ML17331B036

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Insp Repts 50-315/93-19 & 50-316/93-19 on 930911-1019. Violations Noted But Not Cited.Major Areas Inspected:Plant Operations,Maintance & Surveillance
ML17331B036
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 10/01/1993
From: Kobetz T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17331B034 List:
References
50-315-93-19, 50-316-93-19, NUDOCS 9311090056
Download: ML17331B036 (15)


See also: IR 05000315/1993019

Text

U.

S.

NUCLEAR REGULATORY COHHISSION

REGION III

Report Nos.

50-315/93019(DRP);

50-316/93019(DRP)

Docket Nos.

50-315;

50-316

Licensee:

Indiana Michigan Power

Company

1 Riverside

Plaza

Columbus,

OH

43216

License

Nos.

DPR-58;

DPR-74

Facility Name:

Donald

C.

Cook Nuclear

Power Plant, Units

1

and

2

Inspection At:

Donald

C.

Cook Site,

Bridgman,

HI

Inspection

Conducted:

September

11 through October

19,

1993

(I

Inspectors:

J.

A.

Isom

D. J. Hartland

Reactor

rojects Section

2A

~~,

9

ate

Ins ection

Summar

Inspection

from September

11 through October

19,

1993

(Report Nos.

50-315/93019(DRP);

50-316/93019(DRP))

Areas

Ins ected:

Routine,

unannounced

inspection

by the resident

and

Headquarters

inspectors

of: plant operations;

maintenance

and surveillance;

engineering

and technical

support;

actions

on previously identified items;

reportable

events;

and,

NRC Region III requests.

Results:

Two violations were identified (paragraphs

S.d

and 5.e) for which no

Notice of Violation is being issued

based

on conformance

to criteria for

exercise of discretion contained

in the

NRC Enforcement Policy.

h

d.

monitoring of equipment/system

parameters

in the plant

by the auxiliary

operators

was

found to be informal in that they were not required to take data

on operating

systems.

En ineerin

Technical

Su

ort:

The investigation into problems with the

auxiliary feed

pump bearing oil was good.

Safet

Assessment

ualit

Verification:

Overall, the licensee's

root cause

evaluation

and corrective actions for open

items closed during this inspection

period

was satisfactory.

9311090056

931101

PDR

ADOCK 05000315

8

PDR

DETAILS

Persons

Contacted:

  • A. A.
  • K. R.

L. S.

  • J

E

B. A.

  • T

P'-.

F.

D. L.

L. J.

T. K.

S.

A.

P.

G.

  • J. S.

L. H.

  • G. A.
  • D

H. L.

B3 ind,

Pl ant Manager

Baker, Assistant

Plant Manager-Production

Gibson, Assistant

Plant Manager-Projects

Rutkowski, Assistant

Plant Hanager-Technical

Svensson,

Executive Staff Assistant

Beilman, Maintenance

Superintendent

Carteaux,

Training Superintendent

Noble, Radiation Protection

Superintendent

Matthias, Administrative Superintendent

Postlewait,

Design

Changes

Superintendent

Richardson,

Operations

Superintendent

Schoepf,

Project Engineering

Superintendent

Wiebe, Safety

& Assessment

Superintendent

Vanginhoven,

Site Design Superintendent

Weber,

Plant Engineering

Superintendent

Loope,Chemistry

Superintendent

Horvath, guality Assurance

Supervisor

Support

The inspector also contacted

a number of other licensee

and contract

employees

and informally interviewed operations,

maintenance,

and

technical

personnel.

  • Denotes

some of the personnel

attending the Management

Interview on

October 25,

1993.

Plant

0 erations

71707

71710

42700

The inspector

observed

routine facility operating activities

as

conducted

in the plant

and from the main control

rooms.

The inspector

monitored the performance of licensed

Reactor Operators

and Senior

Reactor Operators,

of Shift Technical Advisors,

and of Auxiliary

Equipment Operators

including procedure

use

and adherence,

records

and

logs,

communications,

and the degree of professionalism of control

room

activities.

The inspector

reviewed the licensee's

evaluation of corrective action

and response

to off-normal conditions.

This included compliance with

any reporting requirements.

The inspector

noted the following with regard to the operation of Units

1

and

2 during this reporting period:

a.

