ML17055B747

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Insp Rept 50-220/86-05 on 860414-18.No Violation Noted.Major Areas Inspected:Environ Qualification Files of Limitorque Valve Motors,Rosemount Transmitters & Fenwal Temp Switches & Previously Identified Items
ML17055B747
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/28/1986
From: Anderson C, Cheung L, Paolino R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17055B746 List:
References
50-220-86-05, 50-220-86-5, NUDOCS 8606100074
Download: ML17055B747 (28)


See also: IR 05000220/1986005

Text

(

U.S.

NUCLEAR REGULATORY COMMISSION

REGION I

Report

No.

50-220/86-05

- Docket No.

50-220

License

No.

DPR-63

Priority

Category

C

Licensee:

Nia ara

Mohawk Power Cor oration

300 Erie Boulevard West

S racuse

New York

13202

Facility Name:

Nine Mile Point

Unit

1

Inspection At:

S racuse

New York

Inspection

Conducted:

A ri 1 14-18

1986

Inspectors:

eonard

S.

Cheung,

Reactor

gineer

date

Ralph

P olino,

Lead

R

tor Engineer

da

e

Cliff A erso,

Chief

Plant Systems

Section,

EB

Mark Jacobus,

Sandia National

Lab.

Steve Alexander,

Engineer

IE

s

2.x

P'4

date

Approved by:

Cliff A d rson,

hief

Plant Systems

Section,

EB

date

Ins ection Summar:

Ins ection

on A ril 14-18

1986

Re ort No. 50-220/86-05

~d:,>>

i

  • i

i

i

lid

tial enforcement/unresolved

items

and open

items (50-220/86-05-01

through -11)

and corrective actions

taken

by Niagara

Mohawk Power Corporation with regard to

meeting the requirements

of 10 CFR 50.49.

Also included

as

a part of this inspec-

tion was review of additional

environmental qualification (Eg) files of Limitorque

Valve motors,

Rosemount transmitters

and

Fenwal

temperature

switches.

8606100074

860603

PDR

ADaCZ 05000aa0

G

,

,

PDR

Results:

Status of Previousl

Identified Items

The inspection

determined that the licensee

had completed all but two

corrective actions resulting

from the findings of the

NRC Eg team inspection

of August 15-23,

1985,

as follows:.

Potential

Enforcement/Unresolved

Items

Item Numbers

Status

1.

gualification file deficiencies

2.

Static-0-Ring pressure

switches

3.

Valcor solenoid valves

4.

General

Electric EB-25 terminal

blocks

5.

General

Electric

EB-5 terminal

blocks

6.

Fisher

304 position switches

7.

Rosemount

1151 transmitters

50-220/85-13-01

50-220/85-13-02

50-220/85-13-03

50-220/85-13-04

50-220/85-13-05

50-220/85-13-06

50-220/85-13-07

Cl osed

Closed

Closed

Cl osed

Cl osed

Closed

Closed

~oee

Items

1.

Implementation of Eg procedures

2.

Closed

loop cooling motor

lubrication

3.

Acoustic monitor coaxial

cable

4.

Laurence

solenoid valve

50-220/85-13-08

Open

50-220/85-13-09

Open

50-220/85-13-10

Closed

50-220/85-13-11

Closed

b.

Newl

Identified Items

Two unresolved

items were identified as

a result of a review of additional

E(} files:

1.

gual ification of Limitorque Valve motor wiring

2.

gualification Status of Kerite Cables

d

DETAILS

1.0

Ke

Persons

Contacted

Nia ara

Mohawk Power Cor oration

NMPC

1.2

A. Athelli, Senior

EQ Engineer

W. Connolly,

QA Program

Manager

T.

Egan,

Engineer

  • P. Francisco,

Lead Licensing Engineer

  • G. Gresock,

Manager,

Nuclear Design

  • J. Janas,

Associate

Senior

QA Engineer

  • J. Jirousek,

EQ Manager

K.

Lampman, Assistant Generation

Engineer

~T.

