ML17335A252

Provides Summary of Meeting Held on 980917 with D Cook NPP Staff to Discuss Issues Re Plant Restart Strategy & Performance Indicators & NRC Insp Plan.List of Attendees & Meeting Handout Encl

ML17335A252
Person / Time
Site:	Cook
Issue date:	09/28/1998
From:	Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Powers R AMERICAN ELECTRIC POWER CO., INC.
References
NUDOCS 9810020454
Download: ML17335A252 (15)

Text

CATEGORY 2 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)

ACCESSION NBR: 9810020454 DOC.DATE: 98/09/28 NOTARIZED: NO DOCKET I FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315 50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana M

05000316 AUTH.NAME AUTHOR AFFILIATION GROBE,J.A.

Region 3

(Post 820201)

RECIP.NAME RECIPIENT AFFILIATXON POWERS,R.P.

American Electric Power Co., Inc.

SUBJECT:

Provides summary of meeting held on 980917 with D Cook NPP staff to discuss issues re plant restart strategy performance indicators. List of meeting attendees E meeting handout encl.

DISTRIBUTION CODE:

IE01D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:

E RECXPIENT ID CODE/NAME PD3-3 PD INTERNAL: AEOD/SPD/RAB DEDRO NRR/DRCH/HOHB NRR/DRPM/PERB OE DXR RGN3 FILE 01 EXTERNAL: LITCO BRYCE,J H NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME STANG,J AEOD TTC P~E NRR PECB NUDOCS-ABSTRACT OGC/HDS3 NOAC NUDOCS FULLTEXT COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

D 0

N NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATIONS CONTACT THE DOCUMENT CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 17 ENCL 17

September 28, 1998 Mr. R. P. Powers Senior Vice President Nuclear Generation Group American Electric Power Company 500 Circle Drive Buchanan, Ml 49107-1395

SUMMARY

OF THE SEPTEMBER 17, 1998, PUBLIC MEETING TO DISCUSS D. C. COOK RESTART ACTIVITIESAND NRC INSPECTION PLAN

Dear Mr. Powers,

This letter summarizes the meeting held on September 17, 1998, between staff members of the NRC and the Donald C. Cook plant to discuss issues related to plant restart strategy and performance indicators. This meeting was open to public observation.

Enclosure 1 is a list of meeting attendees.

The NRC presented an. initial Inspection/Activity Plan to address the Case-Specific Checklist items documented in the letter establishing the Manual Chapter 0350 restart panel, dated July 30, 1998.

In addition, the Case-Specific Checklist items were re-presented, some with further subcategorization, providing the NRC's responsible organization/inspection plan for each item. The handout with this information, provided by the NRC during the meeting, is contained in Enclosure 2.

Members ofthe plant staff briefly discussed portions ofyour September 16, 1998 letter to the NRC, which revised the plant's restart schedule from late fourth quarter 1998 to late first quarter 1999. Based on this new restart date, the NRC staff stated that the schedUles given in the initial Inspection/Activity Plan willneed to be reviewed with the plant staff to establish new inspection dates.

The NRC staff stressed that the schedule for our Inspection/Activity Plan continues to depend on when the specific restart items willbe ready for closure, and that the NRC intends to publish the Inspection/Activity Plan with the best available information by the end of October.

The plant staff discussed their restart strategy documents from a broad perspective, arid provided several examples of individual strategies that were still in the development stages.

Since the plant staff had chosen to integrate the closure ofthe restart items with the development of these strategies, the NRC staff expressed their interest in the scheduled completion dates. During the discussions of the restart strategy for the Containment Liner Pitting, the NRC staff discussed weaknesses identified in the recently completed closure package.

Specifically, the NRC staff noted that the effects from pitting had not been considered in the containment liner fatigue life and that the plant's proposed revision to the Final Safety Analysis Report had not identiTied that the containment liner design strain limithad been changed.