Unit

1 status:

The licensee

operated

the unit at full power during the inspection

period except

between

September

10-14,

1993,

when the licensee

b.

reduced 'power to 55 percent to perform

a Clamtrol treatment of its

lake water systems'or

zebra

mussel

infestation.

The licensee

did not experience

any significant operational

problems during the

inspection period.

Unit 2 status:

c

~

The licensee

operated

the unit at

75 percent

power during the

inspection period except

between

September

10-14,

1993,

when the

licensee

reduced'power

to 55 percent to perform

a Clamtrol

treatment of its lake water systems for zebra

mussel

infestation.

'The licensee

did not experience

any significant operational

problems during the inspection period.

Auxiliar

E ui ment 0 erator Plant Tours:

The inspector

accompanied

several

auxiliary equipment operators

(AEOs) for both units during the performance of shiftly plant

tours,

which are prescribed

by 01

L 02-OHP 5030.001.001,

"Plant

Tour Guidelines."'he

procedure

is

a guide for the

AEOs on the

performance of equipment

checks

and what types of plant conditions

are, considered

normal

and should

be expected

during their plant

tours.

In addition to the tour guidelines,

the operators

take

some local readings for input into 01

8

02-OHP 4030.STP.030,

"Daily and Shiftly Surveillance

Checks,"

such

as containment

sump

run time meter readings

and battery

room temperatures,

The inspector

noted

a weakness

with the

"Plant Tour Guidelines"

procedure.

The procedure

does

not contain data

sheets

with

entries for logging local plant readings,

therefore

the AEO's.

plant tours

can potentially miss

components

that are prescribed

to

be monitored

by the guidelines.

This was discussed

with plant

management.

They had

been reluctant to implement data

sheets

for

plant tours

because

they do not want to limit the items that the

AEOs look at during their tours.

They want the

AEOs to maintain

a.

questioning attitude

about all plant equipment rather than

confining them to looking at specific gauges for logging data

points.

Therefore,

they have

implemented

the guidance for plant

tours

and expect the

AEOs to become familiar with all the

equipment

on their tours

and

be aware of any changing conditions

and potentially degraded

equipment.

Licensee

management

was already

aware of the potential

weaknesses

with the

AEO tours

and are considering

plans to upgrade

them.

= They are investigating the

use of computer

pads for the AEOs,

which would allow them to take data points off of local gauges

and

produce

immediate trends of various parameters

on plant equipment.

System engineers

are currently reviewing the "Plant Tour

Guidelines"

procedure

and to determine

what types of parameters

the

AEOs should log for various

components.

Ho violations, deviations,

unresolved

or inspector followup items were

identified.

Maintenance

Surveillance

62703

61726

42700

The inspector

reviewed maintenance

activities

as detailed

below.

The

focus of the inspection

was to assure

the maintenance

activities were

conducted

in accordance

with approved

procedures,

regulatory guides

and

industry codes or standards,

and in conformance with Technical

Specifications.

The following items were considered

during this review:

the Limiting Condi.tions for Operation

were met while components

or

systems

were removed

from service;

approvals

were obtained prior to

initiating the work; activities were accomplished

using

approved

procedures;

and post maintenance

testing

was performed

as applicable.

The following activities were inspected:

a.

Unit

1 Turbine-driven Auxiliar

Feedwater

TDAFW

Pum

Turbine

Bearin

Oil Level:

b.

The inspector

reviewed licensee

actions

in response

to

a problem

encountered

with the Unit

1

TDAFW pump turbine bearing oil system.

The inspector determined that the licensee's

root cause

investigation

and corrective action to the problem were good.

On October

5,

1993,

the licensee

removed the

pump from service for

planned

maintenance,

which included change-out of the turbine

bearing oil

~

The following day, while running the

pump for post-

maintenance

testing,

licensee

personnel

observed that the oil

level

had fallen below the minimum level indicated

in the sight

glass

and that oil was leaking out of the outboard

bearing

housing..

After discussions

with the

pump vendor

and further troubleshooting

activities,

the licensee

determined that the draw-down of the oil

level

was

due to absorption

by the system,

which was expected

during initial pump startup after the oil change.

The licensee

also determined that the leakage

out of the outboard

bearing

was

due to the overfilling of the system.

