ML19270F015
| ML19270F015 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/01/1978 |
| From: | Book H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| Shared Package | |
| ML19270F016 | List: |
| References | |
| NUDOCS 7901110164 | |
| Download: ML19270F015 (2) | |
See also: IR 05000344/1978022
Text
, e c ' h a r c ,'I
'
UNI T ED STAIth
[
s&
NUCLE AIt flEGUL A TOf tY CO T/'?.U S SI O N
.,
-
HEGION V
,
O, Nd
s
Lul E 20?, W ALNtir C RF EK PL AZ A
.
%
/
mo n. c Auronnia nouuvAno
- eee*
W ALNUT CRE EK, C AllFORNI A 94306
$: >io
Docket !!o. 50-344
Portland General Electric Company
121 S. W. Salmon Street
Portland, Oregon 97204
Attention: Mr. Charles Goodwin, Jr.
Assistant Vice President
Gentlemen:
Subject: ilRC Inspection - Trojan
This refers to the inspection conducted by Messrs. J. Baird and H. florth
of this office on October 30 - flovember 3,1978 of activities authorized
by fiRC License flo. NPF-1, and to the discussion of our findings held
by Mr. florth with Mr. F. Lamoureaux and other members of your staff at
the conclusion of the inspection.
Areas examined during this inspection are described in the enclosed
inspection report. Within these areas, the inspection consisted of
selective examinations of procedures and representative records, inter-
views with personnel, and observations by the inspectors.
tio items of noncompliance with flRC requirements were identified within
the scope of this inspection.
In accordance with Section 2.790 of the flRC's " Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and
the enclosed inspection report will be placed in the flRC's Public
Document Room.
If this report contains any information that you believe
to be proprietary, it is necessary that you submit a written application
to this office, within 20 days of the date of this letter, requesting
that such information be withheld from public disclosure. The applica-
tion must include a full statement of the reasons why it is claimed that
7901110 V
.
.
'.. :
Portland General Electric Company
-2-
.
the infomation is proprietary. The application should be prepared so
that any proprietary information identified is contained in an enclosure
to the application, since the application without the enclosure will
also be placed in the Public Document Room.
If we do not hear from you
in this regard within the specified period, the report will be placed in
the Public Document Room.
Should you have any questions concerning this inspection, we will be
glad to discuss them with you.
Sincerely,
907
,
.
11. E. Book, Chief
Tuel Facility and Materials
Safety Branch
Enclosure:
IE Inspection Report
tio. 50-344/78-22
cc w/o Enclosure:
B. Withers, PGE
F. C. Gaidos, PGE
. _ _ _ _ . _ _ _ _ _ _ _ _ _ _
-
b
'
!;
.
.
.
I
U. S . NL' CLEAR REGUUsTORY CO:e!ISSION
r
.
OFFICE OF INSPECTION AND ENFORCEMO:T
f
REGION V
Roport No. ,50-344/78-22
y
Docket No.
50-344
License No.
Safeguards Group
j
.
Licensee:
Portland General Electric Company
121 S. W. Salmon Street
Portland, Oregon 97204
Facility Name:
Trojan
Inspection at:
Rainier, Oregon
Inspection conducted: October 30 - November 3,1978
Ins pec t ors :
.
mN
///a/77
J. d.
aird, Radjation Specialist
Dlte sir,ned
i
9
///3 78
H. 3. North, Raifiation Specialist
Date' Signed
-
Date Signed
!
/2 I [7 #
Approved By:
.
H. E. Book, Chief, Fuel Facility and Materials
Date Signed
Safety Branch
Sutrmary :
Inspection on October 30 - November 3,1978 (Report No. 50-344/78-22)
Areas Inspected:
Emeraency planninq including emergency kits, control
center, communications, effluent monitoring systems and survey instru-
ments maintenance, testing and calibration, meteorological monitoring
system calibration; emergency planning test and drill records; radiation
protection including licensee audits, procedures, instrument maintenance
and calibration, external and internal personnel exposure, posting, labeling,
-
control of access, dose rate, contamination and airborne surveys, sealed
I
source leak tests, notification and reports; radioactive effluent releases,
l
liquid and gaseous, records and reports. effluent control instrumentation,
l
procedures; QA and confirmatory measurm ants; and facility tours. The
inspection involved 63 inspector-hours onsite by two NRC Inspectors.
