Text

Developmental Revision B - Technical Specifications 3.3 - Instrumentation
	ML100550451
Person / Time
Site:	Watts Bar
Issue date:	02/02/2010
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
References
	Download: ML100550451 (66)
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RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-1 (developmental)

A 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1-1.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one or more required channels inoperable.

A.1 Enter the Condition referenced in Table 3.3.1-1 for the channel(s).

Immediately B. One Manual Reactor Trip channel inoperable.

B.1 Restore channel to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR B.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2 Open reactor trip breakers (RTBs).

55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-2 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One channel or train inoperable.

C.1 Restore channel or train to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR C.2 Open RTBs.

49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months D. One Power Range Neutron Flux-High channel inoperable.

NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing and setpoint adjustment of other channels.

D.1.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND D.1.2 Reduce THERMAL POWER to 75% RTP.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months OR D.2.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND

NOTE-------------------

Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable.

D.2.2 Perform SR 3.2.4.2.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR D.3 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-3 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One channel inoperable.

NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

E.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months F. THERMAL POWER > P-6 and < P-10, one Intermediate Range Neutron Flux channel inoperable.

F.1 Reduce THERMAL POWER to < P-6.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OR F.2 Increase THERMAL POWER to > P-10.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months G. THERMAL POWER > P-6 and < P-10, two Intermediate Range Neutron Flux channels inoperable.

G.1 Suspend operations involving positive reactivity additions.

Immediately AND G.2 Reduce THERMAL POWER to < P-6.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months H. THERMAL POWER < P-6, one or two Intermediate Range Neutron Flux channels inoperable.

H.1 Restore channel(s) to OPERABLE status.

Prior to increasing THERMAL POWER to > P-6 I.

One Source Range Neutron Flux channel inoperable.

I.1 Suspend operations involving positive reactivity additions.

Immediately (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-4 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. Two Source Range Neutron Flux channels inoperable.

J.1 Open RTBs.

Immediately K. One Source Range Neutron Flux channel inoperable.

K.1 Restore channel to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR K.2 Open RTBs.

49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months L. Required Source Range Neutron Flux channel inoperable.

L.1 Suspend operations involving positive reactivity additions.

Immediately AND L.2 Close unborated water source isolation valves.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND L.3 Perform SR 3.1.1.1.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-5 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME M. One channel inoperable.

NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

M.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR M.2 Reduce THERMAL POWER to < P-7.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months N. One Reactor Coolant Flow - Low channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

N.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR N.2 Reduce THERMAL POWER to < P-8.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-6 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME O. One Low Fluid Oil Pressure Turbine Trip channel inoperable.

NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

O.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR O.2 Reduce THERMAL POWER to < P-9.

76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months P. One train inoperable.

NOTE-------------------

One train 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 provided the other train is OPERABLE.

P.1 Restore train to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR P.2 Be in MODE 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-7 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Q. One RTB train inoperable.

NOTE-----------------

One train 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, provided the other train is OPERABLE.

Q.1 Restore train to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR Q.2 Be in MODE 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months R. One channel inoperable.

R.1 Verify interlock is in required state for existing unit conditions.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR R.2 Be in MODE 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months S. One channel inoperable.

S.1 Verify interlock is in required state for existing unit conditions.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR S.2 Be in MODE 2.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-8 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T. One trip mechanism inoperable for one RTB.

T.1 Restore inoperable trip mechanism to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR T.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND T.2.2 Open RTB.

55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months U. One Steam Generator Water Level - Low-Low channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

U.1.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND U.1.2 For the affected protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm).

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR U.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-9 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME V. One Vessel T channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

V.1 Set the Trip Time Delay threshold power level for (Ts) and (Tm) to 0% power.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR V.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months W. One channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

W.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR W.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months X. One channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

X.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR X.2 Reduce THERMAL POWER to < P-7.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-10 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Y. One, two or three Turbine Stop Valve Closure channels inoperable.

Y.1 Place channel(s) in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR Y.2 Reduce THERMAL POWER to < P-9.

76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months Z. Two RTS Trains inoperable.

Z.1 Enter LCO 3.0.3.

Immediately SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2

NOTES----------------------------

1. Adjust NIS channel if absolute difference is > 2%.

2. Required to be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER is 15% RTP.

Compare results of calorimetric heat balance calculation to Nuclear Instrumentation System (NIS) channel output.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-11 (developmental)

B SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.3

NOTES----------------------------

1. Adjust NIS channel if absolute difference is 3%.

2. Required to be performed within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after THERMAL POWER is 15% RTP.

Compare results of the PDMS measurements to NIS AFD.

31 effective full power days (EFPD)

SR 3.3.1.4

NOTE------------------------------

This Surveillance must be performed on the reactor trip bypass breaker prior to placing the bypass breaker in service.

Perform TADOT.

62 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.1.6

NOTE------------------------------

Required to be performed within 6 days after THERMAL POWER is 50% RTP.

Calibrate excore channels to agree with the PDMS measurements.

92 EFPD (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-12 (developmental)

A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.7

NOTE------------------------------

For Functions 2 and 3 (Power Range Instrumentation), this Surveillance shall include verification that interlock P-10 is in the required state for existing unit conditions.

Perform COT.

184 days SR 3.3.1.8

NOTES----------------------------

1.

Not required to be performed for Source Range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3.

2.

This Surveillance shall include verification that interlock P-6 is in the required state for existing unit conditions.

NOTE---------

Only required when not performed within previous 31 days Perform COT.

Prior to reactor startup AND Four hours after reducing power below P-10 for intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND Every 31 days thereafter (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-13 (developmental)

A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.9

NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT.

92 days SR 3.3.1.10

NOTE------------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION.

18 months SR 3.3.1.11

NOTE------------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

18 months SR 3.3.1.12 Perform COT.

18 months SR 3.3.1.13

NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT.

18 months (continued)

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-14 (developmental)

A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.14

NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT.

Prior to exceeding the P-9 interlock whenever the unit has been in Mode 3, if not performed within the previous 31 days.

SR 3.3.1.15

NOTE------------------------------

Neutron detectors are excluded from response time testing.

Verify RTS RESPONSE TIME is within limits.