C"",054 98i00204S4 980928 6

PDR ADOCK 050003i5 PQR

R. Powers The plant staff briefly discussed their current set of performance indicators for the various areas.

After comments from the NRC, the plant staff acknowledged that some of the performance indicators, specificall for engineering, only monitored the backlog and would not indicate the quality of the work.

Sincerely, Original's/ J. A. Grobe John A. Grobe, Director Division of Reactor Safety Docket Nos.: 50-315; 50-316 License Nos.: DPR-58; DPR-74 cc w/encl:

J. Sampson, Site Vice President R. Eckstein, Chief Nuclear Engineer D. Cooper, Plant Manager R. Whale, Michigan Public Service Commission Michigan Department of Environmental Quality Emergency Management Division Ml Department of State Police D. Lochbaum, Union of Concerned Scientists Distribution:

RRB1 (E-Mail)

Project Mgr., NRR w/encl J. Caldwell, Rill w/encl C. Pederson, Rillw/encl B. Clayton, Rill w/encl SRI DC Cook w/encl DRP w/encl TSS w/encl DRS (2) w/encl Rill PRR w/encl PUBLIC IE-01 w/encl Docket File w/encl GREENS IEO (E-Mail)

DOCDESK (E-Mail)

DOCUMENT NAME: G:DRS<DCC09258.DRS To reeeNe s eo of this document Indicate In the boxt 'C' without attachment/endosure

'E' wtth attachment/enetosure

'N ~ No OFFICE NAME DATE RIII Brown:s 09

/98 RIII Gavula 09 98 RIII Bur es 09 998 Rill Grob

'9/A9 OFFICIALRECORD COPY

Enclosure 1

Attendees for Thursday, September 17, 1998, Meeting AEP John Sampson Jeb Kingseed Rick Eckstein Jeremy Euto Doug Cooper Mark Ackerman Mark Kelly Frank Pisarsky Mr. Rupricht NRC Bruce Burgess Melvin Holmberg James Gavula

~

Bruce Bartlett Joseph Maynen Brian Fuller

~h

~

~

a

~

~ y e

~

~ s

~

~

~

I

~

~

~ a a

~

~

A

~

I

~

~

~

~ ~-

a ~

~ A A

~

~

~

~

~

~

~ a

~ ~

a ~

~

A

~ A I

I A

~

~

a

~

~

~

~ ~

~

a

~ A i

~

~

A 0

~ ~

~ A

~"

~

A ~

~ 0 ~

0 g

g 0

0

~

Q r

~

I.

~

r ~

- ~ 0 ~ -.

~

r

~

~ ~

r

~

~

~

~

~

~

~ ~-

~ -

~-

r

~

~ r

~

~

~

~

~

~

r

~

s

~ ~

~

a

~ r r

r ~

~

~

~ I I

~

~

r ~

~

) a

~ ~ ~

~ A

~

~

~

~

I' I

- ~

~

a ~

~

~

~

r ~

~

~ ~

r 0 r

~

r

~

~

~

"~

~ ~ r

~ r I

DC COOK RESTART PLAN: CASE-SPECIFIC CHECKLIST MATRIX ITEM NUMBER DESCRIPTION REFER-ENCES LICEN-SEE ACTION STATUS RESPONSIBLE DATE ORGANIZATION/

CLOSED/

INSPECTION MECHAN-PLAN ISM PROGRAMMATICISSUES Programmatic Breakdown in Surveillance Testing 1A Inadequate instructions in surveillance tests.

IR 98004,5,7,9 and 97037 OPEN Resident Staff 1B Acceptance criterion lack IR 98005 sufficient margin to analysis limit.

OPEN Resident Staff 1C 1D Failure to meet technical specification requirements Preconditioning of equipment prior to surveillance testing.

IR 98005,7

~

OPEN and LER 98015-01 IR 98007 OPEN Resident Staff Resident Staff Failure to assess and control the IR 98005 quality of contractors performing surveillance testing.