[
Results: No items of noncompliance or deviations were identified.
RV For:r 719(?)
- . - . .
..
'
.
.
DETAILS
1.
Persons Contacted
- F. Lamoureaux, Assistant Plant Superintendent
- T. Walt, Radiation Protection Supervisor
- R. Russell, Assistant Radiation Protection Supervisor
- L. Quinn, Chemistry Supervisor
G. Bailey, Radiation Protection Engineer
D. Sommerville, Radiation Protection Specialist
R. Davis, Plant Chemist
- J. Reid, QA Supervisor
R. Bennett, I&C Supervisor
R. Budzeck, Shift Supervisor
W. Kernion, Chemical and Radiation Protection Technician
T. Nofziger, Instrument Technician
N. Starr, Radiation Protection Records Coordinator
- Denotes those attending the exit interview.
2.
Emergency Planning - Emergency Kits, Control Centers and Communications
The inspectors examined and verified, by comparison with the
inventory list, the contents of two trunks of emergency supplies
at the Visitors Information Center (VIC) - Dnergency Control Center
(ECC). The verification included the calibration dates of two
portable survey instruments, the availability and serviceability
of two self-contained breathing devices and spare air bottles at
the VIC-ECC. The inspectors verified that radio communications
between the control room, plant security and Columbia and Cowlitz
Counties local law enforcement agencies are tested during each
shift.
No items of noncompliance or deviations were identified.
3.
Emergency Planning - Monitoring System and Survey Instruments
Effluent monitoring system and survey instrument calibration
and testing frequency and procedures were examined as a part of the
Radiation Protection and Waste Management portiors of this inspection
and are reported in Paragraphs 7 and 15, respectively.
.
-2-
~.
Meteorological monitoring instruments located in the control room
were examined. The instruments identified in Technical Specification
3.3-8 were observed to be operable.
The control room instruments are
calibrated semiannually, last done on July 26, 1978, by plant I&C
Department.
Field sensors are calibrated semiannually by the
Environmental Services Dept'tment.
No items of noncompliance or deviations were identified.
4.
Emergency Plannina - Tests and Drills
The inspectors examined the Minutes - Radioloofcal Emergency
Response Plan Exercise Critique for the drill conducted September 20,
1978.
No items of noncompliance or deviations were identified.
5.
Radiation Protection - Audits
The inspectors interviewed licensee personnel concerning audits
performed during 1978 by the onsite 0A organization. The licensee's
QA procedure was redesignated in accordance with the licensee's
procedures, as QAP-18 Quality Assurance Surveillance Program,
Rev. 6, effective August 25, 1978. The inspectors examined audit
and surveillance reports principally in the areas of radiation
protection and waste management. Certain reports in the areas of
training, chemistry and calibration were applicable to the areas of
interest and were examined. Reports examined included three in the
area of radiation protection, two in waste management and one each
in chemistry and training. The reports identified a number of items
for which corrective actions were required. Corrective actions had
been initiated, completed or were not required on all items. The
reports effectively documented the audit and surveillance activities
and the corrective actions.
No items of noncompliance or deviations were identified.
6.
Radiation Protection - Procedures
The inspectors reviewed Revisions 6 (July 25,1977) through 12
(October 3, 1978) to the Radiation Protection Manual.
Changes in
the following Radiation Protection Procedures, which have occurred
during 1978, were discussed with licensee personnel; RP-108
Sealed Source Handling Procedur_e_, RP-110 General Employee Radiation
Protection Traininq Occumentation, RP-lll Portable Radiation Detector
Source Checks, RP-ll2 Personnel and Clothing Report, RP-115
Respirator Medical Evaluation.
-3-
.
.
RP-ll8 Chemical and Radiation Protection Trainino, first issued
September 20,197iC was examined in detiil .
