ML17055C590

by

letter dated August 23,

1985.

Investigation

and analysis of the problem by the licensee

revealed

that the improper acceptance

of this panel

was attributable to one

FQC inspector.

The

NRC inspector

reviewed the following licensee

actions

taken to

resolve this issue.

1.

Complete

100% re-inspection

of all solder inspections

performed

by'he problem inspector.

This involved recalling

and

re-inspecting

work covered

by 22 previous inspection reports.

2.

Verifying the performance of other

FQ inspectors

by surveillance

inspection of 20 of their completed

inspections

of solder work.

~ '

p I-

j<e

S

t,h

3.

Evaluating the adequacy of the training program

used in training

and qualifying

FQ inspectors

to inspect

soldered

connections

including updating

and retraining courses

for the inspectors.

4.

Reworking all identified unsatisfactory

solder connections.

5.

NMP-2 site

QA Evaluation

and Verification Report of Documen-

tation

and Supporting Inspections

dated July 16,

1986 relative

to the subject 50-55(e) construction deficiency item.

The solder connections

in Panel

2 CEC"PNL602 which led to this con-

struction deficiency item were inspected

by the

NRC inspector in

addition to similar connections

in panels

2 CEC~PNL601

and

2 CEC~PNL871.

No unsatisfactory

solder connections

were observed.

This item is closed.

2. 13 (Closed)

Unresolved

Item 50-410/83-08-02.

This item relates

to

a

discrepancy

between

the

NMP-2 commitment to Regulatory

Guide

1. 100

August

1977

and

IEEE 344-1975

and

FSAR commitments

on Page

3. 10B-2

relative to the seismic qualification of certain

equipment within the

GE scope of supply.

The inspector verified the licensee's

corrective actions

taken to

resolve this discrepancy

by Amendment

22 page

3. 10B-2 of the

FSAR dated

November

1985 which now clarifies in paragraph

3. 10.2. 1B

"Methods of showing

NSSS

Equipment

Compliance with IEEE 344-1975

and

Regulatory Guide

1. 100".

This item is closed

2. 14 (Closed) Construction Deficiency Item 50-410/86-00-04.

Cooper

sup-

plied standby diesel

generator

2

EES*EG 61 did not meet its 10-second

starting requirement

due to the slow retraction of the fuel control

cylinder.

This cylinder is extended

in the fuel-off condition and is

retracted

in the fuel-on condition by

a combination of air pressure

and

an internal

compression

spring.

The actual starting time was

13

seconds

for the first start

and less

than

10 seconds

for successive

starts.

This deficiency was reported to

NRC in accordance

with 10 CFR 50.55(e).

Analyses of the problem by the licensee

and the manufacturer

revealed

that the fuel cylinder liner material

was being eroded

by the

harder

compressor

spring material

causing galling and binding.

Corrective actions

taken

by the licensee

were to replace

the fuel

control cylinders

on both Division I and II emergency diesels with

harder Armaloy lined cylinders provided by the manufacturer

to re-

solve this problem.

'

tP

F'

R

The inspector confirmed the licensee's

documentation

of the replace-

ment including NMPC-gA Evaluation

and Verification of the replace-

ments.

This item is closed.

2.15 (Closed) Construction Deficiency Item 50-410/86-00-07.

This defici-

ency is related to an excessive

vibration problem with the low pres-

sure fuel oil supply lines

on the Division I and II standby

emergency

diesel

generators

(EDG).

This vibration led to

a pin hole leak

in the Division I 2 EGS"EGl fuel oil line.

This deficiency was re-

ported to the

NRC by the licensee

in accordance

on

May 8,

1986.

Evaluation of the deficiency and its causes

by the licensee

and the

EDG supplier (Cooper) led to replacement

of the

damaged

fuel oil

lines

on both the Division I and II EDG units and to the installation

of plastic coated fuel line support brackets.

This work was

completed

by the licensee

under Engineering

Design

and Coordination

Reports

C46953

and C47192.