18 months on a STAGGERED TEST BASIS

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-15 (developmental)

B Table 3.3.1-1 (page 1 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOW-ABLE VALUE NOMINAL TRIP SETPOINT

1.

Manual Reactor Trip 1, 2 2

B SR 3.3.1.13 NA NA 3 (a), 4 (a), 5 (a) 2 C

SR 3.3.1.13 NA NA

2.

Power Range Neutron Flux

a.

High 1, 2 4

D SR 3.3.1.1 111.4%

RTP 109% RTP SR 3.3.1.2 SR 3.3.1.7 (b)(c)

SR 3.3.1.11 (b)(c)

SR 3.3.1.15

b.

Low 1 (d), 2 4

E SR 3.3.1.1 27.4%

RTP 25% RTP SR 3.3.1.7 (b)(c)

SR 3.3.1.11 (b)(c)

SR 3.3.1.15

3.

Power Range Neutron Flux Rate

a.

High Positive Rate 1, 2 4

E SR 3.3.1.7 (b)(c) 6.3% R TP with time constant 2 sec 5% RTP with time constant 2 sec SR 3.3.1.11 (b)(c)

b.

High Negative Rate - DELETED

4.

Intermediate Range Neutron Flux 1 (d), 2 (e) 2 F, G SR 3.3.1.1 40% R TP 25% RTP SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (b)(c) 2 (f) 2 H

SR 3.3.1.1 40% R TP 25% RTP SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (b)(c)

(continued)

(a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

(d) Below the P-10 (Power Range Neutron Flux) interlocks.

(e) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-16 (developmental)

B Table 3.3.1-1 (page 2 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOW-ABLE VALUE NOMINAL TRIP SETPOINT

5.

Source Range Neutron Flux 2 (f) 2 I, J SR 3.3.1.1 1.5 E5 cps 1.0 E5 cps SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (b)(c) 3 (a), 4 (a), 5 (a) 2 J, K SR 3.3.1.1 1.5 E5 cps 1.0 E5 cps SR 3.3.1.8 (b)(c)

SR 3.3.1.11 (b)(c)

SR 3.3.1.15 3 (g), 4 (g), 5 (g) 1 L

SR 3.3.1.1 N/A N/A SR 3.3.1.11 (b)(c)

6.

Overtemperature T 1, 2 4

W SR 3.3.1.1 Refer to Note 1 (Page 3.3

-21)

Refer to Note 1 (Page 3.3-

21)

SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15

7.

Overpower T 1, 2 4

W SR 3.3.1.1 Refer to Note 2 (Page 3.3

-22)

Refer to Note 2 (Page 3.3-

22)

SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15

8.

Pressurizer Pressure

a.

Low 1 (h) 4 X

SR 3.3.1.1 1964.8 psig 1970 psig SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15

b.

High 1, 2 4

W SR 3.3.1.1 2390.2 psig 2385 psig SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15 (continued)

(a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(g) With the RTBs open. In this condition, source range Function does not provide reactor trip but does provide indication.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-17 (developmental)

B Table 3.3.1-1 (page 3 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOW-ABLE VALUE NOMINAL TRIP SETPOINT

9.

Pressurizer Water Level-High 1 (h) 3 X

SR 3.3.1.1 92.7%

span 92% span SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

10.

Reactor Coolant Flow - Low 1 (h) 3 per loop N

SR 3.3.1.1 89.6% f low 90% flow SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15

11.

Undervoltage RCPs 1 (h) 1 per bus M

SR 3.3.1.9 4734 V 4830 V SR 3.3.1.10 (b)(c)

SR 3.3.1.15

12.

Underfrequency RCPs 1 (h) 1 per bus M

SR 3.3.1.9 56.9 Hz 57.5 Hz SR 3.3.1.10 (b)(c)

SR 3.3.1.15 (continued)

(b) If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

(h) Above the P-7 (Low Power Reactor Trips Block) interlock.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-18 (developmental)

B Table 3.3.1-1 (page 4 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNEL S

CONDITIONS SURVEILLANCE REQUIREMENTS ALLOW-ABLE VALUE NOMINAL TRIP SETPOINT

13. SG Water Level -

Low-Low 1, 2 3/SG U

SR 3.3.1.1 16.4%

of narrow range span 17% of narrow range span SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

SR 3.3.1.15 Coincident with:

a)

Vessel T Equivalent to power 50% RTP 1, 2 3

V SR 3.3.1.7 (b)(c)

Vessel T

variable input 52.6%

RTP Vessel T variable input 50% RTP SR 3.3.1.10 (b)(c)

With a time delay (Ts) if one steam generator is affected 1.01 Ts (Refer to Note 3, Page 3.3-

23)

Ts (Refer to Note 3, Page 3.3-23) or A time delay (Tm) if two or more steam generators are affected 1.01 Tm (Refer to Note 3, Page 3.3-

23)

Tm (Refer to Note 3, Page 3.3-23)

OR b)

Vessel T Equivalent to power

> 50% RTP with no time delay (Ts and Tm = 0) 1, 2 3

V SR 3.3.1.7 (b)(c)

SR 3.3.1.10 (b)(c)

Vessel T

variable input 52.6%

RTP Vessel T variable input 50% RTP

14.

Turbine Trip

a.

Low Fluid Oil Pressure 1 (i) 3 O

SR 3.3.1.10 43 psig 45 psig SR 3.3.1.14

b.

Turbine Stop Valve Closure 1 (i) 4 Y

SR 3.3.1.10 1% ope n

1% open SR 3.3.1.14 (continued)

(i) Above the P-9 (Power Range Neutron Flux) interlock.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-19 (developmental)

B Table 3.3.1-1 (page 5 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOW-ABLE VALUE NOMINAL TRIP SETPOINT

15.

Safety Injection (SI)

Input from Engineered Safety Feature Actuation System (ESFAS) 1, 2 2 trains P

SR 3.3.1.13 NA NA

16.

Reactor Trip System Interlocks

a.

