Text

Forwards Insp Repts 50-266/97-05 & 50-301/97-05 on 970208-0314.No Violations Noted
	ML20140C557
Person / Time
Site:	Point Beach
Issue date:	04/03/1997
From:	Grobe J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Patulski S; WISCONSIN ELECTRIC POWER CO.
Shared Package
ML20140C561	List: IR 05000266/1997005; ML20140C557;
References
	EA-97-075, EA-97-75, NUDOCS 9704170121
	Download: ML20140C557 (3)
	v • d • e

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April 3,1997

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EA 97-75

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Mr. S. A. Patuiski, Site Vice President

Point Beach Nuclear Plar t

6610 Nuclear Road

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Two Rivers, Wisconsin 54241

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SUBJECT:

POINT BEACH NRC INSPECTION REPORT NO. 50-266/301/97005(DRP)

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Dear Mr. Patuiski:

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On March 14,1997, the NRC completed a special inspection at your Point Beach 1 and 2

reactor facilities. The enclosed report presents the results of that inspection. The

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inspection was conducted to review the use of manual operator action to maintain the

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train A motor-driven auxiliary feedwater (MDAFW) pump operable during an accident. This

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issue was previously described as an unresolved item in the NRC Operational Safety Team

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Inspection Report No. 50-266(301)/96018.

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In April 1996, Point Beach staff determined in two safety evaluations related to this issue

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that an unreviewed safety question did not exist. However, in our subsequent review, we

have determined that the use of manual operator action to maintain the pump operable did

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involve an unreviewed safety question. Based on the unreviewed safety question, we -

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have identified an apparent violation of 10 CFR 50.59 for changing the automatic

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operation of train A of the MDAFW system, which is described in the Final Safety Analysis

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Report, without prior NRC approval.

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The apparent violation identified is being considered for escalated enforcement action in

accordance with the " General Statement of Policy and Procedure for NRC Enforcement

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Actions" (Enforcement Policy), NUREG-1600. No Notice of Violation is presently being

issued for this apparent violation in addition, be advised that the number and

characterization of the apparent violation described in the enclosed inspection report may

change as a result of further NRC review.

As stated at the inspection exit meeting on March 17,1997, we request that you discuss

this apparent violation at the rredecisional enforcement conference scheduled for April 9,

1997, to address the four apparent violations identified in Inspection Report No. 50-

266(301)/96018. The decision to hold a predecisional enforcement conference does not

mean that the NRC has determined that the violation occurred or that enforcement action

will be taken. This conference is being held to obtain information to enable the NRC to-

make an enforcement decision, such as a common understanding of the facts, root

causes, missed opportunities to identify the apparent violation sooner, corrective actions,

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significance of the issue, and the need for lasting and effective corrective action. In

addition, this is an opportunity for you to provide any information concerning your

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perspectives on 1) the severity of the violation, 2) the application of the factors that the

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S. A. Patuiski

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considers when it determines the amount of a civil penalty that may be assessed in

accordance with Section VI.B.2 of the Enforcement Policy, and 3) any other application of

the Enforcement Policy to this case, including the exercise of discretion in accordance with

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Section Vll.

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You will be advised by separate correspondence of the results of our deliberations on this

matter. No response regarding this apparent violation is required at this time.

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in accordance 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, the

enclosures, and your response to the letter will be placed in the NRC Public Document

Room (PDR).

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Sincerely,

/s/ John A. Grobe for

John A. Grobe, Deputy Director

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Division of Reactor Projects

Docket Nos.: 50-266, 50-301

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License Nos: DPR-24, DPR-27

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Enclosure:

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Inspection Report

No. 50-266/301/97005(DRP)

Document: R:\\insprpts\\ powers \\poin\\ poi 97005.drp

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To receive a copy of this document, indicate in the box "C" = Copy without attach /enci

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"E" = Copy with attach /enci "N" = No copy

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OFFICE

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NAME

Kunowski

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DATE

03/J//97

03/A/97

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OFFICIAL RECORD COPY

(See attached distribution)

