ML20065P186

Proposed Tech Specs Re Boron Dilution Analysis for Cycle 4 Reload

ML20065P186
Person / Time
Site:	Millstone
Issue date:	12/04/1990
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20065P184	List: B13678, Boron Dilution Analysis,Cycle 4 ML20065P179 ML20065P186
References
NUDOCS 9012130147
Download: ML20065P186 (51)

Text

- - __

O Docket No. 50-423 B13678 Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Proposed Technical Specification Changes Cycle 4 December 1990 9012130147 901204 3 pg ADOCK 0500

r Attachment 2 B13678/Page 1 December 4, 1990 Millstone Nuclear Power Station, Unit No. 3 Proposed Technical Specification Chanaes. Cycle 4 Section Title Paae Number Index Index Section 3.1.1.1.2 Boration Control-Shutdown New Section Margin Modes 3, 4 and 5 Loops Filled Section 3.1.1.2 Shutdown Margin-Cold Shutdown 3/4.1-3

-Loops not filled Section 3.1.2.1 Flow Path-Shutdown 3/4 1-7 Section 3.1.2,2 Flow Paths-Operating 3/41-8 Section 3.1.2.4 Charging Pumps-0perating 3/4 1-10 .

Section 3.1.2.6 Borated Water Sources-0perating 3/4 1-12 Table 3.3-1 Reactor Trip Instrumentation 3/4 3-2 3/4 3-4 3/4 3-5 3/4 3-6 Table 4.3-1 Reactor Trip Instrumentation 3/4 3-12 Surveillance Requirements 3/4 3-13 l 3/4 3-14 Section 3.4.1.4.2 Cold Shutdown-Loops Not Filled 3/4 4-6 Section 3.4.1.6 Isolated Loop Startup 3/4 4-8 Section 3.9.1.1 Boron Concentration 3/4 9-1 Bases Sections Shutdown Margin B 3/4 1-1 3/4.1.1.1 and 3.4.1.1.2 Bases Section 3/4.1.2 Boration Systems B 3/4 1-3 Bases Section 3/4.4.1 Reactor Coolant Loops and B 3/4 4-1 Coolant Circulation 1

Bases Section 3/4.9.1 Boron Concentration B 3/4 9-1 Section 3.2.4 Quadrant Power Tilt Ratio 3/4 2-26

INDEX s

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION 12SE 3/4.0 APPLICABillTY .............................................. 3/4.0-1  ;

3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - HODES 1 AND 2 ......................... 3/4 1 1 Shutdown Margin - MODES 3, 4, AND 5 LOOPS FILLE 0 ........ 3/4 1-3 FIGURE 3.1-1 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH FOUR LOOPS IN OPERATION ............... 3/4 1-4 FIGURE 3.1-2 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH THREE LOOPS IN OPERATION .............. 3/4 1-5 FIGURE 3.1-3 REQUIRED SHUTDOWN MARGIN FOR MODE 4 ........ 3/4 1-6 FIGURE 3.1 4 REQUIRED SHUTDOWN MARGIN FOR MODE 5 WITH RCS LOOPS FILLED ........................... 3/4 1-7

, Shutdown Margin - Cold Shutdown -

Loops Not filled ........................... 3/4 1-8 FIGVRE 3.1-5 REQUIRED SHUTDOWN MARGIN FOR MODE 5 WITH RCS LOOPS FILLED ........................... 3/4 1-9 Figure 3.1-2 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH Moderator Temperature Coefficient ....................... 3/4 1-10 Minimum Temperature for Criticality...................... 3/4 1-12 3/4.1.2 B0 RATION SYSTEMS Flow Path - Shutdown .................................... 3/4 1-13 Flow Paths- Operating .................................. 3/4 1-14 Charging Pump - Shutdown ................................ 3/4 1-15 Charging Pumps - Operating .............................. 3/4 1-16 Borated Water Source - Shutdown ......................... 3/4 1-17 Borated Water Sources - Operating ....................... 3/4 1-18 3/4 '. l . 3 MOVABLE CONTROL ASSEMBLIES Group Height ............................................ 3/4 1-20 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN-IN0PERABLE FULL-LENGTH R00 .................. 3/4 1-22

, Position Indication Systems - Operating ................. 3/4 1-23 l

i.

l HILLSTONE - UNIT 3 iv Amendment No #

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INDEX

,. e LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION EMI Position Indication System-- Shutdown.................... 3/4 1-24 Rod Drop Time............................................ 3/4 1-25 Shutdown Rod Insertion Limit............................. 3/4 1-26 Control Rod Insertion Limits............................. 3/4 1-27 3/4.2 POWER DISTRIBUTION LIMITS ,

3/4.2.1 AXIAL FLUX DIFFERENCE.................................... 3/4 2-1 Four Loops Operating..................................... 3/4 2 1

-Three Loops 0perating.................................... 3/4/2-4.

3/4.2.2 HEAT. FLUX HOT CHANNEL FACTOR - F g (Z)..................... 3/4 2-7

.Four Loops 0perating...................................... 3/4 2-7 Three Loops 0perating..-.................................. 3/4.2-11 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACT 0R................................................... 3/4 2-15 Four Loops 0perating..................................... 3/4 2-15 ,

Three Loops 0perating.................................... 3/4 2-18 3/4.2.4 QUADRANT POWER TILT RATIO........ ....................... 3/4 2-20 3/4.2.5 DNB PARAMETERS........................................... 3/4 2-23  :

TABLE 3.2-1 DNB PARAMETERS........................................ 3/4 1-24 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION...................... 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION................... 3/4 3-2

-TABLE 13.3-2 REACTOR TRIP. SYSTEM INSTRUMENTATION RESPONSE TIMES.... 3/4 38 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE

. REQUIREMENTS............................................. 3/4 3 3/4.3.2 : ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.......................................... 3/4 3-15 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.......................................... 3/4 3-17 TABLE.3.3-4 , ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0lNTS........................... 3/4 3-26 MILLSTONE - UNIT 3 v Amendment No. A0

L 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORAT10N CONTROL-SHUT 00WN MARGIN - MODES 3. 4 AND 5 LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.1.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 3.1-1, 3.1-3 and 3.1-4 for four loop operation and in Figure 3.1-2 for three loop operation.

