L-75-555, Letter Transmitting Addendum to Proposed Amendment to Facility Operating Licenses, Supplements 9/9/1975 Submittal Which Concerned Increase in Nominal System Operating Pressure for Unit 3, Cycle 3, from 1900 Psia to 2100 Psia

Letter Transmitting Addendum to Proposed Amendment to Facility Operating Licenses, Supplements 9/9/1975 Submittal Which Concerned Increase in Nominal System Operating Pressure for Unit 3, Cycle 3, from 1900 Psia to 2100 Psia

ML18227C718
Person / Time
Site:	Turkey Point
Issue date:	11/21/1975
From:	Robert E. Uhrig Florida Power & Light Co
To:	Boyd R Office of Nuclear Reactor Regulation
References
L-75-555
Download: ML18227C718 (14)

Text

NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL

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FROM Florida Power 6 Light' 'DATE OF DOC DATE REC'D LTR TWX RPT OTHER Miami, Pla. 33101 R E Uhri 11-21-75 11~ 26-75 TO: ORIG CC OTHER SENT NRC PDR Mr. Roger S. Boyd 3 signed 37 SENT LOCAL PDR CLASS UNCLASS PROP INFO 'NPUT NO CYS REC'D DOCKET NO:

XXX 40 50>>250 DESCRIPTION: Ltr notarized 11-24<<75 requests ENCLOSURES: Tech Spec 3.1.6(DNB Paraments 6 to amend App. A of Lic. DPR re incr ase 6 revised Pigure '2.1-1 for Lic. RHK-31 in .nominal system'operating pressu're DPR.

from 1900 p'sic; to 2100 'psi'a S .trans,tht

'ollowing: (40 cys ea encl rec'd)

PLANT NAIVIE: Turkey Pt. Unit 3.

FOR ACTION INFORMATION BUTLER (L) SCHWENCER (L) ZIEMANN (L) REGANopuses (E) REXD (L)

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I DOCKEt Eo '.e t P.O. BOX 3100 MIANII, FLORIDA 33101 Q) Qr USNRC FLORIDA POWER 5 LIGHT COMPANY bk NQY26]97'~ 5 OAK Swig POC~ QNS PP, November 21, 1975 L-75-555 Reguietory Docket Eiie ~i Director of Nuclear Reactor Regulation Attention: Mr. Roger S. Boyd, Acting Director A Division of Reactor Licensing ~

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U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Boyd:

Re: Turkey Point Plant Unit. 3 Docket No. 50-250 Addendum to Proposed Amendment to Facilit 0 crating License DPR-31 In accordance with 10 CFR 50.30, Florida Power Light Company S

submits herewith three signed originals and forty (40) conformed copies of a request to amend Appendix A of Facility Operating License DPR-31. This addendum supplements our September 9, 1975 submittal which concerned an increase in nominal system operating pressure for Unit 3, Cycle 3, from 1900 psia to 2100 psia. It is being submitted in response to requests received during recent discussions with your staff.

A new Technical Specification 3.1.6 (DNB Parameters) and a revised Figure 2.1-1 are attached. The DNB specification puts an upper limit on Tavg and a lower limit on pressurizer pressure.

The revised figure has a new line for 2100 psia.

In addition, the following information is provided in support of a minimum time to clad collapse of 23,500 EFPH for Cycle 3:

The calculation included in the Turkey Point Unit 3, Cycle 2 Technical Specifications gave a finite gap flattening time of 23,200 EFPH based on an assumed Cycle 3 operating pressure of 2250 psia (Case A).

The calculation included in the proposed Cycle 3 Technical Specifications gave a revised finite gap flattening time of 23,500 EFPH based on a new planned operating pressure of 2100 psia (Case B).

CASE A T3.me System Pressure "clad (EFPH) ( sia) ~(si a) 0-4900 2250 1700 4900-17000 1900 1350 17000-23500 2250 1700

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Director of Nuclear Reactor Regulation Attention: Mr. Roger S. Boyd, Acting Director Page Two November 2ll, 1975'ime CASE B QP System Pressure clad (EFPH) (psia) ~(sia) 0-4900 2250 1700, 4900-17000 1900 1350 17000-23500 2100 1550 Clad 0. D. 0.422" Nail Thickness 0.0243" Clad Temperature 590 F Fast Flux (>1 Mev): 7.3,x 10 n/cm per sec.

