ML18004B947

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Ack Receipt of Denying Violations Noted in Insp Rept 50-400/87-22.Staff Assessment of Licensee Response, Concluding That Violation Occurred,Encl.Corrective Actions & Date of Compliance Requested within 30 Days of Ltr Date
ML18004B947
Person / Time
Site: Harris 
Issue date: 09/22/1987
From: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Utley E
CAROLINA POWER & LIGHT CO.
References
NUDOCS 8709290481
Download: ML18004B947 (7)


See also: IR 05000400/1987022

Text

(

ACCESSION

NBR

F*CIL 50-400

AUVH. NAME

GRACEI J. N.

'RECIP. NAME

UTLEYiE. E.

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

8709290481

DOC. DATE: 87/09/22

NOTARIZED:

NO

Sheav on Harv is Nucleav

Poujer Planti

Unit ii Carolina

AUTHOR AFFILIATION

Region

2I Offi ce of Director

RECIPIENT AFFILIATION

Carolina

Power

8c Light 'Co.

DOCKET

05000400

SUBJECT:

Ack

v eceipt of 870821 ltv denying violations noted

in Insp

Rept 50-400/87-22.

Cov v ective steps

ujhich eill be taken

requested

ujithin 30 days of ltv'ate.

DISTRIBUTION CODE:

IEOID

COPIES

RECEIVED: LTR l ENCL g

SIZE:

TITLE: General

(50 Dkt)-Insp Rept/Notice of Violatio'n Response

NOTES: Application For permit

v eneeal filed.

05000400

REC IP IENT

ID CODE/NAME

PD2-1

PD

INTERNAL: AEOD

NRR

MOR ISSEAUi D

NRR/DREP/EPB

NRR/DRIS DIR

OE

EBERMANI J

EG FI

RG

FILE

01

XTERNAL: LPDR

NSIC

COPIES

LTTR ENCL

1

1

1

1

1

1

1

1

1

1

1

1

1

1

1

1

1

1

1

REC IP IENT

ID CODE/NAME

BUCKLEYiB

DEDRO

NRR/DOEA DIR

NRR/DREP/RPB

NRR/PMAS/ILRB

OGC/HDS1

RES

DEPY GI

NRC

PDR

COP 1ES

LTTR ENCL

2

2

1

1

1

1

2

2

1

1

1

1

1

1

TOTAL NUMBER OF COPIES

REQUIRED:

LTTR

20

ENCL

20

Carolina

Power and Light Company

I-ATTN:

Mr. E.

E. Utley

Senior Executive Vice President

Power Supply and Engineering

and Construction

P. 0.

Box 1551

'aleigh,

NC

27602

Gentlemen:

SUBJECT:

NRC

INSPECTION

REPORT

NO. 50-400/87-22

rn

V)

I

CA

Thank you for your

response

of August 21,

1987,

to our Notice of Violation,

issued

on July 8,

1987,

concerning activities conducted at your Shearon

Harris

facility.

We

have

evaluated

your

response

and

found that it meets

the

requirements

of 10 CFR 2.201.

After careful

consideration

of the bases

of your denial of the Violation, we

have determined, for the reasons

presented

in the enclosure

to the letter, that

the violation occurred

as

stated

in the Notice of Violation.

Therefore,

in

accordance

with 10 CFR 2.201(a),

please

submit to this office within 30 days of

the date of this letter,

a written statement

describing

steps

which have

been

taken to correct the violation and the results

achieved,

corrective steps

which

will be utilized to avoid further violations,

and the date

when full compliance

will be achieved.

The

responses

directed

by this letter

are

not subject

to the

clearance

procedures

of the Office of Management

and Budget

as required

by the Paperwork

Reduction Act of 1980,

PL 96-511.

We appreciate

your cooperation

in this matter.

Sincerely,

Enclosure:

Staff Assessment

of Licensee

Response

cc w/encl:

~

A. Watson,

Vice President

Harris Nuclear Project

W L. Tibbitts, Director of Regulatory

Compliance

L. Willis, giant General

Manager

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Regi onal

Administrator

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PIRC Resident

Inspector

A. Upchurch,

Chairman, Triangle J

Council of Governments

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ENCLOSURE

Staff Assessment

of Licensee

Response

Restatement

of Violation

10 CFR 20.201(b)

requires

that

each

licensee

make or cause

to

be

made

such

surveys

as

may

be necessary

for the licensee

to comply with the regulations

in

10 CFR 20, and are reasonable

under the circumstances

to evaluate

the extent of

radiation hazards

that

may be present.

A survey is defined in 10 CFR 20.201(a)

as

an evaluation

of the radiation

hazards

incident to the production,

use,

release,

disposal,

or

presence

of radioactive materials

or other

sources

of

radiation under

a specific set of conditions.

10 CFR 20.101(a)

specifies

the quarterly occupational

radiation

dose limits to

the lens of the eyes

and the skin of the whole body.

Contrary to the above,

the'licensee

failed to perform adequate

evaluations of

individual

exposures

to

noble

gas

in that

algorithms

used

to covert

thermoluminescent

dosimeter

(TLD) readings

to skin and lenses

of the eye dose

for personnel

who

made

containment entries

on June. 17,

1987,

and before

were

inappropriate for the noble gases

present

in containment.

The licensee

used

no

other dose

assessment

technique to assess

doses

due to noble gases.

L'icensee

Comment

The violation as

stated

was denied.

The licensee

stated that adequate

dose

evaluations

were

being

performed

in accordance

with

10 CFR 20,

and that the

dose evaluations

were reasonable-under

the circumstances

to evaluate

the extent

of radiation hazards

that

may have

been present.