APPLICABILITY:- MODES 3, 4 and 5 ACTION:

With the SHVTDOWN MARGIN less than the requirca value, immediately initiate ,

and continue boration at greater than or equal to-33 gpm of a soluttur: .

containing greater than or equal to 6300 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SVRVEILLANCE RE0VIREMENTS 4.1.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be greater than or

, equal to the required valus;

a. Within 1 nour after detection of an inoperable control rod (s) and at least snce 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 verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and

b. 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, i ~2) Control rod position,

3) Reactor Coolant System average temperature,

4) Fuel burnup based .on gross thermal energy generation, j 5) Xenon concentration, and L

l 6) Samarium concentration.

l- 4.1.1.1.2.2 Valve 3CHS-V305 shall -be verified closed and locked at least once

! per 31 days.

MILLSTONE - UNIT 3 3/4 1-3 0007

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FIGURE 3.1-1 REQUIRED SHUTDOWN MARGIN FOR MODE 3 WITH FOUR LOOPS IN OPERATION

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FIGURE 3.1-3 REQUIRED SHUTDOWN WARGIN FOR MODE 4

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FIGURE 3.1-4

, REQUIRED SHUTDOWN MARC.IN FOR MODE 5 WITH RCS LOOPS FILLED

i 1

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION ,

3.1.1.2 'The SHVTDOWN MARGIN shall be greater than or equal to a) the limits shown in Figure 3.1-5 or b) the limits shown .in Figure-3.1-4 and . secure the valves shown in Specification 4.4.1.4.2.3.

APPLICABILITY: MODE 5 LOOPS NOT FILLED ACTION:

- With the SHUTDOWN MARGIN less than the above, immediately initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6300 ppm boron or equivalent until the required SHVTDOWN MARGIN is restored.

SVRVEILLANCE RE0VIREMENTS 4.1.1.2.1 The SHVTDOWN MARGIN shall be-determined to be greater than- or equal-to the above:

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 verified acce) table with an increased allowance for the withdrawn worth of tie immovable or untrippable control rod (s); and.

b' . - 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 1). Reactor Coolant System boron concentration,

2) Control roa position,

3) . Reactor Coolant-System average temperature,

4) Fuel burnup based' on gross thermal energy generation,

5) Xenon concentration, and

6) Samarium concentration.

4.1.1.2.2 Valve 3CHS-V305 shall be verified closed and locked at least once per'31 days.

MILLSTONE - UNIT 3 3/4 1-8

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4 REACTIVITY CONTROL SYSTEMS

-MODERATOR TEMPERATURE COEFFICIENT f LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified in the CORE OPERATING LIMITS REP 0 The maximum upper limit shall be less positive than +0.5 x 10 gTS (COLR).

Ak/k/'F for all the rods withdrawn, beginning of cycle life (BOL), condition for power levels up to 70% RATED THERMAL POWER with a linear ramp to 0 Ak/k/*F at 100% RATED THERMAL POWER.

APPLICABILITY: BOL - MODES I and 2* only**.

End of Cycle life (E0L) Limit - MODES 1, 2, and 3 only**.

ACTION:

a. With the MTC more positive than the BOL limit of Specification 3.1.1.3 above, operation in MODES 1 and 2 may proceed provided:

1. -Control rod withdrawal limits are established and maintained sufficient to restore the HTC to less positive than the above 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. The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition; and

-3. A Special Report is prepared and submitted 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.

b. With the MTC more negative than the E0L limit specified in the COLR, 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 Keff greater than or equal to 1.

• • See Special Test Exceptions Specification 3.10.3.

MILLSTONE - UNIT 3 3/4 1-10 Amendment No. JE, 29, E9 0001

+

i 4

e

' REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE0VIREMENTS 4.1.1.3 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 3.1.1.3,.above, prior to initial operation above 5%

of RATED THERMAL POWER, after.each fuel loading; and b.- The MTC shall be measured at any THERMAL POWER and compared to the 300 ppm surveillance limit specified in the COLR (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium heron concentration of 300 ppm. In the event this comparison indicates the MTC is more negative than the 300 ppm surveillance limit specified in the COLR, the MTC shall be remeasured, and compared to the EOL MTC limit specified in the COLR, at least once per.14 EFPD during the remainder of the fuel cycle.

4 d

A MILLSTONE - UNIT 3 3/4 1-11 Amendment No. 29, Ep

REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICAllTY LIMITING CONDITION FOR OPERATION 3.1.1.4 shall beThe Reactor greater thanCoolant System or equal lowest operating loop temperature (Tavg) to 551'F.

APPLICABILITY: MODES 1 and 2* **.

ACTION:

With a Reactor Coolant System operating loop temperature (T,yg) less than 551*F, restore T,yg to within its limit within 15 minutes or be in HOT STAT'DBY within the next 15 minutes, p'9VEllLANCE RE0VIREMENTS 4.1.1.4 The Reactor Coolant System temperature (T"V9) shall be determined to be greater than or equal to 551*F:

a. Within 15 minutes prior to achieving reactor criticality, and

b. At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T avg is less than 5610F with the T avg-Tref Deviation Alarm not reset.

• With Keff greater than or equal to 1.

• • See Special Test Exceptions Specification 3.10.3.

t MILLSTONE - UNIT 3 3/4 1-12 0007

9EACTIVITY CONTROL SYSTEMS 3/4.1.2 BORAT10N SYSTEMS TLOW PATH - SHQlEQEN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergenc; power source:

a. A flow path from the boric acid storage system via either a boric acid transfer pump or a gravity feed connection and a charging pump to the Reactor Coolant System if the boric acid storage system in Specification 3.1.2.Sa. is OPERABLE, or

b. The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.5b. is OPERABLE.

APPLIC ABij,111: MODES 5 and 6.

