ML17325A903

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Proposed Tech Specs Re New Steam Line Break Analysis
ML17325A903
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 08/15/1988
From:
AMERICAN ELECTRIC POWER CO., INC.
To:
Shared Package
ML17325A902 List:
References
NUDOCS 8808250055
Download: ML17325A903 (12)
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Text

Attachment 2 to AEP:NRC:0916AB Proposed Revised Technical Specification Pages SSOS250055 SBOS15 PDR ADOCK 05000316 P PDC

3 4.1 REACTIVITY CONTROL SYSTEMS 3 4.1.1 BORATION CONTROL SHUTDOWN MARGIN - STANDBY STARTUP AND POWER OPERATION LIMITING COND TION 0 OP R TIO 3.1.1.1 The SHUTDOWN MARGIN shall be > 2.0% hk/k.

APPLICABILITY: MODES 1, 2*, and 3.

ACTION:

With the SHUTDOWN MARGIN < 2.0% Iph,k/k, immediately initiate and continue boration at > 10 gpm of 20,000 ppm boric acid solution or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEI LANC R UIR M S 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be > 2.0% b,k/k:

a 0 Within one hour after detection of an inoperable control rod(s) 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 while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).

b. When in MODES 1 or 2", 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 control bank withdrawal is within the limits of Specification 3.1.3.6.
c. When in MODE 2 , within 4 hours prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3. 1.3.6.
  • See Special Test Exception 3. 10. 1

¹ With K > 1.0

¹¹ W1th K < 1.0 D.C. COOK - UNIT 2 3/4 l-l AMENDMENT NO.

t~ >>

REACTIVITY CONTROL SYSTEMS SURV LLANC E UIR M NTS Continued

d. Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3.1.3.6.
e. When in MODE 3, 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:
1. Reactor coolant system boron concentration,
2. Control rod 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 i

values to demonstrate agreement within 1% hk/k at least once per 31 Effective Full Power Days (EFPD). This comparison 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.

4. 1. 1, 1.3 Prior to blocking ESF Functional Units in accordance with footnotes ¹ and ¹¹ of Table 3.3-3, SHUTDOWN MARGIN shall be determined to be greater than or equal to 2.0% d k/k by consideration of the factors of
4. l. l. l.e above. The Reactor Coolant System average temperature used in making this SHUTDOWN MARGIN determination shall be less than or equal to 350'F. This SHUTDOWN MARGIN shall be maintained at all times when the ESF functions are blocked in-MODE 3.

D. C. COOK - UNIT 2 3/4 1-2 AMENDMENT NO.

t ki

IITY CONTROL S EMS SHUTDOWN MARGIN - SHUTDOWN LI ITING CO DITION FOR OPERATION 3.1.1 ~ 2 The SHUTDOWN MARGIN shall be:

a. In MODE 4:
1. Greater than or equal to 2.0% hk/k when operating with one or more Reactor Coolant Loops in accordance with Specification 3.4.1.3.
2. Greater than the value shown in Figure 3.1-3 when operating with no Reactor Coolant Loops but one or more Residual Heat Removal Loops in accordance with Specification 3.4,1.3.

be In MODE 5:

1. Greater than or equal to 1.0% 5k/k when operating with one or more Reactor Coolant Loops in accordance with Specification 3 '.1.3.
2. Greater than the value shown in Figure 3.1-3 when operating with no Reactor Coolant Loops but one or more Residual Heat Removal Loops in accordance with Specification 3.4.1 3. ~

APPLICABILITY: MODES 4 and 5 ACTION:

With SHUTDOWN MARGIN less than the above limits, immediately initiate and continue boration at greater than or equal to 10 gpm of 20,000 ppm boric acid solution or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE RE UIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the above limits:

a. Within one hour after detection of an inoperable control rod(s) 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 while the rod(s) is inoperable. If .the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod(s).

D. C. COOK - UNIT 2 3/4 1-3 AMENDMENT NO.

n O

O I

5.0 o

MODES 4 & 5 I

a 3.0 O

A ODE 4 2.0 f,+.

~"

~ ~

t T ~ r M "1 ~

"~

= ~ *~ I

  • I D4 1.0 r

MODE 5 Y 0.0L I l 200 400 600 800 1000 1200 1400 1600 1800 2000 BORON CONCENTRATION (PPM)

O Figure 3.1-3 REQUIRED SHUTDOWN MABGIN

CO'ASTROL REACTIVITY SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITIO FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:

Within the region of acceptable operation in Figure 3.1-2, and

-4

b. Less negative than -B.5 x 10 5k/k/ 0 F for the all rods withdrawn, end of cycle life (EOL), RATED THERi4fAL POWER condition.

APPLICABILITY: Specification 3. 1. 1.4.a - NODES 1 and 2* only~

Specification 3.1.1.4.b - NODES 1, 2 and 3 onl~

ACTION:

a. With the NTC more positive than the limit of 3.1.1.4.a above:
1. Establish and maintain control rod withdrawal limits sufficient to restore the MTC to within its limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.
2. Maintain the control rods within the withdrawal limits established above until subsequen" measurement verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.
3. Prepare and submit a Special Repor" to the Commission pursuant to Specification 6.9.2 within 10 days describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

With the MTC more negative than the limit of 3.1.1.4.b above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

  • With K eff greater than or equal to 1.0 See Special Test Exception 3.10.3 D. C. COOK - UNIT 2 3/4 1-5 AMENDMENT NO.

