ML20043B200

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Proposed Tech Specs Re Cycle 2 Extension Using Increased Core Flow & Final Feedwater Temp Reduction
ML20043B200
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 05/18/1990
From:
DETROIT EDISON CO.
To:
Shared Package
ML20043B199 List:
References
NUDOCS 9005250065
Download: ML20043B200 (13)
v • d • e


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POWER DISTRIBUTION LIMITS 1 ELLLMIN1flWMRIIEALEGELSAT10 I

l- LIMITING C"n! TION FOR OPERATION 3.2.3. The MINIMUMshown CRITICAL in FiguresPOWER RATIO 3.2.3-1 thru(MCPR) 3.2.3-18"T shall be eet)imes the Kto or greaterj31

,. than the MCPR lied g shwn in Figure 3.2.3-2 with: .

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tg - tg ,

where:

14 = 1.096 seconds, control red averane scram insertion time -

limit to notch 36 per Specificat'on 3.1.3.3, 1 y b tg = 0.813 + 1.65[

I 3k.018, .

Ii=1"i  !

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NT i t,y, , 4,3 44 ,

n 1 Ng -3 181 [

n = numbe. ' >"*veillance tests performed to date in cycle, ,

th a

, Ng = number et o ^ive control rods measured in the i surveillan., test, j 1 9 = average scram time to notch 36 of all rods measured  :

in the i th surveillance test, and N = total number of active rods measured in Specification j 3 4.1.3.2,a. 1 APPLICABILITY:

OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of

-RATED THERMAL POWER.  ;

ACTION

a. Ontating in the Control Cell Core (CCC) operating mode
  • and MCPR less than t%e applicable MCPR limit shown in Figures 3.2.3-1 thru 3.2.3-18 .;
  • The CCC operating mode includes operation with only A2 rods Al shallow rods less than or equal to notch position 36, all peripheral rods inserted in the core, and rods inserted to position 46. Normal control rod operability checks, coupling checks, scram time testing, and friction testing of non CCC 6 control rods does not to uire the utilization of the more restrictive non CCC l operational mode MCPR li its. Any other ' operation is a non-CCC operating mode.

FERMI - UNIT 2 3/4 2-6 Amendment No. Mi 42 l bcs DVS ER Y ' t% 11ev (wtne k.s

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    • During Cycle 2, operation beyond a normal end-of-cycle core l exposure with core flow increased to (105% of rated corg flow ,

and/or with Final Feedwater Temperature reduced to >370 F is ,

permitted provided that the Moisture Separator Rehester and  :

Turbine Bypass System.are OPERABLE per Specification 3.7.9.

Curves A or B of Figure 3.2.3-1B apply to these operations.

  • fKg = 1.0 during operation with core flow 1100%.

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o POWER DISTR 18UTION LIMITS j 3/4.2.3 MINIMUM CRITICAL POWER RATIO ,

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LIMITING COuDITION FOR OPERATION  ;

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(Curve A) times the applicable K curve shown in Fi finitiate corrective action within 15 minu{estoand required 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 26% of withinrestore the MCP!ure 3 RATED THERMAL POWER within the maxt 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,

)

b. Operating'in the non-CCC operating mode
  • and MCPR less than the '

applicable MCPR limit shown in Figures 3.2.3-1 thru 3.J.31B (Curve B) times the applicable K, curve shown in Figure 3.2.3 2, initiate ,

corrective action within 15 minutes and m store MCPR to within the s

- required 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 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. l i

c. Operating in either the CCC or non-CCC operating mode with either the main turbine bypass system inoperable per Specification 3.7.9 or the
  • moisture separator reheater inoperable, operation may continue and the provisions of Specification 3.0.4 are not applicable provided that, within one hour, MCPR is determined to be equal to or greater than the MCPR limit as shown in Figures 3.2.3-1 thru 3.2.31B (Curve C) by the main turbine bypass or moisture separator reheater inoperable curve times the '