ACTION:

With none of the above flow paths OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations it.volving CORE ALTERATIONS or positive reactivity changos.

SURVElllANCE REQUIREMENTS _

4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that the Boric Acid Transfer Pump Room temperature and the boric acid storage tank solution temperature are greater than or equal to 670F when a flow path from the boric acid tanks is used, and

b. At least once per 31 days by verifying th-t each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

1 MILLSTONE - UNIT 3 3/4 1-13 coor

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+

. REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two* J the following three boron injectioa flow esths shall be OPERABLE:

a. The flow path from the boric acid storage system via a boric acid transfer pump and a charging pump to the Reactor Coolant System (RCS),and

b. Two flow paths from the refueling wuer storage tank via charging pumps to the RCS.

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

ACTION:

With only one of the above required Doron injection flow paths to the RCS OPERABLE, restore at least two boran injection flow paths to the RCS to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> er be.in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least the limits as shown in Figure 3.1 4 at 200'F within the next 6 hottrs; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

I SURVEILLANCE RE0VIREMENfS ,

4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

_a. At least once per 7 days by verifying that the Boric Acid-Transfer Pumn Room temperature and the boric acid storage tank solution temperature are greater than or equal to 67'F when it is a required water source;

b. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed..or otherwise secured in position, is in its correct position,

c. At least once per 18 months during. shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection test signal;; and

d. At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a. delivers at least 33 gpm to the RCS.

• 0nly one boron injection-flow path is required to be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 350'F.

MILLSTONE - UNIT 3 3/4 1-14 0007 l

REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHVIDQMN LIMITING CONDITION FOR OPERATION 3.1.2.3 One ch uging pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no charging pump OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE RE0VIREMENTS 4.1.2.3.1 The above required charging pump shall be demonstrated OPERABLE by verifying,_ on recirculation flow, that a differential pressure across the pump of greater than or equal to 2411 psid is developed when tested pursuant to Specification 4.0.5.

4.1.2.3.2 All charging pumps, excluding the above required OPERABLE pump, shall be demonstrated inoperable at least once per 31 days, except when the reactor vessel head is removed, by verifying that the motor circuit breakers are secured in the open position, i

MILLSTONE - UNIT 3 3/4 1-15 0007

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two* charging pumps shall be OPERABLE.

APPLICABill.11: MODES 1, 2, 3, and 4.

l ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and boratt:d to a SHUTDOWN HARGIN equivalent to at least the limit as shown in figure 3.1-4 at 200'f within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHVTDDWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SVRVEILL@CE REMLREMENTS 4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE by verifying, on recirculation flow, that a differentia ^l pressure across each l pump of greater than or equal to 2411 psid is developed when tested pursuant to Specification 4.0.5.

I 4.1.2.4.2 All charging pumps, except the above allowed OPERABLE pump, shall be demonstrated inoperable at least once per 31 days whenever the temperature of one or more of the Reactor Coolant System (RCS) cold legs is less than or equal to 350'F by verifying that the motor circuit breakers are secured in the open position.

I TA maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 350'f.

i MILLSTONE - UNIT 3 3/4 1 16 0007 2

REACTIVITY CONTROL SYSTEMS 30 RATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 As a minimum, one of the following borated water sources shall be j OPERABLE' l

a. A Boric Acid Storage System with: i

1) A minimum contained borated water volume of 6700 gallons,

2) A boron concentration between 6300 and 7175 ppm, and

3) A minimum solution temperature of 67'F. t

b. The refueling water storage tank (RWST) with:

1) A minimum contained borated water volume of 250,000 gallons,

2) A ninimum boron concentration of 2700 ppm, and

3) A minimum solution temperature of 40'F.

APPLICABILITY: MODES 5 and 6.

ACTION:

i With no borated water source OPERABLE, suspend all operations involving CORE

. ALTERATIONS or positive reactivity changes.

SVRVEILLANCE RE0VIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

a. At least once per 7 days by:

1) Verifying- the boron concentration of the water,

2) Verifying.the contained borated water volume, and

3) Verifying the Boric Acid Transfer Pump _ Room temperature and L the boric acid storage tank solution temperature when it is.

l the source of borated water,

b. 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 verifying the RWST temperature when it is the' source of borated water and the outside air temperature is less than 35'F.

t MILLSTONE - UNIT 3 3/4 1-17 Amendment No. J2 0007 l

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REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 As a minimum the following berated water source (s) shall be OPERABLE as required by Specification 3.1.2.2:

a. A Boric Acid Storage System with:  ;

1) A minimum borated water usable volume of 21,020 gallons,

?) A boron concentration between 6300 and 7175 ppm, and

3) A minimum solution temperature of 67'F.

b. The refueling water storage tank (RWST) with:

1) A minimum contained borated water volume of 1,166,000 gallons,

2) A boron concentration between 2700 and 2900 ppm,

3) A minimum solution temperature of 40*F, and

4) A maximum solution temperature of 50*F.

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

ACTION:

a. With the Boric Acid Storage System ino)erable, restore the system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or se in at least 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 /> and borated to a SHUTDOWN MARGIN equivalent to at least the limits as shown in Figure 3.1 4 at t 200'F; restore the Boric Acid Storage System to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,

b. With the RWST innperable, restore the tank to OPERABLE status Ithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> and in COLD SHVTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

MILLSTONE - UNIT 3 3/4 1-18 Amendment No. J2 0007

REACTIVITY CONTROL $75TLMS SVRVEILL.ANCE RE0MIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPERABLE:

a. At least once per 7 days by:

1) Verifying the boron concentration in the water,

2) Verifying the contained borated water volume of the water source, and

3) Verifying the Boric Acid Transfer Pump Room temperature and the boric acid storage tank solution temperature.

b. 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 verifying the RWST temperature.

MILLSTONE - UNIT 3 3/4 1-19 DC(1

1 REACTIVITY CONTROL SYSTEMS I

3/4.1.3 MOVABLE CONTRQLASSEMBLIES

! GROUP HEIGHT i LIMITING CONDil!ON FOR OPERATION i

3.1.3.1 All full-length shutdown and control rods shall be OPERABLE and

! positioned within 112 steps (indicated position) of their group step counter i deniand position.

