ML17229A324

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SALP Repts 50-335/97-99 & 50-389/97-99 for Period of 960107-970329
ML17229A324
Person / Time
Site: Saint Lucie  
Issue date: 05/05/1997
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17229A323 List:
References
50-335-97-99, 50-389-97-99, NUDOCS 9705130114
Download: ML17229A324 (7)


See also: IR 05000335/1997099

Text

SYSTEMATIC ASSESSMENT

OF LICENSEE PERFORMANCE

ST.

LUCIE NUCLEAR PLANT

50-335/97-99

AND 50-389/97-99

BACKGROUND

The SALP board convened

on April 9,

199?, to assess

the nuclear safety

performance of the St. Lucie Nuclear. Plant for the period January

?,

1996, through March 29,'99?.

The board was conducted in accordance

with Management Directive 8.6,

"Systematic

Assessment

of Licensee

Performance."

Board Members were J.

R. Johnson

(Board Chairperson),

Director, Division of Reactor Projects;

D.

M. Collins, Acting Deputy

Director, Division of Reactor Safety;

and F. J.

Hebdon, Director,

Project Directorate II-3, Office of Nuclear Reactor Regulation.

This

Assessment

was reviewed

and approved

by the Regional Administrator.

PLANT OPERATIONS

This functional area

addresses

the control

and execution of activities

directly related to operating the facility. It includes activities such

as plant startup,

power operation,

plant shutdown,

and response to

transients.

It also includes initial and requalification training

programs for licensed operators.

Overall performance in the operations

area during the assessment

period

was considered

good.

Management oversight

was evident in day-to-day

plant operations

as well as daily plant status

and scheduling meetings.

The plant was operated

competently with few reactor trips,

none of which

were the result of operator error s.

Control

room conduct

and

'rofessionalism

were good.

Control

room communications

were clear

and

well executed

and comprehensive pre-activity briefings were conducted

during this assessment

period.

Operators'erformance

during plant shutdowns,

startups,

and transients

continued to be

a strength.

Operators

demonstrated

conservative

decision making and focused

on safety.

Plant startup

and shutdown

activities were well planned

and properly executed,

including activities

associated

with reduced inventory and fuel handling.

Operators

were properly trained

and qualified.

The requalification

program was adequate

but some weaknesses

existed.

The use of Real

Time

Training Coaches

indicated innovative and proactive Training Department

involvement. in plant activities.

Operators generally conducted routine plant activities in accordance

with management

expectations

and procedural

requirements.

Operator

attention to detai

1 has

shown

some improvement during the assessment

period.

Plant operations

continued to experience

challenges

in

9705f30ff4 970505

PDR

ADQCK 05000335

8

VllP

procedural

adequacy

throughout the assessment

period.

Weaknesses

were

identified in control

room command

and control early in the assessment

pel

1 od.

Deficiencies were noted in the effectiveness

of plant

operators'dentification

of configuration errors.

For examples,

walkdowns of the

units'nstrument air systems'ontainment

spray systems

and post

accident

sampling systems

resulted in the identification of a number of

procedural

inadequacies.

design drawing inaccuracies,

and hardware

deficiencies.

Management

was generally effective in controlling the use of, licensed

and non-licensed

operator

overtime.

However, the routine heavy use of

licensed

operator

overtime to support

normal plant operations

indicated

that maintaining

an adequate

number of licensed reactor operators

remains

a challenge.

Company Nuclear

Review Board activities to review proposed

license

amendments,

due to higher than expected

rates of Unit I steam generator

tube plugging, were found to be probing and competent.

Facility Review

Group activities were thorough

and appropriately

focused

on safety.

Quality assurance

activities associated

with operations

were generally

effective in identifying areas for improvements.

A broad self-

assessment

of the overall site performance at the St. Lucie Nuclear

Plant was comprehensive.