The inspector verified the work performed to correct this deficiency

by physical

inspection of Division I

EDG 2 EGS*EGl and by

a review of

the completed

EEDCR reports including the site

gA Evaluation

and

Verification Report.

This item is closed.

2. 16 (Closed) Violation Item 50-410/86-08-02.

This

10 CFR 50, Appendix B,

item relates

to violations of licensee

FSAR and Electrical Specifi-

cation

E061A Class

1E cable separation

procedure

requirements.

The

inspector

had identified Class

1E electrical

cable

2EGPNGX001

on the

west side of the control building at the control

room elevation of

cable penetration

2WX564G01 which did not have sufficient separation

from non-division class

cables

out of penetration

2WC564N02.

The inspector

found that the licensee

had recently performed work to

the penetration

seals

which required slackening of cables

in the

penetration

area which led to the cable separation

violation.

The

inspector confirmed the licensee's

corrective action by a physical

inspection of cable separation

in the areas

of the violation.

The

inspector

found that the licensee

had achieved

the required

separa-

tion of the cable identified in the violation and eight additional

cables

by the installation of Si 1-Temp fire wrap and metal barriers.

This item is closed.

eC

10

2.17 (Closed) Violation 50-410/86-13-08.

Licensee specification

C081 for

instrument installation required that instrument lines shall

be

tagged with identification marking

on both sides of a wall or floor.

Contrary to this the inspector identified three

instances

where in-

strument lines were not properly identified on either side of their

drywell penetration.

The inspector

reviewed licensee

actions

taken to resolve the problem

as follows:

Specification

C081

was revised to permit identification tagging

of instrument lines outside the drywell to be approximately

6

feet from the penetration

in the vicinity of the excess

flow

check valve.

The specification

was further revised

so that

instrument lines passing

through the biological shield wall need

be tagged only'outside

the wall and lines underneath

the sup-

pression

pool water level

need not be tagged.

2.

The licensee

under Engineering

and Design

Change

Request

F13539A

performed work to tag all instrument lines both inside and out-

side the drywell in accordance

with the revision to specifi-

cation

C081A.

The inspector

performed

a random audit of licensee identification

tagging of the instrument lines by inspection of the following lines

inside the drywell containment:

2ISC-750-340-2,

2ISC-750-311-2,

and

2 ISC-750-335-3,.

No discrepanices

were observed.

The inspector also

reviewed the

NMPC Site

QA Evaluation

and Verification of satisfactory

completion of the tagging in accordance

with specification

C081A,

Revision

5 and

E 8

OCR F13539A.

This item is closed.

2. 18 (Closed) Construction Deficiency Items 82-00-17 83-00-03,

83-00-07,

83-00-17.

These construction deficiency items are Environmental

gualification failures, of operational

components

in the post

LOCA

Hydrogen

Recombiner units supplied

by Rockwell International.

These

items

and their reporting are

summarized

as follows:

Item

82-00-17

Descri tion

Bar ton Pressure

Transducer

Models D4R29098

Re ort to

NRC

10 CFR 21 by letter

10/21/82

by

letter 11/19/82

I

1

h

11

83-00-03

83"00-07

83-00-17

Square

D Disconnect

switch P/N 9422-RC-1

Microswitch

P/N 12TSI-2

ITE Gould Ciruit

Breaker

P/N EF-3-3015

10 CFR 21 by letter

11/3/82

by

telephone

1/26/83

by

1 etter 9/1/83

by

letter 3/26/83

The inspector

reviewed the Rockwell qualification report 290(}R000031,

dated October

16,

1985,

and the warranty of the Hydrogen

Recombiner

unit including modifications

and replacement

components

to meet the

Environmental gualification requirements

of IEEE 323-1974.

The inspector verified actions

taken

by the licensee

in accordance

with Rockwell Technical

Services Bulletin 82ESG-8933 for

modifications

needed for environmental qualification.

