Text

Technical Specifications, Limiting Safety Systems Settings and Instrumentation
	ML042600064
Person / Time
Site:	Millstone ; (NPF-049)
Issue date:	09/14/2004
From:	; NRC/NRR/DLPM
To:	;
References
	TAC MB6166
	Download: ML042600064 (11)
	v • d • e

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

H 0z TABLE 2.2-i (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS NOMINAL n FUNCTIONAL UNIT i

16.

Turbine Trip

a.

Low Fluid Oil Pressure

b.

Turbine Stop Valve Closure

17.

Safety Injection Input W

from ESF

18.

Reactor Trip System Interlocks

a.

Intermediate Range Neutron Flux, P-6

b.

Low Power Reactor Trips Block, P-7

1) Power Range Neutron Flux, P-I0 input (Note 5)

EI

2) Turbine Impulse Chamber Pressure, CD P-13 input z

c.

Power Range Neutron o

Flux, P-8 TRIP SETPOINT

!ALLOWABLE VALUE 500 psig 1% open

> 450 psig

> 1% open N.A.

N.A.

I x 10-10 amp 11% of RTP**

10% RTP** Turbine Impulse Pressure Equivalent 37.5% of RTP**

>9.0x 10 1 amp

< 11.6% of RTP**

5 10.6% RTP** Turbine Impulse Pressure Equivalent 5 38.1% of RTP**

r%3 0

- RTP = RATED THERMAL POWER

0z MT TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

12.

Reactor Coolant Flow-Low

a.

Single Loop (Above P-8)

b.

Two Loops (Above P-7 and below P-8)

13.

Steam Generator Water Level--Low-Low W

14.

Low Shaft Speed--Reactor

t.

Coolant Pumps I S.

Turbine Trip

a.

Low Fluid Oil Pressure

b.

Turbine Stop Valve Closure

16.

Deleted

17.

Reactor Trip System Interlocks

a.

Intermediate Range Neutron Flux, P-6

b.

Low Power Reactor Trips Block, P-7 z

Power Range Neutron Flux, P-10 Input or TOTAL NO.

OF CHANNELS 3/loop 3/loop 4/stm. gen.

4-1/pump 3

4 2

4 CHANNELS TO TRIP 2/loop 2/loop in two operating loops 2/stm. gen.

2 2

4 1

2 1

MINIMUM CHANNELS OPERABLE 2/loop 2/loop 3/stm. gen.

3 2

4 2

3 2

APPLICABLE MODES 1

1 1,2 I**

1***

2##

1 1

ACTION 6

6 6 (1) 6 12 6

8 8

I It3 raw C)

Turbine Impulse Chamber Pressure, P-13 Input 2

8 I

H_

z txl TABLE 4.3-I REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL CHECK CALIBRATION ANALOG CHANNEL OPERATIONAL TEST N.A.

TRIP ACTUATING DEVICE OPERATIONAL TEST R(14)

W

~JJ

-S 0

FUNCTIONAL UNIT

1. Manual Reactor Trip

2. Power Range, Neutron Flux

a. High Sctpoint

b. Low Setpoint

3. Power Range, Neutron Flux, High Positive Rate

4. Deleted ACTUATION LOGIC TEST N.A.

N.A.

S D(2, 4),

M(3, 4),

Q(4, 6),

R(4, 5)

Q S/U(1)

Q N.A.

N.A.

1,2 1 ***, 2 1,2 MODES FOR WHICH SURVEILLANCE IS REQUIRED 1, 2,3*, 4*, 5*

S N.A.

B 5. Intermediate Range 0- 6. Source Rangc, Neutron Flux El 0

Z 7. Overtemperaturc AT

8. Overpower AT 8 9. Pressurizer Pressure--Low y

10. Pressurizer Pressure--High S

S S

S R(4, 5)

R(4, 5)

R R

S/U(1)

SIU(I),

Q(9)

Q Q

Q(18)

Q Q

N.A.

1***, 2 2**, 3*, 4*, 5*

1,2 1,2 1*****

1,2 I

S R

I S

rJ N

C)

11. Pressurizer Water Level--High S

12. Reactor Coolant Flow--Low S

R R

R I

I

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

til (n

TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TOTAL NO.

CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE MODES FUNCTIONAL UNIT ACTION

6.

Auxiliary Feedwater (Continued)

~It to

f. Containment Depres-surization Actuation (CDA) Start Motor-Driven Pumps

7.

Control Building Isolation

a. Manual Actuation

b. Manual Safety Injection Actuation

c. Automatic Actuation Logic and Actuation Relays

d. Containment Pressure--

High-1

e. Control Building Inlet Ventilation Radiation See Item 2. above for all CDA functions and requirements.

2 2

I I

2 2

2 I

2 2.

2/intake 1,2, 3,4 1,2,3,4 1,2,3 19 14 16 18 19 3

2 03 0

3 to rat r~a C) 2/intakc I

8.

Loss of Power

a. 4 kV Bus Under-voltagc-Loss of Voltage

b. 4 kV Bus Undervoltage-Grid Degraded Voltage 4/bus 2/bus 3/bus 3/bus 1,2,3,4 1,2,3,4 27 I

4/bus 2/bus 27 I

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

2. the Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , OR

2. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 (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.

I 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:

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 I

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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; and (2) reenergize the A.C.

vital bus from its associated inverter connected to its associated D.C. bus within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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 *when power 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

v t e Letter Sequence Other
TAC:MB6166, (Approved, Closed)
Initiation Acceptance... Administration Questions 4 December 2002 5 August 2003 Answers 5 November 2003 Results Approval Other: ML042600064
MONTHYEAR2003-08-05 [Table View]

Person / Time
ML042600064
Site:	Millstone (NPF-049)
Issue date:	09/14/2004
From:	NRC/NRR/DLPM
To:
References
TAC MB6166
Download: ML042600064 (11)
v • d • e

ML042600064

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