Text

Insp Rept 50-298/85-31 on 851118-22.Violations Noted:Failure to Remove Jumpers & Identify Inoperable Snubbers to Maintain Housekeeping & to Properly Log & Sign Off Surveillance Discrepancies
	ML20153D502
Person / Time
Site:	Cooper
Issue date:	02/14/1986
From:	Dubois D, Jaudon J, Mcneill W; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	;
Shared Package
ML20153D473	List: ML20153D469; ML20153D502;
References
	50-298-85-31, NUDOCS 8602240164
	Download: ML20153D502 (9)
	v • d • e

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APPENDIX A

U.S. NUCLEAR REGULATORY COMMISSION-

REGION IV

NRC Inspection Report: 50-298/85-31

License /CP:

DPR-46

'

Docket: 50-298

' Licensee:

Nebraska Public Power DistFict

P. O. Box 499

Columbus, Nebraska

68601

'

Facility Name: Cooper Nuclear Station (CNS)

,

Inspection At: CNS Site, Brownville, Nebraska

Inspection Conducted: . November 18-22, 1985

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Inspectors:

-

W. M. McNeill , Project Engineer. . Project

Date

.

Section A, Reactor Projects Branch

(paragraphs 1, 2, 3, 4, and 5)

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D. L. DuBois, Senior Resifent Inspector-

Date '

(paragraphs 1, 2, 4, and 5)

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Approved:

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ief, Project Section A

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ea or Pr ects Branch

Inspection Summary

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Inspection Conducted November 18-22, 1985 (Report 50-298/85-31)

Areas Inspected:

Routine, unannounced inspection of secondary containment

integrity, surveillance of pipe supports-and the fire protection program and

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DETAILS

1.

Persons Contacted

P. Ballinger, Operations' Engineering Supervisor

R. Beilke, Chemistry and Health Physics Supervisor

D. Bremer, Shift Supervisor

R. -Brungardt, Operations Manager

S. Freborg, Lead Mechanical Engineer

H. Hitch, Senior Staff Engineer

H. Jantzen, I&C Supervisor

E. Mace, Plant Engineering Supervisor

J. Meacham, Technical Manager

B. Moeller, Mechanical Engineer

D. Norvell, Maintenance Manager

J. Peaslee,, Surveillance Coordinator

J.. Sayer, Technical Staff Manager

P. Tnomason, Nuclear Operations Division Manager-

V. Wolstenholm, QA Manager

The NRC inspector; also interviewed other plant and general office

personnel, including engineering, administrative, and clerical.

Denotes presence at exit interview.

2.

Surveillance Testing

The purpose of this inspection was to conduct a follow up inspection on

two events related to the control of surveillance testing. These two

events, which are discussed in Sections 2.a and 2.b below, concerned

secondary containment integrity and pipe supports.

'

a.

Secondary Containment Integrity

The objective of this inspection was to conduct a followup inspection

to a licensee report. The licensee had reported that irradiated fuel

was moved on November 14, 1985. At the time of this fuel movement,

the output of detectors which cause automatic actuation of the

standby gas treatment system and automatic isolation of Reactor

Building ventillation was blocked. This means that secondary

, containment integrity was not established.

,

The NRC inspector found the following:

o

Technical Specifications, paragraph 3.7.C.1 requires that

secondary containment integrity be maintained when irradiated,

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fuel is handled inside the secondary containment.

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Technical Specifications, paragraph 3.7.B.1 requires <that both

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channels of reactor building isolation and standby gas treatment

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trains be operable at allJtimes when secondary containment

integrity is^ required-.

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Surveillance Procedure 6.3.7.5 was conducted November 13, 1985,

to demonstrate standby gas treatment system operability. This

surveillance test is the calibration and functional test of

reactor building radiation monitors. These monitors, on an

upscale or inoperative trip of either of the two channels, cause

a reactor building ventilation shutdown, reactor building

isolation, and standby gas treatment initiation.

o

Jumpers are used in accordance with Procedure 6.3.7.5 to prevent

the trip and equipment operations-described above during

calibration or functional testing.

o

Jumpers installed during Procedure.6.3.7.5 were not removed as

required by the procedure.

o

Irradiated fuel was loaded into a fuel transfer _ cask on

November 14, 1985.

o

On November 18, 1985, during a different surveillance test, the

installed jumpers were found. The jumpers were subsequently

removed and the occurrence reported to the-NRC.

The NRC inspector concluded that the incorrect conduct of

Surveillance Procedure 6.3.7.5 had inactivated the automatic

establishment of secondary containment integrity because of high

radiation. Thus, a system designed to protect public health and

safety was not operable in that it would not have functioned

automatically, as it was designed to do, if it-had been called upon

in an accident. This is an apparent violation (8531-01).

b.

