ML042600064

Technical Specifications, Limiting Safety Systems Settings and Instrumentation

ML042600064
Person / Time
Site:	Millstone
Issue date:	09/14/2004
From:	NRC/NRR/DLPM
To:
References
TAC MB6166
Download: ML042600064 (11)

Text

DEFINITIONS E - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the sample) of the sum of the average beta and gamma energies per disintegration (MeV/d) for the radionuclides in the sample.

1.12 DELETED ENGINEERED SAFETY FEATURES RESPONSE TIME 1.13 The ENGINEERED SAFETY FEATURES (ESF) RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and the methodology for verification have been previously reviewed and approved by the NRC.

1.14 DELETED FREOUENCY NOTATION 1.15 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

IDENTIFIED LEAKAGE 1.16 IDENTIFIED LEAKAGE shall be:

a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of Leakage Detection Systems or not to be PRESSURE BOUNDARY LEAKAGE, or

c. Reactor Coolant System leakage through a steam generator to the Secondary Coolant System.

MASTER RELAY TEST 1.17 A MASTER RELAY TEST shall be the energization of each master relay and verification of OPERABILITY of each relay. The MASTER RELAY TEST shall include continuity check of each associated slave relay.

MILLSTONE - UNIT 3 1-3 Amendment No. 84, A, 41-26, 48-,

24I, 220

TABLE 2.2-i (Continued)

H REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 0

z NOMINAL n FUNCTIONAL UNIT TRIP SETPOINT  ! ALLOWABLE VALUE i 16. Turbine Trip

a. Low Fluid Oil Pressure 500 psig > 450 psig

b. Turbine Stop Valve 1% open > 1% open Closure

17. Safety Injection Input N.A. N.A.

W from ESF

18. Reactor Trip System Interlocks

a. Intermediate Range I x 10-10 amp >9.0x 10 1 amp Neutron Flux, P-6

b. Low Power Reactor Trips Block, P-7

1) Power Range Neutron Flux, 11% of RTP** < 11.6% of RTP**

P- I0 input (Note 5)

EICD 2) Turbine Impulse Chamber Pressure, 10% RTP** Turbine 5 10.6% RTP** Turbine P-13 input Impulse Pressure Impulse Pressure Equivalent Equivalent z c. Power Range Neutron 37.5% of RTP** 5 38.1% of RTP**

o Flux, P-8

• • RTP = RATED THERMAL POWER r%3 0

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION 0

zMT MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

12. Reactor Coolant Flow-Low

a. Single Loop (Above P-8) 3/loop 2/loop 2/loop 1 6

b. Two Loops (Above P-7 and 3/loop 2/loop in two 2/loop 1 6 below P-8) operating loops

13. Steam Generator Water 4/stm. gen. 2/stm. gen. 3/stm. gen. 1,2 6 (1)

Level--Low-Low W 14. Low Shaft Speed--Reactor 4-1/pump 2 3 I** 6

t. Coolant Pumps I S. Turbine Trip

a. Low Fluid Oil Pressure 3 2 2 1*** 12

b. Turbine Stop Valve Closure 4 4 4 1*** 6

16. Deleted

17. Reactor Trip System Interlocks

a. Intermediate Range 2 1 2 2## 8 Neutron Flux, P-6

b. Low Power Reactor Trips Block, P-7 z Power Range Neutron Flux, 4 2 3 1 8 I P-10 Input or Turbine Impulse Chamber 2 1 2 1 8 It3 Pressure, P-13 Input I raw C)

TABLE 4.3-I H_ REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS txl TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH z CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED

1. Manual Reactor Trip N.A. N.A. N.A. R(14) N.A. 1, 2,3*, 4*, 5*

2. Power Range, Neutron Flux

a. High Sctpoint S D(2, 4), Q N.A. N.A. 1,2

~JJ M(3, 4),

-S W Q(4, 6),

0 R(4, 5)

b. Low Setpoint S R(4, 5) S/U(1) N.A. N.A. 1***, 2

3. Power Range, Neutron Flux, N.A. R(4, 5) Q N.A. N.A. 1,2 High Positive Rate

4. Deleted B 5. Intermediate Range S R(4, 5) S/U(1) N.A. N.A. 1***, 2 0- 6. Source Rangc, Neutron Flux S R(4, 5) SIU(I), N.A. N.A. 2**, 3*, 4*, 5*