The procedure documents
technician replacement and retraining requirements and specifies
attendance, evaluation (testing), docunentation and traininq recuire-
ments.
Changes in the Radiation Protection f4anual and Procedures were
found to be consistent with regulatory requirements, the technical
specifications and FSAR requirements. The licensee is performing
reviews and is approving revised procedures as required by A0-4-5
Plant Operatina flanual Procedure Review. Revised procedures were
distributed to the appropriate individuals as required.
flo items of noncompliance or deviations were identified.
7.
Radiation Protection - Instruments and Equipment
The licensee's Radiation Protection toeasurinq and Test Equipment
Calibration Procram described in.the Radiation Protection fianual
was examined. A master calibration schedule is maintained as well
as individual maintenance and calibration records for each instrument.
Calibrations are performed by chemical and radiation protection
technicians in accordance with specific written procedures for each
instrument type.
Instruments calibrated included portable survey,
constant air monitoring and portable air sampling (calibration
includes air flow), and pocket ionization chambers (PIC's). On the
basis of discussions with licensee personnel and examination of a
random sample of instruments, master calibration schedule data and
individual instrument calibration records, it appears that instruments
are calibrated and maintained in accordance with and at the frequency
required by the licensee's procedures.
flo items of noncompliance or deviations were identified.
8.
Radiation Protection - External Exposures
The licensee uses Eberline supplied and processed TLD's, exchanged
on a monthly basis. PIC's are used to supplament TLD data.
Finger
TLD's are used for specific work involving possible higher extremity
exposures, i.e., steam generator tube or valve disassembly work.
Approximately 250 TLD's are permanently assigned with an additional
250 used on a nonpermanent assignment basis. Visitors are monitored
using a PIC assigned to the tour guide. The guide has in addition
a permanently assigned TLD. The licensee is currently revising the
procedures related to personnel monitoring, RP-108 - Personnel
Dosimetry Proaram, which provides detailed instructions in issuance,
use and handling. The licensee also prepared a Review Guide for
Personnel Exposure Files and has been reviewing all indTifdiial
-4-
,
exposure files to verify that the files are conplete and current.
The licensee maintains individual files on each person subject to
personnal ronitoring control.
The files contain completed fcres
flRC-4 and 5 (or equivalent), external and internal exposure records,
authorizations for increased exposure and any special reports
(i.e., personnel contamination reports, lost or discharged PIC's or
lost TLD's).
The licensee has found that neither neutron PIC's nor TLD's provide
adequate neutron monitoring capabilities.
For 1977, individual
neutron doses were calculated from containment entry RWP records
and neutron to gamma ratios determined by surveys.
In the future,
the licensee plans to use flTA film to evaluate neutron exposures, the
film to be returned to U.S. Testing, Richland, Washington within
ten days after exposure to minimize fading.
In addition, stay time
and neutron survey results will be used to calculate neutron exposures.
Records of exposures for the first three quarters of 1978 were
examined. The highest quarterly exposure was 1.237 rem. The
highest total exposure for the first three quarters was 1.898 rem.
Total measured exposure for 1978 through August was 174.7 man rem
based on TLD's and 168.0 man rem based on PIC's.
A number of individual
exposure records were examined. The records examined included
completed forms flRC-4 and satisfied the requirements of 1C CFR
20.401(a). fio exposures in excess of limits were identified with
the exception of the two exposures associated with the fuel element
transfer tube (IE Inspection Report 50-344/78-11). The licensee's
procedures limit exposure to minors to ten percent of the 10 CFR 20.101(a) limit. The licensee stated that persons under the age of
18 are not employed in the restricted area. The Personnel Exposure
Investiaation Log, reports 78-1 through 78-75 were examined. Most
reports concerned lost PIC's or TLD's or PIC's off scale due to
shock.
flo items of noncompliance or deviations were identified.
9.