Lempges,

Vice President,

Nuclear Generation

  • S. Loveland,

Lead

EQ Engineer

R. Main, Generation Specialist

  • C. Mangan,

Senior Vice President

"M. Mosier, Associate

Senior Nuclear Engineer

~T. Perkins,

General

Superintendent,

Nuclear

T.

Roman, Station Superintendent,

Unit

1'K.

Sweet, Electrical

Maintenance

Superintendent

~C. Terry, Manager,

Nuclear

Engineering

and Licensing

  • G. Wilson, System Attorney
  • S.

Wilczek,

Manager,

Nuclear Tech.

NMPC Consultants

J. Anderson,

Senior Qualification Engineer,

Wyle Lab.

  • R. Bennett,

Engineering Supervisor,

Wyle Lab.

"T. Brewington,

Engineering

Program Manager,

Wyle Lab.

  • J. Gleason,

Manager,

Nuclear Engineering Service,

Wyle Lab.

  • L. Price,

EQ Engineer,

Gasser

Associates

~J.

Vaden,

Mechanical

Engineer,

Gasser

Associates

1.3

United States

Nuclear

Re ulator

Commission

~J. Kelly, Project Manager

  • W. Johnston,

Deputy Direct,

DRS,

Region I

"Denotes those

present at the exit meeting

on April 18,

1986.

The

and

team members

also contacted

other managers,

supervisors,

engineers

craftsmen

during the inspection.

2.0

Status of Previousl

Identified Items

2.1

Closed

Potential

Enforcement/Unresolved

Item 50-220/85-13-01

pertain-

ing to generic qualification file deficiencies.

The inspector

reviewed

NMPC procedure

NT 100.C,

"Equipment Qualification," Revision 0, dated

January

29,

1986.

Paragraph

6.5. 19 of this procedure

requires

use of

4I

an "Environmental Qualification Checklist" (also called

an

EQ File

Review Checklist) to document

"program implementation."

This checklist

also

shows the claimed level of qualification and

a statement

that

the item is qualified for its "environment."

The 'inspector

checked

approximately six

EQ files and noted that they

contained

the signatures

and the checklists described

above.

The

EQ

master list did contain the entry "yes" in the "Action Completed"

column

for line items the licensee

considered qualified.

The inspector

found

that proper qualification level

was checked

on the checklist.

The inspector

checked four

EQ files and noted that functional perform-

ance

requirements

were properly defined.

The inspector also reviewed

Wyle Report

17655-PERF-1,

which was

used to specify and demonstrate

compliance with the functional performance

requirements

for the appli-

cation of the qualified equipment.

The inspector considers

the licensee's

corrective actions

on this

item adequate

for its closure.

This item is considered

closed.

2.2

Closed

Potential

Enforcement/Unresolved

Item 50-220/85-13-02

pertain-,,

ing to the environmental qualification of Static-0-Ring pressure

switch,

(pc.

No. PS-70-279).

This item included three deficiencies:

1) the

licensee

did not demonstrate

that the equipment

performance

observed

during .the type testing

was adequate

for the application,

2) the inspec-

tion revealed

dependence

on

a cable

seal

internal to the conduit,

however,

the seal

was not qualified,

and 3) the specified qualified

life is 40 years,

however,

no

EQ maintenance

was specified.

Wyle Laboratory report "Nuclear Environmental

Assessment

Report

on

Performance

of Safety-Related

Equipment at Nine Mile Point Unit

1

Nuclear Power Plant"

specifies

acceptable

performance

levels within

which safety-related

equipment

must operate.

The report includes four

categories

of equipment

performance.

The Static-0-Ring pressure

switch

was included in Category

2 Performance

Determined

by Operating

History.

For this equipment

which is only subject to higher-than-normal

radiation,

the effects of radiation

have

been

addressed

and the equip-

ment has

been

shown to not be adversely affected.

The qualification of the switch was originally classified

as

HELB plus

LOCA.

Based

on the location of the switch, its qualification has

been reclassified

to

LOCA only.

Because

the switch is located

outside the drywell, it needs

only to be qualified for radiation

environment.

