ML18005A695

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Insp Rept 50-400/88-27 on 880815-19.Violation Noted.Major Areas Inspected:Environ Qualification of Electrical Equipment Which Included Review of Util Implementation of Program to Meet Requirements of 10CFR50.49
ML18005A695
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 10/20/1988
From: Conlon T, Merriweather N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18005A692 List:
References
50-400-88-27, NUDOCS 8811090278
Download: ML18005A695 (25)


See also: IR 05000400/1988027

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W., SUITE 2900

ATLANTA,GEORGIA 30323

Report No.:

50-400/88-27

Licensee:

Carolina

Power and Light Company

P.

0.

Box 1551

Raleigh,

NC

27602

Docket No.:

50-400

Facility Name:.

Shearon Harris

License No.:

NPF-63

Inspection

Conducted:

August

1 ;19,

1988

Inspectors:

COP

M~~is'i'm

N. Merriweat er,

Team Lea er

EZ'=

Da e Si

ned

/>

Da

e Sig ed

Team Members:

M. Jacobus,

Consultant

Engineer,

Sandia

National Laboratories

C. Kido, Consultant

Engineer,

Idaho National

Engineering

Laboratory

C. Paulk,

Reactor Inspector,

Region II

C. Smith, Reactor Inspector,

Regi.on II

N

Approved by:

T.

E. Conlon, Chief

Plant Systems

Section

Engineering

B'ranch

Division of Reactor Safety

SUMMARY

Scope:

Results:

This routine,

announced

inspection

was

conducted

in the

area

of

Environmental

Qualification

(EQ)

of Electrical

Equipment

which

included:

a

review of Carolina

Power

and Light Company's

imple-

mentatation

of

a program to meet the requirements

of 10 CFR 50.49;

walkdown inspections

of equipment

inside containment;

preventative

and

corrective

EQ maintenance;

EQ procurement;

and

followup

on

previous inspection

issues

and commitments.

In the

areas

inspected,

one violation and

one unresolved

item were

identified.

The violation involves the failure to maintain the qualified status for

certain

EQ equipment.

The root cause for the violation may be the

result of inadequate

training and/or procedures.

The unresolved

item

involves the licensee's

commitment to do additional testing to extend

the qualified life of the coils in Target

Rock Solenoid valves that are

both continously energized,

and

on hot process

piping.

L0

Poli

AOOCK 0 000400

9

PDC

This inspection

was

considered

to

be

Phase II of the previous

Eg

inspection

which

was

conducted

in

Narch

1988.

The

previous

inspection

concentrated

on

Eg equipment

located

in the Steam

Tunnel

and the Reactor Auxiliary Building due to the fact that the plant was

operating

preventing

containment

walkdowns.

The

team

concluded

during- the inspection that the licensee

had

implemented

a

program

which

meets

the

requirements

of

10 CFR 50.49.

The

team

also

concluded

that

the licensee's

training

programs

on

Eg were

weak.

During this

inspection,

the

team

concluded

that

the

licensee

continues

to have

an adequate

Eg program.

The program is considered

to be average

and is not outstanding

at this point.

However, there

are certain initiatives that are-currently

ongoing which will greatly

enhance

their Eg program.

These initiatives include

changes

in the

Eg organization

and responsibilities

to better interface with other

departments

and

organizations

on

Eg

matters

(such

as

design,

maintenance,

procurement

and scheduling)

performing walkdowns of Eg

equipment,

and

conducting

engineering

surveys

of

Eg equipment's

ambient

temperatures

during

power operati'on for age related effects

on

Eg equipment,

and followup on

NRC issues.

The

weaknesses

identified in the

licensee's

Eg

program

related

specifically to

Eg maintenance

and training.

The licensee

performed

maintenance

on

Eg equipment

which failed to maintain the qualified

status

of the

equipment.

The training

provided

the craft

was

considered

marginal

and

procedures

may also

have

been

inadequate.

Staffing for

Eg has

been

increased

with a proposed

new position in

the newly described

organization.

All these

actions

may enhance

the

licensee's

Eg program over the years

to come.

REPORT

DETAILS

Persons

Contacted

Licensee

Employees

  • P. Brady, Senior Engineer,

Harris Plant Modification Unit

  • C. Crawford, Representative,

On-Site Nuclear Station

(ONS),

  • R. Cuthbertson,

Senior Specialist,

Technical

Support

  • E. Evans, Project Engineer,

Nuclear Engineering.Department

(NED)

  • C. Gibson, Director, Program

and Procedures

  • C. Hinnant, Plant General

Manager

  • M. A. Kite, Senior Specialist,

Technical

Support

  • J. Lewis, Senior Engineer,

NED

  • C. McKenzie,'Principal

gA Engineer

  • T. Nelson, Senior Specialist,

NED

  • F. Nowak, Senior Engineer,

NED

  • L.Oakley, Senior Engineer,

Technical

Support

  • L. Olsen, Project Specialist,

Technical

Support

  • A. Roberts,

Senior Specialist,

Technical

Support

  • W. Russell,

Project Engineer,

ONS

  • P. Salas,

Senior Engineer,

Licensing

  • J. Sipp,

Manager

  • C. Sweely, Project Engineer,

NED

  • D. Tibbitts, Director, Regulatory

Compliance

  • R. Van Metre, Manager,

Technical

Support

  • M. Wallace, Senior Specialist,

Regulatory Compliance

  • R. Watson,

Vice President,

Harris Nuclear Project

  • L. Woods,

Engineering Supervisor,

Technical

Support

  • P. Yandow, Senior Engineering,

NED

  • R. Zula, Project Engineer,

Technical

Support

Other

licensee

employees

contacted

during this

inspection

included

craftsmen,

engineers,

operators,

mechanics,

security

force

members,

technicians,

and administrative

personnel.

Other Organizations

  • D. Rhyne,

Patel

Engineers

NRC

  • P. Fredrickson,

Chief, Project Section

1A, Division of Reactor Project

  • C. Hehl, Deputy Director, Division of Reactor Projects
  • E. Merschoff,

Deputy Director, Division of Reactor

Safety

  • M. Shannon,

Resident

Inspector

  • Attended exit interview

2.

Evaluation Of Licensee's

Program

For gualification Of Electrical

Equipment

Located In Harsh Environments

(TI2515/76)

A special

team inspection

was

performed

during the

week of March 7-11,

1988,

to assess

the licensee's

implementation of a

program to meet

the

requirements

of

10 CFR 50.49.

During that

inspection, files for 23

equipment

items

were

reviewed

and

found acceptable

with

some

minor

discrepancies.

