ML19317G478

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Supplements Util Responding to Part 1,Enclosure 1 of NRC W/Info Re Cleanup Operations Following Burnable Poison Rod Assembly Failure
ML19317G478
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 05/19/1978
From: Stewart W
FLORIDA POWER CORP.
To: Reid R
Office of Nuclear Reactor Regulation
References
NUDOCS 8003160090
Download: ML19317G478 (3)


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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOl1ING MATERIAL 50-302 DOCDATE: 05/19/7$'

REC: REID R W ORG: STEWART W P NRC FL FWR DATE RCVD: 05/24/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED SUDJECT:

LTR 1 ENCL 0 FURNISHING ADDL INFO RELATING TO APPLICANT"S CLEANUP OPERATIONS FOLLOWING THE BURNABLE POISON ROD ASSEf1DLY FAILURE PROBLEM AT SUBJECT FACILITY.

PLANT NAME: CRYSTAL RIVER #3 REVIEWER INITIAL:

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GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.

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'"fla"As"Je%8" Nay 19,1978 Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Comission Wa.shington, DC 20555

SUBJECT:

Crystal River Unit No. 3 Docket No. 50-302 Operating License No. DPR-72 Florida Power Corporation

Dear Sir:

This is to provide additional information re a

operations following the Burnable Poison Rod Assembly (BPRA) failure problem at Crystal River Unit No. 3.

In our letter to you of May 16, 1978, which was in response to Part I,, of your letter of May 2,1978, we indicated that all observed debris had been removed from the Core Support Assembly (CSA) except for four (4) small pieces of BPRA pin. We al:0 indicated that if our efforts to remove these pieces failed, we would provide justification for not removing them.

We-have utilized our best efforts and to date have been unsuccessful in removing these pieces. There are four (4) known pieces of BPRA pin, each about four (4) to eight (8) inches in length and each lodged within separate lower grid support posts.

We have evaluated the option of leaving these pieces where they are within the CSA and have concluded that no additional reactor safety concerns would result from this action. Our response to Item 5, Part I,, of your May 2 letter evaluated potential effects that residual poison and metallic fragments could have on plant operations.

That evaluation is applicable to the four (4) known pieces under considera-tion, as well as unknown, residual fragments.

It is our conclusion that additional efforts and schedule delays devoted to further attempts at removal of this debris are not warranted at this time.

There would not be commensurate benefits to be derived and further removal attempts would most probably be unsuccessful.

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Mr. Robert W. Reid Page 2 May 19,1978 We therefore intend to proceed with other repair an!J refueling activities and anticipate placement of the-fuel back in the reactor beginning on

-May 20, 1978.

We appreciate your consideration in this matter and realize that the placement of fuel back in the reactor at this time does not preclude further NRC involvement and review prior to unit startup. Please advise if you desire further discussion at this time.

Sincerely, FLORIDA POWER CORPORATION O.B, Dub:s(Sc W.P. Stewart File:

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