L-77-386, Proposed Amendment to Facility Operating License No. DPR-67. Technical Specifications Proposed Change Concerning Modification of Incore Monitoring Alarm Setpoints & Excore Monitoring Power Scaling Factor to Be More Conservative

Proposed Amendment to Facility Operating License No. DPR-67. Technical Specifications Proposed Change Concerning Modification of Incore Monitoring Alarm Setpoints & Excore Monitoring Power Scaling Factor to Be More Conservative

ML18088B288
Person / Time
Site:	Saint Lucie
Issue date:	12/19/1977
From:	Robert E. Uhrig Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-77-386
Download: ML18088B288 (9)

Text

NRC,FORh! 195 U.S. NUCLEAR REGULATORV COMMISSION DOCKET NUMBER I2-7B)'RC FII.E NUMBER DISTRIBUTION FDR PART 60 DOCKET MATERIAL TO: FROM: DATE OF DOCUMENT Flori'da Power & Light Company 12/19/77 Mr. Victor'tello Miaad., Florida" ',DATE Rober't Ei Uhr2ig RECEIVED'2/23/77 LETTER QNOTORIZEO PROP INPUT* FORM NUMBER OF COPIES RECEIVED PfORIGINAL QHfNC LASS IF I E 0 Ocopv

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N .~P4W84 DESCRIPTION ENCLOSURE

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License No, DPR-67 Appl for ABIend: tech specs

'proposed change concerning modification of the incore monitoring ala'rm setpoints & the excore monitoring power scaling factor to be more conservative than the current tech specs by 1/2%i ~ inotorized 12/19/77 ~~~ ~~~

PLANT NA5IE: St, 'Lucie Unit No 1 12/27/77 (2-P) (1-P)+(1-P)

RGL FOR ACTION/INFORMATION

+u EiiVIRONi4EiITAL ASSIGiiED AD: OR LTR)

CH CHIEF: BRANCH CHIEF:

PROJECT bIANAGER:

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B. HARLESS INTERNAL 0 IST RI BUTION F ES T SYSTEMS SITE SAFETY G ENVIRON ANALYSIS DENTON G NULLER GOSSICK G STAFF ENGINEERING LITO NVIRON TECH ERNST CTORS BALLARD LO D AGEiiENT ACTOR SAFETY TECH ROSS B R GAi~WILL 2)

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December 19, 1977 L-77-386 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director

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U. S.

Division of Operating Reactors Nuclear Regulatory Commission Washington, D. C. 20555

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Dear Mr. Stello:

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cph4ll5gIpN Re: St. Lucie Unit 1 t5-'Il RcllaI Docket No. 50-335 Q Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power 6 Light Company (FPL) submits herewith three (3) signed originals and forty. (40) copies of a request to amend Appendix A of Facility Operating License DPR-67.

Due to information received from the St. Lucie Nuclear Steam Supply System vendor, FPL proposes to modify the incore moni-toring alarm setpoints and the excore monitoring power scaling factor to be more conservative than the current Technical Specification by 1/2%.

The proposed amendment will involve Technical Specification changes as described below and as shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right. hand corner.

Pa e 3/4 2-2 Specification 4.2.1.3.c is revised to incorporate a'dditional conservatism of 1/2S. The relationship L x will become L = L 0

M 17 0(1 005) x M 17 09 x M Also, new Specification 4.2.1.4.b.6 incorporates the additional conservatism of 1/2S by adding a water hole peaking factor bias 'of 1..005.

The detailed explanation and safety analysis for this change are contained in the letter from A. D. Scherrer (Combustion Engineering) to K. Kniel (NRC) dated December 15, 1977 and was further described by CE in a meeting with the NRC on December 16, 1977.

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Mr.

0 Victor Stello, Director Division of Operating Reactors Pa e Two As these modifications are'n the conservative direction, we have implemented them as of December 15, 1977 and will operate St. Lucie Unit 1 under these modified specifications for the remainder of Cycle l.

The proposed amendment has been reviewed by the FRG and CNRB, and the conclusion reached that cant hazards consideration.

it does not involve a signifi-Ver truly yours, Robert E. Uhrig Vice President REU/RRJ/MAS/lah Attachment cc: Mr. James P. O'Reilly, Region Robert Lowenstein, Esquire II Edward Reeves

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POWER DISTRI8UTION LIMITS SURVEILLANCE RE(}UIREHENTS Continued

c. Verifying at least once per 31 days that the THERMAL POWER does not exceed the value determined by the following relationship:

L x M

17. 09 .

where:

1. L is the maximum allowable linear heat rate as determined from Figure 3.2-1 and is based on the core average burnup at the time of the latest incore flux map.

2. M is the maximum allowable THERMAL POMER level for the exist~;~g 'Reactor Coolant Pump combination.

4.2.1.4 Incore Detector Monitorin S stem - The incore detector neni-toring system may be used for monitoring the core power d'istribution by verifying that the incore detector Local Power Density alarms:

a. Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days.

b. Have their alarm setpoint adjusted to less than or equal to the limits shown on Figure 3.2-1 when the following factors are appropriately included in the setting of these alarms:

Flux peaking augmentation factors as shown in Figure 4.2-1,

2. A measurement-cal culaiional uncertainty factor of 1.10,

3. An engineering uncertainty factor of'1.03,

4. A linear heat rate uncertainty factor of 1.01 due to axia1 fuel densification and thermal expansion, and

5. A THERMAL POWER measurement uncertainty factor of 1.02.

6. A water'hole peaking Sactor bias of 1.005.

ST. LUCIE - UNIT1 3/4 2-2 12/l9/77

STATE OF FLORIDA )

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Robert E. Uhrig, being first duly sworn, deposes and says:

That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.

Robert E. Uhrig Subscribed and sworn to before me this

~day of ,

~9'OTA Y PUBLIC, in and for the County of Dade, State of Florida Ny commission expires -c~t:.-o"'i>;"J'""<;;,.','-"'".,-.",2.!".'.~

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