ML20235X183

From kanterella
Jump to navigation Jump to search
Forwards Safety Insp Repts 50-266/87-18 & 50-301/87-18 on 870914-17.No Violations Noted.Summary of Three Exercise Weaknesses Which Require Corrective Actions Encl
ML20235X183
Person / Time
Site: Point Beach  
Issue date: 10/14/1987
From: Shafer W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Fay C
WISCONSIN ELECTRIC POWER CO.
Shared Package
ML20235X187 List:
References
NUDOCS 8710190245
Download: ML20235X183 (3)


See also: IR 05000266/1987018

Text

sg

me

l'

'

Md '

i

f,

'

h*

' , ,

,

h,.

~

.

~

.c

<

OCT L41987

.i

Docket No. 50-266E

f

Docket No. 50-301'

<-

.

.

LWisconsin Electric' Power Company.

'ATTNif Mr. C. W. Fay

'

. le President

_

. . .

. Nuclear Power Department

,

-:231 West. Michigan, Room 308'

$.

.; Milwaukee,'WI_ 53201

c., .

,

'Q di

-

!

Gentlemen:

.

~ y-C

~

l

'

~o

'This refers to'the routine safety inspection conducted by Mr. J. Foster a

f

.

-others of this office on September 14-17, 1987, of activities at the Poin

va

,

Beach-Nuclear.Powe'r' Plant', Units 1 and'2, authorized by NRC Facility Ope

ing

' Licenses No. DPR-24 and No. DPR-27, and to the discussion of our finding g ith

Mr.' J. Zach and others of your staff at the conclusion of the inspection.

-

l

The. enclosed copy ~ of'our inspection report identifies areas examined during

q

the inspection. . ithin these areas, the inspection consisted of a selective

!

W

examination of procedures and representative records, observations, and

interviews with personnel.

No violations of NRC' requirements were identified.during the course of this

inspection.

However, three weaknesses were identified which will requira

corrective actions.

'inese weaknesses are summarized in the attached Appendix

to this-letter.

As required by 10 CFR Part.50, Appendix E (IV.F), any

' weaknesses that are identified must be corrected.

Accordingly, you are

requested to advise us within 45 days of the date of this letter of the

corrective action you'have taken or plan to take, showing the; estimated

date of completion with regard to these exercise weaknesses.

In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of

this letter, and the enclosures, will be placed in the NRC Public Document

Room.

/

qb

<

e

8710190245 B71014

{DR

ADOCX 05000266

PDR

,

- --_ --___ _- - _-_ _ _ -

_

_ _ _ _ _ _ _ - _ _ - _ _ _

_ _ _ _

-

_ _ - _ - _ _ _ - _ _ _ _ _

_ -

_ _ _ _ _ _ _ _ _ _ _

_ _ _ - _ - _ - _ _ - _

_ _ _

_ _ -

.;

.-

.V

Wisconsin Electric Power Company

2

OCT 141987

We will' gladly' discuss'any questions ~you h' ave'concerning this~ inspection.

Sincerely,

.

" Original signed by VI.D. Shafor"

W. D. Shafer, Chief

'i

-

'

Emergency Preparedness and

-l

.

Radiological Protection

Branch

Enclosures:

1. ' Appendix,, Exercise Weaknesses-

!

-2.

Inspection Reports

'

No. 50-266/87018(DRSS);

No.-50-301/87018(DRSS)

cc w/ enclosures:

J..J. Zach, Plant Manager

DCD/DCB (RIDS).

Licensing Fee Management Branch

Resident Inspector, RIII

l.

Virgil Kanable, Chief

'

Boiler Section

Charles ~ Thompson, Chairman

Wisconsin Public Service

Commission

'R. I, Braund (SLO),.

WI.Div. of Emergency Government

Lawrence J.,McDonnell, Chief

Radiation Protection Section

WI Department of-Health and

Social. Services,- Division

of Health

W. Weaver, FEMA,_ Region V

D. Matthews, NRR, EPB

l

1

1

i

RIII.

RII

RII

RII

RII

RIII

RIII

b/

h

hW

i@yfe/mb

P(u) 4er0n

eaettelj

Sm

ne

Pe4rd 7 qcy ip

a iy

Fo

r

}.

w

.

,

_ -_

..

.

EXERCISE WEAKNESSES

1.

The Medical Drill was inadequate.

The team responding to the injured

man did not take along any first aid equipment (first aid kit, trauma kit,

stretcher).

Once the medical team arrived at the scene of the injury, no

first aid actions or concerns were demonstrated, and the team members took

no actions for 30 to 35 minutes.

Excessive simulation of actions

(simulated evacuation of victim, simulated ambulance) further degraded

the demonstration (Item No. 266/87018-02; 301/87018-02) (Section 5.d).

2.

At times, information flow from the Technical Support Center (TSC) was

inadequate.

The Emergency Operations Facility (EOF) staff misunderstood

aspects of plant status and the significance of the (scenario) fire for

more than an hour after it began.

The E0F staff also did not understand

why the TSC escalated to a General Emergency condition.

This appeared to

be caused by a lack of information from the TSC on the location of the

fire and a related problem with the filter dampers.

Associated with this

was the failure to recognize the significant increase in the release rates

being measured by the auxiliary building vent monitor

(Item No. 266/87018-03; 301/87018-03) (Section 5.f).

3.

Various problems in the operation of the EOF were observed, due to

inadequate staffing.

This resulted in the Radcon/ Waste Manager, the E0F

Communicator, and The Assistant Radcon/ Waste Manager being significantly

overburdened with functions and duties.

(Item No. 266/87018-04;

301/87018-04) (Section 5.f).

I

_ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ .