IR 05000206/1976006
| ML20027E200 | |
| Person / Time | |
|---|---|
| Site: | 05000000, San Onofre |
| Issue date: | 07/13/1976 |
| From: | Crews J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Woodbury R SOUTHERN CALIFORNIA EDISON CO. |
| Shared Package | |
| ML20027A625 | List:
|
| References | |
| FOIA-82-394 NUDOCS 8211120246 | |
| Download: ML20027E200 (5) | |
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l Southern California Edison Company Docket lio. 50-206 P. O. Box 800
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2244 Walnut Grove Avenue Rosemead, California 91770
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Attention: !ir. Rollin E. Woodbury Vice President & General Counsel Gentlemen:
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This refers to the inspection conducted by liessrs. !!almros Pate and riorth of this office on June 15-18, 1976, of activities authorized by liRC License lio. DPR-13, and to the discussion of our findings held by l
Messrs. !!almros and tiorth with Messrs. Ottoson, Ray and other members of your staff at the conclusion of the inspection.
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The inspection was an examination of the activities conducted under your
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I license as they relate to radiation safety and to compliance with the
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Commission's rules and regulations and the conditions of your license.
Tne inspection consisted of selective examinations of procedures and
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representative records, interviews with personnel and observations by
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the inspectors.
i Based on the results of this inspection, it appears that one of your activities was not conducted in full compliance with fiRC requirements,
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as set fortn in the flotice of Violation, enclosed herewith as Appendix A.
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This item of noncompliance has been categorized into a level as de-
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scribed in our correspondence to all IIRC licensees cated December 31,
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1974.
This notice is sent to you pursuant to the provisions of Section 2.201 of the llRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations.
Section 2.201 requires jou to submit to this office, within twenty (20) days of your receipt of this notice, a written stater.:ent or explanation in reply including:
(1) corrective steps which have been taken by you and the results achieved; (2) corrective steps wnich will be taken to avoid further violations; and (3) the date when full compliance will be achieved.
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Malmros:smg_ __ Crews
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Tonn ATC.318 (Kev. 9-53) ALC}t 0240 W u. s; sov.RNM.NT PRINTING OF FIC.31974 32 8 8 88 8211120246 820928 PDR FOIA
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RAPKIN82-394 PDR
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Southern Calif.
JUL1~.is Edison Co.
-2-In accordance with Section 2.790 of the HRC'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 to this office, within 20 days of the date of this letter, requesting that such information be withheld from public disclosure.
The application i
must include a full statement of the reasons why it 1s claimed that the information 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
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the Public Document Room.
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Should you have any questions concerning this inspection, we will be glad to discuss then with you.
Sincerely, D6;bi signed by J. L. Cr:ss J. L. Crews, Chief Reactor Operations and Nuclear Support Branch
Enclosures:
A.
IE Inspection Report No. 50-206/76-06
REGION V==
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<IE Inspection Report No.
50-206/76-06
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Licensee Southern California raisnn rn_
Docket No.
50-206 I
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2244 Walnut Grove Avenue
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License No.
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Rosemead, California 91770
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Priority Facility San Onofre Unit 1 Category C
i Location Camp Pendleton, California i-
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Type of Facility PWR (465 MWe, 1347 MWt)
Type of Inspection Routine, Unannounced Dates of Inspection _ June 15-18, 1976 Dates of Previous Inspection March 1-4,1976 (Redctor)
Principal Inspector N/
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M. H. Malmros, Reactor Inspector
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Accompanying Inspectors I
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R. JM Pate, Re ctor Inspector
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Date H. S. North, Radiation Specialist Other Accompanying Personnel: None i
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WI(N W l/l /7(o Revicued by
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J.L/] Cree,' Chief,ReactorOperationsandNuclear
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lj Support Branch
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,E Aa Hu H.E. Book, Chief, Fuel Facility and Materials Safety Date Branch
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Spent Fuel Packaging and Shipping a.
Spent Fuel Storage Area Preparation The inspector verified through discussions with licensee representatives that only one fuel assembly can be out of a safe geometry location at any one time, in that all assembly positions are of safe geometry and the spent fuel pit manipulator crane can handle only one assembly at a time.
The spent fuel pit manipulator crane is not equipped with interlocks, however, crane design limits the height of assembly lift.
Standard operating practice requires movement of assemblies to the south side of the spent fuel pit, to an area not occupied by assembly storage racks, prior to movement in the west-east direction.
Procedures require an annual load testing and certification of cranes and verification of the turbine deck gantry crane limit switch and speed control settings.
The fuel storage building ventilation system is part of the plant ventilation system.
The plant ventilation system HEPA filters were certified by an outside contractor on the basis of hot D0P tests at the time of the last refueling outage. Due to design and operating considerations, Fuel Storage Building isolation does not occur during loading of spent fuel assemblies into the cask.
The ventilation system provides a continuous air flow through the building to the plant ventilation system during spent fuel cask loading.
Spent fuel pool water level is verified by observation.
Operation of the Fuel Storage Building area monitor is verified daily.
The licensee has in the past collected one 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> air sample per week in the spent fuel pit area.
The licensee stated that air sampling in this area would be changed to continuous. The operation of the spent fuel pit cooling and cleanup systems is verified by the licensee during each routine shift tour.
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The inspector verified that the spent fuel pit water level was within the +1 inch limit established by operating procedures, and that the ventilation system was in operation.
b.
Shipping Cask Pre-Loading Activities The licensee maintains a file containing the consignee's SNM license, Certificate of Compliance and other appropriate documentation. An examination of records of previous spent fuel assembly shipments disclosed that the licensee maintains records of the uranium and plutonium in each assembly shipped L
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on form PSSO 228B Shipping Report - Radioactive Material.
The licensee does not maintain a record which identifies mixed fission products and the quantity contained as a constituent in each assembly shipped.
This does not appear to meet the requirements of 10 CFR 71.62(a)(4) which specifies that "the licensee shall maintain...a record of each shipment...of more than a type A quantity of radioactive material... showing... type and quantity of licensed material in each package...".
The licensee's procedures provide for preloading cask inspec-
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tion, verification of fuel assembly spent fuel pit residence time, and gross weight verification.
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Shipping Cask Pre-Shipping Activities The licensee's procedures and control system establish specific requirements' for verifying that:
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(1) The required air void has been established; (2) The cask has been properly sealed; (3) The cask coolant-activity level will not exceed regulatory requirements; (4)
The cask cooling system is functional; (5)
The neutron and gamma dose rates are within regulatory requirements; (6) The cask is secured to the transport vehicle; (7) The cask surface contamination is within regulatory limits.
The above items c(1)-(7) were verified by examination of the records of shipment number S0-135 covering fuel assembly number C-40, which was shipped on May 30, 1976.
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