Under these conditions, qualification of the seal is

not required.

The inspector

reviewed the revised

SCEW sheet,

the

environmental

qualification checklist

and the qualification file

review check to confirm that the switch was reclassified

to

LOCA

alone.

The inspector also reviewed the pressure

switch to confirm

that the reclassification

is justified.

The inspector

reviewed the licensee's

basis for not specifying

Eg

related

maintenance

to confirm that the specified corrective maintenance

was adequate

to preserve

the qualification of this equipment.

This item is considered

closed.

2.3

Closed

Potential

Enforcement/Unresolved

Item 50-220/85-13-03 pertain-

ing to the environmental qualification of Valcor solenoid valve, (pc.

No. SOV-39-14.7).

This item included two deficiencies:

1)

no conduit

seal

was

used in the plant installation,

however,

a conduit seal

was

used in the type test

and 2) the licensee failed to identify required

Eg maintenance

for a 40 year qualified life.

The qualification of the Valcor solenoid valve was originally classi-

fied as

HELB plus

LOCA.

Based

on the location of the solenoid valve,

its qualification has

been reclassified

to

LOCA only.

Since this

valve is located outside the drywell, it needs

only be qualified for

radiation environment.

Under these conditions,

the installation

need

not include

a conduit seal.

The inspector

reviewed the revised

SCEW

sheet,

the environmental qualification checklist

and the qualifica-

tion file review check to confirm that the solenoid valve was re-

classified to

LOCA alone.

The inspector

also reviewed the 'licensee's

technical

basis for excluding the

HELB environment.

Since these

valves are in the emergency

condenser

system,

they would not be

called

upon to mitigate

a

HELB.

With regard to the issue of E(j required maintenance,

the licensee

noted

that they planned

near

term replacement

of these

solenoid valves.

The

inspector confirmed the licensee

plans to replace

the specified Valcor

solenoid valves with ASCO solenoid valves during the current outage.

However, the inspector

noted that other Valcor solenoid valves

on the

master list will continue to be used in the facility.

The inspector

reviewed the required

Eg maintenance

sheets

to confirm that the speci-

fied maintenance

for these

valves

was adequate

to preserve

the qualifi-

cation of the equipment.

The inspector

reviewed the licensee's

disposition of Information Notice 86-65,

"Improperly Rated Field Wiring to Solenoid Valves," as it per-

tains to Valcor Solenoid valves.

This notice relates

to

a potential

deficiency involving field installed electric cables with low tempera-

ture rated insulation being terminated

inside solenoid valves housing

which are subject to high temperatures

caused

by selfheating.

It was

determined that all affected Valcor solenoid valves

were provided

with pigtails which were qualified with the valves.

The inspector

observed

Yalcor solenoid valves

SOV 39-12C,

SOV 39-14C

and

SOV 39-11C

during the plant walkdown and verified the exi stance

of the pigtails.

This item is considered

closed.

I

P

2.4

Closed

Potential

Enforcement/Unresolved

Item 50-220/85-13-04 pertain-

ing to the qualification of GE EB-25 terminal blocks.

The licensee

had identified that all EB-25 terminal blocks were

used for on-off

functioning only.

The operating

time requirement for terminal blocks

inside the drywell had

been

revised

from 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> to

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

(SCEW sheet

711)

~

The tested insulation assistance

during the first hour was very

high and therefore

leakage

current

was not

a problem.

The terminal

blocks located outside the drywell still require

an operating time of

28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.

However,'he

temperature

and pressure

profiles after

an

accident

decay quickly.

The insulation resistance

of the terminal

blocks did not change substantially.

The inspector

reviewed pertinent

EQ documents for the

EB-25 terminal

blocks

and did not identify any more concerns

about the qualification

of the terminal blocks.

This item is considered

closed.

2.5

Closed

Potential

Enforcement/Unresolved

Item 50-220/85-13-05

per tain-

ing to the qualification of GE EB-5 terminal blocks.

The licensee

had determined all EB-5 terminal blocks located inside the drywell

were for on-off functions only.

