ML17215A582

Application for Amend to License NPF-16,revising Tech Specs to Substitute Containment Isolation Check Valve W/Butterfly Valve.Fee Paid

ML17215A582
Person / Time
Site:	Saint Lucie
Issue date:	09/28/1984
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML17215A583	List: ML17215A582 ML17215A584
References
L-84-266, NUDOCS 8410040235
Download: ML17215A582 (4)

Text

REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR:8010000235 DOC ~ DATE: 84/09/28 NOTARIZED:

NO FACIL:50-389 St, Lucie Planti Unit 2i Florida Power 8 Light Co, AUTH,NAME AUTHOR AP F ILIATION HILLIAMSiJ.N.

Florida Power 8 Light Co, RECIP ~ NAME RECIPIENT AFFILIATION EISENHUTi 0 ~ G ~

Division of Licensing

SUBJECT:

Application for amend to License NPF 16irevising Tech Specs to 'substitute containment isolation check valve w/butterfly valve.Fee

Paid, DISTRIBUTION CODE:

A001D COPIES RECEIVED:LTR ENCL SIZE; TITLE:

OR Submittal:

General Distribution NOTES:

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FLORIDA POWER & LIGHTCOMPANY September 28, I 984 L-84-266 Office of Nuclear Reactor Regulation Attention:

Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Eisenhut:

Re:

St. Lucie Unit No. 2 Docket No. 50-389 License Condition 2.C.8 Continuous Containment Pur e S stem 0'0'-

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)(QQ 0 Florida Power & Light Company will be implementing hardware changes during the upcoming refueling outage to satisfy License Condition 2.C.8.

In implementing these

changes, the existing containment isolation valve I-V-25-25, which is a check valve, is being replaced with a butterfly valve designated I-V 36.

Attachment I shows the before configurations for penetration numbers 56 and 57, and Attachment 2 shows the after modification configurations for these penetrations.

The purpose of this letter is to obtain NRC approval for substituting the new valve for the'existing valve in Technical Specification Tables 3.6-1 and 3.6-2.

This is to allow the Technical Specification requirements to be applicable to the new valve upon completion of the modification, while at the same time relieving the requirements on the valve that no longer will be installed.

'Ihe formal license amendment request willbe submitted following completion of the modification.

A similar situation exists for penetration number 8 for the station air system.

Although not a license condition, a plant improvement modification is planned for"~

the upcoming refueling outage that will replace the existing containment isolation valves I-V-I8-794 and I-V-I8-796 with new containment isolation valves I-HCV-l8-2 and I-V-I8-I270 respectively.

Attachment 3 shows the existing configuration for penetration number 8,

and Attachment 4

shows the after modification configuration.

NRC approval for making this change is also being requested.

As stated above, the formal license amendment request will be submitted following completion of the modification. shows the before and after Technical Specification Tables 3.6-I and 3.6-2 for both of the modifications.

These tables will be revised in the formal license.amendment

request, to

. be submitted following completion of the modifications.,

gaOI I

oP PEOPLE... SERVING PEOPLE

Page 2 Office of Nuclear Reactor Regulation Mr. Darrell G. Eisenhut, Director In that both of these items are outage dependent, your approval is requested as early as possible, but no later than October l3, l984.

Attached is a check for $ I50.00 in accordance with IO CFR l70.2I.

Very truly yours, J. W. Williams, Jr.

Group Vice President Nuclear Energy JWW/RJS/kgn Attachments