Text

Insp Rept 50-400/86-05 on 860121-24.Violation Noted:Failure to Follow as-built Documentation Procedure
	ML18019A607
Person / Time
Site:	Harris
Issue date:	02/12/1986
From:	Blake J, Kleinsorge W; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	;
Shared Package
ML18019A605	List: ML18019A604; ML18019A606; ML18019A607;
References
	50-400-86-05, 50-400-86-5, NUDOCS 8603050159
	Download: ML18019A607 (14)
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UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30323

Inspection

C ndu

Inspector:

p

or

ary 21-24,

198

Approved by:

J.

.

a e, Section

C ref

gi

ering Branch

iv sion of Reactor Safety

Report No.:

50-400/86-05

Licensee:

Carolina

Power and Light Company

P. 0.

Box 1551

Raleigh,

NC

27602

Docket No.:

50-400,

I

Facility Name:

Harris

1

License No.:

CPPR-158

.L@

b

Date Signed

z.

el.'te

Soigne

SUMMARY

Scope:

This routine,

unannounced

inspection entailed

30 inspector-hours

on site

in

the

areas

of licensee

action

on

matters

(92702),

housekeeping

(54834B) material identification and control

(42902B)

and material

control

(42940B) safety-related

structures,

safety-related

piping observation of

work and

work activities

(49053B),

spent fuel storage

racks

(50095),

inspector

followup items

(927018)

and licensee identified items

10 CFR 50.55(e).

Results:

One violation was identified - "Failure to Follow As-Built Documen-

tation Procedure" - paragraph

7.

No deviations

were identified.

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REPORT DETAILS

Persons

Contacted

Licensee

Employees

R. A. Watson,

Vice President

Harris

N. J. Chiangi,

Manager

QA/QC Harris

G. L. Forehand,

Director QA/QC

D. McGaw, Superintendent

QA/QC

H. W. Bowles, Director

ONS

C. L. McKenzie, Acting Director QA/QC Operations

Other

licensee

employees

contacted

included

construction

craftsmen,

engineers,

technicians,

and office personnel.

Other Organization

W. Chao,

EBASCO - Civil

NRC Resident

Inspectors

G.

F. Maxwell

S.

P. Burris

Attended exit interview

Exit Interview

The inspection

scope

and findings were summarized

on January

24,

1986, with

those

persons

indicated

in paragraph

above.

The inspector

described

the

areas

inspected

and

discussed

in detail

the

inspection

findings listed

below.

No dissenting

comments

were received

from the licensee.

(Open) Violation 400/86-05-01:

"Failure to Follow As Built Documentation

Procedure"

- paragraph

7.

(Open)

Inspector

Followup

Item 400/86-05-01:

"Spent

Fuel

Storage

Rack

Assembly Support" - paragraph

8.

The licensee

did not identify as proprietary

any of the materials

provided

to or reviewed

by the inspector during this inspection.

Licensee Action on Previous

Enforcement Matters

(92702)

(Closed) Violation 400/85-38-01:

"Failure to Establish

Adequate

Measures

to

Control the Storage of Permanent

Plant Equipment"

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CP5L letter of response

dated

December

18,

1985,

has

been

reviewed

and

determined

to be acceptable

by Region II.

The inspector

held discussions

with the responsible

engineer

and

examined

the corrective actions

as stated

in the letter of response.

The inspector

concluded that

CPSL had determined

the full extent of the subject

noncompliance,

performed the necessary

survey

and follow-up actions

to correct

the present

conditions

and

developed

the

necessary

correction

actions

to preclude

recurrence

of similar circum-

stances.

The corrective actions identified in the letter of response

have

been

implemented.

4.

Unresolved

Items

Unresolved

items were not identified during this inspection.

5.

Independent

Inspection Effort

Housekeeping

(54834B),

Material Identification

and

Control

(42902B)

and

Material Control

(42940B)

The inspector

conducted

a general

inspection of the power block construction

area to observe activities such

as housekeeping,

material identification and

control; material control,

and storage.

Within the areas

examined,

no violations or deviations

were identified.

6.

Safety-Related

Structures

a.

Observation of Work and Work Activities (48064B)

The inspector

examined

completed

work

and associated

records for the

structures/supports

indicated

below to determine

whether

applicable

requirements,

as well

as

work and inspection

procedures,

are being (or

have

been)

met in the following areas:

testing

and

NDE.

Structures/Su

orts

A-SI-51-R-20

Pipe Whip Rupture Restraint

A-SI-50-R-24

Pipe Whip Rupture Restraint

C-1-310

Feedwater Restraint

Frame

C-1-309

Feedwater

Restraint

Frame

Seal

Water Heat Exchanger

b.

