ML20216D012

Summary of 870601 Meeting in Bethesda,Md to Discuss Special Employee Concern Program.Attendee List & Handouts Encl

ML20216D012
Person / Time
Site:	Sequoyah
Issue date:	06/19/1987
From:	Donohew J NRC OFFICE OF SPECIAL PROJECTS
To:	NRC OFFICE OF SPECIAL PROJECTS
Shared Package
ML20216D020	List: ML20216D012 ML20216D047
References
NUDOCS 8706300428
Download: ML20216D012 (54)

Text

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I a ' pasou y ,o UNITED STATES

'g y NUCLEAR REGULATORY COMMISSION y g WASHINGTON, D. C. 205S5 j

\...../ June 19, 1987 t Docket Nos.: 50-327/328 LICENSEE: Tennessee Valley Authority (TVA)  !

FACILITIES: Sequoyah Nuclear Plant, Units 1 and 2

SUBJECT:

MINUTES OF JUNE 1,1987. MEETING ON LICENSEE'S SPECIAL EMPLOYEES CONCERN PROGRAM l

On June 1, 1987, a meeting was held at the headquarters of the Office of i Special Projects (0SP), NRC, in Bethesda, Maryland, between the OSP staff and ]

the licensee's representatives. This meeting was to discuss the licensee's l Special Employee' Concern Program (SECP) and the employee concerns that the licensee is investigating at the Sequoyah site. Attachment 1 is the list of ,l individuals attending the meeting. Attachment 2 is the handouts from the j licensee. There were no handouts from the staff. j Numerous (greater than 5000) TVA employee concerns applicable to Sequoyah have been identified which encompass potentially safety-related issues. The objective of the TVA SECP is to evaluate these concerns and to provide a timely disposition, corrective action and closecut of these issues. This is for TVA to provide assurance that plant safety is not adversely affected by these issues. This ,

program is investigating the employee concerns received by TVA up to February 1986.

TVA explained the history of the SECP to the staff. This included a discussion {

on the following components of the program: the receipt, processing and i evaluation of concerns for corrective actions; the criteria to determine which I concerns are safety-related; the instructions for reviewing concerns for generic l applicability to other sites; the organization of'the concerns into different categories and elemental reports; the criteria to determine which corrective actions must be completed before the restart of Sequoyah Unit 2; and the reports from the program. These are given in the procedures written' by TVA for the SECP.

TVA's ten categories of construction, material control, engineering, cuality i assurance / quality control (OA/QC), management and personnel, industrial safety, operations, welding, intimidatien and harassment and nuclear safety review staff /  !

Stone & Webster Engineering' Corporation (NSRS/SWEC) issues as a group were l discussed. In particular, the engineering category issues were discussed. '

The New Employee ~ Concern Program (ECP) was implemented by TVA on February 1,1986.

It receives the concerns from the TVA employees after this date. Its staff  ;

investigates and resolves these concerns instead of the SECP. '

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1 June 19, 1987 l The conclusions of the meeting were the following:

• OSP will review the EC Programs including' procedures, issue identification, O generic applicability to other sites, evaluator qualification and indepen- ]

dence, subcategory approach, restart corrective action', allegations matched 4 to employee concerns,- NSRC/SWEC category, and_ feedback to employees. .An j

evaluation of this program is required to be generated by the staff-prior- "

to restart.

OSP will also inspect the implementation 'of.the SECP.

OSP will provide TVA its schedule for the review of the engineering element reports.-

OSP will address TVA letters of April 17, 1987, on feedback to employees and of January 27, 1987, on vague concerns.

• ~ TVA will submit the subcategory reports, of which 25% have alreacCy been l submitted..by September 1, 1987. Evaluations by OSP are required to be generated but not prior to restart.

OSP will continue its review of the new ECP. A safety evaluation will be prepared. .

TVA to provide the status of all its corrective' actions. d G b Jack N.'Donohe Jr., Branch: Chief-

.Sequoyah Restar

! Division:of TVA Projects?

Office of Special Projects

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Attachments: )

1. List of Attendees

2. TVA Handout ,

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A__:k Tennessee Valley Authority Sequoyah Nuclear Plant Cc' General' Counsel Regional Administrator, Region II Tennessee Valley Authority U.S. Nuclear Regulatory Commission 400 West Summit Hill Drive 101 Marietta Street, N.W.

E11 B33 Atlanta . Georgia 30323 Knoxville, Tennessee 37902 Resident Inspector /Sequoyah NP.

