P g2 18 SQA191 Revision 1 ATTACHMENT B Page 4 of 7 ,

FUNCTIONAL AREA PERFORMANCE OBJECTIVES Organization and Administration

6. Performance objective: Responsibilities and authority of management.

engineering, and foreman positions are clearly defined.

Criteria ,

A. Position descriptions (or job descriptions where appropriate) for management, engineering, and foreman positions have been written, approved, and are in place.

7. Performance objective: Document control systems provide correct, readily accessible information to support site requirements.

Criteria A. A document control system is in place which makes up-to-date, controlled procedures readily accessible.

B. A program is functioning which ensures that preparation, review, approval, and revision of procedures are properly controlled and applicable source requirements are incorporated.

Plant Doeration

8. Performance objectives: Generic Performance Objectives only.

Maintenance

9. Performance objective: Address the Nuclear Managers Review Group (NMRG) maintenance report recommendations applicable to site maintenance activities.

A. Actions to address NMRG recommendations for prior to restart have been completed.

Technical Support

10. Performance objectives: Generic Performance Objectives only.

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P g3 19 SQA191 Revision 1 ATTACHMDIT B Page 5 of 7 Training Support

11. Performance objective: Training commitment items required prior to restart of Sequoyah Nuclear Plant are identified, evaluated for completeness, and accomplished.

Criteria A. SQN restart training commitments are clearly defined. ,

B. Commitments are reviewed and status is determined.

C. Incomplete items are evaluated and an action plan developed to meet SQN restart schedule.

D. Training commitment items for startup are completed and documented.

l 12. Performance objective: Division of Nuclear Training (DNT) representatives will meet with appropriate site and/or plant supervisors to identify any mandatory training items (not previously identified) to be accomplished prior to restart in support of operational readiness.

Criteria A. Training required prior to restart is identified.

B. DNT will develop an action plan to any training item identified in (A) in order to meet the Sequoyah restart schedule.

C. Items identified as mandatory are completed and documented.

Radioloalcal Controls

13. Performance objectives: Generic Performance Objectives only.

Chemistry

14. Performance objectives: Generic Performance Objectives only.

Emergency Preparedness

15. Performance objectives: Generic Performance Objectiveso'nly, i

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P ga 20 SQA191 Revision 1 ATTACHMDC B Page 6 of 7 Licensing

16. Performance objective: NRC commitments required by restart have been addressed and completed.

Criteria A. NRC comitments communicated to NRC as restart commitments are complete. ,

B. NRC comraitments with "C" due dates which fall before restart have either been completed or a revised completion date negotiated with NRC.

Modifications (See Configuration Control)

Security

17. Performance objectives: Generic Performance Objectives only.

Quality Assurance

18. Performance objectives: Generic Performance Objectives only.

Engineering

19. Performance objective: A process is in place to ensure that engineering change packages are developed consistent with the plant's design basis and meet NRC requirements applicable to the plant.

Criteria A. Procedures are in place which control the development of design change packages:

B. The plant design basis for those systems or portions of systems identified within the scope of Phase I of the Design Baseline Verification Program is known, documented, and utilized in making plant design changes. ,

C. Personnel are trained and have adequate knowledge an the design change process, the plant as-constructed conditio:., and design bas 44 documents.

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P;g) 21 SQA191 Revision 1 ATTACHMENT B Page 7 of 7

20. Performance objective: Provisions made for expedited plant support needed to satisfy limiting conditions for operation.

Criteria A. USQD preparation for TACFs B. Safety evaluations for unexpected situations l C. ECN processing on an expedited basis consistent with plant operating,.

needs D. Methods developed for providing a modification design in less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Inservice Inspection 1

21. Performance objectives: Generic Performance Objectives only.

l Surveillance

22. Performance objectives: Generic Performance Objectives only. This area is addressed more fully under the SI Technical Review Program as described in Volume II.

Configuration Control

23. Performance objective Plant design change / modification programs will ensure proper review, control, implementation, and completion of plant design changes in a safe and timely manner.

Criteria A. Site procedures which define, implement, control, and close all activities associated with the design change process for restart are in place with interfaces established and understood.

B. Programs are implemented to appropriately order, receive, and issue materials and equipment for plant maintenance and modifications which meet design specifications and quality assurance requirements.

C. A minimum set of primary control room drawings shall be specified and in place which represent the as-constructed condition of the plant at restart.

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$04195 sevisten 1 ATTAOeENT C Page 3 of 3 w fernance OhJ. Sitt_Dirstter onsite_ Support A triteria GPS ISS CLtl Ba0 !!LG !!1G l'E TBS !!EE tEL 20R ISS ffS ELE ELS ERS tEi1 LCE SSE M M

• LIC 508 tENI E50 255 LA lO.A X s X C

• 29.A X 3 X C X 3 X

21. (None)

22. (none) 23.A X X X X X X X X X X 3

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-sor Operational Readiness. the P0YC is considered an enstte support organization for those portions of their orpenlaation that prowlde training support to "co nyah.

e 32a95/Olc

d>  ;-

P;g3 25 SQA191 ,

- Revision 1- 1 p'

' ' Rev. 3

+ -

ATTAC10EIC D ~

, PERFORMANCE OBJECTIVES 4

i'

1. Organization: -- - -

- 2. Responsible Manager: /

\

Attachment D.1 contains the performance objectives that must bz met to *

? demonstrate operational readiness. Completion of attachasst U '

substantiates that individual performance objectives have both' mat,or, exceptions justified for restart.

. p.-

All performance objectives for this organization have been met or except1'ons,

• justified for startup. .

j 3. Responsible Manager:

Date 1

4. Reviewed & Concur:

Next Higher Lg tel Manager Date ,

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Pcg2 27 SQA191 Revision 1 Transmitted

, Update ' '

1. Returned ATTACHMENT E s PERFORMWCE AND EVALUATION

1. Organization: ,_

2. . Responsible Manager: ,.

3. Perfomance Objective:

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4. Criterion:

5. Statement of how performance compared against criterion or how performance

' was evaluatid (supporting documentation should be referenced) (attach

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6.' Prepared by: Date Responsible Manager 02885/vle

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P g2 28 SQA191 Revision 1 A17ACHMENT E (continued)

7. Exceptions and Evaluation of Impact (attach additional sheets if necessary):

8. Corrective Action to Resolve Exceptions (attach. additional sheets if necessary):

9. Restart? (Y/N) 10. Schedule for Corrective Action if restart

11. Submitted to P&S (Y/N) 12. P/2 Zone

• _

13. Criterion met or exceptions justified 14. Review and Concurrence:

for restart.

I Responsible Manager /Date Next Higher Level Manager /Date

15. Concurrence:

• 0perational Readiness Staff to Operational Readiness Manager /Date obtain from P&S.

, 0288S/vle

P192 29 SQA191 Revision 1 ATTACEMD.T F Page 1 of 3 P

DULMPLE PERFORMANCE CRITERIA EVALUATION i

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• ^' - - - -

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• ATTACP. MENT F Tec2ctitted Page 30 Opdato # -

Page 2 of 3 R3 turn ;d SQA191 '

ATTACHMENT E R; vision 1

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PERFORMANCE AND EVALUATION

1. Organization: Cb e mISNia J

2. Responsible Manager: h." It" [4 MS

3. Performance Objective: M. , Sin I-+' Ira a el 'u turi //-:ord /n v,. ',9.mni U * -J Ot ra tukrs% nuskt' Yo <v413orf' resl0 r .

4 4 Criterion: 4. N e a rd' I

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5. Statement of how performance compared against, criterion or how performance was evaluated (supporting documentation should be referenced) (attach additional sheets if necessary):

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6. Prepared by: /##e [-[ ' / /d A 6 Responsible Manager / Dat,e 0177H

ATTACHMENT F Paga 31 Page 3 of 3 SQA191 ATTACHMEflT E (centinu:d) RIvision 1

7. Exceptions and Evaluation of Impact (attach addition 11' sheets if necessary):

Fillino fAe f..o v.ua nt c e<lflom idsntl?ied in J /

wet 5 has ben de teem;ne$ not to b e rua utreA I

-fo y re< h i. Y hif Yo!e emlnk's A is bzfel w J/W:m) ~ n,ae n K s m et avs 6 %

,) 6' f Befe< . /fAenri<fra3 nsoa r<s m Ma na e o r . <>b es is eaxerenfle eJ .' c h rl I/ .

8. Corrective Action to Resolve Exceptions (attach additional sheets if necessary):

Y ko lefo nf hed vneancies rol/l he C thol , 4._,7 s ea n$ n va nt$ liEm .

8

9. Restart? (Y/N) k! 10. Schedule for Corrective Action if restart A//A

11. Submitted to P&S (Y/N) A[ 12. P/2 Zone * /4

13. Criterion met or exceptions justified 14. Review and Concurrence:

for restart.