Intermediate Range Neutron Flux, P-6 (1) Enable Manual Block of SR Trip 2 (f) 2 R

SR 3.3.1.11 NA 1.66E-04%

RTP SR 3.3.1.12 (2) Auto Reset (Unblock Manual Block of SR Trip) 2 (f) 2 R

SR 3.3.1.11 7.65E-5% RTP 0.47E-4%

RTP below setpoint SR 3.3.1.12

b.

Low Power Reactor Trips Block, P-7 1

1 per train S

SR 3.3.1.11 NA NA SR 3.3.1.12

c.

Power Range Neutron Flux, P-8 1

4 S

SR 3.3.1.11 50.4%

RTP 48% RTP SR 3.3.1.12

d.

Power Range Neutron Flux, P-9 1

4 S

SR 3.3.1.11 52.4%

RTP 50% RTP SR 3.3.1.12

e.

Power Range Neutron Flux, P-10 1, 2 4

R SR 3.3.1.11 7.6% R TP and 12.4%

RTP 10% RTP SR 3.3.1.12

f.

Turbine Impulse Pressure, P-13 1

2 S

SR 3.3.1.10 12.4%

full-power pressure 10%

full-power pressure SR 3.3.1.12 (continued)

(f) Below the P-6 (Intermediate Range Neutron Flux) interlocks.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-20 (developmental)

A Table 3.3.1-1 (page 6 of 9)

Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOW-ABLE VALUE NOMINAL TRIP SETPOINT

17.

Reactor Trip Breakers (j) 1, 2 2 trains Q

SR 3.3.1.4 NA NA 3 (a), 4 (a), 5 (a) 2 trains C

SR 3.3.1.4 NA NA

18.

Reactor Trip Breaker Undervoltage and Shunt Trip Mechanisms 1, 2 1 each per RTB T

SR 3.3.1.4 NA NA 3 (a), 4 (a), 5 (a) 1 each per RTB C

SR 3.3.1.4 NA NA

19.

Automatic Trip Logic 1, 2 2 trains P

SR 3.3.1.5 NA NA 3 (a), 4 (a), 5 (a) 2 trains C

SR 3.3.1.5 NA NA (a) With Reactor Trip Breakers (RTBs) closed and Rod Control System capable of rod withdrawal.

(j) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-21 (developmental)

A Table 3.3.1-1 (page 7 of 9)

Reactor Trip System Instrumentation Note 1: Overtemperature T The Overtemperature T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.2% of T span.

[

]

+

)I

(

f

)

P P

(

K T

T

)s 1(

K K

T s

1 s

1 T

1 3

2 1

0 5

4 Where:

T is measured RCS T, °F.

TO is the indicated T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T' is the indicated Tavg at RTP, 588.2°F.

P is the measured pressurizer pressure, psig P' is the nominal RCS operating pressure, 2235 psig K1 1.16 K2 0.0183/°F K3 = 0.000900/psig 1 33 sec 2 4 sec 4 3 sec 5 3 sec f1(I) =

-2.62{22 + (qt - qb)}

when qt - qb < - 22% RTP 0

when -22% RTP qt - qb 10% RTP 1.96{(qt - qb) - 10}

when qt - qb > 10% RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-22 (developmental)

A Table 3.3.1-1 (page 8 of 9)

Reactor Trip System Instrumentation Note 2: Overpower T The Overpower T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.0% of T span.

[

]

+

)

(

1 1

1 2

6 3

3 5

4 0

5 4

I f

T T

K T

s s

K K

T s

s T

Where:

T is measured RCS T, °F.

TO is the indicated T at RTP, °F.

s is the Laplace transform operator, sec-1.

T is the measured RCS average temperature, °F.

T" is the indicated Tavg at RTP, 588.2°F.

K4 1.10 K5 0.02/°F for increasing Tavg K6 0.00162/°F when T > T" 0/°F for decreasing Tavg 0/°F when T T" 3 5 sec 4 3 sec 5 3 sec f2(I) = 0 for all I.

RTS Instrumentation 3.3.1 Watts Bar - Unit 2 3.3-23 (developmental)

A Table 3.3.1-1 (page 9 of 9)

Reactor Trip System Instrumentation NOTE 3: Steam Generator Water Level Low-Low Trip Time Delay:

T AP BP CP D

s =

+

( )

3 2

T EP FP GP H

m =

+

( )

3 2

Where:

P

=

Vessel T Equivalent to power (% RTP), P 50% RTP Ts

=

Time Delay for Steam Generator Water Level - Low Low Reactor Trip, one Steam Generator affected.

Tm

=

Time Delay for Steam Generator Water Level - Low Low Reactor Trip, two or more Steam Generators affected.

A = -0.0085041 B = 0.9266400 C = -33.85998 D = 474.6060 E = -0.0047421 F = 0.5682600 G = -23.70753 H = 357.9840

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-24 (developmental)

A 3.3 INSTRUMENTATION 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.2-1.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one or more required channels or trains inoperable.

A.1 Enter the Condition referenced in Table 3.3.2-1 for the channel(s) or train(s).

Immediately B. One channel or train inoperable.

B.1 Restore channel or train to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR B.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2 Be in Mode 5.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-25 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One train inoperable.

C.1

NOTE------------

One train 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 provided the other train is OPERABLE.

Restore train to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR C.2.1 Be in Mode 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND C.2.2 Be in Mode 5.

60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months D. One channel inoperable.

D.1

NOTE------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR D.2.1 Be in Mode 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND D.2.2 Be in Mode 4.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-26 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment Pressure channel inoperable.

E.1

NOTE------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in bypass.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2.1 Be in Mode 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND E.2.2 Be in Mode 4.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months F. One channel or train inoperable.

F.1 Restore channel or train to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR F.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND F.2.2 Be in Mode 4.

60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months (continued)

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-27 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. One train inoperable.

G.1

NOTE------------

One train 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 provided the other train is OPERABLE.

Restore train to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR G.2.1 Be in Mode 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND G.2.2 Be in Mode 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months H. One train inoperable.

H.1

NOTE------------

One train 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 provided the other train is OPERABLE.

Restore train to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR H.2.1 Be in Mode 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND H.2.2 Be in Mode 4.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-28 (developmental)

B ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I.

One Steam Generator Water Level - High High channel inoperable.

