ML17053C847

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IE Insp Rept 50-410/81-07 on 810727-31.Noncompliance Noted: Failure to Follow Procedures for Performing Activities Affecting safety-related Function in Electrical Procedures Implementation
ML17053C847
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 08/27/1981
From: Ebneter S, Paolino R, Varela A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17053C845 List:
References
50-410-81-07, 50-410-81-7, NUDOCS 8109240552
Download: ML17053C847 (16)


See also: IR 05000410/1981007

Text

U.S.

NUCLEAR REGULATORY COMMISSION

OFFICE

OF INSPECTION AND ENFORCEMENT

Region I

Report

No. 50-.410/81-07

Docket No. 50-410

License

No.

CPPR-112

Priority

Category

A2

Licensee:

Nia ara

Mohawk Power Cor oration

NMPC

300 Erie Boulevard West

S racuse

New York

13202

Facility Name:

Nine Mile Point Station

Unit 2

NMP-2

Approved by:

A. Varela,

Reactor Inspector

.D.

Eb

er, Chief, Plant Systems

Section,

Inspection At:

Scriba,

New York

Inspection

Conducted:

July 27-31,

1981

Inspectors:

o ',

Re

tor Ins ector

da

e signed

d te signed

Ins ection

Summar

Inspection

on July 27-31,

1981 (Inspection

Report

No. 50-410/81-07)

Areas Ins ected:

Routine unannounced

inspection

by two regional

based in-

spectors

of established

electrical

QA procedures/implementation,

installation

of safety related

cable trays, potential significant deficiency in the primary

containment

concrete wall, engineering

drawing review for buildings affected

by radwaste

geologic feature

reported

by licensee

under

10 CFR 50.55(e)

and

facility tour.

The inspection

involved 62 inspection-hours

onsite

by two

regional

based

inspectors.

Results:

Of the six areas

inspected,

no items of noncompliance

were identified

in five(5) areas;

one item of noncompliance

in electrical

procedures

im-

plementation

area involving failure to follow procedures

for performing

activities affecting safety related function.

Region I Form

12

(Rev. April 77)

~ 8109240552

810901

PDR

ADOCK 05000410

8

PDR

('

DETAILS

Persons

Contacted

Nia ara

Mohawk Power Cor oration

NMPC

W.

  • S

S.

RJ

  • J

p.

  • E
  • H
  • F

'R.

G.

  • J

Baker

Caube,

QAE

Czuba,

QAE

Dillon, Site

Lead

QAE

Doyle,

QA Technician

Francisco,

Licensing Engineering (via telephone)

Manning,

QA Technician

Mastin,

Lead Electrical (Construction)

Osypiewski,

QAE

Patch,

QA Technician

Sanford,

Construction

Manager

Saurini, 'Assistant Senior

Lead Engineer

Stone

and Webster

En ineerin

Cor oration

S8WEC

S. Cimalleca,

Foreman

C.,Corso,

Electrical Engineer

S.

Crowe, Assistant Superintendent

L.

  • E
  • C. Gay, Superintendent

FQC

E. Goodness,

Material Controller

Dalhans,

Lead

QCE (Electrical)

Eichen, Assistant Superintendent

(Constuction

Engineering)

  • C

AB

  • E

G.

  • G

"H.

A.

G.

C.

Hilton, Superintendent

(Construction)

Holsinger,

QAE (Civil)

Magi 1 1ey, Assi stant Superintendent

FQC

Page,

Assistant Superintendent

(Geotech)

Pierce,

Site

QA Supervisor

Pierre,

Chief Office Engineer

Shah,

Responsible

Lead Engineer (via telephone

Smith, Senior

QC Inspector

Sperling,

Senior Material Controller

R. Wagner,

Resident

Manager

P. Wilde,

QCE

G.

R.

C.

Wilkins,

QCE

Zerrahn,

Cable Storage

Yard Attendent

Sperling,

Senior Material Controller

ITT General

D.

D.

0.

A.

Carey, Project Engineer

Giguere,

QC Manager

Grodi, In-process

Inspection Supervisor

Munger,

PM Records

Coordinator

"denotes

personnel

present at exit meeting.