W ~

Responfible Manager /Date //

H /

Next Higher Level Manager /Date l

15. Co urrence:

/ 8 I 94

• Operational Readiness Staff to Operat i orrini ReaFjessManage//Ddt'e obtain from P&S.

OlI7H/atr

~ . . . _ _ _ ,

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Piga 32 SQA191

- - Revision 1

. ATTACHMENT G MAJOR PROJECT / ISSUE CLOSURE

~ Date Initiated:

. Project / Issue

Description:

Responsible Manager:

Closure Criteria (attach additional pages as needed):

f a

Preparation of criteria: Approval of Criteria:

/ /

Project Manager Date Principal Manager Date Basis for Project Closure (attach additional pages as needed):

Exceptions and Justification for Restart with Exceptions (attach additional pages as needed):

4 Project / Issue closed for Restart: Concurrence:

Responsible Manager /Date Principal Manager /Date 0288S/vlc i-1 2

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.,8; ,e* .. P2g:2 33

, . APPENDIX A SQA191 -

Rzvision 1 OPERATIONAL READINESS STAFF .,

SITE DIRECTOR ONP OPEkATIONAL

- - - - READINESS MANACEl.

H. L. Abercrombie R. Matheny SQN OPERATIONAL .

READINESS MANAGER i

T. D. Knight i

, TRACKINC REPORTS ADP COORDINATOR C. E. Callaher.

l -

l l VOL. II PERFORMANCE STARTUP l

IMPLEMENTATION OBJECTIVES PREREQUISITE COORDINATOR COORDINATOR '

CHECKLIST T. D. Knight K. Jones D. King r

l SAL ITEE5 COORDINATORS * (11)

I p

I l

l l VOL. II INTENTIONS -;

T. D. Knight 1 s

• Coordinators will be selected whose combined knowledge and experience cover the attached MA.}OR PROJECTS areas. Coordinators may be assigned to more than one area and may have other operational

.. readiness duties. -

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PIga 34 SQA191 Revision 1 APPFEDIX A (continued)

PERFORMANCE OBJECTIVES STAFFING WILL SUPPORT THE FOLLOWING AREAS AREAS Operations Project Management Radiological Controls Financial Planning Public Safety Employee Concerns Staff Technical Support Procedures Staff -

Chemistry PSO Maintenance Licensing

> Industrial Safety

• Modifications PORS Quality Assurance Site Services Engineering Personnel Training Planning and Scheduling STAFFINS Functional Assienments Number Vol. II Implementation 3 Performance Objectives 11 Startup Prerequisite Checklist 1 Tracking, ADP, Reports 1 Clerical 1 Total Staffing Number Required 12 l

t 1

0288S/vic i

I

P2g3 14 SQA191 Revision 1 ATTACHMEhT A RESTART INTENTION CLOSURE Date Initiated:

Intention ID No. Volume II Reference (Section, Page):

Intention description:

Responsible Manager: .

Criteria and Justification for Closure: -

l Exceptions and Justification for Restart with Exceptions:

l i

Restart Intention adequately ' Review and Concurrence:

closed and documented for startup:

Responsible Manager /Date Next Higher Level Manager /Date Concurrence:

Operational Readiness Manager /Date 0288S/vic

SCHEDULE OVERVIEW 2/5/87 I. Schedule Overview A. P/2 schedule restart date B. List of significant items not fully considered or detailed in current P/2 schedule update II. Projected Restart Date A. Current view B. Timetable to provide the results of the current schedule assessment III. Significant Issues A. Ampacity B. DB&VP Punchlist C. Employee Concerns D. Procedures eSI

. Site

• Corporate E. Component and Piece Part Replacement Program F. Raychem G. Fuses l

IV. Summary A. Restart Date B. Management Strategy 0260D/ms i 2/4/87  !

l l

• a Ma NRC MEETING FEBRUARY 5,1987 SEQUOYAH ENVIRONMENTAL QUALIFICATION (10CFR50.49) o PROGRAM SCOPE INCLUDES DOCUME3TATION OF EQUIPMENT QUALIFICATION TO THE REQUIREMENTS OF 10CFR50.49 AND THE IMPLEMENTATION OF ANY REQUIRED FIELD CORRECIVE ACTION. THE PROGRAM SCOPZ IS WELL DEFINED AND HAS BEEN REVIEWED BY NRC- -

o PROGRAM IS SUBSTANTIALLY COMPLETE WITH SOME OUTSTANDING TECHNICAL ISSUES TO BE RESOLVED- AND FIELDWORK TO BE IMPLEMENTED. NRC HAS REVIEWED PROGRAM IN DETAIL (NOVEMBER- 18-22, 1985, JANUARY 6-17 FEBRUARY 10-14, JUNE 23-27 AND DECEMBER 8-12, 1986) AND HAS ISSUED A DRAFT SER ON EQUIPMENT QUALIFICATION.

o KEY MILESTONES 4

10CFR50.49 CERTIFICATION LETTER. INCLUDING RESPONSE TO SER CONFIRMATORY ITEMS -- TARGET DATE FEBRUARY 20,1987 NRC FOLLOW-UP INSPECTION OF EQ - TVA RECOMMENDS MID-MARCH ALL PRESENTLY IDENTIFIED EQ FIELDWORK (EXCLUDING AMPACITY ISSUE)

SCHEDULED'TO BE-COMPLETE MID-MARCH TIMEFRAME PER P2.

i .,

FS7035.01 1

, , . . . - . ___-_~ ..-.. . . _ _ . . _ . _ ,....-m., , . , . . , y__. - _ _ _ -_ -_. . _ _ , - _ -. . . . _ - , - _ , , . _ _ , . , , . , _ _

PROJECTED PROGRAM STATUS AT TIME OF 10CFR50.49 CERTIFICATION LETTER (FEBRUARY 20, 1987)

TECHNICAL ISSUES TO BE RESOLVED FOR 10CFR50.49 COMPLIANCE

1. DETERMINE QUALIFICATION REQUIREMENTS FOR CONTAINMENT COOLING FOR CERTAIN OUTSIDE CONTAINMENT-EVENTS (SCR SQNNEB8616)

2. REVIEW OF PIECE PARTS PURCHASED AS QA LEVEL II FOR 10CFR50.49 EQUIPMENT CONFIRMATORY ITEMS FROM DRAFT NRC SAFETY EVALUATION REPORT (1) RESOLUTION OR STAFF APPROVAL OF THE MAIN STEAM LINE BREAK WITH SUPERHEAT RELEASE AND ITS EFFECT ON THE ENVIRONMENTAL QUALIFICATION OF EQUIPMENT IN- THE- EAST AND WEST VALVE VAULT ROOMS ( A1, A2, A10. All) i CURRENTLY UNDERGOING NRC STAFF REVIEW. TVA CONSIDERS THIS TO BE COMPLETE AS A TECHNICAL ISSUE (PENDING COMPLETION OF NRC REVIEW)

(2) ALL EQ FIELDWORK COMPLETE EXCEPT FOR OPEN FIELDWORK LISTED OR NEW WORK RESULTING FROM UNRESOLVED TECHNICAL ISSUES (3) MAIN STEAM VAULT SUBMERGENCE REVIEW TECHNICAL ISSUE IS RESOLVED AND ISSUE IS COMPLETE EXCEPT FOR OPEN i

FIELDWORK LISTED (4) MANAGEMENT REVIEW OF EQ BINDERS COMPLETE 4

(5) SUPPLEMENTAL VENDOR INFORMATION COMPLETE I

(6) CABLE LOAD STUDY

, COMPLETE

{ (7) INSIDE CONTAINMENT FLOOD ANALYSIS FOR 5-MINUTE OPERABILITY 1 -

COMPLETE (8) VERIFICATION OF INSTRUMENT ACCURACY CALCULATION l -

COMPLETE j - ( 9) FINALIZATION OF THE EQ MASTER LIST COMPLETE FS7035.01 l

, - _ _ _ _ _ - z__. _ _ . . _ _ _ _ _ . _ . _ _ . _ _ . _ _ _ _ , . , _ _ _

PROJECTED PROGRAM STATUS AT TIME OF 10CFR50.49 CERTIFICATION LETTER (FEBRUARY 20. 1987) 1 REMAINING FIELDWORK FOR 10CFR50.49 COMPLI ANCE Unit 1/ Unit 2 SEAL CONDUITS BELOW FLOOD LEVEL IN MAIN STEAM VALVE VADLTS X X AND AUXILIARY BUILDING (SCRs SQNEQP8619 AND SQNEQP8621)-

REPLACE CELLULOSE-FILLED TERMINAL BLOCKS WITH MINERAL- X X FILLED BLOCKS- (SCR SQNEQP8622)

REPLACE CABLE FOR DAMPER OPERATOR DUE TO DEGRADED VOLTAGE X "X (SCR SQNEEB8532)

FIN ALIZE QMDS IMPLEMENTATION INCLUDING INSTALLATION OF NEW X X PUMP AND MOTOR ON H ANALYZER.