applicable Kg shown in Figure 3.2.3-2.4 #w

d. Operating in either the CCC or non-CCC operating mode with both the main turbine bypass system inoperable per Specification 3.7.9 and the moisture separator reheater inoperable, operation may continue and the provisions of Specification 3.0.4 are not applicable provided that, within one hour, MCPk is determined to be equal to or greater than the MCPR limit as shown in Figures 3.2.3-1 thru 3.2.3-18 by the main turbine bypass and moisture separator reheater inoperable curve times the applicable Ng shown in Figure 3.2.3 2.# y n f

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  • The CCC operating mode includes operation with only A2 rods, Al shallow rods less than or equal to notch position 36, Nomal control rod operabilityall peripheral ro core, and rods inserted to position 46.

checks, coupling checks, scram time testing, and friction testing of non-CCC control rods does not require the utilization of the more restrictive' non-CCC Any other operation is a non-CCC operating mode.

operational mode MCPR limits.

S e e, Etw ER.T Q n e w hofn o'fe s i

s 3/4 2-6a Amendment No. 42 i FERMI - UNIT 2

Insert p. 3/4 2-6a i:

      • In addition, during Cycle 2 operation beyond normal end-of-cycle core exposure with core flow increased above rated and/or Final i Feedwater Tesiperature reduced below normal restore core flow and l Final Feedwater Temperature to within norstal limits within one s > hour or reduce THERMAL POWER to less than 25% of RATED TIERMAL l

POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

t iKg = 1.0 during operation with core flow 1100%.

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4 POWER DISTRIBUTION LIMIT $

i SURVEILLANCE' REQUIREMENTS 4.2.3.1 MCPR, with: .

a. t = 1.0 prior to performance of the initial scram time measurements for the- cycle in accordance with Specification 4.1.3.2, or
b. t as defined in Specification 3.2.3 used to determine the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusion of each scram time surveillance test required by Specification 4.1.3.2,  :

shall be determined to be equal to or greater than the applicable MCPR limit determined from Figures 3.2.3 1 through 3.2.3-1B and 3.2.3-2.*

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,  !
b. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 151 of RATED THERMAL POWER, and
c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is ,

operating with a LIMITING CONTROL ROD PATTERN for MCPR.

d. The provisions of Specification 4.0.4 are not applicable.

i 4.2.3.2 Prior to the use of Curve A and whenever Surveillance Requirement 4.2.3.1 is performed while using Curve A of Figures 3.2.3 1.through 3.2.3-1B,.  ;

verify that all non-CCC control rods are fully withdrawn from the core.

Non CCC control rods are all control rods excluding A2 rods Al shallow rods

-inserted less than or equal to notch position 36, all peripheral rods, and  !

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rods inserted to position 46. Normal control rod operability checks, coupling checks, scram time testing, and friction testing of non-CCC control rods does not require the utilization of the more restrictive non CCC operational mode l

.MCPR limits.

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6ec /U)EKT % nem Qn%fu Amendment No. fi,44 i FERMI - UNIT 2 3/42-7 l

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  1. Kf = 1.0 during operation with core flow 1100%.

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FERMI - UNIT.2 3/4 3-44 Amendment No. I, 9, 36,42 h >

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i-4 Insert p. 3/4 3-44 footnotes l h< f The Flow Biased RBM Upscale Trip Function shall be clamped with a '

e maximum trip setpoint of 1106% and a miaximum allowable value of i: - 1109% during Cycle 2 operation beyond normal end of cycle exposure with core flow greator than rated. ,

if The Reactor Coolant System Recirculation System Upecale Rod Block trip setpoint may be increased to 1110% with an allowable value i of 1113% to allow Cycle 2 operation beyond normal end-of-cycle core exposure with core flow increased to 1105% of rated.

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. REACTOR-COOLANT SYSTEM.

