ML16341G759

From kanterella
Jump to navigation Jump to search
Forwards Insp Repts 50-275/92-25 & 50-323/92-25 on 920825-0928.Violations noted.Non-licensed Personnel Must Be Specifically Trained & Qualified to Manipulate Sys Important to Safety
ML16341G759
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 10/30/1992
From: Richards S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Rueger G
PACIFIC GAS & ELECTRIC CO.
Shared Package
ML16341G760 List:
References
NUDOCS 9211180233
Download: ML16341G759 (8)


See also: IR 05000275/1992025

Text

~p,g+<Gg

Wp0

c)Q

c

)

0

UNITED STATES

NUCLEAR REGULATORYCOMMISSION

REGION V

1450 MARIALANE

WALNUTCREEK, CAUFORNIA94596-5368

.OCT 30 1992

Pacific

Gas

and Electric Company

Nuclear

Power Generation,

B14A

77 Beale Street,

Room 1451

P. 0.

Box 770000

San Francisco,

California 94177

Attention:

Hr.

G. H. Rueger,

Senior Vice President

and General

Hanager

Nuclear

Power Generation

Business

Unit

Gentlemen:

Subject:

NRC Inspection of Diablo Canyon Units

1 and

2

This refers to the routine inspection

conducted

by H. Hiller and

P. Horrill

during the period from August

25 through September

28,

1992.

This inspection

examined your activities

as authorized

by NRC License

Nos.

DPR-80

and DPR-82.

At the conclusion of the inspection,

the inspectors

discussed

their findings

with members of the

PG&E staff.

Areas examined during. this inspection

are described

in the enclosed

inspection

report.

Within these

areas,

the inspection consisted of selective

examinations of procedures

and representative

records,

interviews with

personnel,

and observations

by the inspectors.

The Notice of Violation (Notice) included in this report is based

on the

findings of NRC inspection report 50-275/91-34

which examined the instance of

a non-licensed

operations

person assisting

licensed

operators

in the control

room following a Unit

1 trip on Hay 17,

1991.

Based

on the results of that

inspection

and our review,

we have concluded that non-licensed

personnel

must

be specifically trained

and qualified to manipulate

systems

important to

safety,

as required

by your procedures,

and that this was not the case during

this event.

However,

we recognize that your organization

has taken

satisfactory corrective actions to control the duties .of non-licensed

operations

personnel;

consequently,

no response

is required to the Notice.

The two open items associated

with inspection report 50-275/91-34

are also

closed.

Several

problems

were identified during this period which w'ere self-revealing,

were identified by the

NRC, or were found as

a consequence

of previous

problems..

These

problems could have

been averted

by more penetrating

understanding

and investigation of previous events.

Of particular note are:

(1) the turbine overspeed

and

RCS cooldown event,

for which two precursors

could

be identified;

and (2) the inadequate

quality oversight program for

post-installation testing of emergency diesel

generator

(EDG) 2-3, which could

have

been

found much sooner.

The latter of these

issues

is the subject of a

non-cited violation,

as described

in Section VII.B of the Enforcement Policy

92iii80233 921030

PDR

ADOCK 05000275

8

PDR

I

~~a I

(Paragraph

6 of the enclosed

inspection report).

You are encouraged

to

promote

a high level of 'quality oversight

and technical

review to anticipate

such problems,"and

to avoid recurrence of previously identified problems.

In accordance

with 10,CFR 2.790(a)',

a copy of this letter and the enclosures

will be placed in the

NRC Public Document

Room.

This. letter and its enclosures

are not subject to the clearance

procedures

of

the Office of Management

and Budget

as required

by the Paperwork Reduction Act

of 1980,

Pub.

L.96-511.

Should you have

any questions

concerning this inspection,

we will be pleased

to discuss

them with you.

.Sincerely,

S. A. Richards,. Deputy Director

Division of Reactor Safety

and Projects

Enclosures:

1. Notice of Violation

2. Inspection

Report Nos.

50-, 275/92-25'nd

50-323/92-25

cc w/enclosures:

J.

A. Sexton,

PG&E

C. J.

Warner,

PG&E

J.

D. Townsend,

PG&E (Diablo Canyon)

D. A. Taggart,

PG&E (Diablo Canyon)

T. L. Grebel,

PG&E (Diablo Canyon)

C.

B. Thomas,

News Services,

PG&E

State of California (Gordon K. Van Vleck)

R. Hendrix, County Administrator

Sandra Silver

-3-

bcc w/copy of enclosures:

Docket File

Project Inspector

Resident

Inspector

B. Faulkenberry

J. Hartin

R.

Huey

P.

Johnson

H. Rood,

NRR

G.

Cook

bcc w/o enclosures:

H. Smith

J.

Bianchi

J. Zollicoffer

REGION

V

PHri

1

10/)K/92

gyr

HHi 1 1 er

. RH

10/g,l /92

10/p( /92

PJohnson

SRichards

10/g //92

10/ ~92

COPY

YES

NO

Q

COPY

R

0

YES

NO

ES

NO

S

CO

ES

NO

C

]

YES

NO

NO

NOTIC

0

VIOLA IO

Pacific

Gas

and Electric

Company'iablo

Canyon Unit

1

Docket No. 50-275

Li'cense

No. DPR-80

During an

NRC inspection

conducted

on August

25 through

September 28,'991,

one violation of NRC requirements

was identified.

In accordance

with the

"General

Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR Part 2, Appendix C, the violation is identified below:

Technical Specification 6.8. 1 requires that written procedures

be

implemented covering the activities referenced

in Appendix A of

Regulatory

Guide 1.33, Revision 2, February

1978.

Regulatory

Guide 1.33, Revision 2, Appendix A lists, in part,

procedures

for authorities

and responsibilities for safe operation

and shutdown.

PG&E Operations

Department Policy A-13, Revision 0,

"Non Licensed

Operator Control

Room Duties," states that

"A Non-licensed

ACO or AO in

the Control

Room shall not be assigned

tasks which involve the following:

.... Operation of controls which have or could possibly have an-indirect

effect on reactivity,

such

as,

Steam

Dump Controls,

Hain Feedwater

Controls, or CVCS charging

and letdown controls."

Contrary to the above,

on Hay 17,

1991, licensee

personnel

directed

a

~

non-licensed

assistant

control operator

(ACO) to shut

down the safety

injection pumps

and the steam driven auxiliary feedwater

pumps, either of

which could have

had

an indirect effect upon reactivity.

This is a Severity Level

IV Violation (Supplement I);

Based

upon the corrective actions already taken

by the licensee,

no response

to this notice is required.

Dated at Walnut Creek, California

this 30'~ day of Q~4>e,,

1992.