2 CHANGE SETPOINTS FOR TS-1-17A AND B, -18A AND B X X (SCR ' SQNEEB86198) FT-72-13, -34 (SCR SQNEQP8615), AND X X TS-74-43 45, -46 (SCR SQNEEB8684) X X PROVIDE ISOLATION OF CERTAIN CATEGORY C DEVICES AND UPGRADE I X AND -REPLACE OTHER CATEGORY C DEVICES DUE TO THE-INTERACTION STUDY OF CATEGORY A AND CATEGORY C DEVICES (SCR SQNEEB8637,

' SCR SQNEEB8642 SCR SQNEEB8678, AND SCR SQNEEB8679)

RELOCATE STEAM GENERATOR'PORY SOLENOIDS OUTSIDE THE VALVE X X

VAULT (SCR SQNNEB8314)

REPLACE UNQUALIFIED TERMIN AL BLOCKS (SCR SQNEQP8521) X X RELOCATE FOUR SOLEN 0ID VALVE ARC SUPRESSION NETWORKS X X (SCR SQNEQP8618)

MODIFY ICE CONDENSER DRAINS FOR IN CONTAINMENT SUPERHEAT I X (SCR SQNNEB8316) -

REPLACE CABLES BASED UPON REVISED AMPACITY TABLES X X REPLACE CABLES AND REFURBISH EQUIPMENT IN MAIN STEAM VALVE X X VADLTS DUE TO LOCALIZED HIGH TEMPERATURES (CAR 86-03-016) l * -

FIELD VERIFY SPLICE CONFIGURATIONS AND REPAIR AS NECESS ARY X X (IE Notice 86-53)

REGEAR 1-FCV-1-18 AND 2-FCV-1-17 (PIR SQNMEB86108) X X l -

COMPLETE WORK ON VARIOUS CONCERNS FOR LIMITORQUE OPERATORS X (E.G. , REGEAR, FIN AL FIELD VERIFICATION, REWIRE, REPLACE I

MOTORS)

COMPLETE MINOR WORK ON LIMITORQUE OPERATORS ON MFIVs X (ECNs L-6676 AND L-6611) l -

REPLACE (2) UNQUALIFIED CABLES INSIDE CONTAINMENT X l (SCR SQNEQP8542)

• SIGNIFICANT FIELDWORK INVOLVED l

I i

l FS7035.01 i

e.

POTENTIAL PROBLEMS ASSOCIATED WITH KEY MILESTONES PIECE PART REVIEW TASK FORCE FORMED TO ADDRESS ISSUE NRC IS REVIEWING PROGRAM, INCLUDING SCOPE AND METHODOLOGY WILL NRC ISSUE SER ON PIECE PARTS ISSUE 7 STELLO PLAN IDENTIFIES IBIS AS A SEPARATE ISSUE.

- THUS, THIS SHOULD BE TREATED AS A SEPARATE ISSUE FROM EQ SCR SQNNEB8616 - CONTAINMENT COOLING FOR EVENTS OUTSIDE CONTAINMENT

- SCHEDULE FOR REVISED CATEGORY AND OPERATING TIMES AND REVISED CONTAINMENT TEMPERATURE PROFILE IS FEBRUARY 20, 1987. THIS WILL COMPLETE THE TECHNICAL ISSUE DEFINITION AND AT THAT POINT, TVA WILL BE ABLE TO BETTER DEFINE ANY POTENTIAL SCHEDULE IMPACTS BINDER REWORK WILL BE REQUIRED TO ACCOMODATE CHANGES. THESE BINDER CHANGES WILL BE EXECUTED IN SAME CONTROLLED PROGRAM AS ALL OTHER EQ DOCUMENTATION. IMPACT ON FIELDWORK NOW UNKNOWN, BUT NOT EXPECTED TO BE SIGNIFICANT.

• SIGNIFICANT REMAINING FIELDWORK - SIXTEEN UNIT 2 ITEMS LISTED BUT ONLY THREE SIGNIFICANT MODIFICATIONS FOR MSVV AREAS OF HIGH LOCAL TEMPERATURES SCHEDULE

! FOR COMPLETION MARCH 2 1987

- CORRECTION OF RAYCHEM SPLICE INSTALLATION SCHEDULED FOR COMPLETION

MARCH 15,1987 l

REPLACEMENT OF 10CFR50.49 CABLES DUE TO AMPACITY CONSIDERATIONS - ,

NEW CABLE BINDERS MAY BE REQUIRED ,

CONFIDENCE LEVEL OF EO PROGRAM EXTENSIVELY REVIEWED INTERNALLY NRC HAS REVIEWED PROGRAM IN-DEPTH NRC HAS ISSUED DRAFT SER WITH NINE CONFIRMATORY ITEMS WHICH ARE ESSENTIALLY COMPLETE EXECUTION OF PROGRAN IS SUBSTANTIALLY COMPLETE OPEN ISSUES CLOSELY TRACKED THROUGH RESOLUTION. IDENTIFIED TECHNICAL ISSUES ARE NOT INDICATIVE OF EQ PROGRAM WEAKNESSES BUT ARE ITEMS WHICH IMPACT EQ PROGRAM. THESE ARE BEING RANDLED IN THE CONTROLLED PROVISIONS OF WHAT TVA BELIEVES TO BE A SOLID EQ PROGRAM.

ONLY A LIMITED NUMBER OF ISSUES PROJECTED TO BE OPEN AT TIME OF CERTIFICATION LETTER AND FOLLOW-UP INSPECTION FS7035.01 l

RAYCHEM Scope Evaluate all 10CFR50.49 Raychem applications and all Class IE ponetration pigtall Raychem applications.

If the evaluation could not substantiate application as required by Raychem or as type-tested by TVA, the Raychem will be replaced or repaired as necessary.

This is projected to affect approximately 900 cables with an average of four conductors per cable.

Milestones Completion of All Rework: March 24, 1987 Closeout of Unit 2 portion of CAR: April 17, 1987 Completion of rework may be impacted by TVA's inability to remove the penetration pigtail outer jacket in a timely manner. TVA is presently pursuing methods to reduce the duration of this activity, program Features

1. All 10CFR50.49 Raychem applications will be evaluated as qualified or will be replaced.

2. A splice database will be created to document composition of splices.

3. Greater emphasis on craft training, attention to detail, and control of Raychem application.

Issue Closure If an inspection of issue resolution is required I recommend it be conducted in conjunction with the environmental quality (EQ) program inspection proposed for March 13, 1987. Full implementation will be confirmed as part of the closure of the EQ program confirmatory items.

MRS:DBB 2/5/87 0612E

0A ISSUES KEY ON "STELLO PLAN"

'S SPECIFIC ITEMS ON QA'S PLATE MANAGEMENT INVOLVEMENT

1) NRC ORDER EA 85-49 NEW CAQ PROGRAM BEING IMPLEMENTED -

DRAFT LETTER ASKING NRC CLOSURE FOR SQN STARTUP MAJOR TRAINING PROGRAM UNDERWAY STELLO PLAN DATES ACCEPTABLE l

• STELLO PLAN, SUBJECT AREA: MANAGEMENT INVOLVEMENT, l

MAJOR TASK 6 (PAGE 21)

+

OA ISSUES

/

QA AUDITS

2) CORRECTIVE ACTION CLOSING SIX FOLLOW ITEMS (CAR DEVIATIONS)

DRAFTING LETTER TO NRC DESCRIBING ACTION TAKEN--MANAGEMENT MEETINGS, DIRECTIVES CONCERNING CAR RESPONSIVENESS IN PARTICULAR AND QA IN GENERAL "STELLO PLAN, SUBJECT AREA: CORPORATE ACTIVITIES, IV QA l AUDIT, ITEMS 3 AND 4 (PAGE 30) l f

'9 QA_LSSUES ,

t.

QA PROGRAMS

3) TOPICAL REPORT NRC APPROVAL END OF JANUARY 1987 REV. 9 (APPROVED) TO BE PUBLISHED S00N NO FURTHER ACTION REQUIRED PRIOR TO RESTART "STELLO PLAN, SUBJECT AREA: QUALITY ASSURANCE PROGRAM, MAJOR TASK 1 (PAGE 31)

0A ISSUES i

QA PROGRAMS

4) INTERIM PROCEDURES NEPs VS. TOPICAL /NQAM EVALUATION IN PROGRESS '

~

DNC (MODIFICATIONS) PROCEDURE COMPLIANCE EVALUATION UNDERWAY l

l l

l

• STELLO PLAN, SUBJECT AREA: QUALITY ASSURANCE PROGRAM,

( MAJOR TASK 4 (PAGE 31) l l

l l

e QA ISSUES QA PROGRAMS

/

5) CORPORATE & SQN QA PROGRAM IMPLEMENTATION 2 INSPECTOR FOLLOW ITEMS (NEPS & ONE MINOR 4

SQN ITEM) l R II TO INSPECT AGAIN 2/17 AND 3/2 l

l

• STELLO PLAN, SUBJECT AREA: QUALITY ASSURANCE PROGRAM, MAJOR TASK 6 (PAGE 31)

. .. . , - . _ _ _ . ... - - - _ _ . - . - - _ = . _ .