The modifi-

cations

were

as follows:

Item

82-00-17

83-00-03

83-00-07

83-00-17

Modification Descri tion

Replace

Barton pressure

Transducer with qualified

Gould series

3200 Transducer

Modify disconnect

switch electrical

circuitry to eliminate the disconnect

switch

Modify the microswitch electrical

ci rcuitry to el iminate the

microswi tch

Modify the circuit breaker electrical

circuitry and components

to replace

the

circuit breaker with qualified Gould A4J10

fuses

and 60356J

fuse blocks.

The inspector

reviewed the licensee final verification of the 50.55e

Hydrogen

Recombiner Corrective Actions Implementation

Report

No.

E

86-00051 dated January

29,

1986.

The report verified both equipment

modifications and drawings revision to reflect the changes.

The

inspector verified equipment modifications by inspection of the

Division 2 Hydrogen

Recombiner Unit and power supply cabinet

and also

confirmed the equipment

and

system

drawi'ng revision.

This item is closed'

/

Al ~

12

2.19 (Closed)

Unresolved

Item (50-410/83-08-04).

This item is related to

the seismic qualification of the Gould supplied Class

1E Motor Con-

trol Centers

(MCC) and to certain wiring deficiencies within the

MCC

units.

The wiring deficiencies

were previously addressed

and cor-

rected

by the licensee

and are closed out in

NRC inspection report

85-44.

The inspector

found that the licensee

had addressed

the seismic

qualification question

by requiring that Wyle Laboratories

conduct

additional

seismic tests with MCC units simulating the installations

at NMP-2.

The seismic qualification tests

report disclosed

the

need

for additional

support brackets within the

MCC units and properly

welding the

MCC Unit bases

to the floor sills.

The inspector

reviewed the licensee's

Seismic Certification Report

and inspected

the licensee's

installation of the additional

seismic

supports

and

base welding in accordance

with the seismic qualifica-

tion report.

The inspector also reviewed licensee site

gA Evaluation

and the Verification report for seismic qualification dated

January

20,

1986.

This item is closed.

2.20 (Closed) Construction Deficiency Unresolved

Item 50-410/85-00-29.

This item relates

to an improperly sized excitation

impedance

match-

ing resistor in the

HPCS diesel

generator control circuitry.

This

deficiency was reported to the

NRC in accordance

with 10 CFR 50.55e

by letter January

13',

1986.

The licensee

and the

HPCS supplier

(Stewart

and Stevenson)

'evaluation disclosed that the resistor

sup-

plied with the voltage regulator would not permit sufficient signal

adjustment

to the generator exciter to achieve

the full 2600kw

1950kvar rated output of the generator.

Optimization of the imped-

ance matching resistor

led to replacing the

50

ohm with a

25

ohm

resistor.

The inspector

reviewed licensee

documents

covering the change includ-

ing

DR 07441 (replacement),

gCIR 2-86-1584

and 2-86-2145 (g-C in-

spections),

and

PR 01689 (revision of drawings).

The inspector also

verified the resistor

replacement

including qualification, location

and mounting.

This item is closed.

2.21 (Closed) Construction Deficiency Item 86-00-10 'his construction

deficiency relates

to cracks in Bendix supplied Division I and II

emergency diesel

generators

fuel injector delivery valve holder fit-

tings (P/N 10-328469-3).

This deficiency was reported

by the lic-

ensee

in accordance

by letter

on May 30,

1986.

Examination

and analysis of the problem by the licensee

revealed that

the fittings were not made in accordance

with the design drawing.

An improper radius of the fitting created

excessive

stress

in the

fitting at

a sharp

edge causing

the cr'acking.

( \\.

IC

1(

A

441

13

Bendix supplied proper replacement fittings.

These

were inspected

by

the licensee

and installed'.

The inspector

reviewed the licensee

documentation

of the replacement

and the site

gA Evaluation, Verifi-

cation

and acceptance

of the replacement.

This item is closed.

2.22 (Closed) Construction Deficiency Item 86-00-12.

This contruction

deficiency relates

to improperly fitted air start valve seat inserts

for two valves in the Division I emergency

diesel

generator.

It was

reported to

NRC by the licensee

in accordance

on

June

25,

1986.

