ML16341F083

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Forwards Insp Repts 50-275/89-01 & 50-323/89-01 on 890123-0228 & Notices of Violation & Deviation
ML16341F083
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 03/21/1989
From: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To: Shiffer J
PACIFIC GAS & ELECTRIC CO.
Shared Package
ML16341F084 List:
References
NUDOCS 8904110129
Download: ML16341F083 (12)


See also: IR 05000275/1989001

Text

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REGULATORY INFORMATION DISTRIBUTION SYSTEM

(RI DS)

ACCESSION NBR:8904110129

DOC.DATE: 89/03/21

NOTARIZED:

NO

~

~

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CIL:50-275 Diablo Canyon Nuclear Power Plant, Unit 1, Pacific

Ga

50-323 Diablo Canyon Nuclear Power Plant, Unit 2, Pacific

Ga

AUTH.NAME

AUTHOR AFFILIATION

MARTIN,J.B.

Region 5, Ofc of the Director

RECIP.NAME

RECIPIENT AFFILIATION

SHIFFER,J.D.

Pacific Gas

& Electric Co.

SUBJECT:

Forwards Insp Repts 50-275/89-01

& 50-323/89-01

on

890123-0228

& notices of violation

& deviation.

DISTRIBUTION CODE

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TITLE: General

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ENCL

25

Harch 21I 1989

Docket Nos.

50-275

50-323

Pacific

Gas

and Electric Company

77 Beale Street,

Room 1451

San Francisco,

California

94106

Attention:

Mr. J.

D. Shiffer, Vice President

Nuclear

Power Generation

SUBJECT:

Gentlemen:

NRC Inspection of Diablo Canyon Units

1 and 2.

This refers to the special,

announced

inspection

conducted

by Messrs.

C. J.

Bosted

and

M. J.

Royack of this office, Messrs.

E. V. Imbro and

S.

R. Stein of the office of Nuclear Reactor Regulation,

and NRC*Contractors,

on January

23 through February 28,

1989, of activities authorized

by

NRC

License

Nos.

DPR-80 and DPR-82,

and to the discussion of our findings held

with you and other members of your staff on February 3,

1989.

The specific areas

examined during this inspection

are described

in the

enclosed

inspection report.

Within these

areas,

the inspection consisted

of

examination of selected

Pacific

Gas

and Electric Safety

System

Functional

Audit and Review

(SSFAR) documents,

Safety System Outage Modification

Inspection Surveillance

(SSOMIS) audits,

procedures,

representative

records,

interviews with site

and corporate office personnel,

and observations

of

related

equipment

by team personnel.

Based

on the results of the inspection, it appears

that certain activities

were not conducted

in full compliance with NRC requirements,

as set forth in

the Notice of Violation and Notice of Deviation, enclosed

herewith

as

Appendices

A and B, respectively.

Your response

to these Notices is to be

submitted in accordance

with the provisions stated

in the associated

Notice.

In addition, three apparent violations identified in the enclosed

inspection

report will be the subject of additional

NRC review and will be addressed

in

future correspondence.

Ins ection Overview

The inspection

conducted

by the

team

was

a review of your Safety System

Functional Audit and Review (SSFAR),

and Safety System Outage Modification

Inspection Surveillance

(SSOMIS) inspection

programs.

The purpose of our

inspection

was to assess

the effectiveness

of these

programs

and to assess

the

quality of your performance of technical

work.

In order for the inspection

team to adequately

review these

programs,

the team

performed

an abbreviated

independent

SSFAR and

SSOMIS type inspection

on

systems

which had

been previously reviewed

by your programs.

The

SSFAR and

SSOMIS packages

that were reviewed included the Auxiliary Saltwater

(ASW)

System,

Control

Room Ventilation

(HVAC) System,

Diesel

Generator

System,

8904ii0i29 89032i

PDR

ADOCK 05000275

Q

FDC

Diesel

Generator

Fuel Oil System,

Component Cooling Water

(CCW) System,

Safety

Injection (SI) Pumps,

and safety related ventilation systems.

In assessing

the associated

systems

and modification packages,

the team

focused

on the design basis of the systems

and the ability of the engineering

staff to evaluate

and maintain the design basis,

when modifying the systems

and during system operations.

The team evaluated

the actual

implementation of

the design basi s through maintenance,

surveillance,

testing,

and plant

operational

aspects

associated

with the selected

systems.

Team Findin

s

The inspection of the systems

and modification packages

identified a number of

deficiencies

and raised significant questions.

The team's

findings indicate

three areas

of generic weakness.

The first two of these

areas

of weakness

were previously identified during the

NRC Maintenance

Team inspection in

July 1988.

These

weaknesses

are

summarized

as follows:

The Plant Staff Does Not Full

Understand

the Plant Desi

n Basis

Plant procedures

addressing

CCW/ASW operation did not ensure that

the operation of the

CCW heat exchangers

was consistent with design

calculations.

Work was performed

on the plant ventilation system apparently

without consideration

of the effect of the work on plant operation.