As corrective action,

the licensee

lowered the

maximum level

indication

on the sight glass to prevent overfilling the system in

the future.

The licensee

was evaluating

enhancement

to the

applicable plant instruction to ensure that the system is properly

vented

when filling.

Surveillances

observed:

The inspector

observed

the following surveillances

and noted

no

deficiencies:

"Unit 2 Essential

Service

Water High Differential Pressure

Hotor

Operator Valve Testing,"

"Turbine Driven Auxiliary Feed

Pump Trip and Throttle Valve

Operability Test,"

2-OHP 4030.STP.017TV..

No violations, deviations,

unresolved

or inspector followup items were

identified.

En ineerin

and Technical

Su

ort

37828

The inspector monitored engineering

and technical

support activities at

the site

and,

on occasion,

as provided to the site from the corporate

office.

The purpose of this monitoring was to assess

the adequacy of

these

functions in contributing, properly to other functions

such

as

operations,

maintenance,

testing, training, fire protection

and

configuration management.

a.

Em t

Unit 2 "Auxiliar

Feedwater

AFA

Pum

Oil Bubbler:

b.

On October

2,

1993,

the inspector

accompanied

the

AFW system

engineer to determIne

the quantity of oil which could

be removed

from the turbine-driven auxiliary feedwater

(TDAFW) pump outer

bearing before oil lubrication using the slinger ring would be

lost.

The test

was performed using the spare

TDAFW pump to

. determine

whether the low oil condition found by

NRC inspectors

on

September

2,

1993,

was

a situation in which no oil was available

for lubrication of the outboard

bearings

(see

paragraph

2d of

50-315/93018(DRP); 50-316/93018(DRP)

.

The system engineer's

discussion

with the vendor indicated that

lubrication could still be provided to the bearings

as long

as the

slinger ring was

immersed

in oil.

The engineer

determined that

the bearing

housing contains

360 milliliters of oil from the

bottom of the bubbler assembly to

a level below the slinger ring.

Therefore,

based

on the 320 milliliters it took to refill the

bearing

housing to the bottom of the bubbler assembly

on

September

2, it appeared

that there 'was about

40 milliliters

available to provide lubrication to the bearings.

This

showed

that the oil level

was not found

so low as to render the

AFW pump

inoperable.

Unit 2 West Centrifu al Char in

Pum

The inspector

examined

the licensee's

investigation into the

failure of the Unit 2

"W" centrifugal charging

pump

(CCP)

(50--

315/93016(DRP);

50-316/93016(DRP))

through reviews of various

licensee

documents

and interviews with system engineers.

The

failed internal

assembly

was sent to We'stinghouse

for disassembly

and inspection to determine

the cause of the breakdown,

The high

vibrations

on the

pump were caused

by

a four inch,

180 degree

circumferential

crack through the number

9 impeller shaft

keyway.

Westinghouse

also reported

2 minor cracks

on the number

3 and

number

8 impeller shaft

keyways.

A metallurgical

analysis of the

shaft is still in progress.

Westinghouse

personnel

believe that

excessive

radial loadings

were applied to the keyways.

System

engineers

are continuing to perform

a root cause

determination

by .

reviewing the

pump operating history.

The inspector will continue

to follow the licensee's

determination of the root cause of the

pump failure and the corrective actions taken,

as appropriate.

c.

Unit

1 East Centrifu al

Char in

Pum

While performing predictive maintenance activities, the licensee

identified an increasing

trend

on the Unit

1 "E" CCP outboard

bearing vibration.

Although,this bearing

was not required to be

monitored

by the licensee's

IST program, this condition could have

been

symptomatic of a problem with the

pump which could result in

pump failure.

The inspector

reviewed licensee activities in

response

to this condition

and determined

that they were

satisfactory.

The licensee

responded

to this increasing

trend in vibration by

increasing

the surveillance

frequency of bearing vibration

measurement

from quarterly to biweekly.

In 'addition, the licensee

installed temporary instrumentation

to measure

the phase

angle of

the shaft.

A shift in the phase

angle would have

been indicative

of a circumferential

crack propagating

in the shaft.

No such

phase

angle shift was observed.

