ML20245F450

From kanterella
Jump to navigation Jump to search
Notice of Consideration of Issuance of Amends to Licenses NPF-10 & NPF-15 & Opportunity for Hearing on 890310 Request to Revise Tech Spec 3.9.7, Fuel Handling Machine - Spent Fuel Storage Pool Bldg & Tech Specs 5.6.1,5.6.2 & 5.6.4
ML20245F450
Person / Time
Site: San Onofre  
Issue date: 04/12/1989
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245F455 List:
References
NUDOCS 8905020385
Download: ML20245F450 (7)


Text

,

L.

j 1

i 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION q

SOUTHERN CALIFORNIA EDISON COMPANY, ET AL DOCKET NOS. 50-361 AND 50-362 j

NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS TO' l

FACILITY OPERATING LICENSES AND OPPORTUNITY FOR HEARING The U. S.' Nuclear Regulatory Commission (the Commission). is considering

.)

issuance of amendments to Facility Operating License Nos. NPF-10 and NPF-15 issued to Southern California Edison Company (SCE), San Diego Gas and Electric Company, the City of Riverside, California and the City of Anaheim, California (the licensees), for operation of San Onofre Nuclear Generating Station, Units 1

2 and 3 located in San Diego County, California. The request for amendments was submitted by letter dated March 10, 1989 and identified as Proposed Change

]

1 PCN-287.

]

The proposed change would revise Technical Specifications 3.9.7, " Fuel HandlingMachine-SpentFuelStoragePoolBuilding;"5.6.1(b)and5.6.2," Fuel Storage Criticality;" and 5.6.4, " Fuel Storage Capacity." The purpose of the proposed Technical Specification changes is to provide for increasing.the capacity of the fuel storage racks at both Unit 2 and Unit 3 from 800 to 1572 fuel assembly storage locations and for conducting specific heavy load lifts above the new storage racks that are needed for-construction 'and normal fuel i

pool operations.

l The licensees have proposed replacing the existing spent fuel racks, 4

l which have 800 storage locations, with new high density spent fuel racks, with l

1572 fuel assembly storage locations.at both San Onofre Unit 2 and Unit 3.

The new racks would be free standing and use Boraflex neutron absorbing material for criticality control. A two region design would be used, with 312 storage' i

locations.in Region I for storage of all types'of Unit I and Units 2 or.3 8905020385 890412 o

PDR ADOCK 05000361 M

P PDC

.]

uranium oxide fuel, and 1260 storage locations in Region II for storage of Unit 1 and Units 2 or 3 uranium oxide fuel which either meets specified burnup criteria or is stored in prescribed patterns. Approval of storage of spent fuel produced by operation of San Onofre Unit 1 in either Unit 2 or Unit 3 was authorized June 22, 1988 by Amendments 63 and 52, respectively.

The proposed Technical Specification changes are described below:

I.

Technical Specification 5.6.1(b) would change the current 12.75" center-to-center rack storage location spacing to y

10.40". center-to-center spacing for Region I, and to 8.85" center-to-center spacing for Region II.

2.

Existing Technical Specification 5.6.2 for dry storage of I

the first core in the fuel pool in alternate rows and columns will be deleted. This Technical Specification was only applicable to dry storage of the first core.

3.

New Technical Specification 5.6.2 and accompanying Figures 5.6-1, 5.6-2, 5.6-3, and 5.6-4 would define the fuel enrichment /burnup limits for storage of Units 1, 2, and/or 3 fuel in Region II of the high capecity spent fuel storage racks.

This new Technical Specification would also define the conditions and storage patterns (checkerboard or alternating row) required for storage in Region II of new or burned fuel which does not meet the enrichment vs. burnup criterion.

Lastly, this new Technical Specification would define the conditions under which a new/ burned fuel reconstitution station may be established in Region II.

i

4 -

4.

Technical Specification 5.6.4 would be revised to specify that no more than 1572 fuel assemblies may be stored in the spent fuel racks.

5.

Technical Specification 3.9.7 would be revised to list the following allowable lifts of heavy loads above stored spent fuel:

A.

Spent fuel pool gates shall not be carried at a height greater than 30 inches (elevation 36 feet 4 inches)overthefuelracks.

