ML20042G290
| ML20042G290 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/01/1990 |
| From: | Kokajko L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20042G265 | List: |
| References | |
| NUDOCS 9005140048 | |
| Download: ML20042G290 (4) | |
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMIS$10N SOUTHERN CALIFORNIA EDISON COMPANY ET AL.
DOCKET NOS. 50-361 AND 50-362 NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U.S. Nuclear Regulatory Comission (Comission) has issued Amendment No. 87 to Facility Operating License No. NPF-10 and Amendment No. 77 to Facility Operating License No. NPF-15, issued to Southern California Edison Company, San Diego Gas and Electric Company, The City of Riverside, California and The City of Anaheim, California (the licensees), which revised the Technical l
Specifications for operation of the San Onofre Nuclear Generating Station, Unit Nos. 2 and 3, located in San Diego County, California.
The amendments were effective as of the date of issuance.
These amendments revised the following Technical Specifications:
TechnicalSpecification5.6.1(b)changedthecurrent12.75 inches center-to center rack storage location spacing to 10.40 inches center-to center spacing for Region I, and 8.85 inches center-to-center spacing for Region II.
Existing Technical Specification 5.6.2 for dry storage of the first core in the fuel pool in alternate rows and columns was deleted. This Technical Specification was sly applicable for the first core and the pool is filled with. ter which is maintained at a minimum level as prescribed by Technical Specification 3.9.11, ' Water level -- Storage Pool.'
New Technical Specification 5.6.2 and accompanying Figures 5.6.1, 5.6-2, 5.6-3, and 5.6-4 defines the fuel enrichment /
burnup limits for storage of Units 1, 2, and 3 fuel in Region II of the high capacity spent fuel storage racks. This new Technical S>ecification defines the conditions and storage satterns (cieckerboard or alternating row) which new or
>urned fuel that does not meet the enrichment vs. burnup criteria for unrestricted storage in Region II may be stored in Region II.
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Lastly, this new Technical Specification defines the conditions k
(empty-alternatingcells-empty)underwhichanew/ burned fuel reconstitution station may be established in Region II.
l-Technical Specification 5.6.4 was revised to designate that no i
more than 1542 fuel assemblies may be stored in the spent fuel racks which is an increase of 742 from the current limit of 800 elements.
i Technical Specification 3.9.7 was revised to prohibit the lift of construction heavy loads over the spent fuel or cask pools except for the following four cases:
l Spent fuel pool gates shall not be carried at a height i
greater than 30 inches (elevation 36 feet 4 inches) over the fuel racks.
Test equipment skid (4500 pounds) shall not be carried at a height greater than 72 inches (elevation 39 feet 10 inches) over rack cells that contain Unit 2 or 3 fuel assemblies or greater than 30 feet 8 inches (elevation 64 feet 6 inches) over rack cells that contain Unit 1 fuel assemblies.
Installation or removal of the cask pool cover over the i
cask pool with fuel in the cask pool.
The lift of construction loads including the temporary gantry crane and the old and the new fuel storage racks sincluding lifting equipment and rigging, above the cask poolwiththecaskpoolcoverinplacean)dfuelinthecask pool. This includes temporary storage of these construction i
loads on the cask pool cover during construction. These lifts are prohibited prior to a minimum fuel decay time of l
88 days for all stored fuel assemblies.
l The basis for Specification 3.9.7 was revised to reflect the i
analysis for the heavy load drops associated with the revised e
Specification 3.9.7.
A new Technical Specification 3.9.13 (Bases 3/4.9.13) was added to specify the boron concentration limit in the pool as 1850 ppm, which includes 50 ppm for measurement uncertainties, prior to any fuel movement.
TechnicalSpecification3.9.12(Bases 3/4.9.12)wasrevisedto allow both trains of the fuel Handling Building Post-Accident Cleanup Filter System to be out of service during the construction period for reracking the spent fuel pool.
This revision to
Technical Specification 3.9.12 was required to allow continued operation of the spent fuel handling machine witbout fuel, temporary gentry crane and cask handling crane with the fuel handling building equipment hatches open.
1 Compliance with this revised Technical Specification 3.9.12 i
will ensure that with a minimum fuel decay time of 88 days, the radiological consequences of the worst postulated heavy load drop in the pools will not result in releases that exceed 25 percent of the 10 CFR 100 limits at the exclusion area boundary.
Revision to design features section of 5.6.3-of the Operating License will provide consistency with Technical Specification l
3.9.11 value of 23 feet of water to be maintained over the top of irradiated fuel assemblies.
These anlendments were in response to an application for amendments designated as.PCN 287.
I The application for amendments complies with the standards and requirements oftheAtomicEnergyActof1954,asamended(theAct),andtheCommission's rules and regulations. The Comission has made appropriate findings as t
required by the Act and the Commission's rules and regulations in 10 CFR Chapter 1, which are set forth in the license amendments.
Notice of Consideration of Issuance of Amendments and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER onApr.1124,1989(54FR16438-B). No request for a hearing or petition for leave to intervene was filed following this notice.
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an Environmental Assessment and Finding of No Significant Impact has been prepared.. A Notice of Issuance of Environment Assessment and Finding of No Significant Impact was published 1
l in the Federal Register on February 27 1990 (55 FR 8248), as supplemented April 6,1990(55FR12971).
Based on the Environmental Assessment, the j
Commission has determined that the issuance of the amendments will not result in any significant environmental impact, i
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Forfurtherdetailswithrespecttotheactionsee(1)theapplications for amendments dated Merch 10, April 19, May 4, May 19, June 1, June 2, i
September 22, November 2, November 9,1989, January 18, February 9. February 16, and March 20,1990;(2) AmendmentNo.87toLicenseNo.NPF-10;(3) Amendment No. 77 to License No. NPF-15; (4) the Comission's related Safety Evaluation dated May 1,1990; and (5) the Comission's Environmental Assersment, dated February 27,1990(55FR8248),assupplementedApril 6,1990(55FR12971).
All of these items are available for public inspection at the Comission's l
Public Document Room, 2120 L Street N.W., Washington, D.C.
20555, and at the General Library, University of California, P.O. Box 19557, Irvine, California 92713.
Acopyofitems(2),(3),(4)and(5)maybeobtaineduponrequest addressed to the U.S. Nuclear Regulatory Comission Washington, D.C. 20555, Attention: Director, Division of Reactor Projects !!!, IV, Y and Special Projects.
Dated at Rockville, Maryland this 1st day of May 1990, FOR THE NUCLEAR REGULATORY COMMISSION
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lawrence E. Kokajko, Project Manager Project Directorate V Division of Reactor Projects - III, r
IV, Y and Special Projects Office of Nuclear Reactor Regulation l.
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