ML16341E181

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Insp Repts 50-275/87-11 & 50-323/87-10 on 870323-27.No Noncompliance or Deviations Identified.Major Areas Inspected:Followup of IE Temporary Instructions,Part 21 Repts & Previously Identified Insp Items
ML16341E181
Person / Time
Site: Diablo Canyon  
Issue date: 04/14/1987
From: Burdoin J, Mendonca M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML16341E182 List:
References
50-275-87-11, 50-323-87-10, GL-83-28, IEB-85-003, IEB-85-3, NUDOCS 8704290396
Download: ML16341E181 (12)


See also: IR 05000275/1987011

Text

U.

S.

NUCLEAR REGULATORY COMMISSION

REGION V

Report Nos. 50-275/87-11,

50-323/87-10

Docket Nos. 50-275,

50-323

Li.cense

Nos.

DPR-80,

DPR-82

Licensee:

Pacific Gas

and Electric Company

77 Bea1e Street,

Room 1451

San Francisco,

Cali fornia

94106

Facility Name:

Diablo Canyon Units 1 and

2

Inspection at:

Diablo Canyon Site,

'San Luis Obispo County, California

Inspection

condu

e

March 23-2

, 1987

Inspectors:

Approved by:

F.

ur own,

eacto

Inspector

~a

M.

M nd

ca,

C .ief

eactor

Project .Section

1

0 te Ss,gned

ate Signed

~Summa':

Ins ection Durin

Period of March 23-27

1987

Re ort Nos. 50-275/87-11

and,

50"323 87"10

non-1>censed staff training; followup of IE Temporary Instruction(s).,

Part

21(s),

and previous identified inspection item(s),

and an independent

inspection of various vital areas

and equipment in the plant.

Inspection

procedu'res

nos.

30703,

41400,

71707,

and 92703 were used

as guidance for the.

i.rjspection.

Results:

No items .of noncompliance or deviations were identified.

8704290396

870414

PDR

ADOCK 05000275

8

PDR

'I

DETAILS.

Individuals Contacted

Pacific Gas

and Electric

Com an

(PG8E)

  • R.

C. Thornberry, Plant Manager

"J.

A. Sexton,

Plant Super'intendent

"L. F.

Momack, Operations

Manager

  • T. L. Grebel,

Regulatory Compliance Supervisor

R.

M. Luckett, Regulatory Compliance

T. J. Martin, Training. Manager

J.

E.

Mol.den, Operations Training, Supervisor

D.

R. Clifton, Technical

and Maintenance Training Supervisor

N.

M. Bennett, Instructor Training Coordinator

G.

H. Gund, Mechanical.-Maintenance

Training Instructor

T.

N. Gray,

I8C Senior. Training Instructor

D.

R.

Geske, Verification Planning Group Supervisor

C.

L. Meyers,

Docume'nt Control Analyst

M.

L. Smith,

Power Production

Engineer

I

Various other engineering

and

gC personnel.

  • Denotes attendees at exit meeting

on March 27, 1987.

In addition,

NRC Resident Inspector(s)

attended

the exit management

meeting.

Area Ins ection

An independent

inspection

was conducted in Units 1 and

2 Turbine and

Auxiliary Buildings.

The equipment

and areas

inspected

included

A.

Five Emergency Diesel Generator

Rooms

B.

Six 4160 Volt Switchgear

Rooms

C.

Combined Two-Unit Control

Room

D

Two Containment

Spray

Pumps, Unit 1

E.

Three Charging

Pumps,

Units 1

F.

Four Safety Injection Pump Areas.

G

Four

RHR Pump Areas

H.

Six .Component Cooling Pumps

I.

Auxiliary Feedwater

Pumps

J.

Six 480 Volt. Vital Bus Rooms

K.

Two Cable Spreading

Rooms

L.

Two Hot Shutdown Panels

M.

Two 480 Volt Center Areas

N.

Turbine Building .at Elevations 140'nd

85'on-I

incensed Staff Trainin

The inspector

examined the licensee's

program for training of

non-licensed staff to determine that it sati.sfies

regulatory requirements

and meets the licensee's

commitments for training.