2.

~FiT

2

The inspector

observed

work activities in progress,

completed work

and plant status

in several

areas

of the plant during

a general

inspection of Unit 2.

The inspector

examined work items for obvious

defects or noncompliance with NRC requirements

or licensee

commitments.

Specifically, the inspector

observed

concrete

placement

and testing

activities for. the electrical

and service water tunnels

and the

removal of rock from the intake

and discharge

tunnels

and the

radwaste building foundation.

The inspector also observed testing

and pilot hole drilling for the installation of expansion

type

concrete

anchors for the unit heater wall supports

in the south

auxiliary building.

The inspector conferred with crafts personnel,

supervision

and quality control personnel

encountered

enroute.

Particular

note was taken regarding

the presence

of quality control

personnel

and indications of quality control activities through

visual evidence

such

as inspection

records,

material identifications,

nonconformance

and acceptance

tags.

No items of noncompliance

were identified.

3.

Electrical

Com onents

and

S stems

--Review of

A Records/Procedures

The inspector

reviewed quality assurance

plans, instructions

and

procedures

for electrical

components

and

systems

to determine

whether appropriate

and adequate

procedures

are included or referenced

in the

QA manual

to assure

the specific activities are controlled

and performed according to

NRC requirements.

Documents

examined for this determination

include:

Specification

E-061A, revision 3, dated

June 3,

1981 entitled

"Electrical Installation";

Specification

E-021A on Electrical Penetration;

NMPZ-SM01, revision 5, dated

February 3,

1981 entitled "Storage

and Maintenance

During Storage of Permanent

Plant Equipment";

Specification

EOC-5, revision 2, dated

September

19,

1978

Criteria for Identification and Separation

of Cable

and

Raceway

Sections;

2

Specification

E-026A on Cable Trays;

Quality Assurance

Inspection

Plan

(QSIP)

No.

N20E061 AF0002,

revision 0,

change

1 dated January

15,

1981

on Installation of

Electrical

Raceways;

('

QAIP No.

N20E061A F0001 dated

June

29,

1981

on Installation of

Electr ical

Embedments;

QAIP No.

N20E061A F003 dated

June

29,

1981

on Installation of

Electrical

Raceway

(Condui ts)

and Field Inspection.

QAIP No.

N20E061A F004 dated

June

29,

1981

on Installation of

Electrical

Raceways

(Manholes

Duct lines);

QAIP No.

N20E061A F007 dated

June

29,

1981

on Installation of

Electrical

Embedments (sil 1s for electrical

equipment);

QAIP No.

N20E061A F0030 dated

June

29,

1981

on Crimp Tool

Verification Program;

QAIP No.

N20E061A F0040 dated June

29,

1981

on Field Inspection

AC/DC Motors-Transformers;

QAIP No.

N20E061A-098 dated

February

28,

1980

on Electrical

Installation

(Raceway Inspection);

Engineer

QA Manual;

Engineers

Q-Standards

Manual

and Implementing Procedures,

Directives

and Instructions.

No items of noncompliance

were identified.

4.

Electrical

Com onents

and

S stems Work Observations

The inspector

observed

work performance, partially completed work

and completed work, as appropriate,

relative to electrical

cable

and equipment

storage

and the installation of cable trays to determine

whether the requirements

of applicable specifications,

work procedures

and inspection

procedures

are accomplished

in accordance

with NRC

requirements

and licensee commitments'reas

examined for this

determination

include:

Cable Storage

Yard

The inspector

examined Material Receiving Report Nos.81-495,

81-350

and 81-2411.

In addition, the inspector toured the cable yard noting that

a

large

number of Rockbestos

cable reels were roped off and

tagged

as Rejects.

The licensee

indicated the cable

was nonconforming

and that

a

determination

was underway -by the Architect Engineer to ascertain

where the cable is being

used

and its affect on safety related

systems.

An interoffice memorandum

from the Architect Engineer

dated July 30,

1981 indicates

two of the single conductor

lighting cable reels

are nonconforming

and are to remain

on

reject status

and that all other single conductor lighting

cable reels listed in attachment

"A" of memo can

be removed

from the reject status.