0El I

Q(9)

Z 7. Overtemperaturc AT S R Q N.A. N.A. 1,2

8. Overpower AT S R Q N.A. N.A. 1,2 8 9. Pressurizer Pressure--Low S R Q(18) N.A. N.A. 1*****

I y 10. Pressurizer Pressure--High S R Q(18) N.A. N.A. 1,2

11. Pressurizer Water Level--High S R Q N.A. N.A. I

12. Reactor Coolant Flow--Low S R Q N.A. N.A. I rJ N

C)

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.

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

• • • • • Above the P-7 (At Power) 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 CALIBRATION.

(5) Detector plateau curves shall be obtained, and evaluated and compared to manufacturer's data. For the Source Range, 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-1 0 are in their required state for existing plant conditions by observation of the permissive annunciator window.

MILLSTONE - UNIT 3 3/4 3-13 Amendment No. 6, 40, 49, 220

TABLE 3.3-3 (Continued) til ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (n MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

1. 6. Auxiliary Feedwater (Continued)

f. Containment Depres- See Item 2. above for all CDA functions and requirements.

surization Actuation (CDA) Start Motor-Driven Pumps

~It to 7. Control Building Isolation

a. Manual Actuation 2 I 2 19

b. Manual Safety 2 I 2 1,2, 3,4 19 Injection Actuation

c. Automatic Actuation 2 I 2 1,2,3,4 14 Logic and Actuation Relays

d. Containment Pressure-- 3 2 2. 1,2,3 16 High-1

e. Control Building Inlet 2/intakc I 2/intake

• 18 0

3 Ventilation Radiation 3

0 8. Loss of Power

a. 4 kV Bus Under- 4/bus 2/bus 3/bus 1,2,3,4 27 I voltagc-Loss of Voltage to b. 4 kV Bus Undervoltage- 4/bus 2/bus 3/bus 1,2,3,4 27 I Grid Degraded Voltage rat r~a C)

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 27 - a. With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

1. The inoperable channel is placed in the tripped condition within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />, and

2. the Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> for surveillance testing of other channels per Specification 4.3.2.1.

b. With the number of OPERABLE channels one less than the Minimum Channels required OPERABLE:

1. Place one channel in bypass and other channel in trip condition within one hour and restore one channel to OPERABLE status in 48 hours2 days <br />0.286 weeks <br />0.0658 months <br />, OR

2. Be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.

MILLSTONE - UNIT 3 3/4 3-25a Amendment No. 220

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

(2) Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch Water Gauge at less than or equal to a pressurization flow of 230 cfm relative to adjacent areas and outside atmosphere during the filtered pressurization mode of operation; and I (3) Verifying that the heaters dissipate 9.4 +/-1 kW when tested in accordance with ANSI N510-1980.

f. After each complete or partial replacement of a HEPA filter bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a DOP test aerosol while operating the system at a flow rate of 1120 cfhn +/-20%; and

g. After each complete or partial replacement of a charcoal adsorber bank, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 for a halogenated hydrocarbon refrigerant test gas while operating the system at a flow rate of 1120 cfm +/-20%.

• ANSI N510-1980 shall be used in place of ANSI N510-1975 referenced in Regulatory Guide 1.52, Revision 2, March 1978.