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9 Status of Evaluations e ALL BUT 15 REPORTS ARE SUBMITTED Category No. Reports Action EN 8 5 require revised corrective action by SQN 3 require action by ECTG 2 SQN can respond I final issue stage MC 3 All require revised corrective action by SQN QA 2 All require revised correcti,ve action by SQN

> WE 2 All require revised corrective action by SQN

• All restart corrective actions are scheduled

- Projected SQN completion: 3/21/87

- ECTG closure: 4/1/87

- Closure documented on CATD 1

i l

- ~ -

, .-e- e w. - - - - - - ~ - - - - - - -r-~n.- -~, - - , , , , . - , . - - - ,e, ,_ .--,,,n-.. -

O to STATUS OF PROGRAN ISSUES Resolution of Outstanding Comments Programmatic review of OP reports - 2/7/87 completion Enhanced communication on specific comments Revision to restart report documentation as needed

- Watts Bar Evaluation Status ,

MC and C0 complete OP - 2/14/87 forecast completion WE - Weld Task Group Program QA and EN - All issues were applicable to SQN (WBN evaluations underway)

Technical Issues / Employee Concern e Keyword search (2/6/87 submittal) e Draft SER review e Group leader review of concern list SON Final Report

! e Discussed with NRC 12/16/86 e Revision 2 in review e Submittal by 3/15/87 l

a NAJOR NRC/TVA COORDINATION ITEN Feedback to Baployees e Facilities in place e TVA process in place e March 2, 1987 implementation?

l t

i l

l

Watts Bar Nuclear Plant P. O. Box 800 Spring City, Tennessee 37381 Nr. Hugh L. Thompson, Jr.

Director Division of Licensing Office of Nuclear Regulatory Regulation 7920 Norfolk Avenue Bethesda, Maryland 20814

Dear Mr. Thompson:

Enclosure I transmits an updated to the internal status report which provides the dates that the initial and/or final element reports for Sequoyah Nuclear Plant were submitted to the NRC. This transmittal is provided to assist you in scheduling completion of the Sequoyah employee concern effort. Enclosure 2 provides an updated forecast completion of the reports not yet finalized.

Please telephone Martha Martin at (615) 365-3587 (Watts Bar) if you have any questions.

Very truly yours, l TENNESSEE VALLEY AUTHORITY J. A. Mcdonald Watts Bar Nuclear Plant Site Licensing Nanager l ENC: ENC l

cc (See page 2.):

l i

i

_ _ - , _ _ . .m..-.. .. . _. _ , . , _ __, ,. , _ . . _ . _ . - _ . - , - . , , _ . - - . , - . . . _ , _ _ _ _ . , , , _ . . - , , , , - . _ - - . _ , _ _ . , _ , . . . . . - . , - , _ , . ,

e s . . ...: *

- w 2 .

. U.S. Nuclear Regulatory Comunission - ,

a cc (Rnclosures): _ .

Mr. James N. Taylor Director je Office of Inspection and Reforcement ,

U.S. Nuclear Regulatory Courissica s

Washington, D. C. 20555 U.S. Nuclear Regulatory Censsission 't-i

. Region II Atta: Mr. Gary Zech -

101 Marietta Street,.NW, Suite 2900 Atlanta,~ Georgia 30323 t ,

Nr. B. J. Youngblood, Profast Director

!. PWR Project Directoratch#4' ~'

Division of PWR Licensing A 4

U.S. Nuclear Regulatory Comeission l 7920 Norfolk Avenue Room 440, 5 Story Phillip0

~

Bethesda, Maryland 20814 ,

Mr. B. D. Liaw, Branch Chiof -

! U.S. Nuclear Regulatory Commission

, 7920 Norfolk Avenue .

Room T-1132 /

. Bethesda, Maryland 20814 ,

. Mr. Steve Richardson

. U.S. Nuclear Regulatory Comunission  ;-/

7920 Norfolk Avenue /

l' #/,

l Room T-1132 / -

Bethesda, Maryland 20814 [

.g RINS, NR 4N 72A-C'(Encicoures retained by RCTG.) > j N. L. Abercronble, Sequoyah ONP cy

! W. R. Brown, Jr., RCTG, Watts Bar ONP (w/o enclosures) ,, # (' )" '

i R. C. Denney, DSC-P, Sequoyah ONP (w/o enclosures) "

R. L. Gridley, LF SN 1578-C J 'i N. Narding, Sequoyah ONP ,

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SEQUOYAH RESTART Et.EEENT REPORTS n

')i CATEGORY CONSTRUCTION

.i UPDATED 02/06/87 N.

k%

, NRC e n REPORTS ,

INITIAL - FINAL CATD \k , y C010107 031186 101586 0 I

}[

C010307 102086 112086 1 '

C010501 NONE 101586 0 4

i- C010504 091186 101586 0

> C010505 n 091186 101586 0 C010603 111786 122486 2 C010703 111786 122486 3 C010900 091786 012987 9 RESTART C011101 091186 11d586 1 C011102 091086 101586 0 C011103 092586 122,486 3 RESTART C011106 120986 010287 1 e ,

J C011202 091186 101586 0

'- , d C)11203 101586 110586 1 RESTART C011206 NONE 102486g 0

, C011207 091786 101586 0 C011301 111786 010987 8 C011302 091186 101586 0 I C011305 091186 122486 3 C011306 092586 121686 1 C015101 091186 101586 1 4

C015102 091186 101586 0 C015105 091186 101586 0 C015109 NONE 101586 0 C017101 NONE 101586 0

.).

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4 SEQUOYAH RESTART ELEMENT REPORTS CATEGORY C04STRUCTION UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD C017105 091186 012987 2 RESTART C017301 101586 011387 2 RESTART C017303 101586 020587 1 RESTART C017304 091186 010287 2 C019101 NONE 110586 0 C019201 101586 020587 6 RESTART C019203 101586 011387 3 2840T 4

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2

SEQUOYAH RESTART ELEMENT REPORTS CATEGORY ENGINEERING UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD EN20101 010287 012687 1 RESTART EN20103 121086 011587 1 RESTART EN20104 NONE 122286 0 EN20105 NONE 012687 4 RESTART EN20106 NONE 010987 0 EN20302 NONE 122486 0 EN20303 010887 012987 4 RESTART EN20401 NONE 011587 0 EN20402 NONE 011587 0 EN20403 NONE 011587 0 i

EN20404 NONE 011587 0 EN20405 NONE 011587 0 EN20406 NONE 011587 0 EN20407 NONE 011587 0 EN20408 NONE 011587 0 EN20409 NONE 011587 0 EN20411 NONE 011587 0 EN20501 121786 012087 2 RESTART EN20502 121786 011587 1 RESTART EN20503 NONE 122486 0 EN20504 NONE 020587 6 RESTART EN20601 3 RESTART EN20702 NONE 012687 0 EN20703 NONE 122486 0 EN20704 NONE 122486 0

SEQUOYAH RESTART ELEMENT REPORTS

,- CATEGORY ENGINEERING

- UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD EN20801 NONE 0102d7 0 EN20901 112486 012787 1 EN20902 112486 012787 1 EN21001 NONE 012687 0 EN21002 NONE 020587 1 RESTART EN21202 NONE 122486 0 EN21301 112086 011587 2 RESTART EN21302 NONE 122286 0 EN21303 121086 012987 3 RESTART EN21304 NONE 010287 0 EN21501 NONE 111786 0 EN21502 NONE 012987 2 RESTART EN21506 NONE 012987 3 RESTART EN21509 110586 1 RESTART EN21510 NONE 111786 0 l EN21801 NONE 122486 0 l

[ EN21804 NONE 011587 1 RESTART L EN21807 122286 1 RESTART EN22001 NONE 011387 1 I EN22003 122286 011587 1 l

[. EN22011 110586 010287 1 RESTART l

EN22102 NONE 010287 1 EN22106 NONE 010287 1 RESTART EN22110 112086 010287 1 RESTART EN22202 121086 012987 1 EN22203 112086 010287 1