Implementation of plant management initiatives

to address

each of the fundamental

weaknesses

identified in the

assessment

was considered

necessary

to sustain

improvements.

The Plant Operations

area is rated Category 2.

MAINTENANCE

This functional area

addresses

activities associated

with diagnostic,

predictive, preventive

and corrective maintenance of plant structures,

systems

and components.

It also includes all surveillance testing, in-

service inspection

and tests

and other tests

associated

with equipment

and system operability.

Maintenance activities were generally conducted well with some

improvement noted during this assessment

period.

The Maintenance

Department

was reorganized into functional units with rotating shift

supervisors to improve performance.

There was generally

good planning

and attention to detail in the performance of mechanical

and electrical

maintenance.

Where used.

predictive maintenance

was effective in

improving equipment

performance.

The in-service inspection activities

were well planned,

appropriately

performed

and well managed.

In-service

testing

and surveillance activities were well coordinated

and

effectively implemented.

Management efforts toward upgrading procedures

and training personnel

to

use them were not completely successful,

particularly in Instrumentation

and Control

(IKC) .activities.

Licensee eff'orts to correct instances

of

inadequate

maintenance

work instructions in use at work sites

were more

effective toward the end of the period.

Planning

and management

control were deficient when the responsibilities

for calibration of the Unit

1 radiation monitoring systems

were

transferred

from the Chemistry Department to the

I8C Department before

the

I&C technicians

were qualified to perform those calibration

activities.

Subsequent

calibrations of plant radiation monitoring

equipment were not adequate.

Reductions

in operator

work arounds,

overdue preventive maintenances,

and maintenance

non-outage

work orders

demonstrated

improved

effectiveness

in the overall maintenance

program.

Plant material

condition was

good and improved during the

SALP period.

Nevertheless,

there continued to be challenges

in equipment

performance,

for the most

part in balance-of-plant

equipment,

that impacted plant reliability and

challenged plant operation.

Progress

made during the last

SALP period

in operation of the Post Accident Sampling System

(PASS) did not

continue this period.

The

PASS system

was not well maintained.

A self-assessment

of the Maintenance

Rule implementation

conducted prior

to rule implementation identified program areas

needing additional

attention.

A followup audit found good corrective actions

and

identified specific areas

needing further corrective action.

Late in

the period, the licensee

established

a program of quarterly self-

assessments

by each functional group in the Maintenance

Department

and

an annual

self-assessment

as

a whole.

The Maintenance

area is rated Category 2.

ENGINEERING

This functional

area

assesses

activities associated

with the design of

plant modifications,

and engineering

support for operations,

maintenance,

surveillance,

and licensing activities.

Overall performance in the engineering

area declined from its previous

superior level to an overall rating of good.

Engineering provided good

support for plant operations

and continued superior performance in the

area of licensing activities.

However.

weaknesses

were noted in the

preparation of modification packages,

in the quality verification and

validation of'omputer software,

and in the identification and

correction of'ong-standing

design control deficiencies.

Reduction in the number of operator work-arounds

was aggressively

pursued

and the backlog of plant changes

and modifications decreased

during the period.

No plant transients

attributable to engineering

occurred during the assessment

period.

The In-service Inspection

Program

was well planned,

well managed,

and effective in identifying and

correcting material

problems prior to impacting plant operations.

Problems related to modification planning

and design control persisted

during this period.

A number of problems related to the preparation of

design

changes,

independent verification, and post-modification testing

were identified associated

with a modification to the nuclear

instrumentation

system.

Failure to ensure that the computer

software

for the Digital Data Processing

System

was updated correctly resulted in

operation in slightly excess of maximum rated thermal

power for an

extended

period of time.

Although improvements

were noted toward the

end of the assessment

period, identification of problems in these

areas

indicated the need f'r continuing management

attention.

Recent

expansion of the System Engineer

program was viewed as

a

significant potential

improvement to the engineering

program.

However,

many of the System

Engineers

were still new to thei r positions

and

required further training and development.