. APPLICABillTY: MODES 1* and 2*.

l l

ACTION: l I

1 a. With one or more full-length rods inoperable due to being '

immovable as a result of excessive friction or mechanical i

interference or known to be untrippable, determine that the l SHU100WN MARGIN requirement of Specification 3.1.1.1 is satisfied within I hour and 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 />.

[ b. With one full length rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligned from its

, group step counter demand height by more than 112 steps (indicated L sosition),POWEROPERATIONmaycontinueprovidedthatwithin1

, 1our:

1

1. The rod is restored to OPERABLE status within the above alignment requirements, or i 2. The rod is declared inoperable and'the remainder of the rods in the group with the inoperable rod are aligned to within 1

112 steps of the inoperable-rod while maintaining the rod sequence and insertion limits of Specification 3.1.3.6. The

-THERMAL POWER level shall be restricted pursuant to 3 Specification 3.1.3.6 during subsequent operation, or

3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1-is satisfied.' POWER OPERATION may then continue provided that:

. a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for. the_ duration of operation  !

p under these conditions; b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 F is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

• See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

MILLSTONE - UNIT 3 3/4 1-20 Amendment No. JE f n 0007 b _ -_-_,_ ,. _-_-__ - -,. ,___ _ ,_., _ _ _ _ _

REACTIVITY CONTROL SYSTEMS LIMITlhG CONDITION FOR OPERATION ACTION (Continued c) Apowerdistributionmapisobtagnedfromthemovable incore detectors and F (Z) and F a within their limits wi9hin 72 ho$s;reandverified to be d) With four loops operating, the THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER, or e) With three loops operating, the THERMAL POWER level is reduced to less than or equal to 50% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the Neutron Flux High Trip Setpoint is reduced to less than or equal to 60% of RATED THERMAL POWER.

c. With more than one rod trippable but inoperable due to causes other than addressed by ACTION a. above, POWER OPERATION may continue provided that:

1. Within I hour, the remainder of the rods in the bank (s) with the inoperable rods are aligned to within 12 steps of the inoperable rods while maintaining the rod sequence and insertion limits of Specification 3.1.3.6. The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and

2. The inoperable rods are restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

d. With more than one rod misaligned from its group step counter demand height by more than 112 steps (indicated position), be in H0T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the rod position deviation monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

MILLSTONE - UNIT 3 3/4 1-21 Amendment No. EE 0007

TABLE 3.1 1 at[lDENT ANALYSES REQUIRING REEVALUATIQN IN THE EVENT OF AN IN0PERABLE FULL-LENGTH ROD Rod Cluster Control Assembly insertion Chart.cteristics Rod Cluster Ccntrol Assembly Hisalignment 4

Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in large Pipes Which Actuates the Emergency Core Cooling System Single Rod Cluster Control Assembly Withdrawal at full Power Major Reactor Coolant System Pipe Ruptures (Loss-of-Coolant Accident)

Major Secondary Coolant System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) l i

MILLSTONE - UNIT 3 3/4 1-22 0007

l ..

REACTIVITY CONTROL ?"13TEMS ,

c 1 l POSITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION

)

! 3.1.3.2 The Digital Rod Position Indication System and the Demand Position .

. Indication System shall be OPERABLE and capable of determining the control j; rod positions within il2 steps.

i

! APPLICABILITY: MODES I and 2.

ACTION:

a. With a maximum of one digital rod position indicator per bank inoperable:

I

1. Determine the position of the nonindicating rod (s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and ,

j immediately after any motion of the nonindicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or j 2. With four loops operating, reduce THERMAL POWER t' $han 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or

3. reduce THERMAL POWEI less than

Withthreeloopsoperatink,within8 32% of RATED THERMAL POWE hours.

4

b. With a maximum of one demand position indicator per bank inoperable:

i

1. Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod-of the bank are witbin a maximum I of 12 steps of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 1

2. With four loops operating, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or

3. _ With three loops operating, reduce THERMAL POWER to less than 32% of RATED THERMAL POWER within.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILLANCE RE0VIREMENTS 4.1.3.2 Each digital rod position indicator shall' be determined to be '

OPERABLE by verifying that the Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps-at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the' rod position deviation

. monitor is inoperable, then compare the Demand Position Indication System and the Digital Rod Position Indication System at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

MILLSTONE - UNIT 3 3/4 1-23 0007

_..__ _____. _ _.,...__ _-_--__ _ -__ __. ~ _ _ . . - _ . . _ _ . . . _ _ . _ . . _ . _ _ . _ .- n.._... . .

REACTIVITY CONTROL SYSTEMS 2 POSITION INDICATION SYSTEM - SHUTDOMH LIMITlHG CONDITION FOR OPERATION _

3.1.3.3 One digital rod position indicator (excluding demand position indication) shall be OPERABLE and ca)able of determining the control rod position within 112 steps for each s tutdown or control rod not fully inserted.

APPLICABILITY: MODES 3* **, 4* **, ant. 5* **.

ACTION:

With less than the above required position indicator (s) OPERABLE, immediately open the Reactor Trip System breakers.

SURVEILLANCE RE0VIREMENTS 4.1.3.3 Each of the above required digital rod aosition indicator (s) shall be determined to be OPERABLE by verifying that tie digital rod position indicators agree with the demand position indicators within 12 steps when exercised over the full range of rod travel at least once per 18 months.

• With the Reactor Trip System breakers in the closed position.

• • See Special Test Exceptions Specification 3.10.5.

-MILLSTONE - UNIT 3 3/4 1-24 0007-

REACTIVITY CONTROL SYSTEMS ROD DROP TlHE LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full-length (shutdown and control) rod drop time from the fully withdrawn position shall be less than cr equal to 2.7 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:

a. T,yg greater than or equal to 5510F, and

b. All reactor coolant pumps operating.

APPLICABillTY: MODES 1 and 2.

