ML17263A841

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Insp Rept 50-244/94-21 on 941003-06.Violations Noted.Major Areas Inspected:Ep Readiness,Including Procedure Changes, FTS 2,000 Network,Erfs,Equipment,Instrumentation & Supplies
ML17263A841
Person / Time
Site: Ginna 
Issue date: 11/15/1994
From: Keimig R, David Silk
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17263A837 List:
References
50-244-94-21, NUDOCS 9411150030
Download: ML17263A841 (17)


See also: IR 05000244/1994021

Text

U. S.

NUCLEAR REGULATORY COMMISSION

REGION I

License/Docket/Report

No.:

DPR-18 50-244 94-21

Licensee:

Facility Name:

Inspection At:

Rochester

Gas

and Electric

Com an

RG&E

R.

E. Ginna Nuclear

Power Station

Ontario

New York

Inspection

Conducted:

October

3

6

1994

Inspectors:

D. Silk, Senior

E ergency

Preparedness

Specialist

J. Laughlin,

Emergency

Preparedness

Specialist

F. Lopresti,

Emergency

Response

Assistant

Qe

Approved By:

.

R;

ei ig,

ef

Emergency

re

redness

Section

Division of Radiation Safety

and Safeguards

Areas Inspected:

Emergency

Preparedness

(EP) readiness,

including: procedure

changes;

Federal

Telecommunication

System

(FTS)

2000 network;

emergency

response facilities (ERFs),

equipment,

instrumentation,

and supplies;

organization

and management

control;

emergency

response

organization

(ERO)

training; independent

audits;

and the licensee's

corrective action program

pertaining to

EP items.

Results:

The program's state of readiness

was determined to be good.

Procedure

changes

were acceptable,

however,

the licensee

had not submitted

three recent Nuclear

Emergency

Response

Plan

(NERP) revisions to the Regional

Office as required

by 10 CFR 50.54(q).

The

ERFs were found to be well

equipped.

However,

two quarterly siren growl tests

were not performed

by the

licensee

as required

by the

NERP.

The

EP organization

had undergone

some staff

changes

but was found to be adequate.

The depth in

ERO staffing was at least

three'n

each position.

The

EP training program was well implemented.

Audits

were found to be satisfactory.

Corrective actions pertaining to the

EP

program were acceptable.

No safety items were identified but two apparent

violations were issued

because

of the failure to test sirens

and the failure

to submit

NERP changes.

The two violations were

symptoms of a program

control s- weakness,

941ii50030 94ii07

PDR

ADOCK 05000244

8

PDR

DETAILS

Personnel

Contacted

RGKE

R. Beldue,

Corporate

Nuclear

Emergency

Planner

F. Orienter,

Coordinator Radiological

Safety Communications

P. Polfleit, Onsite

Emergency

Planner

W. Poulton, Training Specialist

B. Stanfield, guality Assurance

Engineer,

Independent

Assessment

Other licensee

personnel

were also interviewed during the inspection.

Nuclear

Re ulator

Commission

J. Laughlin,

Emergen'cy

Preparedness

Specialist

F. Lopresti,

Emergency

Response

Assistant

+ 'enotes

attendance

at the October 3,

1994 Entrance Heeting.

Denotes

attendance

at the October 6,

1994 Exit

Heeting.'.0

Emergency

Plan

and Implementing Procedures

The inspectors

reviewed implementing procedure

(EPIP)

changes

to

determine

whether

any changes

resulted

in a decrease

in effectiveness

of

,

the overall

emergency

plan.

Prior to this inspection,

the inspectors

reviewed the procedures

listed in Section 9.0 of this report in the

Region I Office.

The changes

were assessed

as acceptable.

During the inspection,

however,

the inspectors

discovered that three

NERP revisions

had

been

made without the Regional Office being

aware of

it.

Changes

to the

NERP can

be

made without NRC approval if they do not

decrease

the effectiveness

of the

NERP, but the changes

must

be

submitted to the Regional Office in accordance

with 10 CFR 50.54(q).