MILLSTONE - UNIT 3 3/4 7-17 Amendment No., 23, 4-+, 203, 220

ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION OPERATING LIMITING CONDITION FOR OPERATION 3.8.3.1 The following electrical busses shall be OPERABLE in the specified manner: I

a. Train A A.C. Emergency Busses consisting of:

1) 4160-Volt Emergency Bus #34C, and

2) 480-Volt Emergency Bus #32R, 32S, 32T, and 32Y.

b. Train B A.C. Emergency Busses consisting of:

1) 4160-Volt Emergency Bus #34D, and

2) 480-Volt Emergency Bus #32U, 32V, 32W, and 32X.

c. 120-Volt A.C. Vital Bus #VIAC-1 energized from its associated inverter connected to D.C. Bus #301A-1*,

d. 120-Volt A.C. Vital Bus #VIAC-2 energized from its associated inverter connected to D.C. Bus #301B-I*,

e. 120-Volt A.C. Vital Bus #VIAC-3 energized from its associated inverter connected to D.C. Bus #301A-2*,

f. 120-Volt A.C. Vital Bus #VIAC-4 energized from its associated inverter connected to D.C. Bus #301B-2*,

g. 125-Volt D.C. Bus #301A-1 energized from Battery Bank #301A-1,

h. 125-Volt D.C. Bus #301A-2 energized from Battery Bank #301A-2,

i. 125-Volt D.C. Bus #301B-I energized from Battery Bank #301B-1, and

j. 125-Volt D.C. Bus #301B-2 energized from Battery Bank #301B-2.

• Two inverters may be disconnected from their D.C. bus for up to 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> as necessary, for the purpose of performing an equalizing charge on their associated battery bank provided: (1) their vital busses are energized, and (2) the vital busses associated with the other battery bank are energized from their associated inverters and connected to their associated D.C. bus.

MILLSTONE - UNIT 3 3/4 8-16 Amendment No. 64, 220

ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With one of the required trains of A.C. emergency busses not OPERABLE, restore the inoperable train to OPERABLE status within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.

b. With one A.C. vital bus either not energized from its associated inverter, or with the inverter not connected to its associated D.C. bus: (1) reenergize the A.C. vital bus within 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />; and (2) reenergize the A.C.

vital bus from its associated inverter connected to its associated D.C. bus within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.

c. With one D.C. bus not energized from its associated battery bank, reenergize the D.C. bus from its associated battery bank within 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> or be in at least HOT STANDBY within the next 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> and in COLD SHUTDOWN within the following 30 hours1.25 days <br />0.179 weeks <br />0.0411 months <br />.

SURVEILLANCE REQUIREMENTS 4.8.3.1 The specified busses shall be determined OPERABLE in the specified manner at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses.

MILLSTONE - UNIT 3 3/4 8-17 Amendment No.-64, 220

LIMITING SAFETY SYSTEM SETTINGS BASES Reactor-Trip System Interlocks (Continued)

P-8 On increasing power, P-8 automatically enables Reactor trips on low flow in one or more reactor coolant loops. On decreasing power, the P-8 automatically blocks the above listed trips.

P-9 On increasing power, P-9 automatically enables Reactor trip on Turbine trip. On decreasing power, P-9 automatically blocks Reactor trip on Turbine trip.

P-10 On increasing power, P-l0 provides input to P-7 to ensure that Reactor Trips on low flow in more than one reactor coolant loop, reactor coolant pump low shaft speed, pressurizer low pressure and pressurizer high level are active *whenpower reaches 11%. It also allows the manual block of the Intermediate Range trip and the Low Setpoint Power Range trip; and automatically blocks the Source Range trip and deenergizes the Source Range high voltage power.

On decreasing power, P-10 resets to automatically reactivate the Intermediate Range trip and the Low Setpoint Power Range trip before power drops below 9%. It also provides input to reset P-7.

P-13 On increasing power, P-13 provides input to P-7 to ensure that Reactor trips on low flow in more than one reactor coolant loop, reactor coolant pump low shaft speed, pressurizer low pressure and pressurizer high level are active when power reaches 10%.

On decreasing power, P-13 resets and provides input, along with P-1I, to automatically block the Low Power Reactor Trip (P-7) before power drops below 10%.

MILLSTONE - UNIT 3 B 2-8 Amendment No. 8-, 2417, 220