O SEQUOYAH RESTART ELEMENT REPORTS -

CATEGORY ENGINEERING UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD EN22205 NONE 012687 1 RESTART EN22206 110586 012087 2 EN22301 NONE 012087 3 EN22302 NONE 010287 0 EN22303 121086 012787 1 RESTART EN22405 110586 112486 0 EN22500 NONE 112086 0 EN22600 121086 011387 3 EN22800 122286 012987 3 RESTART EN22901 010287 012687 1 RESTART EN22902 NONE 122486 0 EN22905 NONE 122486 1 RESTART EN22906 NONE 012087 0 EN22908 NONE 011387 0 EN22910 NONE 012087 0 EN22911 010987 012687 0 EN22912 NONE 012087 0 EN23001 121086 012987 1 EN23005 120186 012687 2 EN23101 NONE 012687 1 EN23104 NONE 011387 1 EN23105 010287 012687 1 EN23106 NONE 012987 1 EN23202 NONE 111786 0 EN23203 111186 010287 0 EN23206 112086 112486 0

SEQUOYAH RESTART ELEMENT REPORTS

, CATEGORY ENGINEERING UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD EN23208 NONE 122286 0 EN23209 NONE 122486 0 EN23501 NONE 122486 0 EN23502 NONE 121086 0 EN23504 NONE 121086 0 EN23508 NONE 122486 0 EN23511 EN23701 010287 020587 4 RESTART EN23702 121786 012987 5 RESTART EN23704 010287 012987 2 RESTART EN23706 NONE 121086 0 EN23801 122486 4 RESTART EN23803 122486 10 RESTART EN23900 NONE 020587 4 RESTART EN24000 121086 4 RESTART EN24101 EN24102 122286 4 RESTART EN24103 NONE 122486 0 EN24104 NONE 121086 0 EN24105 EN24200 121786 4 RESTART EN24300 112486 011587 3 RESTART 2850T l

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- SEQUOTAH RESTART ELEMENT REPORTS

. CATEGORY OPERATIONS UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD OP30101 092386 112486 1 OP30102 '102186 010987 2 OP30105 091586 110586 0 OP30107 102186 112486 1 RESTART OP30108 102186 010287 1 OP30111 100786 110586 0 OP30112 090986 102486 0 OP30114 091586 112486 1

'l l OP30115 112486 6/ ret? 1 EESTART OP30201 102086 8/Jet 7 1 RESTART OP30202 111786 122286 1 RESTART OP30204 091586 111186 1 l OP30206 090986 102486 0 OP30301 NONE 102486 0 OP30302 110486 121086 2 OP30303 102086 111786 2 l

OP30305 102186 122286 2 RESTART l OP30401 110486 111186 1 I

OP30402 110486 112486 1 OP30403 110486 112086 3 RESTART OP30501 091586 010987 2 OP30601 102186 112486 2 OP30701 NONE 122486 0 OP30702 092386 111786 1 OP30704 NONE 122486 2 l OP30705 102186 122286 1 l

l v.- -- --.

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SEQUOYAH RESTART ELEMENT REPORTS CATEGORY OPERATIONS UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD OP30706 NONE 112486 1 OP30707 091586 102486 0 OP30708 NONE 102486 0 OP30711 NONE 112086 3 OP30713 102186 010987 2 RESTART OP30801 091586 110566 0 OP30802 120586 010987 3 RESTART OP30803 111286 010287 1 OP30804 NONE 122486 1 4 OP30805 NONE 112486 2 OP30806 102186 111186 0 OP30807 110486 010987 1 OP30901 NONE 112486 1 OP30905 102186 102486 0 OP31001 091586 111786 1 OP31002 092386 111786 1 OP31003 110486 111186 1 OP31101 091586 010987 1 OP31102 090986 011387 0 OP31103 092386 111186 1 OP31104 110486 111786 1 OP31105 NONE 010287 4 OP31106 111286 010987 1 OP31201 090986 102486 0 OP31204 091586 102486 0 OP31208 100786 102486 and 020587 0

a as S

SEQUOYAH RESTART ELEMENT REPORTS CATEGORY OPERATIONS UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD OP31211 102186 112486 3 OP31302 091586 102486 0 OP31303 092386 102486 0 OP31304 NONE 102486 0 OP31306 090986 011387 2 l i

OP31307 NONE 102486 0 j OP31309 NONE 112486 0 2843T f

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SEQUOYAH RESTART ELENENT REPORTS

, CATEGORY NATERIALS l UPDATED 02/06/87 l

l NRC i REPORTS INITIAL FINAL CATD NC40201 092986 010987 1 NC40206 091586 102486 0 NC40301 100386 110586 1

NC40302 092986 120986 1 ' RESTART NC40307 100386 110586 1 NC40400 102086 1

, NC40503 102086 110586 0

NC40510 091586 102486 0 4

- NC40512 100386 111786 1 RESTART NC40703 6 RESTART NC40705 NONE 110586 0 NC40709 120986 2 1

W 2851T e

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SEQUOYAH RESTART ELEMENT REPORTS

, CATEGORY QUALITY ASSURANCE UPDATED 02/06/87

~

NRC REPORTS INITIAL FINAL CATD QA80000 NONE 020587 1 QA80101 NONE 020587 1 RESTART QA80102 NONE 011387 and 010287 0 QA80104 NONE 102486 0 QA80201 012687 020587 3 QA80202 NONE 011387 2 RESIART QA80203 NONE 010987 and 020587 2 QA80205 NONE 011387 1 QA80303 011387 3 QA80401 NONE 121786 0 QA80402 NONE 010987 1 QA80404 NONE 111786 0 QA80501 NONE 012987 1 RESTART QA80503 01?987 6 QA80504 NONE 020587 0 2842T r

t 4

l

~

SEQUOYAH RESTART ELEMENT REPORTS

, CATEGORY SWEC ISSUES UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD SWEC-01 NONE 111786 0 SWEC-02 NONE 110586 0 SWEC-03 NONE 110586 0 SWEC-04 NONE 111786 0 SWEC-05 NONE 111186 0 SWEC-06 NONE 012987 0 SWEC-07 NONE 110586 0 SWEC-08 NONE 110586 0 SWEC-09 NONE 121086 0 SWEC-10 NONE 111786 0 SWEC-11 NONE 112086 0 SWEC-12 NONE 010987 0 SWEC-13 NONE 010987 0 SWEC-14 NONE 110586 0 SWEC-15 NONR 111786 0 SWEC-16 NONE 111786 0 SWEC-17 NONE 111786 0 SWEC-18 NONE 111186 0 l SWEC-19 NONE 112086 0 t SWEC-20 NONE 111786 0 SWEC-21 NONE 122286 0 SWEC-22 NONE 010987 0 SWEC-23 NONE 010987 0 SWEC-24 NONE 112086 0 i

SWEC-25 NONE 112086 0 l

SWEC-26 NONE 111786 0

SEQUOYAH RESTART ELEMENT REPORTS CATEGORY SWEC ISSUES UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD SWEC-27 NONE 122286 0 SWEC-29 NONE 010987 0 SWEC-30 NONE 010987 0 SWEC-31 NONE 111186 0 SWEC-32 NONE 110586 0 SWEC-33 NONE 011387 0 SWEC-34 NONE 110586 0 SWEC-35 NONE 112086 0 SWEC-36 NONE 122286 0 SWEC-37 NONE 111786 0 SWEC-38 NONE 111786 0 SWEC-39 NONE 111786 0 SWEC-40 NONE 112086 0

, SWEC-41 NONE 112086 0 SWEC-42 NONE 112086 0 SWEC-43 NONE 112086 0 SWEC-44 NONE 112086 0 SWEC-45 NONE 112086 0 SWEC-46 NONE 112086 0 SWEC-47 NONE 112086 0 SWEC-48 NONE 010987 0 SWEC-49 NONE 120586 0 SWEC-50 NONE 110586 0 SWEC-51 NONE 112086 0 SWEC-53 NONE 112086 0 SWEC-54 None 121686 0

SEQUOYAH RESTART ELEMENT REPORTS

, CATE00RT SWEC ISSUES UPDATED 02/06/87 NRC REPORTS INITIAL FINAL CATD SWEC-55 NONE 010987 0 SWEC-56 NONE 112086 0 SWEC-57 NONE 112086 0 SWEC-58 NONE 120586 0 SWEC-59 NONE 112086 0 2848T

SEQUOYAH RESTART ELEMENT REPORTS

, CATEGORY WELDING UPDATED 02/06/87 NBC REPORTS INITIAL FINAL CATD WP-01 091786 120986 0 WP-02 091586 120986 0 WP-03 091786 012787 0 WP-04 090386 120186 0 WP-05 090386 112486 0 WP-06 090386 112486 0 WP-07 090386 112486 0 WP-08 110586 012787 1 WP-09 090386 120986 0 WP-10 090386 112486 0 WP-11 090386 112486 0 WP-12 091786 120186 0 WP-13 090386 112486 0 WP-14 091586 112486 0 WP-15 091786 121686 0 WP-16 090386 121086 0 091786 WP-17 090386 112486 0 WP-18 110586 112486 0 WP-20 091586 112486 0 WP-21 111086 112486 0 WP-22 NONE 012687 0 WP-23 NONE 122486 0 013-001 NONE 120586 0 85-135 120586 012787 3 85-346 NONE 120586 0 85-373 NONE 020587 4