The operating

time requirements

for

these

terminal blocks

had

been

revised

from 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> to

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

(SCEW

sheet

042).

The tested insulation resistance

during the first hour

remains

high and therefore

leakage current would not create

a problem.

For terminal blocks located outside the drywell, five were

used for

analog signal transmission,

four for Rosemount transmitters

(FT 81. 1-01

and

02 and

LT 68-28

and 29)

and

one for temperature

sensor

TE-36-29.

The rest were for on-off function only.

The licensee

performed

an engineering

analysis for each of the

EB-5

terminal blocks

used for analog signal transmission,

and demonstrated

that. the resultant

loop error was within the allowable limit.

The re-

sults of these

analyses

were documented

in their report

No.

17655-PERF-1.

The inspector

reviewed pertinent

EQ documents

and considered this item

closed.

2.6

Closed

Potential

Enforcement/Unresolved

Item 50-220/85-13-06 pertain-

ing to the environmental qualification of Fisher model

304 position

switch, part

No. 39-ll-1LSC.

The switch has

been qualified to

DOR

guidelines

as noted in licensee

assessment

report

No.

17655-LSW-16,

Revision A, dated

September

14,

1985;

EQ reference

No.

246 and

Deficiency Resolution

Report

No.

17655-LSW-16. 1, Revision

B, dated

October 8,

1985.

The

SCEW sheet indicates

the position switch is located outside

the

containment

and is subjected

to only a radiation environment.

This

item was included by the licensee

in the listing of changes

from HELB

to

LOCA radiation only made to equipment qualification records

as

a

result of the licensee

post-audit (¹85-13) reevaluation.

This change

was reported to the

NRC in a Narch 4,

1985 letter (NMP1L-0032) from

the licensee.

e i~

+p >r

In reviewing the position switch qualification package,

the inspector

noted that

an internal

memo,

dated

December

5,

1985,

has

been

issued

by the

EQ engineer to the

EQ coordinator stating that the Fisher model

304 position switch is being replaced with a qualified

NAMCO Model

EA-180 switch.

Switches

scheduled for replacement

during the

1986

outage

are listed in

SCEW sheet

Nos.

582,

583,

584,

585,

401,

402,

403

and 404.

This item is closed.

2.7

Closed

Potential

Enforcement/Unresolved

Item 50-220/85-13-07 pertain-

ing to the qualification status of Rosemount

1151 transmitters'he

licensee

completed

a retest of Rosemount

1151DP transmitters

in 1985

and

had developed

a

new qualification file for this equipment.

The

inspector

noted that the

new file now contained

QC inspection report

No. 79-589A dated April 6,

1979 for the installation of the transmitters.

This report established

the beginning of qualified life and justified

the

DOR guideline

as the basis for qualification.

The

new test report (prepared

by Wyle Lab.) indicated that partial type

testing

and

new analysis

had been

done using

a Rosemount

1151DP

4E

transmitter with one

BUNA-N and one

EPR 0-ring installed.

Qualified

lives for both 0-rings

as limiting components

were calculated

using

actual

service temperature

historical data weighted for time at that

temperature

and using

a summation of degradation

intervals technique.

All BUNA-N 0-rings

had

been

replaced with EPR 0-rings which have

much

longer qualified life.

0-ring replacement

intervals were verified to

have

been

less

than their qualified life.

The transmitters

as

a whole

were evaluated

to have

a qualified life greater

than

40 year s.

This item is closed.

2.8

0 en

0 en item 50-220/85-13-08

pertaining to the implementation of

EQ procedures

and control of the

EQ program.

This item covers

several

areas.

Each area is discussed

separately

as follows:

2.8. 1

E

rocedures

and

rocedure

im lementation

The licensee

issued

top tier document

NT-100.C,

"Equipment Quali-

fication," Revision 0, in January,

1986.

The licensee

considered

thi s document contains sufficient detail to be used for various

categories.

Procedure

NT-100.C establishes

methods

which can

be used

by

licensee

engineering

and licensing,

in conjunction with site

technical

support,

to satisfy the requirements

of 10 CFR 50.49.