ACTION:

a. With the drop time of any full-length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.

b. With the rod drop times within limits but determined with three reactor coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to less than or equal to 65% of RATED THERMAL POWER with the reactor coolant stop valves in the nonoperating loop closed.

SURVE1LLANCE REQUIREMENTS 4.1.3.4 The rod drop time of full-length rods shall be demonstrated through measurement prior to reactor criticality:

a. For all rods following each removal of the reactor vessel head,

b. For specifically affected individual rods following any maintenance on or modification to the Control Rod Drive System which could affect the drop time of those specific rods, and

c. At least once per 18 months.

MILLSTONE - UNIT 3 3/4 1-25 0007

REACTIVITY CONTROL SYSTEMS SHUTDOWN ROD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be limited in physical insertion as specified in the core operating limits report (COLR).

APPLICABILITY: MODES 1* and 2* **.

ACl103:

With a maximum of one shutdown rod inserted beyond the insertion limits specified in the COLR except for surveillance testing pursuant to Specification 4.1.3.1.2, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either:

a. Restore the rod to within the limit specified in the COLR,.or

b. Declare the rod to be inoperable and apply Specification 3.1.3.1.

SURVEILLANCE RE0VIREMEllTS 4.1.3.5 Each shutdown rod shall be determined to be within the insertion limits specified in.the COLR:  ;

a. Within 15 minutes prior to withdrawal of any rods in Control Bank '

A, B, C, or D during an approach to reactor criticality, and

b. 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.

• See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

1 L **With K,f 7 greater. than or equal to 1.

l l

l I

MILLSTONE - UNIT 3 3/4 1-26 Amendment No. JE 0007

- - - . , , . , _ ~ . - . - , _ _ . - - - _ . - . - . - - - - - . . - . ~ . . . . - . - . - . . - - . - - , _ . . - . . . ~ . . . - -

o REACTIVITY CONTROL SYSTEMS CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as specified in the core operating limits report (COLR).

APPLICABILITY: MODES 1* and 2* **.

ACTION:

With the control banks inserted beyond the insertion limits specified in the COLR, except for surveillance testing pursuant to Specification 4.1.3.1.2:

a. Restore the control banks to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or

b. Reduce THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank posi-tion using the insertion limits specified in the COLR, or

c. Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SVRVEILLANCE RE0VIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the rod insertion limit monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

• • With Keff greater than or equal to 1.

1 MILLSTONE - VNIT 3 3/4 1-27 Amendment No. Ep l coor l

= .- - _ _ _ - - - . . - ._ .

!' l i

.}

TABLE 3.3-1 -

i 'U3 REACTOR TRIP SYSTEM INSTRUMENTATION -

1, . O uP,

• NININUM 2

E TOTAL NO. CHANNELS CHANNELS APPLICABLE 7 FUNCTIONAL UNIT OF CHANNELS- TO TRIP OPERABLE MODES ACTION l

E I. ' Manual Reactor Trip 2 1- 2 1, 2 1 j' ~~ 2 1 2 3*, 4*, 5* 11 ,

w i

4

2. Power Range, Neutron Flux  !

a. High Setpcint 4 2 3 1, 2 2

b. Low Setpoint '

4 2' 3 l#H, 2 '2

j. .

.j j' 3. Power Range, Neutron Flux 4 2 3 1, 2 2

High Positive Rate l' .

\

4. Power Range, Neutron Flux, 4 2 3 1, 2 2  !

. w High Negative Rate w 5. Intermadiate Range, Neutron Flux 2 1 2 18##, 2 3 l j 6. Source Range, Neutron Flux  !

a. Startup' 2 1 2 2M 4 .I 4 b. Shutdown 2 1 2 3*, 4*, 5* 11 i i

7. Overtemperature AT '

[

! a. Four Loop Operation 4 2 3 1, 2 6 -

l p b. Three Loop Operation 3 2 2 1, 2 6

! E 8. Overpower AT 'I i

5 a. Four Loop Operation 4 2 3 1, 2 6 [

5 b. Three Loop Operation 3 2 2 1, 2 6

== t j -

9. Pressurizer Pressure--Low .4 2 3 1** 6 (1) 'I

! -u j 10. Pressurizer Pressure--High 4 2 3 1, 2 6 (1)

11. Pressurizer Water Level--High 3 2 2 1** 6 y

-. . .. .~ - - - _ _ _ _ _ _ -

}; -

l p . .

o .r.  ;

" ;: - TABLE 3.3-1 (Continued)

- r-

'M 1

U REACTOR TRIP SYSTEM INSTRUNENTATION t

! M i .

MINIMUM i.

c TOTAL NO. CHANNELS CHANNELS APPLICABLE- .

5. FUNCTIONAL UNIT' 0F CHANNELS TO TRIP OPERABLE MODES ARTION I l

i 17. Reactor Trip System Interlocks (Continued)  !

1-t l' c. Power Range Neutron 1

Flux, P-8 4 2 3 1 8 )

d. Power Range Neutron 4 2 3 1 8 Flux, P-9

e. Power Range Neutron-i Flux, P-10 4 2 3 1,2 8 i, a-  ;

I i

! w 18. Reactor Trip Breakers 2 1 2 1, 2 10, 13 i j 1 2 1 2 3*, 4*, 5* 11 l' u  !

! 1. 19. Automatic Trip and Interlock 2 1 2 1, 2 10 Logic 2 1 2 3*, 4*, 5* 11

20. Three loop Operation 8' 2 8 1, 2 I Bypass Circuitry (1 switch per (From differ-ent loop i loop in each 4 l x train) switches in  !

M bypass) i- E i

2 21. Shutdown Margin Monitor 2 0 2 39, 4, 5 5 5

F 4

=

1

1.

• I t

i:

I, ' -. , , . . . , . - - ,. .,

. . . l 4

! )

l TABLE 3.3 1 (Continued)

1 TABLE NOTATIONS l

• When the Reactor Trip System breakers are in the closed position ar,l Control Rod Drive System is capable of rod withdrawal.

• • Above the P 7 (At Power) Setpoint.