I.1

NOTE------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR I.2.1 Be in Mode 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND I.2.2 Be in Mode 4.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months J. One or more Turbine Driven Main Feedwater Pump trip channel(s) inoperable.

J.1 Restore channel to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR J.2 Be in Mode 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months K. One channel inoperable.

K.1

NOTE------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

Place channel in bypass.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR K.2.1 Be in Mode 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND K.2.2 Be in Mode 5.

108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months (continued)

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-29 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One P-11 interlock channel inoperable.

L.1 Verify interlock is in required state for existing unit condition.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR L.2.1 Be in Mode 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND L.2.2 Be in Mode 4.

13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months M. One Steam Generator Water Level - Low-Low channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

M.1.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND M.1.2 For the affected protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm).

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR M.2.1 Be in Mode 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months AND M.2.2 Be in Mode 4.

84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months (continued)

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-30 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. One Vessel T channel inoperable.

NOTE-------------------

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

N.1 Set the Trip Time Delay threshold power level for (Ts) and (Tm) to 0%

power.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR N.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months O. One MSVV Room Water Level High channel inoperable.

NOTE-------------------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

O.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR O.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-31 (developmental)

B SURVEILLANCE REQUIREMENTS

NOTE----------------------------------------------------------

Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.2.2 Perform ACTUATION LOGIC TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.2.3 Perform MASTER RELAY TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.2.4 Perform COT.

184 days SR 3.3.2.5

NOTE------------------------------

Slave relays tested by SR 3.3.2.7 are excluded from this surveillance.

Perform SLAVE RELAY TEST.

92 days OR 18 months for Westinghouse type AR and Potter &

Brumfield MDR Series relays (continued)

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-32 (developmental)

A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.6

NOTE------------------------------

Verification of relay setpoints not required.

Perform TADOT.

92 days SR 3.3.2.7 Perform SLAVE RELAY TEST on slave relays K603A, K603B, K604A, K604B, K607A, K607B, K609A, K609B, K612A, K625A, and K625B, 18 months SR 3.3.2.8

NOTE------------------------------

Verification of setpoint not required.

Perform TADOT.

18 months SR 3.3.2.9

NOTE------------------------------

This Surveillance shall include verification that the time constants are adjusted to the prescribed values.

Perform CHANNEL CALIBRATION.

18 months SR 3.3.2.10

NOTE------------------------------

Not required to be performed for the turbine driven AFW pump until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 1092 psig in the steam generator.

Verify ESFAS RESPONSE TIMES are within limit.

18 months on a STAGGERED TEST BASIS SR 3.3.2.11

NOTE------------------------------

Verification of setpoint not required.

Perform TADOT.

Once per reactor trip breaker cycle

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-33 (developmental)

B Table 3.3.2-1 (page 1 of 9)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

1.

Safety Injection

a.

Manual Initiation 1, 2, 3, 4 2

B SR 3.3.2.8 NA NA

b.

Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C

SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5 SR 3.3.2.7

c.

Containment Pressure - High 1, 2, 3 3

D SR 3.3.2.1 1.6 psig 1.5 psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10

d.

Pressurizer Pressure - Low 1, 2, 3 (a) 3 D

SR 3.3.2.1

> 1864.8 psig 1870 psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10

e.

Steam Line Pressure - Low 1, 2, 3 (a) 3 per steam line D

SR 3.3.2.1

> 666.6 (d) psig 675 (d) psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10

2.

Containment Spray

a.

Manual Initiation 1, 2, 3, 4 2 per train, 2 trains B

SR 3.3.2.8 NA NA

b.

Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C

SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5

c.

Containment Pressure -

High High 1, 2, 3 4

E SR 3.3.2.1

< 2.9 psig 2.8 psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10 (a)

Above the P-11 (Pressurizer Pressure) Interlock.

(b)

If the as-found channel setpoint is outside its redefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

(d)

Time constants used in the lead/lag controller are t1 > 50 seconds and t2 < 5 seconds.

(continued)

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-34 (developmental)

B Table 3.3.2-1 (page 2 of 9)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

3.

Containment Isolation

a.

Phase A Isolation (1) Manual Initiation 1, 2, 3, 4 2

B SR 3.3.2.8 NA NA (2) Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C

SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5 SR 3.3.2.7 (3) Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

b.

Phase B Isolation (1) Manual Initiation 1, 2, 3, 4 2 per train, 2 trains B

SR 3.3.2.8 NA NA (2) Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C

SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5 SR 3.3.2.7 (3) Containment Pressure -

High High 1, 2, 3 4

E SR 3.3.2.1

< 2.9 psig 2.8 psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10 (continued)

(b)

If the as-found channel setpoint is outside its redefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-35 (developmental)

B Table 3.3.2-1 (page 3 of 9)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

4.

Steam Line Isolation

a.

Manual Initiation 1, 2 (e), 3 (e) 1/valve F

SR 3.3.2.8 NA NA

b.

Automatic Actuation Logic and Actuation Relays 1, 2 (e), 3 (e) 2 trains G

SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5

c.

Containment Pressure -

High High 1, 2 (e), 3 (e) 4 E

SR 3.3.2.1

< 2.9 psig 2.8 psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10

d.

Steam Line Pressure (1) Low 1, 2 (e), 3 (a)(e) 3 per steam line D

SR 3.3.2.1

> 666.6 (d) psig 675 (d) psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10 (2) Negative Rate - High 3

(e)(f) 3 per steam line D

SR 3.3.2.1

< 108.5 (g) psi 100 (g) psi SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10 (continued)

(b)

If the as-found channel setpoint is outside its redefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

(d)

Time constants used in the lead/lag controller are t1 > 50 seconds and t2 < 5 seconds.

(e)

Except when all MSIVs are closed and de-activated.

(f)

Function automatically blocked above P-11 (Pressurizer Interlock) setpoint and is enabled below P-11 when safety injection on Steam Line Pressure Low is manually blocked.

(g)

Time constants utilized in the rate/lag controller are t3 and t4 > 50 seconds.

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-36 (developmental)

B Table 3.3.2-1 (page 4 of 9)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

5.

Turbine Trip and Feedwater Isolation

a.

Automatic Actuation Logic and Actuation Relays 1, 2 (h), 3 (h) 2 trains H

SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5

b.

