ML20127D652

Ack Receipt of 920821 Response to Emergency Preparedness Weaknesses Noted in Insp Rept 50-482/92-13 on 920720

ML20127D652
Person / Time
Site:	Wolf Creek
Issue date:	09/04/1992
From:	Beach A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
References
NUDOCS 9209150113
Download: ML20127D652 (5)

See also: IR 05000482/1992013

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Docket No, STN 50-482

License No, NPF-42

Wolf Creek Nuclear Operating Corporation

ATTN:

Bart D. Withers

President and Chief Executive Officer

P.O. Box 411

Burlington, Kansas 66839

Gentlemen:

SUBJECT: NRC INSPECTION REPORT N0. 50-482/92-13

Thank you for your_ letter of August 21, 1992, in response to the emergency

preparedness weaknesses identified in NRC Inspection Report 50-482/92-13 datea

July 20, 1992. -We have examined your reply and find - it responsive to the

concerns raised in our inspection report. We will review the implementation of

your corrective actions during a future inspection.

Sincerely,

.I

dr. Bill Beach, Director

Divisien of Reactor Projects

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.cc:

Wolf Creek Nuclear Operating Corp.

ATTN:

Otto Maynard, Director

Plant Operations

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P.O. Box 411

Burlington, Kansas 66830

Shaw, Pittman, Potts.& Trowbridge

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ATTN: Jay Silberg, Esq.

2300 M Street, NW

Washington, D.C.

20037

920913o113 920904

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Wolf Creek Nuclear

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Operating Corporation

Public Service Commission

ATTN:

C. John Renken

Policy & Federal Department

P.O. Box 360

Jefferson City, Missouri

65102

U.S. Nuclear Regulatory Commission

ATTN:

Regional Administrator, Region 111

799 Roosevelt Road

Glen Ellyn, Illinois 60137

Wolf Creek Nuclear Operating Corp.

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ATTN:

Steven G. Wideman

Supervisor Licensing

P 0. Box 411

Burlington, Kansas 66839

Kansas Corporation Commission

ATTH:

Robert Elliot, Chief Engineer

Utilities Division

1500 SW Arrowhead Rd.

Topeka, Kansas 66604-4027

Office of the Governor

State of Kansas

Topeka, Kansas 66612

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Attorney General

1st Floor - The Statehouse

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Topeka, Kansas 66612

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Thuirman, Cof fey. County Commission

Coffey tounty Courthouse-

Burlington,. Kansas 66839-1798

Kansas Department of Health

and Environment

Bureau of Air Quality 3 P.adiaticn

Control

ATIN: Gerald Allen, Public

Health Physicist

Division'of Environment

Forbes Field Building 3?.1

-Topeka, Kansas 66620

Kansas Department of Health and Environment

ATTN:

Robert Eye, General Counsel

LS00, 9th Floor

900 SW Jackson

Topeka, Kansas 66612

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J. L. Milhoan, RA

L. J. Callan DRSS

J.-P. Jaudon, DRSS

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D. B. Spitzberg, FIPS

Resident inspector, OPS - Wolf Creek

A. Howell, Section Chief. DRP/0

Lisa Shea, RM/Alf (MS 4503)

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J. L. Milh an, RA

L. J. Lallan, DRSS

J. P. Jaudon, DRSS

B. Murray, flPS

D. B. Spitzberg, flPS

Realdent inspector, OPS - Wolf Creek

A. Howell, Section Chief, DRP/D

Lisa Shea, RM/ALF (MS 4503)

Section Chief, (Rlli, DRP/3C)

Callaway, Rlli

flPS file

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August 21, 1992

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WM 92-0135

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U. 3. Nuc?. car Regulatory cornission

ATTH:

Document Control Denk

hall Station F1-137

washington,

D. C.

20555

Reference:

Letter dated July 20, 1992 from A. B.

Be a c'

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B. L. Withers, WCNOC

'3P 3-01,

Subjecti

Docket No. 50-482:

Response to weaknesses

.

482/9213-02 and 482/9213-03

Gentlemen:

This letter prov. des Wolf Creek Nuclear Operating Corporation's response to

Weaknesses 482/9213-01,

482/9213-02 and 482/9213-03 as a result of an

inspection of the operational status of the emergency preparedness progren and

dose calculation and assessment.

Weakness 482/9213-01 involved emergency

classification of accident conditions by operating crews.

Weaknesa 9213-02

consisted of several exemples of errors and umissions in notification messages

and in the formulation and issaance of protective action recommendations.

Weakness 482/9213-03 identified the failure of the dose assessment procedure

to previde guidance on obtaining accurate integrated dose projections based on

prior release conditions.

If you have any questions concerning this matter, please contact me or

Mr. Kevin J. Moles of my staff.

Very truly yours,

J _Af

Bart D. Withers

President and

Chief Executive officer

DDW/jra

Attachment

cc:

A. T. howell (NRC), w/a

J. L. Milhoan (URC), w/a

G. A.

Pick (NRC), w/a

W.D.