These valve seats

are supplied

by Cooper

Energy

Services

as

an integral part of the cylinder head.

The valve seat inserts

on cylinders

3 and

7 were found to be loose

(one due to an undersize

and one

due to an oversize fitting problem).

The licensee

inspected

and tested all the remaining air start valve

seats

inserts

in both division

1 and

2 diesels

and found them to be

acceptable.'he

deficient valve seats

inserts

were replaced with

proper fitting inserts.

The inspector

reviewed the licensee's

documentation

of the inspection

and replacement

and reviewed the Site

QA Evaluation, verification and

acceptance

of the replacement.

This item is closed.

2.23 (Closed)

Unresolved

Item 86-13-10 'his item relates

to Stone

and

Webster

(SWEC) Balance of Plant

ESF Actuation Logic diagrams

12177-

LSK-27-19G and

19H in which

SWEC identifications corresponding

to the

GE identifications were not correlated.

(The inspector

had pre-

viously verified that

SWEC had correlated all other similar documents

with both the

GE and

SWEC identifications).

The inspector confirmed

licensee

actions

taken to correct this deficiency through Engineering

Change

Notices

ECN 602,

606 and 607.

This item is closed.

2.24 (Closed) Construction Deficiency Item 50-410/86-00-03.

This defici-

ency is related to factory installed jumpers across

reactor protect-

ion "Thermal

High Trip output relays

K19 and

K20.

. These jumpers

would inhibit reactor protection

system

response

to

a thermal trip.

This deficiency was reported to the

NRC by the licensee

in accordance

on March 26,

1986.

Evaluation of the safety

consequences

of the loss of thermal trip

were

made

and reported

by

GE letter dated April 24,

1986.

GE"con-

cluded that "this condition would not have adversely affected the

safety of operation of the plant at any time throughout the expected

P

i

E'

0

4

a ~

'

lifetime of the plant were it to have

remained uncorrected.

It is

therefore

recommended

that Niagara

Mohawk Power Corporation act

on

this conern

as not reportable

per

10 CFR 50.55(e)".

The licensee

advised

NRC accordingly

on April 25,

1986.

The inspector

reviewed licensee

actions

taken to correct the problem

including

GE Field Deviation Disposition Report K61-4895,

NMP-2 De-

ficiency Report 09955

and Engineering

and Design Coordination

Report

E & CDR C46438 which removed the jumpers thus enabling

the

RPS ther-

mal trips.

This item is closed.

2.25 (Closed)

Construction Deficiency Item 84-00-46.

This deficiency

relates

to licensee identified incorrect wiring of torque switches

on Clow Corporation

supplied Limitorque valves.

These deficiencies

were reported to the

NRC in accordance

by letter

dated

May 17,

198S.

The inspector

reviewed the following licensee

documentation

of the

deficiencies,

investigations,

and correction of the problems.

Engineering

and Design Coordination

Report

(E&DCR)

F 20,541

Nonconformance

and Disposition Report

No. 11,892

Inspection

Reports of work performed

under

E & DCR F20,541-

Reports

E5A83 102 and

ESA48845

Closed

E & DCRs F20,532

and F12,709 which provided the drawing

changes

for the Limitorque-changes

in

N & DR 11,892

License site

gA Evaluation

and Verification Report dated July 3,

1986 in which the correction disposition

was found complete

and

acceptable.

This item is closed.

2.26 (Closed) Construction Deficiency 86-00-15.

This construction def-

iciency relates

to a problem with the moderate

energy line crack

(leak) detection

temperature

switches

which are

used to respond to an

'ir

temperature

rise resulting

from a leak in the

RHR system.

The

licensee

found that the response

time for these

switches is too long

to detect

and isolate moderate

energy cracks within the time frame

consistent with the equipment qualification analysis.

This defici-

ency was reported to the

NRC in accordance

on

July 8,

1986.

L

15

The inspector

reviewed the following licensee

documentation

of the

evaluation,,modifications,

and

QA verification of the modifications.

1.

