IR 05000206/1978017
| ML13323A574 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/09/1979 |
| From: | Book H, Curtis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323A573 | List: |
| References | |
| 50-206-78-17, NUDOCS 7902220276 | |
| Download: ML13323A574 (5) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report N /78-17 Docket N License N DPR-13 Safeguards Group Licensee:
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Unit 1 Inspection at:
Camp Pendleton, California Inspection Conducted:
December 19-21, 1978 Inspectors:
/ 9-P 7)
Curtis, Radiation Spciaist Date Signed Date Signed Approved By:
.
H. E. Book, Chief, Fuel Facility and Date Signed Materials Safety Branch Summary:
Inspection on December 19-21, 1978 (Report No. 50-206/78-17)
Areas Inspected:
Routine unannounced inspection of emergency planning, including observation of an emergency drill and drill critique, review of status of revisions to plans, practices and procedures in the emergency response plan; collection of comparative measurement samples and review of reported results of recent samples; discussion with licensee representatives with regard to revisions and improvements to selected radiological control procedures. The inspection involved 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> onsite by one inspecto Results:
No items of noncompliance or deviations were identifie F174 IE:V Form 219 (2)
DETAILS 1. Persons Contacted J. Curran, Plant Manager R. Brunet, Superintendent, Unit 1 M. Sullivan, Chemical-Radiation Protection Supervisor J. Mortensen, Chemical-Radiation Protection Engineer G. Peckham, Chemical-Radiation Protection Engineer D. Bihl, Chemical-Radiation Protection Engineer Other members of the SONGS Staff General Operations The inspector discussed the operations status of the station with licensee representatives responsible for the radiation protection program. The reactor was at full power at the beginning of the inspection with a planned schedule of reducing power to shut-down condition for the dual purpose of (1) allowing for operator licens ing training and qualification and (2) to conduct a planned contain ment sphere entry for a general quality assurance and maintenance check on equipment worked on during the recent refueling outag The sphere entry and work performed within the containment was per formed according to station procedures using pre-entry radiological condition assessment, issuance of Radiological Exposure Permits and Job Tickets for work to be performed. Airborne activity in the sphere was assaye One inspection/maintenance team worked in the area above the reactor vessel adjacent to the vessel head. The personnel exposures re ported for persons involved in the sphere entry were in the range of 30 to 450 mRe The inspector discussed the status of licensee action regarding handling and documentation of instances involving personnel con tamination. Licensee efforts include establishing and formalizing a procedure for documenting these instances, taking protective and preventative action when specific residual contamination levels exist after decontamination attempts, and a management notification system for significant case Licensee plans and proposals for increasing awareness and limiting access to high radiation areas were discussed (Ref. 50-206/78-16).
Possible action and proposals involving increased use of barriers,
-2 entry annunciating devices, and or extensive formalized adminis trative access control methods were being discussed and considere Continued consideration of proposals would be made, but no formal procedural changes will be made to existing controls until the next major-outag No items of noncompliance or deviations were identifie.
Emergency Planning - Tests and Drills The licensee conducts drills of portions of the emergency response plan on a quarterly schedule. The last drill was reviewed with the licensee.. The exercise was held in the early morning hours in the latter part of September 1978 and involved perimeter alarm signal tests and a controlled area evacuation and muster drill. A critique was held and the drill was documented, action was taken to overcome deficiencie The inspector discussed preplanning efforts for the current (December 21st) drill with Mr. G. Peckham, Chemical-Radiation Protection Engineer who was responsible for preparing the drill scenario. Preplanning effort included generation of a scenerio, projected flow chart for the drill, drill messages, and instruc tion to persons responding to submit response time information for communication channels and response effor The December 21st drill was initiated at approximately 9:45 AM when the Chemical-Radiation Protection Engineer notified the Operations Watch Engineer-in-Charge that the emergency exercise was about to begin. The inspector observed the initial response activities from the control room and adjacent visitor viewing area. The visitor viewing area is designated as the onsite control center and evacua tion assembly are The scenario called for the evaluation of emergency radiation monitoring readout information to establish the radiological.con ditions and to decide on the amount of involvement by local offsite agencie The local agencies were put on "alert" status as part of the drill, for a communication link check. The proposed radiologi cal conditions and the actual meteorological conditions were used by the Watch Engineer (W.E.) and Plant Superintendent to establish that no additional offsite action or.evacuation was necessar The drill scenerio called for an "unaccounted for" person at the muster. The W.E./Emergency Coordinator mobilized a search/rescue party who found the "victim" with a "contaminated burn injury."
Rescue, using a litter, was effected and the ambulance service and the agreement hospital were alerted to particpate in the exercis Response by the ambulance was slow, as was anticipated - the ambu lance dispatcher had been advised that the call was.a dril The "victim" was transported to the SCE first aid room by station personnel and to the hospital via ambulance using the SCE special purpose personnel carrier. Some difficulties were encountered in manipulation and transfer of the carrier in and out of the ambulanc At the hospital, emergency room and nuclear accident response personnel did not actively participate in the medical emergency response exercise. The channels of communication within the hospital that would effect coordination of response for the exer cise evidently broke down. Active hospital participation in a nuclear emergency response was being planned by the hospital at a later dat. Emergency Drill - Critique of Exercise Licensee representatives held a critique meeting following the exercise. The inspector attended the meeting attended by the Plant Supervisor and Chemical-Radiation Protection personnel who were observers or participants in the dril Individuals reported on their general observations and any specific problem areas that were made apparent by the exercise. Suggestions for solutions to problems were discussed. The time relationship between the begin ning of the drill and receipt of notification by SCE and offsite response groups is to be submitted to the Radiation Chemical En gineer for response time tabulation and evaluation. Some areas needing attention were noted, e.g., coordination of the hospital nuclear accident response team with SCE, training sessions for security personnel regarding priorities for access/egress for injured personnel, and additional training for operations person nel in use of dose and cloud projection using equations and overlay A written report is being generated reflecting the response time information and reporting on significant items discussed at the critique with proposed action to improve the station's emergency response capabilit No items of noncompliance or deficiencies were identife.
-4 5. Confirmatory Measurements Two categories of samples in the confirmatory measurements were found acceptable by comparison with HSL results. The categories acceptable for the 1978 series were Particulate Filter and Halogen Charcoal Cartridge. During this inspection a liquid sample, (VSL-8) from a waste tank and a gaseous sample (VSG-10) were col lected, counted for preliminary evaluation and submitted to HSL to complete the 1978 series of confirmatory measurement sample Analytical results will be corrected to the collection date of 12/20/78, 11:00 AM for decay correction and gross beta analysis (VSG-10) will be performed by SCE and HSL on 1/17/19, 11:00 A Results will be compared when received by both analytical group No items of noncompliance or deviations were identifie. Exit Interview A brief exit interview was conducted summarizing the inspectio No items of noncompliance or deficiencies were identified.