The

NRC regulations require the licensee to submit

one copy of the

changes

to the

NRC Document Control

Desk and the Resident

Inspector,

and

two copies to the

NRC Regional Office within 30 days of implementing the

change.

The inspectors

identified that

NERP Revision

12 (July 1, 1993),

Revision

13

(Hay 4, 1994),

and Revision

14 (August 31,

1994)

had not

been submitted to the

NRC Region I Office, even though they had

been

submitted

on

a timely basis to the Document Control

Desk and the

Resident

Inspector.

The reason

given by the licensee for the oversight

was that the

EP Group sends

copies of the changes

to the Document

Control

Desk and the Resident

Inspector directly, whereas

Region I is

sent copies through the licensee's

document control group.

The document

control group

had received notification of the changes

from the

EP Group

but overlooked its distribution to the Region I Office.

This is an

apparent violation (VIO 50-244/94-21-01).

3

Emergency Facilities,

Equipment,

Instr umentation,

and Supplies

The inspectors

toured the Control

Room (CR), Technical

Support Center

(TSC), Operational

Support Center

(OSC),

and

Emergency Operations

Facility (EOF) to determine their state of operational

readiness.

These

facilities were well-maintained,

contained all necessary

communications

equipment,

and conformed with the facility description in the

NERP.

Overall, they were in very good operational

condition.

However,

controlled copy Number

17 of the

EPIPs in the

TSC was missing

EPIP 2-7,

Management of Emergency

Survey Teams.

The licensee

immediately

added

a

copy of this procedure.

When questioned,

a licensee

representative

could only surmise that it had

been

removed,

used,

and not returned.

The inspector

checked other controlled copies

and found them intact.

No

other procedural

discrepancies

were noted.

The inspectors

conducted

an inventory check of sealed

equipment lockers

for the

TSC and

OSC.

These lockers

were amply supplied with necessary

emergency

equipment

and

no inventory discrepancies

were found.

The

inspectors

also reviewed the most recent

equipment inventory checklists

for the

TSC and

OSC.

These

were completed properly,

signed

by the person

completing the inventory,

and reviewed

by

EP personnel.

The inspectors

spot-checked facility radiation monitoring equipment

and found it

operational

and within calibration time limits.

Overall, the facilities

contained

adequate

emergency

equipment

which was well-maintained.

The inspectors

discussed

the logistical details of an

NRC team

responding

to an emergency with the licensee's

Onsite

Emergency

Planner

(OEP).

As

a result of that discussion,

the licensee will designate

additional

space

in the

EOF for NRC dose

assessment

and re-position the

NRC's Director of Site Operations

(DSO) with the licensee's

Emergency

Director (ED).

The inspectors

also verified the licensee's

conversion to the

FTS 2000

telecommunications

network in accordance

with Generic Letter 91-14,

Emergency Telecommunications.

The inspectors

confirmed the installation

and operation of FTS 2000 telephones

at the appropriate locations in the

CR,

TSC,

and

EOF.

The inspectors

noted that telephone stickers,

which

were provided

by the

NRC and list the new primary, back-up,

and

facsimile numbers for the

NRC Operations

Center,

had not been affixed to

"the telephones

in the

EOF and

TSC.

This matter was discussed

with the

OEP,

and prior to close of the inspection,

the inspectors

were informed

that the stickers

had

been placed

on the telephones.

This was confirmed

by the resident

inspectors

subsequent

to the inspection.

The inspectors

reviewed

EPIP 5-1, "Offsite Emergency

Response

Facilities

and

Equipment Periodic Inventory Checks

and Tests,"

Revision 5,

and

verified that it requires

monthly tests of the

FTS 2000 telephones.

However, the inspectors

found that the primary telephone

number for

contacting the

NRC Operations

Center

was incorrect.

In addition, the

back-up telephone

number listed in Attachment

1 of EPIP 5-1 was

no

longer valid.

These discrepancies

were brought to the licensee's

attention but are

now resolved

since the stickers contain the correct

telephone

numbers.

The inspectors

reviewed the licensee's

public notification system.