This document is used to determine

environmental qualification

criteria; identification of design

requirements

and control;

installation requirements,

EQ maintenance

requirements,

and

EQ

file requirements.

For example,

section

6. 10. 1 states

that

"zonal

maps shall

be maintained

as control documents,

and

include

peak values of temperature,

pressure

and relative

humidity that would be experienced

in each

area of the plant

analyzed for High Energy Line Break (HELB)."

JI

The licensee

has developed

individual zonal

maps

based

on

a study

by NUS (NUS-1961-SAAl).

The zonal

maps contain the required infor-

mation

as stated

in the procedure.

The procedure

(NT-100.C) references

24 documents

which may be used

in conjunction with the procedure.

Of the 24 documents

referenced,

all have

been

issued

except

seven.

The

seven

have

been written

and approved,

ready to be issued.

Their i ssuance

is pending

formal

training of personnel

in use of the procedures.

This training is

scheduled for May 1986.

The inspectors

considered this area

completed

except for the

EQ

maintenance

requirements

which are discussed

below.

E

Re uired Maintenance

and Site Maintenance

Procedures

U dates

The

EQ maintenance

requirements

are defined in paragraph

6.7 of

NT-100.C.

The

EQ required maintenance

(EQRM) for each type of

equipment is listed in the

EQRM form and transmitted to the site

for implementation.

The site personnel

are responsible

for

scheduling,

performing, inspecting,

and tracking the required

maintenance activities.

A computer

program

has

been developed

by the licensee

to track the status of each maintenance activity.

The site personnel

are also responsible

to update their site

maintenance

procedures

to include the

EQ requirements.

Two groups

are involved in these activities.

The Electrical

Equipment group

and the

18C group.

The Electrical Maintenance

supervisor

indicated that

28 electrical

maintenance

procedures

need to be updated.

Five of them are to

be used for the

EQ maintenance

during the current outage.

These

five procedures

(Nl-EPM-Cl and C2,

Nl-EPM-R1, Nl-EPM-C14 and

Nl-EPM-122-R135)

have

been drafted

and will be issued

before plant

restart

from the current outage.

The rest of the

28 procedures

will be updated

and issued

before the end'of this year.

Twenty-three

IKC mai'ntenance

procedures

need to be updated to in-

clude the

EQ requirements.

Of these

23 procedures',

all but one

have

been written and are in the review process.

One of these

has

been

approved

and is ready to be issued.

Four have

been

reviewed

and are in process for corrections prior to release.

These four

are

scheduled for issue

on April 19,

1986.

The remainder (in

various

stages

of approval) will be issued

before the

end of the

current outage.

In the interim, work is being done per Work Requests

and

EQRMs

based

on existing procedures

which form the basis for the

18C

EQ

maintenance

procedures.

The

EQ maintenance

activity involving replacement

of Rosemount

Transmitter 0-rings was confirmed by reviewing Work Request

Nos.

10100,

11009,

11010

and

11011,

dated

March 24,

1986.

2..

EttTEii

P

2.8.3.1

Site Personnel

Trainin

The inspector

reviewed

and discussed

the licensee's

EQ

training program

and implementation of training proce-

dures relating to equipment qualification.

Topics

covered in the training program will enable

licensee

personnel

to utilize a

SCEW sheet,

Environmental

Maps

from the Equipment Qualification Procedure

NT-100.C

and the

EQ Master Equipment List.

The training program is in effect for Electrical

and

Instrumentation

and Control personnel.

Training records

indicate the program

has

been in effect since

September,

1985.

The records

also indicate that personnel

are

tested

on the material

presented

and must demonstrate

an understanding

of the equipment qualification program

as evidenced

by an achievement

of 80 percent or better

in the examination.

2.8.3.2

Cor orate

Personnel

Trainin

Corporate training has

been delayed.

The Corporate

EQ

training program originally scheduled for February,

1986

has

been delayed to May, 1986.

Corporate

EQ personnel

have

been

given copies of the

EQ material

(NT-100.C, i.e.)

to read

and acknowledge receipt of this material.

