ML17279A927

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Forwards Mgt Meeting Rept 50-397/88-07 on 880301.Topics Discussed Listed
ML17279A927
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 03/16/1988
From: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Mazur D
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
Shared Package
ML17279A928 List:
References
NUDOCS 8804040225
Download: ML17279A927 (4)


See also: IR 05000397/1988007

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION

NBR: 8804040225

DOC. DATE: 88/03/16

NQT*Rl ZED:

NO

FACIL: 50-3cij'7

WPPSS Nuclear

Pro Jecti

Unit 2i

Washington Public

Poee

AUTH.'NAME

AUTHOR AFFILI*TION

MARTINiJ. B.

Region

5i

Qfc of the Director

REC IP. NAME

RECIPIENT AFFILIATION

MAZURi D. W.

Washington Public

PoUJer

Supply

System

SUBJECT:

Foreard s

Mgt Meeting Rept 50-397/88-07

on 880301. Top ics

discussed

listed.

DISTRIBUTION CODE;

IEOID

COPIES

RECEIVED. LTR

I

ENCL J

SIZE;

TITLE: General

(50 Dkt)-Insp Rept/Notice

of Violation Response

NOTES:

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EXTERNAL:

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NRC

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TOTAL NUMBER QF COPIES

REQUIRED:

LTTR

22

ENCL

22

"'MR 16

1gg8

Docket No. 50-397

Washington Public Power Supply System

P.O.

Box 968

Richland, Washington

99352

Attention:

Mr.

D.

W. Mazur

Managing Director

Gentlemen:

Subject:

Management

Meeting

This refers to the Management

Meeting held with Mr. A.

L. Oxsen

and other

members of the Supply System staff at the Region

V office on March 1, 1988.

The purpose of this meeting

was to discuss

items of interest pertaining to the

activities authorized

by NRC license

NPF-21.

Subjects

discussed

during the

meeting are

summarized

in the enclosed

meeting report 50-397/88-07.

The following topics were given special

emphasis

in our discussions

during this

meeting:

1.

We discussed

the reactor building roof overpressurization

event

experienced

on February 14,

1988 and the root cause

assessment

conducted

by your staff.

While the Supply System

appeared

to have

done

a thorough

root cause

assessment,

we expressed

concern that your management

did not

place

more emphasis

on the

human performance

aspects

of this event.

Specifically, it appeared

that the plant staff did not fully appreciate

the concept of not proceeding with an activity until anomalous

equipment

bahavior or indications are understood.

It was agreed that this concept

would be reemphasized

to the plant staff before restart.

2.

Your staff could not give assurance,

based

on thorough

system testing,

that controls,

alarms,

and protective trips associated

with the reactor

building ventilation system would perform as intended

by the design

bases.

We noted that additional

emphasis

needed to be given'to complete

end-to-end testing of system features

(such

as the high and low pressure

trips of the ventilation fans).

We agreed during the meeting that this

testing of the reactor building ventilation system would be accomplished

before plant restart.

3.

The potential

impact of balance-of-plant

system failures

was discussed

briefly.

We stated that your staff should assess

whether

other balance-

of-plant fai lures could adversely

impact the operation or integrity of

safety-related

systems.

4.

We noted that our previous meeting

on February 4,

1988

had included

a

discussion of design-related

issues

and the program you are undertaking to

correct problems identified in the design area.

The design problems

found

8804040225

88000

g031b

PDR

ADOCK 0

PDR

6

-2"

in the reactor building ventilation system,

as discussed

during our

March 1 meeting, further illustrated this concern.

In addition, the

errors identified in Anticipated Transient Without Scram

(ATWS) design

change

packages

issued for installation

have raised serious

questions

regarding the effectiveness

of your current program for performing design

and design review activities.

We intend to conduct further assessments

of

the quality of your design activities,

and encourage

you to do the

same.

5.

We expressed

continuing interest in the performance of your quality

oversight groups (the Nuclear

Safety Assurance

Group and gA/gC

organization)

and the need for these

groups to assume

a more active role

in the identification and correction of human performance

and design

problems

such

as those discussed.

Completion of the testing

and briefings discussed

in items

1 and

2 above,

respectively,

was

documented

in Mr. A.

L. Oxsen's letter dated

March 5, 1988,

which was given to our Senior Resident

Inspector

before plant startup.

We

would anticipate further discussion .of items 3, 4,

and

5 above during our next

management

meeting.

In accordance

with 10 CFR 2.790(a),

a copy of this letter and the enclosure

will be placed in the

NRC Public Document

Room.

Should you have

any questions

concerning this meeting,

we will be glad to

discuss

them with you.

Q-ibiWI6(

J.

B. Martin

Regional Administrator

Enclosure:

Inspection

Report

No. 50-397/88-07

cc w/enclosure:

C.

M. Powers,

WPPSS

P.

L. Powell,

WPPSS

R.

B. Glasscock,

WPPSS

G.

E.

Doupe,

Esq.,

WPPSS

A.

L. Oxsen,

WPPSS

State of WA

N.

S.

Reynolds,

Esq.,

BLCP8R

bcc w/enclosure:

Resident

Inspector

Project Inspector

D. Persinko,

NRR

G.

Cook,

RV

B. Faulkenberry,

RV

J. Martin,

RV

docket file

bcc w/o enclosure:

LFMB

M. Smith

REGION V

CCaldwe

ot

Phial

n

3//$ /88

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3/15/88

3/7( /88

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