Radiation Protection - Internal Exposures
The inspector examined selected bioassay records and air sampling
records associated with the survey program. The Radiation Protection
Manual requires for individuals assigned to work in the controlled
access area, initial, annual and termination whole body counts of
licensee enployees and initial and termination whole body counts of
others when the airborne activity of particulates and halogens is
greater than 25% of the MPC. The procedures also require strontium
urine analysis where internal fission product deposition is greater
-5-
.
than 10% of the maximum permissible body burden. Tritium analyses are
rerformed on urine sanples from selected personnel involved in fuel
h iling. Whole body counts are performed usinq an onsite Peloeson
th.ulear Service Company whole body counter.
Records of whole body
cosnting from December 29, 1977 through September 29,1978 were
examined. A total of 1018 persons were counted during this period.
Maximum values of identified nuclides were as follows:
fluclide
Observed (nCi)
MPBB*(nCi)
% of MPBB
Cs-134
53
20,000
0.26
129.4
30,000
0.43
Co-58
1296.5(1)
2,900
45
196.7
1,100
18
11
700
1.5
5.2
3,600
0.14
ZrNB-95
19
1,600
1.2
- Maximum Permissible Body Burden reported by Helgeson fluclear
Service Company
(1) The individual with the high Co-58 value was a Westinghouse
crud sampler. The initial whole body count on this individual,
prior to his entry into the restricted area, indicated Co-58
and Co-60 levels of approximately 1 and 1.5 percent of the
MPBB respectively. Whole body counting following the conclusion
of his work indicated uniformly distributed contamination with
Co-58 and Co-60 at approximately 45 and 11 percent of the MPBB.
After four showers and shampoos activity levels of Co-58 and
Co-60 had been reduced to approximately 12 and 3 percent of
the MPBB respectively. The contamination was uniformly
distributed indicating external contamination.
As a part of the routine monitoring program, CARP's record Continuous
Air Monitor (CAM) readings on survey records and the collection and
results of analysis of air samples.
In addition, grab air samples
are collected to evaluate airborne cctivity when required. The results
of analysis of particulate and halogen samples are included in the
survey records.
The licensee issued an interim Radiation Protection Policy to CARP's
on June 2,1978.
The policy states that use of portable air samplers
is required when activities or conditions might result in airborne
activity and a CAM is not available at the location of interest.
-6-
.
The policy prohibits the use of Process and Effluent Monitor (PERM)
data in such cases. Air sampling is specifically required when
opening contanina, d systens cr where surface contamination exceeds
20,000 cpm /100 cm
Survey records including air sampling results for the period March
- M y 1978 were examined. Airborne activity was generally less than
10~3uCi/cc. The licensee stated that no credit had been taken
-
for the use of respiratory protection devices. The licensee's
implementation of the respiratory protection program will be examined
during a subsequent inspection.
No items of noncompliance or deviations were identified.
10.
Radiation Protection - Posting, Labeling and Control
During a tour of the facility, the inspectors observed posting and
control of access to radiation and high radiation areas, labeling
of containers of radioactive material and posting of radioactive
material storage areas. An examination of the licensee's procedures
verified that they address the requirements for posting, labeling
and control of access. The licensee's Radiation Work Permit (RWP)
procedures require that all entries to the controlled access area
be nade under an RUP.
RWP's in effect specified the work and location
covered by the RWP and the protective cl7 thing and dosimetry
requirements, provided for special instructions and the recording of
sign in-and-out times and PIC readings.
The inspectors noted that a form NRC-3 and the notice required by
10 CFR 19.11 were posted at the access control point.
No items of noncompliance or deviations were identified.
11.
Radiation Protection - Surveys
The licensee's procedures provide for routine and special surveys
for radiation levels, contamination and airborne activity. The
survey records distinguish between penetrating and nonpenetrating
radiation and in association with surveys for RWP implementation,
identify areas where extremity exposure monitoring is required.
Survey procedures also address personnel surveys performed on
departure from the controlled access area. Neutron rem meter
surveys are performed during containment entries when the reactor
is operating. Survey records for the period March through May
1978 were examined. The licensee's Personnel Contamination Log
.
.
-7-
.
and _ personnel Contamination Reports 78-1 through 78-93 were examined.
The Rad Con Log, September 1 through October 15, 1978 and the CARP
Rotating Technician Log (beginning) October 15 through October 31,
-
T378 were examined.
