ML17339A634

Request Amends to Licenses DPR-31 & DPR-41 Revising Tech Specs Re Control Rod Position & Rod Position Indication. Tech Specs Pages 3.2-2 & 3.2-3 & Table 4.1-1 Encl

ML17339A634
Person / Time
Site:	Turkey Point
Issue date:	02/27/1980
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17339A635	List: ML17339A634 ML17339A637
References
L-80-62, NUDOCS 8003040474
Download: ML17339A634 (6)

Text

REGUL'ATORY FORMATION DISTRIBUTION SY M (RIDS)

ACCESSION NBR!8003040rl7rl OOC ~ DATE! 80/0?/27, NOT'ARIZED: YKS DOCKET FACIL:50 250'urkey Pojnt Plant< Unit 3i Florida> Power and L,jght C 05000250 BYNAME 50 251 Turkey Po.int P'l'antr Unit 0r F:lorida: Power and L.ight C 05000251 AUTH AUTHOR AFFILIATION UHRIGr R ~ E ~ . F>l or,i de- Power 8 l.i ght Co, RECIP ~ NAME RECIPIENT'FFIlIATION SUB JEC>T t Reques t amends toi L>i censes DPR~31 L DPR 01. rev i s j ng Tech Specs r e control rod posi tion 8 rod posi t ion, indication ~

Tech Specs Pages 3 ~ 2 2 8 3.2 3 8 Table 4 ~ 1 1. encl ~,

DISTRIBUTION CODE: A001S COPIES RECEIVED:LiTR ENCL","~ SIZEt ,2 f.a TITLE! Genera,l Distribution for afte'r Issuance of Opera'ting Lic NOTES>> >>

RECIPIENT COPIES RECIPIENT COPIES ID ID COOK/NAME, L>TTR ENCL; 05 BC, CODE'/NAME'CT:ION

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INTERNAL': 0 G FIL'E 1 1 02 NRC 'PDR 1 12 2 2 '15 CORE'ERF" BR 1 1 17 ENGR BR 1 18 REAC SF>TY BR 1 1 19 PLANT SYS BR 1 1 20 EEB 1 1 21 EFLT TRT SYS '1 EPB~DOR 1 OELD 1 0 STS GROUP LEADR 1, 1 EXTERNAL: 03 'LPDR 1 1 04 NSIC 1 1 23 ACRS 16 ib>>

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TOTAL NUMBER OF .COPIES REQUIRED: lTTR 38 KNCl 37

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FLORIOA POWER 8 LIGHT COMPANY Director of Nuclear Reactor Regul'ation Attention: Nr. Darrell G. Eisenhut, Acting Director February 27, 1980 Division of Operating Reactors L-80-62 U- S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Nr. Eisenhut:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41. This proposal is submitted in response to A. Schwencer's letter of October 29, 1979 on control rod position and rod position indication.

The proposed amendment is described below and shown on the accompanying Technical Specification pages beari ng the date of this letter in the lower right hand corner.

Pa es 3.2-2 and 3.2-3 Technical Specifications 3.2.2 and 3.2.4.b are revised to change the control rod misalignment limit from "15 inches" to "12 steps".

Table 4.1-1 Sheet 1 Item 9 A note is added to the "Remarks" section of Item 9 (Analog Rod Position) to specify that indicated position be calibrated to within 12 steps of actual position.

The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.

They have concluded that it does not involve an unreviewed safety question.

Very truly yours, obert E. Uhrig Vice President Advanced Systems 8 Technology REU/HAS/cph Attachment cc: J. P. O'Reilly, Region II Robert Lowenstein, Esquire Booooco g $ 5(

PEOPLE... SERVING PEOPLE

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f. Except for low power physics tests, the shutdown margin with allowance for a stuck control rod shall exceed the applicable value shown on Figure 3.2-2 under all steady-state operating conditions from zero to full power, including effects of axial power distribution. The shutdown margin as used here is defned as the amount by which the reactor core would be subcritical at hot shutdown conditions (540 F) if all control rods were tripped, assuming that the highest worth control rod remained fully withdrawn, and assuming no changes in xenon, boron concentration or part-length rod position.

g. During physics tests and control rod exercises, the i nsertion limits need not be met, but the required shutdown margin, Figure 3.2-2 must be maintained or exceeded.

2. MISALIGNED CONTROL ROD If a part length* or full length control rod is more than 12 steps out of alignment with its bank, and is not corrected within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> power shall be reduced so as not to exceed 75K, of interim power for 3 loop or 45$ of-interim power for two loop operation, unless the hot channel factors are shown to be no greater thn allowed by Section 6a of Specification 3.2.

3. ROD DROP TIME The drop time for each control rod shall be no greater than 1.8 seconds at full flow and operati ng temperature from the beginning of rod motion to dashpot entry.

4. INOPERABLE CONTROL RODS

a. No more than one inoperable control rod shall be permitted during sustained power operation, except it shall not be permitted if the rod has a potential reactivity insertion upon ejection greater than 0.3'A ak/k at rated power. Inoperable rod worth shall be determined within 4 weeks.

b. A control rod shall be considered inoperable if (1) the rod cannot be moved by the CRDM, or

2) the rod is misaligned from its bank by more than 12 steps for longer than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or (3) the rod drop time is not met.

c. If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate for the withdrawn worth of the inoperable rod.

• Any reference to part-length rods no longer applies after the part-length rods are removed from the reactor.

3~ 2 2 2-27-80

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