This position is based

on the

following:

(1) the

TLD dose algorithm was adequate

considering concentrations

of noble

gas

found in containment,

and

(2) it was

reasonable

for radiation

protection

personnel

to assume,

based

on the low concentrations

of noble gases

measured

during routine monitoring and the expected

MPC-hours of exposure,

that

personnel

dose

from the noble

gas would be insignificant and that further dose

evaluations

were not necessary.

NRC Res

onse

The licensee's

response

implies that

an informed judgement

.had

been

made

by

onsite

radiation protection

personnel

that the

TLD was

adequate

to monitor

exposures

from inconsequential

noble

gas concentrations.

The onsite personnel

actually were unaware of the capabilities of the

TLD in this regard.

The noble

gas concentrations

in the vicinity of the work were riot known since noble gas

air

samples

in the

work area

were

not taken.

The installed

Radiation

Monitoring System

(RMS) indicated

noble

gas concentrations

in containment

were

approximately at

Maximum Permissible

Concentration

(MPC) levels,

although

the

licensee

had not yet concluded tests to demonstrate

how representative

the

RMS

readings

were for various

areas

in containment.

Offsite personnel

were aware

of the TLD's capabilities,

but had not communicated this to onsite

personnel

Encl osure

and

were

not involved routinely in the daily personnel

protection decision

process

at the plant.

Thus the onsite

health

physics staff who controlled

exposures

to workers,

did not

have in 'place

a system to provide sufficient

information on total dose.

Lacking information on the dose to workers from the

noble gas,

the

dose

evaluations

were not reasonable

or adequate.

They were

based

on the erroneous

assumption that the

TLD measured

the noble

gas exposure.

In order for an evaluation

to

be

considered

acceptable,

the licensee

must

include

an assessment

of the potential

source

and the capability of the

TLD to

measure

exposures

from that source.

In this case,

the licensee

did neither,

but rather

assumed

there

was

no problem in the absence

of data.

Licensee

Comment

The

TLD dose algorithm utilizes beta correction factors which are based

on the

range of beta

energies

most responsible for personnel

exposure.

Although some

noble

gases

emit beta particles

with energies

outside of this

range,

the

resultant

dose

which

may

go

unassigned

is

very

small.

Conservative

calculations

based

on air sampling

results

at

SHNPP

show that the

maximum

potential

unassigned

dose to any individual during the first two quarters of

1987 were less

than

7 mrem to the skin and I mrem to the lens of the eye.

Such

low doses

are considered

insignificant.

Therefore the assumption

by radiation

protection

personnel

that

the

TLD would adequately

monitor the exposure

of

personnel

entering containment

was correct.

NRC Res

onse

Prior to the

NRC calling the situation to the attention of station personnel,

they were not aware that the dose

from certain noble gases

were not measured

by

the

TLD.

Although the station personnel's

subsequent

evaluation

has

shown the

dose

from unmeasured

exposure

to noble

gas

was

low, there

was

a failure to

perform an adequate

evaluation prior to exposing workers to the noble gas.

The

onsite radiation

personnel

stated

to the. inspector that they thought that the

TLD was measuring

the noble

gas exposure,

which it wasn'.

They did not assume

that

the

noble

gas

hazard

was insignificant

and therefore

did not warrant

monitoring.

Had

there

been

a significant

noble

gas

concentration

in

containment,

the control

systems

in place would not have called for changes

as

workers accumulated

dose from noble gas since station staff believed that their

TLD was monitoring the noble gas exposure.

Licensee

Comment

The maximum unassigned

doses

to the skin and lens of the eye correspond

to less

than

0. 1% of the

applicable

quarterly

dose

limits in

10 CFR 20.

NRC

regulations

do not require monitoring when exposure

is not expected

to exceed

25K of the quarterly limit.

NRC Res

onse

The licensee's

position would be relevant if workers only received

exposures

during the 'quarter

from a small

number of noble gas exposures.

But many plant

. workers

receive

exposures

from other sources

during the quarter which are in

~ Encl osure

excess

of the

record

keeping criteria.

Measurable

noble

gas

exposure

then

becomes

part of the worker's cumulative quarterly exposure.

It should also

be

noted

that

the

licensee

would not

have

known whether or not minor or

significant exposures

were being received

because

their TLDs were not capable

of monitoring this dose,

and they did not assess

the potential

exposure

by any

other means.

Licensee

Comment

In conclusion,

the

dose

assessment

techniques

used for

SHNPP were adequate

to

evaluate

the

exposure

to noble

gases.

However,

CP8L recognizes

that with

continued .plant operation,

the potential for higher noble

gas levels exists.

If this occurs, it will be

noted during routine monitoring

and appropriate

actions will be

taken

to ensure

that

dose

evaluations

are

reasonable

to

evaluate

the extent of any radiation hazard present.

NRC Res

onse

i

The staff does not agree with the licensee's

conclusion.

The station personnel

charged with controlling dose to workers did not assess

the dose from noble

gas

exposure,

therefore

the dose

assessment

technique

could not have been adequate.

The

TLD algorithms

were not capable of measuring

the dose

from noble gas,

and

no other

dose

assessment

technique

was used.

The onsite personnel

incorrectly

assumed

the

TLD could

measure

dose

from noble

gas

exposure.

The licensee's

evaluation

showed that resultant

errors in total

dose

were low, however,

the

adequacy

of the dosimetry to measure

noble gas,

the concentration of noble gas

and

the likely doses

to

be

encountered

had

not

been

evaluated

prior to

assigning

dosimetry

and establishing

work controls.

The licensee

had

not

established

a system to establish

controls to ensure that, if noble gas levels

become higher, they will be appropriately identified and evaluated.

NRC Conclusion

For

the

above

reasons,

the

NRC staff concludes

that the violation occurred

as

stated.