ML17229A054

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Forwards Insp Repts 50-335/96-12 & 50-389/96-12 on 960712 & Notice of Violation.Failure to Recognize an Unreviewed Safety Question Related to Implementation of Valve Lineup Change to EDG Fuel Oil Transfer Sys
ML17229A054
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 09/19/1996
From: Ebneter S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Plunkett T
FLORIDA POWER & LIGHT CO.
Shared Package
ML17229A055 List:
References
NUDOCS 9610030009
Download: ML17229A054 (8)


See also: IR 05000335/1996012

Text

CATEGORY 2

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

CCESSION NBR:9610030009

DOC.DATE: 96/09/19

NOTARIZED: NO

ACIL:50-335 St. Lucie Plant, Unit 1, Florida Power

& Light Co.

50-389 St. Lucie Plant, Unit 2, Florida Power

&. Light Co.

AUTH.NAME

AUTHOR AFFILIATION

EBNETER,S.D.

Region

2 (Post

820201)

RECIP.NAME

RECIPIENT AFFILIATION

PLUNKETT,T.F.

Florida Power

& Light CO.

SUBJECT: Forwards insp repts

50-335/96-12

& 50-389/96-12

on 960712

&

notice of violation. Failure to recognize

an unreviewed

safety question related to implementation of valve lineup

change

to

EDG fuel oil transfer

sys.

DISTRIBUTION CODE:

ZEOID

COPIES

RECEIVED:LTR

I

ENCL

[

SIZE: 5 N

TITLE: General

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

NOTES:

DOCKET I

05000335

05000389

RECIPIENT

ID CODE/NAME

PD2-3

PD

INTERNAL: ACRS

AEOD

ER

FB

NRR/DRPM/PERB

OE DIR

RGN2

FILE

01

EXTERNAL: LITCO BRYCE,J

H

NRC

PDR

COPIES

LTTR ENCL

1

1

2

2

1

1

1

1

1

1

1

1

1

'1

1

1

1

1

1

1

RECIPIENT

ID CODE/NAME

WIENS,L.

AEOD/SPD/RAB

DEDRO

NRR/DISP/PIPB

NRR/DRPM/PECB

NUDOCS-ABSTRACT

OGC/HDS3

NOAC

COPIES

LTTR ENCL

1

1

1

1

1

1

1

1

1

1

1

1

1

1

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0

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0

E

NOTE TO ALL "RIDS" RECIP1ENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS

OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL

DESK

(DCD)

ON EXTENSION 415-2083

TOTAL NUMBER OF COPIES

REQUIRED:

LTTR

19

ENCL

19

Seotemoer

i9.

1996

EA 96-236 and

EA 96-249

Florida Power

& Light Comoany

ATTN:

Hr. T.

F. Piunkett

President

-

Juclear Division

Post Office Box :4000

Juno Beach.

Floriaa

33408-0420

SUBJ. '::

NOTICE

F '/IOLATiON (NRC Special

Tnspection

Repor t Nos.

50 335 and

Dear "ir. P1'unkett:

his refers to :.".e

nsoection

c.mo!eted

on

uly :".

996. at

our St

faci',i y

The :nsoection

inc,'uaea

a review of se!ectea

aspects

of youl

confIguration manaaement

ana l0 CFR 50.59 safetv =valuation proarams.

The

result,s of our

ns"ecticn were sent to you by letter aated Julv 26.

1996.

."',cse

.

reaec.s.c."ai

en orc men. conference:vas

=:nauctea

In the Region II

orfice on Augus-.

.

996.

.vith vou and

memoers cf your staff :o discuss

the

-ooarent vioiat'."ns.

he ~cot causes.

and your ccrroc.-:ve actions to preclude

r;cir;ence. ,'--=r summariz;.".g

.".e ccnference
.as

=-ent .o 'ou by letter

datea

September

.

996.

Based

on the infor~ation developed

during the insoection

and

.he information

you provided dur.."." the conference.

'he

NRC has cetermined that violations of

NRC requirements

occurred.

The violations are cited '

the

nclosed Notice of

= d -",e

';. c

.,s ances

=-.rr"unc;",.a

.".em are ".escribed 'n

'V

4 A V

~

a

w Il

ws

~

zetai,

n the:.0;=-:::nsoe t.:n

."=- or"..

The violation in Part

I of the Notice involves your failure to recognize

an

i nreviewed safety "uestion related to tt e imoiementation of a valve lineuo

chanae to the Emergency Diesel Generator

(EDG) iuei oil transfer

system.

Specifically.

n

~iy 1995. the licensee

implemented

a change to the

2B

EDG

system to permit closing of a manual isolation va!ve from the Diesel

Fuel

011

Storaae

Tank to the aay tanks in order to minimize fuel oil around leakage

between the two :anvs.