Mr. R. L. Gridley c/o U.S. Nuclear Regulatory' Commission Tennessee Valley Authority 2600 Igou Ferry Road SN 157B Lookout Place Soddy Daisy, Tennessee 37379 Chattanooga, Tennessee 37402-2801 Mr. Richard King Mr. H. L. Abercrombie c/o U.S. GA0 Tennessee Valley Authority 1111 North Shore Drive Sequoyah Nuclear Plant Suite 225, Box 194 P.O. Box 2000 Knoxville Tennessee 37919' Soddy Daisy, Tennessee 37379 Tennessee Department of Mr. M. R. Harding Public Health Tennessee Valley Authority ATTN: Director, Bureau of Seouoyah Nuclear Plant Environmental Health Services P.O. Box 2000 Cordell Hull Building Soddy Daisy, Tennessee 37379 Nashville. Tennessec 37219 Mr. D. L. Williams Mr. Michael H. Mobley, Director-Tennessee Valley Authority Division of Radiological-Health 400 West Summit Hill Drive T.E.R.R.A. Building -

W10 B85 150 9th Avenue North-Knoxville, Tennessee 37902 Nashville, Tennessee.- 37203

~ County Judge Mr.'S. A. White Hamilton County Courthouse

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Manager.of Nuclear Power

' Chattanooga, Tennessee 37402 Tennessee Valley Authority-6N 38A Lookout. Place 1101 Market Street Chattanooga, Tennessee 37_402-2801

, a_ V ATTACHMENT'1 Attendees

! MEETING ON TV Ef1PLOYEE CONCERNS .,

PROGRAMS June 1, 1987

' Affiliation Name NRC/OSP J. Donobew NRC/OSP' M. Fields C ' Jordan -Bechtel/TVA SECP TVA

. G. McNutt NRC/OSP R.'Pierson TVA W. R. Brown TVA M. J. Martin

'NRC/OSP P. Hearn H. Garg NRC/OSP' R. Auluck NRC/0SP T. Ippolito -TVA consultant J; Zwolinski ,NRC/OSP Tennessee Valley Authority-TVA Special Employee Concern Program-SECP l

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e ,. 3-i ATTACHMENT 2 Employee Concern Task Group Program q Description j

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i EMPLOYEE CONCERN TASX' GROUP #l PROGRAM DESpRIPTION  !

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'& ' ' THE ECTG's PRIMARY RESPONSIBILITY 13 70 RF, SOLVE EMPLOYEE CONCERNSL f*' e,/ , ORIGINATING PRIOR TO FEBRUARY 1. 1986. ,._

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Concerns expressed $to "Line' managers- ,

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i THE TASK GROUP HAS ADDITIONAL' RESPONSIBILITY FOR TWO SPECIAL CLASSES OF OPEN ITEMS.

Not part of employee concern program-

• Stone and Webster Systematic Assessment items Open NSRS reports i

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=THERE ARE'NINE CATEG0EIES FOR EMPLOYEE CONCERNS AND ONE CATEGORY FOR

-NSRS/SWEC.

Program Menager: - W. R. Brown, Jr., Manager of Nuclear Construction Assistant Managers: .M. S. Martin, R,'Gibbs, J. Russell Construction.- Jack Howard'

• Material Con' trol - Joe Inger

Engineering - George McNutt;(Bechtel)

.QA/QC -'Joel Karr~(Stone & Webster)

Management and-Personnel (Not eafety related) ' Mark Whitaker- #, -

• ' Industrial-Safety (Not safety related) - Lon Ellis Operations - Bill Lagergren-(Impe11)

Welding - James Lewis (EG&G)'

Intimidation & Marassment Tish Jenkins.(Inspector.: General);

• . NSRS/SWEC . Art Debbage' t

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A SENIOR REVIEW PANEL OF INDUSTRY EXPERTS.0VERVIEWS THE' PROGRAM.

Reports to Admiral Wnite >

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Individually concur / reject! reports-

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- fotmer: Director of Engineering and

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M. Bender -

. Oak Ridge National ~ Laboratory-,

J. Dunford- - Former Startup Readiness Consultant; for.Three Mile-Island.

R. E. Kosiba - Former: Vice-President of Quality and - -

Technology for,B & W

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J. Lava 11ee, Jr. - Former Nuclear Project Manager for:-

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CONCERNS WERE ORIGINALLY CLASSIFIED BY THE TECNHICAL ASSISTANCE STAFF (TAS).

• Nuclear Safety Related?

Generically Applicable?

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j EVALUATIONS ARE CONDUCTED IN ACCORDANCE WITH THE PROCEDURES IN THE ECTG l

PROGRAM MANUAL.

ECTG M.1 Program Description / Pro essing of new concerns ECTG M.2 Program Description for NSRS/SWEC Y

ECTG A.1 Processing of Generically Applicable Employee Concerns 3 ECTG A'.2 Filing and Protection of Sensitive Information ECTG A.3 Employee Concern Program Computer System Data .i Processing ) ,

ECTG A.4 Program Procedure Revisions s ECTG C.1 Receipt, Processing, and Evaluation of Concerns' ECTG C.2 Analysis and Reporting of Evaluation Results ECTG C.3 Corrective Actions f

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.i EVALUATORS ARE EXPERIENCED IN THEIR FIELDS AND RECEIVE ADDITIONAL 3 TECHNIQUES TRAINING, j

Evaluator experience profile One Day Evaluator Training. Course ,

• Procedure Manual Training ]

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EVALUATIONS ARE' CONDUCTED AS APPROPRIATE AT EACH' NUCLEAR SITE,

' Initial. subcategory:: evaluation plan

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For a site: : 1) Site specific' concern 2)> Potentially' generic c.oncerns.