The

EQ function has

been

supported

to date

by experienced

contract personnel.

Licensee

personnel will gradually

move in to perform the

EQ function as training is com-

pleted.

2.8.4

This item remains

open pending

NRC peview and evaluation of the

licensee's

completion of their

EQ maintenance

program

and Corporate

personnel

training.

2.9

0 en

0 en item 50-220/85-13-09

concerning

the oil spillage

under each

of the reactor building closed

loop cooling motors M70-01,

02 and 03.

The licensee

stated that this problem was due to lubricant overfill

during the routine maintenance.

The licensee

proposed

two steps to

prevent recurrence

of this problem:

1) to instruct the maintenance

personnel

not to overfill lube oil during the lubrication maintenance,

and 2) to adjust the motor lube oil filler level

such that any over-

filled oil will be drained to the drain pan.

The inspector verified

through training record that the first step

was completed in September,

1985.

However, the

second

step

had not yet been taken.

The licensee

stated that

one of the three motors

was being overhauled

and the other

two motors

had to run continuously.

Once the overhaul

is completed,

they would adjust the motor oil filler level.

This item remains

open.

10

2. 10

Closed

0 en item 50-220/85-13-10

pertaining to verification of procure-

ment documentation

to establish similarity for acoustic monitor coaxial

cable

and the Rockbestos

coaxial cable for which the file established

qualification.

The inspector

reviewed licensee

procurement

document

No. 52657, product

code

Nos.

?46-3422

(38/C ¹16XLPE/NED) and

146-0021

(2/C ¹16XLPE/NED)

verifying similarity of cable type

and size.

The document review

included certified test reports for the

above product

code

numbers,

cable

megger termination

and interconnecting wiring diagram

No.

3-N21-E21.5.

Thi s i tern i s cl osed.

2. 11

Closed

0 en item 50-220/85-13-11

pertaining to

a deformed

gasket

in

a conduit coupling for a related

switch and the seismic acceptability

of the valve (No. 50V-201.2-23) installation with respect

to

a steel

clamp.

The deformed gasket

has

been

replaced

and operator training provided

for replacement

and positioning of gasket

seals.

For the valve installation,

the licensee

has provided

an engineering

evaluation with supporting calculations

(No. S22.4-201.2-H24)

for the

installed configuration-( support

No. 201.2-H-24)

minus the steel

clamp.

The support

was analyzed

and designed for East/West

and Vertical loads.

The analysis

does not reflect

a north/south restraint of the valves

that would occur with the

use of a clamp.

The licensee

could not explain why the steel

clamp was installed.

The

clamp was

removed

and

a second

evaluation

and calculation

was performed

by the licensee

to determine if there

had been

any damage

as the result

of using the steel

clamp which would have prevented

thermal

expansion

in the north/south direction of the valve support.

The analysis

shows

that while the clamp was in place, it did not cause

overstress

in either

the piping or pipe support.

This item is closed.

3.0

Licensee

Post-Ins ection Reevaluation

of

E ui ment

uglification

Following the

NRC inspection of the licensee's

Equipment gualification

Program conducted

August 19-23,

1985,

the licensee

took steps

to correct the

identified deficiencies.

The licensee

corrective

actions

are described

in

three letters to the

NRC dated

September

30,

1985,

November

15,

1985 and

December

2,

1985.

Corrective actions related to specific file deficiencies

are evaluated

in section

2 of this report.

N '"

(4

k

With regard to programmatic deficiencies identified during the inspection,

the licensee

described their general

corrective actions during

an enforce-

ment conference

at the

NRC Region I office on February

5,

1986.

These

actions

included the following programmatic activities:

Reassessment

of EQ test Reports

Revision of

EQ test Reports

Addition of Page/Paragraph

References

Qualification File Review Checklist

Traceabi lity Matrix (Summary Table)

Functional

Performance

Reassessment

During the current inspection

each of these

programmatic activities were

reviewed both programmatically

and

as they related to specific equipment

qualification files reviewed during the inspection.

No programmatic defi-

ciencies

were identified.