A walkdown was performed of equipment located in the

steam

tunnel

and auxiliary building with

some

maintenance

concerns

being

identified.

Due to the operational

status

of the plant walkdowns of

equipment,

inside

containment

could not

be

accomplished;

however,

the

licensee's

Eg

program

appeared

to

be

adequate.

This inspection

was

considered

a continuation of the first inspection concentrating

on those

inside

containment

components

which were not examined

during the first

round

Eg inspection.

Similar to the first inspection,

the

NRC inspectors

examined files

as

the

basis

for qualification for

Eg equipment

inside

containment;

performed

walkdown

inspections

of

equipment

(inside

containment

only); continued

the review of the

Eg maintenance

program;

examined

the licensee's

procurement

program for

Eg components

and

spare

parts;

reviewed

Eg training;

and examined

what actions

had

been

taken

on

previous

inspection

concerns.

The results

of the inspection

and -the

conclusions

reached

are discussed

below:

a ~

Maintenance

During this

inspection,

work requests

that

had

been

closed

out

(either by completion or cancellation)

and those that had been

issued

since

March 1988,

were reviewed.

At first there

appeared

to be many

problems

in the

area

of Eg.

This

was

because

many of the work

requests

identified "unqualified" components,

"unknown" components,

and missing components.

The

"unqualified"

and

"unknown"

components

were

associated

with

Limitorque motor operators.

The number of these

items

was alarming

since

the licensee

stated

that

a

1005 walkdown of environmentally

qualified Limitorque operators

had

been

performed

in

1986.

Upon

questioning

by the inspector,

the licensee

was able to show for the

1986

data

that

the

questionable

item

was

not

"unknown"

or

"unqualified."

These

items were identified by the licensee

during the performance of

EPT-072;

Limitorque

Valve Actuator

Inspection

Guidelines.

The

procedure

requires

the performer to annotate

what is found.

When

something

was

found that

was

questionable,

the technician

would

indicate the item was

"unknown" or "unidentified".

The procedure

does

not

provide

any

acceptance

criteria

to determine

what

would

be

acceptable

or to identify any discrepancies.

The procedure

requires

the

Eg Coordinator

or

Designee

to resolve

any discrepancies,

yet

there is no acceptance

criteria or reference list of acceptable

items

for this person to use in meeting this signoff requirement.

3'everal

factors are involved in this issue.

The individuals that are

performing

the

procedure

are

not

adequately

trained

in

Eg,

the

procedure

does

not provide

any acceptance

criteria for determining

what is acceptable,

and management

appears

to have only" a handful of

. people

knowledgeable

in Eg.

Unless the technicjans

and electricians

understand

Eg

and

the

requirements

for maintaining

equipment

qualified, qualification issues will arise.

In this instance,

ther e

was

no hardware

problem, but there

was

a problem with the training of

personnel

responsible for performing

Eg related activities.

0

During

the

review of the

work requests,

a

problem with motor

operators

missing T-drains

was identified.

The following scenario

indicates

that although corrective

actions

were

taken,

they were

considered

inadequate

to prevent similar problems

from

recurring.'n

1986,

WRSA 86-BMBS1

was written to correct

a cable termination

problem in the limit switch for Yalve No.

1RH-63.

The work request,

did not specify what was required to maintain the limit switch in

a

qualified configuration;

WRY 87-AMPE1 was

issued April 24,

1987, to

re-establish

the environmental

qualification of the limit switch

by

replacing

the .front cover

gasket.

The

work

was

completed

on

August 6,

1987.

On

August 7,

1987,

NCR 87-098

was

issued

and it identified the

problem with WRSA 86-BMBSl as not meeting the requirements

of MMM-012

which

states "if the

work request

is

on a[n]

Environmentally

gualified component...the

planner will determine if the environmental

boundary will be

degraded

by the

maintenance

action

and

provide

planning instructions

as

necessary

to restore

the

Eg boundary."

The

root- cause

was identified as'[i]ncorrect planning of

WR 86-BMBSl did

not include

Eg requirements".

The corrective actions

were to issue

WR87-AMPE1 and to provide training.

On August 21,

1987,

Planners

were trained

on

EQ requirements

and the

processing

of work requests

involving Eg.

Classes

to indoctrinate

18C

and

Electrical

personnel

were

scheduled

to

begin

in

,

September

1987.

On, or about,

September

17,

1987,

the motor operated

valve

1MS-70,

the

Main

Steam

supply to the

Turbine Driven Auxiliary Feedwater

(TDAFW) pump from the "B" main steam line, was replaced

in accordance

with

WR 87-BCLY1.

On February

29,

1988,

WR 88-AEKE1 was initiated to replace

the motor

operator for valve

1AF-143,

the

AFW isolation valve to the

"B" S/G"

from the

TDAFW

pump.

The

work request

did

not

require

the

electricians

to

remove

the T-drains

from the old motor and install

them

on the

new motor, however,

they did.

This is another

example of

the work request

not being completed with the necessary

information

to ensure electrical

equipment maintains

environmental qualification.

On March 2,

1988,

WR 88-AEgMl was written to install the T-drains

on

the operator

motor for valve

1NS-70

which were

not installed in

September

1987.

On April 15,

1988, it was

"discovered"

by the licensee

that the

missing T-drains

was

a "qualification problem:

and

SOOR 88-068

was

initiated.

WR 88-AE(Ml was performed

on April 15,

1988,

and T-drains

were

installed

in the limit switch

housing,

not

the

motor

as

instructed

by the

WR.

On April 21,

1988,

WR 88-AIXH1 was initiated based

on

a review of

WR

88-AEKE1.

The review identified that

no T-drains

were

removed

from

supply

and it was

assumed

that

none were, therefore,

installed

on

1AF-143.

Workmen were dispatched

to perform the work request

but

found the T-drains already installed

and cancelled

the work request.

On June

23,

1988,

WR 88-APgS1

and

SOOR 88-114 were initiated due to-

the T-drains

being installed

in the limit switch housing

on

1NS-70.

The

T dr ains were correctly installed in the motor on June 23,

1988.

The above scenario

shows that the licensee identified

a problem with

the maintenance

of

Eg equipment.

Although corrective actions

were

taken,

the scenario

shows that those

actions

were inadequate

since

there

continues

to

be

problems

with

Eg maintenance.

Specifically,

technicians

and/or electricians

not adequately

trained to ensure that

environmental qualification is maintained after performing work, and

work planners

not providing adequate

instructions for maintaining

environmental

qualification.