3) Potentially generic issues.

Techniques: 1)- Pro'eedures

2) Interviews -j

3) Field ' Evaluations -

.4) Integration with ongoing technics 1' programs' Evaluation Case Files t

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3 CORRECTIVE' ACTIONS ARE DOCUMENTED'ON A CORRECTIVE ACTION TRACKING DOCUMENT.(CATD).

C/A plan defined by line orgadization- ,

Approved by;ECTG Concurred ~with by Senior Review Panel: ,

Closure Verified by ECTG

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THERE IS A HIERARCHY OF REPORTS WHICH DOCUMENT EVALUATIONS.

Final ECSP Report (1)

Category Reports (9)

Subcategory Reports (117)

Element Reports (317 SQN + Unoffical) i 4

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FOR SEQUOYAH RESTART ONLY, ELEMENT REPORTS WERE PROVIDED TO NRC.

SQN specific evaluations Incorporated into subcategory evaluations 6

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1 THE SUBCATEGORY REPORT PROVIDES A

SUMMARY

OF THE EVALUATIONS AT ALL FOUR J

PLANTS.

List of. Concerns i

I Characterization of Issues Evaluation Methodology Sumary of Findings By Site and Programatic Causes 1 Corrective Action Provided by Line  !

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FINAL CLOSURE OF.Tf!E ECTG REPORTS WILL. PROVIDE A HISTOR CAL DATABASE!

"New" employee concern program checks our database Reports will be available to'all employees and concerned' individuals

• TransitionTeamwillfollowreportsuntil_finalC/Ajlosure" ..;

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A NUMBER OF CRITICAL ACTIVITIES REMAIN.FOR NRC CLOSURE.OF PROGRAM.

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l'. . Review an'd approval of Engineering element, reports i? .

I' 2.. Feedback to Employees - June'29 Target!.

3. SQN Wrap-up Report

4. Program Inspection

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1. Review of Subcategory Reports (37:of.117 submitted).:..

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3. Review of Category and Fina1LReports- _' j 1

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BACKUP MATERIAL Ik 1

1) Organization Chart- - .M.1, Attachment A - Page 1 ]

2) ' Nuclear Safety'Related Criteria - M.1, Attachment C - -Page 2: El

3) Safety Significant Criteria .- M.1, Attachment.D Page 6

4) . Generic Applicability Criteria . - . M.1, ~ Attachment E ' ' - , Page 7  !

j 5)- Subcategorizing Concerns Guidance - M.1, Attachment'F - Page 9

6) Corrective Action Tracking Document (CATD) Form -

(C.3,) Attachment A - .Page 10

7) Instructions for. Completion of-CATD FormL-(C.3.) Attachment B - Page.11

8) Verification of C/A Checklist. -o ~ C.3.-Attachment E -

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9) AlleSotion' Matrix Example - 'Page 16-

10) NSRS Items for SQN - Page'18 3

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ECTG M.1 Attachment C Page.1 of 4 Revision 4 I

l CRITERIA FOR EVALUATING CONCERNS TO DETERMINE THOSE THAT ARE NUCLEAR SAFETY- l RELATED FOR USE AS APPLIES TO EMPLOYEE CONCERNS A. GENERAL GUIDANCE '

The evaluation to determine whether a concern is' safety-related must always be resolved in a conservative direction to ensure that nuclear safety is the priority consideration. Consideration of plant capacity factor, economics and the effects of. plant unavailability are not to be taken into account when performing this evaluation.

For use by Employee Concerns Task Group (ECTG), the term " nuclear safety-related" as defined below applies to systems, structures, and  ;

components that perform a primary safety function and.to related 1 activities. Such systems,' structures, and components are listed in the .I Q-list for WBN and in the Critical Structures Systems and Components (CSSC) list for other plants.

4 Items performing a primary safety function are those that are necessary to ensure:

1. The integrity'of the reactor coolant pressure boundary, s

) 2. The capability to shut down the reactor and maintain-it in a' safe 1

condition; and/or .

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3. The capability to pre' vent or mitigate the consequences of an incident: 1 i

which could result in potential offsite exposures comparable to those j specified in 10 CFR Part 100.

The CSSC items could be affected by any concern.related'to: '

The'CSSC item itself (i.e., its design, operation, maintenance,  !

material or any other hardware deficiency), i Activities related to any portion of the process necessary to achieve a final operational configuration of safety-related items.