All single conductor cables

not on

Attachment "A" and all multiconductor control cables

are to

remain

on reject status

pending approval of proposed

vendor

corrective action

and approval of disposition"No.

N8D-A017.

Level

B Warehouse

The inspector

examined electrical

equipment

storage

in level

B

warehouse.

The inspector

selected

pump motor S/N JMJ-901023,

P.O.¹

P-800A,

MPL ¹E12C002 to verify maintenance

and surveillance

activity as defined in section 2.6.3 of specification

E-061A

which states,

in part, that ".

.

.Motor winding insulation

resistance

shall

be megger tested.

. .for motors rated

50 hp.

and larger, at 90 day intervals.

. ..

Acceptable

resistance

parameters

.

. .shall

be as specified in the testing section."

Section

5. 1.4 of the Testing Section,

on motors,

states

in

part, that:

"All motors shall

have motor windings.

~

~ resistance

megger tested

as specified in section 2.6.3.

All test

~re orts

shall

be submitted to the emnineers

for evaluation~The

inspector

noted that the megger testing

was done

by one subcontractor

and the test data obtained

was stored

by another

subcontractor.

Neither contractor felt obligated to submit the test data to

engineering for evaluation.

Discussions

with the licensee

and engineers

indicate the test

data is not submitted to the engineers

for evaluation

as

required in Specification

E-061A.

The licensee

was informed

that this was

an item of noncompliance

and

an infraction of 10 CFR 50, Appendix B, Criterion

V which states,

in part, that"

"Activities affecting quality shall

be prescribed

by documented

institutions.

.

.and shall

be accomplished

in accordance

with

those instructions...."

(50-410/81-07-01).

The inspector

examined

the installation

and arrangement

of

cable tray openings

and sleeves

in the control building,

elevation

287'-7~2" to 305'-1~2" per drawing Nos.

EE-37AH-3,

EE-

37B-3,

EE-37B-6 and

EE-37A.

In addition, the inspector

reviewed

the quality assurance

inspection reports

T-158E for installation

Nos.

E-061A/IR/E9006487

and E-061A/IR/E9006568.

No items of noncompliance

were identified.

The inspector

observed

work in progress

involving cable tray

installation in the control building cable

spreading

room,

elevation 237'-0".

The inspector

noted that three installed

horizontal trays at the

AK line,

4 ft east of the

10 3/4 line

had

a 9/16 inch hole in the side rail in the area of the

splice plate fitting.

Section 3..1.2.6 of the Electrical Installation specification

states,

in part, that:

"where conditions require special

lengths of tray.

.

. or extra holes in side rails for support.

.punch or drill as necessary..

. .except

as otherwise

approved

by the Engineers, all holes in side rails shall

be located

close to support points;

no holes shall

be

made in the middle

portion of any

span or fitting.

The above instructions

appear

to be contradictory in that the

first part allows holes to be drilled as necessary.

The last

part permits

no holes in the middle span or fitting.

In

addition, the special

trays are cut from standard

12 ft. tray

sections with prepunched

holes that could end

up in the middle

span

or near the fitting depending

on where the special

tray

section is cut.

The licensee

has issued

an Action Sheet

No. 80.27 requesting

clarification of Section

3. 1.2.6 of Specification

E-061A

regarding

holes in cable tray side rails.

This item is unresolved

pending

NRC review of licensee action.

(50-410/81-07-02)

5.

Potential

Si nificant Deficienc /Primar

Containment Wall Concrete

~Deficienc

The licensee

reported

by telephone

on July 24,

1981

a potential

significant deficiency item due to voids in concrete

and exposed

rebar

which was observed

when concrete

forms were

removed

from the

primary containment wall.

The licensee

stated that

a repair procedure

had been

prepared

and

an evaluation

was underway to determine

reportabi lity of the deficiency under

10 CFR 50.55(e).

The inspector

inspected

the reported deficiency and observed that unsound concrete

had been

removed surrounding

rebar to various depths.

The voids

were found to exist

on the outside

surface of the ring beams

surrounding

both the drywell equipment

and personnel

hatches.