~

SEQUOYAH RESTART ELENENT REPORTS

. CATEGORY WELDING UPDATED 02/06/87

~

NRC REPORTS INITIAL FINAL CATD 85-560 120586 012787 2 ,85-636 NONE 120586 0 85-652 NONE 120586 0 85-735 NONE 120586 0 85-738 120586 012787 2 85-750 NONE 120586 0 85-756 NONE 120586 0 85-776 NONE 120586 0 86-115 120586 012787 1 088-003 NONE 120586 0 100-001 NONE 012087 0 101-006 020587 1 WP-19 110586 012787 0 WP-24 020587 0 WP-25 NONE 011587 0 2844T

A P

SEQUOYAH RESTART ELENENT REPORTS

- CATEGORY NSRS UPDATED 02/06/87 '

NRC REPORTS INITIAL FINAL CATD NSRS-01 122386 013087 RESTART NSRS-02 122386 011687 RESTART 3496T e

l

Element Report Ftr e st Fleal Comp 1"tiam NC 40400-SQIf 03/01/87.

E 40703-SQIf 03/01/87 NC 40709-SQIf 03/01/87 QA 80303-SQIf 03/01/87 QA-80503-SQN 03/01/87 WP-24-SQIf 03/01/87 ERT-H -101-006 03/01/87 5 20601-SQIf 03/01/87 M 21807-SQN 03/01187 a 23511-SQN 03/01/87 m 23801-SQN 03/01/87 a 23803-SQN 03/01/87 a 24000-SQN 03/01/87 M 24101-SQN 03/01/87 M 24102-3Q11 03/01/87 M 24105-SQIf 03/01/87 M 24200-SQIf 03/01/87 2770T 4

s a G

l 4

l BASIC POLICIES GOVERNING-SI REVIEW COMPLIANCE WITH EXISTING PROCESSES

- AI-4, Preparation, Review, Approval and Use of Plant Instructions

- SQA21, Onsite Independent Review (Plant Operations Review Committee)

- AI-7, Recorder Charts and Quality Assurance Records

~

- SQA191. Evaluation of Operational Readiness Prior to Plant Restart

- NQAM COMPLETE EFFORT (INCLUDING PORC APPROVAL) PRIOR TO PREPARATION TO ENTER MODE 4 (SOME PROCEDURES MAY REQUIRE COMPLETION OF VALIDATION AND VERIFICATION AFTER

, MODE 4 DUE TO PLANT CONDITIONS).

SURVEILLANCEINSTRUCTIONAPPROVEDLI5TMAINTAINEDANDTRACKEDTOENSUREALL

,_ sis CAPTURED.

TECHNICAL SPECIFICATION SURVEILLANCE INSTRUCTIONS MATCHED TO sis TO ENSURE ALL SURVEILLANCE REQUIREMENTS CAPTURED AND MET.

CONFIRMATION THAT THE SUM OF THE PARTIAL SATISFACTION OF SURVEILLANCE REQUIREMENTS EQUALS THE TOTAL REQUIREMENTS.

VALIDATION AND VERIFICATION OF sis TO BE PERFORMED RESPONSIBLE SECTION WALKDOWN AND WALKTHROUGH (PLANT CONDITIONSDEPENDENT).

4

- sis TO BE SATISFACTORILY COMPLETED IN FIELD AT LEAST ONCE WITHOUT

, SIGNIFICANT PROBLEM BEFORE WE ARE SATISFIED. PERFORMANCE FOR " RECORD" i TO SATISFY TECHNICAL SPECIFICATIONS MAY INVOLVE TEMPORARY CHANGES ACCORDING TO APPROVED PRACTICES AND PROCEDURES. (PLANT CONDITION DEPENDENT) l -

REQUIRED FORMAL FEEDBACK ON AT LEAST FIRST PERFORMANCE IN FIELD TO

' ' VALIDATE ACCEPTABILITY AND IDENTIFY ANY NEEDED REVISIONS. EXPEDITE j TURNANOUND ON REVISIONS.

4 INDEPENDENT OBSERVATION / VALIDATION OF ACCEPTABLE SI PERFORMANCE (SAMPLING BASIS AND DEPENDENT ON PLANT CONDITIONS).

4 a

4 0224c

R.: VISION STATUS ON PROCEDURES REQUIRED FOR RESTART AND OPERATION (February 3, 1987)

Responsible Total In Review Approved /

Organization Procedures Cycle Issued Operations 277 72 148 Inst Mtn 554 320 154 Elect Mtn 130 28 56 Chem Engs 71 23 6 Mech Mtn 194 60 110 Mech Test 160 151 1 DPS0 102 17. 83 Safety 43 - 3 34 Reac Engs 44 24 13 PSS 36 13 22 TOTALS 1611 711 627 NOTES:

Total of 29 groups have total of 1712 procedures. Of 1712, 736 are in review cycle and 695 (41%) have been approved.

These totals include the technical specification surveillance instructions.

0218e

DEMAND SCHEDULE TECHNICAL SPECIFICATION SURVEILLANCE INSTRUCTIONS Responsible Week Ending/ Weekly Approvals Organization 1/31 2/7 2/14 2/21 2/28 3/7 3/14 3/21 Inst Mtn 35 35 35 35 36 58 58 59 Mech Test 15 15 15 16 17 25 26 26 Operations 8 10 10 10 10 16 16 16 Chem Engg 6 6 6 6 7 10 10 10 Elec Mtn 4 4 4 4 5 7 7 7 Mech Mtn 3 3 3 3 3 5 5 5 ,

Reac Engg 2 2 3 3 4 4 4 5 DPS0 2 2 2 2 2 2 2 3 TOTALS 75 77 78 79 84 127 128 131 NOTE:

Demand schedule based on approval of 50% by 2/28/87 and approval of all procedures by 4/4/87.

K 0221c

HEVISION STATilS OF TECllNICAl. Sl'ECIFICATION SijRVEll.I.ANCK INSTRUCTIONS REQllINED FOR RESTART AND OPERATION (February 3, 1987)

Responsible Total In Review Approved /

Organization Procedures Cycle Issued

. Operations 103 48 19 Inst Mtn 353 277 2 Elect Mtn 43 21 1 Chem Enst 64 20 6 Mech Mtn 32 21 0 Mech Test 155 147 1 DPS0 18 15 1

, Safety 5 2 0 i Rose Enss 30 21 1 DNE 2 0 0 TOTALS 805 572 31 i'

e90 4

i-8

't i

1 0219e

?

i

1

?

F SECTION SI SECTION RETYPED S!

! REVIEW PER DECISION TO  ? O O TO SECTION NEW APP. F M VISE SI E W F TG , NCE j g FOR PR3CFING APP F ORIGINAL PLUS 1 COPY l l ' FILE CENT RETURN TO SI fEYIBf E g5tISINAL TO SPS TO PREPARE SECTION FOR ,

EEClast CI5fML SI FOR INFORMAL 0 RESOLUTION F AfP F  : PORC REVIEW

, yye SEET TO 55

! I h

' INFORMAL PORC SI PLACED OR GUALIFIED E88 SECTION RESOLVES 3

IN BOXES AT  ? IseIVIDUALS  ? W ES COMENTS OF GIs SPS OFFICES REVIEW AND 95 SI

. C0eseENT WWE

sums i

I SPS DOCUMENT D ""

I -

- PORC YES, Cc TAGL FOR r YI 8 " "

' APPROVAL FOR PROOFING DISTRIBUTICN CONTROL PORC APPORYAL NO RET 15N TO PREPARER 4 1r FLOW CHART FOR TECFNICAL DETEReeINATION APP F TO SI SPECIFICATICN FRAT 8 Or Aee F eACxAsE aevIE. cocaa SUWFTII AtCE INSTRITIGS " *"o0CIE# '" REvIe"."."I Ts 12/18/86

i '

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• APPENDIX G -

Page 161 Attachment 1 "*'iSi " 18 Page 1 of 1

CarTEftlA i

i t 1

i N EY

• j j PLANT STS -

3 ENGudEERS ,

i i

. * {

m .

Puwr mEviEur AcaseSr

. TECH SPEC N ---

CHANGES F TECH SPECS NECESSARY ECNo - . l l

Ev i m -

Sv5,g,,n,L,uafloM ag a noe sumurrvsD To WP GENERATED i PN " , uooricatioNs g TO UPDATE ,

FOft flE3cLUTIoM

+ AC ORAEWINGS '

! i i oo. TO S.

t mEwitur  ;

j

-w r i * -

$ naammenen  :

i U

' NOS. N 3, DD*

j one APPuCAeLE

-.g TO SUftWEILLANCE --g e w-am r oo* REVISED IIEVIEMIED TO DETEftWINE O oftNNING NOS. BGSTftUCTIONS F She NEED HEWSING gg8 l

~  !