Water level alarm switches in the

ASW pump

room were

removed

from

the calibration program apparently without considering

the function

served

by the switches.

480 volt power cable

was routed through the plant without

consideration

of its affect on electrical

separation criteria.

The Interface

Between

En ineerin

and the Plant is Weak.

Analysis of off-normal plant operating conditions which resulted in

a need for plant operating procedure

changes

were not effectively

communicated to the operations staff.

Procedure

changes

to insure

that

a 'second

Component Cooling Water

(CCW) System heat exchanger

is

placed in service

when certain

CCW pumps were inoperable

was not

issued

as

recommended

by Engineering.

Operation of the plant in

other than the

mode prescribed

by the

recommended

procedure

changes

could have resulted in the operation of the plant outside of the

safety analysis

during an accident.-

Modifications to the

GE/GW Ventilation system were made,

and

a blank

flange

was

used to establish

the main stack exhaust

boundary.

The

blank flange was installed without prior engineering

input.

The

field change

request

used to document the work was issued after the

work was completed.

Maintenance

was performed

on this system without

the

use of normal administrative controls.

4

En ineerin

Work Has

Been

Incom lete or Inade uate.

Plant modifications,

such

as the Auxiliary Salt Mater

(ASW) system

pump impeller change,

were not adequately

reviewed to establish

the

complete

impact

on the plant.

A review of the final seismic analysis for the safety injection pump

2-2 change

out was not made until after the applicable unit entered

an operating

mode in which the

pump was required.

Preliminary

approval

was

used

as justification for a mode change,

rather than

documented calculations.

A number of calculations

reviewed did not fully identify design

assumptions

and did not reference

input information.

With regard to the conduct of your SSFAR and

SSOMIS inspection

programs,

we

are encouraged

that you have undertaken this initiative.

The team considered

the quality of your inspections

to have

been

improving and noted that several

significant deficiencies identified by your efforts were vigorously pursued.

However,

improvements in your inspections

is needed,

particularly in view of

the engineering

type problems identified during our inspection.

The team

has

analyzed

the findings of this inspection

as it relates

to your SSFAR and

SSOMIS inspection

programs

and

has

reached

the following conclusions:

Your SSFAR teams did not perform comprehensive

technical

evaluations.

The focus of the first SSFAR inspections

appeared

to be

focused

on administrative verification instead of the type of

inspection which emphasizes

technical

aspects.

The composition of your SSFAR and

SSOMIS inspection

teams did not

include sufficient numbers of personnel

with the expertise/

background to question engineering activities and calculations.

When

personnel

with the expertise

to question

engineering

activities or

calculations

were assigned

to the inspection

teams,

they were placed

in a position of questioning their

immediate supervisors

or other

personnel

who have authority over that person.

The teams

begin the inspection with the assumption that the present

design is adequate

and that design

documents,

FSAR commitments,

and

procedures,

do not have to be reviewed

or questioned.

This

philosophy unnecessarily

limits the depth

and scope of your

inspection

and is not consistent with a high degree of

self-criticism.

Although your inspections

did identify significant problems in their

later

SSFAR inspections,

your teams did not take the problems

down

to the source or root cause,

nor did they consider the problems for

generic implications; i.e.,

how many other systems

can have this

same or similar problem.

You are encouraged

to aggressively

continue your efforts to conduct your SSFAR

and

SSOMIS inspections.

When properly conducted,

we consider this type of

effort to be of value in attempting to identify problem areas,

prior to those

problems

becoming self revealing.

In addition to the responses

directed

by

the enclosed

Notices,

please

provide

a written response

addressing

our

conclusions

regarding your conduct of SSFAR and

SSOMIS inspections,

as

discussed

above.

Additionally, as

we have previously discussed

with you,

we propose

to meet

with you in the near

future to discuss

the results of your

upcoming

CCM system

SSFAR.

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.

The responses

directed

by this letter and the attached

Notices are not subject

to the clearance

procedures

of the Office of Management

and Budget

as required

by the Paperwork Reduction Act of 1980,

PL.96-511.

Should you have

any questions

concerning this inspection,

we will be pleased

to discuss

them with you.

Sincerely

p; f',~g

~ j'(g(

John

B. Martin,

)

Regional Administrator

Enclosures:

1.

Appendix

A (Notice of Violation)

2.

Appendix

B (Notice of Deviation)

3 ~

Inspection

Report

No. 50-275/89-01,

50-323/89-01

cc w/enclosures:

S.

M. Skidmore,

PG&E

R.

F.

Locke,

PG&E

J.

D. Townsend,

PG&E (Diablo Canyon)

D.

A. Taggert,

PG&E (Diablo Canyon)

News Services,

PG&E Co.

T.

L. Grebel,

PG&E (Diablo Canyon)

State of California

Sandra Silver (Report Only)

bcc w/enclosures:

RSB/Document Control Desk,

(RIDS) (IEOI )

Docket File

Project Inspector

Resident

Inspector

Docket File

R.

Nease.

NRR

G.

Cook

B. Faulkenberry

J. Martin

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