OPEN Resident Staff

ITEM NUMBER DESCRIPTION REFER-ENCES LICEN-SEE ACTION STATUS RESPONSIBLE ORGANIZATION/

INSPECTION PLAN DATE CLOSED/

MECHAN-ISM Corrective Action Program Breakdown 2A Failure to promptly identify and evaluate conditions adverse to quality.

IR 98005 OPEN DRS -ECATI 2B Inadequate corrective actions for IR 98004,5,9 previously identified conditions and 97017 adverse to quality.

LERs 98010, 98017 OPEN DRS - ECATI

ITEM NUMBER DESCRIPTION REFER-ENCES LICEN-SEE ACTION STATUS RESPONSIBLE DATE ORGANIZATION/

CLOSED/

INSPECTION MECHAN-PLAN ISM Programmatic Breakdown in the Maintenance of the Design Basis 3A Inadequate design control pertaining to uncontrolled and/or unintended changes in the plant design.

IR 98004,5,7,9 and 97017 OPEN DRS - ECATI 3B 3C 3D Failure to update the Final Safety Evaluation Report.

Failure to consider instrument uncertainties, setpoints and/or instrument bias.

Inadequate consideration for system/component failure modes.

IR 98005 IR 98009 IR 98009 OPEN DRS - ECATI OPEN DRS - ECATI OPEN DRS - ECATI

ITEM NUMBER DESCRIPTION Safety Evaluations REFER-ENCES LICEN-SEE ACTION

'STATUS RESPONSIBLE ORGANIZATION/

INSPECTION PLAN DATE CLOSED/

MECHAN-ISM 4A Failure to perform safety evaluations or safety evaluation screenings.

IR 98004,7 OPEN DRS - ECATI 4B Inadequatesafetyevaluations IR98004,9 OPEN DRS - ECATI

ITEM NUMBER 5A 5B 5C 5D DESCRIPTION Operator Training Issues Training staff ability to develop technically accurate examination material in accordance with examination guidelines was considered poor.

Operator ability to determine the correct Protective Action Recommendations for the emergency event was in question.

High failure rate for the operator examinations indicated that the applicants were not well prepared.

Applicant abilities to communicate and diagnose events, during the dynamic simulator scenarios was considered weak.

REFER-ENCES IR 97305 IR 97305 IR 97305 IR 97305 LICEN-SEE ACTION STATUS OPEN OPEN OPEN OPEN RESPONSIBLE ORGANIZATION/

INSPECTION PLAN DRP -RRATI DRP - RRATI DRP - RRATI DRP - RRATI DATE CLOSED/

MECHAN-ISM

I e

s 0

0

~

~

~

A

~

~ r r

'e I I

'o II'

~

I

~ 0 0 5 5

~

~

~

~

r

~

r ~

~

~

~

~

~

~

~

~

~

~ ~

~

e

~ ~ -.e

' ll

~ ~ ~

~

r

~ r

~

~

~ I I

~

~

~

'all r

~

~ r

~

~

~

~ ~ -. ~

0

~ ~

~ r

~

~

~

~

~ I a I ~ y ~

r

~ r

~ r

~

~ ~ -. ~

R

~

~

~

r

~

~

~

~

~

~

~

R

~

0

~ ~

r

~ r

ITEM NUMBER DESCRIPTION REFER-ENCES.

LICEN-SEE ACTION STATUS RESPONSIBLE ORGANIZATION/

INSPECTION PLAN DATE CLOSED/

MECHAN-ISM Restart Plan 13 14 15 Systems and Containment Readiness Assessments Programmatic Readiness Assessment Functional Area Readiness Assessment Licensee Restart Plan Licensee Restart Plan Licensee Restart Plan OPEN OPEN OPEN DRS - ECATI DRP - RRATI DRS - ECATI DRP - RRATI DRS - ECATI DRP - RRATI DRP - Division of Reactor Projects, Region III NRC DRS - Division of Reactor Safety, Region III NRC RRATI - Restart Readiness Assessment Team Inspection ECATI - Engineering and Corrective Actions Team Inspection