SWEC letter 9N2-18,898 dated

May 23,

1986 and Problem Report

dated

May 12,

1986.

These

documents

are the basis of the

"Description of the Problem

and Analysis of Safety Implica-

tions".

2.

SWEC

E&DCR Y04011A which provided the engineering directions to

replace

the existing temperature

switches with faster

response

PYCo units.

3.

SWEC Inspection

Report

16A80902 which shows acceptable

replace-

ment in accordance

with E8DCR Y04011A.

4.

NMP-2 site

QA Evaluation

and Verification documentation

of the

Correction of Construction Deficiency 86-00-15 dated August 13,

1986.

Based

upon the licensee's

corrective actions this item is closed

2.27 (Closed) Construction Deficiency Item 86-00-16.

This deficiency

relates to improperly-installed

GE supplied

PYCo temperature

sen-

sing elements

which are

used to detect

pipe line breaks (leaks)

in

the

RHR,

RCIC,

RWCS and

MSS systems.

These detectors

were installed

enclosed within pipe sleeves

that prevent air from directly impinging

upon them.

At the time of qualification, these

elements

were exposed

to air.

Early detection of pipe line breaks

and their early isola-

tion are essential

to minimize blowdown which could expose

safety-

pressures

outside their environ-

mental qualification envelope.

This deficiency was reported to

NRC in accordance

with 10 CFR 50.

55(e)

on July 10,

1986.

The inspector

reviewed the licensee's

analysis of the deficiency,

corrective actions taken,

and

QA/QC verification and acceptance

as

contained

in the following documents.

1.

SWEC Letter Report of the 50.55(e)

problem to Niagara

Mohawk

dated July 2,

1986.

2.

SWEC

E 5

OCR 203135 analysis

and report of the problem

PYCo type

thermocouples

dated

June

6,

1986.

1

h

16

3.

SWEC

E&DCR Y18911B,

Y18935 and Y1835B which provided the cor-

rective actions.

This included relocation of temperature

ele-

ments, cutting/relocating

supports

and/or cutting

a section of

the pipe insulation to expose

the sensing

elements

to air.

4.

gA/gC inspection

and acceptance

of completed work for E&DCR's

in 3 above.

2.28

Based

upon the licensee's

corrective actions, this item is closed.

(Closed) Construction Deficiency Report 84-00-36.

This deficiency

was related to the operation of curtain-type fire dampers

supplied

by

Pacific Air Products.

During operability tests for gA-Category II

&-IIIdampers, it was Noted that

some

dampers -failed to satisfacto-

rilyy

close

under air flow and pressure

conditions.

The licensee,

therefore,

evaluated

similar dampers

in category-I

systems.

In order

to verify the operability of dampers

in category-I

a test

program was

implemented.

Of the fifty-one (51) dampers

tested

under this program,

forty-four were found satisfactory.

The'remaining

seven

required

modification.

The modification was completed

and the dampers

were

successfully

tested to indicate proper operability.

This item is closed.

2.29 (Closed)

IE Bulletin 80-BU-16 relating to potential misapplication of .

Rosemount transmitters with either

A or

D output codes.

This was

perviously closed

as

a construction deficiency item in inspection

report 50-410/82-12.

This item is closed.

2.30 (Closed)

Finding (86-08-04) relating to damaged

instrument tubing

K117 and impulse line of 2RHS * PDT24B.

The licensee

has performed

the corrective actions through Deficiency Report ¹21062.

The in-

spector verified that the licensee's

training program offers added

emphasis

for employee

awareness

to preclude similar act of negli-

gence.

Moveover, the startup organization

has committed to perform

a

final walkdown prior to fuel load to assure

that instrument tubing is

free from any damage.

This item is closed.

2.31 (Closed)

Finding 86-08-05 relating to noncompliance with slope require-

ments in installation drawings.

The licensee

has re-inspected

65% of

all line segments

for the Reactor

Pressure

Vessel

level

and recircu-

lation system

and performed corrective actions/analysis

to confirm

the absence

of a negative

slope

and effective positive slope.