The licensee

also took the

pump out of service

on October 4,

1993,

to perform

a hot alignment check of the

pump

and motor shafts,

and

to check the tightness of the base plate

and foundation bolts.

The licensee

did not identify any deficiencies

associated

with

this work activity.

At the

end of the inspection period,

the

vibration levels

on the bearing

had

begun to trend

downward

and

were steady,

although still considered

in the "rough" range.

The

.

inspector will continue to follow the licensee's

investigation

into the bearing vibration problem.

No violations, deviations,

unresolved

or inspector followup items were

identified.

Actions on Previousl

Identified Items

92701

92702

Closed

IFI 50-315 92016-01

50-316 92016-01:

Licensee

Evaluation

of A e

Oe radation of Ex ansion Joints

This IFI involved

a concern related to failure of safety-related

expansion joints in the plant due to age degradation.

The licensee identified

a total of eight safety-related

expansion

joints in the plant.

All were installed in emergency

diesel

generator

(EDG) support

systems

(essential

service water cooling

'ater

supply

and combustion air supply).

Two of the joints had

been installed since

1990.

The licensee

was not able to determine

when the other six joints were installed.

In response,

the

licensee

contracted

a vendor to inspect the joints.

Based

on the

vendor's

recommendations,

the licensee

determined that

none of the

joints required

immediate replacement.

However,

the licensee

generated

action requests

to replace

the six joints during the

1994 refueling outages.

In addition,

the licensee

committed to

revise their preventive maintenance

program to require replacement

of the safety-related joints on

a 7-1/2 year interval.

Closed

Violation 316 92022-01:

Failure to Maintain Both EDG's

~oerable

Closed

Violation 316 92022-02:

Failure to Include Acce tance

Criteria For

EDG's

Closed

Violation 316 92022-03:

Failure to Prom tl

Identif

and

Correct Unit 2 "AB" EDG Leak

These violations were issued

in response

to the Unit

2 "AB" EDG

inoperability event

on September

28,

1992.

On that date,

the'EDG

tripped

on low lube oil pressure

due to insufficient oil inventory

in the

EDG lube oil tank.

A detailed investigation into the

event,

as

documented

in IR Nos.

50-315/92022(DRP);

50-

316/92022(DRP),

established

that the

EDG was inoperable for a

period of time in excess

of that allowed by TS.

The inspector identified several

root causes

for the event.

The

surveillance

procedure that monitored the

EDG lube oil level

on

a

weekly basis did not contain

any minimum acceptance

criteria.

As

long-term corrective action to this concern,

the licensee

performed

a review of the applicable tour procedures

to verify

that appropriate critical parameters

were monitored during the

AEO

tours.

The licensee

revised the

procedure es to include acceptance-

criteria

and trending methods for the parameters,

In addition,

the licensee

was currently developing

a computerized

system for

providing input and processing

the parameters

taken

on

AEO tours,

which will provide

a more formalized system for monitoring the

parameters.

The licensee

expected

to implement this system

by the

end of 1993.

Another root cause for the event

was the licensee's

failure to

take action to repair the leak which resulted

in the loss of the

lube oil inventory.

The licensee initiated

a work request

to

repair the leak several

months prior to the event,

but the request

did not quantify the leak,

and the licensee

assigned

the request

a

low work priority without periodically re-evaluating

the

significance of the leak,

In response

to this concern,

the

licensee

enhanced

the work request

review process

by requiring

a

more detailed description of deficiencies

on work requests.

The

licensee

also established

a work classification organization

within the scheduling

department,

consisting of three licensed

operators,

to review work requests

for detail

and assign

the

appropriate priority and schedule

date.

The licensee

also

added

a

requirement for system engineers

to periodically review work

requests

associated

with their assigned

systems.

Contributing factors to the event were

an inaccurate

level

indication

and the failure of the low level alarm to actuate.

In

response,

the licensee

was performing weekly dip measurements

of

the lube oil tank levels.

In addition,

the licensee verified

proper operation of each

EDG lube oil level alarm

and will

increase

the frequency of the level alarm operational

checks

from

once every four years to every refueling outage.

