ML17158B666

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Discusses Predecisional EC on 960507 Re Insp Repts 50-387/96-03 & 50-388/96-03 on 951211-15 & Notice of Violation
ML17158B666
Person / Time
Site: Susquehanna  
Issue date: 06/10/1996
From: Wiggins J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Byram R
PENNSYLVANIA POWER & LIGHT CO.
Shared Package
ML17158B667 List:
References
EA-96-087, EA-96-87, NUDOCS 9606200195
Download: ML17158B666 (7)


See also: IR 05000387/1996003

Text

,

CATEGORY 2

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

CCESSION NBR:9606200195

DOC.DATE: 96/06/10

NOTARIZED: NO

"

,

DOCKET

FACIL:50-387 Susquehanna

Steam Electric Station, Unit 1, Pennsylva

05000387

50-388

Susquehanna

Steam Electric Station, Unit 2, Pennsylva

05000388

AUTH.NAME

AUTHOR AFFILIATION

WIGGINS,J.T.

Region

1 (Post

820201)

RECIP.NAME

RECIPIENT AFFILIATION

BYRAM,R.G.

Pennsylvania

Power

& Light Co.

SUBJECT: Discusses

insp repts

50-387/96-03

& 50-388/96-03

& forwards

notice of violation.

DISTRIBUTION CODE:

IE01D

COPIES

RECEIVED:LTR

ENCL

SIZE:

+

TITLE: General

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

NOTES:

05000387

E

RECIPIENT

ID CODE/NAME

PDl-2

PD

INTERNAL: ACRS

EOD/g.'-R.

FILE CENTER

fDR'CH/ HFB

NRR/DRPM/PERB

OE DIR

RGN1

FILE

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TERNAL: LITCO BRYCE,J

H

NRC

PDR

NOTES:

COPIES

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1

1

2

2

1

1

1

1

1

1

1

1

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1

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1

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ID CODE/NAME

POSLUSNY,C

AEOD/SPD/RAB

DEDRO

NRR/DISP/PIPB

NRR/DRPM/PECB

NUDOCS-ABSTRACT

OGC/HDS2

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!

CONTACT THE DOCUMENT CONTROL DESK,

ROOM OWFN SD-5(EXT. 415-2083)

TO ELIMINATE YOUR NAME FROM

DISTRIBUTION LISTS

FOR

DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES

REQUIRED:

LTTR

20

ENCL

20

I

June

10,

1996

EA 96-087

Hr. Robert

G.

Byram

Senior Vice President-

Nuclear

Pennsylvania

Power

and Light Company

2 North Ninth Street

Allentown, Pennsylvania

18101

SUBJECT:

NOTICE OF VIOLATION NO. 50-387/388/96-03-01,

96-03-02,

96-03-03

Dear Hr. Byram:

This refers to the predecisional

enforcement

conference

held

on Hay 7,

1996,

at the

NRC Region I office located in King of Prussia

PA.

The conference

was

held to discuss

apparent violations outlined in NRC inspection report

50-387/388/96-03

performed

between

December

11-15,

1995,

and March 4-8,

1996,

at the Susquehanna

Steam Electric Station

(SSES).

The inspection

focused

on

issues

important to the public health

and safety

and consisted of independent

evaluations of your engineering

program.

The enforcement

conference

involved apparent violations concerning

the high

pressure

coolant injection (HPCI) system operability,

and the identification

and correction of the susceptibility of a HPCI injection valve to pressure

locking. It also considered

the manner in which longstanding

design

deficiencies

in the reactor water cleanup

(RWCU), containment

atmosphere

'leanup

and seismic monitoring systems

were addressed

in accordance

with the

plant licensing basis.

Based

on the information developed

during the inspection

and the information

that you provided during the conference,

the

NRC has determined that

violations of NRC, requirements

occurred.

These violations are cited in the

enclosed

Notice of Violation (Notice)

and the circumstances

surrounding

them

are described

in detail in the subject inspection report.

The violations highlight the fact that your organization did not appropriately

consider the regulatory significance of design deficiencies

in the

RWCU and

seismic monitoring systems

once they were identified by plant personnel.

Further,

changes

that your organization

made to the

RWCU leak detection

and

isolation system

were not entered

into the Final Safety Analyses

Report

(FSAR)

as required

by

10 CFR 50.71(e).

With regards

to the apparent violations that were considered for the HPCI

system,

we have concluded

you had responded

appropriately considering the

information that

was available at the time concerning

pressure

locking and

thermal binding.