General Electric has identified the

RPV level

and Recirculation

system to be most sensitive to slope requirements.

FDDRs KG1-2724,

0688,

0701,

0708,

0448 provide adequate justification and corrective

action to alleviate the above concern.

This item is closed,

k

~

%

ff

W

I

l

)

17

2.32 (Closed)

IE Bulletin No. 86-BU-02 relating to the erratic behavior of

Static 0 Ring differential pressure

switches belonging to series

102

and

103.

The licensee

does not utilize the above referred type of

Static

0 Ring pressure

switches.

This item is closed

2.33 (Closed)

IE Circular 80-CI-16 relating to operational

deficiencies

in

Rosemaunt

Model

510

DU trip units and Model

1152 pressure

transmit-

ters.

The licensee

has clarified from GE, the supplier that two

Rosemount

model

510DU trip units were reworked

by the manufacturers.

This was the only remaining concern identified by inspection report

82-12.

This item is closed.

2.34 (Closed) Construction deficiency 86-00-06 relating to loose conduit

fitting that connects

environmental

seals to the various instruments.

The licensee

has modified the installation

away from the travel

direction

and tightened the loose fittings.

The

NRC inspector re-

viewed the corrective actions

performed

under

Noncomformance

Dis-

position Report 816884,

14791

and verified the field installations.

No discrepancies

were observed.

This item is closed.

2.35 (Closed)

Unresolved

Item 50-410/86-13-09.

This item relates to lic-

ensee

actions required to verify scram pilot valve voltages,

to con-

firm the selection of Electrical Protection

Assembly

(EPA) trip set-

tings,

and Technical Specification allowable voltage values in order

to assure

protection of the

scram solenoids within the

105-125

VAC

tolerance

range.

The inspector confirmed licensee

action taken

as

follows:

Scram pilot valve voltages

have

been verified, voltage calcul-

ations

12177

EC-125 Revisions

2 and

3 further verify that the

EPA voltage trip settings

as

shown in the technical specifi-

cation will provide adequate

protection for the

scram pilot

solenoids within the specified voltage tolerance

range of 105 to

125

VAC for all conditions of operation.

Technical Specification

Paragraph

4.8.4.5

has

been revised to

provide allowable voltage values for all conditions of operation.

Licensee actions

taken

appear to provide assurance

that the

scram pilot solenoids

are adequately

protected.

This item is closed.

il

t

18

2.36 (Closed)

Unresolved

Item 85-03-02 relating to unqualified flow trans-

mitters

and lack of documentation

to indicate that manufacturer

corrective action

has

been

performed.

The licensee

has completed

the corrective actions in replacing flow

transmitters with the qualified Rosemount

1153 transmitters.

The

inspector

reviewed documents

N&D Nos.

12134,

E&DCR ¹F02057

and

verified field installations at random.

NMP-2 has the following procedures

to document unqualified equipment

and track the corrective

actions.

PP.76

Control of

SWEC Supplied

Equipment requiring

qualification.

II

QS. 15. 1

Nonconformance

and Disposition Report.

QS. 14.2

Inspection

Report System.

This item is closed.

2.37 (Closed) Construction Deficiency 86-00-17 relating to cracked contact

levers

on

NAMCO EA180 limit switches

mounted

on MSIV.

The licensee

has

done

a complete inspection of all Category I

NAMCO

EA170 and

EA180 series of limit switches.

All the cracked levers

were replaced.

Engineering

& Design Coordination

Report ¹C4112B

documents

the corrective action.

This item is closed.

2.38 (Closed)

Unresolved

Item 86-18-04 pertaining to the

NRC Electrical,

Instrumentation

and Control

Systems

Branch ( EICSB) site audit of

January 7,8 & 9,

1986.

The purpose of the site visit was to verify

that the installation of electrical

instrumentation

and control

equipment

conforms to applicable design criteria regarding phyical

separation

between

redundant

safety related circuits and between

safety-related

and non-safety related circuits.