Licensing submittals

were timely and well prepared.

Host submittals

were found acceptable

by the staff with no need for additional

information.

Requests

were submitted well in advance of when needed.

allowing ample time f'r staff'eview.

The licensee's

responses

to

NRC

requests

have

been timely and thorough.

Of particular note, the

NRC

staff recently reviewed the licensee's

actions related to Thermo-Lag

modifications

and concluded the plans were reasonable.

The Engineering

area is rated Category 2.

PLANT SUPPORT

This functional area

addresses

all activities related to the plant

support function, including radiological controls,

radioactive

effluents,

chemistry.

emergency

preparedness,

security, fire protection,

and housekeeping.

Implementation of the radiation protection program was good.

Strong

upper

management

support for maintaining radiation worker doses

As Low

As Reasonably

Achievable resulted in individual line management

accountability

and good control of individual and collective doses..

Efforts to correct contamination control problems were not fully

effective.

Radiological

worker practices

were inconsistent.

Audits and corrective actions for radiological control programs

were

generally thorough with appropriate corrective actions,

but the

threshold for identifying findings was high in review of the Process

Control

Programs

and Offsite Dose Calculational

Manual.

The threshold

was appropriately adjusted.

Corrective actions to assure that sampling

procedures

were properly implemented were not fully effective; repeated

procedural

non-compliances

resulted in inoperability of the Unit

1

containment radiation monitor on three occasions.

Training of Health Physics

personnel

was effective.

The radiological

effluent control

and monitoring program implementation

was good.

Water

chemistry was well controlled.

Efforts to reduce the large inventory of

contaminated

material

and solid radioactive waste

on site were very

effective.

The radioactive material

shipment

program was effective.

There was

a significant decline in the Radiological

Emergency

Preparedness

(REP) program early in the period.

Indicators of the

decline were identified to licensee

management,

but timely corrective

actions were not taken.

Corrective actions to audit findings were not

timely.

This indicated that management

oversight of and priority to the

emergency

preparedness

program were inadequate

early in the period.

The

REP program implementation

began to show improvement at the end of the

assessment

period.

The emergency

plan was

implemented effectively during several

actual

Unusual

Events.

An exercise early in the period also demonstrated

that

the onsite

emergency

plan could be effectively implemented.

Two

practice drills were requi red before this exercise for licensee

management to be satisfied with performance.

This was

an indication of

problems with the effectiveness

of training.

The program to assure that

all individuals assigned

emergency

response

f'unctions were properly

trained

was not fully effective.

The primary and backup methods for augmentation of onsite staff for

emergency

response

were not effective until corrective actions

were

taken late in the period.

0

The security program was generally effective, but there were problems

with access

control.

Training and qualification continued to be

a

strength.

Security equipment

and facilities were well maintained

and

compensatory

measures

were generally good.

Control of personnel

access

was weak.

Badges of terminated

employees

were not promptly .cancelled.

The licensee's

Access Authorization Program

was satisfactory.

The

licensee identified errors in implementation of the Fitness-for -Duty

Program

and took appropriate corrective actions.

Overall, the licensee's

response

to potential

and actual

tampering

events

was satisfactory,

but initially did not include evaluation of'he

full extent of condition.

Appropriate preventive

and corrective actions

were taken.

Fire prevention/protection

procedure quality was generally

good and

implementation

was effective.

Training of fire brigade personnel

was

good;

however,

personnel

with expi red medical certification were

assigned to the brigade.

Fire protection equipment maintenance

and

operability were overall effective; however,

several fire protection

features

were modified without adequate

evaluation.

Plant housekeeping

was very good, with significant improvement toward the end of the

assessment

period.

Licensee

management

supported

extensive efforts to

reduce stored

radwaste,

reducing the volume substantially.

Very few

plant system leaks were observed

and,

when identified, were promptly

repaired.

The Plant Support

area is rated Category 2.