This

is identified

as

Violation

88-27-01,

Failure

to

Take

Adequate

Corrective

Actions for

Eg

Problems.

The maintenance

of the licensee's

Eg program is not as strong

as it

should

be.

Improvements

must

be

made

in training,

procedural

compliance,

and

procedures

in order to avoid problems

in the future.

This will require

more

management

support

and

involvement than is

present

at this time.

Eg Personnel

Training

The

Eg inspection

conducted

March 7-11,

1988, identified deficiencies

in the

Eg training of licensee

personnel.

At the

time of the

inspection,

licensee

management

was

in the

process

of reviewing

lesson

plans

gA6084G,

and

gA6085G in preparation for development of a

formalized

Eg training program.

A commitment date of Nay 15,

1988,

was

also

given

as

the starting

date

for implementation

of the

training

program.

Based

on

review of objective

evidence

and

discussions

with licensee

training staff the inspector verified that

a formalized

Eg training program

had

been

developed

and

implemented

for non-craft personnel

in accordance

with licensee

commitments.

Requirements

for providing training,

continuing

training,

and

on-the-job

training for maintenance

personnel

is specified

in

procedure

TI-113.

Pursuant

to review of this procedure

during the

first round

Eg inspection,

the inspector determined that

a formalized

training

program

had

not

been

established

for indoctrination

and

training

of Electrical

and

Instrumentation

and

Control

(I8C)

personnel

in the requirements

of Harris

Eg program.

This deficiency

was

previously

recognized

by the Electrical

Craft

and

Technical

Steering

committee in late

1987.

They recommended

that gualification

Checkout

Cards

(gCCs)

that define specific

tasks

related

to the

implementation of the

Eg program

be developed

and

used for craft

Eg

training.

The inspector

determined that the

above

recommendation

has

not been

acted

upon

by licensee

management.

Additionally, the Electrical

and

I8C maintenance

personnel

have not been indoctrinated

and trained in

the

requirements

of the

Eg program to

an extent similar to 'that

provided non-craft

personnel.

Licensee

management

has identified

deficiencies

in the implementation of the

Eg maintenance

program.

A

prime contributor to these deficiencies

was identified as lack of Eg

training of the craft.

Corrective

actions

completed

included

development

and presentation

of a one

hour. course

(No. CT1010H), to

maintenance

personnel.

Licensee

management

further indicated that

long term corrective action in the form of continuing training on the

requirements of the

Eg program was presently

being established.

This

would involve expansion

of course

CT101H in lieu of the use of gCCS

and

would

be

given periodically every

two years.

The licensee

indicated that training will begin

on or around

February

1989.

Eg Equipment Replacement

and Spare Parts

Procurement

A review of the

implementation

of the

procurement

program

was

performed

to verify conformance

with applicable

industry

codes

and

standards

and regulatory requirements.

The following environmentally

qualified

equipment,

selected

for physical

inspection

during

the

plant walkdown,

was chosen for this review.

E ui ment Descri tion

SFD.

Ta

No.

ASCO Solenoid .Valve

CP-5:005

Pressurizer

Safety Valve

Position Indicators

(CR0534)

NAMCO limit Switch

(CV Purge Valve)

Target

Rock Valves

ZS-R530SAB

1CP-5:004

1RC-901

E ui ment Descri tion

cont

SFD.

Ta

No.

Barton Transmitter

(Model 764)

Barton Transmitter

(Model

763)

LT-474

PT-455

Barton Transmitter

(Model 752)

FT-414

Purchase

Orders

(PO) for the

above

equipment

were retrieved

by the

Licensee

Engineering

Technical

Support

group via on-line

Supply

Inventory

System

computer

network.

The

inspector

reviewed

the

purchase

orders

and verified that applicable

technical

and quality

requirements

required

for environmentally qualified equipment

had

been

specified.

Additionally, the review was

performed

to ensure

that reference

to an

Eg Test Report,

and the requirement of 10 CFR 21

had

been

included.

No deficiencies

were identified during this

effort.

Procedure

number

TMM-104, paragraph

5.4.4.

defines

"Off-the-Shelf"

item as

commercial

grade

and provides criteria for commercial

grade

items that are similar to 10 CFR 21.3(4)(a-l).

Paragraph

5.4 of this

procedure further specifies

the method for determining the technical,

quality,

and regulatory

requirements

for procurement

documents

and

delineate

the applicable guality Classes

on which these

requirements

are to

be

imposed.

Guidance for the determination of guality Class

of

replacement

parts,

equipment

and

material

is

shown

on

Attachment

E.

This attachment

permits

the procurement of coomercial

grade

replacement

parts for end use in basic

components.

Interviews

were

conducted

with licensee

personnel

to determine

the

technical

adequacy

of the

Dedication

process

for commercial

grade

items

prior

to their

use

in basic

components.

The

inspector

determined

that

CP8L

Corporate

equality

Assurance

Manual,

Section 5.5.a

requires

that

an engineering

evaluation

be performed

prior to

the

use

of an "Off the Shelf"

item.

The

procurement

evaluation

process

specified

in Section

4.3.4 of the

manual

is

intended

to meet this engineering

evaluation

requirement

and allows

for the

preparation

of purchase

requisitions

in accordance

with

approved

procedures,

or alternatively,

by performance of a specific

engineering

evaluation.

Section

4.3.4 of the Corporate

guality

Assurance

Manual also states

that

once

an item has

been evaluated

to

,be acceptable

for off-the-shelf use the original specification

does

not

remain

as

the

governing

purchasing

criteria,

and

vendors

supplying off-the-shelf items

are not required to be

on the approved

Suppliers List.

Direct

replacement

parts

are

procured

by part

number

via

the

preparation

of purchase

requisitions

in accordance

with procedure

TMM-104.

Guidance

for

performing

'the

required

engineering

evaluations

are

delineated

in Attachments

A,

B,

and

C of this

procedure.

Pursuant

to review of these

attachments

and discussions

with licensee

personnel

the

inspector

determined

that

adequate

procurement

controls

have

not

been

developed

and

implemented

to

verify

the critical

characteristic

data

of

commercial

grade

replacement

parts

intended for use in

Eg applications.

The existing

procurement

controls for replacement

parts

do not ensure identifica-

tion of select critical characteristics.

Licensee

management

stated

that ordering replacement

parts

by part number

guarantees

receipt of

like-in-kind replacements.

However,

because

the

replacement

parts

are

procured

commercial

grade

no documentation

are required

to

be

provided

by the

vendor

to assure

that

the

replacement

parts

are

identical

to the original parts..