The

system consists

of 96 sirens

supplemented

by more than

40 tone -alert

radios within Wayne

and Monroe counties.

The activation of the system

is controlled

by the county officials.

The

NERP requires periodic siren

reliability testing at three levels of operation:

1) bi-weekly silent

tests to verify system electronic

components

are functioning,

2) quarterly manually activated

growl tests to verify siren operation,

and 3)

an annual full duration audible test of the entire system.

The

inspectors

reviewed surveillance

records to confirm adherence

to the

NERP regarding

performance of the siren reliability tests

conducted

in

1994.

Bi-weekly silent tests

and annual full duration audible test were

performed satisfactorily.

However, the last quarterly growl test

was

conducted

on March 2,

1994.

As such,

two quarterly tests

had not been

performed

as required.

The inspectors

also reviewed the

1994 quarterly

growl test schedule

(RGRE Inter-Office Correspondence

Memorandum,

dated

July 1,

1994, Subject:

1994 Ginna Siren Silent and Growl Tests).

The

inspectors

noted that the

1994 growl test frequency

was not scheduled

at

quarterly intervals.

This matter was discussed

with the Corporate

Nuclear

Emergency

Planner

(CNEP)

who promptly initiated action to have

the growl tests

performed for the

96 sirens.

Following the inspection,

the licensee

informed the inspectors

via teleconference

that the tests

were completed

on October 7,

1994

and all of the sirens functioned

properly.

Test documentation will be reviewed during

a subsequent

inspection.

The causes

of missed

growl tests

were twofold.

First, the

EP Group established

a surveillance

schedule with the Electric Heter

Lab

and Telecommunication

Group but this group did not properly inform the

Line Operating

Group (which actually performs the tests).

Secondly,

the

EP group did not verify that the tests

were being performed.

Failure to

conduct quarterly siren growl tests

as required

by the NRC-approved

NERP

is

an apparent violation (VIO 50-244/94-21-02).

Organization

and Management Control

During this inspection,

the licensee's

recent

(September

1994) re-

organization

was evaluated

as to its impact

on the

EP group.

Under the

previous organization,

the five member

EP Group was under the Director,

Corporate

Radiation Protection

and that was his sole responsibility.

Under the

new organization,

th'is

same individual is now the Manager,

Nuclear Assessment

(HNA).

The

MNA now has five areas of responsibility

of which

EP is one.

The Corporate

Nuclear

Emergency

Planner

(CNEP),

who

reports to the

HNA, was scheduled

to retire at the end of October

1994.

He will be replaced

by the

OEP.

The inspector

was informed that the

OEP

position would be posted within a few weeks following the inspection.

The retiring

CNEP has already delayed his retirement

one month to turn-

over the position to the

new CNEP.

The

new

CNEP has,

in the past,

performed various duties of the

CNEP and is, therefore,

not unfamiliar

with the position.

The Corporate Health Physicist

(CHP),

who was

previously in the

EP group,

has retired

and that position was

moved to

the station

because

the

CHP was only infrequently used for EP and when

S

5.0

the

EP group needs

any health physics assistance, it is available

onsite.

No problems related to the reorganization of the

EP Group were

apparent,

but the

NRC will monitor the impact of these

changes

during

future inspections.

The inspector

reviewed the

Emergency

Response

Organization

(ERO)

and

observed that the licensee

had at least three individuals for all key

positions.

Thus,

the licensee

has satisfactorily maintained its

ERO

during this period of re-organization

and "right-sizing".

The inspectors

also interviewed the Vice President

Nuclear Operations.

He is currently qualified as

a Recovery

Manager in the

ERO.

He stated

that

he was kept abreast

of EP issues

through the

gA audit reports,

post

exercise critiques,

meeting with the

HNA, and

by reviewing the tracking

system.

He was

aware of the transitional

status of EP due to the re-

organizational

and program changes

such

as implementing

a new Emergency

Action Levels

(EALs) and Protective Action Recommendation

methodology,

and integrating the licensee's

nuclear

emergency

response

program with

severe

weather

and gas

emergency

programs.

