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 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 A.1 Enter the Condition Immediately one or more required referenced in channels inoperable. Table 3.3.1-1 for the channel(s).

B. One Manual Reactor Trip B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months channel inoperable. OPERABLE status.

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

(continued)

Watts Bar - Unit 2 3.3-1 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One channel or train C.1 Restore channel or train 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. to OPERABLE status.

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

Flux-High channel The inoperable channel may be inoperable. 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 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to 75% RTP.

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)

Watts Bar - Unit 2 3.3-2 (developmental) A

RTS Instrumentation 3.3.1 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 F.1 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and < P-10, one POWER to < P-6.

Intermediate Range Neutron Flux channel OR inoperable.

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

G. THERMAL POWER > P-6 G.1 Suspend operations Immediately and < P-10, two involving positive Intermediate Range reactivity additions.

Neutron Flux channels inoperable. AND G.2 Reduce THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to < P-6.

H. THERMAL POWER < P-6, H.1 Restore channel(s) to Prior to increasing one or two Intermediate OPERABLE status. THERMAL POWER Range Neutron Flux to > P-6 channels inoperable.

I. One Source Range Neutron I.1 Suspend operations Immediately Flux channel inoperable. involving positive reactivity additions.

(continued)

Watts Bar - Unit 2 3.3-3 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J. Two Source Range Neutron J.1 Open RTBs. Immediately Flux channels inoperable.

K. One Source Range Neutron K.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Flux channel inoperable. OPERABLE status.

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 L.1 Suspend operations Immediately Neutron Flux channel involving positive inoperable. reactivity additions.

AND L.2 Close unborated water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months source isolation valves.

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)

Watts Bar - Unit 2 3.3-4 (developmental) A

RTS Instrumentation 3.3.1 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 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to < P-7.

N. One Reactor Coolant --------------------NOTE-------------------

Flow - Low channel One channel may be bypassed for inoperable. 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 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to < P-8.

(continued)

Watts Bar - Unit 2 3.3-5 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME O. One Low Fluid Oil Pressure --------------------NOTE-------------------

Turbine Trip channel The inoperable channel may be inoperable. 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 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months POWER to < P-9.

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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

OR P.2 Be in MODE 3. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months (continued)

Watts Bar - Unit 2 3.3-6 (developmental) A

RTS Instrumentation 3.3.1 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required state for existing unit conditions.

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required state for existing unit conditions.

OR S.2 Be in MODE 2. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months (continued)

Watts Bar - Unit 2 3.3-7 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T. One trip mechanism T.1 Restore inoperable trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable for one RTB. mechanism to OPERABLE status.

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

Water Level - Low-Low One channel may be bypassed channel inoperable. 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 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm).

OR U.2 Be in MODE 3. 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

Watts Bar - Unit 2 3.3-8 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME V. One Vessel T channel --------------------NOTE-------------------

inoperable. 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 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months threshold power level for (Ts) and (Tm) to 0% power.

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 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months POWER to < P-7.

(continued)

Watts Bar - Unit 2 3.3-9 (developmental) A

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Y. One, two or three Turbine Y.1 Place channel(s) in trip. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Stop Valve Closure channels inoperable. OR Y.2 Reduce THERMAL 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months POWER to < P-9.

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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months calculation to Nuclear Instrumentation System (NIS) channel output.

(continued)

Watts Bar - Unit 2 3.3-10 (developmental) A

RTS Instrumentation 3.3.1 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 31 effective full NIS AFD. 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 92 EFPD measurements.

(continued)

Watts Bar - Unit 2 3.3-11 (developmental) B

RTS Instrumentation 3.3.1 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---------------------------- ----------NOTE---------

1. Not required to be performed for Source Range Only required when instrumentation prior to entering MODE 3 from not performed within MODE 2 until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entry into MODE 3. previous 31 days

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

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)

Watts Bar - Unit 2 3.3-12 (developmental) A

RTS Instrumentation 3.3.1 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)

Watts Bar - Unit 2 3.3-13 (developmental) A

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

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER ALLOW- NOMINAL SPECIFIED REQUIRED SURVEILLANCE ABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 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% 109% RTP SR 3.3.1.2 RTP 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% 25% RTP SR 3.3.1.7 (b)(c) RTP SR 3.3.1.11 (b)(c)

SR 3.3.1.15

3. Power Range Neutron Flux Rate

a. High Positive 1, 2 4 E SR 3.3.1.7 (b)(c) 6.3% R 5% RTP Rate SR 3.3.1.11 (b)(c) TP with with time time constant constant 2 sec 2 sec

b. High Negative Rate - DELETED (d)

4. Intermediate Range 1 , 2 (e) 2 F, G SR 3.3.1.1 40% R 25% RTP Neutron Flux SR 3.3.1.8 (b)(c) TP SR 3.3.1.11 (b)(c) 2 (f) 2 H SR 3.3.1.1 40% R 25% RTP SR 3.3.1.8 (b)(c) TP 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.