Activities related to any portion of the process which could' result  ! -

in.fallure of a CSSC. '

Commitments TVA made to regulatory agencies. - m 3

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- i- . Attachment C page 2 of 4 Revision 4 A concern in any of the above areas could affect adversely the ability of a CSSC item to perform its intended function or to meet requirements established by regulatory agencies necessary to assure the safe operation of the plant and to protect the health and safety of the nuclear plant employees and.the public. Therefore,-it should' be categorized as nuclear safety-related. These areas are discussed in more detail below.

Additionally, those it ems which are necessary for. the following

• are also to be treatedlas nuclear safety-related for purposes of generic-applicability determinations and corrective action and to' emphasize their importance to nuclear plant safety cnd licensins:

The physical security of CSSC.

Conformance with the ALARA concept.

An adequate fire. protection program.

B. SPECIFIC GUIDANCE

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Concerns about safety-related items (i.e., CSSC itemsliare'to be

. designated as' nuclear safety-related as=specified above. . Any item (including instruments and controls) 'should be considered CSSC:if it' performs (traff its failure would degrade) any of the following-specific safety-related functions:

1. Maintains core reactivity control under emergency, conditions' including those covered by. anticipated transients without scram (e.g., reactivity contr(1 systems).

2. provides a barrier for containing'r'esctor coolant'within the reactor coolant pressure boundary-(e.g.,1 reactor coolant' piping .

valves, and fittings).

3. Cools.the reactor core under emergency conditionsJ(e.g.,' residual core heat removal systems),

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Maintains fuel clad integrity (e.g., fue1~ clad, core power- '

monitoring systems).

5..:Provides power, control, logic.' indication, and' protection to ,

systems or components to enable them to accomplish tteirisafety3 -

function ~(e.g., diesel generators.: vital ac and dc~pcwer);

. g6. Supports or houses egulpment thatLperforms'a safety l function-or~

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protects that safety-related~ equipment 4from pote'tial/

n natural phenomena',' equipment failure, and man-made. hazards (e.g., Seismic-f) Class ~I containment-and structures, fire' protection systems). '

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7. Maintains specified environment (e.g., temperature, pressure, humidity, radiation) as required in vital areas to maintain W equipment operability and personnel access (e.g., control room :d habitability systems). .

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8. Supplies cooling water for the purpose of. heat removal from the i systems and components that provide a safety function (e.g.,

essential component cooling and service. water' systems). {

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9. Contains radioactive waste such that its failure could result in the uncontrolled release of radioactive waste to the offsite -

environments (e.g., low-level radioactive waste discharge .W isolation' valves).

10. Controls fuel storage to prevent inadvertent' criticality (e.g., (

fuel storage racks).  !

11. Ensures adeguate cooling for irr6diated fuel in spent fuel storage (e.g., spent fuel cooling system).

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12. Minimizes the probability of dropping objects on stored fuel i s (e.g., overhead crane).  !

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13. Maintains primary containment'as required.by the FSAR to meet- ll General Design Criteria (GDC) 54, 55,'56, and 57 (e.g., .j containment penetrations and associated isolation and boundary

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14 Doors and hatches that serve one or more of the following'.

functions for safety-related equipment and areas: (1) pressure i confinement, (2) leakage confinement. (3)-misslie protection,-(4)

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J pipe whip and jet impingement barrier, (5) equipment rupture  !

flood protection,'.(6) natural flood. protection, or'(7) fire protection.

15. Any other function required by 10 CFR 50,~ Appendix A (the GDC). Lj I

16. Any activities that may directly or' indirectly affect-the' ability d

- - . , -. of.CSSC to perform their' safety-related functions. These include. but are not limited. to the following:

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16.1 Designing

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26.4 Handling 16.5 Shipping I 36.6 Storing 16,7 Erecting or Constructing  !

16.8 Cleaning 16.9 Inspecting

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16.11 Operating 16.12 Maintaining 'l 16.13 Repairing i i

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.., 16.14 Modifying 16'.15 Auditing 16.16 Fire protection

17. Any' concern expressed by an employee, an interested individual, or a group that relates in a' negative manner to the ability,of-CSSCs to perform their intended' function, to safety-related ,

activities, or to a violation or deviation.from TVA commitments '

should be classified as nuclear safety-reisted.

18. Any concern expressed by an employee involving those activities'- '

regulated by 10 CFR'20, " Standard for Protection'Against i Radiation." i

19. Any concern expressed-by an employee about the' physical security; .{

aspects of safety-related systems. '

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20. Any concern expressed by an employee that impacts 'a technical  ;

. specification operability requirement. "" "

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1 ECTG M.1 Attachment D Page 1 of 1 Revision 4 CRITERIA FOR EVALUATING SAFETY-RELATED EMPLOYEE CONCERNS TO DETERMINE IF AN UNREVIEVED SAFETY-SIGNIFICANT OUESTION OR SAFETY HAZARD EXISTS A. GENERAL GUIDANCE

1. The safety evaluation may be based on engineering judgments to the extent deemed necessary to the individuals involved in the review, but '

questions that result in significant doubt must always be resolved in favor of a nuclecr safety finding.

