ML13323A563
| ML13323A563 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/03/1978 |
| From: | Curtis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323A564 | List: |
| References | |
| 50-206-78-15, NUDOCS 7812150185 | |
| Download: ML13323A563 (5) | |
See also: IR 05000206/1978015
Text
U. S.
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report No. 50-206/78-16
Docket No. 50-206
License No, DPR-13
Safeguards Group
Licensee:
Southern California Edison Company
P. 0. Box 800, 2244 Walnut Grove Avenue
Rosemead, California 91770
Facility Name: San Onofre Unit 1
Inspection at:
Camp Pendleton, California
Inspection conduct d 2 October 16-19, 1978
Inspectors: 9/r
X7
W. R. Curtis, Radiation Specialist
/
sate Signed
Date Signed
Date Signed
Approved
By:
21c7_
E. Book, Chief, Fuel Facility and Materials
Date Signed
Safety Branch
Summary:
Inspection on October 16-19, 1978 (Report No. 50-206/78-16)
Areas Inspected:
Routine, unannounced inspection of the Radiation Pro
tection Program during the refueling outage, and some followup activity
related to the status of confirmatory measurement sample analysis, and
emergency plan tests and drills.
The inspection involved 38
man-hours
onsite by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
RV Form ?19(2)
7812 150(5 5
DETAILS
Persons Contacted
- J. Curran, Plant Manager
- R. Brunet, Superintendent Unit 1
- M. Sullivan, Chemical Rad-Protection Supervisor
J. Mortensen, Chemical Rad-Protection Engineer
G. Peckham, Chemical Rad-Protection Engineer
D. Bihi, Chemical Rad-Protection Engineer
- G. McDonald, QA/QC Supervisor
- D. Dunn, QA Supervisor
- H. Key, Chemical Rad-Protection Foreman
The inspector also interviewed other members of the SONGS-1 staff.
- Denotes attendance at exit interview.
2. Radiation Protection Procedures
Samples of radiation protection procedures related to operations
conducted during the refueling outage were reviewed. Changes in
procedures related to access control, tabulation and maintenance of
airborne radioactivity'and external personnel radiation exposure
had been made and were put into effect. They were beneficial to
the access control and radiation.protection effort.
The licensee has a program for periodic review of procedures that
is in use and the Chemical/Radiation Protection Supervisor has
initiated additional radiation protection procedure review effort
by a staff radiation protection engineer.
No items of noncompliance or deviations were identified.
3. Advance Planning and Preparation
Licensee representatives of the radiation protection staff were
interviewed regarding plans and preparations for the refueling
outage. The inspector observed that these plans and procedures
were being utilized in the radiation protection program during the
outage.
No items of noncompliance or deviations were identified.
-2
4.
Training
Radiation protection training for the refueling met the require
ments of licensee procedures and 10 CFR 19.12. In some cases
involving the requirements for authorized access to the containment
sphere, formalized walk-thru indoctrination tours and documentation
had not been accomplished. This was discussed at the exit inter
view and licensee representatives indicated that the qualification
procedure would be formalized to assure that the formal indoctrina
tion tours would be accomplished and documented in the future.
No items of noncompliance or deviations were identified.
5. External Exposure Control
The licensee utilizes a sophisticated system for documentation and
updating of records of personnel exposure. Self-reading dosimeters
are used to indicate short term exposure. These are supplementary
devices to the SCE TLD and Landaur film dosimeters used. The
accumulated exposure for all persons entering the controlled area
is updated at least daily. Quarterly exposure limits for individuals
is controlled by limiting access to radiation areas. Whenever the
individual's reported dose exceeds 1800 mRem, written management
approval is required to authorize further access to the controlled
area. The individual's monthly personal dosimeter is processed and
his official exposure updated before access is allowed.
There was no evidence of personnel exposure exceeding regulatory
limits.
No items of noncompliance or deviations were identified.
6. Respiratory Protection Program
The licensee has an established program for evaluating airborne
radioactivity based on air sample analysis and the determination of
average airborne radioactivity concentration. The routine air
sampling program has been expanded to cover more area during the
refueling outage. Special air samples, special precautions and
engineering controls are utilized on projects when unusual airborne
activity is anticipated.
Respiratory protection has been formally prescribed for steam
generator tube plugging operations. Approved filtered air hoods
are utilized in this operation and a protection factor of 1000 is
applied to air sample data.
Assignments of MPC hour exposure are made and tabulated for all
persons who enter areas when airborne activity is anticipated and
air samples are taken.
-3
SCE radiation protection staff members were interviewed regarding
training for.use, fitting, maintenance and storage of the self
contained, filtered air hoods usedin the respiratory protection
program. Licensee action in this area was adequate; to date the
use was of limited scope. The maintenance program had not been
formalized and documentation of various aspects of the program was
being established. This was discussed at the exit interview and
licensee management representatives indicated that action to im
prove documentation and formalization of the program would be
taken.
No items of noncompliance or deviations were identified.
7. Posting and Access Control
The licensee's program for refueling outage surveillance includes
special and routine surveys in the containment sphere and other
portions of the controlled area. Appropriate signs are posted at
the access control points. The containment sphere is posted as a
Locations at which significant radiation
levels are measured are posted with signs and, in some cases, by
barriers and signs. Radiation levels indicated are related to
levels found during routine or special surveys.
One area at the -10 foot level of the containment sphere was posted
with a sign indicating significantly higher radiation levels. A
radiation level of 200 R/hr was detectable in a generally in
accessible area when measured with an extended probe, teletector
survey instrument. Sheet lead and bags of lead shot shielding had
been placed in and around the location and barriers with signs had
been erected around the general area. General access to the con
tainment sphere is controlled and a system utilizing colored arm
bands and work permits was utilized to further control access
within the sphere.
No items of noncompliance or deviations were identified.
8. Surveys
See Item 7, Posting ...
above. Interviews with licensee staff were
conducted regarding the survey program for refueling operations.
Sample records of routine swipe and radiation levels were examined.
No items of noncompliance or deviations were identified.
9. Confirmatory Measurements
The inspector discussed the status of results of the analysis of
confirmatory measurement samples. Mock charcoal cartridge and
particulate filter samples have been provided. They have been
-4
analyzed on the licensee's GeLi detector/multi-channel analyzer
system.
Isotopes were identified and activities as of July 1, 1978
were being calculated and would be submitted to Region V.
No items of noncompliance or deviations were identified.
10. Emergency Plan Tests and Drills
Continued licensee activity regarding emergency response review and
planning for tests and drills was reviewed by the inspector. The
June 13, 1978 drill was principally involved with offsite mobili
zation and communication, and did not involve onsite personnel to a
great extent. Licensee management was asked for clarification
regarding their understanding of the requirement for an annual
exercise involving onsite personnel and coordination with offsite
response groups, at least at the level of communication link checks.
The next exercise is projected to involve onsite personnel and
licensee representatives indicated that offsite communication links
would be incorporated in the drill to meet the annual drill require
ment.
No items of noncompliance or deviations were identified.
11.
Exit Interview
An exit conference was held with SONGS-1 staff and management
personnel (denoted in Paragraph 1) to review the scope and findings
of the inspection including those items referred to in Paragraph 4, 6
and 10 of this report. The inspector advised licensee represent
atives that no items of noncompliance were. identified.