4

.fEFEfENCED N SIe PItote - d i SI-1 APPEBeEK F t ustsee eer sie w

, A 6MM r

{ est asD usesD assoe [

ftEWISED  ;

As cafeSwtuctED - '

l Oft 8tED LaSD i Duf0 NOS. (10-17 86) ,

,_ -n- ,

n.- , . , , , - ~ , , - - - e,, n - - - - , , , . -r - - - - - , . _ , - --.,-r,r-- . - - , - - - . . - - -- - -. , , . -

b SCHEDULE AND MILESTONES TVA provide submittal to NRC describing scope of SI review and revision.

with justification. February 27, 1987.

TVA provide consolidated program plan for SI review and revision.

February 27, 1987.

Complete SI review and revisions prior to system alignment preparatory to

, entering Mode 4.

NRC confirm that current scope of SI review and revision is appropriate.

Complete SI review and revision.so that each section is at the 50-percent

approval level. Current schedule February 28, 1987.

Current schedule jeopardized by lack of production in key sections, related issues such as step-by-step skill of the performer requirements.

recycle revisions due to revised Appendia F, and adequacy of product as seen by Independent Review Group and Site QA.

NRC inspection of program and program results at 35 to 50 percent level.

Current schedule Narch 8-15, 1987.

4 NRC should be able to provide SER input on program acceptability and results thus far based on inspection.

. NRC inspection (s) to confirm adequacy of program results (acceptable sis) i past the 35 to 50 percent completion level. Complete 30 days before criticality.

'l NRC should be able to provide Commission briefing input on acceptability of program results and readiness to enter Mode 4 based on inspection (s).

NRC inspections of SI validation and verification program (dependent on plant conditions) to verify that sis remain valid or that appropriate revisions are promptly accomplished, i

NRC inspection to confirm that procedures and processes are in place and i functioning to ensure that future required changes are identified and j performed expeditiously with proper control. Schedule prior to Mode 4.

l l

l i

0225c I

I I

DESIGN BASELINE AND VERIFICATION PROGRAM -

SCOPE I. VERIFY ADEQUACY OF PLANT MODIFICATION SINCE OPERATING LICENSE

• MITIGATE DESIGN BASIS EVENTS

• SAFELY" SHUTDOWN THE PLANT

2. PROVIDE CONFIDENCE THAT MODIFICATIONS ARE SUPPORTED BY :

• EhGINEERING ANALYSIS

• DOCUMENTATION

3. ENSURE THE MODIFICATIONS CONFORM WITH LICENSING COMMITMENTS AND DESIGN

~

REQUIRMENTS STATUS

1. DESIGN CRITERIA

• COMPLETE

2. SYSTEMS WALKDOWN/ TEST

• COMPLETE EXPECT FOR INSTRUMENTATION WALKDOWNS

3. REVIEW OF SYSTEM MODIFICATIONS

• COMPLETE

4. SYSTEM EVALUATIONS

• .W OF 35 ISSUED

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KEY MILESTONES C d p

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1. COMPLETE SYSTEM EVALUATION REPORTS FEB 19

/

2. EA ACTION ITEMS sTOTAL 313

/

'?- C'.0S ED 198 OPEN 115 I RESOLVED -66

' UNRESOLVED 49 . ,,

0 3 ., NRC INSPECT 10hS-

? ECN INSPECTION REPORT SYSTER INSPECTION - MARCH u .

SYSTER INSPECTICM REPORT

f. 4 -

4. SAFETY EVALUATION REPORT - ,

- TVA RESPONSE - FEB 20

5. HYDROGEN MITIGATION / ICE CONDENSER SCOPE .

REVIEW PROGRAM IN PROGRESS FEB 28 ,- ..

6. PHASE 1 REPORT ,,

e

' PROGRAM DESCRIPTION . q.

! FINDINGS CONCLUSION & RECOMMENDATIONS RESULTS SIGNIFICANCE RESTART I

PHASE 2 UNIT 1 .

I 4D 1

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7. OPERATIONAL READINESS: REPORT MAR 20 REPORT OUTLINED' >

a ,

8. PUNCHLIST ITEMS TOTAL ITEMS) - 8118 .

t '

OPEN RESTART ITEMS 3170 ,

OPEN UNDETERMIhED ITEMS 1038 .

1 \

' CORRECTIVE-ACTION SCHEDULED' FEB 12' 4  :

COMPLETION RESTART ACTIONS APR 1

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ICE CONDENSER / HYDROGEN ANALYZER SCOPE .

DESIGN BASELINE AND VERIFICATION PROGRAM' O

CONTAINMENT ISOLATION PORTION OF SYSTEMS EXPANDED SCOPE / APPROACH 0

REVIEWED 150+ ADDITIONAL CHANGE DOCUMENTS 0 REVIEWED SUPPORTING DOCUMENTS (FSAR, EXISTING DESIGN CRITERIA, ETC.)

0 REVIEWED CALCULATIONS CONCLUSION CHANGES DO NOT ADVERSELY AFFECT THE CAPABILITY OF THE SYSTEMS TO PERFORM THEIR REQUIRED SAFETY FUNCTION STATUS REVIEW COMPLETE REPORT BEING PREPARED t

IMPROVEMENTS IN DESIGN CHANGE CONTROL PROCESS

1. Development of Modification Criteria to document design basis for ths change.

2. Issuance of design change as a unitised, design-complete package of a manageable size which includes a USQD based on completed design

3. Field walkdown for the modification with Operations, Modifications and Maintenance to improve constructability and to ensure design is based on current plant configuration.

4. Completed modifications result in a single drawing for the modification that reflects as-built configuration for the modification.

5. Formation of a Change Control Board to review necessity of the change and to ensure the modification process is being properly implemented and closed.

6. Design enhancements included in the design package consist of:

• Identification of special installation instructions

• Definition of functional testing and acceptance criteria required to verif y design integrity

• Review for impact of 10CFR50 Appendix R and Environmental Qualification (EQ) analyses

• Identification of special inspections and associated acceptance criteria Operability, maintainability, reliability, and performance analyses Listing of recommended spare parts

• Identifying changes to vendor manuals and EQ binders /10CFR50.49 list

7. Assignment of a Task Engineer to ensure design work is performed; ensure package is assembled, reviewed, and approved; help to resolve implementation problems; and ensure the work is tracked, completed, and closed.

8. Design documents are not revised and issued until work associated with the modification is completed, tested, and accepted.

SQEP Feb. 5,1987 DE05;JB7 035.01

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MAINTENANCE CURRENT STELLO PLAN (PAGE 19)

~TVA PRCAllDE. 15 7. CAT. 1 INSPEc.T MAtNT DEscRtPTIChi  ; INSPFCTtot4 y PRocaRAM DERCL EKtES i REMN OF C/As RESOLVED NMRG REPcR.T (1/87) (2/23/87) (3/fo/8'7) 2.. 3. t. ,7 Issue INSP. UPDATE R E fD R T.

SER i

j IMPuT Y

(4 /8'7) j (3/31/ 87) 6-l 5 OPERATtONAL j READINESS ----------i---<---

SER  !

4...

t . . q. _ _

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MAINTENANCE PROPOSED STELLO PLAN cus/s,) . (PAGE 19)

TVA NOTIFY NRC 3.

DETAtLED C/As ~'7 57. N M RC l' ScHEDut.E.  : CAT. 'l C./A s ,

IDENTIFIED FoR COMPLETE. T 4-CAT.l NM RC, FlMDIN C, S d stGN. PROCESS (3/6/67) or4 IFTs /u,RIs Defined cou.rse of NRC INSPECT.

oc+-ion j schedu.It . Prograrn c nficknce, (2/5/8% MAINT. PR06fAM

• Only imple.mentafion -only some,impkmenfrdien M.rnaining i Sl W .

remainin3 '

TVA 7.NFOR.M IMPLEMENTATbl

' NRC CTATuS - largely enhancemenis 'NN M I C/M M AINT. rem 4ihiv13

• G.

IFIs/ u RIs W6D DefincJ ccurse of acHon j sche.Jh.fe Issue

• Dnly implemeritaiion '

1R ecmaihinj v

C-30 e-t 0 S*

or earlier) (4) (*) ( 3/31/87)

Com MissioW commtsstoN OPERATIONAL. 3ER, CRITICALITf - T -c PAPER. TO 4 PAPER, <  ; READINESS  ;< IwPuT l CommisSIOM IN PuT j SER, j

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activifies activille 5 e.3.+rnining ..<...

te rie.d to other Pr"Sco.ms' input

EQ PROPOSED l STELLO PLAN

.. (PAGE 12)  %.