The inspector

made

a random selection of commercial

grade

replacement

parts

used

by the licensee

in

Eg applications

to verify conformance

with technical

and regulatory requirements.

The parts selected

were

primarily non-electrical

replacement

parts,

gaskets,

and lubrication

oil.

The inspector

determined

that the licensee

has established

a

chemical

and

consumable

control

program

for

replacement

parts

identified

as

consumables.

Applicable requirements

of this program

are

imposed

during the

procurement

of bulk commercial

grade

items

such

as gaskets,

O-rings,

'and lubricants.

The requirements

provide

for identification of chemical characteristics

of the material and/or

special,

or limited use associated

with the material

because

of plant

specific

requirements.

No

Eg deficiencies

were identified during

this review.

The

inspector

selected

a

broader

sample

consisting

of electrical

replacement

parts.

Documentation

associated

with the part

numbers

selected

were transmitted

to the

Regional

Office

by the licensee

after completion of the inspection.

The following purchase

orders

and supporting

documents

were reviewed.

PO No.

44109700

198507BT

"1 91108 8F

46813 1BT

425388AR

Part

No.

727-653-73

725-619-12

725-631-82

726-048-87

726-039-96

Material Description

Si licone

Caulk

,Groove Pin

Limit Switch Rotor

Terminal Block

Silicone Gasket

The licensee

uses

various

methods

to ensure

recei pt of like-in-kind

replacement

parts.

The

replacement

parts

were

procured

by part

number from the original equipment manufacturer

who in some instances

provided

compliance.

The Certificate of Compliance certified that

the

materials

met

all

the

requirements

of

the

PO

and

specification.

Additional

controls,

demonstrated

for

PO

No.

191108BF,

the procurement of only nuclear grade replacement

parts

which are

then

used in both standard

and nuclear applications.

The

limited engineering

evaluations,

performed

for determination

of

replacement

parts

critical characteristics,

do

not

appear

to

adversely

affect

the

procurement

of like-for-like parts.

The

purchase

order

imposes

instructions that there shall

be

no change in

part

numbers

or item description

unless

approved

by the purchaser.

Design

changes

initiated

by the

vendor

needs

to

be reported

and

should state

whether the

new part number services

the

same fit, form

and function

as

the old part

number.

Additionally,'he receipt

inspection

process

provides for verification of easily identified

physical

characteristics,

part

number;

and

when

ne'cessary,

verification of performance characteristics

by performance of special

tests.

Based

on the

sample

reviewed,

the inspector

concluded that

technical

and quality requirements. for like-in-kind replacement

parts

are maintained

during implementation of the procurement

program.

No

EQ deficiencies

were identified -during this review.

QA/QC Interface

Nonconformance

Report

No.87-098,

was written on August 7,

1987; to

document

a significant deficiency in the

implementation of the

EQ

maintenance

program.

The

problem

involved

degradation

of the

environmental

qualification

boundaries

of

equipment

caused

by

maintenance

activities.

The

root

cause

was

determined

to

be

inadequate

training of both the maintenance

planners

and maintenance

craft personnel

in requirements

of Harris

EQ program.

Corrective

actions

taken, to

resolve

this

deficiency

are

described

in

paragraph

"b" above.

Additional corrective action,

implemented the week of August 8,

1988,

=to correct

the

above

deficiency

included

restructuring

the

EQ

Technical

Support organization.

An additional staff positions

have

been

added with responsibilities for administrative control of the

EQ

maintenance

program.

The objective of the

reorganization

is to

provide centralized

control for implementation of the

EQ maintenance

program.

Functional responsibilities,

levels of authority,

and lines

of internal

and

external

interface

communications

will also

be

specified to better coordinate

and assess

the effectiveness

of the

EQ

program.

Pursuant

to discussions

with licensee

management

the inspector

was

informed

that

procedure

PLP-108,

"Environmental

Qualification

Program," wi 11

be revised to reflect the above organizational

change.

A commitment date of October 1,

1988,

was

given for completion of

this

revision.

The

inspector

also

reviewed

section

4.4.2

of

procedure

PLP-108,

and verified that

inadequacies

in the

program

description identified during the first round

EQ inspection

had

been

corrected.

The corrective

action

was

completed

in accordance

with

the licensee prior commitment.

Within this area,

no violations or deviations

were identified.

Eg Documentation Files

and Walkdown Items

The

NRC inspectors

examined files for 28 equipment

items,.where

an

item is

defined

as

a

specific

type of electrical

equipment,

designated

by manufacturer

and model, which is representative

of all

identical

equipment in

a plant area. exposed

to the

same environmental

service conditions.

The inspector selectively reviewed areas

such

as

(1) required post-accident

operating time compared to the duration of

time

the

equipment

has

been

demonstrated

to

be qualified,

(2) similarity of tested

equipment

to that installed in the plant,

(3) adequacy

of test

conditions

enveloping, calculated

accident

profile conditions,

(4) aging

calculations

for qualified life

determination,

(5) temperature

related effects

on instrument accuracy

due to decreases

in insulation resistance,

(6) evaluation of test

anomalies,

and (7) applicability of Eg problems reported in IEBs/IENs

and their resolution.

The results of the file reviews

and walkdown

items will be

discussed

in detai

1 in the paragraphs

that follow;

however,

in general,

the files were considered

adequate.

(I)

General Electric Vulkene

Supreme

Mire (E(DP 6.10)

The inspector

reviewed

the- file for General

Electric Vulkene

Supreme

SIS wire used outside

containment for control applica-

tions.

The qualification basis

was

NUREG-0588,

Category I.

The

worse

case

steam

environment is in the steam

tunnel

where the

peak

temperature

reaches

437'F for about ten minutes,

followed

by a fairly rapid return to much lower temperatures.

A thermal

lag analysis

(File

No. 2202.006,

not reviewed) yielded

a peak

temperature of'28'F.

The radiation dose is 43 Hrad normal

and

I Mrad,accident.

The

cable

was qualified to

nominal

IEEE 323-1974

conditions

and is reported tin

FRC report

F-C4497-2.

All plant

parameters

were

enveloped.

The tested

cable

was

identical

to the

cable

purchased

for the plant.

Good

IR

performance

was indicated

by the

steam test.

No findings were

identified.

(2)

Rockbestos

Coaxial

Cable

(E(DP 6.7)

The inspector

reviewed

the file for Rockbestos

coaxial

cable

used for instrumentation circuits, including the General

Atomics

radiation

monitor inside

containment.

Cables

used

include

RSS-6-104/LD,

RSS-6-105/LD,

and RSS-6-108/LD.