Closed

Unresolved

Item 315 93011-05:

CCW Flow to

Emer enc

Core

Coolin

S stem Heat

Exchan ers

During walkdown of the Component

Cooling Water

(CCW) system,

the

inspector

found that there were

no installed flow instruments

which could

be used to verify flow to the individual heat

exchangers

(which are in parallel) for the safety-related

charging

pumps.

At the time, the inspector

was concerned

that the licensee

would not be able to ensure that each of the heat

exchangers

was

receiving

adequate

design flow and that the licensee

would not be

able to detect degradation

in heat

exchanger

performance.

Each safety-related

charging

pump is designed with four heat

exchangers

which provide cooling to the pump's bearing oil, gear

oil and the two mechanical

seals.

The two mechanical

seal

heat

exchangers

are in-series

and, therefore,

are effectively one heat

exchanger.

One flow instrument is provided at the

CCW return

header

from these

heat

exchangers

to measure total

combined

CCW

flow.

The inspector

reviewed the instrumentation

and annunciators

associated

with the charging

pump system

and found that the

control

room operators

would not be able to determine

whether

there

was

a degradation

in heat

exchanger

performance

because

they

did not have annunciators

which could alarm to alert them of

degrading

heat

exchanger

performance.

One annunciator,

"East(West)

Lube Oil Temp Or Press

Low" (drop

13 on annunciator

panel

number

209)

alarms

on decreasing

lube oil temperature

or

decreasing oil pressure.

It appeared

that this alarm was

installed to detect excessive

CCW flow being provided

and to

detect for low oil conditions.

Additionally, only the bearing oil

cooler

had

a temperature

gauge which could

be used to monitor heat

exchanger

performance.

The inspector

reviewed the licensee's

flow curves

and determined

that if the heat

exchangers

performed

as designed,

there should

be

adequate

flow distribution between

the three heat

exchanger

sets.

There

have

been

no adverse

pump performance

problems resulting

from lack of

CCW cooling being provided to the charging

pumps.

'dditionally,

the

CCW system is

a closed

system

such that

potential fouling of the heat

exchangers

appeared

unlikely during

normal routine operations.

Closed

Unresolved

'Item 50-315 92009-01

LER 50-315 92006:

Failure of Hain Steam 'Safet

Valves to Neet Technical

S ecification Lift Set oint Re uir ements

Due to Set oint Drift

Historically, the licensee

has

had problems meeting the Technical

'Specification

(TS) lift requirement for their steam generator

safety valves.

Although this problem has

been uncorrected for

some time, it appeared

that this was

a generic industry problem.

Since then,

the licensee

has

performed further calculations

and

analysis to allow a

TS change

request to increase

the lift

~ setpoint tolerance

from

1 to

3 percent.

The inspector's

discussion

with the

NRR project manager

indicated that this

TS

change

request,

AEP:NRC: 1169,

dated

November

11,

1992,

was

reviewed

by the

NRR technical

section

and

was found to be

acceptable.

The

TS change

should minimize or possibly eliminate

the inability for the safety valves to meet their lift setpoint

requirements'dditionally,

the licensee will perform

refurbishment for safety valves which are found to exceed

the plus

or minus

3 percent

requirement.

This problem involved

a failure to prevent repetition of a

condition prohibited

by the TS.

However, the problem

had minimal

safety significance

because

the licensee

analysis

(based

on the

new Westinghouse

analysis)

showed that safety limits were not

exceeded

for either loss of load/turbine trip or small

break loss-

of-coolant scenarios.

In addition,

the licensee

properly reported

the event

and took appropriate corrective actions.

Therefore,

pursuant to the

NRC enforcement

policy (10 CFR 2, Appendix C), the

NRC is exercising

enforcement discretion for this matter,

and

no

Notice of Violation will be issued.

Closed

Unresolved

Item 50-315 92014-01

LER 50-315 92009-LL:

Failure of Two Pressurizer

Safet

Valves to Neet Technical

S ecification Lift Set oint

Re uirements

The licensee

has experienced

problems with failure of the

pressurizer

safety valves to liftwithin the required

pressures

in

the Technical Specifications

(TS).

LERs, 50-315/90016-LL for Unit

1

and 50-316/92006-LL

and 50-316/89-04 for Unit 2 dealt with the

same

problem.

Although the problem of safety valve setpoint drift

caused

a repeated

TS violation, the licensee's

complete

disassembly,

and inspection of the failed valves found no cause for

the setpoint drift.

