ML17289A260

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Insp Rept 50-397/91-42 on 911104-1206.Violations Noted.Major Areas Inspected:Evaluation of Ability of SGTS to Perform Safety Function
ML17289A260
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 01/03/1992
From: Johnson P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML17289A257 List:
References
50-397-91-42, NUDOCS 9201220090
Download: ML17289A260 (20)


See also: IR 05000397/1991042

Text

U.S.

NUCLEAR REGULATORY COMMISSION

REGION V.

Report No:

Docket No:

Licensee:

Facility Name:

50-397/91-42

50-397

Washington Public Power Supply System

P.O.

Box 968

Richland,

WA 99352

Washington Nuclear Project

No.

2

(WNP-2)

Inspection

Conducted:

November

4 - December

6,

1991

Inspector:

Approved by:

~ummar:

K. E. Oohnston,

Project Inspector

nson,,

ie

React

Projects Section

3

te

)gne

ection on November

4 - December

6

1991

Re ort No. 50-397 91-42

~td:

Th h'l

f th

l

p tl

t

p

f

l tl

of the ability of the standby

gas treatment

system

(SGTS) to perform its

safety function.

To support this evaluation,

the inspector performed

a system

walkdown in accordance

with inspection

procedures

71710.

Inspection

procedures

36800;

61700,

and 62700 were also used.

Safet

ssues

Mana ement

S stem

SIMS

Items:

None.

~esul ts:

Gene} al Conclusions

and

S ecific Findin

s

~Stree ths:

The inspector found the system condition and lineup accept-

able,

the system engineer

knowledgeable of the system

and its current

condition, operators

knowledgeable of system operations

and following

applicable operating procedures,

and with minor exceptions,

surveillance

and operating

procedures

up to date

and well written.

h

h <<:

Th

l

p t

tdl t

l t

thtt hl

tions were not thorough.

Paragraph

4.a of this report describes

a

Problem Evaluation Request

(PER) which addressed

a surveillance test of

the

SGTS heaters.

This

PER did not address

the potential of heater

damage

which might have resulted

from operation at higher voltages.

Paragraph

4.b describes

a design

change to allow greater

SGTS fan flow.

The analysis

supporting the design

change did not thoroughly address

the

capability of the

SGTS fan motors to support this change.

920i220090 920i03

PDR

ADOCK 05000397

8

PDR

~

'

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0

f

-2-

In both instances,

the licensee

was able to show that the equipment

could

continue to perform its design function.

However, in each

case,

the

design margins were considerably

reduced.

.Si nificant Safet

atters:

none

Summar

of Violations and Deviations:

One violation was identified

regarding the failure to follow the procedure

implementing the

requirements

contained in 10 CFR 50.59 (paragraph 4.b).,

0 en

tems

Summar

One new enforcement

item was opened

and one previous

enforcement

item was closed.

l

0

N

I

gETlgLS

1.

ersons

Contacted

Washin ton Public Power

Su

1

S stem

l

  • A. L. Oxen,

Deputy Managing Director

  • J.

W. Baker,

Plant Manager

  • R. L. Webring, Plant Technical

Manager

  • A. G. Hosier, Licensing Manager
  • W. S. Davison,

Plant guality Assurance

Manager

  • J. F. Peters,

Plant Administrative Manager

.

  • D. J; Pisarcik, Assistant'ealth

Physics

and Chemistry Manager

  • C. L. Fies,

Compliance

Engineer

  • B. E..Pesek,

Plant Technical

Supervisor,

Balance of Plant

J.

V. Hanson,

Plant Technical

Lead Engineer,

Balance of Plant

  • J.

E. Bekhazi,

Plant Technical

Engineer,

Balance of Plant

  • L. D. Sharp,

Plant Support Engin'eering,

Principal

Engineer

W. D. Bainard,

Plant Support Engineering

uclear

Re ulator

Commission

  • P.= L.'ng, Project Manager,

NRR

The inspector also talked to other licensee

employees

during the course

of the inspection.

"<<Attended the Exit Heeting

on December

6,

1991.

2.

Standb

Gas Treatment

S stem

SGTS

Walkdown

The objective of the inspection

was to perform an evaluation of the

ability of the

SGTS to perform its safety function.

