ML20195G994

From kanterella
Jump to navigation Jump to search
Insp Repts 50-313/88-35 & 50-368/88-35 on 881030-1104. Violation Noted.Major Areas Inspected:Unit 1 Containment Integrated Leak Rate Test
ML20195G994
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 11/17/1988
From: Ray Azua, Seidle W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20195G978 List:
References
50-313-88-35, 50-368-88-35, NUDOCS 8811300166
Download: ML20195G994 (5)


See also: IR 05000313/1988035

Text

_ _ _ - -

_--

- - - - - - - - _ - - - - - - - - _ - - - - - - - _ _ _

_ _ _ _ _ _

,

..

.

.

.

'

APPENDIX

'

1

U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

i

i

NRC Inspection Report: 50-313/88-35

Operating Licenses: OPR-51

'

50-368/88-35

NPF-6

!

'

Dockets:

50-313

50-368

-

!

Licensee: ArkansasPower&LichtCompany(AP&L)

l

P. O. Box 551

i

I..ittle Rock, AR 72203

t

Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2

Inspection At: ANO site, Russellville, Arkansas

InsWction Conducted: October 30 through Novet6ber 4, 1988

,

i

Inspector:

M

wh 7// /

-

e

R. V. Azua.,Jeactor Inspector Test

Date

i

Programs Section, Division of Reactor Safety

,,

.

!

Approved:

-

h/// M/

'

W. C. Seidly Chief, Test Programs Section

Date

Division of Reactor Safety

j

i

!

Inspection Summary

Inspection Conducted October 30 through November 4, 1988 (Report 50-313/88-35)

[

i

'

Areas Inspected:

Routine, announced inspection of the Unit 1 Containment

.

Integrated Leak Rate Test (CILRT).

I

Results: Within the area inspected, one apparent violation was identified.

j

(Failure to correstly follow procedures, paragraph 3)

7

{

Inspection Conducted October 30 through November 4, 1988 (Report 50-368/88-35)

f

I

Areas Inspected:

No inspection of Unit 2 was conducted.

!

l

R?sults:

Not applicable.

6

!

8811300 66 88111e

i

PDR

A

M 05000313

f

0

PNU

[

- -

- - - - - -

-

_ _ _ _ _ _ _ .

_ _ - _ _ _ _

_ ___ _ . _ _ _

_ _ - _ _

l

l

j

.

-2-

.

.

DETAILS

l

1.

Persons Contacted

  • J. Levine, Executive Director, Nuclear Operations

)

  • J. Vandergrift, Manager, Nuclear Operations
  • R. Lane, Manager. Engineering

,

  • H. Greene Superintendent, Quality Assurance
  • J. Taylor-Brown, Superintendent Quality Control / Quality Engineering
  • D. Crabtree Supervisor, Engineering Services

.

J. Roberson, Supervisor, Instrumentation and Controls (I&C)

  • D. B. Lomax. Supervisor, Plant Licensing
  • P. Michalk, Licensing Specialist
  • R. Oxner, Engineering Services. CILRT Test Director

!

  • R. McWilliams, Engineer Engineering Services

'

B. Neal, Instructor. I AC Training

i

Bechtel, Inc.

A

L. ' Young, Engineer (CILRT)

R. Blum. Engineer (CILRT)

NRC

  • W. Johnson, Senior Resident Inspector

The NRC inspector also contacted other plant personnel, includire

l

operators, technicians, and administrative personnel.

  • Denotes those present during the exit interview.

2.

Unit 1 CILRT Procedure Review (70307)

!

Ouring the week of October 30 through November 4,1988, the licensee was

preparing for a full pressure CILRT on the Unit I containment building.

The NRC inspector reviewed the licensee's CILRT Procedure No. 1092.030,

Revision 0, to verify that the requirements of the Unit 1 Technical

l

Specifications; ANSI N45.2 (1972), ANSI /ANS 56.8 (1981) and Bechtel Topical

Report BN-TOP-1 had been incorporated.

In addition, the procedure was

i

verified to have the proper approvals as indicated by appropriate

!

signatures.

,

l

The NRC inspector randomly chose several systems, which were addressed in

[

Procedure No. 1092.030, for review against the licensee's Piping and

'

Instrumentation Diagrams (P&lDs). This was done in an effort to

detertnine that all the appropriate valves in the selected systems were

addressed in the procedure (Appendix B). The NRC inspector also reviewed

l

,

-

- - - -

.

, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ - _

_

,

4

9

.

3-

the test position of the valves, listed in the same procedure, to verify

that the associated systems were placed in correct alignment for the

performance of the CILRT.

Finally, the NRC inspector detennined that all

appropriate systems required to be aligned for the CILRT were addressed

in the procedure.

The NRC inspector reviewed the changes that were made to the CILRT

procedure and found them to be acceptable. They did not alter the

technical content of the procedure or change the way in which the test was

being performed. The NRC inspector also verified that the changes were

approved, as indicated by the appropriate signatures.