Overall, the inspector

determined that

EP issues

are understood

by senior

management

and

receive sufficient senior

management

attention.

EP Training

The inspectors

reviewed various training documents

and interviewed

training personnel

to assess

the adequacy of the licensee's

EP training

program.

The inspectors

audited the training records of several

randomly selected

individuals from various

key

ERO positions to check that their

qualifications were current.

In all cases,

the inspectors

were

shown

that the individuals had attended

the required requalification training

courses

and

had participated

in a drill or exercise

as required.

The

inspectors

also randomly selected

several

individuals that could be

required to wear respiratory protection

and found that all

had

been

trained

and qualified on the appr'opriate

type(s) of equipment.

Additionally; the inspector

reviewed lists of

ERO members

and their

qualification expiration dates

and found that

no expiration dates

were

exceeded

at the time of this inspection.

The inspectors

also interviewed the Operations Training Supervisor

and

reviewed several

records pertaining to licensed operator

EP training.

The operating

crews review event classifications

by utilizing the

EALs

during each simulator scenario

session.

The licensed operators

also

receive three

and one-half hours of EPIP training per cycle.

This

training includes table top scenarios

that involve operating

crews

as

well as the shift technical

advisor

and

an

HP technician.

The scenarios

task the players with implementing all the necessary

ERO

responsibilities

such

as event declarations,

dose projections,

and

making notifications

and

PARs.

Also,

as scheduling permits, mini-drills

have

been

conducted that integrate simulator requalification training

scenarios

with TSC and/or

EOF activation

and participation.

This not

6.0

only maximizes simulator usage

and Licensed Operator Requalification

Training

(LORT) but also exercises

the activation

and interfacing of

several

ERFs.

The inspectors

assessed

this as

a good initiative.

Independent

Audits/Reviews

The inspector

reviewed the

1994

EP audit report

and interviewed

a member

of the Quality Assurance

(QA) Department to assess

the adequacy of this

activity.

The audit was conducted

February

28 Harch 4,

1994,

under

the supervision of the

QA Department.

The two-man team consisted of one

person

from QA and one person

from the

New York Power Authority's

Corporate

Radiation Protection

Group who had extensive

EP background.

The inspector

concluded that the auditors

possessed

the appropriate

expertise

to conduct

an effective audit of the

EP program.

The scope of the audit was good,

and the. audit plan

and checklist were

adequate.

The inspector

noted that the audit fulfilled the requirements

of 10 CFR 50.54(t).

The audit report received

wide distribution to

licensee

management

and was

made available

by correspondence

to state

and county officials.

The audit identified no findings and six observations,

none of which had

any safety significance.

Findings were defined

as discrepancies

which

contradict licensing commitments,

procedures,

or applicable

purchase

order requirements.

Observations

were items in need of improvement.

The observations

were documented

via Quality Assurance

Observation

Reports

(QAORs).

Although the observations

were of no regulatory

significance,

a response

was required

from the responsible

department.

The inspectors

questioned

the

EP audit program relative to

10 CFR 50;54(t) that requires audits

be conducted

"by persons

who have

no

direct responsibility for implementation of the emergency

preparedness

program."

This requirement

prevents

a potential conflict of interest

and ensures

that audits

are conducted

in an unbiased

manner.

However,

in this organization

the

HNA is responsible for EP and for QA, who

performs the audits.

The inspector brought this to the attention of the

HNA and

a

QA lead auditor.

They stated that this

same organizational

structure

had occurred in the past but there

was never

a problem

resolving

QA findings.

They stated that it was unusual for those

audited to disagree

with QA's findings.

Procedurally,

QA can elevate

issues

to the next higher level of management, if necessary,

for

resolution.

Also,

QA auditors report to lead auditors,

who in turn

report to the

QA Hanager,

who then reports to the

HNA.

Therefore,

there are several

levels of review between the auditors

and the

HNA.

Furthermore,

the

HNA does not prepare

the auditors'erformance

appraisals.

The inspectors

accepted

the licensee

explanation of the

organization

but will monitor this during future inspections

to verify

that effective 50.54(t) audits

are being performed.