To support this

evaluation,

the inspector did the following:

system

walkdown in accordance

with NRC Manual Chapter

71710

system

walkdown with the Plant. Technical

system engineer

observation of system operations

and review .of operating procedures

review of surveillance

procedures

review of scheduled

maintenance,

selected

maintenance

procedures,

and vendor manuals

review of system description contained in the Final Safety Analysis

Report

(FSAR), training material,

and other design basis

documents

C

In summary,

the inspector found:

the system condition and lineup were acceptable,

e

'

-2-

the system engineer

was knowledgeable of the system

and its current

condition,

, operators

were knowledgeable of system operations

and were following

applicable operating procedures,,

  • 'ith minor exceptions

di'scussed

below, surveillance

and .operating.

procedures'were

up to date

and well written.

During the review of the annunciator

response

procedures

for the

SGTS

panels

(4.827.KI), the inspector noted that one of the steps for an

annunciator

window did not make

sense

(Window 4-1, step

5 and 6).

The

inspector pointed this out to the licensee

who acknowledged

the error and

committed to change the procedure.

The inspector

found two instances

wherein engineering

work was 'less

than

rigorous.

These

examples,

one-regarding

the review of an out-of-specifi-

cation surveillance test

and th'e other regarding

a design

change,

are

discussed

in section.4 of this report.

To support the discussion

in

section 4, it was necessary

to provide the following brief system

description.

3.'GTS Descri tion

The

SGTS was designed to limit the release

of airborne radioactive

contaminants

from the secondary

containment

(the reactor building) to

atmosphere

following a design basis accident.

In additi.on, the system

was designed to enable

purging of the primary containment

through the

SGTS filters when airborne radiation levels inside the, primary contain-

ment are too high to permit direct purging to atmosphere.

The system is

required

by the Technical Specifications

(TS) to be operable

in Nodes I,

2,

and

3 and during refueling operations.

The system

was designed

to

remove

99 percent of iodides

and particulates.

The

SGTS is composed of two .full-capacity filter trains, originally sized

to provide

a reactor building pressure,

under design basis conditions,

0.25 inches of water

gage (w.g.) lower than atmospheric pressure.'ach

filter train consist of the following:

a moisture separator,

a prefilter, two high efficiency particulate-

air (HEPA) filters, and two 4" deep

banks of impregnated

charcoal

adsorber filters,

two banks of electric blast coil heaters,

rated at 20.7

kW each at

460V, provided to limit the relative humidity of the incoming air to

-70 percent,

and

two full-capacity centrifugal fans,

powered from separate vital 480V

buses.'he

SGTS will automatically initiate on high drywell pressure,

reactor

vessel

low water level,

and high radiation level in the reactor building

exhaust air plenum.

With an automatic actuation,

reactor building intake

valves,

fan intake valves,

and

SGTS discharge

valves to the elevated

0

Jl

t',

-3-

release

duct will open

and

one of the electric heaters will energize.

Following a 10-second

delay,

one fan on each train will start.

If it

does not operate

successfully

(achieve

a flow of 500 cfm), the second

fan

and electric heater will start.

System flow is controlled to maintain building pressure

negative with

respect to atmosphere

and is limited to a maximum flow.

The differential

pressure

is measured

on the four sides of the reactor build>ng at the

572'evel

(the reactor building basement

is at 422'nd the refueling

floor is at 606').

System flow is measured

by annubars

at the fan

.discharge.

It was recognized

in 1989 that by controlling the reactor building to

-0.25" w.g. with monitors

on the 572'evel, it would not be possible to

maintain pressure'negative

with respect to atmosphere

at all locations.

To achieve -0.25" w.g. in all locations,

the licensee

determined through-

tests

and calculations that building, pressure

ne'eded to be controlled to

-1.7" w.g. using the monitors

on the 572'evel.

It. was.noted that the

licensee

has led the industry in the study of atmospheric effects

on

reactor building differential pressures.

To establish

a more negative building pressure,

the

SGTS fans'pper

flow

limit was increased

from 4457 cfm (as measured

by a discharge

flow

annubar)

to 5600 cfm.

