ML17339A999
| ML17339A999 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/01/1980 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 1-80-134, NUDOCS 8005060151 | |
| Download: ML17339A999 (10) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8005060151 DOC ~ DATE: 80/05/01 NOTARIZED'O FACIL:50 250 Turkey Point Pl anti Uni t 3i Florida Power and Light C
50-251 Turkey Point Plant~
Unit 0i Flor ida Power and Light C
AUTH BYNAME AUTHOR AFFILIATION UHRIGr R ~ Ee Florida Power 8 Light Co, REC IP o NAME RECIPIENT AFFILIATION EISENHUT<D ~ G, Division of Licensing DOCKET ¹ 05000250 05000251
SUBJECT:
Forwards addi info re accuracy of flux vs load checkpin response to NRC request L as supplement to 770125 request for amend. Draft operating Procedure 12300.3 encl, DISTRIBUTION CODE!
A001S COPIES RECEIYED;LTR J.
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TITLE: General Distribution for after Issuance of Operating Lic ES P0 ~
OTES ~
RECIPIENT ID CODE/NAME ACTION; 05 BC 6 8 ~ (
INTERNAL:
REG FILE 1
17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS OELD EXTERNAL: 03 LPDR 23 ACRS COPIES LTTR ENCL 7
7 1
2 2
1 1
1 1
1 1
1 0
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16 16 RECIPIENT ID CODE/NAME 02 NRC PDR 15 CORE PERF BR 18 REAC SFTY BR 20 EEB EPB~DOR STS GROUP LEADR 00 NSIC COPIES
.LTTR ENCL
>>eo TOTAL NUMBER OF COPIES REQUIRED'TTR 38 ENCL 37
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P.O. BOX 529100 MIAMI,FL 33152
~l 66 FLORIDAPOWER & LIGHTCOMPANY May 1, 1980 L-80-134 Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut Acting Director Division of Operating Reactors U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Eisenhut:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 "dT vs Reactor Power" Curve The attached information is provided in response to a request from your staff and supplements our amendment request of January 25, 1977 (L-77-32).
Very truly yours, Robert E. Uhrig
~
~
~
~
Vice President Advanced Systems 8 Technology REU/RAK/ah Attachment cc:
J.
P. O'Reilly, Region II Harold F. Reis, Esquire gooi
/gi PEOPLE... SERVING PEOPLE
n 0
r
ATTACHMENT Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 "hT vs Reactor Power" Curve 1.
Florida Power 8 Light Company has determined that the flux vs load check is accurate to within +lX, and the hT vs reactor power check is accurate to within +0.74.
Input signal to curve contributors have been considered in the accuracy determination.
2.
The hT vs reactor power check will be included in a Turkey Point Plant operating procedure.
An example of a draft procedure is shown in the attached marked up copy of Operating Procedure 12304.3.
3.
We plan to perform both the flux vs load and hT vs reactor power checks initially.
4.
We do not intend to delete the flux vs load check from the operating procedures, but plan,to retain it as a
back-up to the hT vs reactor power check.
~
FLORXDA POMER
& LXGHT COMPANY TURKEY POXNT UNXTS 3
& 4 OPERATXNG PROCEDURE 12304.3 NOVEHBER 30 1976 Hzcevco APH r o 1880
'censing f gavjronmental Planning
1.0 Title
POWER RAGE NUCLEAR XNSTRtNENTATXON SHXPT CHECKS AND DAXLY CALXBRATXONS 2.0 A
royal and List of Effective Pa es:
- 2. 1
~Arousal:
Change Dated ll/30/76 Reviewed by PNSC November 30 1976 Approved by Plant Supt.,
2.2 List of E ective P 's:
~Pa e
Date 1
11/30/76 2
ll/30/76 3
11/30/76
~Pa e
Date 4
11/30/76 5
10/23/75 6
11/30/76
~Pa e
Date 8/28/75 ll/30/76 3.0
~Pur ose:
This procedure provides the necessary instruction to perform the shift checks and daily calibrations of the Nuclear Power Range Xnstrument
'hannels.
4.0 Precautions and Limits:
4.1 Shift checks and daily calibrations shall be done when the reactor is above 10 percent of rated power..
4.2 Before adjusting a power range gain, verify none of the other channels are in the trip mode.
4.3 Adjust only one power range gain at a time.
4.4 NXS Power Range Meters will be maintained within the following limits:
1.
Reactor Power equal to or greater than 90 percent, the average of the power range meters should be within + 1 percent of the thermal calorimetric.
2.
Reactor power less than 90 percent, the average of the power range meters should be within + 2 percent of the thermal calorimetric.
OPERATING PROCEDURE 12304.3, PAGE 3 P~
RANGE NUCLEAR INSTRUMEÃZATI~
SHWT CHECKS AND DAILX CALIBRATIO~
11/3O/76 8.0 Y'ctt'8'RH, lnstruttions:
Q~
6'lY't'i'El.
5+Otlooi Q.L oR
>LV~ us.
8.1 Shift Check of NXS Use Data and Horksheet:
NOTE: All curv'es referred to belo~ are from the Plant Cuxve Book Section I.
1.
Read the generator
- load, condenser vacuum, barometxic pressure and power range meters and record.
2.
Calculate the back pressure (barometer
. condenser vacuum) and record.
3.
Obtain and record the estimated reactor power from the Flux vs-Lo-ad Curve (Figure P FCB) using the generator load and back pressure.
4.
5.
Obtain the correction, C, from'the most recent NIS Calibration.'alculate the corrected Figure 1 power by adding the correction C, to the power obtained in 8.1.3.
- 6. 'alculate the average of the power range meter readings recorded in 8.1.1 and record it in the space pxovided.
7.
Calculate the estimated NIS error
(%) as the difference
. between the average meter reading and the corrected Figure 1
power.
XhhRRR ScCOog
- 8. If the estimated NIS error exceeds the values stated in step 4.4, complete section.8-.4; 8 3 Daily thermal calibration of the NIS g.3.( ~.r-DDPS Method 1.
Compute the reactor power by using the datalogger's pxogram (CAL).
Record the necessary data outputed to the line printer on a form similar to that displayed on page 8 ~
Minimum infor-mation shall include
% power from all operating power range
- channels, calorimetric power, meter correction factor, flux ys. load power and shift check correction factor.
NOTE:
Xf the datalogger is inoperative the manual method described in step 4-.~ shall be used.
G.o 5 2.
Power Range currents may also be recorded.
3.
Calculate a meter correction value for each NIS channel as the calorimetric power minue the meter reading.
The error printed from the DDPS is inaccurate and shall not be used fox a meter correction.
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