Review of guality Records

(48066B)

The inspector

reviewed pertinent work and quality records for the below

listed structures

and supports

to determine

whether these

records

meet

established

procedures

and

whether

these

records

reflect

work

accomplishment

consistent

with

NRC requirements

and

SAR commitments in

the following areas:

materials;

installation/erection;

and inspection

(gC) records.

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Structures/Su

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C-1-309

Pipe Whip Rupture Restraint

Pipe Whip rupture Restraint

Feedwater

Restraint

Frame

Feedwater

Restraint

Frame

Within the areas

examined,

no violations or deviations

were identified.

Safety-Related

Piping - Observation of Work and Work Activities (49063B)

The

inspector

selected

five as-built/final

design

safety-related

piping

drawings indicated

below and

compared

them with the actual installation.

ISO No.

1-BR-337-R2

1-CC-207-R5

1-CC-215-R3

1-SW-208-R5

1-CC-134-R3

~Sstem

Boron Recycle

Component

Cooling Water

Component

Cooling Water

Service Water

Component

Cooling Water

Cl ass

With regard

to the inspection

above,

the inspector

noted that

on drawing

1-SW-208-R5 the distance

between

the centerline of line 3SW6-80SB-1

and the

socket face of field welds

1SW-208-FW-1099

and

1SW-208-FW-1102

were recorded

as

9 15/16-inches.

In both cases

this is one inch more than the actual

as

built dimensions.

The above is contrary to CPIIL Procedure

WP-141, Revision

4

"As Constructed

Pipe",

Appendix

A paragraph

which requires

as-built

measurements

to be accurate

to 1/16-inch for stress

analyzed lines.

Failure

to accomplish activities affecting quality in accordance

with procedures

is

a violation of Title 10,

Code of Federal

Regulations

Part 50, Appendix

B

Criterion V.

This violation will be identified as 400/86-05-01 "Failure to

Follow As-Built Documentation

Procedure".

Within the

areas

examined,

no violations or deviations

were identified

except

as noted above.

Spent

Fuel Storage

Racks

(50095)

The inspector

observed

ongoing

work activities to determine

whether

the

licensee

work control

system

is functioning properly

and

whether

the

installation

of spent

fuel

storage

racks

is

in compliance

with

NRC

requirements,

licensee

commitments

and applicable

codes

as described

below.

The

inspector

observed

handling,

cleaning,

installation

and

leveling

activities during the installation of the spent fuel racks into the spent

fuel

pool

to verify the

following:

availability

and utilization of

specially trained personnel

and equipment;

approved

drawings, specifications

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and procedures

are available for use (latest revision) at installation site;

proper location

and orientation

checked

against

drawings; seismic restraints

in place

and

gapped;

no apparent

damage

to racks or spent fuel pool during

installation; required installation welds

and performance of specified

NDE;

required bolting, shimming,

and torquing of fasteners

are being performed in

accordance

with approved

procedures;

gA inspection

coverage is adequate;

and

corrosion test

specimens

are installed properly (if required

by specifi-

cations).

With regard

to the

above inspection,

the licensee

informed the inspector

that the design of and the installation pattern of the spent fuel storage

rack assemblies

had

changed

with respect

to the spent fuel pool bottom and

the spent fuel storage

rack assembly

embedded

support plates.

This change

resulted

in

some of the

spent

fuel

storage

rack

assembly

support feet

resting

on liner plate

and

not

on the

intended

embedded

support plates

resulting in deflection of the liner plate.

The condition is described

in

Field

Change

Request

No. AS-10360.

Pending

NRC review of the

above Field

Change

Request,

this issue will be identified

as

inspector

followup item

No. 50-400/86-05-0:

"Spent

Fuel Storage

Rack Assembly Support".

Within the areas

examined,

no violations or deviations

were identified.

9.

Inspector

Followup Items

(92701B)

(Closed)

Item 400/84-30-01:

"VT-2, 3, and

4 Examiners"

At the

time of the inspection

discussed

in

NRC Report 400/84-30-01,

the

licensee's

program did not address

qualification of visual

examiners

VT-2,

3,

and

4.

The licensee

has

subsequently

issued

CPSL Procedure

IST-108,

Rev.

1, dated

January

3,

1986,

"Nuclear Inservice

Inspection

Procedure

for

the Certification of Visual

Examination

Personnel

(NES)" to address

the

above qualification.

This inspector

reviewed

the

procedure

and

has

no

further questions.

This matter is considered

closed.

10.

Licensee Identified Items

(10 CFR 50.55(e))

a ~

(Open)

Item

400-CDR-80-41:

"Potential

Failure

of

the

Reactor

Protection

System Following Secondary

High Energy Line Rupture"

On July 7, 1980,

the licensee notified

NRC Region II of a 50.55(e)

item

concerning

a potential

failure of the

reactor

protection

system

following a secondary

high energy line rupture.

