IR 05000206/1977009
| ML20027E241 | |
| Person / Time | |
|---|---|
| Site: | 05000000, San Onofre |
| Issue date: | 06/21/1977 |
| From: | Book H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Woodbury R SOUTHERN CALIFORNIA EDISON CO. |
| Shared Package | |
| ML20027A625 | List:
|
| References | |
| FOIA-82-394 NUDOCS 8211120295 | |
| Download: ML20027E241 (5) | |
Text
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JUN 2 3 g Docket No. 50-206 Southern California Edison Company P. O. Box 800
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2244 Walnut Grove Avenue Rosemead. Califor.nia 91770
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Attention: Mr. Rollin E. Woodbury Vice President and General Counsel Gentlemen:
Subject: Inspection of Southern California Edison Company San Onofre Unit.1 This refers to the inspection conducted by ftr. H. fiorth of this office on April 18-22 and May 26-27, 1977 of activities authorized by fiRC l.icense ib. DPR-13, and to the discussion of our findings held bv
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Mr. ilorth with fir. H. Ottoson and other members of your staff at the
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conclusion of the inspection.
The inspection was an examination of the activities conducted under your license as they relate to radiation safety and to compliance with the Comission's rules and regulations and the conditions of The inspection consisted of selective examinations of
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your license.
procedures and representative records, interviews with personnel and
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j observations by the inspector.
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Based on the results of this inspection, it appears that one of your activities was not conducted in full compliance with fiRC requirements,-
as set forth in the riotice of Violation, enclosed herewith as i
This item of noncompliance has been categorized into a Appendix A.
level as described in our correspondence to all liRC licensees dated i
j December 31, 1974.
i This notice is sent to you pursuant to the provisions of Section 2.201 of the liRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations. Section 2.201 requires you to submit to this office within twenty (20) days of your receipt of this notice, a written I
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.. . SbuthernCaliforniaEdisonCompany-2-JUN 211977 statement or explanation in reply including: (1)correctivesteps which have been taken by you and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved.
In accordance with Section 2.790 of the NRC'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 NRC'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 J 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 the information is proprietary. The application should be prepared so .. that any proprietary information identified is contained in an enclosure .. J 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.
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Should you have any questions concerning this inspection, we will be
glad to discuss them with you.
Sincerely, Original signed by F. A. Wenslawski.$ Herbert E. Book, Chief Fuel Facility and Maierials Safety Branch . i
Enclosures:
i 1.
Appendix A - Notice of Violation 2.
IE Inspection Report No.
50-206/77-09 ,
REGION V== Report No.
77-09 Docket No.
50-206 License No.
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 conducte'd: April 18-22 and May 26-27, 1977 [[M/77 Inspectors: y H. S. North, Radiation Specialist Dhte Signed , !' Date Signed , Date Signed l Approved By-om j 6 /d//77 . Herbert E. Book, Chief, Fuel Facility and Da'te Signed ' ' , Materials Safety Branch Summary: . Inspection on April 18-22 and May 26-27, 1977 (Report No.
, 50-206/77-09) . Areas Inspected: Routine, unannounced inspection of radiation protection program including, personnel qualifications; internal audits; training; external and internal exposure control and documentation; I notifications and reports.
Radioactive waste management; quality control i and confirmatory measurements (separate report). Spent fuel packaging and shipping including storage area preparation; shipping cask pre-loading activities; shipping cask preshipment activities; observed first fuel shipment in the current campaign.
Emergency planning including facilities, equipment and procedure changes; emergency kits; medical arrangements; training; implementing procedures; tests and drills performed and records.
Review and followup of licensee reported events and personnel exposures.
Verified corrective action on previously identified -noncompliance items. The inspection involved 38 inspector hours on-site by one inspector.
- Results: Of the 16 areas inspected, no apparent items of noncompliance or deviations were identified in 15 areas; one apparent item of noncompliance was identified in one area (infraction - personnel exposure in excess of limits - Paragraph 19).
.. , , , IE:V Form 219 (2) ,
. .,. . -5-in Paragraphs 17 and 20 of the Details.
Three reports of possible exposures in excess of the limits of 10 CFR 20.405(a) were submitted including the previously identified report submitted pursuant to 10 CFR 20.403.
Details relating to the possible exposures are reported in Paragraphs 17,18 and 19 of Details.
No items of noncompliance or deviations were identified.
9.
Radwaste System - QC and Confirmatory Measurements The inspector discussed changes in the QC program and established that no changes had been made in the analytical QC procedures since June 1976. Specific individuals are assigned technical and administrative responsibility for the analytical program.
-- Instrument calibration procedures provide for the identification and correction of analytical errors. A contractor provides strontium and plant stack composite filter analysis service.
The contractor conducts an internal quality control program.
Instrument calibration procedures and tests were discussed and examined.
Calibration standards were identified, and records of calibration were examined.
Liquid and gaseous waste samples and a particulate filter and charcoal cartridge were obtained and sent for analysis at an NRC laboratory.
The results of the comparisons will be contained in a subsequent report.
No items of noncompliance or deviations were identified.
Spent Fuel Packaging and Shipping Discussion with licensee representatives, review of procedures and observations established that the following spent fuel storage area preparations were included: a.
Limit imposed on the number of fuel assemblies out of safe geometry at one time; b.
Turbint gantry crane cannot pass over spent fuel storage area; c.
Loaded cask is within the weight limit of the turbine gantry crane; d.
Ventilation system operates on a continuous basis, failure is signaled in control room; e.
Filter bank 00P tested on installation, no requirements for retest; f.
Spent fuel building isolation during spent fuel loading not required; L
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Minimum pool water level verified by pool level alarm and, mark on side of pool, and visually by the inspector; h.
Procedures require radiation protection coverage and air sampler operation; i.
Radwaste system capable of processing cask and cleaning water.
The following shipping cask preloading_ activities were verified by discussion and a review of records: a.
Current file of required documentation relating to fuel shipments is maintained; b.
Procedures require cask conformance and condition verification; c.
Inspection and test of cask head closure; d.
Independent verification of fuel by assembly number and residence time, includes burnup and discharge date, confirmed by temperature measurements after loading; Turbine gantry crane is tested by State-approved inspector.
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The licensee's procedures provide for: a.
Establishing an air void on wet shipments; b.
Verifying cask properly sealed; Flushing and repeat analysis verify coolant activity c.
for both wet and dry shipments; d.
Cask surveyed on receipt and shipment for gamma and neutron dose rates; e.
Cask attachment to vehicle verified on procedure check list; f.
Cask surveyed for smearable activity, not released in excess of limits.
Records of shipment of assembly number D-03 examined and require-ments verified. Observed shipment of assembly number D-03 from the site on the evening of April 18, 1977.
No items of noncompliance or deviations were identified.
11.
Changes in Emergency Plan Facilities, Equipment and Procedures The inspector determined that there had been tio changes in facilities or equipment since the last inspection. A total of nine emergency procedures, series S-VIII, reviewed or revised since the last inspection were examined. Meeting minutes were examined to verify that two randomly selected procedures were , i }}