Pipe Supports and Directional Restraints

The objective of this inspection was .to determine whether or not the

surveillance of pipe supports and directional restraints (snubbers)

for safety-related piping and equipment was in conformance with the:

Technical Specifications.

The NRC inspector reviewed the Technical Specifications,

._

_.

Section 3.6.H, the Updated Safety' Analysis Report and the following-

procedures:

Revision

Procedure Number

. Title

Nunber

Date

.

MP 7.2.34

Snubber Inspection

15

9/19/85

MP 7.2.52

Pipe Snubber Removal and

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6/17/85

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During a previous inspection, an NRC inspector had noted a potential'

problem with one snubber installed in the drywell. This problem was

that a horizontally mounted snubber, which supported a vertical pipe,

appeared to be very close to a deck grating. The' licensee had

reviewed this situation and issued a nonconformance. report-

(NCR-004989 dated October 25,1985). The NRC inspectors reviewed

this NCR and the licensee's followup actions during this inspection.

The licensee had . replaced the snubber in question after removing the.

deck grating under it. The removed snubber was scheduled to be tested

by an independent laboratory.

The licensee had conducted a surveillance inspection of this snubber

and 50 other drywell snubbers'in July 1985. Since this surveillance

had not identified the apparent problem with one snubber, the 50

snubbers were reinspected. The licensee identified one additional

snubber of the 50 with an interference problem and found an

interference problem with a snubber which was not in the specified

sample. The surveillance inspection was expanded to include all

144 drywell snubbers, and, one additional snubber was found to have

an interference problem. These three snubber problems were documented

on NCR-004994.

The snubbers were replaced and the interferences

removed.

The NRC inspector noted that there were a total of 292 safety-related

snubbers. Of these,144 were in the drywell, and the remaining 148

outside of the drywell. The NRC inspector noted that the surveillance

procedures were not specific with regard-to interference; however,

one procedure did address " impaired operability." -It was further

noted that the inspection of snubbers had been reassigned from

engineering to maintenance. - During.the period August 20 to October 5,

1985, there had been four snubbers with interference problems while

the plant was in operation. These included the snubber originally

questioned by the NRC inspector and the three other snubbers

identified by the licensee as having interference problems.

The NRC inspector selected a sample of ten.snuubers outside the

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'drywell- to be inspected. The licensee elected to accompany the NRC

inspector during this inspection. The NRC inspector found one

snubber in the sample of ten that was apparently inoperab.le because

lof interference between the clevis and the paddle and two other

snubbers with possible interferen~ce problems. The NRC inspector also

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"noted a' snubber, outside the selected sample of ten, with the pipe

clamp loose and two other snubbers with potential interference ~

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problems. The licensee decided that a complete reinspection of all

snubbers was required. The result of this inspection was that a

total of 21 snubbers (5 in the drywell and 16 outside of the drywell).

-

had problems including those identified by the NRC inspector. Thus,

the total number of snubbers with identified problems after all

inspections was 25 (out of a total of 292 safety-related snubbers). -

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requirements _(para.- 4.6.H, which requires . visual inspection for damage

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tion or; supporting _ structure).. ~This is an apparent violation (8531-01)'.

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Nire Pho ectionlProgra.n and Its Implementation

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$The objectives of this inspectio'n were to ascertain whether the 1.icensee's:

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(program and-its implementation for fire protection and prevention is in-

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!conformance with' regulatory requirements, commitments in the application

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iand; industry guides and standards.

In this regard, the USAR, Technical

. Specifications, Quality Assurance Program for Operation l Policy Document,

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Revision 2, dated April 29, 1985, and the following procedures were

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Procedure-

kevision

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Numberi

Title

Number

Date-

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QAP 800

Fire' Protection

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02/18/85

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5.0 2:2.30-

Fire Protection System

24

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- EP 5.4.1

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General' Fire ~ Procedure

19

10/03/85

'EP 5.4.2.1-

Battery Room Fire

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08/06/84

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EP 5.4.2.2

Cable. Spreading Room Fire

9

07/25/84

EP 5;4.2.3-

Computer Room Fire.

10

08/06/84'

EP 5.4.2.4..

Control Building Basement Fire

9

08/06/84

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CSCS-Pump Room Fire

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Drywell Fire '

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460 V MCC Fire'

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480 V Switchgear Fire

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08/27/84

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Number

Title.

Number

Date

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EP 5.4.2.16

ReactorFeedPuhp011 Fire

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Reactor Recirculation System MG Set

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Transformer' Fire

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08/06/84

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Tufbine Basement Oil Fire

[ '17

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EP 5.4.2.21-

Turbine' Generator Bearing Fire .

