ML17221A630

From kanterella
Jump to navigation Jump to search
Insp Repts 50-335/87-31 & 50-389/87-30 on 871206-880102. Violation Noted.Major Areas Inspected:Tech Spec Compliance, Operator Performance,Overall Plant Operations,Qa Practices, Station & Corporate Mgt Practices & Security Procedures
ML17221A630
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 02/09/1988
From: Bibb H, Christensen H, Crlenjak R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17221A628 List:
References
50-335-87-31, 50-389-87-30, NUDOCS 8802220005
Download: ML17221A630 (7)


See also: IR 05000335/1987031

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

'l01 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30323

Report Nos.:

50-335/87-31

and 50-389/87-30

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

Inspectors:

r enga

enlor

sl dent

nspector

Approved by:

.

8

b,

esl ent

spector

H.

rlstensen,

ection

C lef

c lng

Division of Reactor Projects

Facility Name:

St. Lucie

1 and

2

Inspection

Conduct

.

December

6,

1987 - January

2,

1988

te

1 gne

2

'F 8P

ate

lgne

5'N

a

lgne

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,

and surveillance activities.

Results:

Of

the

areas

inspected,

one

violation

was

identified.

50-335/87-31-01,

Failure to implement

procedure

1-0970020,

Operation of the

120Y Instrument

AC System

(Class

1E).

8802220005

880209

PDR

ADOCK 05000335

0

DCD

REPORT DETAILS

Persons

Contacted

Licensee

Employees

K. Harris, St.

Lucie Site Vice President

~G. Boissy, Plant Manager

R. Sipos,

Service

Manager

J.

Barrow, Operations

Superintendent

"T. Dillard, Maintenance

Superintendent

"J. Harper,

gA Superintendent

C. Burton, Operations

Supervisor

~R. Frechette,

Chemistry Supervisor

C.

Leppla, I

8

C Supervisor

"C. Pell, Technical Staff Supervisor

E. Wunderlich, Reactor Engineering Supervisor

  • H. Buchanan,

Health Physics

Supervisor

W. White, Security Supervisor

B. Sculthorpe,

Reliability and Support Supervisor (Acting)

J.

Barrow, Fire Prevention

Coordinator

R.

Dawson, Assistant,

Plant Superintendent

- Electrical

C. Wilson, Assistant,

Plant Superintendent

- Mechanical

"N. Ross, guality Control Supervisor

"R. Burgess, Reliability and Support Staff

"L. McLaughlin, Technical Staff

"B. Mikell, Outage

Management

"R.

Packwood,

Electrical Maintenance

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 January 8, 1988, with

those

persons

indicated in paragraph

1 above.

The licensee

did not identify as proprietary any of the materials

provided

to or reviewed by the inspectors

during this inspection.

Licensee Action on Previous

Enforcement Matters

This subject

was not addressed

in this inspection.

Plant Tours (Units j. and 2), Modules

71707

8 71710

The inspectors

conducted

plant tours periodically during this inspection

interval to verify that monitoring equipment

was

recording

as required,

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 fluid leaks,

piping vibrations,

pipe

hanger

and seismic restraint settings,

various

valve

and

breaker

positions,

equipment caution

and danger tags,

component

positions,

adequacy of fire fighting equipment,

and instrument calibration

dates.

Some tours were conducted

on backshifts.

The

inspectors

routinely conducted partial

walkdowns of emergency

core

cooling

(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

area

of the unit 1

and unit 2

emergency

diesel

generators

and

AC/DC safety-related

switchgear to verify that the lineups

were in accordance

with licensee

requirements

for operability and equip-

ment

material

conditions

were

satisfactory.

Additionally,

flowpath

verifications

were performed

on the following systems:

unit 1 and unit 2

chemical

and

volume control,

main

and auxiliary feedwater,

and diesel

generator air start

and diesel

fuel oil supply.

No violations or deviations

were identified.

Plant Operations

Review (Units 1 and 2), Module 71707

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

tagouts

(clearances):

Unit 1

1-8-55

Control

Room ILRT Air Supply - Isolate

1-11-67

Intake Cooling Closed

Blowdown Heat Exchanger - Repair

Leaks

1-12-75

Reactor Trip Circuit Breaker - [PM] Preventive

Maintenance

1-12-112

HVE - 10B - Change

HEPA Filter

Unit 2

2-12-87

2B

Instrument Air Compressor

Turbine

Cooling Water Jacket-

Cl can

2-12-91

B Side

Steam Jet Ejector - Repair

Steam

Leak

2-12-96

2A gualified Safety

Parameter

Display System - Change

DC Supply

Breaker

No violations or deviations

were identified.

