ML16340A443

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IE Insp Rept 50-323/79-09 on 790220-23.No Noncompliance Noted.Major Areas Inspected:Training in Emergency Planning & Radiation Protection,Staffing,Respiratory Protection, Radioactive Waste Sys & Offsite Dose Calculation Manual
ML16340A443
Person / Time
Site: Diablo Canyon 
Issue date: 03/19/1979
From: Book H, North H
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML16340A445 List:
References
50-323-79-09, 50-323-79-9, NUDOCS 7905230664
Download: ML16340A443 (8)


See also: IR 05000323/1979009

Text

.

Report

No.

50-323/79-09

Docket

No.

50-323

U ~ S.

NUCLEAR REGULATORY COMMISSION

OFFICE

OF INSPECTION AND ENFORCEMENT

REGION V

License

No.

CPPR-69

gadeguarda

Group

Licensee:

Pacific,Gas

and Electric Company

77 Beale Street

San

Fran is

o

C

ifo ni

Facility Name:

Inspection at:

San Luis Obis

o Count

, California

Inspection conductedy'

bruar

20-23

1979

/

Inspectors:

dg--

H

S. North Radiation Specialist

Date Signed

Date Signed

Approved By:

Summary:

H.

E. Book, Chief, Fuel Facility and Materials

Safety Branch

Date Signed

Date Signed

Ins ection

on Februar

20-23,

1979

Re ort No. 50-323 79-02

~A:

y id

d

g

ypp

dg.

d

d

d

p

radiation protection, staffing, respiratory protection; radioactive

waste systems.

Offsite Dose Calculation Manual; monitoring procedures;

preoperational

tests;

and plant tour.

The inspection involved eight

inspector-hours

onsite

by one inspector.

Results:

No items of noncompliance

or deviations

were identified.

RV Form pip (l

F905 S So@< +

i

-

DETAILS

Persons

Contacted

  • R. Ramsay, Plant Superintendent
  • J. Shiffer, Assistant to Plant Superintendent
  • J. Giscoln,

Power Plant Engineer

  • M. Norem, Startup

Engineer

  • D. Backens,

Maintenance

Supervisor

  • R. Smith, Security Chief Supervisor

~J. Shearer,

Office Supervisor

  • C. Seward,

gA Engineer

J. Boots, Senior Chemical-Radiation

Protection

Engineer

l<. O'ara,

Chemical Radiation Protection

Engineer

  • J. Diamonon,

gC Supervisor

4

S., Fridley, Assistant Training Coordinator

J. Arnold, Coordinating

gC Engineer

  • Denotes those present at the exit interview.

'i Q

2.

3.

Trainin

- Emer enc

Plannin

Radiation Protection'

computerized training record program is being implemented.

The

program will include records for all plant personnel,

except opera-

tors, in the areas of radiation protection,

emergency

planning,

security and quality control.

The program will identify individuals

by name,

social security

number and job classification which desig-

nates

the training level required

as specified in Administrative

Procedure

B-2.

Copies of class

attendance lists and

exams will be

the only paper

records

retained.

Standard radiation protection

lecture notes

have

been

prepared

and included as training require-

ments for particular job classification.

Standard

lecture notes in

other areas will be prepared.

At the time of the inspection, radiation

protection training data

had

been

entered in the computer.

Records

of training in areas

other than radiation protection will be entered

in the computer in the near future.

The licensee

plans

an extension

training effort to assure that all personnel

have received the

required training and retraining.

No items of noncompliance

or deviations

were identified.

'adiation

Protection - Staffin

The licensee is in the process of selecting three additional

Radi-

ation and Process

Monitors (RPM's) which will increase

the staff

from eight to eleven.

Training of the last four

RPM's added to the

staff is approximately 95/ complete.

No items of noncompliance

or deviations

were identified.

-.e

Radiation Protection - Res irator

Protection

The licensee

stated that implemention of the airborne radioactivity

surveillance

and respiratory protection

program would occur approxi-

mately at startup of Unit 1.

The inspector verified that the

licensee's

procedures

addressed

sections 8.d., e., g., h., i., l.,

m.

and n. of Regulatory Guide 8.15.

No items of noncompliance

or deviations

were identified.

5.

Radioactive

Waste

S stems - Offsite Dose Calculation

Manual

{OCDM)

The inspector

examined

a copy of the licensee's

Chemical

A~nal sis

Procedure

No. A-8, Offsite Dose Calculations

and

a draft copy of

the

OCDM Information prepare'd

in response

to the requirement

to

submit an

OCDM as

a part of the Radiological Effluent Technical

Specifications for Unit 1.

The inspector

commented

that, the docu-

ments did not appear to satisfy the intent of the

OCDM but that

documents

would be evaluated

by NRR.

No items of noncompliance

or deviations

were identified.

6.

Gaseous

Radioactive

Waste

S stems - Monitorin

Procedures

The licensee

informed the inspector that the following previously

approved

procedures

examined

as

a part of the Unit

1 inspection

program (IE Inspection Report 50-275/77-21)

would have to be re-

vised

as

a result of the requirements for the

OCDM.

Chemical Analysis Procedure

No. F-8

Noble

Gas Release

Rate Calculations, calculator program for

.calculating

the percent of the release

rate limit for noble

gases

and the dose to the affected

downwind sector at the site

boundary.

Chemical Analysis Procedure

No. F-9

Iodine, Particulate

Tritium and Carbon-14'Release

Rate

Calculations, calculator

program for calcu ating the release

rate,

percent of maximum permissible release

rate and the

sector

dose

due to the release of a mixture of radionuclides

other than noble gases.

No items of noncompliance

or deviations

were identified.

7.

Preo erational Testin

Test data from completed preoperational

tests

were examined to

assure that the test results

were within the previously established

acceptance

criteria and,

as applicable,

deviations

from acceptance

criteria were properly identified and disposed

in accordance

with

the licensee's

administrative procedures.

Records for the followi.ng

completed tests

which had

been

approved

and accepted

by operations

were examined.

Test

No.

19.2.10

Rev.

1

23. 6

Test Descri tion

Flush and

Preop of Reactor Coolant

Drain Tank,

Pumps

and Associated

Piping.

Inplace Testing of Auxiliary and

Fuel

Handling Building Charcoal

and

HEPA

Filters.

23. 9

(Testing performed

by AAF and witnessed

by PG8E personnel.

HEPA filters

tested with cold generated

DOP.

DOP

penetration

less

than 0.035.

Charcoal

filters tested with refrigerant

R-

112.

R-112 penetration

less

than or

equal

to 0.05/.)

Inplace Testing of Control

Room

Yentilation HEPA and Charcoal Filters.

(Performed

by AAF and witnessed

by

PGSE personnel.

Cold generated

DOP

maximum penetration

0;00485.

Refrigerant

R-112 maximum penetration

0.00565.)

No items of noncompliance

or deviations

were identified.

8.

Plant Tour

The inspector toured various areas of common interest of the

containment, auxiliary and turbine buildings with the resident

inspector.

No items of noncompliance

or deviations

were identified.

9.

Exit Interview

The inspector

met with licensee

representatives

(denoted in Para-

graph 1) at the conclusion of the inspection

on February

23,

1979.

The licensee

was informed that no items of noncompliance

had been

identified.

The inspector

summarized

the scope

and findings of the

inspection.

The inspector

requested

that the licensee

keep the

inspector

informed as to the schedule of the emergency

plan drill.

The inspector

informed the licensee that at lease

30 days prior to

the first use of respiratory protection

under

the program author ized

by 10 CFR 20.103,

the licensee

must make the notification required

by 10 CFR 20.103(e).

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