4s part of the chanae.

". e licensee

instituted,

-- ministrative - a=-.res

".,ciuairg =edicat;:cn c- : .".on-:icense

operator

and

proceaural

revisions to assure

timely opening of the valve following an

EDG

start.

Although

=- safety evaluation performed to evaluate this change

-"nc..'ded -hat :-= =robaoi'!itv :;

oss of the

""=" emergency

"us

ncreased

y

ix .-ercent.
t

=-. 'neousiv concii aea that no increase

in the

rooabi lity of a

"cmporent .aiiur

.as created.

.n addit;on.

he

".RC:".as acne:uaed

that

I vo

new --ilure moaes

.ere .:ntroaucea

by the cnange: ,') ootential .ailure of the

~peratol

to u!il<-.ate t4e -uei oil '-;,ne ana (",'=-ilure cf the manual

96i0030009 9609i9

PDR

ADOCK 05000335

8

PDR

Florida Power

8 Light Company

-2-

isolation valve to open.

Therefore.

both the possibility for a malfunction of

a type different than any evaluated

previously in the Updated Final Safety

Analysis Report

(UFSAR) was introduced.

and the probability of a failure of a

component

important to safety was increased,

representing

a valid unreviewed

safety question.

At the conference.

you stated that

a safety evaluation

was prepared

for this

change consistent with Florida

Power

and Light Company procedures

and industry

guidance

(NSAC-125).

However.

NRC's position with respect to an "increase in

probability" differs.

Although the

NRC recognizes

in this case that the

increase

in probability of component fai lure was small,

a normally passive

component

was

made active and

an absolute

increase

in probability was

realized.

Notwithstanding the small probability increase.

the violation in

Part I of the Notice is of significant regulatory concern

because

a change

was

made to the

EDG system resulting in the emergence of an unreviewed safety

question for which a license

amendment

and

NRC approval

was not sought.

Further,

such failures to comply with the requirements of 10 CFR 50.59

resulted in facility operations

which depart

from the licensing and or design

bases

described in the

UFSAR.

Therefore.

the violation in Part I of the

Notice is classified in accordance with the "General

Statement of Policy and

Procedures

for

NRC Enforcement Actions" (Enforcement Policy),

NUREG-1600,

as

a

Severity Level III violation.

In accordance

with the Enforcement Policy,

a base civil penalty in the amount

of $50,000 is considered for a Severity Level III violation.

Because

your

facility has

been the subject of escalated

enforcement

actions within the last

two years'

the

NRC considered

whether credit was warranted

for

Identification and Corrective Action in accordance

with the civil penalty

assessment

process

described

in Section VI.B.2 of the Enforcement Policy.

In

this case,

the

NRC concluded that it is not appropriate to give credit for

Identification because

the violation was discovered

by the

NRC.

With regard

to consideration for Corrective Action, at the conference

you stated that your

actions related to the violation in Part I of the Notice included revision of

engineering safety evaluation guidance to clarify the definition of an

increase

in probability

and issuance of a technical alert to all engineers

regarding this issue.

Further,

although not directly related.to this

violation, additional

emphasis

has

been placed

on the importance of 10 CFR 50.59 and the

UFSAR.

Your recent actions in this regard include:

(1)

10 CFR 50.59 reviewer certification; (2) additional

10 CFR 50.59 training for

designated staff: (3)

10 CFR 50.59 procedural

enhancements;

and (4)

implementation of the

UFSAR Review Project.

Based

on the above.

the

NRC

determined that credit was warranted for Corrective Action. resulting in the

base civil penalty.

A Severity Level III problem and proposed civil penalty of

$50.000 were issued

on

Narch 28.

1996

(EA 96-040) related to a reactor coolant system boron dilution event.

A Severity

Level III violation and proposed civil penalty were issued

on November

13.

1995

(EA 95-180)

related to inoperable

power operated relief valves.

Florida Power

8 Light Company

-3-

As

a result of these considerations,

a civil penalty of $50,000 would normally

be warranted for this Severity Level III violation.

However,

i'n this case,

you did perform

a 50.59 evaluation

and promptly thereafter

communicated with

the

NRC staff and discussed

your plans to reposition the fuel oil transfer

isolation valve,

as well as your preparatory

and compensatory

measures

to

minimize the potential for system failure.

Accordingly. under the

circumstance of this case,

a civil penalty is not warranted.

I have been

authorized,

after consultation with the Director. Office of Enforcement.

and

the Deputy Executive Director for Nuclear Reactor Regulation,

Regional

Operations

and Research,

to exercise

enforcement discretion,

in accordance

with the guidance set forth in Section VII.B.6 of the Enforcement Policy,

and

not propose

a civil penalty in this case.