Technical Specification

Compliance (Units 1 and 2)

During this reporting interval,

the inspectors

verified compliance with

limiting conditions

for operations

(LCO's)

and results

of selected

surveillance

tests.

These

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-

rences

as they happened.

No violations or deviations

were identified.

Maintenance

Observation,

Module 62703

Station

maintenance

activities of selected

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 - 4643

PWO - 8628

PWO - 8630

Measuring

8 Test Equipment - Calibration

1B Diesel Generator

Soak-Back

Pumps - Inspection

1B Diesel Generator Air Line Lubricators -

PM Inspection

Unit 2

PWO - 6204

2B1

Reactor

Coolant

Pump

Controlled Bleedoff,

F1A-1170

Calibrate

PWO - 6860

Radiation Monitor, RM-11 - Repair

PWO - 2168

2B Fuel

Pool Cooling

Pump -

PM

No violations or deviations

were identified.

Physical

Protection (Units

1 and 2), Module 71707

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

organization

of the security force,

the establishment

and maintenance

of

gates,

doors

and isolation

zones

in the proper conditions,

that

access

control

and badging

was proper,

and procedures

were followed.

No violations or deviations

were identified.

Surveillance

Observations,

Module 61726

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 the affected

components

were

accomplished,

test

results

met requirements

and were

reviewed

by

personnel

other

than

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

portions of the following sur vei llances:

Unit 1

OP 0030126

OP 1-0110050

OP 0120026

ECC Calculation Worksheets

Control Element Assembly Periodic Exercise

Reactivity - Deviation from Design

OP 1-0010125

1A Boric Acid Pump - Monthly Code

Run (Data Sheet

12)

Unit 2

AP 2-0010123

Valve, Switch Deviation Log (Appendix

C)

AP 0010132

2B

Component

Cooling

Water

Pump

Baseline

Data

Sheet

(Attachment

1)

No violations or deviations

were identified.

Reactor Trips, Module 93702

On

December

21,

1987,

St. Lucie Unit IIl tripped while in

Mode

1 at

100

percent

power.

The trip was

caused

by a high startup rate trip signal

which was

generated

while a non-licensed

operator

was attempting to place

the

1D instrument

inverter

back

in service after

completing routine

preventive maintenance.

At

100

percent

power the

high startup

rate trip signal

is

bypassed.

However,

about

one

week prior to the trip the

B channel

high startup rate

bistable

had

been pulled for a routine surveillance

check which placed the

startup

rate

ci rcuit in

an active 1-out-of-3 trip mode.

Operations

personnel

were

unaware

that this condition existed;

they

assumed

that

above

15 percent

power the high startup rate circuit was automatically

and

permanently

bypassed.

The licensee

discovered that pulling a startup rate

bistable

reinstated

the rate trip.

Upon completion of the preventive

maintenance

procedure

on

the

1

D instrument

inverter,

the

operator

attempted

to

place

the

inverter

back

into service

by

removing

the

clearance

tags

and

repositioning

breakers.

The

operator

used

the

clearance

procedure

rather

than follow the

operations

procedure

for

placing

an inverter back into service.

By so doing,

power was lost to all

the

D channel

instruments

because

the

D instrument inverter output breaker

was not closed

when the operator transferred

function to the

D inverter.

This caused

loss of power to the

D startup rate

channel

which was in

a

1-out-of-3 mode

and caused

the reactor trip.

Other non-licensed

operators

were interviewed

by Florida Power and Light

to

determine

how they

would

have

performed

this

operation

and all

responded

in

a proper

manner, i.e., follow the operations

procedure,

so

this does not appear to be

a breakdown in the operations training program,

but

an isolated

incident of operator

error.

The operator

has

been

counseled

on

the

importance

of following procedures,

the training

department

has

evaluated

their training methods,

and

a

human factors

performance

study

is

being

conducted.

All systems

and

components

performed normally during and after the trip.

The

root

cause

of the

reactor trip

was

a

personnel

error

by

a

non-licensed

operator

for not following a plant

approved

procedure,

Operation

of the

120 Volt Instrument

AC Class

lE System.

This is

a

violation of the Unit

1

TS 6.8. 1, failure to establish

or implement

procedures

(50-335/87-31-01).