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. S. A. Patuiski

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Distribution:

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cc w/ encl:

R. R. Grigg, Pretident and Chief

Operating Officer, WEPCO

A. J. Cayia, Plant Manager

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Virgil Kanable, Chief,

Boiler Section

Cheryl L. Parrino, Chairman

Wisconsin Public Service

Commission

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State Liaison Officer

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Docket File w/ encl

SRI Point Beach w/enci

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PUBLIC IE-01 w/enci

OC/LFDCB w/enci

A. B. Beach, w/enci

Rlil Enf. Coordinator, w/enci

Deputy RA, w/enci

CAA1 w/enci (E-mail)

Project Manager, NRR, w/ encl

DRP, w/ encl

Rill PRR w/enci

DRS (3) w/ encl

TSS w/enci

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UNITED STATES

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NUCLEAR HEGULATORY COMMISSION

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801 WARRENVILLE ROAD

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April 3, 1997

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EA 97-75

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Mr. S. A. Patuiski, Site Vice President

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Point Beach Nuclear Plant

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6610 Nuclear Road

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.Two Rivers, Wisconsin 54241

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' SUB ECT:

POINT BEACH NRC INSPECTION REPORT NO. 50-266/301/97005(DRP)

{

.

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Dear Mr. Patuiski:

i

_On March 14,1997, the NRC completed a special inspection at your Point Beach 1 and 2

,

reactor facilities. The enclosed report presents the results of that inspection. The

'

inspection was conducted to review the use of manual operator action to maintain the

train A motor-driven auxiliary feedwater (MDAFW) pump operable during an accident. This

,

issue was previously described as an unresolved item in the NRC Operational Safety Team

I

,

Inspection Report No. 50-266(301)/96018.

In April 1996, Point Beach staff determined in two safety evaluations related to this issue

that an unreviewed safety question did not exist. However, in our subsequent review, we

have determined that the use of manual operator action to maintain the pump operable did

involve an unreviewed safety question. Based on the unreviewed safety question, we

have identified an apparent violation of 10 CFF. 50.59 for changing the automatic

operation of train A of the MDAFW system, which is described in the Final Safety Analysis

Report, without prior NRC approval.

1

The apparent violation identified is being considered for escciated enforcement action in

accordance with the " General Statement of Policy and Procedure fr,i NRC Enforcement

l

Actions" (Enforcement Policy), NUREG-1600. No Notice of Violation is presently being

issued for this apparent violation. In addition, be advised that the number and

characterization of the apparent violation described in the enclosed inspection report may

change as a result of further NRC review.

As stated at the inspection exit meeting on March 17,1997, we request that you discuss

this apparent violation at the predecisional enforcement conference scheduled for April 9,

1997, to address the four apparent violations identified in inspection Report No. 50-

266(301)/96018. The decision to hold a predecisional enforcement conference does not

mean that the NRC has determined that the violation occurred or that enforcement action

.will be taken. This conference is being held to obtain information to enable the NRC to

make an enforcement decision, such as a common understanding of the facts, root

causes, missed opportunities to identify the apparent violation sooner, corrective actions,

significance of the issue, and the need for lasting and effective corrective action. In

addition, this is an opportunity for you to provide any information concerning your

perspectives on 1) the severity of the violation, 2) the application of the factors that the

.

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.

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.

S. A. Patuiski

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NRC considers when it determines the amount of a civil penalty that may be assessed in

accordance with Section VI.B.2 of the Enforcernent Policy, and 3) any ottier application of

the Enforcement Policy to this case, including the exercise of discretion in accordance with

'

Section Vll.

3

You will be advised by separate correspondence of the results of our deliberations on this

l

matter. No response regarding this apparent violation is required at this time.

In accordance 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, the

enclosures, and your response to the letter will be placed in the NRC Public Document

Room (PDR).

,

l

' Sincerely,

D

,

.

l

ohn A. Grobe, Deputy Director

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ivision of Reactor Projects

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Docket Nos.: 50 266, 50-301

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