In addition,

the site

review included verification that the actual installation

was con-

sistent with the staff's understanding

of the design

based

on applic-

able

FSAR schematics

and diagrams.

Specific concerns

were identified by the

NRC EICSB staff in six areas

for followup by Region I personnel

as follows:

1.

Verification that the

one inch and (as applicable)

six inch se-

paration is maintained

between

non divisional cabling

and div-

isional cabling

and between different divisional cabling within

panel

nos.

602,

603,

608B, 852,

880A, 880B,

880C & 880D.

4

,IJ

11

r,

19

The inspector

reviewed Deficiency Report nos.

13124,

19045,

17421,

17420

and Quality Control Inspection

Report

nos - (QCIR)

2-86-6637,

2-86-5225,

2-86-5965,

2-86-5970

and 2-86-6032.

Identifying corrective actions

taken to correct separation

deficiencies.

In addition,

a visual observation of work was

performed

by the inspector to verify corrective actions.

Panel

no.

H13-6088 internal

separation

is exempt from meeting

the literal requirements

of Regulatory Guide 1.75 per General

Electric document

no.

304A2638 Revision 0,

sheet

no.

33 and

licensee

procedure

no.

E-062A, section 8.2.9 line 8.47 -8.50

and

FSAR item 8, Table 421.47-1

Amendment

17.

This item is closed.

Verification of RRCS divisional cabling separation

of

1 inch

between

channels

A and

B of Division

1 and channels

A and

D of

Division 2.

Addressed

in item

1 above

(Panel

602/603).

Verification of nomenclature

associated

with RCIC System trip

units located in Panel

629.

The inspector

reviewed Deficiency Report

No.

12193 identifying

problem marker plates

and replacement .with correct marker plate

per

E&OCR ¹C-46469.

The marker plate

was revised per

FDDR

No.

KG1-4941 Revision

0 and

GE engraving drawing No.

137C6497

Revision 3.

This item is closed.

Verification that conduit and cabling designations'ithin

Remote

Shutdown

Panel

are correct.

The inspector

reviewed the Nonconformance

and Disposition Report

(N 4 0) No.

11545 identifying nonconformities in color coding of

Division and non-division conduit and improper location of

marker sleeves

on right bank of switches

No.

SW2-2RSSN81

for

Remote

Shutdown

Panel

405.

The verification of the corrective

action per

EKOCR ¹F-40545 included application of GE FDI-TYLR

marker tapes.

The switch marker sleeves

were determined to be

acceptable

with engineering

authorized "use-as-is".

This item is closed.

4v

0

20

5.

Verification of Installation of acoustic monitoring system,

scram discharge

instrume'nt

volume and the turbine first stage

pressure

transmitters.

The inspector

reviewed vendor level switch drawings

and

drawing

159C4361

change

1 & 2 verifying installation of scram

discharge

volume instrumentation.

For the turbine first stage

pressure

transmitter

the inspector verified that the installed

pressure

transmitter

was

2MSS * PT16C&0.

The acoustic monitor

has

been installed.

Preoperational

test

No. 86 was performed

with the test data

reviewed

and approved

by

SORC

on April 24,

1986.

This item is closed.

6.

Verification of nomenclature utilized in main

steam line flow

transmitter instrument racks.

The inspector

reviewed

GE drawings

EK-401G,

M; FSK-3-1A,

H and

design specification

No.

22A5257 identifying design

requirements

for locally mounted instruments of the nuclear

steam

supply

system

and loop diagram

No.

2MSS-A & B identifying the

mar k Nos.

for instruments of the main

steam line flow verifying nomencla-

ture

used is consistent with applicable designations.

This item is closed.

2.39 (Open) Construction Oeficiency 86-00-14.

This deficiency relates

to

possible insufficient control voltage present at

some

120

VAC and

125

VAC control device terminals

such that the devices

may not operate

when considering

the minimum design voltages at the distribution

system.

The inspector confirmed that the licensee

had performed

a control

circuit length verification study in response

to

INPO Finding

DC 3-1,

item

C in order to evaluate

the terminal voltages available for

operation.