(z/zo/8'8 ( a /2.7 /B7) 50.4 9 CERI NRc. STAFF- EELD WORK .. B(NDERS LETTER. k y EVAL. OF COMPLETE CER.T. LETTER COMPLETE '

SER RESPONSE. i 4 SER RESPbHSE l

(.3/2.o/B7) - excee piece.pa. -ts (4/iof gg) .

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- EG field work. ( irnpiementa6m p,g gL

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TVA M tFY CoNMisstord CoMronsst0N CRITICALITY PAPER.TO S E R C o N F. MPER ComMtSSION I#E

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INPt.AT '

• Date could shift to prior to mode 4 due to late final implementation closeout of field work I

and documentation closure omnociated with pieceports. SCR 8616 and/or ampacity

, .s EQ CURRENT STELLO PLAN (PAGE 12) Ga. 4 (3/27/B7).

BELD WRK COMPLETE 50.49 CERT. STAFF EVAtuATt0N BINDERS

- - - LETTER { r CERT. LETTER > r COMPLETE.

SER RESPONSE i RESP NSE SER ITEMS (4/gofsg)

(2/20/87) (3/2.0/B7) WPLETE Gb.

G. 7.

. (3/ 27/87)

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( ) ( 4/07) - (4/to/87) coMWSSION FINAL FotmuP

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l CURRENT STELLO PLAN SCHEDULE ~

EMPLO YE8 CONCEllA/S N/[C .SAmP4/N6 h

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ELECTRICAL PROGRAM r---------------.

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ORERABIt rTY:

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As discussed TVA provide NRC ISS U E TVA RESPOND NRC -> CotAMiSS ION AWActW Iss u E.-

PROGRAM

> DRAFT > TD DRAFT > 3 pApEg.

RESU LTS -> SER. G E.R. S E R. -> INPUT 2/23/87 3/20/87 4/10/87 C-30 DATE C-10 DATE r------------------, .r---------------.

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2/23/87

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TECHNICAL SPECIFICATION SURVEILLANCE REVIEW PROGRAM STELLO PLAN TvA To suSMIT TVA TECHMCAL REC,loN 31' DA sI REva EW  : REviEv/ - r TEc.4 N LCAL gra FoR. 3 5 % 5 0 7.

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WA T sumiT TvA TECHNICAL T/A TECl4. TVA PRCNi DE

$1 REwEW RE.vt EW - REviEkr 100% NRC (bNFE R-PRc6 CAM FOR go 7,

? cmA_EW E a N ATioN T14 AT NRC REvsEW wxs. PRtoR RR.REYsEW UMPLETE  ; To cetTLCAt. TTY g00% COMPLETE

( 2 -7."1 - 8'7) ( 2.- 28 -87)

REC, tom E A I.SS kE w g,9g INSPECTION > " C##"$6[0N > SRLEFINC, 30 SER (NPuT A DAYS B E F O R E-cRtTGL.tT(

(3/8 to ( 3/3sjeq} (4/is/67) 3/ts /87) ins,9ECTt0N KEPoe-T (4/ts/B7)

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O CORPORATEACTIVITIES r

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PRESENT STELLO Pl.AN LOGIC ..g.f },*

'b FOR C,0RTORATE ACTIVITIES

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'n TVA Provide organization

!!RC Review TVA Submittals/

NRC Revise and Circulate Draf t NRC Issue Draf t Corporate TVA Response to Draft NRC Issue

[

~

Infortsation to --J Applicable ECs M Corporate SER 4 SER 4 Corporare M NRC and Revise Final  !;7 SER Corpora te W Draft SER SER f (1) Scheduled (2) Scheduled (5) Scheduled (8) Scheduled (9) Scheduled (10) i 1/23/87 2/13/87 3/27/87 3/31/87 4/15/87 Scheduled 6 In review presently- 4/30/87 i

~

a

. s' g-TVA Submit flRC Review NRC-Mang. Ass- .

Vol. 1, Rev. 4 4 Changes in essment of TVA 1

Vol. 1, Rev. 4 Implementation of Corp. Commii . 9

& fiang. change .

3

Critical ATs  ;

(3) Scheduled (4) Scheduled (11) Scheduled 2/28/87 3/13/87 3/27/87 f4

1. AT: 8-3 = 1 fronth

$d

" ~

2. AT: 3 - flow : 3-1/2 weeks I3

)N NRC RII NRC update 3. AT 9 - 8  : 2 weeks P

![

'g 1 Followup Insp-

?

SER input 4. AT: 10 - 8 : 1 rnonth I ':l i and I'valuatioi of}AAudit ,

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g r Fin Ings 5 . g, (6) Scheduled (7) Scheduled 7

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TVACriticalItemsforIssuanceofVol.1(Corp.)SER.

1. Submittal of organization information

2. Submittal of Vol. 1 Rev. 4

3. Review of Draft Corp. SER NRCCriticalItemsforIssuanceofVol.1(Corp.)SER

1. Review of TVA's submittal of organization information

2. Review of Vol. 1 Rev. 4 3.InspectionofescalationofQAauditfindings

4. Revision and circulation of draft corporate SER

5. Management assessment of TVA implementation of corporate commitments and managementchanges

6. Review of TVA comments on draft SER and issuance of final SER

F TVA Actions To Improve Critical ATs 1.Al2.AVol.iRev.4internalscheduleforsubmittalis2/23/87(asopposed toSTELLOPLANdateof2/28/87) 1.8Discussionlclosec00dinationoforganizationinformationrequestedby NRCwithLarryCrocker 3.Al4.AConsiderationforassemblingagroupofkeymanagerswhowouldmeetin TVA's Bethesda office to review and coment on Draft SER over a period of3 days (presentlyscheduledfor~2wks.)

4.BLicensingwillworkwithNRCtoestablishthestartdateforNRC's assessment of TVA implementation of corporate comitments and managementchangesbycloselymonitoringimplementationofVol.1 comitments.

I

2 ProposedActionsforNRC'sConsiderationToImproveCriticalATs 1.WorkcloselywithLicensingl0Ainestablishinginspectiondatefor followupInspectionofQAAuditfindings

2. N.A.

3. N.A.

4.AConsidertheassemblingofagroupofkeyNRCmanagerstomeetwithTVA keymanagersonthisissue,subsequenttoTVA'sreviewofthedraftSER.

TheTVAandNRCmanagerswouldhaveastheirobjectivetoworkthroughall thehardspotsnecessarytobeaddressedbeforeissuingtheFinal CorporateSER 4.8Workcloselywithlicensinginestablishinginspectiondateformanagement assessmentofTVAimplementationofcorporatecommitments Overall-Identifynewopenissues/hardspots/scheduleslipstoBob Alsupassoonaspossible l

r

~

Conclusions:

Weseetherequirementsasthefollowing:

(1) Completion of he Corporate SER by C-15 to support the Commission Paper (2) Completion of NRC - Management Assessment of TVA Implementation of CorporateCommitmentsandManagementchangesbyC-7IVAlNRCstaff Comissioner's meeting (3) All other critical ATs are support activities for the above and can occurparallelwiththoseefforts L

l 0364j 1

l

%,' ; $21.- Y Li

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,i 4: PROPOSED LOGIC USING SAME STELLO PLAN ATs T' '

i- FOR CORPORATE ACTIVITIES ".:I' i

- (DOES t[0T REFLECT AT Il'PROVEMENTS TVA BELIEVES CAN BE MADE)

.f

.? i -@

4

{l 4 -

hg i TVA Provide f.'RC Review TVA NRC Revise and NRC 1ssue TVA Response NRC

' f'./ '

Organi::ation Submittals/ Circulate Draf t 'Draf t Corporate to Draft Issue ,

fd information to --3) AppiJcable ECs 4 Corporate SER 4 SER d Corporate d Final

,- Ep ' NRC .md Revise SER Corpora te 3,

[-l

f - I Draft SER ,

SER {3j

'4 .

f. (1) 2/23/87 (2) 3/16/87 (5) 4/27/87 (8) 5/1/87 '(9) 5/16/87 (10) 5/31/87' ,

di (C-15) *1 T- r :2 M  :

TVA Submit NRC Review NRC--Hang. Ass- Commission Vol. 1, Rev. 4 g Changes in essment of TVA Briefing 7

Vol. 1, Rev. 4 Impicmentation TVA/NRC

~

of Corp. Commii .

. & ffang. : change:

(3) 2/23/87 (4) 3/8/87 (11) 3/27/87 C-7

• t

~$' <

NRC R1I

.: NRC update li Followup Insp- SER input I 2'!'l. . and L'valua tici  ?

• gh of OA Audit Findings g -) ,

l-

..> '.. (6) 3/6/87 (7) 3/13/87 I *'. ,

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