Your treatment of the

HPCI injection valve was consistent

with NRC expectations

outlined in the Generic Letter 89-10 program.

Accordingly,

no violation existed.

9b0b200i95

9bOb10

PDR

ADGCK 050003S7

8

PDR

gl

Robert

G.

Byram

While we believe that your response

to

a single failure in the containment

atmosphere

cleanup

system

was not timely,

we have not completed

our

consideration

on the matter of enforcement

action.

That action will be

determined after

we complete

a review of the concerns

outlined in NRC

unresolved

items 96-03-02,

96-03-03

and escalated

enforcement

item 96-03-04 of

NRC inspection report 96-03.

You will be notified of our conclusions

regarding

these

issues later in separate

correspondence.

Although your organization's

problem identification capability is superior,

we

are concerned that your organization did not resolve the design

issues

in the

RWCU leak detection

and seismic monitoring systems

in a timely manner.

Further, your organization did not appropriately consider the regulatory

'ignificance

of these

design deficiencies.

Accordingly, the operability of

the

RWCU leak detection isolation system

was questionable

from 1989-1996.

Further,

the location of seismic monitoring instrumentation

has not been in

compliance with the plant Technical Specifications

since the start of

commercial plant operation.

We note the

RWCU leak detection

and isolation system consists of diverse

isolation components.

Since the design deficiency concerned

only one portion

of the

RWCU isolation system,

and other components

were operable,

the safe'ty

consequence

of the

RWCU design

weakness

was low because

other

RWCU isolation

system

components

could perform

an equivalent isolation function if required.

Additionally, the safety consequence

of the inappropriately located seismic

monitoring instrumentation

is also low since the information provided by the

monitors is only part of the information that would be used

by your

organization to assess

plant response

to

a seismic event.

Therefore,

these

violations have

been categorized

in accordance

with the "General

Statement of

Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy),

(60 FR 34381;

tune 30,

1995) at Severity Level

IV .

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.

In accordance

with 10 CFR 2.790 of the

NRC's "Rules of Practice,"

a copy of

this letter, its enclosure(s),

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.

Robert

G.

Byram

The response

directed

by this letter and the enclosed

Notice are not subject

to the clearance

procedures

of the Office of Hanagement

and Budget

as required

by the Paperwork

Reduction Act of 1980,

Pub.

L. No. 96.511.

'incerely,

Oocket Nos.

50-387;

50-388

License

Nos.

NPF-14;

NPF-22

Enclosure:

Notice of Violation

James

T. Wiggins, Director

Division of Reactor Safety

cc w/encl:

G. T, Jones,

Vice President

-, Nuclear Engineering

G. Kuczynski, Plant Hanager

J.

H. Kenny, Supervisor,

Nuclear Licensing

G.

D. Hiller, Hanager - Nuclear Engineering

R,

R. Wehry, Nuclear Licensing

H.

H. Urioste,

Nuclear Services

Hanager,

General

Electric

C. 0.

Lopes,

Hanager - Nuclear Security

W. Burchill, Hanager,

Nuclear Safety Assessment

H. 0, Woodeshick,

Special Office of the President

J.

C. Tilton, III, Allegheny Electric Cooperative,

Inc.

Nuclear Safety Information Center

(NSIC)

Commonwealth of Pennsylvania

0

Robert

G.

Byram

Distribution w encl:

Region

I Docket

Room (with concurrences)

K. Gallagher,

DRP

NRC Resident

Inspector

PUBLIC

Distribution w encl:

(Via E-Mai 1)

W. Dean,

OEDO

C. Poslusny,

Project Manager,

NRR

J. Stolz,

PDI-2,

NRR

Inspection

Program

Branch,

NRR

( IPAS)

R.

Zimmerman,

ADPR,

NRR

J.

Goldberg,

OGC

J.

Lieberman,

OE

(OEMAIL)

D. Holody,'I

DOCUMENT NAME:

A: EA96087.SUS

To receive a copy oF this document, indicate in the hox: "C"

Copy~thout attachment/cn

ur

~ Copy with attachment/enclosure

"N'

Yo copy

OFFICE

R I/OE

RI/DRP

RI/DRS

RI/DRS

NAME

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DATE

06/03/9

06/ ")/96

06/

9

OFFICIAL RECORD

COPY

06/

/96

06/

/96