IR 05000206/1975004
| ML20027E194 | |
| Person / Time | |
|---|---|
| Site: | 05000000, San Onofre |
| Issue date: | 06/03/1976 |
| From: | Fish R, North H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20027A625 | List:
|
| References | |
| FOIA-82-394 PNO-760603, NUDOCS 8211120226 | |
| Download: ML20027E194 (6) | |
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IDEhIIFICATION k
Name (Facility or Licensee):6MhpoF/fNcLtd sucard: Rsur
"P P/#- / 3 Event Date: -5s72_.5'/7/.o M
' Docket No: g y.c o M _ License No:
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Ys Event Description: ?c c ci h7 CG OPF/JT EML l*MSK/VA$-/8 M r's qI cc,vo in scewu mnm.m. - kmumeenrx~u~ra> zz, c.-o apm /ocen h
'Notifieation Date :.s'/rf/76.$725/76 Tim 6 : //// f - /v'es' Method : 7E#tv- /~#X W
Notified By: N Sem ergs - /fSu d, w Notification Received By: # A/5s - led
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b Regulation Requiring the Report
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' PRELIMINARY RESPONSE M[
Importance Category and Response Level:
I II
, III X, Other
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I::=;ediate Site Insp/ Invest Required:
)Vo Report No:
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Individual Date and Time Notified NRC:HQ
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Press Release:
Issued by Licensee (Date)
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SCREENING.
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Have reporting requirenents been met?
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Is the Licensee Event Report (LER) Form complete and do responses hjij; '
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Is the description adequate to assess the event?
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Have corrective actions been identified?
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Do proposed corrective actions appear appropriate?
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Is enforeccent action by IE appropriate?
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Date written report due from Licensee?
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wi EVALUATION
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ES Evaluation Assigned To:
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Has the cause been identified?
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If not, has an investigation program been identified?
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Have the safety implications been identified?
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within the facility been Bas the generic applicability */ d(Z
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considered?
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Do generic aspects warrant IE action?
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Do the f acts warrant other actions bi the Licensee?
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Evaluation assistance requested:
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Recom:nended followup actions:
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Resolution of IE concerns identified above:
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Date:
Completed By:
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T ffJed Date: 4 '/ 7 / '76 k
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U S. NUCLEAR REGULATORY CO.T11SSION
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- * OFFICE OF INSPECTION AND ENFORCEMENT
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REGION V
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.: IE Inspection Report No. En-?ngf75_nA
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Docket No. 50-206 i
Licensee Southern California Friicnn rnm. nan,,
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2244 Walnut Grove Avenue
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License No. DPR-13
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Rosemead, California 91770 Priority
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Facility San Onofre Unit 1
- Category C
Location Camp Pendleton, Califor'nia
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i'ype of Facility PWR (450 MWe,1347 MWt)
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Type of InspectionRoutine, Unannounced
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I Dates of InspectionJuly 8-11, 1975 Dates of Previotis Inspection Ancil 21 7t, 1075
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Principal Inspector s.
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R. T. Dodds, Reactor Inspector
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7/M'/70_
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Accompanying Inspectors
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/ Datd R. F. Fish, Radiatien Specialist
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Date
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Other Accompanying Personnel:
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Reviewed by WW-
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Date
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G. S. Spence ()r, Chief, Reactor Testing & Operations Branch i
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H. E. Book', Chief, Radiolo*gical & Environmental
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Date
Frotection Branch
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12.
Survey Program and Records The licensee's survey program was found to be as described in paragraph 4 of inspection report No. 50-206/74-06.
During this inspection the routine daily and weekly radiation (smear and direct radiation) and special survey records for the period January 1 through June 30, 1975 were examined on a random basis.
This exami-nation disclosed that removable contamination levels within the controlled and exclusion areas generally were lets than in the previous year. No significant contamination was found in the uncontrolled areas (station limit 1,000 disintegrations per square foot). The special survey made inside the containment sphere shortly after shutdown for refueling showed radiation levels of 1-50 mR/hr on the operating deck, 250-1500 mR/hr around the pres-surizer and 50-500 mR/hr around the coolant pumps. A special survey was made prior to a diver entering the transfer area of the fuel storage pool for the purpose of repairing the fuel upender. The survey showed that radiation levels varied over the range of 65-115 mR/hr from pool bottom to a height of 20 feet.
The~ contamination levels and radiation levels shown on the survey records examined were not considered to be excessive for the areas in which they existed.
The records of spent fuel shipping cask a veys made during the period May 1 through July 9,1975 were also examined. A survey of I
the empty cask has been made when received at the plant.
Surveys
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f were also made when the loaded cask was on the decontamination pad and when loaded on the truck trailer. These surveys include direct radiation measurements and smears for detecting removable contami-nation levels. The radiation levels at three feet from the loaded cask varied between 0.2 and 4 mR/hr. Removable contamination levels on the loaded cask varied over the range of 0 to 2040 disintegrations per minute per 100 square centimeters.
In order to reduce the possibility of contamination problems during the shipping process, the licensee has recently modified the loading procedure by (a)
wetting the cask with demineralized water prior to placing it in the and (pool, (b) shortening the time the cask is in the fuel pool,c) in fuel nation.
13. Respiratory Protection Program This inspection showed that the present program was found to be as described in paragraph 8 of inspection report No. 50-206/74-06.
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-13-isolation valves associated with certain of the monitors.
The portable survey meters have been calibrated by the chemical-radiation technicians, except that an instrument technician is present during the calibration of the teletector instruments.
The records showed that, since January 1,1975, these survey meters have been calibrated every three months, except for the neutron meters which have been calibrated every six months. The area monitors have been calibrated on a monthly frequency by the instrument technicians with appropriate records made.
The process monitors have been calibrated at least every six months.
Included in this calibration is the calibration of the radwaste discharge flow meter. The examination of the process monitor calibration records showed they were perfor..ied as required with satisfactory results except for the component cooling system liquid monitor.
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The results of the source calibration were not recorded because high background readings interfered with the calibration.
This condition, which existed starting with the April 2,1973 calibration, was corrected and a satisfactory calibration accomplished on March 17,1975.
16. Shipping and Receiving Radioactive Materials
/ The shipping of radioactive materials involves solid radioactive waste, contaminated clothing and spend fuel elements.
The only recent receipt of such material has been the contaminated (inside)
empty fuel casks. Procedures for such receipt and shipping have been prepared and followed.
Forms have been used to record the pertinent data for these actions.
Included in the records are the date of the shipment or receipt, the isotope (s) involved, tne radiation and contamination levels on the outside of the container (s).
The records for the period October 1974 through July 9,1975 were examined.
The required information was being recorded.
17. Radioactive Waste Records The records showing the release of liquid and gaseous radioactive wastes to the environment during the period July 1,1974 through June 30,1975 were examined on a random basis.
The'se records include the individual release permits and the monthly sunmary data.
The initial authorization to release a batch (liquid tank, waste decay tank or purge of the sphere) has been based upon the analyti-cal results of samples from the tank to be released or the contain-ment sphere.
The wastes actually released excluding the gaseous wastes released directly through the stack (i.e., sphere purges),
have been based upon the proportional samples taken afte'r the mechanical filter (liquid) and the cryogenic system (gas) - see
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