The issue

was discussed

by the licensee in a

Justification for Continued Operation

(JCO)

and was the subject of

Licensee

Event Reports

(LERs) 89-40

and 89-40, Revision

1 (dated. June

19,

1990).

4.

~indin

s

a.

Electric Heaters

0 crated at Hi

h Volta e Durin

Surveillance

~Testin

On April 15,

1991, shortly after plant shutdown for the

a refueling

outage,

a surveillance test

was performed

on

SGTS heaters

to measure

whether their heat generation

was

i'n compliance with the TS.

On two

heaters,

heat'generation

was found to be higher than the

TS limit.

This was

due to a high bus voltage condition.

To evaluate the con-

'ition and initiate corrective action,

a Problem Evaluation Request

(PER)

was initiated.

The inspector

reviewed the

PER (No. 291-250)

and found the following

weaknesses:

The actions

taken were poorly documented,

The review did not adequately

address.

whether the heaters

had

been

damaged,

and

The review did not address

whether the heaters

could operate

in

all voltage conditions

and still meet

TS requirements.

']

I

III

i

l

f

4

-"

escri tion of the Surveillance

and

P

R

TS surveillance 4.6.5.3.d.4

requires that every

18 months the

licensee verify that the

SGTS heaters

dissipate

20.7

+ 2. 1

kW.

TS

surveillance

procedure

TSS 7.4.6.5.3.4

was performed

on April 15,

1991 to meet this

TS requirement.

The'methodology of TSS 4.6.5.3.d.4

was to measure

the line current

and phase-to-phase

voltage of each of the nine heater coils which

make

up each heating unit.

The product of the current

and voltage,

cor rected for the coil configuration (three sets of coils wired in

delta) provided heat dissipated

in watts.

The measured

heat dissipation

was

as follows:

SGT-EHC-1A1

23.12

kW

(SGTS train A; Division

1 power supply)

SGT-EHC-1A2

-

22.21

kW

(SGTS train A; Division 2 power supply)

SGT-EHC-181

23.82

kW

(SGTS train B; Division

1 power supply)

SGT-EHC-1B2

22.79

kW

(SGTS train B; Division 2 power supply)

The heat dissipation

on SGT-EHC-1A1 and 1Bl were above the

TS limit

of 22.8

kW.

These results

could have

been anticipated.

Bus voltage

conditions,

as might be expected

during an outage,

were higher than

during normal operations

due to the reduced

bus loading.

Voltage

supplied to the heater cabinets

was measured

to be

9X higher than

nominal voltage

(460V).

Due to the exponential

relationshi,p

between

voltage

and power which exists in resistive loads

such

as heaters,,

the heat generation

was approximately

20X greater

than would have

been

expected

at 460V,

on which the 20.7

kW power rating was based.

The licensee initiated

PER 291-250 to address this issue.

The

surveillance

procedure

was revised to change

the methodology for

calculating heat dissipation.

Essentially,

the actual

heat output

was normalized to what would have

been expected

had the voltage at

the'eaters

been

460V.

The normalized heat outputs 'for SGT-EHC-1Al

and

1B1 were calculated to be 19.5 and 20.1 respectively.

Based

on

these results,

the licensee

concluded that the

TS surveillance

requirement

had been met,

and the

PER was closed.

Problem Evaluation

Re ort Documentation

The review and resolution of this issue

were not well documented

in

PER 291-250.

The Management

Review Committee

(MRC); which reviews

all

PERs,

selected

as the problem resolution method

"NONE/CLOSE

PER."

The comments section provided the details of the resolution:

"High bus voltage is normal

on plant shutdown.

Equip. previously

evaluated

in LER [Licensee

Event Report] to withstand high voltage.

This has

been evaluated

by compliance

and found to be acceptable.

Closed with the

PDF [Procedure-Deviation

Form] already written."

t

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,(

1

Weaknesses

noted in this evaluatio~'ere:.

The

PER referenced

an

LER as supporting the ability of the

heaters

to withstand high voltages.'t

did not provide

an

LER

number or maximum high voltage allowed.

When questioned,

the

licensee

could not produce the supporting

LER.

The

PDF number

and date were not provided, nor was the date the

surveillance

was performed.

These

documents

were subsequently

retrieved

by the inspector.

