ML17221A615

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Insp Repts 50-335/87-25 & 50-389/87-24 on 871101-1205.One Violation Noted.Major Areas Inspected:Tech Spec Compliance, Operator Performance,Overall Plant Operations,Qa Practices, Station & Corporate Mgt Practices & Refueling Activities
ML17221A615
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 01/11/1988
From: Bibb H, Christensen H, Crlenjak R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17221A611 List:
References
50-335-87-25, 50-389-87-24, NUDOCS 8802100324
Download: ML17221A615 (8)


See also: IR 05000335/1987025

Text

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UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30323

Report Nos.:

50-335/87-25

and 50-389/87-24

Licensee:

Florida Power and Light Company

9250 West Flagler Street

Miami, FL

33102

Docket Nos.:

50-335

and 50-389

License Nos.:

DPR-67 and NPF-16

Facility Name:

St.

Lucie j. and

2

Inspection

Conducted:

November

1 - December

5,

1987

Inspector:

r en'

en>or

es>

en

nspec or

oS0-

~

.

>

,

es>

en

nspector

Approved by: 7W8&

r)s ensen,

ec

>on

>e

c >ng

Division of Reactor Projects

/ /i P'

e

~gne/'s

a

e

>gne

e

cygne

SUMMARY

Scope:

This inspection

involved on site activities in the areas of Technical

Specification

compliance,

operator

performance,

overall

plant operations,

quality

assurance

practices,

station

and

corporate

management

practices,

corrective

and

preventive

maintenance

activities, site security procedures,

radiation

control

activities,

surveillance

activities,

and

refueling

activities.

Results:

Of the areas

inspected,

one violation was identified (paragraph

7)

8S0"1003

4 Seoli4

PDR

ADQC)( 05000335

G

PDR

REPORT DETAILS

Person

Contacted

Licensee

Employees

K. Harris, St.

Lucie Vice President

"G.

J

~ Boissy, Plant Manager

R. Sipos,

Services

Manager

.

~J.

H. Barrow, Operations

Superintendent

T.

A. Diliard, Maintenance

Superintendent

J.

B. Harper,

gA Superintendent

J.

West, Operations

Supervisor (Acting)

R. J. Frechette,

Chemistry Supervisor

C.

F.

Leppla,

I8C Supervisor

CD

A. Pell, Technical Staff Supervisor

E. J. Wunderlich,

Reactor

Engineering Supervisor

H.

F.

Buchanan,

Health Physics

Supervisor

W. White, Security Supervisor

"C.

L. Burton, Reliability and Support Supervisor

J,

Barrow, Fire Prevention

Coordinator

R.

E.

Dawson, Assistant Plant Superintendent

- Electrical

C. Wilson, Assistant Plant Superintendent

- Mechanical

"N.

G.

Roos, guality Control Supervisor

Other licensee

employees

contacted

included technicians,

operators,

mechanics,

security force members

and office personnel.

"Attended exit interview

Exit Interview

The inspection

scope

and findings were

summarized

on

December

21,

1987,

with

those

persons

indicated

in paragraph

1

above.

The

inspectors

described

the

areas

inspected

and

discussed

in detail

the inspection

findings listed below.

Dissenting

comments

were not received

from the

licensee.

Violation 50-335/87-24-01:

Entry into an operational

mode without meeting

the conditions of LCO 3. 6. 6. 2 being met.

The licensee

did not identify as proprietary any of the materials

provided

to or reviewed by the inspectors

during this inspection.

Plant Tours (Units

1 and 2)

The inspectors

conducted

plant tours periodically during the inspection

interval to verify that monitoring equipment

was

recording

as required,

4.

equipment

was properly tagged,

operations

personnel

were

aware of plant

conditions,

and plant

housekeeping efforts were adequate.

The inspectors

also

determined

that

appropriate

radiation

controls

were

properly

established,

critical clean areas

were being controlled'in accordance

with

procedures,

excess

equipment

or material

was

stored

properly

and

combustible

materials

and debris

were disposed of expeditiously.

During

tours,

the inspectors

looked for the existence

of unusual

fIuid leaks,

,

piping vibrations,

pipe'anger.

and seismic restraint settings,

various

valve

and breaker positions,

equipment caution

and danger tags,

component

. positions.

adequacy of fire fighting equipment,

and instrument calibration

da'tes.

Some tours were conducted

on backshifts.

The

inspectors

routinely conducted

partial

walkdowns of

ECCS

systems.

Valve,

breaker/switch

lineups

and

equipment

conditions

were

randomly

verified both locally

and in the control

room.

During the inspection

period

the

inspectors

conducted

a complete

walkdown in the accessible

areas

of the Unit 1 component cooling water and emergency

diesel

generator

systems,

and Unit 1 and

2 chemical

and

volume control

system to verify

that

the

lineups

were

in accordance

with licensee

requirements

for

operability

and

equipment

material

conditions

were

satisfactory.