SG Water Level -

High High (P-14) 1, 2 (h), 3 (h) 3 per SG I

SR 3.3.2.1

< 83.1%

82.4%

SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10

c.

Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

d.

North MSV Vault Room Water Level - High 1, 2 (h)(i) 3 per vault room O

SR 3.3.2.6

< 5.31 inches 4 inches SR 3.3.2.9 (b) (c)

e.

South MSV Vault Room Water Level - High 1, 2 (h)(i) 3 per vault room O

SR 3.3.2.6

< 4.56 inches 4 inches SR 3.3.2.9 (b) (c)

(continued)

(b)

If the as-found channel setpoint is outside its redefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

(h)

Except when all MFIVs, MFRVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

(i)

Mode 2 if Turbine Driven Main Feed Pumps are operating.

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-37 (developmental)

B Table 3.3.2-1 (page 5 of 9)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

6.

Auxiliary Feedwater

a.

Automatic Actuation Logic and Actuation Relays 1, 2, 3 2 trains G

SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5

b.

SG Water Level

- Low Low 1, 2, 3 3 per SG M

SR 3.3.2.1

> 16.4%

17.0%

SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10 Coincident with:

1) Vessel T Equivalent to power 50% RTP 1, 2 3

N SR 3.3.2.4 (b) (c)

Vessel T variable input 52.6% RTP Vessel T variable input 50% RTP SR 3.3.2.9 (b) (c)

With a time delay (Ts) if one SG is affected 1.01 Ts (Note 1, Page 3.3-40)

Ts (Note 1, Page 3.3-40)

Or A time delay (Tm) if two or more SGs are affected 1.01 Tm (Note 1, Page 3.3-40)

Tm (Note 1, Page 3.3-40)

OR

2) Vessel T equivalent to power

> 50% RTP with no time delay (Ts and Tm = 0) 1, 2 3

N SR 3.3.2.4 (b) (c)

Vessel T variable input 52.6% RTP Vessel T variable input 50% RTP SR 3.3.2.9 (b) (c)

c.

Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(continued)

(b)

If the as-found channel setpoint is outside its redefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-38 (developmental)

B Table 3.3.2-1 (page 6 of 9)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

6.

Auxiliary Feedwater (continued)

d.

Loss of Offsite Power 1, 2, 3 4 per bus F

Refer to Function 4 of Table 3.3.5-1 for SRs and Allowable Values.

e.

Trip of all Turbine Driven Main Feedwater Pumps 1,

(j) 2 (k) 1 per pump J

SR 3.3.2.8

> 48 psig 50 psig SR 3.3.2.9 (b) (c)

SR 3.3.2.10

f.

Auxiliary Feedwater Pumps Train A and B Suction Transfer on Suction Pressure - Low 1, 2, 3 3

F SR 3.3.2.6 A) > 0.5 psig A) 1.2 psig SR 3.3.2.9 (b) (c)

SR 3.3.2.10 B) > 1.33 psig B) 2.0 psig

7.

Automatic Switchover to Containment Sump

a.

Automatic Actuation Logic and Actuation Relays 1, 2, 3, 4 2 trains C

SR 3.3.2.2 NA NA SR 3.3.2.3 SR 3.3.2.5

b.

Refueling Water Storage Tank (RWST)

Level - Low 1, 2, 3, 4 4

K SR 3.3.2.1

> 155.6 inches from Tank Base 158 inches from Tank Base SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10 Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

And Coincident with Containment Sump Level - High 1, 2, 3, 4 4

K SR 3.3.2.1

> 37.2 inches above el. 702.8 ft 38.2 inches above el. 702.8 ft SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

SR 3.3.2.10 (continued)

(b)

If the as-found channel setpoint is outside its redefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

(j)

Entry into Condition J may be suspended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when placing the second Turbine Driven Main Feedwater (TDMFW) Pump in service or removing one of two TDMFW pumps from service.

(k)

When one or more Turbine Driven Feedwater Pump(s) are supplying feedwater to steam generators.

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-39 (developmental)

B Table 3.3.2-1 (page 8 of 9)

Engineered Safety Feature Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

8.

ESFAS Interlocks

a.

Reactor Trip, P-4 1, 2, 3 1 per train, 2 trains F

SR 3.3.2.11 NA NA

b.

Pressurizer Pressure, P-11 (1) Unblock (Auto Reset of SI Block) 1, 2, 3 3

L SR 3.3.2.1

< 1975.2 psig 1970 psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

(2) Enable Manual Block of SI 1, 2, 3 3

L SR 3.3.2.1

> 1956.8 psig 1962 psig SR 3.3.2.4 (b) (c)

SR 3.3.2.9 (b) (c)

(b)

If the as-found channel setpoint is outside its redefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(c)

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the Nominal Trip Setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the Surveillance procedures (field setting) to confirm channel performance. The Nominal Trip Setpoint and allowable values are specified in WCAP 17044, Setpoint Methodology for Watts Bar Unit 2. The as-found and as-left tolerances are defined in the Nuclear Engineering Setpoint and Scaling Documents.

ESFAS Instrumentation 3.3.2 Watts Bar - Unit 2 3.3-40 (developmental)

A Table 3.3.2-1 (page 9 of 9)

Engineered Safety Feature Actuation System Instrumentation NOTE 1: Steam Generator Water Level Low-Low Trip Time Delay:

T AP BP CP D

s =

+

( )

3 2

T EP FP GP H

m =

+

( )

3 2

Where:

P

=

Vessel T Equivalent to power (% RTP), P 50% RTP.

Ts

=

Time Delay for Steam Generator Water Level - Low-Low Reactor Trip, one Steam Generator affected.

Tm

=

Time Delay for Steam Generator Water Level - Low-Low Reactor Trip, two or more Steam Generators affected.

A = -0.0085041 B = 0.9266400 C = -33.85998 D = 474.6060 E = -0.0047421 F = 0.5682600 G = -23.70753 H = 357.9840

PAM Instrumentation 3.3.3 Watts Bar - Unit 2 3.3-41 (developmental)

B 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.3-1.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE----------------

Not applicable to Functions 3, 4, 14, and 16.

One or more Functions with one required channel inoperable.