The

HRC resolution

was misleading;

the

PDF was the resolution

method.

The lack of thorough documentation of the problem and path of

resoluti.on

appears

to have contributed to

a less

than thorough

technical

review as discussed

below.

The inspector discussed

these

weaknesses

with the licensee

at the exit meeting.

The licensee

committed to reopen the

PER and address this issue.

Haximum Heater

ut ut

The licensee

had not performed

an adequate

review of the ability of

the heaters

to withstand heat dissipation in excess of their TS

limit.

This demonstrated

an incomplete review of the technical

issues

raised

by the failed surveillance test.

The

TS surveillance

acceptance

criteria provide

10X allowance

above

and below the 20.7

kW rating of the heaters.

The 20.7

kW, according

to design

documents,

was

based

on 460V supplied to the heaters.

The

licensee

stated that the

IOX rating was typical of heaters.

The measured

output on one heater

was 23.8

kW, or 15X greater than

the design rating.

The inspector

questioned

whether this could have

damaged

the heater.

After discussions

with the vendor regarding

these

heaters,

the lice~see

found that under low flow conditions

a

watt density of 60 W/in

would have

been acceptable.

Higher watt

densities

could reduce the life of the heaters

or, if substantially

higher,

damage

the heaters.

The lic~nsee determined that 23.8

KW

provided

a watt density of 56.7 W/in, and concluded that the

heaters

were not damaged

(20.7

KW provides 49.3 W/in ).

The licensee

should

have included

an engineering

review of the

acceptable

watt density effects

on the heaters

in the resolution of

the

PER.

In this case,

the heaters

had additional margin.

0 eration of the Heaters

Under All Desi

n Conditio

s

Operation of the heaters

at elevated

voltages

does not appear to

have

been considered

in the plant design.

This point should

have

been recognized during the review of PER 291-250.

A complete review

should

have considered

the maximum voltage condition at which the

heaters

would be expected

to operate.

~

hl

k

t

Licensee

procedure

TSS 7.4.8.3.2,

which required that

bus voltages

be measured

on

a weekly basis,

allowed

a maximum voltage at the

bus

of 520 V. If a surveillance test found that

a heater dissipated its.

maximum acceptable

output of 22.8

KW at 460 V,'his heater

would

operate at a watt density (~ccording to calculations

performed

by

the inspector) of 69.3 W/in

at 520 V.

According to vendor data,

this worst case situation could result in heater degradation.

onclusion

The licensee's

disposition of PER 291-250

was not rigorous in either

technical

or administrative

aspects.

In this case,

adequate

margin

existed to prevent equipment

damage.

The licensee

committed at the exit meeting to reopen,

PER 291-250 and-

address

the issues

discussed

above.

SGTS

an Motor

oadin

The inspector reviewed the design

change

which allowed the

SGTS fans

to provide

up to 5600 cfm.

The inspector found that the design

change did not adequately

consider

whether the installed fan motors

could operate

the fans at the greater

flow under all design

conditions.

In response

to this finding, the licensee

determined

that under worst case conditions,

the nameplate rating of the fan

motor and the full load current would be exceeded.

However, tak'ing

into account the fan motor service factor and the size of the fan

motor overload device,

the licensee

concluded that the fans would

operate

under the conditions described

in their Justification for

Continued Operation

(JCO) regarding the

SGTS, discussed

in LER

89-40, Revision l.

As discussed

in the Section 3,

"System Description," the upper flow

limit of the

SGTS fans

was raised

from 4457 to 5600 cfm in 1989 to

provide

a. greater

reactor building negative pressure.

To accomplish

this change,

the flow limiter setpoints for all four fans

(SGT-LNTR-

lA1, 1A2,

1B1,

and

1B2) were revised

by Instrument Setpoint

Change

Request

ISCR 952.

The design

change

review,

documented

in a

10 CFR 50.59 evaluation,

concluded the following:

The charcoal

residence

time remained within Regulatory

Guide

1.52 requirements,

Differential pressure

across

the

HEPA filters was within the

manufacturer's

tolerances,

and

The heaters

could maintain relative humidity less than

70X.

The evaluation fu'rther stated that

"Ho other elements of the design

are considered

impacted

by the reliance

on the higher than design

flow rate for a single. SGT train."