(The primary wall

is 5'-3" thick and is increased

1'-6" on both the interior and

exterior ring beams at both hatches.)

Both hatches

were deficient

in concrete

in the

one through

two o'lock positions,

to depths of

from 1" to 20" maximum and,

exposing

layers of ¹18 ring bars.

The

inspector

observed

the voids occurred early in the concrete

placement

identified as

a 360

x 16'-9" high Pour No.

17.

At both diametrically

opposite

hatches,

the voids were in the

same quadrant,

starting at

the horizontal construction joint.

The left hand quadrant of the

,ring beam at both hatches

had

no deficient concrete.

I>

~

"J

~ ~

g4

~

'&D

No. 2248 dated July 7,

1981 states

that voids exist in the

drywell escape

hatch

and equipment

hatch concrete,

which exposes

reinforcing steel

in a number of areas.

The inspector

observed

noticeable differences

in the texture of the concrete,

indicating

a

lack of consolidation during placement.

The inspector also reviewed

related

nonconformance

and disposition report Nos., 2306

and 2308,

gC inspection reports,

engineering

drawings

and specifications.

The inspector

interviewed responsible

personnel

to determine

the

nature,

extent

and possible

cause

of deficiencies

in concrete

placement

made

June

26,

1981.

These observations,

in addition to

the review of gC documentation

on controls during the concrete

placement

and craft interviews confirm that the concrete

voids at

both hatches

resulted

from lack of consolidation.

N&D No.

2248 disposition details for the removal of unsound

concrete

and their repair with separately

identified placement

steps

and

controls

was observed

to be prescribed

by

S&M engineering with

adequate

design

review and appropriate

approval.

The

N&D also

gives technical justification for repairs

using proprietary

grout.'t

is consistent

with design/specification

requirements

for concrete

density

and is stated

to have

no detrimental effect

on shielding

capabilities.

Observation of completed repairs

and

gC record

review will be performed in a subsequent

inspection.

The licensee's

engineering

report as to the safety related significance of the

above deficiency, identified as

No. 81-00-03, will be evaluated

when the final report is submitted.

The inspector

has

no further questions

at this time.

No items of

noncompliance

were identified.

Review of Corrective Actions in Desi

n for Potential

Deficienc

Includin

Movement of Radwaste

Bui ldin

Geolo ic Feature

The licensee's

final report of the

10 CFR 50.55(e) deficiency

regarding possible future movement of the

Radwaste

Building geologic

feature,

dated

June

25,

1981, identifies that corrective action of

all affected safety related structures will consist of conservative

allowance for anticipated horizontal

movement (<1/4 inch) and

potential

settlement

(<1/10 inch).

The inspector

observed

in approved

drawings dated July 1,

1981 the following features

which represent

changes

in design different from those

presented

in the

PSAR

~

a

~

The reinforced concrete

foundation for the liquid radwaste

tanks is not bonded to the rock.

It is separated

by a layer

of Polyethylene

~

b.

The bottom of the foundation

and the exterior structural

reinforced concrete walls, represented

in

PSAR Supplement

10

Figure 2.7-7A and B, with protected waterproof

membrane of

polyvinyl chloride sheet or butyl rubber is replaced

by interior

welded liner plates

anchored to the reinforced concrete.

~

Q-

a

I'

I

Pending

review and approval

by

NRC Office of Nuclear Reactor

Regulation

of the magnitude of vertical

and horizontal

movement

due to the

geologic feature presented

in licensee's

final report the

NRC

inspector will review in a subsequent

inspection other related

information such

as adjustments

for piping between

the

Radwaste

and

adjacent buildings not affected

by the Radwaste

geologic feature.

The inspector

has

no further questions

at this time.

7.

Unresolved

Items

Unresolved

items are matters

about which more information is required

in order to ascertain

whether they are acceptable

items or items of

noncompliance.

An unresolved

item is discussed

in Details,

Paragraph

4d.

~Ei

The inspectors

met with licensee

and construction

representatives

(denoted

in Details,

Paragraph

1) at the conclusion of the inspection

on July 31,

1981.

The inspectors

summarized

the purpose

and

scope

of the inspection

and identified the inspection findings described

in the report.