The qualification

basis

was

NUREG-0588,

Category I.

The plant parameters

were

enveloped

by the test

and the

LD/LE similarity analysis

was

included

in the file.

Performance

(IR) of the

cable

is

addressed

elsewhere '(in General

Atomics radiation monitor file,

not reviewed).

No findings were identified.

(3)

Instrument

Loop Accuracy Calculations

(EgDP 90. 1)

10

(4)

The inspector briefly reviewed

the

instrument

loop accuracy

calculations

of

EgDP 90.1.

This file contains

the basis

and

justification for data

supplied

to Westinghouse

for input to

loop accuracy

calculations.

The reviewed calculation

does

not

include

any, degraded

IR calculations.

Cable lengths

and

IRs

used

for cables,

connectors,

penetrations,

and

splices

are

determined

in the

package

and justified based

on

peak expected

containment

temperature.

No findings were identified.

Rockbestos

Instrumentation

and Control Wire (E(DP 6.8)

The inspector

reviewed the file for Rockbestos

chemically

XLPE

(Type XXL-760D) insulated

600V control

and thermocouple

cable.

The control

cable

is used

in Limitorques

and the thermocouple

cable is

used

in Westinghouse

penetrations.

The qualification

basis

was

NUREG-0588,

Category I.

The plant parameters

were

enveloped

by

the

test

conditions.

Insulation

resistance

performance

was satisfactory

during the test.

No findings were

identified.

(5)

Rockbestos

Instrument

and Control Wire (EgDP 6.9)

The inspector

reviewed

the file for Rockbestos

radiation

XLPE

insulated

cable.

All information for this cable is the

same

as

for the chemically

XLPE cable

in

4 above.

No findings were

identified.

Okonite Okozel

Cable

(EgDP 6. 13)

The inspector

reviewed the. file for okonite cable insulated with

Okozel,

an

ETFE flouropolymer (Tefzel).

The qualification basis

was

NUREG-0588,

Category I.

The cable

is

used for internal

jumpers

and for field cable terminators for Target

Rock Solenoid

valves.

This cable

was purchased

and installed

as

a result of

IEN 84-68.

The cable is rated at 150'C in dry locations with a

qualified life of ten years.

The cable

type designation

are

Z

and

ZW.

The only area

questioned

was that of documentation

required to support

Category

I qualification.

Prior to the end

of the inspection,

additional

documentation

was

obtained

and

will be added to the file.

The

new documentation

was considered

adequate

for Category I qualification.

No findings

were

identified.

(7)

Anaconda Control Cable

(EgDP 6.11)

The inspector

reviewed the package for Anaconda

NSIS switchboard

and

control wire.

The qualification basis

was

NUREG-0588/

Category I.

The cable

has

FR-EP. insulation

and

a

CPE jacket.

The test

parameters

enveloped

the

plant

parameters

with

a

qualified life of 40 years

at 71'C.

The

two test

specimens

identical

to the

cable

used

in the plant both carried

rated

voltage

and

current with IRs

in excess

of 107L.

The test

results

are reported

in

FRC report F-C4969-1.

No findings were

identified.

(8)

(9)

(Io)

(II)

Anaconda

Power Cable

(EgDP 6.6)

d

The inspector briefly reviewed

the file for Anaconda

medium

voltage

(15

kV) power cable.

The cable is specifically excluded

from safety-related

use in the containment or main steam tunnel,

resulting in a peak accident

temperature of only 133'F and less

than

1 Mrad radiation.

No findings were identified.

Anaconda

Instrumentation

Cable

(E(DP 6.2)

The inspector

reviewed

the file for Anaconda

instrument

and

thermocouple

extension

cable.

The, qualification

basis

was

NUREG-0588/Category I.

The test conditions

enveloped

the plant

parameters

with

a qualified life of

40

years

at

71'C.

Submergence

testing

was

included.

The

cable

uses

FR-EP

insulation

and

a

CPE jacket.

The tested

cables

are similar to

those

used

in the plant with the only significant difference

being

conductor

materials

in

some

of

the

plant

cables

(thermocouple

extension wire).

IR performance

during the

30 day

LOCA was better than

106L.

The test results

are reported in

FRC

reports

F-C4969-I and F-C4836-2.

No findings were identified.

Eaton Thermocouple

Extension

Wire (EgDP 6.3)

The

inspector

reviewed

the file for Eaton

(Samuel

Moore)

thermocouple

extension

wire using

an

FR-EPDM insulation.

The

qualification basis

was

NUREG-0588/Category I.

gualification

was

based

on tested

specimens

with the

same insulation material.

IR

performance

during

the test

remained

better

than

I ML.

Submergence

testing

was included

and all plant parameters

were

enveloped.

No findings were identified.

Bishop Electrical

Tape

(EgDP 16.2)

(>2)

The

inspector

briefly

reviewed

the file for

Bishop

semiconducting

electrical

tape

used

for

600

V

and

15

kV

terminations.

The

qualification

basis

was

NUREG-0588/

Category II.

The tape is not used for safety applications

in

the

containment

and main

steam

tunnel,

giving

a peak accident

tempertaure

of 167'F.

The

only significant qualification

parameter

is

43 Mrad of aging which is enveloped

by a 200 Mrad

radiation test.

No findings were identified.

Scotch Electrical

Tape

(EgDP 16.4)

The

inspector briefly reviewed

the file for Scotch

semi-

conducting

electrical

tapes.

The qualification

basis

was

12

(13)

NUREG-0588/Category II.

The

cable

is

not

used

in safety

applications

in the containment

and

main

steam

tunnel,

making

the

maximum accident

temperature

167'F.

A Radiation aging dose

of 43 Mrad was enveloped

by test.

No findings were identified.

Okonite Electrical

Tape

(EQDP 16.3)

The inspector

reviewed

the file for Okonite T-95

and

No.

35

electrical

tapes

used for splices

and terminations

outside of

the containment

and main steam tunnel.

The worst case

accident

temperature

is 167'F.

The qualification basis

was

NUREG-0588/

Category I.

The

normal

aging

dose

of

43

Nrad

was

easily.

enveloped

by test.

No findings were identified.

(14) AIW Cable

(EQDP 6.5)

The

inspector

reviewed

th'e file for

AIW cable

used

for

instrumentation

and control

applications

outside

containment.

The qualification basis

was

NUREG-0588/Category I.

Both the

tested

and installed cables

are single conductor with 30 mil .of

EPDN insulation.

The test profile enveloped

the plant require-

ments.

IRs

measured

during the

steam

exposure all exceeded

108L.

No findings were identified.

