ML14174A972

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Forwards SALP Rept 50-261/87-22 for Nov 1985 - June 1987. Plant Continues to Sustain Excessive Reactor Trip Rate.Util Should Review Design & Engineering Support Based on Weaknesses in Safety Sys Design Control & Engineering
ML14174A972
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 10/06/1987
From: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Utley E
CAROLINA POWER & LIGHT CO.
Shared Package
ML14174A973 List:
References
NUDOCS 8710160052
Download: ML14174A972 (3)


See also: IR 05000261/1987022

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM

(RIDS)

ACCESSION NBR:8710160052

DOC.DATE:

87/10/06 NOTARIZED:

NO

DDCKET 4

FACIL:50-261 H.E. Robinson Plant, Unit 2, Carolina Power & Light C

05000261

AUTH.NAME

AUTHOR AFFILIATION

GRACEJ.N.

Region 2, Office of Director

RECIP.NAME

RECIPIENT AFFILIATION

UTLEY,E.E.

Carojina Power & Light Co.

SUBJECT: Forwards SALP Rept 50-261/87-22 for Nov 1985 -June 1987.

Plant continues to sustain excessive reactor trip

rate.Util

should review design & engineering support based on

weaknesses in

safety sys design control & engineering.

DISTRIBUTION CODE:

IE40D

COPIES RECEIVED:LTR I

ENCL

SIZE:

TITLE: Systematic Assessment of Licensee Performance (SALP) Report

NOTES:

RECIPIENT

COPIES

RECIPIENT

COPIES

ID CODE/NAME

L.TTR ENCL

ID CODE/NAME

LTTR ENCL

PD2-1 LA

1

0

PD2-1 PD

1

1

ECCLESTON

1

1

INTERNAL: AEOD BAILEYB

1

0

AEOD/DOA

1

AEOD/DSP/TPAB

1

1

COMMISSION

5

5

DEDRO

1

1

NRR MORISSEAUD

i

1

NRR/DEST/SIB

1

1

NRR/DLPO/HFB

1

1

NRR/DLPGIPEB

1

1

NRR/DOEA/EAB

I

NRR/DREP/EPB

1

1

NRR/DREP/RPB

1

1

NRR/DRIS DIR

1

1

NRR/PMAS/ILRB

1

1

OE LE-l

MANJ

1

1

OGC/HDS1

I

1

EG FILE

02

1

1

RGN2

FILE

01

i

1

EXTERNAL: H ST LOBBY WARD

1

1

LPDR

1

1

NRC PDR

1

1

NSIC

1

1

TOTAL NUMBER OF COPIES REQUIRED: LTTR

29

ENCL

27

OCT 0 6 18I

Carolina Power and Light Company

ATTN:

Mr. E. E. Utley

Senior Executive Vice President

Power Supply and Engineering

and Construction

P. 0. Box 1551

Raleigh, NC 27602

Gentlemen:

SUBJECT:

REPORT NO. 50-261/87-22

The

NRC Systematic Assessment of Licensee Performance

(SALP)

Board has

completed its periodic evaluation of your H. B. Robinson, Brunswick,

and

Shearon Harris facilities.

The H. B. Robinson and Brunswick facilities were

evaluated for the period of November 1, 1985 through June 30,

1987.

The

Shearon Harris facility was evaluated for the period August 1, 1986, through

June 30, 1987.

The results of the evaluation for Brunswick and Shearon Harris

were documented in the SALP Board Reports transmitted in a letter dated

September 23, 1987.

Those reports were discussed with you at the Brunswick

Visitors Center on September 30,

1987 and at the Harris Energy and Environ

mental Center on October 1, 1987.

The results of the evaluation for H. B.

Robinson are documented in the enclosed SALP Board Report,

and will be

discussed with you at the Robinson Visitors Center on October 13, 1987.

The performance of your H. B. Robinson facility was evaluated in the functional

areas of plant operations, radiological controls, maintenance, surveillance,

fire protection, emergency preparedness, security, outages, quality programs

and administrative controls affecting quality, licensing activities, training,

and engineering support.

As in our September 23,

1987 letter, several performance aspects of H. B.

Robinson relate to the overall performance of Carolina Power and Light Company

(CP&L).

Robinson has maintained a higher than national average collective

annual dose, similar to the performance of Brunswick. As in Brunswick's case

annual exposure is improving, but having two out of three of your plants being

above the national average concerns us over the future performance of Shearon

Harris and the ability of CP&L to expeditiously address and solve this utility

problem. Although, overall plant operations is satisfactory, Robinson continues

to sustain an excessive reactor trip rate, even though a trip reduction program

was instituted during the previous assessment period.

CP&L management should

review this continuing problem. The area of engineering support is an optional

assessment area, based on facility engineering and design activity. At Robinson,

a Safety System Functional Inspection (SSFI) identified a number of weaknesses

in safety system design control and engineering. We are concerned not only about

the problems identified at Robinson, but also that these weaknesses may have

caused problems in other Robinson systems and in systems at Brunswick and

Harris.

CP&L should review design and engineering support at all three

facilities, in light of the SSFI findings.

8710160052 871006

PDR

ADOCk 0!5000261

a

PDR

Carolina Power and Light Company

2

Any comments you have concerning our evaluation of the performance of your

facility should be submitted to this office within 30 days following the date

of our meeting at your H. B. Robinson facility on October 13,

1987.

Your

comments, summaries of our plant specific meeting, and my disposition of your

comments will be issued as appendices to the enclosed SALP Board Report.

Should you have any questions concerning this letter, we will be glad to

discuss them with you.

Sincerely,

4.

4ELSO>

J. Nelson Grace

Regional Administrator

Enclosure:

SALP Board Report - H. B. Robinson

cc w/encls:

G. P. Beatty -

Vice President

Robinson Nuclear Project Department

R. E. Morgan -

Plant General Manager

bcc w/encls:

NRC Resident Inspector -

H. B. Robinson

Document Control Desk

State of South Carolina

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