In performing the control circuit length verification

study the following parameters

were considered:

Minimum voltage required for the operation of the device

on

equipment

connected

to the circuit

Minimum voltage available at the power source

Cable size

and length

As

a result of the study,

the licensee

concluded that

some circuits

exhibited excessive

voltage drop to the powered devices.

In order

to provide adequate

voltage,

the licensee either modified the circuit

to reduce electrical

resistance

or used interposing relays.

1

'%

0

21

The inspector

reviewed licensee

engineering

and design

change

req-

uests

Y07801,

Y07801B,

Y07801E,

and Y07804 which covered the modifi-

cations to assure

adequate

control voltage.

All work on these

E&DCRs

has

been

completed evaluated

and verified by NMP-2 Site

gA except for

work on the

RCIC system

under

E&OCR Y07804.

To prevent recur rence of

this problem

NMP-2 engineering will review all future

MOV,

SOV and

MOD circuits to ensure

that the minimum voltage requirements

of these

devices

are satisfied.

2.40

The licensee

has committed to complete

E&OCR Y07804 relating to the

RCIC system prior to initial criticality. It is noted that this

system

serves

no safety function prior to initial criticality.

This

item remains

open pending completion of E&OCR Y07804.

(Closed) Construction Deficiency 83-00-04 relating to an

inconsistency of separation criteria notes in the General

Electric

wiring/fabrication drawing.

The licensee

has

documented

the above

deficiencies

in Nonconformance

Reports

53,

55

& 56.

The inspector

reviewed the relevant excerpts of the following documents

to verify

the licensee's

corrective actions

and compliance to the criteria.

Reference:

1.

FSAR Ch.8 Section

3 Amendment

26

2.

FSAR Table 421.47-1

Amendment

17

3.

Specification for Electrical Installation

& Field Modification

to PGCC,

E062A Rev.2 dated

December

2,

1985

4.

FODR ¹KG1-3898

5.

Surveillance

Report 85-00887

6.

GE letter NMP2-5024 dated

May 3,

1983

Ref:

2 note

2 covers the

use of Sil-Temp tape

as

a barrier within the

panel

wherever separation

distance

cannot

be mentioned.

The use

of,

flexible/rigid conduit or steel barriers

as

a separation barrier is

covered in note.

3 of the

same reference.

Based

on the above,

the

NRC inspector

randomly inspected corrective actions in H13-P601

&

P602.

No deficiencies

were found.

This item is closed.

2.41 (Closed) Construction deficiency 84-00-14 relating to nonconformances

to separation criteria in Power Generations

Control

Complex

(PGCC).

The nonconformances

extended

to between divisions,

between

channels,

and between divisions and channels.

1

I<5

E

22

In order to facilitate installation,

compliance

and verification

General Electric has clarified their separation

requirements

in a

criteria document titled "Power Generation

Control

Complex Separation

Practices

Handbook" dated

February

21,

1985.

This is

a supplement to

"Specification for Electrical Installation

& Field Modification to

PGCC" E062A, Rev.2, dated

December

2,

1985.

The inspector

reviewed the following documents:

1.

Nonconformance

Report 53, which documents

the subject problem.

2.

Test Report

on Electrical Separation

& Verification 1.613-5001

Rev.B.

by Wyle lab.

3.

Verification and Closure of Nonconformance

Report No.53.

As per

FSAR table 421.47-1

Note

2 and

3 (Amendment 17),

NMP2 uses

Si 1

Temp tape, flexible/rigid conduit or steel

enclosures

as

a barrier

whenever separation

distances

cannot

be maintained.

Based

on the

above

documents

the inspector

randomly selected

cabinets

H13-P609,

631

& 602 and verified the installation against

the revised

separa-

tion/compatibility table in GE

FDDR 03898..

No deficiencies

were

observed.

This item is closed.

2.42 (Closed) Construction deficiency 84-00-32 relating to lack of se-

paration distance/barriers/isolation

devices

in HPCS switchgear

and

control panels.

The inspector verified the selected

corrective

actions

performed

under