2. Consideration of plant capacity factor, economics, and the effects of plant unavailability are not to be taken into account when performint I

this evaluation.

B. SPECIFIC GUIDANCE Safety Significant Criteria are those criteria used to analyze a potential safety-related concern that if validated couldt

1. Result in potential offsite exposure exceeding those limits specified in the Technical Specifications or 10 CFR 100.

2. Increase the probability of an occurrence or the consequences of an

/""?} -

accident or malfunction of equipment important to safety previously '

evaluated in the s'afety analysis report.

3. Create the possibility for an accident or malfunction of a different j

\

type than any evaluated previously in the safety analysis report.  ;

4. Reduce the margin of safety as defined in the basis of any technical specification.

If any of hazard maythebeabove criteria are met, a safety-significant question or scfety involved.

A prioritized corrective action must be completed before an identified plant operational mode is achieved. The significance of the safety question or hazard will determine the priority of the completion of corrective action. .Such determination and the corrective actions planned or taken shall be included in the appropriate Program required report (s).

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ECTG M.1

. Attachment E Page 1 of 2 Revision 4 INSTRlICTIONS FOR REVIEW OF EMPLOYEE CONCERNS FOR GENERIC APPLICABIL]TY Expressed concerns may have' implications or appilcability beyond the identified circumstances. The generic implications / applicability may invo3ve additional structures, components, systems, features,.or.processos at.the plant where the concern has been identified, or mcy involve-other TVA p2 ants.

In order to determine whether a concern has. potential'or actual generic applicability, the,information'avr.ilcble is to be reviewed for this specific'.

purpose using the elements and considerations set:forth in this attachment.

The objectives of the review are to: . (1) identify those concerns.with generic implications, (2) identify'which plants are' implicated .(3) provide advance notification to organizations responsible.for the areas impilcated,.and (4)>

ensure that all implications of the concern are evaluated.'

Determinations of generic app 3icability should-be approached on a conservative, yet reasonable basis. The determination'is to'have a, reasonable.

factual basis (not rierely speculation)- It is acceptable to base the generic determination ~on.the evaluator's_ knowledge or experience. The explanation on Form A-of this attachment shall provide enough detail to clearly communicate the basis, or reasoning, for drawing-the conclusion. 1For instance, the reason "if it happened at Watts Bar. .it could happen at Sequoyah," is. insufficient .

-g.. reason to determine an item generic.. There must be some reasonable factual basis presented which explains why that is the case, e.g., ".; . .;this concern

,, appears to have resulted from a deficiency in 0-39-(upper-tier document that applies to all plants), therefore, it is generic . . . " is an; adequate and reasonable, factual' basis for concluding that 1,he concern is1 generic. 'In: .

other words, you must be~able to define in writing some reasonable common link, between the' concern and other plants or plant features which Indicates.that those other plants or features (which are beyond the scope of the concern) could be similarly affected. When there is.not enough definitive information to identify (or eliminate) a generic issue, it.is acceptableLto say so.

As each concern or group of concerns is identifiedLto be generic to other plants, a. list or lists will be maintained identifyltig.each concern and to which plant each concern is applicable. Each generic. applicability review shall be reviewed and concurred with by a second party.

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ECTG M.1 FORM A Attachment E Page 2 of 2 i Revision 4 GENERIC APPLICABILITY DETERMINATION 1 l

-- __ Concern Number l A. Meaningful Evaluation Possible / / Yes / / No B. Generic Implications h Yes O No; if Yes, O Same Plant? O Other Locations?

C. Other Locations / / Knox / / Chatt / / WBN / / SQN / / BLN / / BFN-  !

and Plants /.ffected D. Erplanction/Juctificction _,

i

^

Evaluated by / Reviewed by /

_______________________________________________________.___________________;_.. ']

The following provides clarifying instructions and guidance for completing this form.

I. Evaluation - Assume the concern, as stated,'is'true.

l A. To conclude that a concern is generic.;you'must be able to define (in {

writing) some. reasonable. common link between'the concern and other

,_ plants'and TVA locations or between the concern and other plant'

, features or processes'of the came plant which indicates that those:

other plants or features could be similarly affected. If there is not .

enough information to identify and define (or.else eliminate) such a I common link, then there is not enough information to perform a .

meaningful preliminary evaluation so~Part I.A should be answered "No." In this case, Parts I.B and I.C need not be completed.

