ML17335A391
| ML17335A391 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/09/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Powers R AMERICAN ELECTRIC POWER CO., INC. |
| Shared Package | |
| ML17335A392 | List: |
| References | |
| 50-315-98-25, NUDOCS 9812160089 | |
| Download: ML17335A391 (8) | |
See also: IR 05000315/1998025
Text
CATEGORY 2
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
CCESSION NBR:9812160089
DOC.DATE: 98/12/09
NOTARIZED: NO
DOCKET
FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana
M
05000315
AUTH.NAME
AUTHOR AFFILIATION
GROBE,J.A.
Region
3
(Post
820201)
RECIP . NAME
RECIPIENT AFFILIATION
POWERS,R.P.
American Electric Power Co., Inc.
SUBJECT:
Forwards insp rept 50-315/98-02
on 981112-19.No violations
noted.
RECIPIENT
ID CODE/NAME
PD3-3
COPIES
LTTR ENCL
1
1
RECIPIENT
ID CODE/NAME
STANG,J
COPIES
LTTR ENCL
1
1
DISTRIBUTION CODE: IEOlF
COPIES
RECEIVED:LTR
ENCL
SIZE:
TTTLE: General
(50 Dkt)-Insp Rept/Notice
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NOTES:
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'OTE TO ALL "RZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DZSTRZBUTION LISTS
OR REDUCE THE NUMBER OF COPIES
RECEZVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL
DESK
(DCD)
ON EXTENSION 415-2083
TOTAL NUMBER OF COPIES
REQUIRED:
LTTR
17
ENCL
17
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'
December 9,
1998
Mr. R. P. Powers
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, Ml 49107-1395
'UB
JECT:
NRC INSPECTION REPORT NO. 50-315/98025(DRS)
Dear Mr. Powers:
On November 19, 1998, the NRC completed a special inspection at your D. C. Cook, Unit 1
reactor facility. The inspection was an examination of'activities conducted under your license as
they relate to your establishment of restart metric indicators to gage plant readiness for restart
and to evaluate the progress in engineering resolution of ice condenser issues.
Because the
restart metrics factor into your assessment
of plant readiness for restart, the NRC Manual
Chapter 0350 Restart Panel willcontinue to monitor your progress in meeting established
performance goals for these metrics. The enclosed report documents the results of the
inspection.
4
'he 22 restart metric indicators developed, demonstrated
substantive progress toward
achieving a data collection system to provide semiguantitative measurement tools for assessing
plant process and programmatic readiness for restart.
The metric performance indicators with
more potential value measured process product quality, such as 50.59 Quality, Calculation
Quality and Root Cause Quality, or effectiveness, such as Corrective Actions Effectiveness.
A recent Performance Assurance department assessment
identified weaknesses
in the grading
process used for safety evaluations, which indicated that more work is needed to effectively
implement the restart metric indicator of 50.59 Quality. Additionally, the corrective action for this
finding, to mentor engineering department personnel, may artificiallyinfluence the safety
evaluation quality measurement for engineering.
Progress was observed in engineering resolution of issues pertaining to the ice condenser with
the establishment of ice basket damage criteria and a systematic approach to incorporation of
ice condenser information into the Updated Final Safety Analysis Report.
However, resolution
of previous NRC ice condenser findings had not progressed to a point that supported a final
NRC review.
In accordance with 10 CFR 2.790 of the NRC'S "Rules of Practice," a copy of this letter, the
enclosures,
and your response to this letter, ifyou choose to provide one, willbe placed in the
NRC Public Document Room (PDR).
98i2fh0089
98%209'DR
ADQCK 050003i5
8
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+a*++
UNITED STATES
NUCLEAR REGULATORYCOMMISSION
REGION III
801 WARRENVILLEROAD
USLE, ILUNOIS60532-4351
December 9, 1998
Mr. R. P. Powers
Senior Vice President
Nuclear Generation Group
American Electric Power Company
500 Circle Drive
Buchanan, MI 49107-1395
SUBJECT:
NRC INSPECTION REPORT NO. 50-315/98025(DRS)
Dear Mr. Powers:
On November 19, 1998, the NRC completed a special inspection at your D. C. Cook, Unit 1
'eactor facility. The inspection was an examination of activities conducted under your license as
they relate to your establishment of restart metric indicators to gage plant readiness for'restart
and to evaluate the progress in engineering resolution of ice condenser issues.
Because the
restart metrics factor into your assessment
of plant readiness for restart, the NRC Manual
Chapter 0350 Restart Panel willcontinue to monitor your progress in meeting established
performance goals for these metrics. The enclosed report documents the results of the
'nspection.
The 22 restart metric indicators developed, demonstrated
substantive progress toward
achieving a data collection system to provide semi-quantitative measurement tools for assessing
plant process and programmatic readiness for restart.
The metric performance indicators with
more potential value measured process product quality, such as 50.59 Quality, Calculation
Quality and Root Cause Quality, or effectiveness, such as Corrective Actions Effectiveness.
A recent Performance Assurance department assessment
identified weaknesses
in the grading
process used for safety evaluations, which indicated that more work is needed to effectively
implement the restart metric indicator of 50.59 Quality. Additionally, the corrective action for this
finding, to mentor engineering department personnel, may artificiallyinfluence the safety
evaluation quality measurement for engineering.
Progress was observed in engineering resolution of issues pertaining to the ice condenser with
the establishment of ice basket damage criteria and a systematic approach to incorporation of
ice condenser information into the Updated Final Safety Analysis Report.
However, resolution
of previous NRC ice condenser findings had not progressed to a point that supported a'final
NRC review.
In accordance with 10 CFR 2.790 of the NRC'S "Rules of Practice," a copy of this letter, the
enclosures, and your response to this letter, ifyou choose to provide one, willbe placed in the
NRC Public Document Room (PDR).
I.
il',
. R. Powers
We willgladly discuss any questions you have concerning this inspection.
Sincerely,
Original /s/ John A. Grobe
John A. Grobe, Director
Division of Reactor Safety
Docket No.: 50-315
License No.: DPR-58
Enclosure:
Inspection Report 50-315/98025(DRS)
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)
RPC (E-Mail)
Project Mgr., NRR w/encl
J. Caldwell, Rillw/encl
C. Pederson, Rill w/encl
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DRP w/encl
TSS w/encl
DRS (2) w/encl
Rill PRR w/encl
Q~P.UBL'IC'IE-'01'/enyct,'.;~~
Docket File w/encl
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IEO (E-Mail)
DOCDESK (E-Mail)
DOCUMENT NAME: G:DRS(DCC98025.wpd
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