The final report was

submitted

on

February

28,

1985.

The report

has

been

reviewed

and

determined

to

be

acceptable

by

NRC

Region II.

The inspector

held

discussions

with responsible

licensee

and/or

contractor

represen-

tatives,

reviewed supporting

documentation,

and observed

representative

samples

of work to verify that the corrective actions identified in the

report

have not been

completed.

This matter

remains

open

pending the

NRC verification of the

adequacy

of the insulation that the licensee

plans to employ and the completion of the installation.

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(Closed)

Item

400-CDR-82-92:

"Bolted Structural

Connections

with

Excessive

Gaps"

On July 2, 1982, the licensee notified

NRC Region II of a 50.55(e)

item

concerning

excessive

gaps

in bolted structural

connections.

The final

report was submitted

on Nay 10,

1985.

The report

has

been

reviewed

and

determined

to

be acceptable

by

NRC Region II.

The inspector

held

discussions

with responsible

licensee

and/or contractor

representa-

tives,

reviewed

supporting

documentation,

and observed

representative

samples

of work to verify that the corrective actions identified in the

report have

been completed.

This matter is closed.

(Closed)

Item

400-CDR-81-102:

"Grease

In Friction

Type Structural

Connections"

On

September

15,

1982,

the

licensee

notified

NRC

Region II of

a

50.55(e)

item

concerning

grease

in friction

type

structural

connections.

The final report

was submitted

on

May 10,

1985.

The

report

has

been

reviewed

and

determined

to

be

acceptable

by

NRC

Region II.

The inspector

held discussions

with responsible

licensee

and/or contractor

representatives,

reviewed supporting

documentation,

and

observed

representative

samples

of work to verify that

the

corrective actions identified in the report have

been

completed.

(Closed)

Item 400-CDR-82-111:

"Seismic gualification Test Failure of the

Starting Air Check

Valves for the

Emergency

Diesel

Engine

Generator

Set"

On December

23,

1982, the licensee notified

NRC Region II of a 50.55(e)

item concerning

seismic qualification test failure of the starting air

check valves for the

emergency

diesel

engine generator

set.

The final

report

was

submitted

on August 16,

1984 dated

August 17,

1984.

The

report

has

been

reviewed

and

determined

to

be

acceptable

by

NRC

Region II.

The inspector

held discussions

with responsible

licensee

and/or contractor representatives,

reviewed

supporting

documentation,

and

observed

representative

samples

of work to verify that

the

corrective action identified in the report has

been completed.

(Closed)

Item 400-CDR-82-112:

"Deficiencies In Bolted Connections"

On

December

29,

1982,

the

licensee

notified

NRC

Region II of

a

50.55(e)

item

concerning

deficiencies

in

bolted

structural

connections.

The final report

was submitted

on Harch 29,

1985.

The

report

has

been

reviewed

and

determined

to

be

acceptable

by

NRC

Region II.

The inspector

held discussions

with responsible

licensee

and/or contractor

representatives,

reviewed

supporting

documentation,

and

observed

representative

samples

of work to verify that

the

corrective actions identified in the report have

been completed.

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Item 400-CDR-83-115:
"Base Material
Defect in Spool
Piece
Supplied
by Southwest
Fabrication
and Welding Company"
On January
26,
1983,
the licensee notified
NRC Region II of a 50.55(e)
item concerning
base
material
defects
in
a spool
piece
supplied
by
Southwest
Fabrication
and Welding
Company
(Southwest
Fab.),
The final
report
was
submitted
on July 29,
1983.
The report
has
been
reviewed
and determined
to
be acceptable
by
NRC Region II.
The inspector held
discussions
with responsible
licensee
and/or contractor
representa-
tives,
reviewed
supporting
documentation,
and
observed
representative
samples of work to verify that the corrective actions identified in the
report have
been completed.
g.
(Closed)
Item CDR-83-123:
"Pressure
Boundary Material Supplied
By Tube
Line Corporation
Not Meeting Specification
Requirements"
On March 30,
1983,
the licensee
notified
NRC Region II of a 50.55(e)
item concerning
pressure
boundary
material
supplied
by
Tube
Line
Corporation
not meeting specification
requirements.
The final report
was
submitted
on April 28,
1983.
The report
has
been
reviewed
and
determined
to
be acceptable
by
NRC Region II.
The inspector
held
discussions
with responsible
licensee
and/or contractor
representa-
tives,
reviewed
supporting
documentation,
and observed
representative
samples of work to verify that the corrective actions identified in the
report have
been completed.
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