Violations A and

B described

in Part II of the Notice have been categorized

at

Severity Level

IV.

The violations involve four instances

where you failed to

effectively incorporate design

changes

into plant operating procedures

or

drawings.

These violations were

NRC identified and are of concern

because of

the potential for misleading operators

and the similarity of the violations to

annunciator

response

procedure deficiencies identified during previous

inspections.

The fifth apparent

example of the configuration management

violation discussed

at the conference

involved your failure to incorporate

roperly the spent fuel pool heat load calculation into operational

procedure

imitations prior to initiating core off-load.

For this issue,

the

NRC has

decided to exercise discretion

and characterize

the violation as non-cited

(NCV 50-335/96-12-01)

in accordance

with Section VII.B.1 of the Enforcement

Policy.

Specifically. you identified the violation and promptly instituted

appropriate corrective action.

NRC has concluded that no violation occurred with respect to the three

additional

apparent fai lures to comply with 10 CFR 50.59 addressed

in the

subject inspection report and discussed

at the conference.

Specifically,

(1) the Unit 2 Control Element Drive Mechanism Control System Enclosure

was

not required to be included in the

UFSAR

~

and installation and subsequent

modifications did not require

10 CFR 50.59 safety evaluations;

(2) the

configuration of a temporary fire pump placed in stand-by during the 1996

Unit 1 refueling outage did not requi re

a

10 CFR 50.59 evaluation in that the

configuration was

as described in the

UFSAR (i.e.

~ the discharge

valve was

closed

and the

pump was isolated

from the system):

and (3) the failure to

perform

a

10 CFR 50.59 safety evaluation to change the setpoints

and

procedures

for operating the fuel hoist was identified and corrected

by you

prior to actual

fuel movement.

This letter closes

any further

NRC action

on

these matters.

You are required to respond to this letter and should follow the instructions

specified in the enclosed

Notice when preparing your response.

In your

response,

you should document the specific actions taken

and any additional

actions you plan to prevent recurrence.

After reviewing your response

to this

Notice, including your proposed corrective actions

and the results of future

inspections.

the

NRC will determine whether further

NRC enforcement

action is

necessary

to ensure

compliance with NRC regulatory requirements.

Florida Power

5 Light Company

4

In accordance

with 10 CFR 2.790 of the NRC's "Rules of Practice,"

a copy of

this letter, its enclosure,

and your

response will be placed in the

NRC Public

Document

Room (PDR).

To the extent possible.

your response

should not include

any personal

privacy, proprietary.

or safeguards

information so that it can be

placed in the

PDR without redaction.

Sincerely.

Docket Nos. 50-335.

50-389

License

Nos.

DPR-67,

NPF-16

Enclosure:

Notice of Violations

cc w/encl:

J.

A. Stall

Site Vice President

St. Lucie Nuclear Plant

P. 0.

Box 128

Ft. Pierce,

FL

34954-0128

H.

N. Paduano,

Manager

Licensing

and Special

Programs

Florida Power

and Light Company

P. 0.

Box 14000

Juno Beach,

FL

33408-0420

J. Scarola

Plant General

Manager

St. Lucie Nuclear Plant

P. 0.

Box 128

Ft. Pierce,

FL

34954-0128

E. J.

Weinkam

Plant Licensing Manager

St. Lucie Nuclear Plant

P. 0.

Box 128

Ft. Pierce,

FL

34954-0218

cc w/encl: (Cont'd on Page

5)

J'tewart D. Ebneter

Regional Administrator

Florida Power

II Light Company

cc w/encl (Cont'd):

J.

R.

Newman,

Esq.

Morgan.

Lewis

8 Bockius

1800

M Street.

NW

Washington,

D.

C.

20036

John T. Butler,

Esq.

Steel,

Hector and Davis

4000 Southeast

Financial

Center

Miami, FL

33131-2398

Bill Passetti

Office of Radiation Control

Department of Health and

Rehabilitative Services

1317 Winewood Boulevard

Tallahassee.

FL

32399-0700

Jack Shreve,

Public Counsel

Office of the Public Counsel

c/o The Florida Legislature

111 West Madison Avenue,

Room 812

Tallahassee,

FL

32399-1400

Joe Myers, Director

Division of Emergency

Preparedness

Department of Community Affairs

2740 Centerview Drive

Tallahassee.

FL

32399-2100

Thomas

R.

L. Kindred

County Administrator

St. Lucie County

2300 Virginia Avenue

Ft. Pierce,

FL

34982

Charles

B. Brinkman

Washington Nuclear Operations

ABB Combustion Engineering,

Inc.

12300 Twinbrook Parkway, Suite 3300

Rockvi lie.

MD

20852