Overall,

no deficiencies

were identified and this area

was

assessed

as

being satisfactorily implemented.

7

Effectiveness of Licensee Controls

8.0

8.1

The inspectors

reviewed documentation

and interviewed

EP,

gA,

and

licensing personnel

to determine

the adequacy of licensee control

mechanisms

for problem identification and correction.

Licensee

procedure

A-30, Ginna Commitments

and Actions, described

the process

used for management

of commitments

and action items.

This procedure

was

written as part of a commitment to the

NRC to establish

and maintain

a

commitment tracking system.

It summarized

management

responsibilities

for Commitment/Action Item (C/AI) tracking, established

the Commitment

and Action Tracking System

(CATS) Administrator,

and outlined proper

disposition of all licensee

C/AIs. It assigned

C/AI priority by item

source,

distinguishing regulatory

agency

items from other sources.

The licensee effectively tracked

and resolved C/AIs.

The inspectors

noted that the Licensing Department's

CATS Administrator had

a separate

file on each

item, including all findings in

NRC reports.

When

responsible

departments

completed corrective actions,

they were signed

off and the

CATS database

was updated.

The inspectors

noticed

one

weakness

in CATS administration.

Although the Licensing

CATS

Administrator received training on Procedure

A-30 in 1991

when the

procedure

was written, there

was

no ongoing training program for

department

CATS coordinators.

For example,

the

EP

CATS Coordinator

was

not familiar with the procedure

and was incorrectly filling out

documentation for submission to licensing.

This did not result in any

documentation

deficiencies,

however,

since the licensing administrator

was trained

on the procedure.

Audit findings were documented

in Audit Finding Corrective Action

Reports

(AFCARs)

and audit observations

in gAORs.

Both were tracked in

the

CATS,

and both required

a response,

although only the

AFCARs

required action to correct deficiencies.

The inspectors'eview

of the

most recent

EP

CATS printout revealed

two items, neither of which were

safety significant, that were overdue.

The

CATS was generally effective

in resolving items in the allowed time frame.

Review of Open Items

(CLOSED) IFI 50-244/93-11-02:

During Inspection

93-11 (July,

1993), the inspectors

noted several

issues

pertaining to licensed operator shift crews.

During table-top

exercises,

which simulated fast breaking accident

scenarios,

the

inspectors

observed

areas

related to their

EP duties that could be

improved,

such

as radiological

hazards to

ERO personnel,

verification of

accuracy of dose projection calculations,

and

EAL interpretation.

During this inspection,

the inspector

interviewed the Operations

Training Supervisor

and reviewed several

records pertaining to licensed

operator

EP training.

It was determined that the licensed

operators

receive three

and one-half hours of EPIP training per cycle.

This

training included table-top scenarios

that involve operating

crews

as

8;2

well

as the shift technical

advisor

and

an

HP technician.

The scenarios

require the participants to perform their

ERO responsibilities,

such

as

event declarations,

dose projections,

and making notifications

and

PARs.

Also,

as scheduling permits, mini-drills have

been conducted that

integrate simulator requalification training scenarios

with TSC and/or

"

EOF activation

and participation.

This not only maximizes simulator

usage

and

LORT simulator scenario training but also-exercises

the

activation

and interfacing of several

ERFs.

The inspector

assessed

this

as

a good initiative.

During normal

LORT, the operating

crews review

event classifications

by utilizing the

EALs during each simulator

scenario

session.

Therefore,

based

on the crews'raining

and the

absence

of any poor performance

indications during the November

1993

exercise,

this item is closed.

(CLOSED)

URI 50-244/93-18-01:

During the November

1993 exercise,

an area for potential

improvement

was

identified regarding the formation of a repair team to restore

power to

a valve so that

a leaking pipe in the auxiliary building could be

secured.

Specifically,

due to the high radiation level

and iodine

concentration

in the vicinity of the motor control center

(60 rem

general, area),

the health physics/chemistry

manager

recommended

an air

.

fed respirator for personnel

radiation protection.

The available

electrical

maintenance

personnel,

however,

were not respirator-

qualified.