A.1 Restore required channel to OPERABLE status.

30 days B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action in accordance with Specification 5.9.8.

Immediately (continued)

PAM Instrumentation 3.3.3 Watts Bar - Unit 2 3.3-42 (developmental)

B ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

One or more Functions with two required channels inoperable.

OR Functions 3, 4, 14, and 16 with one required channel inoperable.

C.1 Restore one channel to OPERABLE status.

7 days D. Required Action and associated Completion Time of Condition C not met.

D.1 Enter the Condition referenced in Table 3.3.3-1 for the channel.

Immediately E. As required by Required Action D.1 and referenced in Table 3.3.3-1.

E.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND E.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. As required by Required Action D.1 and referenced in Table 3.3.3-1.

F.1 Initiate action in accordance with Specification 5.9.8.

Immediately

PAM Instrumentation 3.3.3 Watts Bar - Unit 2 3.3-43 (developmental)

B SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

31 days SR 3.3.3.2

NOTES----------------------------

1. Neutron detectors are excluded from CHANNEL CALIBRATION.

2. Not applicable to Functions 11 and 16.

Perform CHANNEL CALIBRATION.

18 months SR 3.3.3.3

NOTES----------------------------

1. Verification of relay setpoints not required.

2. Only applicable to Functions 11 and 16.

Perform TADOT.

18 months

PAM Instrumentation 3.3.3 Watts Bar - Unit 2 3.3-44 (developmental)

B Table 3.3.3-1 (page 1 of 3)

Post Accident Monitoring Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS /

TRAINS CONDITION REFERENCED FROM REQUIRED ACTION D.1

1)

Intermediate Range Neutron Flux (g) 1(a), 2(b), 3 2

E

2)

Source Range Neutron Flux 2(c), 3 2

E

3)

Reactor Coolant System (RCS) Hot Leg Temperature (T-Hot) 1, 2, 3 1 per loop E

4)

RCS Cold Leg Temperature (T-Cold) 1, 2, 3 1 per loop E

5)

RCS Pressure (Wide Range) 1, 2, 3 3

E

6)

Reactor Vessel Water Level (f) (g) 1, 2, 3 2

F

7)

Containment Sump Water Level (Wide Range) 1, 2, 3 2

E

8)

Containment Lower Comp.

Atm. Temperature 1, 2, 3 2

E

9)

Containment Pressure (Wide Range) (g) 1, 2, 3 2

E

10)

Containment Pressure (Narrow Range) 1, 2, 3 4

E

11)

Containment Isolation Valve Position (g) 1, 2, 3 2 per penetration flow path (d)(i)

E

12)

Containment Radiation (High Range) 1, 2, 3 2 upper containment 2 lower containment F

13)

RCS Pressurizer Level 1, 2, 3 3

E

14)

Steam Generator (SG) Water Level (Wide Range) (g) 1, 2, 3 1/SG E

(continued)

PAM Instrumentation 3.3.3 Watts Bar - Unit 2 3.3-45 (developmental)

B Table 3.3.3-1 (page 2 of 3)

Post Accident Monitoring Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS /

TRAINS CONDITION REFERENCED FROM REQUIRED ACTION E.1

15)

Steam Generator Water Level (Narrow Range) 1, 2, 3 3/SG E

16)

AFW Valve Status (j) 1, 2, 3 1 per valve E

17)

Core Exit Temperature-Quadrant 1(f) 1, 2, 3 2 (e)

E

18)

Core Exit Temperature-Quadrant 2(f) 1, 2, 3 2 (e)

E

19)

Core Exit Temperature-Quadrant 3(f) 1, 2, 3 2 (e)

E

20)

Core Exit Temperature-Quadrant 4(f) 1, 2, 3 2 (e)

E

21)

Auxiliary Feedwater Flow 1, 2, 3 2/SG E

22)

Reactor Coolant System Subcooling Margin Monitor (h) 1, 2, 3 2

E

23)

Refueling Water Storage Tank Water Level 1, 2, 3 2

E

24)

Steam Generator Pressure 1, 2, 3 2/SG E

25)

Auxiliary Building Passive Sump Level (j) 1, 2, 3 2

E

PAM Instrumentation 3.3.3 Watts Bar - Unit 2 3.3-46 (developmental)

B Table 3.3.3-1 (page 3 of 3)

Post Accident Monitoring Instrumentation (a)

Below the P-10 (Power Range Neutron Flux) interlocks.

(b)

Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(c)

Below the P-6 (Intermediate Range Neutron Flux) interlocks (d)

Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, pressure relief valve, or check valve with flow through the valve secured.

(e)

A channel consists of two core exit thermocouples (CETs).

(f)

The Common Q Post Accident Monitoring System provides these functions on a flat screen display.

(g)

Regulatory Guide 1.97, non-Type A, Category 1 Variables.

(h)

This function is displayed on the Common Q Post Accident Monitoring System flat screen display and digital panel meters.

(i)

Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(j)

Watts Bar specific (not required by Regulatory Guide 1.97) non-Type A Category 1 variable.

Remote Shutdown System 3.3.4 Watts Bar - Unit 2 3.3-47 (developmental)

A 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System LCO 3.3.4 The Remote Shutdown System Functions in Table 3.3.4-1 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3 ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required Functions inoperable.

A.1 Restore required Function to OPERABLE status.

30 days B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Remote Shutdown System 3.3.4 Watts Bar - Unit 2 3.3-48 (developmental)

B SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

31 days SR 3.3.4.2 Verify each required control circuit and transfer switch is capable of performing the intended function.

18 months SR 3.3.4.3

NOTE----------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each required instrumentation channel.

18 months SR 3.3.4.4 Perform TADOT of the reactor trip breaker open/closed indication.

18 months

Remote Shutdown System 3.3.4 Watts Bar - Unit 2 3.3-49 (developmental)

A Table 3.3.4-1 (page 1 of 1)

Remote Shutdown System Instrumentation and Controls FUNCTION/INSTRUMENT OR CONTROL PARAMETER REQUIRED NUMBER OF FUNCTIONS

1.

Reactivity Control

a.

Source Range Neutron Flux 1

b.

Reactor Trip Breaker Position Indication 1 per trip breaker

2.