Technical Specification 3/4.7.7 Sealed Source Contanination, requires
the performance of tests of sealed sources for contamination at
specified intervals. The licensee's records of tests for source
contamination from July 11, 1977 through July 28, 1978 were examined,
llo items of noncompliance or deviations were identified.
12.
Radiation Protection - flotification and Reports
The licensee representative stated that there had been no losses
or thefts of licensed material and no unreported incidents. Technical Specification 6.9.1.5.a. requires the submission of an annual report
of station, utility, and othee personnel receiving exposures greater
than 100 mrem / year and their associated man rem exposure according
to work and job function. Title 10 CFR 20.407 requires the sub-
mission of a statistical summary report of personnel monitoring
durinq the preceding calendar year.
Regulatory Guide 1.16, C.l.b.
(2)(f) requires a report of any single release or radiation exposure
specifically associated with an outage which accounts for more than
10 percent of the allowable annual values.
The three required reports identified above for calendar year 1977
were submitted in a timely fashion as a part of the Annual Operating
Report for 1977. The identified reports were examined as a part of
the inspection. flo discrepancies or anomalous information was
identified.
flo items of noncompliance or deviations were identified.
13.
Radioactive Waste Sysiems - Liquid and Gaseous Technical
Specification Requiro1ents
Technical Specificat ans, Appendix B, Paragraphs 2.4.2, 2.4.3,
2.4.5 and 2.4.6 identify the specifications for concentrations,
release iates, effluent monitoring, maximum tank contents, un-
planned or uncontrolled releases, and requirements for sampling
and monitor calibration for liquid and gaseous radioactive waste
monitoring and release. The inspectors discussed and examined
records concerning licensee procedures, practices and implementation
of the requirements related to sampling, analysis, limits on release
rates, concentrations, limitations on tank contents, and monitoring
of release pathways for liquid and gaseous wastes.
. -
-8-
.
.
flo items of noncompliance or deviations were identified.
14
Padioactive Waste Systens - Liquids and Gaseous - Records
and Reports
The inspectors examined the licensee's semiannual Radioactive
Effluent Release _ Report for the period January 1,1977 through
June 30,1978, required by Technical Specification Appendix B,
5.5.1.b; Gaseous Discharge Permits. G-1-78 (January 13, 1978)
through G-32-78 (October 9, 1978); and Radioactive Liquid Waste
Discharge Pemits 1/78 through 26/78 (January 1978) and 98/78
(April 197'8) through 120/78 (October 1978). The Gaseous Discharge
Pemits contain the following information; discharge type, maximum
and actual discharge rate (uCi/sec), operational status of process
and effluent monitors (PER'4) and meteorological sensing and recording
system, meteorological parameters (wind speed and direction, hourly
during release), fan operating status, average PERM reading during
discharge, initial and final tank / containment pressure and time
of start and conclusion of discharge. The Radioactive Liquid, Waste
Discharce Permits contain the following information; tank identity,
initial level and volume, flow rate, time and volume recirculated,
PERM setpoints and background, maximum release rate. average
PERM reading during discharge, total discharge time, final tank
level and volume discharged, average and maximum dilution flow.
Cumulative records of liquid releases and gaseous dose calculations
are maintained and used in evaluating proposed releases.
No items of noncompliance or deviations were identified.
15.
Radioactive Waste Systen - Effluent Control Instrumentation
Technical Specifications 2.4.2.e, 2.4.3.f, 2.4.5.d, and 2.4.6.d
require for liquid and gaseous monitoring systems a quarterly
demonstration of the automatic isolation system, a quarterly NBS
traceable monitor calibration, monthly functional tests and daily
instrument checks.
The inspectors discussed and reviewed test and calibration procedures
and examined records of calibrations (January, April, July and
October,1978) and functional tests including isolation valve
operational tests which are performed monthly (November 18, 1977 to
October 2,1978) for the following instruments:
PERM-1
Containment Monitoring System
PERM-2
Auxiliary Building Vent Exhaust Monitoring System