ML17213B306

Advises That First Reactor Vessel Matl Irradiation Surveillance Specimen Will Be Removed in Conjunction W/ Current Extended Outage to Remove Reactor Vessel Thermal Shield,Tentatively Scheduled for Completion in Dec 1984

ML17213B306
Person / Time
Site:	Saint Lucie
Issue date:	04/25/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Clark R Office of Nuclear Reactor Regulation
References
L-83-257, NUDOCS 8304280075
Download: ML17213B306 (6)

Text

C~'EGULA Y INFORMATION DISTRIBUTIG 'YSTEM (RIDS)

SEDATE:

AOCESSION NBR:8304280075 DOC 83/04/25 NOTARIZED: NO DOCKET FACIL:50-335 St, Lucie Plantg Uniit i~ Florida Power K Light Co> 05000335 AUTH ~ NAME AUTHOR AFFILIATION UHRIG i R, E, Flor ida Power 8 Light Co ~ .

RECIP ~ NAME RECIPIENT AFFILIATION CLARKgR ~ AD Operating Reactors Branch 3

SUBJECT:

Advises that first reactor vessel matl irradiation surveillance specimen will be removed in conjunction w/

current extended outage,to remove reactor vessel'hermal shielditentatively scheduled for completion in Dec 1984 CODE: A001S COPIES RECEIVED:LTR 3 ENCL .$ SIZE:. 'ISTRIBUTION TITLE: OR Submittal; General Distribution NOTES:

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FLORIDA POWER & LIGHT COMPANY April 25, 1983 L-83-257 Office of Nuclear Reactor Regulation Attention: Mr. Robert A. Clark, Chief Operating Reactors Branch g3 Division of Licensing U. S. Nuclear Regulatory Ccmmission Washington, D. C. 20555

Dear Mr. Clark:

Re: St..Luci e Unit 1 Docket No. 50-335 Reactor Vessel Surveillance Specimen In conjunction with the current extended outage to remove the reactor vessel thermal shield, we have decided to renove the first reactor vessel material irradiation surveillance specimen fran St. Lucie Unit 1. This removal is, in our judgment, in accordance with the St. Lucie Unit 1 Technical Specifications and Appendix H to 10 CFR 50.

Technical Specification 4.4.9.1.c requires that the first specimen be removed after eight calendar years. As the operating license for St.

Lucie Unit 1 was issued on March 1, 1976, the specimen is due to be removed on March 1, 1984, or approximately seven and a half months from the anticipated end of the current refueling outage. The following refueling outage is tentatively scheduled to be finished around the end of 1984. This would be approximately ten months past the eight-year 'ecember date. This future outage may be slipped further depending on cycle length adjustments and the overhaul schedules of other units.

Section II.e of 10 CFR 50 Appendix H, allows modification of withdrawal schedules to coincide with the refueling outage most closely approaching the withdrawal schedule. Because the end of the current outage most closely approaches the withdrawal schedule, we will remove the specimen during this outage. Our NSSS vendor concurs with this action.

Removing the specimen during the outage will al low us to evaluate the specimen to determine a material ir radiation baseline for operation of St.

Luci e Unit 1 without the thermal shield. We are also planning to replace the specimen with temperature and dosimetry instruments to obtain fluence data during the upcaning cycle.

T 8304280075 830425 I 1 PDR ADOCK 05000335 P PDR, I i PEOPLE SERVING PEOPLE

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, Office of Nucle Reactor Regulation Attention: Mr. Robert A. Clark Page 2 Should you or your staff have any questions on this subject, please contact us.

Very truly yours, Rober E. Uhrig Vice President Advanced System 5 Technology REU/PLP/js Attachments cc: Mr. James P. O'Reil ly, Region II Harold F. Rei s, Esquire

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