Due to the need to restore

power to the valve

(HOV-851A),

the

Emergency Coordinator waived the respirator qualification

requirement'.

1

During this inspection,

the inspectors

reviewed the licensee's

corrective action to this issue.

The licensee

issued

a memorandum to

all

ERO personnel.

It provides

management's

policy of having sufficient

personnel

who are respirator qualified.

Furthermore, it specified the

type of respirator for which

ERO groups,

such

as

damage repair teams

and

survey teams,

are to be qualified.

The licensee

reviews individual

respirator qualifications

on

a monthly basis

when the General

Employee

Training qualifications are reviewed.

The inspectors

sampled

several

ERO members that could be required to wear

a respirator

and found that

they were qualified for their specified respirator

equipment.

Therefore,

based

upon the licensee's

policy and the verification that

ERO members

are properly qualified, this item is closed.

8.2

(UPDATE) URI 50-244/93-18-02:

During the November

1993 exercise,

an area for potential

improvement

was

noted regarding

a failure to issue

a timely protective action

recommendation

(PAR).

When

a

GE is declared,

a

PAR is to be issued with

the 15-minute notification.

The licensee's

notification form lists four

choices for PARs:

1) There is no need for protective actions outside the

site boundary,

2)

Need for protective action is under evaluation,

3)

Sheltering

recommended,

and 4) Evacuation

recommended.

During the

exercise,

the

GE was declared

at approximately

10: 15 a.m.

At 10:25

a.m.,

the licensee

issued

the

PAR

- "Need for protective action is

under evaluation."

The licensee

was prepared

to issue

a

PAR based

on

plant conditions at the time of the

GE declaration,

however, prior to

making the offsite notifications, plant conditions

changed

such that the

PAR also changed,

The licensee

took time to evaluate

the latest plant

and radiological conditions to make the appropriate

PAR,

and correctly

issued

the

PAR to shelter at 10:55 a.m.

This was

40 minutes after the

GE had

been declared

and did not meet the

15 minute goal.

During this inspection,

the inspector determined that the licensee

deleted

"Need for protective action is under evaluation"

as

a

PAR

option.

This removes the implication that

PAR issuance

can

be delayed.

Also, the inspector

reviewed requalification training lesson

plans

and

confirmed that the objective of issuing

a

PAR within 15 minute of the

GE

declaration

was emphasized

to potential

decision-makers.

However,

due

to the potential public impact of delaying

a

PAR, this issue will remain

open pending timely and accurate

PAR issuance

by the licensee

during

an

NRC evaluated

exercise.

9.0

Listing of Document

Change

Reviews

As discussed

in Section 2.0 of this report, the inspectors

reviewed

recent

changes

to the Ginna Nuclear

Emergency

Response

Plan Implementing

Procedures

(EPIPs) to determine if any of these

changes

decreased

the

effectiveness

of the procedures.

The following revisions

were reviewed:

EPIP

Revision

s

1-0

1-5

1-6

1-11

1-12

1-14

1-15

2-1

2-2

2-4

2-5

2-6

2-8

2-10

2-11

2-12

2-13

2-14

2-18

3-3

3-6

3-.7

4-1

4-2

4-3

15,

16,

17,

& 18

16,

17,

& 18

5

8

2

6

7

10

& 11

5

6

24&5

3

2

35&6

4

44&5

2

14

& 15

4

& 5

3

5

4

4-5

4-6

4-7

5-1

5-2

5-3

5-4

5-5

5-6

5-7

5-10

10

2

7

4

6

8. 7

8, 9,

10 5 ll

10

& 11

5

2ll

25,3

No degradations

in procedure effectiveness

were. identified.

10.0

Exit Meeting

The inspectors

met with the licensee

personnel

identified in Section

1.0

at the conclusion of the inspection to discuss

the inspection

scope

and

findings.

The inspectors

highlighted the items in Sections

2'.0 through

9.0 of this report,

and provided

a summary evaluation of the

EP program.

The licensee

acknowledged

the findings and commitments

made during the

inspection

as stated

by the'nspectors.