ML17340A521

Application to Amend Licenses DPR-31 & DPR 41 Authorizing Proposed Changes to Tech Specs Per TMI Lessons Learned

ML17340A521
Person / Time
Site:	Turkey Point
Issue date:	12/23/1980
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML17340A522	List: ML17340A521 ML17340A523
References
L-80-417, NUDOCS 8012300320
Download: ML17340A521 (10)

Text

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~ e So REGULAT RY INFORMATION DISTRIBUTION'YSTEM (RIDS) ie ACCESSION NBR:801230032 DOC ~ DATE! 80/12'/23 50 ARIZED: NO, DOCKET' FACIL:50 250 Turkey Point Planti Unit 3E Florida Power and Light C'5000250 50 251 Turkey Point Plant-E Unit OP Florfdai Power and Light C 05000251 AUTH'AME AUTHOR AFFILIATION UHRIGg R ~ E ~ Flor.fda Power 8 Light Co.

'REC IP ~ NAME RECIPIENT AFFILIATION EISKNHUTEDRG. Division of LicenSing.

SUBJECT:

DPR Qi authorizing Application to amend Licenses DPRss31TNIL Lessons proposed ohsnBes to Tech Speos per Learned;.

DISTRIBUTION.CODEt ABOIS COPIES RECEIVED:LTR. ENCL. SIZE ..., P'.I ~

TITLKg General Distribution for after. Issuance of Operating Lfcense NOTES'ECIPIENT RECIPIENT COPIES IO CODE/NAMEOQ'OPIESLTTR ENCL ID COOK/NAME" LTTR ENCL ACTION VARGAg S ~ 13 INTERNAL: D/D IR g HUM FAC08 1 1 OIR"p OI V OF L IC 1 1 ILE Ob 2 2 NRC. PDR 02" 1 1-OEL FIL ilir 0

1 1

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OR .ASSESS BR 10 1 0 EXTERNAL: ACRS 09 16 16 LPDR 03 ~

1 NSIC 05I 1 TOTAL'UMBER OF COPIES REQUIRED! LTTR 39 ENCL- 37" '

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P.O. BOX 529100 MIAMI,F L 33152 FLORIDA POWER & LIGHT COMPANY December ?3 1980.

L-80-417 Director of Nuclear Reactor Regulation Attention: Hr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Hr. Eisenhut:

RE: Turkev Point Un'.ts 3 8 4 Docket Nos 50-250 8 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 & DPR-41 In accordance with '10 CFR 50.30, Florida Power 5 Light Company submits herewith three (3) signed originals and forty (40) copi'es of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41.

This proposal is submitted in response to your letter of July 2, 1980. The license condition changes from Enclosure 2 of that letter have not been included in this proposal- These items will be forwarded as a separate request. The proposed changes are shown on the acccmpanying Technical Specification pages bearing the date of this letter in the lower right hand corner.

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

Very trul yours, Robert E- Uhrig Vice President Advanced Systems 8 Technology N)NbG Qgg'g3S NOllAGIHI Sl6 REU/HAS/ras QN> N Attachment 930 ~<~

cc: Hr. James P. O'Reilly, Region II Harold F. Rei s, Esquire J.IHA S"'AIA1"; .

IN)LAtilUL~~l'-""-"

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PEOPLE... SERVING PEOPLE

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ATTACHMENT RE: Turkey Point Units 3 8 4 Proposed Tech Spec Change TMI Lessons Learned Pa e 3.l-la Specification 3.1.1 is expanded to include the pressurizer, the PORYs, and associated block valves.

The requirement for a monthly flux map is moved to Chapter 4, Surveillance Requirements (Table 4-1-1).

Pa e 3.3-1 Containment Isolation Yalves are added to Specification 3.3.

Pa es 3.5-1 and Tables 3.5-2 3.5-4 8 3.5-5 Additional accident monitori ng instrumentation is added to Specification 3. 5 and the Tables for ESF Actuation and ESF Setpoints- Table 3.5-5 is a new Table-Table 4.1-1 Sheets 1~3 and 4 Testing requirements for certain AUXILIARY FEEDWATER INSTRUMENTATION and ACCIDENT MONITORING INSTRUMENTATION.are added to this Table (Minimum Frequencies for Checks, Calibrations, and Test of Instrument Channels). This requirement for a monthly flux map is also added to this Table.

Pa e 4-10-1 Specification 4.10 is expanded to include 18 month testing requirements for the Auxiliary Feedwater System.

Table 6.2-1 Shift manning requirements are modified and include the Shift Technical Advisor.

P.a<ac 6-5 Miniminum qualifications for the Shift Technical Advisor are added to Specification 6.3.1.

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Presssurizer The pressurizer shall be operable with a steam bubble, and with at least 125 KM of pressurizer heaters capable of being supplied by emergency power, when the reactor coolant is heated above 350F.

e. Relief Valves

l. A power operated relief valve (PORY) and its associated block valve shall be operable when the reactor coolant is heated above 350F.

2., If the average coolant temperature is greater than 350F and the conditions of 3.l.l-e-l cannot be met because one or more PORV(s) is inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to operable status or close the associated block valve(s) and remove power from the block valve(s); otherwise, be in a condition with Keff < 0-99 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3. If the average coolant temperature is greater than 350F and the conditions of 3. 1.1-e.l cannot be met because one or more block valve(s) is inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve(s) to operable status or close the block valve(s) and remove power from the block valve(s); otherwise, be in a condition with Keff < 0.99 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3. 1-1 a

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(b) (1') The measurement of total peaking facto r,,F~ a shall f

h i nc reased by three percent to account forr q manu acturing tol erances and further increased by five percent too account ac be t

for measurement error-(2} T(e measurement of the enthaipy rise hot c h anne factor, F H, sshall a be increased by four percent to account for measurement error.

If the measured hot channel factor exceedss it i s 1 imitt specified under Item /a t he reactor power shall be reduced so as not to t' theF exceed a fraction of the rated value equal to th eraioof imit to measured value, whichever is less, and the hi h neutron flux trip setpoint shall be reduced by the same ratio-If subsequent incore mapping cannot, within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period demonstrate that the hot channel factors t, h shall bee brought to a hot shutdown condition with return to ower authorized only for the purpose of .physics testin . Th may be returned too hiig her er power levels when measurements indicate th a t h ot channel factors are within limits.

The reference equilibrium indicated axial flux difference as a function of power level (called the target flux difference) shall be measured at least once per effective f 11 the axial flux difference has not been measured in the last effective full power month, the target flux difference must be updated monthly by linear interpolation using the most recent measured value and the value predicted fo r th e en d o f the cycle life.

d. Except during physics tests or during excore calibration procedures and as modified by items Ge through 6 b 1 indicat ed axial flux difference shall be maintained with a + 5$

band about the target flux difference ( this is defin e ines t h e target band on axial flux difference).

e. If the indicated axial flux difference 'at a power level reater than 905 of rated power deviates

3. 2-4

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