ML17212A711

Proposed Amended Tech Specs 3/4.1.1,3.1.1.1,4.1.1.1,4.1.1.2, 3.1.1.4,4.1.1.4.1,3.4.1,4.4.1,3/4.1.1.1,3/4.1.1.2,3/4.1.1.3 & 3/4.1.1.4 for Boration Control,Moderator Temp Coefficient, Reactor Coolant Pumps & Boron Dilution & Addition

ML17212A711
Person / Time
Site:	Saint Lucie
Issue date:	09/04/1981
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17212A710	List: ML17212A709 ML17212A711
References
NUDOCS 8109100215
Download: ML17212A711 (7)

Text

3/4.1 REACTIVITY NTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T > 200.F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be > 5.0%% k/k.

APPLICABILITY: MODES 1, 2*, 3 and 4.

ACTION:

With the SHUTDOWN MARGIN < 5. 0/ g k/k, immediately initiate and continue boration at > 40 gpm of 1720 ppm boron or equivalent until the required SHUTDOWN MARGTN is restored.

SURVEILLANCE RE UIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be > 5.0g,hk/k:

a~ Within one hour after detection of an inoperable CEA(s) and at least onc'e per 12 hours thereafter whil e the CEA(s) is inoperable. If the inoperable CEA is immovable or untrippable, the above .required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth'f the immovable or untrippable CEA(s).

b. lthen in MODES 1 or 2g, at- least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that CEA group withdrawal is within the Power Dependent Insertion Limits of Specification 3.1.3.6.

C>> When in MODE 2gg, at least once during CEA withdrawal and at least once per hour thereafter until the reactor is critical.

d. Prior to initial operation above 5/ RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the CEA groups at the Power Dependent Insertion Limits of Speci fication 3.1.3.6.

See Special Test Exception 3.10.1.

With Keff > 1.0 With K ff < leO.

ST LUCIE UNIT 1 3/4 1-1 81091002iS 8i0904 PDR ADOCK OS00033S P

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS Continued

e. When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

l. Reactor coolant system boron concentration,

2. CEA position *

3. Reactor coolant system average temperature, 4, Fuel burnup based on gross thermal energy generation,

5. Xenon concentration, and

6. Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 1.(C a k/k at least once per 31 Effective Full Power Days (EFPD). This cuoparison shall consider at least those factors stated in Specification 4.1. l.l.l.e, above. The predicted .

reactivity values shall be. adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.

• For Modes 3 and= 4, during calculation of shutdown margin with all CEA's verified fully: inserted, the single CEA with the 'highest reactivity worth need not be assumed to be 'stuck in the fully withdrawn position.

ST. LUCIE UNIT 1 3/4 1-2

AEACT IVI TY .CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:

POWER is < 7'f a.Less positive than 0. 5 x 10 4b k/k/'F RATED THERMAL POWER, whenever THERMAL b.Less positive than 0.2 x 10 4 6, k/k/'F whenever THERMAL POWER is > 7(g of RATED THERMAL POWER, and c.Less negative than -2.2 x 10 4 b, k/k/'F at RATED THERMAL POWER.

MODES 1 .and 2*4

'PPLICABILITY:

ACTION:

With the moderator temperature coefficient outside any one of the above

,limits,, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQU IR EME NTS 4.1.1.4.1 The MTC shall be determined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.

• With K ff > 1.0.

gSee Special Test Exception 3.10.2 ST. LUCIE - UNIT 1 3/4 1-5

3/4.4 REACTOR CO T SYSTEM

) <<,Y..v REACTOR COOLANT LOOPS

'IMITING CONDITION FOR OPERATION 3.4.1 Four reactor coolant pumps shall be in operation.

APPLICABILITY: As noted below, but excluding MODE 6.

'CTION:

MODES 1 and 2:

,'+.-"-"'With less than four reactor coolant pumps in operation. be in at least HOT

~

. STANDBY within 6 hours.

4 MODES 3, 4 and 5:

Operation may pr oceed "provided (1) at least one reactor coolant. loop is in

'-'.-":;.-, operation, with an associated reactor coolant pump or shutdown coo'l,ing pump and

':-"(y(2) the SHUTOONN NARGIN 'requirement of Specification 3.1.1.1 is increased to

""and maintained at > 5.0g, h k/k during operation in flODE 3 when less than four reactor coolant pumps are in operation. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENT 4.4.1 The F1ow Dependent Selector Switch shall be determined to be in the 4 pump position within 15 minutes prior to making the reactor critica'I 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 /> thereafter All reactor coolant pumps and shutdown cooling pumps may be de-energized for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, provided no operations are permitted which could cause dilution of the reactor coolant system boron concento ation.

ST. LUCIE - UNIT 1 3/4 4-1

3/4.1 REACTIVIT NTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1. 1.1 AND 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RGS'- boron concentration, and RCS Tav The most restrictive condition occurs at'.EOL, with Tav at no load operating temperature, and is associated with. a 'ostulated steam line break accident and resulting uncontrolled RCS, cooldown. In the analysis of this accident, y minimum SHUTDOWN MARGIN ,:,'.: of 5. OX d. k/k is required to control the reactivity transient. Accord'i'ngly, the SHUTDOWN MARGIN requir ed by Specification 3.1.1.1 is based upon thi's limiting condition and is consist'ent with FSAR accident analysis assumptions. For earlier periods during the fuel cycle, this value is conservative. With Tav < 200 F the reactivity transients resulting from

-any postulated accident ate minimal and' 2g, ak/k shutdown margin provides adequate protection.

3/4.1.1.3 BORON DILUTION AND ADDITION A minimum fl ow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration changes in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System .

volume of 11,400 cubic feet in approximately 26 minutes.. The reactivity .

change rate assoicated with boron concentration changes will be within .the capability for operator recognition and control.

3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT MTC The limiting values assumed for the MTC used in the accident and transient analyses were + 0.5 x 10 "< k/k/'F for THERMAL POWER levels < 7Q of RATED THERMAL POWER, + 0.2 x 10 4 a k/k/'F for THERMAL POWER levels >70g, of RATED THERMAL and -2.2 x 10 4 h, k/k/'F at RATED THERMAL POWER. Therefore, these limiting values are included in this specification. Determination of MTC at the specified conditions ensures that the maximum positive and/or negative values of the MTC will not exceed the limiting values.

ST. LUCIE - UNIT 1 B 3/4 1-1

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