The

FSAR

.does

not.

specifically identify any nuclear or'industrial

standards

-to which the

licensee is committed.

In conversation

.with the training'manager, it was

determined that the licensee's

training program conforms to ANSI standard

"

N18. 1-1971 "Selection

and Training of Nuclear

Power Plant Personnel."

The

FSAR describes

training for non-licensed staff as follows:

Replacement training for operation

personnel

hired at Diablo Canyon prior

to April 27,

1984 followed established

company procedures

and programs

which required

new nonlicensed auxiliary operators

to undergo

a- formal 30

month training program.

This program consists of lesson

assignments,

review tests,

and qualification examinations.

Replacement training,for operation

personnel

hired. after April 27,

1984

is conducted in accordance

with .a plant manual

procedure.

Each

new

auxiliary operator

undergoes

a formal structured training program

consisting of two parts;

seventeen

weeks of classroom training,

and

approximately

24 months on-the-job watchstation qualifications'he

17

weeks of classroom training is in fundamentals

which includes

mathematics,

nuclear/m'echanical/electrical

sciences,

etc.

and systems

which includes. electrical/primary/secondary

systems,

and primary and

, secondary

support systems.

Matchstation gualifications,

an on-the-job

phase of traini.ng, prepares

the candidate to operate

components

outside

the control

room and to gain operating experience prior to taking over

the..sole responsibilities of standing .a watch.

This phase 'is divided by

watchstation ta give the. operator

a logical approach to qualification.

Replacement

training. for. nonopqrating personnel,

such

as technicians

and

craft journeymen, is conducted

as required by procedures.

Although these

positions are generally filled with experienced, personnel,

training is

provided to qualify individuals to perform the many specialized

duties of

these positions.

In general,. the training is accomplished

in two phases:

academic

and hands-on (on-the-job) training.

This training is, in

additi.on to the training provided under. the General

Employee Training

Program.

The inspector

examined

the, licensee's

prognam for training of nonlicensed

staff by reviewing. the followi.ng administrative procedures:

AP-B-150,- Rev. 1, dated June 25, 1986,

"Non-Licensed Operator Training

Program"

AP-B-450,

Rev. 1, dated August 21, 1985, "Instrumentation

and Control

Technician Training".

AP-B-750, Rev.,',

dated August 12, 1985,

"Maintenance

Personnel

Training"

The inspector

examined the following training records to determine if the

. above procedures

were properly implemented.

Auxiliary operators;

records for ten people of approximately sixty

nine operators-were

reviewed

0

IBC technicians;

records for seven people of approximately sixty

five technicians

were reviewed

.

Maintenance electricians;

records

for. eight people of approximately

sixty two electricians

were reviewed

It is concluded

from review of the administrative procedures

above

and

examination of the aforementioned training records that the training

program for non-licensed

operators,

I8C technicians

and maintenance

electricians

appears

to satisfy the training requirements

for these

disciplines

as described in the

FSAR.

The inspection in this area

was not completed during this inspection

period and-will be continued during a future inspection.

This item will be followed as open item 50-275/87-11-01.

No violations or deviations

were identified.

Foll.owu

of IE Tem orar

Instruction .s) (TI)

TI 2515/73 (IE Bulletin 85-03) "Motor-0 crated Valve

Common

Mode Failures

Durin

Plant Transients

Oue to

Im ro er Switch Settin s"

Thi.s TI outlines inspection requirements

for IE Bulletin 85-03, which

requested

licensees, to develop

and implement a program to ensure that

switch .settings

on certain .safety-related

motor-operated

valves are

selected,

set and maintained correctly to accommodate

the maximum

differential pressures

expected

on these

valves during both normal

and

abnormal

events within. the design basis.

The inspector

as

a followup to inspection report 50-275/86-31 selected

as

a sample

the following five motor operated

valves;

8107,

8801B,

8974B,

FCV-95 and

LCV-109 from the

27 valves of Unit 1 for which torque/limit

switch adjustments

had been

made during the Unit 1 refueling outage in

fall of 1986.