The licensee

discussed

the results of their post-inspection

reevaluation

during the February

5,

1986 conference call with the

NRC and in their letter

dated

March 4,

1986 to the

NRC.

The licensee's

re-inspection

of accessible

qualified equipment

was initiated in April 1985.

This re-inspection

did not

identify any substantial

deficiencies.

The licensee

conducted

a re-evalua-

tion of all the equipmert qualification files in light of the deficiencies

identified during the August 19-23,

1985 inspection

and the programmatic

activities listed above.

As

a result of this re-evaluation

three-hundred

five (305) changes

were

made to the files as of February

17,

1986.

Of

this number,

17 affected the qualification status of qualified equipment.

The licensee

stated that

none of these

changes

required testing or additional

analyses

to establish qualification.

Furthermore,

no unqualified equipment

or required

hardware

changes

were identified.

the inspector

reviewed the

details associated

with a sample of the

17 file changes

affecting qualified

status.

Specifically, the inspector

reviews

changes

associated

with the

D.G. O'rien electrical penetrations.

The licensee

increased

the specified

operating

time from 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> to 100 days.

the inspector

confirmed that these

changes

in the specified operating

time were enveloped

by the qualification

of the equipment.

A summary review of several

other file changes

affecting

qualified status

by the inspector

confirmed the licensees

conclusion that

equipment specifications

were enveloped

by the equipment qualification.

No significant deficiencies

were identified by the inspector

in the licen-

see's

post-inspection

reevaluation

of Equipment Qualification.

4.0

Review of Additional

E

Files

4. 1

The inspectors

reviewed the

EQ files and

SCEW sheets

for three selected

equipment-types

to verify the qualification status

of the equipment

within the

scope of 10 CFR 50.49.

In addition to comparing plant

service conditions with qualification test conditions

and verifying

the bases for these conditions,

the inspectors

selectively reviewed

areas

such

as required post-accident

operating

time compared to the

duration of time the equipment

has

been

demonstrated

to be qualified;

12

similarity of tested

equipment to that installed in the plant (e

~ g.,

materials of components

of the equipment,

tested configuration

compared

to installed configuration,

and documentation

of both); evaluation of

adequacy

of test conditions;

aging calculations

for qualified life

and replacement

interval determination;

evaluation of test anomalies;

and applicability of EQ problems reported

in IE INs/Bulletins and

their resolution.

4.2

The following equipment-types

were selected

for review:

a)

Rosemount

Model

1153D transmitters.

(SCEW sheets

062,

063,

064,

343 and 344).

b)

Limitorque Model

SMB-3 valve actuations

(SCEW sheets

078,

079,

080

and 185).

c)

Fenwal

Model

17002-40 temperature

switches

(SCEW sheets

20 through

35).

4.3

~Findin

Within the

scope of this review,

no unacceptable

conditions were iden-

tified.

.0

n ii

i

.

i

E

The inspector

reviewed the licensee's

method of verifying that generic equip-

ment installed in the plant is included in the Equipment (}ualification master

list and backed

by Equipment gualification files supporting

the qualification

of the equipment.

Examples of generic

equipment

are cables,

terminal blocks,

switch gear

and splices.

The methods

used

by the licensee

to verify installed generic

equipment vary.

For several

of the generic

items

on the master list such

as switch gear

and

power supplies,

the licensee

conducted

a walkdown of the items.

For the

cable splices,

the licensee

recently replaced

most of the cable splices with

qualified splices.

The verification methods

used for other items are not as

definitive as the above methods

and the verification methods

are not clearly

documented.

An example of an item in the latter category is cable.

Verifi-

cation of installed cable is accomplished

through

a combination of licensee

and vendor records relating to site cable procurement

and applications.

In

some,

but not all cases,

cable

can

be identified by walkdowns through cable

jacket markings,

SIS wire marking or samples

of unmarked cable

are returned

to the vendor for positive identification.

Additional information relating

to installed cable is available in the plant archives.

However, this infor-

mation is not computerized

or readily available for this purpose.

