ML20096C039

Application to Amend License DPR-16,consisting of Tech Spec Change Request 127 to Revise Section 5.3.1.E by Moving Weight Limitation of Spent Fuel Shipping Cask

ML20096C039
Person / Time
Site:	Oyster Creek
Issue date:	08/28/1984
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20096C038	List: ML20096C033 ML20096C039 ML20096C270
References
NUDOCS 8409050004
Download: ML20096C039 (7)

Text

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s 0YSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE N0. DPR-16 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 127 DOCKET NO. 50-219 Applicant submits by this Technical Specification Change Request No.127 to the Oyster. Creek Nuclear Generating Station Technical Specifications, changes to Section 5.3.1.E.

,a 1 By EE "W P. E. Fiedler Vice President and Director Oyster Creek Sworn and subscribed to before me this 28th day of August 1984.

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e UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF

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GPU NUCLEAR CORPORATION )

DOCKET N0. 50-219 CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No.

127 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the United States Nuclear Regulatory Comission on August 28 1984, has this 28 day of August

,1984, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

The Honorable Henry A. Delo, Jr.

Mayor of Lacey Township 818 West Lacey Road Forked River, N.J.

08731 By IC P.1P.=fredl er Vice President and Director Oyster Creek 1r/0339e

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GPU Nuclear Corporation NUCI88r R$ief;;,8r388 o

Forkeo River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

August 28, 1984 The Honorable Henry A. Delo, Jr.

Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731

Dear Mayor Delo:

Enclosed herewith is one copy of the Technical Specification Change Request No.127 for the Oyster Creek Nuclear Generating Station Operating License.

This document was filed with the United States Nuclear Regulatory Comission on August 28, 1984.

Very truly yours,

-n r

ice President and Director Oyster Creek 1r/0339e i

GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporation

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-0YSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 127 LApplicant hereby requests the Commission to change Appendix A to the above captioned-license as follows:

- 1.

Sections to be changed:

Section 5.3.1.E

-2.

Extent of changes:

To reinove the 30 ton limitation on spent fuel shipping casks associated withthe'spentfuell pool.:

3.

Changes requested:

Replace old pages 5.3-1 with the attached new page 5.3-1.

4.

Discussion:

By' letter dated March 30, 1977, the NRC issued Amendment No. 22 to the Oyster Creek Technical Specifications. This amendment addressed the increased spent fuel pool storage capacity and the requirements that go with it. One of these requirements had to do with limiting the weight of a spent fuel shipping cask, which could be raised over the top plate of the cask drop protection system (CDPs). to a maximum weight of 30 tons.

Although'the analysis for the cask drop protection system had been performed by GPUN using a 100 ton cask, and this analysis being found acceptable by the NRC as discussed in their March 30, 1977 SER of Amendment 22, the NRC imposed the 30 ton limitation "until the details of the means used to limit the height to which the cask can be raised over the. operating deck have been submitted by the licensee and approved by the NRC staff."

On October 14, 1983, Judge Elfvin of the U.S. District Court, Western District of New York, signed a Partial Settlement Agreement and Order which requires GPUN to return 224 spent fuel assemblies from the Western New York Nuclear Service Center in West Valley, NY to Oyster Creek. This Court Order requires GPUN to use its best efforts to obtain the use of two (2) TN-9 spent fuel shipping casks..Accordingly, in preparation for-receiving these fuel assemblies, GPUN is contracting for the use of two (2) TN-9 spent fuel shipping casks each having a full load weight of 40.5 tons. The use of these casks will reduce the number of shipments from West Valley to 32 instead of the 114 required if the NLI 1/2 cask was utilized.

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The purpos' cf this amendment chang] requ:st is to remove th) 30 ton e

limitation so that GPUN can utilize the TN-9 shipping casks. GPUN is developing and will use a specific procedure for handling the TN-9 casks. To insure that the cask will not be raised more than 6" above the top plate of the (CDPs), limit switches on the crane will be set to limit the cranes upward travel to a level such that the bottom surface of the cask base plate will be limited to a maximum height of six (6) inches above the top plate.

In addition, a "GO, NO-G0" gauge will be used to insure the cask is at the correct height prior to movement.

The above requirements that will be incorporated into the procedure for handling the TN-9 shipping casks should satisfactorily resolve the concerns raised in the NRC SER of !! arch 30, 1977, and allow for the removal of the 30 ton limitiation from the Oyster Creek Technical Specification.

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0VSTER CREEK NUCLEAR GENERATING STATION s

PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 l

. TECHNICAL' SPECIFICATION CHANGE REQUEST NO. 127 s

7 Pursuant to 10CFR 50.91. an analysis concerning significant hazards considerations is provided below:

a

1..

Section to be changed:

f Section 5.3.1.E

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a-2.

Extent of changes::

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,, 'ITo remove the 30 ton limitation on spent fuel shipping casks associated

-with the spent fuel pool.-

3.'

Channes requested:

+

Replace old page 5.3-1 with the attached new page 5.3-1.

4.

Discussion:

By letter dated March 30, 1977, the NRC issued Amendment No. 22 to the i

'j-Oyster Creek Technical Specifications. This amendment addressed the f

-increased spent fuel pool storage capacity and the requirements that go with it. One of these requirements had to'do'with limiting the weight of

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'a spent fuel shipping cask, which could be raised over the top plate of

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a thecaskdropprotectionsystem(CDPs),to'amaximumweightof30 tons.

Although the analysis for the cask drop protection system had been I

performed by GPUN using a 100 ton cask, and this analysis being found acceptable by the NRC as discussed in their March'30, 1977 SER of Amendment 22, the NRC imposed the 30 ton limitation "until the details of the means used to limit the height to which the cask can be raised over the operating deck have been submitted by the licensee and approved by the NRC staff."

J On October 14, 1983 Judge Elfvin of the U.S. District Court, Western

' District of New York.-signed a Partial Settlement Agreement and Order which requires GPUN to return 224 spent fuel assemblies from the Western New York Nuclear Service Center in West Valley, NY to Oyster Creek. This Court Order requires'GPUN to'use its best efforts to obtain the use of two 2) TN-9 spent fuel shipping casks. Accordingly, in preparation for rece ving these fuel assemblies M UN is contracting for the use of two (2)TN-9spentfuelshippingcaskseachhavingafullloadweightof40.5 tons. The use of these casks will reduce the number of shipments from West Valley to 32 instead of the 114 required'if the NLI 1/2 cask was i

utilized.

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The purpoge of this amendment change request is to remova the 30 ton 11 itation so that EPUN can utilize the TN-9 shipping casks. GPUN is developing and will use a specific procedure for handling the TN-9 casks. To insure that the cask will not be raised more than 6" above the top plate of the CDPs..lfmit switches on the crane will be set to limit t

the cranes upward travel to a level such that the bottom surface of the cask base plate will be limited to a maximum height of six (6) inches above the top plate.

In addition, a "G0, NO-G0" gauge will be used to insure the cask is at the correct height prior to movement.

The above requirements that will be incorporated into the procedure for handling the TN-9 shipping casks should satisfactorily resolve the concerns raised in the NRC SER of March 30, 1977, and allow for the removal of the 30 ton Ifmittation from the Oyster Creek Technical Specification.

We have determined that this change request involves no significant hazards considerations in that operation of the Oyster Creek plant in r

accordance with the proposed amendment will not:

1)

Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)

Involve a significant reduction in a margin of safety.

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