The work orders

under which the torque/limit switch adjustments

for the.

selected

valves are listed below:

Valve No,'.s..

Mork Order No's.

Valve -No.'s.

Word Order No'.s.

8107

8801B

8974B

G-0001355

C-0002025

C"0002049

FCV-95

LCV-109

C"0003045

C-0002059

The inspector

examined the work orders for task (work},description,

safety/plant

impact, initial review/signoff,

gC inspection

holdpoints/signoff;

summary

comments, operability test/signoff, test data

results,

completion verification, etc.

The records

appeared

to be in

order and adequate.

The requirements of TI 2515-73/IE Bulletin 85.-03 not addressed

in this

repbrt or inspection report 50-275/86-31 will be inspected .during a

subsequent

inspection(s)

and reported

under

Open Item TI 2515/73.

No violations or deviations

were identified.

Followu

of 0 en Items List (OIL

Part 2ls

The following part 21 reports applicable to some nuclear

power plants

were reviewed with the licensee:

OIL 86-20-P, Susceptibility of BH line of instrument manufactured

by

Foxboro, to deterioration resulting in equipment failure.

OIL 86-22-P, Failure of Milmar electronics

underpower relays to meet

gA

standards

required for nuclear

power plant

OIL 86-23-P, Stationary sleeve

on thrust bearing of Atwood 8 Morrill MSIV

must be machined to prevent galling.

The licensee

concluded following his study of the above part 21 reports

that the equipment described

in these

reports is not installed at the

Diablo Canyon Plant.

Consequently,

no action is required of the

licensee.

These

items. are closed.

No=-violations or deviations. were identified.

Followu

of Previous Identified Ins ection Item s

Closed

Item 50-275/85-37-01

Generic Letter 83-28. Item 3.2 Post

Maintenance

Teston

Item 3.2. 1

NRC Requirements

The licensee

shall review maintenance

procedures

and technical

specification to assure

post maintenance

operability testing of all

safety-related

equipment is performed.

Licensee Action

Administrative Procedures

NPAP-CG. "Clearances,"

and AP-C-6S3,

"Post-Maintenance

Testing," are in place,

which ensure that the

appropriate tests

are conducted to verify that equipment which has

been

removed from service for maintenance

(either corrective or preventive)

be

tested prior to its return to service to determine that it is operable

and.is

capable of performing its intended'safety

function.

Following

completion of maintenance. work, the appropriate

postmaintenance

test is

run after. the equipment is return to service,

but before declaring it

"operable".

E

~

Item 3.2.2

NRC Requir ement:

The licensee

shall review vendor

and engineering

recommendations

to

ensure that appropriate test guidance is included in test

and maintenance

procedures

and technical specifications

where required.

Licensee Action

The licensee

has reviewed the applicable

vendor

and engineering

recommendations to ensure that appropriate test guidance is included in

maintenance

procedures

or technical specifications

as required.

No

technical specifications

changes

were made.

Of the postmaintenance

testing recommendations

generated

from the review,

few recommendations

need further review to determine if they should

be

incorporated into future procedure

revisions.

If they are determined to

be applicable,

the procedures will be revised

by mid-November

1986.

The licensee.'.s

actions described

above were submitted to the .staff in

DCL-86-074 dated

March 20, 1986.

This material

was reviewed by the staff

along with additional material

on the subject submitted earlier.

The

staff's safety evaluation

forwarded to the licensee

October

21,

1986

concluded that the licensee's

actions

taken in response

to. Items 3.2.1

and 3.2.2 were acceptable.

The inspector

examined administrative procedures

NPAP-C6 "Clearances,"

and AP-C-6S3,

"Post-Maintenance

Testing,"

and concluded that they

appeared

to be in order and satisfy the requirements'of

Items 3.2.1.

This item is closed.

No violations or deviations

were identified.

The inspector

conducted

an exit meeting

on March 27, 1987, with the Plant

Manager

and other members of the plant staff.

During this meeting,

the

inspector

summarized the scope of the inspection activities and reviewed

the inspection findings as described

in this report.

The licensee

acknowledged

the concerns identified in the report.

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