Additionally,

flowpath verifications

were

performed

on the following

systems:

emergency

diesel

generator

fuel oil and air start

and auxiliary

feedwater.

Plant Operations

Review (Units

1 and 2)

The inspectors,

periodically during the

inspection

interval,

reviewed

shift logs

and

operations

records,

including data

sheets,

instrument

traces,

and

records

of equipment

malfunctions.

This

review included

control- room logs

and auxiliary logs, operating orders,

standing orders,

jumper

logs

and

equipment

tagout

records.

The

inspectors

routinely

observed

operator

alertness

and

demeanor

during plant tours.

During

routine

operations,

operator

performance

and

response

actions

were

observed

and

evaluated.

The

inspectors

conducted

random off-hours

inspections

during the reporting interval to assure

that operations

and

security

remained

at

an acceptable

level.

Shift turnovers

were observed

to verify that they were

conducted

in accordance

with approved

licensee

procedures.

The inspectors

performed

an in-depth review of the following

safety-related

tagout (clearances):

Unit 1

1-11-43

lA INSTRUMENT AIR COMPRESSOR-"PM

1-11-46

PM ON FAN HVE 6B

1-11-47

1B DIESEL GENERATOR SOAKBACK PUMPS

Unit 2

2-11-363

FUEL HANDLING BUILDING FAN HVS-7

PM

2-11-380

2A INTAKE COOLING WATER PUMP STRAINER

s.

Technical Specification

Compliance (Units 1 and 2)

During this reporting interval,

the inspectors

verified compliance with.

limiting conditions

for operations

(LCOs)

and

results

of -selected

surveillance

tests. 'hese

verifications

were

accomplished

by direct

observation

of monitoring

instrumentation,

valve

positions,

switch

positions,

and

review of completed

logs

and records.

The licensee's

compliance

with

LCO action

statements

were

reviewed

on selected

occur-'ences

as they happened.

Maintenance

Observation

Station

maintenance

activities of se'lected

safety-related

systems

and

components

were observed/reviewed

to ascertain that they were conducted

in

'accordance

with requirements.

The following items were considered

during

.

this review; limiting conditions for operations

were met, activities were

accomplished

using

approved

procedures,

functional tests

and/or calibra-

tions

were performed prior to returning components

or systems to service;

quality control

records

were maintained;

activities were accomplished

by

qualified personnel;

parts

and materials

used were properly certified; and

radiological controls

were

implemented

as

required.

Work requests

were

reviewed

to determine

status

of outstanding

jobs

and to assure

the

priority was

assigned

to safety-related

equipment.

The

inspectors

observed portions of the following maintenance activities:

Unit 1

PWO

0830

PWO

1789

PWO

2000

1B FIRE PUMP--REPAIR

PM--1A CHARGING PUMP ACCUMULATOR

PM--1B AUXILIARYFEEOWATER

PUMP

Unit 2

PWO 6689

QUARTERLY CALIBRATION--EXCORE NEUTRON FLUX MONITOR

Review of Nonroutine Events

Reported

by the Licensee

(Units

1 and 2)

The following Licensee

Event

Reports

(LERs) were

reviewed for potential

generic

impact,

to detect

trends,

and to determine

whether 'corrective

actions

appeared

appropriate.

Events which were reported

immediately were

also

reviewed

as

they occured to determine that technical specifications

were

being

met

and that

the public health

and safety

were of upmost

consideration.

The following LERs are considered

closed:

Unit 1

LER 87-15

dated

November 16,

1987.

This

LER describes

an event

which

occured

on October 14,

1987,

whereby Unit 1 operators

violated Technical

Specification

(TS)

3. 0.4

by entering

Mode 4 from

Mode 5 without the

requirements

of TS 3.6.6.2,

Shield Building Integrity, being met.

Several

administrative failures occurred which are not in keeping with the

usual

standards

of the

St.

Lucie's operations

staff and appear

to

be

indicative of a recent

trend toward laxity in attention to detail.

-The

sequence

of events

went thusly:

On October 13, St.

Lucie 1 was in Mode

5

preparing

to enter

Mode 4.

The

Mode change

requires

completion of a

Pre-startup

Checkoff List,

Step

8.3.11 of which

has

a sign-off for

completion of Data

Sheet ¹3,

Containment

and Shield Building Integrity.

Early

on October 14,

the

operators

completed

Data Sheet ¹3 (or it is

assumed

so)

and signed off Step 8.3.11.

Later that

same

day, after

a

shift

change

and during

review of the Pre-start

Checkoff List,

the

completed

copy of Data

Sheet

¹3 could not be

found.

(First example of

inattention

to detail).

The Assistant

Nuclear Plant Supervisor

(ANPS)

directed that another

Data Sheet ¹3 be completed.