• • • Above the P 9 (Reactor Trip / Turbine Trip Interlock) Setpoint.

1. 1. Below the P 6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

0 The Shutdown Margin monitor may be blocked during reactor startup in accordance with approved procedure.

(1) The applicable MODES and ACTION statements for these channels noted in Table 3.3 3 are more restrictive end, therefore, applicable.

6CT10N STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the hinimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 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 />.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Cliannels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1, and i

i c. Either, THERMAL POWER is restricted to less than or caual l to 75% of RATED THERMAL POWER for four loop operation or 50% of RATED THERMAL POWER for three loop operation and the Power Range Neutron Flux Trip Setpoint is reduced to l

less than or equal to 85% of RATED THERMAL POWER for four loop operation or 60% of RATE' THERMAL POWER for three loop operation within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.

MILLSTONE - UNIT 3 3/4 3-5 Amendment No. E7 0034

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continue.d1 ACTION 3 With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P 6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P 6 Setpoint, and

b. Above the P 6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.

ACTION 5 - (a) With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or suspend all operations involving positive reactivity changes and verify valves as per Specification 4.4.1.4.2.3 are closed and secured in position within the next four hours. Entry into an OPERATIONAL MODE pursuant to S>ecification 3.0.4 is not permitted with no source range c1annel OPERABLE.

(b) With no channels OPERABLE, suspend all operations involving positive reactivity changes and verify valves per Specification 4.4.1.4.2.3 are closed and secured in position within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1.2 or 3.1.1.2 as applicable within the next hour.

Continue to verify valves closed and secured every 14 days and verify SHUTDOWN MARGIN every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTVP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - (Not used)

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3, MILLSTONE - UNIT 3 3/4 3-6 Amendment No. E7 0034

i i

p ,

' 25 TABLE 4.3-1 (Continued) .

, ' ? i

, $ REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS  :

! E TRIP l ANALOG ACTUATING MODES FOR E- CHANNEL DEVICE idHICH 4

Q CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE ,

i w FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST 15 REQUIRED

18. Reactor' Trip Breaker' N.A. N.A. N.A. M(7,11) N.A. 1, 2, 3*, 4*, 5*

19. Automatic Trip and M.A. N.A. M.A. N.A. M(7) 1, 2, 3*, 4*, 5*

f Interlock logic j t

20. Three Loop Operation N.A. N.A. N.A.

R N.A. 1, 2

Bypass Circuitry

R

21. Reactor. Trip Bypass N.A. N.A. M.A. M(15) N.A. 1, 2, 3*, 4*, 5*

Breakers R(16)

I Y

22. Shutdown Margin Monitor N.A. N.A. . Q(19) M.A. N.A. 3,4,5 i f I i i

1 f' l 1

i I

l )

i

1 1

1 TABLE 4.3-1 (Continued)

TABLE NOTATIONS

• When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.

• • Below P 6 (Intermediate Range Neutron Flux Interlock) Setpoint.

• • • Below P 10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) If not performed in previous 31 days.  ;

(2) . Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1.

-(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CAllBRATION.

(5) Detector plateau curves shall be obtained, and evaluated and compared to manufacturer's data. For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

-(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER.-- The-provisions of Specification 4.0.4 are not applicable for entry' into MODE 2 or 1.

(7) Each train shall be tested at least every 62 days on. a . STAGGERED TEST BASIS.

(8) (Not-used)

(9) Quarterly surveillance in MODES 3*, 4*, and 5*- shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator-window.

l '

i MILLSTONE - UNIT 3 3/4 3-13 0035

_~ _ . . _ . ~ , . . . _ _ _ . , _ . _ . _ _ _ . _ . _ . _ . - _ , _ _ . _ _ _ . _ _ _ _ _

TABLE 4.3 1 (Continued)

TABLE NOTATIONS (Continued)

(10) Setpoint verification is not applicable.

(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(12) (not used)

(13) Reactor Coolant Pump Shaft Speed Sensor may be excluded from CHANNEL i

CALIBRATION.

(14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Tri) Function. The test shall also verify the OPERABILITY of the Bypass Brea(er trip circuit (s).

(15) local manual shunt trip prior to placing breaker in service.

(16) Automatic undervoltage trip.

(17) Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.

(18) The surveillance frequency and/or MODES specified for these channels in Table 4.3 2 are more restrictive and, therefore, applicable.

(19) Quarterly surveillance shall include verification that the Shutdown Margin Monitor is set per the CORE OPERATING LIMITS REPORT (COLR).

l l

l MILLSTONE - UNIT 3 3/4 3 14 Amendment No. J/

0035 l

.y--- e. -, g - ' -y s .m-.y y ,-m - -. . y __y w

REACTOR COOLANT SYSTEM COLD SHVTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE

• and at least one RHR loop shall be in operation.** The chemical and volume control system (CVCS) shall be aligned to preclude Reactor Coolant System boron concentration reduction or the SHUTDOWN MARGIN of Specification 3.1.1.2 shall be met.

APPLICABILITY: MODE 5 wita less than two reactor coolant loops filled.

ACTION:

a. With less than the above required RHR loops OPERABLE, immediately initiate corrective action to retuin the required RHR loops to OPERABLE status as soon as possible,

b. With no RHR loop in operation, suspend all operations involving a reduction in boron concentration of the P. actor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.

c. With the CVCS dilution flow paths not closed and secured in position, immediately close and secure the paths or satisfy the SHUTDOWN MARGIN of Specification 3.1.1.2.

SVRVEIL LANCLRE0VIREMENTS 4.4.1.4.2.1 The required RHR loops shall be demonstrated OPERABLE pursuant to Specification 4.0.5.

4.4.1.4.2.2 At least one RHR loop shall be determined to be in operation and circulating reae. tor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.4.2.3 At least per 31 bys the following valves shall be verified closed and locked. The valves may be opened on an intermittent basis under administrative control.

~

• 0ne RIDI Ioop may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing providea the other RHR loop is OPERABLE and in operation.

