ML17251A331

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Forwards Integrated Performance Assessment Team Insp Rept 50-244/88-15 on 880908-22.No Violations Noted.Programmatic Weaknesses Noted in 10CFR50.59 Safety Evaluations, Verification of Design Calculations & Adequacy of Q List
ML17251A331
Person / Time
Site: Ginna Constellation icon.png
Issue date: 10/13/1988
From: Kane W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
Shared Package
ML17251A332 List:
References
NUDOCS 8810210397
Download: ML17251A331 (4)


See also: IR 05000244/1988015

Text

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Docket No. 50-244

OCT 18 lg88

Rochester

Gas

and Electric Corporation

ATTN:

Mr. Robert

C. Mecredy

General

Manager

Nuclear Production

49 East Avenue

Rochester,

New York

14649

Gentlemen:

Subject:

Inspection

Report

No. 50-244/88-15

This report transmits the September

8-22,

1988 Integrated

Performance

Assessment'eam

inspection findings at the

R.

E. Ginna Nuclear

Power Plant,

located in Ontario,

New York.

These findings are

based

on our observation of activities, interviews,

and document reviews,

and were discussed

with you, your management,

and members

of your staff on September

22,

1988, at the conclusion of the inspection.

The inspection

reviewed

a number of functional areas with primary emphasis

on ef-

fectiveness

of RME's management

decision-making

process,

the timeliness

and ef-

fectiveness

of corrective action programs,

use of QA/QC as

a management tool, en-

gineering technical

depth

and support to operations,

and material conditions in

radiologically controlled areas.

Your operation of Ginna was found to essentially

reflect previous conclusions

from SALP Report 86-99 regarding operating

record

and

experienced

and qualified working-level staff and supervision.

However,

many pre-

vious concerns

in quality program effectiveness,

engineering

depth,

and the quality

of the physical plant environment wherein safety-related

equipment

must function,

were amplified during this inspection.

The team also identified several

important

safety questions

regarding the condensate

storage

tank level

and Appendix

R issues

for which you have

implemented certain

immediate actions but warrant additional

attention.

Several of the team's findings reflect the need for an improved safety perspective

in key elements of your organization.

For example,

fundamental

weaknesses

were

identified in programmatic

areas of importance to

NRC related to 10 CFR 50.59

safety evaluations,

verification of design calculations,

overall procedural

ad-

herence,

and the adequacy of your Q-List to support safety-related

maintenance

and

modifications.

Although

some

new and promising initiatives are evident, albeit

in the early stages

of development,

we feel that your emphasis

needs to shift to

achieve

a better balance

between reactive

and proactive activities.

This is par-

ticularly apparent

in the need for improved quality of programs

and procedures,

and

a complete understanding

of the safety bases for the Ginna design.

Your over-reliance

on experienced

and qualified personnel is, in our estimation,

not properly balanced.

There is an apparent

lack of emphasis

on the

need for sound

programs

and procedures

in order to assure

continued

safe operation of your facility

andimproved performance of your organization.

This could be particularly import-

ant in organizational

areas

where there

may be

a significant turnover of staff or

where staffing levels are currently strained.

OFFICIAL RECORD

COPY

8310210397

SS1013

PDR

ADOCK 05000244

O

PDC

DL50-244/88-15

0001.0.0

~/

09/26/88

Rochester

Gas

and Electric Company

QGT

1 3 48BS

In order to better understand

these

issues

and discuss your actions to address

them,

a management

meeting will be scheduled

shortly after your receipt of this letter.

Your c'ooperation with us is appreciated.

Sincerely,

ORfGINL SIGNED By

William F.

Kane, Director

Division of Reactor Projects

Enclosure:

NRC Region Inspection

Report

No. 50-244/88-15

cc w/encl:

Harry H. Voigt, Esquire

Central

Records

(4 copies)

Director,

Power Division

Public Document

Room

Local Public Document

Room (LPDR)

Nuclear Safety Information Center

(NSIC)

NRC Resident

Inspector

State of. New York

bcc w/encl:

Region I Docket

Room (with concurrences)

Management Assistant,

DRMA (w/o encls)

DRP Section Chief

C. Stahle,

PM,

NRR

Robert J.

Bores,

DRSS

R. Wessman,

NRR

B. Boger,

NRR

B. Clayton,

EDO

Team Members

S. Ebneter,

DRSS

T. Martin,

DRS

A. Asars,

Haddam

Neck

RI: DRP

Kaucher/meo

9/26/88

RI: DRP

1 ly

I:DRP

owgi

RI:

RP

- Bettenhausen

(0

OFFICIAL RECORD

COPY

DL50-244/88"15 - 0002.0.0

09/26/88

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