B.

Test equipment skid (4500 pounds) shall not be carried at a height greater than 72 inches (elevation 39 feet 10 inches)overrackcellswhichcontain Units 2 or 3 fuel assemblies or greater than 30 feet 8 inches (elevation 64 feet 6 inches) over rack cells which contain Unit 1 fuel assemblies.

1 C.

Installation or removal of the cask pool cover.over the cask pool with fuel in the cask pool.

D.

The lift of construction loads, including the temporary gantry crane and the old and the new fuel storage racks (including lifting equipment and rigging), above the cask pool with the cask pool a

cover in place and fuel in the cask pool. This includes temporary storage of these construction j

loads on the cask pool cover during construction.

i l

l 1

4 6.

The basis for Specification 3.9.7 will be revised to reflect the analysis for the heavy load drops associated with the revised Specification 3.9.7.

Before issuance of the proposed license amendments, the Comission will have made findings. required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulatfor.s.

i By May 24 1989 the licersees may file a request for a hearing with l

respect to issuance of the amendments to the subject facility operating licenses, and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for hearing and petition for leave to intervene. Requests for a J

hearing and petitions for leave to intervene shall be filed in accordance with l

the Comission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.

If a request for a hearing or petition for leave to intervene is filed by the above date, the Comission or an Atomic Safety and Licensing Board designated by the Comission or by the Chairman of the Atomic Safety and Licensing Board Panel will rule on the request and/or petition, and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.

As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how thot interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:

(1)thenature of the petitioner's right ur der the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other l

l

interest in the proceeding; and (3) the possible effect of any order which may 1

be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has' filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fifteen (15) days prior I

to the first pre-hearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.

Not later than fifteen (15) days prior to the first pre-hearing conference

]

1 scheduled in the proceeding, a petitioner shall file a supplement to the'

)

petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set

\\

forth with reasonable specificity. Contentions shall be limited to matters j

within the scope of the amendments under consideration. A petitioner who l

i l

fails to file such a supplement which. satisfies these requirements with respect

~

to at least one contention will not be permitted to participate as a party.

Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the i

opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.

1 A request for a hearing or a petition for leave to intervene shall be filed with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, DC 20555, Attention: Docketing and Service Branch, or may be delivered to the Comission's Public Document Room, 2120 L Street, NW, Washington, DC, by the above date. Where petitions are filed during the last ten (10 ) days of the notice period, it is requested that the petitioner or i

H !

representative for the petitioner promptly inform the Comission by a toll-free telephone call to Western Union at 1-(800)325-6000(inMissouri 1-(800)342-6700).

The Western Union operator should be given Datagram Identification Number 3737 dnd the following message addressed to George W. Knighton: petitioner's name 1

and telephone number; date petition was mailed; plant name; and publication date and page number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Comission, Washington, DC 20555, and to Mr. Charles R. Kocher, Esq., Southern t'

C611fornia Edison Company, 2244 Walnut Grove Avenue, P.O. Box 800, Rosemead, California 91770 and Orrick, Herrington and Sutcliffe, Attention: David R. Pigott, Esq., 600 Montgomery Street, San Francisco, California 94111, attorneys for the licensees.

Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Comission, the presiding officer or the presiding Atomic Safety and Licensing Board, that the petition and/or request shou?' be granted based upon a balancing of the factors specified in the 10 CFR2.714(a)(1)(1)-(v)and2.714(d).

If a request for hearing is received, the Comission's staff may issue the amendments after it completes its technical review and prior to the completion of any required hearing if it publishes a further notice for public coment of its proposed finding of no significant hazards consideration in accordance with 10 CFR 50.91 and 50.92.

f.

1 For further details with respect to this action, see the application for amendments which is available for public inspection at the Commission's public-Document Room, 2120 L Street NW, Washington, DC, and at the General Library, University of California at Irvine, Irvine, California 92713.

Dated at Rockville, Maryland, this 12th day of April

,1989.

FOR THE NUCLEAR REGULATORY COMMISSION J

-eorgp. Knight

, Director i

Projett Direct 6te V Division of Reactor Projects - III, IV, Y and Special Projects.

Office of Nuclear Reactor Regulation 1

i I

l l

4 l

_.