• • The RHR pump may be deenergized for up to I hour prosided: (1) no opera- l tions are permitted that would cause dilution of the Reactor Coolant System 1 boron concentration, and (2) core outlet temperature is maintained at icast i 100F below saturation temperature.

MILLSTONE UNIT 3 3/4 4 6 0036

4 1

SURVEllLANCE RE0VIREMENTS (Con't)

Valve Number Valve Function Valve Position l

1. V104(Z-) Primary Grade Water Closed l to CVCS

2. V119 - BTRS Inlet Closed

3. V147 -

BTRS Outlet Closed

4. V797(Z-) Failed fuel Monitoring Closed Flushing

5. V100(Z-)- Resin Sluice, CVCS Cation Closed Bed Demineralizer

6. V571(Z-) Resin Slutce, CVCS Cation Closed Bed Demineralizer

7. Ylll(Z-) Resin Sluice, CVCS Cation Closed Bed Demineralizer

8. Vil2(Z-) Resin Sluice, CVCS Cation Closed Bed Domineralizer

9. V98(Z-)/V99(Z-) Resin Sluice, CVCS Mixed Closed Bed Domineralizer

10. V569(Z-)/VS70(Z-) Resin Sluice, CVCS Mixed Closed Bed Demineralizer

11. V107(Z-)/V109(Z-) Resin Slutce, CVCS Mixed Closed Bed Domineralizer

12. V108(Z-)/V110(Z-) Resin Sluice, CVCS Mixed Closed Bed Demineralizer MILLSTONE - UNIT 3 3/4 4-6a 0036

REACTOR COOLANT SYSTEM ISOLATED LOOP 3TARTUP LlHITING CONDITION FOR OPERATION 3.4.1.6 A reactor coolant loop shall remain isolated with power removed from the associated RCS loop stop valve operators until:

a. The temperature at the cold leg of the isolated loop is within 20'F of the highest cold leg temperature of the operating loops,

b. The boron concentration of the isolated loop is greater than or equal to the boron concentration of the operating loops, or greater than 2600 ppm whichever is less, l

c. The isolated portion of the loop has been drained and is refilled, and

d. The reactor is subcritical by at least the value required by Specifications 3.1.1.1.2 or 3.1.1.2 for Mode 5 or Specification 3.9.1.1 for Mode 6.

APPLICABillTY: MODES 5 and 6.

AC110N:

a. With the requirements of the aMve specification not satisfied, do not open the isolated loop stop valves.

SURVEILLANCE REQUIREMENTS 4.4.1.6.1 The isolated loop cold leg temperature shall be determined to be within 20*F of the highest cold leg temperatur9 of the operating loops within 30 minutes prior to opening the col' leg stop /alve.

4.4.1.6.2 The reactor shall be determined to be suberitical by at least the value required by Specifications 3.1.1.1.2 or 3.1.1.2 for Mode 5 or Specification 3.9.1.1 for Mode 6 within 30 minutes prior to opening the cold leg stop valve.

4.4.1.6.3 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to opening the loop stop valves, the isolated loop shall be determined to:

a. Be drained and refilled, and

b. Have a boron cencentration greater than or equal to the boron concentration of the operating loops, or greater than 2600 ppm I whichever is less. 3 MILLSTONE - UNIT 3 3/4 4-8 Amendment No. U , E7 0010

. . . . i 3/4.9 REFUEllNG OPERATIONS 3/4 ,9'.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION i

, 3.9.1.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ,

ensure that the more restrictive of the following reactivity conditions is '

met; either:

a. A K,77 of 0.95 or less, or

b. A boron concentration of greater than or equal to 2600 ppm; Additionally, the-CVCS valves of Specification 4.4.1.4.2.3 shall be closed and secured in position.

APPLICABILITY: MODE 6.*

ACTION:

a. With the requirements of the above specification not satisfied, immediutely suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 33 gpm of a solution containing greater than or equal to 6300 ppm boron or its equivalent until K is reduced to less than or equal to 0.95 or the boron concentratN is restored to greater than or equal to 2600 ppm, whichever is the more restrictive. 1

b. With.any of the CVCS valves of Specification 4.4.1.4.2.3 not closed ** and secured in position, immediately close and secure the valves.

SURVEILLANCE RE0VIREMENTS 4.9.1.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a. Removing or unbolting the reactor vessel head, and

b. Withdrawal of any full-length control rod in excess of 3 feet from

.its fully inserted position within the reactor vessel.

4.9.1.1.2 The boron . concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

4.9.1.1.3 'The CVCS valves of Specification 4.4.1.4.2.3 shall be~ verified closed and locked at least once per 31 days.

9 he reactor shall be maintained in N0DE 6 whenever fuel is in the raactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

• • Except those opened under administrative control.

MILLSTONE - UNIT 3 3/4 9-1 Amendment No. Ep 0025 i

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3/4.1 REACTIVITY CONTROL SYSTEMS BASES UJL.l .1 B0 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHV'DOWN MARGIN A sufficient SHVTDOWN MARGIN ensures that: (1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the -hutdown condition.

SHVTDOWN MARGIN requirements vary throughout cae life as a fLnction of fuel depletion, RCS boron concentration, and RCS T In MODES 1 and 2, the most restrictive condition occurs at E0L with fV9 at no load operating temperature, and is associated with a postulated st8niline break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.3% AK/K is required to control the reactivity transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this it iting condition and is consistent with FSAR safety analysis assumptions, in MODES 3, 4 and 5, the most restrictive condition occurs at BOL, associated with a boron dilution accident. In the analysis of this accident, a minimum SHVTDOWN MARGIN as defined in Specification 3/4.1.1.2 is required to allow the operator 15 minutes from the initiation of the Shutdown Margin Monitor alarm to total loss of SHUTDOWN MARGIN. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting requirement and is consistent with the accident analysis assumptions. The required SHUTDOWN MARGIN is plotted as a function of RCS critical boron concentration.

U4.1.1.3 MODERATOR TEMPERATURE COEfflCIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.

l The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC, value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions.