REACTIVITY CONTROL SYSTEMS SURVEILLANCE + EQUIREMENTS 4.1.1.4.1 The MTC shall be determined to be within its limits by confirmatory measurements. Measured MTC values shall be extrapolated and/or compensated to permit direct comparison with the above limits.

4.1.1.4.2 The MTC shall be determined to be within its limits during each fuel cycle as follows:

a) The MTC shall be measured and compared to the BOL limit of Specification 3.1.1.4.a, above, prior to initial operation above i% of RATED THERMAL POWER, after each fuel loading.

b) The MTC shall be measured at any THERMAL POWER within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm and the extrapolated MTC value compared to the EOL limit. In the event this comparison indicates that the MTC will be more negative than the EOL limit, the MTC shall be remeasured at least once per 14 EFPD during the remainder of the fuel cycle and the MTC value compared to the EOL limit.

D. C. COOK - UNIT 2 3/4 1-6 Amendment No.

TABLE 3.3-4 Continued ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

4. STEAM LINE ISOLATION
a. Manual Not Applicable Not Applicable Ce d.

Automatic Actuation Logic Containment Pressure Steam High-High Flyv in Tvo Steam Lines High Coincident with Tavg Not Applicable

< A 2.9 psig function defined as follows:,,A ap correspon-Not Applicable

< A 3.0 psig function defined as follovs: A hp correspon-I Low-Low ding to 1.47 x 10 lbs/hr ding to 1.62 x 10 lbs/hr steam flov between 04 and steam flow between 04 and 204 load and then a dp 204 load and then a zp in-increasing linearly to a creasing linearly to a hp zp6corresponding to 4.02 x cop'esponding to 4.07 x 10 lbs/hr at full load. 10 lbs/hr at full load.

T avg-> 541 F. T > 539 F.

e. Steam Line Pressure Low > 600 psig steam line > 585 psxg steam lane pressure pressure
5. TURBINE TRIP AND FEEDWATER ISOLATION
a. Steam Generator Water Level < 674 of narrow range < 684 of narrow range High-High instrument span each steam Instrument span each steam generator generator

TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

3. Pressurizer Pressure-Low
a. Safety Injection (ECCS) < 24.0"/12.0¹
b. Reactor Trip (from SI) < 2.0
c. Feedwater Isolation < 8.0
d. Containment Isolation-Phase "A" < 18.0¹
e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedwater Pumps < 60.0 9, Essential Service Water System < 48.0"/13.0¹
4. Differential Pressure Between Steam Lines-Hi h

'a ~ Safety Injection (ECCS) < 12.0¹/24.0¹¹

b. Reactor Trip (from SI) < 2.0 C. Feedwater Isolation < 8.0
d. Containment Isolation-Phase "A" < 18.0¹/28.0¹¹
e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedwater Pumps < 60.0
g. Essential Service Water System < 13.0¹/48.0¹¹
5. Steam Flow in Two Steam Lines - Hi h Coincident with Tav LOW LOW

'a ~ Safety Injection (ECCS) Not Applicable b, Reactor Trip (from SI) Not Applicable C. Feedwater Isolation Not Applicable

d. Containment Isolation-Phase "A" Not Applicable
e. Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable g, Essential Service Water System Not Applicable
h. Steam Line Isolation < 10 D. C. COOK - UNIT 2 3/4 3-27 AMENDMENT NO.

E 3 4. 1 REACTIVITY CONTROL SYSTEMS BAS S 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, RCS boron concentration, and RCS Tav The most restrictive condition for increased load events occurs at EOL, with T at no load operating temperature, and is associated with a postulate5 steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 2.0% hk/k is initially required to control the reactivity transient and automatic ESF is assumed to be available.

Technical Specification requirements call for verification that the SHUTDOWN MARGIN is greater than or equal to that which would be required for the MODE 3 low temperature value, 350'F, prior to blocking safety injection on either the P-ll or P-12 permissive interlocks. This assures in the event of an inadvertent opening of two cooldown steam dump valves that adequate shutdown reactivity is available to allow the operator to identify and terminate the event.

With T < 200'F, the reactivity transients resulting from a postulated steam line Nanak cooldown are minimal and a 1% hk/k SHUTDOWN MARGIN provides adequate protection for this event.

In shutdown MODES 4 and 5 when heat removal is provided by the residual heat removal system, active reactor coolant system volume may be reduced.

Increased SHUTDOWN MARGIN requirements when operating under these conditions is provided for high reactor coolant system boron concentrations to ensure sufficient time for operator response in the event of a boron dilution transient.

The SHUTDOWN MARGIN requirements are based upon the limiting conditions described above and are consistent with FSAR safety analysis assumptions.

3 4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 12,612 cubic feet in approximately 30 minutes. The reactivity change rate associated with boron reductions will therefore be within the capability for operator recognition and control.

D. C. COOK - UNIT 2 8 3/4 1-1 AMENDMENT NO.

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