Part I.D should provide the justification for the "No" answer. i B. A concern has generic implications if an approved code, standard, i procedure, specification, process,-etc., is deficient, is, implied _to j be deficient, or is being improperly. implemented in other than an '

isolated case. Generic applicability is not restricted to the items listed above. Any other programmatic' deficiencies.: common problems, ,

etc., should also be considered in the review. '

C. Self-explanatory

~

D. Provide enough' detail to clearly communicate the basis, or reasoning, for the conclusion. '

~

Miscellaneous Instructions 't o Be sure to record concern number in top, right-hand corner.  ;

o Answer all questions and fill in'all blanks except.as noted.

o .Date your signature.

o Signature in " reviewed by" signifies concurrence'with all-information

, in the section signed.

4 o Explanation / justification may be continued on an attached'b1'ank' sheet .

_- as long as the applicable sectionLis' clearly identified.

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ECTG'M.1 Attachment-F Page l'of.,1 Revision 4 CRITERIA FOR SUBCATEGORIZING CONCERNS Concerns cre to be subcategorized by the CEG for evaluation. ' factors to be considered include the'following:

1. Is the concern the same, or'similar to, the other concerns?

2. Would the evsluation activities be the same or similcr?

'3. Does the concern fit within the defined' boundary of the. subcategory?-

4. When the subcategory evt.luation is completed.In:accordance with the:

evaluation plen, will the concern,' as' stated, be specifica11y'and clear 3y addressed both in the eva3uation and in the'subectegory evaluation report?.

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ECTG C.3  !

Attachment A Page 1 of 1 Revision 4 ECTG Corrective A_ction Trackinr Document (CATD)

INITIATION Applicable ECTG Report No.:

1. Immediate Corrective Action Required: O Yes O No

2. Stop k'ork Recommended: O Yes O No

3. CATD No. 4. INITIATION DATE j

5. RESPONSIBLE ORGANIZATION:

6. PROBLEM DESCRIPTION: O QR O NQR

7. O ATTACHMENTS 1 PREPARED BY: NAME DATE:

8. CONCURRENCE: CEG-H DATE:

9. APPROVAL: ECTG PROGRAM MGR.

I DATE: -

CORRECTIVE ACTION

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10. PROPOSED CORRECTIVE ACTION PLAN:

11. O ATTACHMENTS PROPOSED BY: DIRECTOR /MGR: DATE:

12. CONCURRENCE: CEG-H:

DATE:

ECTG PROGRAM MANAGER

- DATE:

i

-- VERIFICATION AND CLOSE0UT

~13.

Approved implemented.corrective actions have been verified as satisfactorily SIGNATURE TITLE i DATE 4869T

9 .

9 1

ECTG C.3-Attachment B ,

Instructions for Completinr. Page.1 of-2 the CATD Form. ]

Revision 4 INITIATION-  :

1. Identify if immediate-(remedial) corrective actions is needed.

2. Identify if-immediate stop work is recommended.

3. Enter the CATD number - this number is made up of the associated Subcategory Report Number plus a dash, the applicable plan acronym (i.e. BFN,. BLN. SQN, k'BN or NPS 'if 'not plant specific) . plus a dash, and.a sequential number for each CATD issued against that plant in a the report.

NOTE: CATDs may'also be issued by the'ECTG Program Manager against the ECTG Final Report for root causes' identified in the Report. .,

1 4

Enter the CATD initiation date.

5. j Identify the organization responsible'for identifying and taking- '

corrective action.

6. . Describe the prob]em - provide sufficient detail to' allow the '

responsible organization to prepare the proposed' corrective. action:

~

plan. Attach additional pages if-necessary. 'Try to limit each CATD to single problems. -Also check one box to identify if'the_ problem'is quality-related ("QR") or nonquality-related ("NQR").

7. preparer of the CATD signs and dates.

8. The CEG-H signs and dates - noting-concurrence; 9.

The ECTG Program Manager signs and. dates - noting approval.

CORRECTIVE ACTION 10.

The identified responsible organization describes:the proposed. ,

corrective actions. The' actions shall include lthe following;

,. _ a. Actions to identify all similar items;or instances if the problem stated in six indicates there may,be:other items or instances:

involved and thefeate(s)'for completing these actions.

b.

Actions taken or. planned to correct thelidentified and similar items or. Instances ~and'the-date(s) for completing these' actions.

~

c. Actions'taken or plan'ned that will preclude th'e recurrence'ofJ l

the identified problem and the date(s)- for. completingithese actions.

d. Actions completed to date and the results. achieved.

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'4

1, ECTG C.3 Attachment B Instructions ~for Completinr. Page 2 of 2

-the CATD Form Revision 4-NOTE: Attach additional pages if necessary. Also. identify.

by number or atta'ch a copy of any quality assurance - 1,

(

program deficiency documents initiated and whose 'l j

disposition has been approved as a part of your response to quality-related CATDs.