MILLSTONE UNIT 3 8 3/4 1-1 Amendment No. 29 0026

9 REACTIVITY CONTROL SYSTEMS BASES BORAT10N SJSTEMS (Continued)

MARGIN from expected operating conditions of equivalent to that required by figure 3.1-5 after xenon decay and cooldown to 200'F. The maximum expected boration capability requirament occurs at E0L from full power equilibrium xenon conditions 6nd requires a usable volume of 21,020 gallons of 6300 ppm borated water fron the boric acid storage tanks or 1,166,000 gallons of 2700 ppm borated water from the refueling water storage tank (RWST). A minimum RWST volume of 1,166,000 gallons is specified to be consistent with ECCS requirement.

With the RCS te,nperature t:elow 200'F, one Earon Injection System is acceptable without s6ngle failure consideration on the basis of the r'.able reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron Injection System becomes inoperable.

The limitation for a maximum of one centrifugal charging pump to be OPER-ABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 350'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

The boron capability required below 200'F is sufficient to provide a SHUTDOWN MARGIN of 1.3% Ak/k after xenon decay and couldown from 200'F to 1400F. This condition requires either a usable volume of 4100 gallons of 6300 ppm borated water from the boric acid storage tanks or 250,000 gallons of 2700 ppm borated water from the RWST. The unusable volume in each boric acid storage tank is 1300 gallons.

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.0 and 7.5 for the solution recirculated within containment after a LOCA. This pH band mininitzes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and coniponents.

The minimum RWST solution temperature for MODES 5 and 6 is based on analysis assumptions in addition to freeze protection considerations. The minimum / maximum RWST solution temperatures for MODES 1, 2, 3 and 4 are based on analysis assumptions.

The OPERABILITY of one Boron Injection System during REFUELING ensures that this system is available for re ctivity control while in MODE 6.

MILLSTONE - UNIT 3 8 3/4 1 3 Amendment No. U 00t1

, 3/4.4 REACTOR COOLANT SYSTd DASES 3/4.4.1 REAU0k COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate in MODES 1 and 2 with three or four reactor coolant loops in operation and maintain DNBR greater than the design limit during all normal operations and anticipated transients. With less than the required reactor coolant loops in operation this specification requires that the plant be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

In MODE 3, three reactor coolant loops, and in Mode 4, two reactor coolant loops provide sufficient heat removal capability for removing core decay heat even in the event of a bank withdrawal accident; however, a single reactor coolant loop provides sufficient heat removal capacity if a bank withdrawal accident can be prevented, i.e., by opening the Reactor Trip System breakers.

In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or RHR loop provides rufficient heat removal capability for removing dacay heat; but single failure considerations require that at least two loops (either RHR or RCS) be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single RHR loop J provide sufficient heat removal capability for removir- .iecay heat; but single failure considerations, and the unavailability of the :, team generators ae a heat removing component, require that at least two RHR loops be OPERABLE.

The locking closed of the required valves in Mode 5 (with the loops not filled) will preclude the poss4bility of uncontrolled boron dilution of the Reactor Coolant System by preventing flow to the RCS of unborated water.

The operation of one reactor coolant pump (RCP) or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.

The restrictions on starting an RCP with one or more RCS cold legs less than or equal to 350'F are provided to prevent RCS pressure transients, caused by energy additions from the Secondary Coolant System, which could exceed the limits d Appendix G to 10 CFR Part 50. The RCS will be protected against overprs m re transients and will not exceed the limits of Appendix G by eithert (1) restricting the water volume in the pressurizer and thereby providing a volume for the reactor coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 50'F above each of the RCS cold leg temperature' MILLSTONE - UNIT 3 B 3/4 4-1 Amendment No. 7 0029 i

L .. . . . .

O ,4 REACTOR COOLANT SYSTEM BASES (Continued)

The requirement to maintain the isolated loop stop valves shut with power

- removed ensures that no reactivity addition tu the core could occur due to the startup of an isolated loop. Verification of the boron concentration in an idle loop prior to opening the stop valves provides a reassurance of the adequacy of the boron concentration in the isolated loop. The 2600 ppm is sufficient to bound shutdown margin requirements and provide for boron concentration measurement uncertainty between the loop and the RWST. Draining and refilling the isolated loop within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to opening its stop

] valves ensures adequate mixing of the coolant in this loop and prevents any reactivity effects due to boron concentration stratifications.

MILLSTONE - UNIT 3 B 3/4 4-la Amendment No. 7 0029

3/4.9 REFUEllNG OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. The value of 0.95 or less for K a 1% Ak/k conservative allowance for uncertainties.

Similaffy, includes the boron concentration value of 2600 ppm or greater includes a conservative uncertainty allowance of 50 ppm boron. The 2600 ppm provides for boron concentration measurement uncertainty between the spent fuel pool and the RWST. The locking closed of the required valves during refueling operations precludes the possibility of uncontrolled boron dilution of the filled portion of the RCS. This action prevents flow to the RCS of unborated water by closing flow paths from sources of unborated water.

3/4.9.1.2 Boron Concentration in Spent Fuel Pool The limitations of this specification ensure that in the event of a fuel assembly handling accident involving either a misplaced or dropped fuel assembly, the K eff of the spent fuel storage racks will remain less than or equal to .95.

3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the safety analyses.

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY ensure that a release of radioactive material within cor.tainment will be restricted from leakage to the environment. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture ba.Ted upon the lack of containment pressurization potential while in the REFUELIN1 MODE.

3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

MILLSTONE - UNIT 3 8 3/4 9-1 Amendment No. J2 0030

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continuedl

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% 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 />; and

3. Identify and correct the cause of the out-of-limit condition prior to incraasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL 00WER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until verified at 95% or greater RATED THERMAL POWER.

SURVEILLANCE RE0VIREMrNTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE, and

b. Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady-state operation when the alarm is inoperable.

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the

-limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors to . confirm that- the normalized symmetric power distribution, obtained from two sets of- four symmetric ~ thimble locations or full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at-least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i MILLSTONE - UNIT 3 3/4 2-26 Amendment No. A7 0011

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