ML17286A392

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Forwards Insp Rept 50-397/90-20 on 900904-13.No Violations Noted.Insp Identified Three Deviations in Areas of EOPs
ML17286A392
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/23/1990
From: Zimmerman R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
Shared Package
ML17286A394 List:
References
NUDOCS 9011080210
Download: ML17286A392 (6)


See also: IR 05000397/1990020

Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9011080210

DOC ~ DATE: 90/10/23

NOTARIZED:

NO

DOCKET ¹

FACIL:50-397 WPPSS Nuclear Project,

Unit 2, Washington Public

Powe

05000397

AUTH.NAME

AUTHOR AFFILIATION

MMERMAN,R.P.

Region

5 (Post

820201)

CIP.NAME

RECIPIENT AFFILIATION

RENSEN,G.C.

Washington Public Power Supply System

SUBJECT: Forwards

Insp Rept 50-397/90-20

on 900904-0913.No violations

noted.

DZSTRZBUTZON CODE:

ZEOZD

COPZES

RECEZVED:LTRj ENCL J

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TITLE: General

(50 Dkt)-.Insp Rept/Notice of Violation Response

NOTES:

RECIPIENT

ID CODE/NAME

PD5

PD

INTERNAL: ACRS

AEOD/DEIIB

DEDRO

NRR SHANKMAN,S

NRR/DREP/PEPB9D

NRR/DST/DIR 8E2

NUDOCS-ABSTRACT

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ID CODE/NAME

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NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK,

ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION

LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES

REQUIRED:

LTTR

23

ENCL

23

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Docket No. 50-397

UNITED STATES

NUCLEAR REGULATORY COIVlIVIISSION

REGION V

1450 IVIARIALANE,SUITE 210

WALNUTCREEK, CALIFORNIA94596

OCT g g tgw

Washington Public Power Supply System

P. 0.

Box 968

3000 George Washington

Way

Richland,

Washington

99352

Attention:

Mr. G. C. Sorensen,

Manager

Regulatory

Programs

Gentlemen:

Subject:

NRC Emergency Operating

Procedures

Team

Inspection at Washington Nuclear Project

No.

2

(WNP-2)

This refers to a special,

announced

team inspection of your emergency operating

procedures,

conducted

by the

NRC, at the

WNP-2 site from September

4 - 13, 1990.

The findings and details of this report were discussed

during the inspection,

and summarized

during the exit meeting with members of your staff identified

in the enclosed

inspection report.

Areas evaluated

during the inspection included the review of your Emergency

Operating

Procedures

(EOPs),

EOP support

procedures

(ESPs),

some supporting

procedures

involved in the use of EOPs,

the documents

used to develop the

EOPs, the

EOP verification and validation program,

and the

EOP training and

evaluation

program.

The inspection included plant walkdowns of the

EOPs

and

EOP support procedures

with operators,

evaluation of a crew's performance

in

the simulator,

and

a human factors evaluation.

The team determined that the

WNP-2 EOPs,

when used

by trained operators,

appeared

adequate

to mitigate emergency situations.

However, they were, in

some instances, difficult for operators

to use, with the potential for causing

safety significant errors.

The team identified three deviations

from the Boiling Water

Reactor

Owners'roup

{BWROG), Emergency

Procedure

Guidelines

{EPGs), Revision 4, that are of

specific concern.

The acceptability of your justifications for these

deviations could not be determined

by the inspectors.

These three

items

have

been referred to the Division of Reactor Projects, Office of Nuclear Reactor

Regulation

(NRR), for further evaluation.

Furthermore,

the team considered

that the development of the

EOP writer'

guide,

and the implementation of the verification and validation program for

the

EOPs,

were marginal.

This resulted

in procedures

that, in places,

were

difficult for operators

to use, with a potential for causing safety-significant

errors.

The team also noted that

human factors considerations

in this program

were lacking, particularly, in its validation aspects.

Two detailed findings were of particular

concern.

First,

one deficiency

involved the lack of EOP guidance for determining the temperature

near

9011080210

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G

PNU

AT)> Nx

Reactor Pressure

Vessel

(RPV) level instrument

runs in the secondary

containment.

This information is essential if operators

are to correctly

apply

EOP 5.0.0,

Caution I, "RPV Saturation

Temperature."

Second,

our

inspectors

found that your staff had

made errors in transcribing

some of the

approved engineering

derived curves to

EOP 5.0. 1,

"EOP Graphs," Revision 0.

Some of these errors

would have allowed operations

in the area defined

by

engineering

as unsafe.

Your letter responding to this finding should address

the potential

generic applicability of this issue to other curves

used in the

EOPs.

These findings were discussed

with the members of your staff identified in the

attached report.

You are requested

to respond to these findings, documenting your proposed

corrective actions,

including the schedule for the completion of these

corrective actions, within 30 days.

In accordance

with 10 CFR 2.790(a),

a 'copy of this letter and the enclosures

will be placed in the

NRC Public Document

Room.

The response

directed

by this letter is not subject to the clearance

procedures

of the Office of Management

and Budget

as required

by the Paperwork Reduction

Act of 1980,

PL 96-511.

Should you have

any questions

concerning this inspection,

we will be pleased

to

discuss

them with you.

Sincerely,

E2 ~g,

Roy P.

Zimmerman, Director

Division of Reactor Safety

and Projects

Enclosure:

NRC Inspection Report 50-397/90-20

cc w/enclosure:

Mr. J.

W. Baker,

WNP-2 Plant Manager

Mr. A. G. Hosier,

WNP-2 Licensing Manager

Mr. G. D. Bouchey, Director, Assurance

& Licensing

Mr. G. E. Doupe, Esq.,

WPPSS

Mr. A Lee Oxsen,

Deputy Managing Director

State of WA (Mr.Curtis Eschels)

Mr. M. H. Phillips, Attorney

Bishop,

Cook, Purcell

& Reynolds

OCT 2 3

)goo

bcc w/enclosure:

Docket File

Resident

Inspector

Project Inspector

G.

Cook

B. Faulkenberry

J. Martin

Mr. J. Wermiel, Branch Chief,

NRR/LHFB

M. Jordan, RIII

D. McNeil, RIII

A. Suthoff,

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