11. Signature and date of the responsible site director or otheri responsible TVA manager.

12. Concurrence signatures and.date of the ECTG CEG-H and the ECTG'- -

Program Manager when they concur.with the proposed corrective- i action plan. '

13. Designation of the'1ead responsible' organization for implementation: 1. -

of.TROI action items.

1 1  ;

14. The date or milestone that should be entered as the'overall TROI- I.

item priority date. ll ll j VERIFICATION AND CLOSEOUT a.

15.. - Upon verification of the satisfactory implementation and completion..

3 of the proposed.. corrective action'as evidenced'byialcompletedJ .l:

attachment E, the. signature of the'CEG-H along withLthe-date.of- .-t. .<

verification will be included on~the CATD.~!Vesification.'willL '

4 i

be performed by the appropriate individual'as followsi l

a. Prior to disbandment of the ECTG: i

1. Any cognizant indihidual from;the ECTGlwill.'close'out; bothi .,

quality-related-and-nonquality-related CATDs

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Note: For quality-related CATDs kthe-verifyingaindividual- 1 shall ensure that QA and/or QC hasiclosed out the;

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l proposed, corrective"actioni.through 'normalilinei ' l

, documen tati'on.

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b. After: disbandment.of the ECTG: ^

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1. . A cognizant ONP ECP representative will :close; out all - .

CATDs.. # !lj d

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.16 . -The: responsible site director.or other;respon'sibin;.TVA' manager wil

• l be: notified by the ECTG Program Manager:upon final closeout of: the; ,

.CATD.'

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L ECTU C.3 Attachment E .j page 1 of 3 .

Revjslon4 <

ECTG VERIFICATION CLOSE0UT' CHECKLIST ,

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lCATD No. l- l - -

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lThis CATD was designated: l C/A completion notification .I

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l . l Memorandum RIMS No. l ,,

lD QR CAQ No. l F' #

-l l This memorandum denoted CATD: .- G 10 NQR l D Partial Closure- ,_ - [ i '

l l D Complete Closure '

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SUMMARY

C/A elements reviewed f .-l i.

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l D Walk.down documents O Procedure and/or drawing revisici is 'o il D Document ~ and/or drawing reviews D Training records. - +

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l'O Examination or test results O Modification'(ECN)'documeni'r

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l D Engineering analysis D New program (s) >

., I l D R! pair or replacement records D Other - specify l 1 l .

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. .. . 1-l DISCUSSION: Discuss verification actions taken (including' documents /

I hardware-reviewed as applicable). See; verification guidance.- l l t' l page'3 of 3 of this attachment. a 1.

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.lLCenclusions: Corrective actions were adequate D res: 'O ho DO N/A l' l ;- a gg l; 'Yss No N/A: v- .I 1; O D. .D Deficiencies adequately scoped- ' "

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, 1 l D D. O Actions required to prevent rece.rrence complete' '

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, Attachment E

-' Page 2 of 3 Revision 4 i

VERIFICATION CLOSEOUT CHECKLIST l

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, J CARD NO. - '-

In i t 5 d.'s Date j {

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ECTG C,3 Attachment E j Page 3 of 3 1 Revision 4 VERIFICATION GUIDANCE -

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-l CATD NO. Initials Date j j i I -j 1 .

I l Verification' activities should answer two guestions l .

l I I lt(1) Were specific corrective action commitments 'and requirements

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-l The verifier should consider whether or not the' corrective actions taken

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I l' address the. identified problem in a manner. consistent with the. explicit l- i l and implied elements of the corrective' action plan that was accepted by' 1 l ECTG. At a minimum, the corrective actions should have identified all ~1 I similar deficiencies'if similar deficiencies. exist,' corrected all, 1.

l Identified deficiencies, and implemented all actions required.to prevent. l l recurrence where' applicable. The verifier'should~ describe the evidence l' I found to substantiate verification of corrective action and give the l-

'I appropriate document references and/or hardware observed to aid'in '

.l' l retrieval of the supporting documentation and/or justify conclusions. I l'If the " Corrective Actions were adequate" N/A. block is checked in the 1.

I conclusion section, this indicates that no' corrective. actions were 1 l required and'an explanation of'this finding'should be given in the

! discussion section. -l 1.

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/Mk AA L44 8 6 1 l'2 6 814 SN 157B Lookout Place NOV 26 G86 Mr. Harold Danton */

Director of Nuclear Reactor Regulation '

U.S. Nuclear Regulatory Comission 7920 Norfolk Avenue Bethesda, Maryland 20814

Dear Mr. Denton:

In the Matter of the Application of ) Docket Nos. 50-327, 50-328 Tennessee Valley Authority ') 50-390,'50-391 EMPLOYEE CONCERNS TASK GROUP (ECTG) - SEQUOYAH (SQN) AND WATTS BAR (WBN)

NUCLEAR PLANTS In my letter to you dated October 27, 1986, TVA indicated that the Employee Concern Task Group (ECTG) would re-evaluate all open Nuclear Safety Review Staff (NSRS) recomendations to identify any additional . items requiring.

evaluation before SQN restart. This assessment has been completed and the results are sumarized in enclosure 1.

f The review of the open recommendations' indicated an additional 17 items

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require closure verification by ECTC before SQN startup. This makes a total of 27 open NSRS recommendations which will be reviewed before restart.