As

a

result of discussions

with the licensee,

they plan to document the various

methods

they used to verify installed generic

equipment at Nine Mile l.

No significant deficiencies

were identified by the inspector in this review.

0

Ef

'4l

'I

13

6.0

Plant

Ph sical

Ins ection

6.1

The inspectors

selected

a sample of four Limitorque valve actuators

(Model

Nos.

SMB-O,

SMB-1 and SMB-2), four Rosemount

11530 transmitters,

and four cables for physical

inspection.

All these

items were located

outside the drywell and were accessible

at the time of the inspection.

One Limitorque valve actuator

(Model

No.

SMB-1) is

a

new actuator

not

yet installed.

The inspectors

examined

the characteristics

such

as

mounting configuration, orientation,

interfaces,

model

number,

ambient

environment,

and physical conditions.

For the Limitorque valve actua-

tors,

the inspector also

examined

the identity of the internal wiring.

6.2

~Findin

s

a)

For Limitorque valve actuators,

the

NRC inspectors

did not identify

any unacceptable

conditions other than those already identified

by the licensee.

The licensee

had established

a program in 1984

to identify and replace,

as necessary,

all jumper cables

from the

limit switches to the torque switches if the cables

were not

either

Raychem "Flamtrol" or'ockbestos

"Firewall III."

They

developed

Procedure

Nl-EMP-45.96,

"Equipment gualification of

Limitorque Yalve Actuators

and Associated

Motor Type

SMB and

SB"

in 1984 to implement this program.

According to the licensee,

there

are

39 Limitorque valve actuators

requiring environmental qualification.

They conducted

a reinspec-

tion during the week of April 7,

1986, of 35 of these

actuators

and found that

20 of the

35 contained

jumper cables

(from the limit

switches to the torque switches)

whose identify was

unknown

and

qualification status

could not be established.

Subsequently,

work requests

had

been

issued

to replace

the jumper cables of

these

20 actuators

with qualified cables.

As of April 14,

1986,

four had

been

completed.

The rest will be completed during the

current outage.

The other four actuators will be reinspected

for their jumper

cables.

The licensee

plans to replace

the cables

where necessary

with qualified cables prior to startup

from the current outage.

The licensee

stated that the cases

where identification of the wire

was not immediately possible is not necessarily

a condition of

non-qualification but rather

a case

where the qualification could

not be established

without additional

research

or additional

test/analysis.

Since the qualification status of the affected valve actuators

cannot

be determined for the period from November 30,

1985 to

the time when the jumper cables

are or were replaced, this is

considered

an unresolved

item pending further.NRC evaluation of

the issue

(50-220/86-05-01).

~'

i

b)

The inspector identified that two Kerite cables

(one Model

HTK

power cable wired to Limitorque valve actuator.

IV-31-07, one

Model

FR II FR control cable wired to Limitorque valve actuator

FCV-80-118) were not included

on the master list, nor were any

SCEW sheets

prepared for this type of cable.

The licensee indi-

cated that the cables

were previously covered in a Kerite splice

qualification file.

However,

the qualification file had

been

deleted

from the master list when all the splices

were replaced

by other qualified splices.

This item is unresolved

pending

NRC review of the licensee's

corrective action

on the qualification of these

types of Kerite

cables

(50-220/86-05-02).

7.0

Unresolved

Items

Unresolved

items are matters

which require

more information in order to

ascertain

whether they are acceptable

items, or violations.

Unresolved

items identified during this inspection

are discussed

in Details, in para-

graph 6.2.

8. 0

Exit Me~et i e

The inspector

met with licensee

and licensee

representatives

(denoted

in

paragraph

1.0) at the conclusion of the inspection

on April 18,

1986 at

the corporate office.

The inspector

summarized

the

scope of the inspection,

the inspection findings

and confirmed with the licensee

that the documents

reviewed

by the team did

not contain

any proprietary information.

The licensee

agreed that the inspec-

tion report

may be placed in the Public Document

Room with prior licensee

review for proprietary information ( 10 CFR 2.790).

At no time during this inspection

was written material

provided to the

licensee.

t