To support this conclusion,

a test

was performed for fan SGT-FN-1A1

which found:

'I

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l

tl

Motor current to be 25.5

amps at 5600 cfm

  • ,

Leakage tests

and adsorption tests to be with specification

The inspector determined that the licensee

should

have considered

the following design basis

par ameters,

each of which could have

affected the maximum current drawn by the

SGTS fan motors:

~ddV1t:

C

t

qd

t

i

i tl

motors

under

degraded

voltage conditions.

The licensee

stated

that the design basis

degraded

voltage condition for the moto'rs

was 405

V and determined that this would increase

current draw

by 13.6X.

nstrument

Inaccuracies:

The overall inaccuracy of the flow

controllers

was

10X.

Testing performed

on June

5,

1991, in

accordance

with TS 4.6.5.3.2.d.l,

which requires verification

of system flow, found that for one of the fans the-actual

flow

was

9X greater

than the controller setting.

Cold Buildin

Tem eratu

s:

The fan performance

curves

were

established

for a building temperature of 104'.

A reduction

in building temperature

provides

a proportional

increase

in air

density

and motor amps required to move the

same

volume of air.

A 5'emperature

drop corresponds

to a

1X increase

in the motor

current requirement.

The difference in temperature

between the

performance

curves

and the minimum'building temperature

of,

50'

increases

current requirements

by 11X.

In response

to the inspectors

concerns,

the licensee

performed

a

calculation which considered

these three factors.

The results

indicated that under the worst-case

conditions,

motor current would

not trip the thermal overload devices.

The licensee

factored into

their analysis

the effects of low ambient temperature

on the

set~oints of thermal

overload trip devices.

These devices,

rated at

104

F, trip at higher currents at lower ambient temperatures.

The calculation performed

by the licensee

assumed

a maximum steady

state

SGTS fan flow of 5075 cfm versus the flow limiter setpoint of

5600 cfm.

This was

based

on actual

performance

tes'ts

completed in

September

1991.

These tests

concluded that to maintain the required

negative pressure,

full system flow (5600 cfm) would not be

required.

A factor in the tests

was that actual air leakage into the reactor

building (1475 cfm) was substantially less than the maximum leakage

the

TS allow (2240 cfm). 'he licensee's

JCO, discussed

in LER

89-40,

Revision

1, supported

the use of lower reactor building air

leakage.

The

LER stated that air leakage into the reactor building

would be limited to 1475 cfm until the reactor building negative

pressure

issue could be completely resolved.

~

i

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Incom lete Desi

n Chan

e

Revising the

SGTS flow requirement

from 4457 cfm to 5600,cfm was

a

design

change

implemented

by ISCR 952.

The change

included

an

.

"unreviewed safety question" evaluation required by 10 CFR 50.59.

These evaluations

are governed

by licensee

procedure

PPH 1.3.43..The

evaluation did not consider the ability of the .fan motor to operate

the fan at the higher flow under all design basis conditions.

These

conditions included degraded

voltage,

instrument inaccuracies,

and

the effects of building temperature.

The failure to consider

these

conditions in the evaluation is an apparent'iolation

(Enforcement

Item 91-42-01) .

5.

ollowu

on 0 en

tems

The inspector

reviewed the actions taken

by the licensee

in response

to

the Notice of Violation,(NQV) tr'ansmitted with Inspection

Report

No.

91-24

and found them to be acceptable.

The

NOV addressed

the licensee's

failure to initiate a

PER to address diesel-starting air system high

'ressures.

The licensee's

root cause evaluation

and corrective actions

were discussed

in letters dated

October

14,

1991

and October 28,

1991.

In addition, the licensee's

commitment'o

improvements

in the Plant

Technical

system engineering

program,

discussed

in their October

14,

1991

letter,

were reviewed

and found to be appropriate.

Enforcement

Item 50-

397/91-24-01 is closed.

S.

~iN

An exit meetings

was conducted

on December

6,

1991, with the licensee

representatives

identified in Paragraph

1.

The inspector

summarized the

inspection

scope

and findings as described

in the Results section of this

report.

The licensee

did not identify as proprietary

any of the information

provided to or reviewed

by the inspector during this inspection.

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