(>5)

(I6)

RdF Temperature

Elements

(EQDP 39.8)

The inspector

reviewed the file for RdF model

21205

RTDs used to

monitor

RCS hot

and

cold leg temperatures.

The qualification

basis

was

NUREG-0588/Category I.

The test units were identical

to

those

used

in

the plant.

Qualification

was

based

on

supplement

2-E06A of WCAP-8687.

Aging was

performed for 264

hours

at 400'F giving

a qualified life of 23 years

at

100'C

(50'C

ambient

+

50'C

heat

rise

due

to

process

fluid).

Performance

was monitored

by measuring, the detector

outputs

and

monitoring

insulation

resistance

to

ground

periodically

(specification of I NL minimum).

Because

of testing

problems,

the cable to the detector

was installed in sealed

conduit to get

the unit to pass.

The plant requires

the installation of

a

Conax

T8 sealed

termination

head with a

Conax

ECSA to address

the sealing

requirement.

The qualified life determination

is

still pending verification of service

temperature.

No findings

were identified.

BIW Triaxial Cable

(EQDP 6. 1)

The inspector

reviewed

the package for BIW triaxial cable with

Tefzel

insulation.

The qualification basis

was

NUREG-0588/

Category I.

Testing

to

envelope

the

plant conditions

was

performed

but the

documentation

in the file was

considered

inadequate

to support

Category

I qualification.

Specifically,

the

items of Section

8.3 of

IEEE 323-1974

were

not fully

13

(I7)

addressed.

However, this item was previously accepted

by

NRR in

NUREG-1038,

Supplement

4, Section 3.11.4.

Target

Rock Solenoid Valves

(E(DP 3. I)

The

inspector

reviewed

the file for Target

Rock

799 series

solenoid

valves.

The qua'lification

basis

was

NUREG-0588/

Category I.

The valves

are primarily sampling

system contain-

ment isolation

valves.

Some of the

valves

are continuously

energized

and/or

subject to process

heat rise during

normal

operation.

Typically, the valves all closed at the beginning of

an accident,

but there still may

be process

heat rise.

The

licensee

performed

calculations

which

showed

very

short

'ualified

lives for

some of the valves

(on the order of one

month),

based

on the artificial aging performed.

An analysis,

based

on testing

done

on

a valve

removed

from Sequoyah

after'ive

years of continuously energized

service,

was

used to extend

th'e

minimum qualified life to one cycle.

Two questions

wer e

posed

to the licensee.

First, the valve

removed

from Sequoyah

did not appear

to be

one which would be subject to process

heat

rise,

resulting

in

a question

of the applicability of the

Sequoyah

valve.

Second, .it was, not clear what process fluid

temperature

was

used

in the Target

Rock test,

resulting in

a

question

of whether

the

plant valves

cou'Id

be

exposed

to

temperatures

above their qualification when accident conditions

are combined with process

heat rise.

The licensee

is addressing

the first question

through

on-going

evaluation

and

a test

program using naturally-aged

valves being removed from the plant

during the current outage.

The second

question

was adequately

addressed

by considering

the accidents

where the valves would be

needed,

their required

state

during these

accidents,

and the

actual

accident profile.

The question of qualified life and the

results

of additional

testing will be

reviewed at

a future

inspection.

Therefore,

this

item is

considered

unresolved

pending

the results of the testing to be performed

on the coils

removed

during this outage

and documentation

of the results

by

NED in the

E(DP (Unresolved

Item (URI) 50-400/88-27-02).

(18) Limitorque Actuators

(Dual Voltage),

Equipment

Tag Nos.

1CC-249

and,lCS-470

(Inspection Plan TI 2500/17)

The

Phase

1

Eg inspection

held

March 7-11,

1988, identified

URI

50-400/88-04-01,

Nylon

type

Crimp

Connectors

on

Dual

Voltage

Limitorque Actuators.

At the

close

of that

inspection,

the

licensee

committed

to obtain qualification

documentation

for the

nylon crimp connectors

or

remove

the

connectors

and replace

them with qualified splices.

The purpose

of the

Phase

2 equipment

walkdown was to physically inspect the

dual voltage limitorque actuators

inside containment,

determine

if the

nylon

connectors

were

being

used,

and

evaluate

the

licensee's

basis for qualification of these

connectors.

14

There

are

two dual

voltage Limitorque actuators

(1CC-,249

and

1CS-470)

inside

containment.

The

walkdown of these

valves'erified

that the mounting configuration was consistent

with the

tested

configuration.

The T-drains

and

grease

reliefs

were

found to be properly installed.

The equipment

was identified by

the manufacturer's

nameplate

as

a

dual

voltage

model.

The

licensee. stated that the nylon connectors for both were replaced

with Raychem splices.

The inspection of

1CS-470 verified that

Raychem splices

were

installed

on the motor lead connections.

When questioned,

the

~ licensee

could not identify the type of connectors

since

the

connectors

were not saved.

The licensee

stated that there

was

documentation

available

from Limitorque which indicated that

only Thomas

and Betts connectors

were supplied in the actuators.

Aging qualification could

be

demonstrated

by

a separate

test

report

on

the

motor.

Although,

these

documents

were

not

reviewed, it appeared

that

the

connectors

were qualifiable.

This finding was identified

as

a potential violation,

on the

basis

that

at

the

time of the

inspection

the

Eg file was

deficient in showing the qualification of the nylon connectors,

however, it is not clear that the licensee

should

have

been

aware

of this

problem

considering

the

location of these

connectors.

Therefore,

a violation will not be cited.

(I9)

Component

1CC-249

was

not

inspected

internally

since

the

licensee

stated that the

same

Raychem splices

were installed to

replace the nylon connectors.

Limitorque Actuators

Equipment

Tag Nos.

1RH-40,

1RH-2,

IED-94,

and 1SI-246 (TI 2500/17)

The

above

Limitorque actuators

were

inspected

for mounting

configuration, T-drains,

grease reliefs,

nameplate

information,

and internal wiring.

The installed configuration

was

found to

be consistent

with the

tested

configuration.

All walkdown

concerns

were addressed

prior to the close of the inspection.

The inspection of 1RH-40 discovered

a small

leak of red grease

inside

the

housing for the limit switches.

The

licensee

identified the grease

as Mobil 28 and stated that orientation of

the

actuator

prevented

the

grease

from reaching

the

switch

contacts.

Work ticket

WR5A 88AUJSI

was

issued

to clean

the

housing.

Valves

1RH-2

and

1CS-470

were

found to

have

terminal

boards

wired at adjacent

points, while 1SI-246

was wired at alternate

points.