Reckley (NRC), w/a

D.

B.

Spitsberg (N RC) , w/a

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PO Box 411 i Burbngton, KS 66839 Phone (316) 2%BB31

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Attachment to WM 92-0135

Page 1 of 3

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Weakness (482/9213-01)!

Eminenev ClatalligAlion of Accident conditions.

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The inspector ebserved and evaluated the ability of each crew to detect,

assess, and classify abnormal and accident conditions. Two out of three crews

f ailed to recognire that emergency action level initiating conditions had been

met for a scenario event.

Consequently, the two shift supervisors did not

declare a Site Area Emergency when they became aware of plant conditions

indicating a breach of, or challenge to the integrity of two fission product

barriers.

Specifically, fuel cladding was challenged as the result of an

anticipated transient without trip, and containment was breached because of a

steam generator atmospheric relief valve that was stuck open and unisolable.

These conditions met the emergency action level for a Site Area Emergency

contained in EPP 01-2.1, " Emergency Classification."

Analysist

During inter *.4ews with operators it was evident that Emergency Plan Procedure,

EPP 01-2.1,

" Emergency Classification" phraseology lead to the weakness.

The

wording in Step 3.6.3 of procedure EPP 01-2.1 can lead to confusion in

clasAlfying a containment breach when coupled with another fission product

barrier breach,

fdgnpetive Actionst

Proceauce EPP 01-2.1 will be revised to clarify Step 3.6.3.

A course titled,

" Emergency Plan Practical" will be retaught during the current operator

requalification' training

cycle.

Classifications

made

dt. ring

the

requalifis ation training by each operating crew will also be reviewed.

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p.gte When Corrective Action Will Be Comoleted:

Procedure EPP 01-2.1 will be revised by October 30, 1992 and issued within 30

days of NRC approval.

The current operator requalification training cycle

will be completed September 11, 1992.

Review and critique of classifications

made by operating crews are conducted after_each session on the simulator and

will also be completed by September 11, 1992.

Weakness (482/9213-02):

Notifications and Protective Action Recommendations

Made to Offsite Authorities

Errors and omissions in notification messages and in the formulation and

issuance of protective action recommendations were identified during the

walkthroughs as evidenced by several observations.

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Attachment to WH 92-0135

Page 2 of 3

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only the classification section of Patt A f An the Immediate Notification Form

is reviewed during Opetator Requalification Examinations

Tnerefore, only

.

this section has been emphasized during training.

This has resulted in

inexperience in completing the entire notification form.

g,orrectivtletiong

Simulator training scenarios will

be

reviewed to ensure

they contain

sufficient detail for the instructor to evaluate if the Immediate Notification

Form has been completed correctly.

During all future simulator sessions, with

the exception of practice examinations and requalification examinations, all

of Part A of the Immediate Notification Form will be completed by the Shift

Supervisar.

The form will be evaluated with the Shift Supervisor as part of

the crit Aq.e

session.

Annually,

Emergency Plan personnel

or Training

personnel 3111 monitor each crew for proper form completion.

Date When Corrective Action 2 Will Be Completed:

In order to allow several opportunities for each crew to be on the simulator,

corrective actions will be completed by March 31, 1993.

Weakness (482/9213-03):

Tailure of the Dose Assessment Procedure to Providg

GuidaDCm htAining Accurate Intearated Dose

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Proiecticns Unsed on Prior Release Conditions

one crew was unable to obtain an accurate estimate of the offsite radiological

consequences of the release, because the dose assessment procedure did net

provide guidance for initiating a dose projection after initial release

conditions 1:ad changed significantly.

In this case, the chemictry technician

had been dispatched from the centrol room by the emergency director prior to

the release to obtain steam tenerator samples.

When he returned, the release

had been in progress for approximately 20 minutes.

The chemistry technician

then promptly

calculated the

initial

post-release dose projections

in

accordance with EPP 01-7.2 but used real time flow data from the release

source.

At the time, however, the flow had decreased about 70 percent since

the onset of the release because of depressurization.

Therefore, this dose

projection did not provide an accurate assessment of the consequences of the

release from the time it began,

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Attachment to WM 92-0135

P3ge 3 of 3

6a011Elit t

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A review of this weakness determined that procedure EPP 01-7.2, "Cottputer Dose

calculations," does not provide guidance to obtain the highest flow or release

rates from the beginning of a release.

Correct ive_.ACLA2aA 1

Procedure EPP 01-7.2 will be revised to provide more complete guidance.

Training for personnel performir.g dose calculations will be provided following

issuance of procedure EPP 01-7.2.

All other dose assessment personnel will

complete required reading on procedure EPP

01-7.2.

Chemistry personnel

continue to train on the simulator with the operating crews to provide them

,

with control room experience.

Date When Corrective Acti2D8 Willle CCerittadt

Procedure

EPP 01-7.2 will be revised and issued by October 30,

1992.

R6 quired reading will be completed within 60 days of issuance of the required

reading notice.

Training for personnel performing dose assessment will be

completed by March 31, 1993,

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