Reactor Coolant System (RCS) Pressure Control

a.

Pressurizer Pressure Indication or RCS Wide Range Pressure Indication 1

b.

Pressurizer Power Operated Relief Valve (PORV) Control and Pressurizer Block Valve Control 1 each per relief path

c.

Pressurizer Heater Control 1

3.

RCS Inventory Control

a.

Pressurizer Level Indication 1

b.

Charging and Letdown Flow Control and Indication 1

4.

Decay Heat Removal via Steam Generators (SGs)

a.

RCS Hot Leg Temperature Indication 1 per loop

b.

AFW Controls 1

c.

SG Pressure Indication and Control 1 per SG

d.

SG Level Indication and AFW Flow Indication 1 per SG

e.

SG Tsat Indication 1 per SG

5.

Decay Heat Removal via RHR System

a.

RHR Flow Control 1

b.

RHR Temperature Indication 1

LOP DG Start Instrumentation 3.3.5 Watts Bar - Unit 2 3.3-50 (developmental)

A 3.3 INSTRUMENTATION 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation LCO 3.3.5 The LOP DG Start Instrumentation for each Function in Table 3.3.5-1 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4, When associated DG is required to be OPERABLE by LCO 3.8.2, "AC Sources-Shutdown."

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one channel per bus inoperable.

NOTE-------------------

Enter applicable Conditions and Required Actions of LCO 3.3.2, "ESFAS Instrumentation," for Auxiliary Feedwater Start Instrumentation made inoperable by LOP DG Start Instrumentation.

A.1 Restore channel to OPERABLE status.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. One or more Functions with two or more channels per bus inoperable.

B.1 Restore all but one channel to OPERABLE status.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (continued)

LOP DG Start Instrumentation 3.3.5 Watts Bar - Unit 2 3.3-51 (developmental)

A ACTIONS continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time not met.

C.1 Enter applicable Condition(s) and Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.

Immediately SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table 3.3.5-1 to determine which SRs apply for each LOP Function.

SURVEILLANCE FREQUENCY SR 3.3.5.1

NOTE------------------------------

Verification of relay setpoints not required.

Perform TADOT.

92 days SR 3.3.5.2 Perform CHANNEL CALIBRATION.

6 months SR 3.3.5.3 Perform CHANNEL CALIBRATION.

18 months

LOP DG Start Instrumentation 3.3.5 Watts Bar - Unit 2 3.3-52 (developmental)

A Table 3.3.5-1 (page 1 of 1)

LOP DG Start Instrumentation FUNCTION REQUIRED CHANNELS PER BUS SURVEILLANCE REQUIREMENTS TRIP SETPOINT ALLOWABLE VALUE

1.

6.9 kV Emergency Bus Undervoltage (Loss of Voltage)

a.

Bus Undervoltage 3

SR 3.3.5.1 SR 3.3.5.2 5994 V and 6006 V 5967.6 V

b.

Time Delay 2

SR 3.3.5.3 0.73 sec and 0.77 sec 0.58 sec and 0.94 sec

2.

6.9 kV Emergency Bus Undervoltage (Degraded Voltage)

a.

Bus Undervoltage 3

SR 3.3.5.1 SR 3.3.5.2 6593.4 V and 6606.6 V 6570 V

b.

Time Delay 2

SR 3.3.5.3 9.73 sec and 10.27 sec 9.42 sec and 10.49 sec

3.

Diesel Generator Start 2

SR 3.3.5.1 SR 3.3.5.2 4733.4 V and 4926.6 V with an internal time delay of 0.46 sec and 0.54 sec 2295.6 V with an internal time delay of 0.56 sec at zero volts

4.

Load Shed 4

SR 3.3.5.1 SR 3.3.5.2 4733.4 V and 4926.6 V with an internal time delay of 2.79 sec and 3 21 sec 2295.6 V with an internal time delay of 3.3 sec at zero volts.

Containment Vent Isolation Instrumentation 3.3.6 Watts Bar - Unit 2 3.3-53 (developmental)

A 3.3 INSTRUMENTATION 3.3.6 Containment Vent Isolation Instrumentation LCO 3.3.6 The Containment Vent Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies within containment.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation monitoring channel inoperable.

A.1 Restore the affected channel to OPERABLE status.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

Containment Vent Isolation Instrumentation 3.3.6 Watts Bar - Unit 2 3.3-54 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. --------------NOTE--------------

Only applicable in MODE 1, 2, 3, or 4.

One or more Functions with one or more manual or automatic actuation trains inoperable.

OR Two radiation monitoring channels inoperable.

OR Required Action and associated Completion Time of Condition A not met.

NOTE-------------------

One train of automatic actuation logic may be bypassed and Required Action B.1 may be delayed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Surveillance testing provided the other train is OPERABLE.

B.1 Enter applicable Conditions and Required Actions of LCO 3.6.3, "Containment Isolation Valves," for containment purge and exhaust isolation valves made inoperable by isolation instrumentation.

Immediately (continued)

Containment Vent Isolation Instrumentation 3.3.6 Watts Bar - Unit 2 3.3-55 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. --------------NOTE--------------

Only applicable during movement of irradiated fuel assemblies within containment.

One or more Functions with one or more manual or automatic actuation trains inoperable.

OR Two radiation monitoring channels inoperable.

OR Required Action and associated Completion Time for Condition A not met.

C.1 Place and maintain containment purge and exhaust valves in closed position.

Immediately OR C.2 Enter applicable Conditions and Required Actions of LCO 3.9.4, "Containment Penetrations," for containment purge and exhaust isolation valves made inoperable by isolation instrumentation.

Immediately

Containment Vent Isolation Instrumentation 3.3.6 Watts Bar - Unit 2 3.3-56 (developmental)

B SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Vent Isolation Function.

SURVEILLANCE FREQUENCY SR 3.3.6.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.2

NOTE------------------------------

This surveillance is only applicable to the actuation logic of the ESFAS instrumentation.

Perform ACTUATION LOGIC TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.6.3

NOTE------------------------------

This surveillance is only applicable to the master relays of the ESFAS instrumentation.

Perform MASTER RELAY TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.6.4 Perform COT.