When questioned,

the licensee

explained

that either

wiring configuration

was

acceptable,

since

Limitorque report

80119 supported

the

use

the

GE, marathon,

and

Buchanon terminal

blocks

in their worst

case

wiring configuration

(adjacent

points).

15

There were several

Raychem splices

where the shim protruded

from

the sleeve

and other

c'ases

where the sl'eeve

overlapped

the shim.

When questioned

the licensee

stated that the

Raychem installa-

tion Guide was used

as the basis for the plant 'procedures

-WP-210

and

EMP-3.

The installation

guide indicates that

an accident

location

requires

a 2-inch

seal

length.

In

a single

shim

installation

the

shim may

be overlapped

or protrude

from the

insulation

sleeve.

The seal

lengths

of several

splices

were

measured

and found acceptable.

Barton Transmitter

Models

763

and

765,

Equipment

Nos.

LT-474,

LT-477, 1RC-455,

and

1RC-456

The above transmitters

were inspected for mounting configuration

'and wiring and found acceptable.

Raychem splices

were used for

all connections.

Single

shims

were

used

and

appeared

to

be

properly installed.

There

were

no concerns

identified during

the walkdown.

(21)

(22)

Minco RVLIS RTD, Equipment

Tag Nos.

TE-1313

and TE-1314

The

above

RTDs

were

inspected for mounting configuration

and

wiring and found acceptable.

Raychem splices

were used for all

connections.

Single shims were used

and appeared

to be properly

installed.

The locations of all Minco RTDs were identified and

found to

be

above

flood level.

There

were

no

concerns

identified during the walkdown.

Reliance

Motors,

Equipment

Tag

Nos.

1CV-E002:004

and

ICV-E002:005

As a result of the

Phase

1

Eg inspection,

the licensee

committed

to inspect

the

Re'liance

motors

and

remove

the grease

lines to

the sealed

bearings.

However,

subsequent

to that commitment the

licensee

determined that the motor had double shielded

bearings

for which the use of grease

lines

was specified.

The licensee

surveyed

knowledgeable

personnel

at

Shearon

Harris

and other

plants for advice

on lubrication of the motor bearings,

but the

results

were inconclusive.

The licensee

took the conservative

approach

and committed to install the grease

lines

on the motors

during the outage.

The work tickets were identified and found

acceptable.

The licensee will void the original work tickets to

remove the grease

lines.

This explanation

was acceptable.

The

motors

were not inspected

during the walkdowns

due to limited

time.

(23) Hydrogen Recombiner

Equipment

Tag No.

1SP-E003

The

equipment

was

inspected

for mounting configuration

and

wiring and

found acceptable.

The

5

and

I

Raychem

splice

=

16

(2~)

configuration appeared

to be properly 'installed.

There were no

concerns

identified during the walkdown.

Electrical

Penetration

Assembly,

Equipment

Tag

Nos.

1AB-S1206

and

1AB-1225

(25)

These

penetration

assemblies

were

inspected

for mounting

configuration

and wiring and

found acceptable.

Penetra4ion

1AB-S1206

(and

other

EPAs

in

the vicinity) could

not

be

identified from the back panel,

which required

someone

to crawl

around

the

penetration

assemblies

in order

to

locate

the

equipment

tags.

There

was

a concern

that personnel,

exposure

would be incr eased

anytime

someone

needed

to identify a specific

penetration

assembly.

The licensee

issued

WRSA 88-AUNG1

and

committed to lable the penetrations

on the

back side of each

enclosure.

This was acceptable.

The inspection of Penetration

1AB-1255 discovered

several

black

wires with the

bare, conductor

showing where the insulation

was

stripped back.

When questioned,

the licensee

explained that the

Raychem splices

associated

with these

cables

were supplied

by

Westinghouse

as part of the electrical

penetration

assembly.

Installation was done in accordance

with the

Raychem guidelines.

The shield

on all cables

spliced

by Westinghouse

are covered for

isolation purposes

only.

This explanation

was acceptable.

GEMS

Transmi tter,

Equipment

Tag

Nos.

LE-01CT-7160ASA

and

LE-01CT-7160ASB

(26)

The

equipment

was

inspected

for mounting configuration

and

wiring and

found acceptable.

Raychem

splices

were

used

and

appeared

to be properly installed.

The junction box was filled

with silicon oil as

required

to seal

the terminations for the

sensors.

No concerns

were identified during the walkdown.

Eg Cable Identification

During the

walkdown portion of the inspection,

the inspector

obtained

cable identification

numbers

from the cable

connected

to selected

Eg equipment.

The licensee

was then

asked

to show

that

the

installed

cable

was .qualified

by their existing

'qualification

documentation.

With the 'cable

identification

number,

the licensee

referenced

the applicable pull card which

showed

the

cable routing,

reel

number

and termination

points

along with

a receipt

inspecti'on report which shows the bill of

materials

number for the installed cable.

The bill of materials

number

was

shown

on the

Eg Master List which identified the

Eg

file which established

the qualification for that cable.

.With

this

sampling,

the

inspector

determined

that

adequate

traceability

existed

for the

cables

requiring

environmental

qualification.

17

(27)

Samples of Target

Rock Solenoid Valves,

ASCO Solenoid Valves and

Namco Limit Switch installations

were

examined

in various

locations inside containment for manufacturer

and model

number,

orientation,

installation,

and interfaces (i.e.,

cable splice

and

entrance

seals).

No concerns

were identified during the

walkdown.

Since

the

inspection

the

licensee

has

reported

several

concerns

regarding

the

qualified

status

of their

installed Target

Rock valves

as

a result of cracked insulation

on

Reed Switch lead wires, cracked terminal blocks

and lack of

~

similarity between

tested

configuration

versus

vendor supplied

components

(i.e.,

terminal

blocks

and wiring).

All these

components

are

internal

to the

device.

Licensee

plans

to

replace all questionable

parts prior to restart.

f.

Followup of Licensee's

Commitments

Resulting

From the

Phase I

EQ

" Inspection

At the conclusion of the

Phase I

EQ inspection,

there

were

numerous

action

items which the licensee

committed to perform.

During the

Phase

2

EQ inspection

the

INEL inspectors

examined

the

EQ files,

PCR

change

requests,

and

work requests

to verify that

the

licensee

fulfilled its

commitment to resolve

these

items.

These

documents

were reviewed

and discussed

with the licensee

to verify that the

EQ

concerns

were adequately

addressed.