Very truly yours, Robert E. Uhrig Vice President REU/MAS/cpc Attachments cc: Mr. Norman C. Moseley Jack R. Newman, Esquire

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'first duly F J ROBERT E. UHRXG,. being sWorn,,'deposes and says:

That he is h Vice Pxesident, of Florida Power & Light Company, the Licensee herein) 1 That, he has executed the'foregoing 'instrument, that. the statements made in this said ins~ument are true and correct to the best of his knowledge, information and belief; and that he is authorised to ezecute the instrument of said Licensee.

Robert E. Uhr g Subscribed and sworn to before me th9.s p 1975 Not ry Pub c n an for the State of orida at Large

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TA'BLE OF CONTENTS Regulatory LOkek I'rle'pa Section Title e TECHNICAL SPECXFXCATXONS 1 DEFINITIONS "'- r'/~~a' 1-1 1.1 Safety Limits

> ccfo l-l 1.2 Limiting Safety System Settings l-l 1.3 Limiting Conditions for. Operation l-l 1.4 Operable 1-1 1.5 'ontainment Integrity 1-2 1.6 Protective Instrumentation Logic 1-2 1.7 Instrumentation Surveillance 1-3 1.8 Shutdown 1-3 1.9 Power'peration .

l. 10 Refueling Operation 1-4 1.11 Rated Power 1-4

• 1.12 Thermal Power 1-4 1.13 Design Power 1-4

1. 14 Abnormal 1-5 1.15 . Tilt Occurrence'ower 1-5

. 1.16 Interim Limits 1-6 1.17 Low Power Physics Tests 1-6 SAFETY LIMITS AND LIHITXNG SAFETY SYSTEM SETTINGS F 1 1 21 Safety Limit, Reactor Core 2.1-1 2.2 Safety Limit, Reactor Coolant System Pressure 2~2 1 2.3 Limiting Safety System Settings, Protective Instrumentation 2.3-1 3 LIMITING CONDITIONS FOR OPERATXON 3. 1-1 3.1 Reactor .Coolant System 3.1-1 Operational Components 3.1-1 Heat Up and 'Cool Down 3 1 2 Leakage 3~1 Maximum Reactor Coolant Activity 3~ 1 5 Reactor Coolant Chemistry 3.1-6 DNB Parameters 3. 1-7 3.2 Control Rod and Power Distribution Limits 3.2-1 Control Rod Insertion Limits , 3.2-1 Misaligned Control Rod 302-2 Rod Drop Time 3~2 2 Inoperable Control Rods 3~2 2 Control'od Position Indication 3 2 3

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Power Distribution Limits 30 2-3 In-Core Instrumentation 30 2-7 Axial Offset Alarms 3.2-8 3.3 Containment 3.3-1 3.4 Engineered Safety Features 3.4-1 Safety Injection and RHR Systems 3.4-1 Emergency Containment Cooling Systems '.4-3 Emergency Containment Filtering System 3.4-4 Component Cooling System 3.4-4 Xntake Cooling Mater System 3.4-5 3.5 Instrumentation 3.5-1 3.6 Chemical and Volume Control System 3.6-l 11/21/75

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UNIT NO. 3

6. DNB PARAK TERS The following DNB related parameter ,limits shall be maintained during power operation:

a. Reactor Coolant Syst: em Tavg ( 570.6 'F

b. Pressurizer 'Pressure > 2070 psia With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce thermal power to less than 5% of rated thermal power using normal shutdown procedures.

Compliance with this specifi,cation is demonstrated I

by verifying that each of the parameters is within its limits at least once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

3.1-7 UNIT NO. 3 11/21/75

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0 650

'640 2400 PSIA 630 2250 PSIA 620 Ch 2IOO PSIA I-

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I- 6IO C) 600 I900 PSIA I

590 Ih I700 PSIA 580 570 560 550 0 20 40 60 80 IOO I20 RATED POWER (PERCENT)

Figure 2.1-1. Reactor Core Thermal and Hydraulic Safety Limits, Three Bop OperationI, ~

ll/21/75

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