92 days SR 3.3.6.5 Perform SLAVE RELAY TEST.

92 days OR 18 months for Westinghouse type AR and Potter &

Brumfield MDR Series relays (continued)

Containment Vent Isolation Instrumentation 3.3.6 Watts Bar - Unit 2 3.3-57 (developmental)

A SURVEILLANCE REQUIREMENTS (Continued)

SURVEILLANCE FREQUENCY SR 3.3.6.6

NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT.

18 months SR 3.3.6.7 Perform CHANNEL CALIBRATION.

18 months

Containment Vent Isolation Instrumentation 3.3.6 Watts Bar - Unit 2 3.3-58 (developmental)

B Table 3.3.6-1 (page 1 of 1)

Containment Vent Isolation Instrumentation FUNCTION REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1.

Manual Initiation 2

SR 3.3.6.6 NA

2.

Automatic Actuation Logic and Actuation Relays 2 trains SR 3.3.6.2 SR 3.3.6.3 SR 3.3.6.5 NA

3.

Containment Purge Exhaust Radiation Monitors 2

SR 3.3.6.1 SR 3.3.6.4 SR 3.3.6.7 8.41E-02 Ci/cc(a)

(3.43x104 cpm)

< 2.8E-02 µCi/cc(b)

(1.14x104 cpm)

4.

Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.

(a) During movement of irradiated fuel assemblies within containment.

(b) Modes 1, 2, 3, and 4.

CREVS Actuation Instrumentation 3.3.7 Watts Bar - Unit 2 3.3-59 (developmental)

A 3.3 INSTRUMENTATION 3.3.7 Control Room Emergency Ventilation System (CREVS) Actuation Instrumentation LCO 3.3.7 The CREVS actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, 4, 5, and 6 During movement of irradiated fuel assemblies.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one channel or train inoperable.

A.1 Place one CREVS train in emergency radiation protection mode.

7 days (continued)

CREVS Actuation Instrumentation 3.3.7 Watts Bar - Unit 2 3.3-60 (developmental)

A ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with two channels or two trains inoperable.

B.1.1 Place one CREVS train in emergency radiation protection mode.

Immediately AND B.1.2 Enter applicable Conditions and Required Actions for one CREVS train made inoperable by inoperable CREVS actuation instrumentation Immediately OR B.2 Place both trains in emergency radiation protection mode.

Immediately C. Required Action and associated Completion Time for Condition A or B not met in MODE 1, 2, 3, or 4.

C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND C.2 Be in MODE 5 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and associated Completion Time for Condition A or B not met during movement of irradiated fuel assemblies.

D.1 Suspend movement of irradiated fuel assemblies.

Immediately E. Required Action and associated Completion Time for Condition A or B not met in MODE 5 or 6.

E.1 Initiate action to restore one CREVS train to OPERABLE status.

Immediately

CREVS Actuation Instrumentation 3.3.7 Watts Bar - Unit 2 3.3-61 (developmental)

A SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table 3.3.7-1 to determine which SRs apply for each CREVS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.7.2 Perform COT.

92 days SR 3.3.7.3

NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT.

18 months SR 3.3.7.4 Perform CHANNEL CALIBRATION.

18 months

CREVS Actuation Instrumentation 3.3.7 Watts Bar - Unit 2 3.3-62 (developmental)

A Table 3.3.7-1 (page 1 of 1)

CREVS Actuation Instrumentation FUNCTION REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1.

Manual Initiation 2 trains SR 3.3.7.3 NA

2.

Control Room Radiation Control Room Air Intakes 2

SR 3.3.7.1 SR 3.3.7.2 SR 3.3.7.4 9.45E-05 C/cc (3,308 cpm)

3.

Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.

ABGTS Actuation Instrumentation 3.3.8 Watts Bar - Unit 2 3.3-63 (developmental)

A 3.3 INSTRUMENTATION 3.3.8 Auxiliary Building Gas Treatment System (ABGTS) Actuation Instrumentation LCO 3.3.8 The ABGTS actuation instrumentation for each Function in Table 3.3.8-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.8-1.

ACTIONS

NOTE-------------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one channel or train inoperable.

A.1 Place one ABGTS train in operation.

7 days B. One or more Functions with two channels or two trains inoperable.

B.1.1 Place one ABGTS train in operation.

Immediately AND B.1.2 Enter applicable Conditions and Required Actions of LCO 3.7.12, "Auxiliary Building Gas Treatment System (ABGTS)," for one train made inoperable by inoperable actuation instrumentation Immediately OR (continued)

ABGTS Actuation Instrumentation 3.3.8 Watts Bar - Unit 2 3.3-64 (developmental)

A ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)

B.2 Place both trains in emergency radiation protection mode.

Immediately C. Required Action and associated Completion Time for Condition A or B not met during movement of irradiated fuel assemblies in the fuel handling area.

C.1 Suspend movement of irradiated fuel assemblies in the fuel handling area.

Immediately D. Required Action and associated Completion Time for Condition A or B not met in MODE 1, 2, 3, or 4.

D.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND D.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

Refer to Table 3.3.8-1 to determine which SRs apply for each ABGTS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.8.2 Perform COT.

92 days (continued)

ABGTS Actuation Instrumentation 3.3.8 Watts Bar - Unit 2 3.3-65 (developmental)

A SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.8.3

NOTE------------------------------

Verification of setpoint is not required.

Perform TADOT.

18 months SR 3.3.8.4 Perform CHANNEL CALIBRATION.

18 months

ABGTS Actuation Instrumentation 3.3.8 Watts Bar - Unit 2 3.3-66 (developmental)

A Table 3.3.8-1 (page 1 of 1)

ABGTS Actuation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1.

Manual Initiation 1,2,3,4 2

SR 3.3.8.3 NA (a) 2 SR 3.3.8.3 NA

2.

Fuel Pool Area Radiation Monitors (a) 2 SR 3.3.8.1 SR 3.3.8.2 SR 3.3.8.4 1161 mR/hr

3.

Containment Isolation Refer to LCO 3.3.2, Function 3.a., for all Phase A initiating functions and requirements.

(a) During movement of irradiated fuel assemblies in the fuel handling area.

ML100550451

Text

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