The Phase

2 inspection verified that the basis for corrective action,

qualification analyses,

s'afety analyses,

revisions to the

EQ files,

and

internal

reviews

were

performed

and

accepted

by the licensee

before

the

Phase

1 action

items

were considered

closed.

Discussion

with the

licensee

and

a brief walkdown of the 'central

files

determined

that

the

document

control

was

acceptable.

All work

requests

resulting

from the initial inspection

were

found to

be

completed or scheduled for completion during the outage.

Other

NRC

Inspectors

verified the licensee's

commitments for

EQ training and

replacement

equipment.

The following documents

were reviewed with respect

to updating the

EQ

files and found acceptable:

EQDP 3.3

Limitorque Actuators

EQDP 8.2

GA High Range Monitor

EQDP 8.3

'GEMS Transmitter

EQDP 8. 11 Barton Transmitter

763 and

764

EQDP 15. 1 Westinghouse

Electrical penetration

PCRs

2959,

2960,

3036,

3037,

3038,

3039,

3040,

3041,

3042,

3078

and

3414

With the

exception of the Limitorque crimp connectors,

all action

items resulting from the previous

inspection

were reviewed

and found

to be closed or awaiting closure during the outage.

18

3.

Action On Previous

Inspection

Findings

(92701)(92702)

a ~

(Closed)

URI 50-400/88-04-01,

Nylon Type

Crimp Connectors

On

Dual

Voltage Limitorque Actuators'TI 2515/75)

During the first round

Eg inspection,

the possible

use of nylon type

crimp connectors

in dual voltage Limitorque operators

was identified.

The

licensee

identified four valves

(two inside

and

two outside

containment)

with

dual

voltage

operators

and

possible

crimped

connectors.

The information that

was available to the licensee

was

not adequate

to establish qualification of the crimp connectors.

The

licensee,

therefore,

committed

to either obtaining

the

necessary

documentation

or to remove all the nylon type crimped connectors

and

replace

them with qualified splices.

The . licensee

issued

Work Requests

88-ATS41

and

88-ATSZ1 for 1CS-470

and

1CC-249, respectively,

to remove the nylon type crimp connectors.

The work requests

were completed

a few days prior to this

inspection.'ven

though the licensee

was aware of =the qualification issue

and its

importance,

the nylon type crimp connectors

that were

removed

from

the

motors

had

been

thrown

away.

However,

recent

information

obtained

during

an

inspection

of

Limitorque

(NRC

Report

No.

99900100/88-01)

seems

to indicate that only

TSB

joints were used.

The test report the licensee

referenced

during the first inspection

(Limitorque Test

Report

B0003)

could only

be

used

to establish

qualification of the

connectors

for six to twelve months

had the

connectors

been

Thomas

and Betts

RB-4 or

6 models for use outside

containment.

Without the

removed

connectors,

the licensee

could not

clearly establish qualification of the affected motor operators

.to any

test

report.

The

licensee's

failure

to

have

qualification

-documentation

in

a file for the

TSB connectors

is

an

apparent

violation of the

Eg rule; however,

as stated earlier in the paragraph

2.e. 18.,

no vi'olation will be cited

because it is not clear the

licensee

should have

been

aware of this problem.

While the

connectors

were being

replaced

on

1CS-470,

the licensee

identified that the T-drains were missing

on the motor.

Work request-

88-ATSXI was performed

on August 13,

1988, to install the T-drains

on

the motor.

The licensee

was asked

to provide

a scenario of when the

T-drain

issues

had

occurred.

For

1CS-470, it was

found that

WR86-BFPV1

had

been

performed to install T-drains

on the motor.

Even

though

the

work request

had

been

signed off as

being

completed,

1CS-470 did not have T-Drains installed

when it was being worked on

in August

1988.

Although this T-drain issue

was identified

by the licensee, it is

considered

as another

example of Violation 88-27-01.

This is due to

the fact that the licensee

had

been notified that

NRC would look at

this particular valve during this inspection.

'

19

b.

4.

Exit

(Closed)

Inspector

Followup Item 86-88-03,

Continue

Review of Cable

-Splicing Program

and TI2500/17, Inspection

Guidance for Meat Shrinkable

Tubing

Documentation

to qualify the

Raychem 'heat

shrinkable

tubing

was

reviewed

and

documented

in

NRC Inspection

Report No. 50-400/88-04

as

being acceptable.

A walkdown of a sample of splices

was performed

by

the

inspectors

as well

as

a review of the licensee's

activities

regarding

Raychem heat shrinkable splices.

The

walkdown did

not identify

any splices

in

an

unqualified

configuration.

The licensee

had identified

some splices

prior to

this

inspection

that, did not

meet

the

bend

radius

specified

in

procedure

ENP-3 for installing the heat shrink tubing.

Although the

procedure

was

not followed,

the splices

were qualified

by the

qualification package.

The licensee

has taken corrective actions to

require

gC inspection

hold points during this installation of the

Raychem splices.

It should

be noted that

had this been identified by NRC, it would have

resulted

in the citing of

a violation for failure to follow

procedures.

However, since this was identified by the licensee, it

fits in the Severity

Level IV or

V category, it did not require

reporting,

corrective

actions

have

been

taken,

and it was

not

a

repeat violation.

No violation will be cited in this case.

Based

on the results

of the

walkdowns

and

the previous

document

reviews,

these

items are considered

closed.

Interview

The inspection

scope

and results

were summarized

on August 19,

1988, with

those

persons

indicated

in Paragraph

1.

The inspectors

described

the

areas

inspected

and

discussed

in detail

the inspection

results listed

below.

Proprietary

information is

not contained

in this report

and

dissenting

comments

were not received from the licensee.

The following new items were identified during this inspection:

Violation 50-400/88-27-01,

The

licensee

failed to

take

adequate

corrective action to ensure that maintenance

did not violate the

Eg

boundaries

of Eg equipment,

paragraph

2.a.

Unresolved

Item 50-400/88-27-02,

EgDP 3. 1 is the qualification file

for Target

Rock

790 Series

Solenoid

Valves.

The licensee

performed

aging calculations

which

showed

very short qualified lives for the

continuously energized

valves

(on the order of one month),

based

on

the artificial aging of tested

samples.

The licensee

extended

the

qualified life to

a cycle based

on a

TVA report.

The

NRC questioned

20

the

use of the

TVA report

because

the licensee failed to show the

'similarity between their installation (i.e;, continuously energized

on

hot

process

pipe)

and

TYA's installation, at

Sequoyah.

The

licensee

committed to do additional testing

on naturally-aged

valves

being

removed

from

the

plant, during

the

current

outage,

paragraph

2.e.17.