A non-licensed

operator

completed

Data Sheet ¹3, with one exception;

he

found the

West Shield Building access

door open,

and so, did not initial

the sign-off space.

The operator

turned the data

sheet

in without the

sign-off and with no explanatory

note

nor any discussion

with the

ANPS

(second

example of inattention to detail).

The

ANPS reviewed the data sheet

and did not notice the unsigned

space for

the

West Shield Building door (third example of inattention to detail).

At 1521

on October 14, Unit 1 entered

Mode 4.

At 2355, while attempting

to perform

a monthly surveillance

on the shield building ventilation

system,

the West Shield Building door was found open.

This is a violation

of Unit 1 Technical Specification

3. 0.4 (50-335/87-24-01).

Several

opportunities

for detection

existed

which could

have prevented

this

occurrence,

but were

missed

through

a lack of thoroughness

in

performing/reviewing

operations.

Other

examples

of this over the past

several

months

which

may indicate

a trend

are (a) loss of component,

cooling

water train

independence

for several

days

due to

improper

implementation of and recovery

from an equipment clearance

(ref. inspec-

tion report

50-335/87-14),

(b) electrical

misalignment

of condensate

pumps,

causing

a reactor trip (ref. inspection report 50-335/87-21),

(c)

misalignment of fuel handling building ventilation (ref. inspection report

50-335/87-10),

and

(d)

improper rigging during lifting of the incore

instrument plate,

causing

damage

to the plate (ref. inspection report

50-389/87-20).

Unit 2

LER 87-16 -- reactor trip due to loss of condensate

pump due to inadequate

procedure (ref. inspection report 50-335/87-21).

Other plant

events

occurred

during the

inspection

period

which will,

generate

LER's.

On Wednesday,

November 25, with Unit 2 at 50X power for

physics testing following the refueling outage,

the reactor tripped due to

a generator

lockout and turbine trip.

The generator

lockout was caused

by

the

Permanent

Magnet Generator

(PMG) going to ground,

which was caused

by

the ¹9 turbine

generator

bearing failing.

All reactor safety

systems

5

performed

normally.

On Saturday,

November 28, while preparing to return

Unit 2 to power following the

PMG repairs,

a fire was discovered

on the

2Al Reactor

Coolant

Pump

(RCP) at

10: 10 a.m.

At 10:23

a.m.

an unusual

event

was

declared

and the

necessary

notifications were

made.

The fire

team

was

immediately mobilized

and all flames were extinguished

by 10:30

a.m.

All affected

lagging

was

removed

and

the

unusual

event

was

terminated

at

12: 20

p. m., approximately

two hours after declaration.

The

fire was

caused

by oil which had dripped onto a

RCP support lug.

The oil

source

was

found to be

a loose

packing nut on

an isolation valve for a

local

pressure

indicator at

the discharge

of the

RCP oil lift pumps.

Further investigation

also revealed

a hole in a oil collection pan which

had

been installed for fire prevention

purposes.

The necessary

repairs

and testing

were performed,

the other RCP's

were inspected,

and the unit

was returned to power on Wednesday,

December

2.

Physical

Protection (Units 1 and 2)

The inspectors verified by observation

and interviews during the reporting

interval

that

measures

taken

to assure

the physical

protection of the

facility met current requirements.

Areas inspected

included the organiza-

tion of the security force,

the establishment

and

mainte'nance

of gates,

doors

and isolation

zones

in the proper conditions,

that access

control

and badging

was proper,

and procedures

were followed.

Surveillance

Observations

During the inspection period, the inspectors verified plant operations

in

compliance

with selected

Technical

Specifications

(TS)

requirements.

Typical of these

were confirmation of compliance with the

TS for reactor

coolant

chemistry,

refueling water tank,

containment

pressure,

control

room ventilation

and

AC

and

DC electrical

sources.

The

inspectors

verified that

testing

was

performed

in

accordance

with

adequate

procedures,

test

instrumentation

was calibrated,

limiting conditions for

operations

were met,

removal

and restoration of affected

components

were

accomplished,

test results

met requirements

and were reviewed by personnel

other that

the individual directing the test,

and that any deficiencies

identified during

the testing

were properly

reviewed

and resolved

by

appropriate

management

personnel.

The inspectors

observed

the following

surveillance

(s):

Unit 1

1-0030151

1-0120026

1-1120050

REMOTE

SHUTDOWN

MONITORING

INSTRUMENTATION PERIODIC

CHANNEL CHECK

REACTIVITY--DEVIATIONFROM DESIGN

AREA RADIATION SYSTEM PERIODIC TEST

Unit 2

2-0410050

HPSI/LPSI

PERIODIC TEST

2-0420050

CONTAINMENT SPRAY

AND IODINE REMOVAL SYSTEM PERIODIC

TEST