Also, the licensee's

evaluation

has

found

that there

was

no safety significance

from the setpoint drift

since,

in the event of an overpressure

transient,

the safety

valves would still have limited the peak transient

pressure

to

0

2659 psig.

This is below the

TS safety limit of 2735 psig.

In

addition,

the licensee

properly reported

the event

and took

appropriate corrective actions.

Therefore,

pursuant to the

NRC

enforcement

policy (10 CFR 2, Appendix C), the

NRC is exercising

enforcement discretion for this matter,

and

no Notice of Violation

will be issued.

Two'on-cited violations were identified.

No deviations,

unresolved

or

inspector followup items were identified.

Re ortable

Events

92700

92720

The inspector

reviewed the following Licensee

Event Reports

(LERs)

by

means of direct observation,

discussions

with licensee

personnel,

and

review of records.

The review addressed

compliance to reporting

requirements

and,,as

applicable,

that immediate corrective action

and

appropriate

action to prevent recurrence

had

been

accomplished.

Closed

LER 315 92010-LL: Hissed Surveillance

Due to the

Use of

Obsolete

Documentation

in Su

ort of Thermo-La

330 Ins ection:

The licensee

submitted this

LER because

they had determined, that

a

section of Thermo-Lag

330 which enclosed

a conduit in the Unit 2

blowdown-flash tank area

had not been

included in the survei~lance

p'rogram for fire barriers

as required

by Technical Specification

3/4.7. 10.

However, further review by the licensee

found that this

particular conduit did not need to have this fire barrier protection.

Two modifications

(12-2900-B.04

and 12-3053)

had provided redundant

indications which were routed through different fire zones.

Therefore,

the licensee

determined, that they

had not violated the

TS requirements

and retracted

LER 50-315/92010.

No violations, deviations,

unresolved

or inspector followup items were

identified.

Re ion III Re uests

92705

TI 2500 028:

Em lo ee Concerns

Pro ram:

Ttle objective of this TI was to determine

the characteristics

of the

licensee's

program to provide employees

an alternate

path from their

supervisor or normal line management

to express

safety concerns.

Additionally, this type of program would encourage

people to come

forward with their concerns

without fear of retribution.

The inspector

noted that the licensee

had just recently

implemented

the program that

met this objective; therefore,

the inspector

was unable to determine

the

effectiveness

of the program at this time.

The licensee

implemented their Human Performance

Improvement

System

(HPIS) in March 1993.

The licensee

designed

the program to supplement

and build upon the current plant corrective action program

by pro-

actively identifying precursor

events

which are indicative of

10

~

potentially significant problems.

The licensee

modeled the program

after the

INPO HPES program

and provided

an alternate

vehicle for plant

personnel

to raise safety issues.

The

Human Performance

Analyst (HPA),

reporting directly to the Safety

and Assessment

Manager,

manages

the

program.

Plant personnel

report potential

safety

issues

by filling out forms

located throughout the plant or calling the in-plant

"Human Performance

Hot-Line."

Personnel

may provide

anonymous reports,

and also

may keep

their identity from being revealed, if requested.

The HPA,was currently

conducting meetings with plant personnel

to inform them of the program,

and enhancements

to the program were also reported

by bulletin board

postings

and in the plant newsletter.

To provide

an incentive for

reporting issues,

the licensee publicly recognized

individuals who made

significant contributions

on bulletin board postings.

The licensee

was

also considering

awards for future incentive.

The

HPA followed up on issues

identified with help from cognizant plant

personnel,

as

needed.

The licensee

was currently developing procedural

guidelines for evaluating

and trending the issues identified.

In

addition,

the licensee

had not yet established

specific goals to measure

the effectiveness

of the program.

No violations, deviations,

unresolved

or inspector followup items were

identified.

Nana

ement Interview:

The inspectors

met with licensee

representatives

denoted

in paragraph

I

on October

25,

1993, to discuss

the scope

and findings of the

inspection.

In addition,

the inspector

also discussed

the likely

informational content of the inspection report with .regard to documents

or processes

reviewed

by the inspector during the inspection.

The

licensee

did not identify any such

documents

or processes

as

proprietary.

l'