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SURVEILLANCE REQUIREMENTS-4.4.1.1.1' Each pump discharge valve shall be demonstrated OPERABLE by c cling' '

O' 'each valve through at least one complete cycle of full travel-during each STARTUP* prior to THERMAL POWER exceeding 25% of RATED THERMAL POWER.

4.4.1'1.2 Each pump MG set scoop-tube mechanical and electrical stop shall be-i 1 demonstrated OPERABLE with overspeed setpoints less than or e:ual to IJO % and

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102.5%,respectively,ofratedcoreflow,atleastonce-peritmonths.7

'4.4.1.1.3 Establish a baseline APRM and LPRM** neutron flux noise va19* within 'I the regions for. which monitoring is required (Specification 3.4.1.1, ACT!0ii c) s h' within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of~ entering the region for which monitoring is required unlesa "

'baselining has previously been performed in the region since the last refueling )

outage. '

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  • If.not performed within the previous 31 days,
    • Detector levels A and C of- one LPRM string per core octant plus detectors A and C of one LPRM string in the center of the core should be monitored.

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lh f Each pump MG set scoop tube mechanical and electrical stop may be 4 set with overspeed setpoints less than or equal; to 107% of rated . .

core flow to allow Cycle 2-operation beyond normal end of cycle 1 core exposure with core flow increased up to j,105% of rated.'

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POWER DISTRIBUTION LIMITS

BASES g _j

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314.t.3 RINIMUM CRITICAL POW S RAf!0 (Contioned)-

bypass Systeer or the moisture se RAftDTHERMALPOWERisexceeded,paratorreheaterbetaoperable b

the MCPR ehack sust be sempleted wittin one ]

hour.-

The evaluation of a given transient begins with the system initial parameters shown in UFSAR Table 16.0.1 that are input to a SE-oore dynamie .

A tehavior transient computer program. The codes used to evaluate transients are described in SESTAt !!. The principal result of this evaluation:is the

. reduction in MCPR caused by the transient.

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The purpose of the K- factor of Figure 3.t.3 2 is to define operating J limits at other than rateI core flow conditions. At less then 2005 of '

rated flow the required MCPR is the product of the MCPR and the y factor. The K, factors assure that the Safety Limit MCPR will not be violated during a flow' l 1hcrosse transient resulting from a motor-generator speed control failure. The Kf factors may be applied to both annual and automatic flow control modes.

The K, factor values shown.in Figure 3.t.3 2 were developed generically 1 and are-apflicable to's11 SWR /2, BWR/3, and SWR /4 reactors. The K, factors- -

. were derived using the flow control line corresponding to RATED THERMAL POWER -

at rated core flow, although they are applicable for the extended opera *.ing _ ' q region. l

'For the manual flow control mode, tho' Kg factors were calculated'euch thst~ i'

for the maximum flow rate, as limited by the pump scoop tube setpoint and.the L correspondingTHERMALPOWERalongtheratedflowcontrolline'thelimiting i L bundlesrelativepowerwasad,1usteduntiltheMCPRchangesWIthdifferantcaro_

flows. The ratio of the MCPR calculated at a given point of core flow, divided by the operating limit MCPR, determines the y.  ;

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L FERMI - UNIT 2 3 3/4 2-4b Amendment No. 89.42.44 .[

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' Near the end -of an operating cycle, the reactivity f rom' the withdrawl - ,

,. of. control rods can. no longer maintain full RATED THERMAL POWER with other parameters. at r:ominal or rated conditions (for example, rated ,

o core flow, nominal feedwater temperature and equilibrium xenon). The core average exposure where this occurs is considered the normal end g . of cycle core exposure. - Operation beyond this exposure at a THERMAL POWER greater -than' what would otherwise be achieved can be .

accomplished-by reducing' the final feedwater temperature and/or t

. increasing the core-flow. Such operation was evaluated-for Cycle 2  :

and is acceptable provided' the restrictions of the LCO are met.

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