The CILRT procedure listed, in Appendix B, the valves that were required

to be aligned for the test.

This list contained two signature lines

beside each identified valve. One was for the operator that positioned

the valve, and the other was for the individual who verified that the

valve was in the proper position.

The methodology used for the valve

lineup is described in Appendix B (page 30 of 123) of this procedure.

In

addition Section 2.3 of Appendix B stated that "independent verification

will be done in accordance with ANO Station Policy Z."

The NRC inspector

reviewed both Appendix B and the ANO Station Policy Z, and found them to

be acceptable.

Attachment A of Appendix M in the CILRT procedure, contains an example

of the CILRT equipment tags.

The NRC inspector noted that the tags did

not provide any signature lines for either the operator, who positions

the valve, or the individual who performs the independent verification.

The licensee stated that the reason for omitting the signature lines was

because it was too difficult for the operators to sign the cards while

wearing the anticontamination clothing. The licensee explained that the

operators would carry a copy of the valve list into the containment

building and would check off those valves that were completed. The

operators would then use this list as a reference, to fign-off the

affected valves in the controlled copy of the CILRT procedure. The NRC

inspector mentioned to the licensee that a checkoff box for the

independent reviewer could be used on the CILRT tag.

This would remove the

need for a signature, but would still provide another method by which the

licensee could verify that the valve was actually reviewed.

Finally, the CILRT procedure was reviewed by the NRC inspector for

technical adequacy.

No violations or deviations were identified in the review of this program

area.

3.

CILRT Surveillance (70313)

The NRC inspector performed several tours of the containment building and

the auxiliary building. This was done to monitor the installation of the

test equiptrent and th: valve lineup process. The NRC inspector reviewed

a sample of 56 valves that had been positioned and tagged for this test.

.

- _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

___

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __

____

.

,

.

'

-4-

.

While examining Valve ICW-32, an 8-inch valve in the instrument cooling

water system, the NRC inspector noted that the valve appeared to be

closed.

The valve lineup sheet and the attached CILRT tag called for the

valve to be open.

The NRC inspector notified the licensee who, in turn,

sent an operator who confirmed that the valve was in the wrong (shut)

position for performing the CILRT.

The NRC inspector then reviewed the

,

controlled copy of the CILRT procedure, and noted that valve ICW-32 had

,

been signed-off and second-checked as verified for proper (open) valve

!

position.

The licensee interviewed the operators involved in positioning and

[

verifying the affected valves.

In addition, other operators that had

i

been manipulating valves in the vicinity of ICW-32 were also interviewed.

Fo? lowing the interview, the licensee was unable to determine conclusively

,

how the valve. ICW-32, came to be mispositioned.

The licensee expressed a

high degree of confidence that it was not an error that was over looked by

r

the independent verification process, but that the valve was manipulated

1

inadvertently by another operator after the valve had been tagged and

verified.

Based on the information provided by the licensee, the NRC inspector

could not find enough evidence to support the licensee's contention that

the valve was manipulated after it had been tagged and verified. Without

[

any further information, the NRC inspector concluded that the error was

caused by inadequate verification.

This is an apparent violation of

the CILRT Procedure No. 1092.030, Revision 0, for valve lineup and

,

verification requirements.

i

The licensee took immediate corrective action after the operator had

[

concurred that the valve was mispositioned.

The corrective action

,

included repositioning Valve ICW-32 to its correct test position, and

!

performing a second independent verification of all valves that had

been tagged for the CILRT.

The calibration documentation for the test equipment (RTDs, dewpoint

hygrometers, voltmeters, and pressure gauges), provided by General

Electric Company, Rockwell International and the site I&C department,

!

were reviewed by the NRC inspector.

The procedures by which the plant

I

!&C technicians calibrated some of the equipment were reviewed by the NRC

!

inspector. No errors were detected and all instruments were found to be

I

in calibration for the period encompassing these tests.

The NRC

i

inspector also reviewed the certification and training records of one of

!

the technicians involved in calibrating some of the test equipment.

[

l

Due to time constraints and a slip in the licensee's schedule, the NRC

l

inspector was unable to be present during the actual test, i.e., pump-up,

i

stabilization, data taking, and pump-down.

The data and the results of

i

this test will be forwarded to the NRC for review.

The results of the

!

review will be addressed in a separate report.

j

i

!

!

. . .

_ _ _ _ _ _ _ _ . _ _

.

.

]

_

- _ _ _ _ - _ _ _ _ _ _ _ _ _

_

_

__

_

.. .

'

..

5-

The data acquisition station had not been fully assembled while the NRC

inspector was on site.

This precluded the NRC inspector from witnessing

the channel checks or the insitu calibration of the test equipment.

4.

, Exit Interview

An exit interview was held on November 4, 1988.

The NRC inspector

summarized the scope and findings of the inspection.

The licensee did

not identify as proprietary any of the information provided to, or

reviewed by, the NRC inspector.