Another 71 items'are applicable to SQN but do not require closure verification' before restart. This determination was made using the " Criteria for Evaluation of Potential Restart Items" provided in Volume 2 of the Nuclear Performance Plan and has been reviewed and approved by the Sequoyah Site Director.

ECTG plans to issue to NRC two evaluation reports. The first report.

(ECTG-NSRS-01) will address the original 10 restart items provided in the ECTG scope of work for SQN as identified in our August 29, 1986 submittal on the ECTG program.

• second report (ECTG-NSRS-02) will address the 17 newly identified ites_. These reports will be provided through the normal'ECTG reporting process.

• If you have any questions, please get:in touch with Martha Martin at'(615)'

365-3587,- Watts Bar Nuclear Plant. ~

Very truly yours, TENNESSEE VALLEY AUTHORITY Original Signed By , '

, R. L. Gridley .

R. L. Gridley, Director j Enclosure

-Nuclear Safety-and Licensing-cc: (See page 2) 4

- Enclosura 1

' *~~ -

Pass 1 Eof 2-NSRS OPEN ITEMS APPLICABLE TO SON ,

1

-11/20/86 The.following ten items were originally identified in the 8/29/86 submittal-of- h the ECTC program as requiring closure verification before SQN restart. .l

. 1 To be addressed in Report ECTG-NSRS-01 4

R-84-19-WBN-01, -07 )

I-85-06-WBN-01, -02, -05 R-80-05-SQN-4B

.R-85-02-SQN/WBN-2 q R-86-01-SQN-01 Addressed in NMRG Report R-86-02-NPS R-85-03-NPS-07, -08 (closed)

The following seventeen additional items require closure verification by ECTG l before start-up.  ;

To be Addressed in Report ECTG-NSRS-02 h

R-80-05-SQN-10

. R-82-07-WBN

-- R-82-08-NPS-10c  ;

R-84-07-WBN-1 R-84-17-NPS-10, 11, 12  ;

R-84-19-WBN-6 I-84-34-SQN-3 I-85-06-WBN-3 l R-85-08-0E/NUCPR - 1 through 6 -

I-86-101-SQN j; The following 71 items are also considered applicable _to SQN but closure -

before startup is not required.

Former Browns Ferry Items R-80-10-BFN-1, IVA l

R-81-02-BFN-(R-82-11-BFN-B)

R-84-17-BFN-6 Former Watts Bar Item R-84-05-WBN-14

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j Former Power and Engineerinn' Items.

79-09-01-1, 2, 3 j i

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, No. ' Description 201' INCORPORATION OF REQUIREMENTS AND COMMITMENTS INzDESIGN

'203- EXPERIENCE FEEDBACK 204 0RGANIZATION OR OPERATING' PROCEDURES 205 CONTROL OF DESIGN CALCULATIONS-206 AS-BUILT RECONCILIATION 1207 DEVIATION: DOCUMENTATION 208' HUMAN FACTORS

'209 'Q-LIST.

210  ; ENVIRONMENTAL QUALIFICATION PROCESS 212 PIPE SUPPORT PROGRAM' 213 ELECTRICAL PROCEDURES 216 FLUSHING-215 CIVIL / STRUCTURAL DESIGN 218 PIPE STRESS CALCULATIONS' 220 SUPPORT DESIGN GENERAL 221 PIPE SUPPORT DESIGN 222 SUPPORT WELD DESIGN '

223 INSTRUMENT SUPPORTS DESIGN 224 RACEWAY SUPPORT DESIGN 225 BATTERY SUPPORT DESIGN 226- SEISMIC INTERACTION DESIGN 227 PIPE, WHIP RESTRAINT DESIGN 228 UNISTRUT SUPPORT' DESIGN 229 INSTRUMENTATION. AND CONTROL DESIGN' 230 'HVAC DESIGN' 2 31 FIRE PROTECTION DESIGN 232 PIPING AND-VALVE DESIGN 233 ESSENTIAL RAW COOLING WATER PIPING e

234 ACCESS TO EQUIPMENT 235 ELECTRICAL SAFETY-237 ELECTRICAL PROTECTION DESIGN, .

238 RACEWAY OVERFILLS AND CABLE-PULLING 239' CABLE AND' RACEWAY PROGRAM, 240' CABLE AMPACITY-241 CABLE TERMINATION AND SPLICES.

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, CHECK LIST l I

CIVIL. I i

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1 a) Review concerns j b) Clarify unclear aspects )

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