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08/27/84;

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Turbine .0il Condiiioner"Rooni' Fire e '

7

07/25/84

EP 5.4.2.23

l Turbine Oil Reservoir Room F, ire i

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10/25/84

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Turbine Oil Storage , Room Fire

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EP 5.4.2.25

Turbine. Generator Floor 011 Fire

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Augmented Radwaste Fire-

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Fire Protection System Montnly

38

11/07/85.

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' Inspection.

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SP 6.4.5.2

Fire Protection System Annual

30

11/07/85'

Inspection

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SP 6.4.5.3

Fire Pump Weekly Operability Test-

12

10/24/85:

SP 6.4.5.5

Fire Detection System Semi-Annual

10

10/09/85

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Inspection

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Fire Detection System Circuitry

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08/24/85

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Operability

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SP 6.4.5.7

Diesel Generator CO, Operability

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12/20/79

SR 6.4.5.8

Hose Station Valve Operability

'8

02/01/84

SP 6.4.5.9

Diesel Fire Pump Inspection:

5-

09/24/84

SP 6.4.5;12

Diesel Fire Pump Fuel Quality Test

2

02/01/84

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SP 6.4.5.13

Fire Detection' System Annual Inspection l 6

04/29/85.1

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SP-6.4.5.14

High Pressure CO, Bottle ~ Inspection

6.

05/31/85

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Fire Protection System Flow Verifica-

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Fire: Protection System 18-Month

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Number

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SP-6.4.5.17

Fire Fighting Equipment Monthly

10

10/24/85

Inspection

SP 6.4.5.18

Fire Protection System Flow Test

2

06/07/85

ihe Nd inspecor found that the program for fire prevention designated '

personnel to implement the program and delineated requirements for

training and qualification of the designated personnel requirementt, The

NRC inspector.found that administrative controls' had been established for

control of combustibles. These included prohibition of wastes, debris,

etc., and periodic inspections for accumulation of combustibles.

It was

also noted that welding, cutting and other ignition sources were required

to be controlled. A fire brigade and its organization and qualifications

had been established. General as well as specific or special fire

procedures were established. These procedures were found to address fire

reporting and fire fighting instructions in the emergency procedures

series 5.4.x.x.

Surveillance procedures series 6.4.5.x delineated

inspection and testing requirements of fire protection and prevention

equipment.

In regard to implementation of the program, the curre.it fire brigade

rosters (crew assignments) were reviewed. The training and medical

records of brigade members were verified. The qualification and offsite

training of the station fire chief were inspected. Orill records of all

five crews were examined. One fire locker, chosen at random, was,

inventoried. A facility tour was made of the reactor control ~and turbine

buildings to observe housekeeping, restriction of materials and' fire

protection and fighting equipment. Surveillance reports were reviewed of

the current calendar year.

In respect to housekeepi.ng it'was noted that

the RHR heat exchanger "B" room and the HPCI' room in the southwest quad

were found to have several boxes of refuse and other trash in their- door

ways and access areas sufficient.to limit access of personnel and fire

equipment. A # ire hose in the southwest quad at 882 elevation was

covered with personnel clothing. A radiation waste effluent monitors

(TB-486) at elevation 903' on the south wall of the re' actor building was.

found to have a plastic pail on top of an electric motor.

In the 4160-

volt switchgear room a number of aerosol cans of flammable laaterials were

fcund within '3 t- 4 feet of switchgear equipment with electric heaters.

The above was identified as an apparent violation 1(8531-02).

In regard-to surveillance inspections, certain monthly and annual'

.

inspections were found where discrepancies were not. identified in the

shift supervisor's log nor did the shift supervisors sign off the

'

surveillance report when a work item was initiated ~to correct-

discrepancies. The procedures for monthly and annual inspections both .

-

,

state that all dis ~crepancies shall.be recorded in the shift supervisor's

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log. Also, the surveillance checklists or reports provide for the shift

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supervisor signoff'if a NCR or work item is initiated.

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monthly: inspections dated August 4, September 2,' September 28. and. .

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Octoberi29, 1985, all noted work iteas were initiated but'did not have the

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xSeptember 28,l1985, had discrepancies identified yet they were not- noted

in the shift supervisor's log. The above-was identified as an apparent'

violation'(8531-03).

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4 .'

. Exit Meeting

The NRC inspectors conducted an exit meeting'on November 22,'1985~, with'

the licensee personnel denoted in paragraph 1. ~ At this. meeting, the.

purpose'and the findings of the inspection were sumarized.

5.

Enforcement Conference

On December-17, 1985, an enforcement conference was held 't the NRC

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Region IV office to discuss these findings of the-i.nspection.

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