Watts Bar - Unit 2 3.3-15 (developmental) B

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 9)

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

5. Source Range 2 2 I, J SR 3.3.1.1 1.5 E5 1.0 E5 cps Neutron Flux SR 3.3.1.8 (b)(c) cps SR 3.3.1.11 (b)(c) 3 (a), 4 (a), 5 (a) 2 J, K SR 3.3.1.1 1.5 E5 1.0 E5 cps SR 3.3.1.8 (b)(c) cps 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 Refer to SR 3.3.1.3 Note 1 Note 1 SR 3.3.1.6 (Page 3.3 (Page 3.3-SR 3.3.1.7 (b)(c) -21) 21)

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 Refer to SR 3.3.1.7 (b)(c) Note 2 Note 2 SR 3.3.1.10 (b)(c) (Page 3.3 (Page 3.3-SR 3.3.1.15 -22) 22)

8. Pressurizer Pressure

a. Low 1 (h) 4 X SR 3.3.1.1 1964.8 1970 psig SR 3.3.1.7 (b)(c) psig 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 2385 psig SR 3.3.1.7 (b)(c) psig 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.

Watts Bar - Unit 2 3.3-16 (developmental) B

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 9)

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

9. Pressurizer Water 1 3 X SR 3.3.1.1 92.7% 92% span Level-High SR 3.3.1.7 (b)(c) span SR 3.3.1.10 (b)(c)

(h)

10. Reactor Coolant 1 3 per loop N SR 3.3.1.1 89.6% f 90% flow Flow - Low SR 3.3.1.7 (b)(c) low 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 (h)

12. Underfrequency 1 1 per bus M SR 3.3.1.9 56.9 Hz 57.5 Hz RCPs 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.

Watts Bar - Unit 2 3.3-17 (developmental) B

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 9)

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

13. SG Water Level - 1, 2 3/SG U SR 3.3.1.1 16.4% 17% of Low-Low SR 3.3.1.7 (b)(c) of narrow narrow range SR 3.3.1.10 (b)(c) range span SR 3.3.1.15 span Coincident with:

a) Vessel T 1, 2 3 V SR 3.3.1.7 (b)(c) Vessel Vessel T Equivalent to SR 3.3.1.10 (b)(c) T variable input power variable 50% RTP 50% RTP input 52.6%

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

OR b) Vessel T 1, 2 3 V SR 3.3.1.7 (b)(c) Vessel Vessel T Equivalent to SR 3.3.1.10 (b)(c) T variable input power variable 50% RTP

> 50% RTP input with no time 52.6%

delay (Ts and RTP Tm = 0)

14. Turbine Trip (i)

a. Low Fluid Oil 1 3 O SR 3.3.1.10 43 psig 45 psig Pressure SR 3.3.1.14

b. Turbine Stop 1 (i) 4 Y SR 3.3.1.10 1% ope 1% open Valve Closure SR 3.3.1.14 n (continued)

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

Watts Bar - Unit 2 3.3-18 (developmental) B

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 5 of 9)

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

15. Safety Injection (SI) 1, 2 2 trains P SR 3.3.1.13 NA NA Input from Engineered Safety Feature Actuation System (ESFAS)

16. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 (1) Enable 2 (f) 2 R SR 3.3.1.11 NA 1.66E-04%

Manual SR 3.3.1.12 RTP Block of SR Trip (2) Auto 2 (f) 2 R SR 3.3.1.11 7.65E- 0.47E-4%

Reset SR 3.3.1.12 5% RTP RTP below (Unblock setpoint Manual Block of SR Trip)

b. Low Power 1 1 per train S SR 3.3.1.11 NA NA Reactor Trips SR 3.3.1.12 Block, P-7

c. Power Range 1 4 S SR 3.3.1.11 50.4% 48% RTP Neutron Flux, SR 3.3.1.12 RTP P-8

d. Power Range 1 4 S SR 3.3.1.11 52.4% 50% RTP Neutron Flux, SR 3.3.1.12 RTP P-9

e. Power Range 1, 2 4 R SR 3.3.1.11 7.6% R 10% RTP Neutron Flux, SR 3.3.1.12 TP P-10 and 12.4%

RTP

f. Turbine 1 2 S SR 3.3.1.10 12.4% 10%

Impulse SR 3.3.1.12 full-power full-power Pressure, P-13 pressure pressure (continued)

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

Watts Bar - Unit 2 3.3-19 (developmental) B

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 6 of 9)

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

17. Reactor Trip 1, 2 2 trains Q SR 3.3.1.4 NA NA Breakers (j) 3 (a), 4 (a) , 5 (a) 2 trains C SR 3.3.1.4 NA NA

18. Reactor Trip 1, 2 1 each T SR 3.3.1.4 NA NA Breaker per RTB Undervoltage and Shunt Trip 3 (a), 4 (a) , 5 (a) 1 each C SR 3.3.1.4 NA NA Mechanisms per RTB

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.

Watts Bar - Unit 2 3.3-20 (developmental) A

RTS Instrumentation 3.3.1 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.

1+ s (1+ 1s)

T 4 T0 K1 K2 [T T] + K3 (P P) f1(I) 1+ 5s (1+2 s)

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.

Watts Bar - Unit 2 3.3-21 (developmental) A

RTS Instrumentation 3.3.1 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 + 4s s T T0 K4 K5 3 T K6[T T"] f2 (I )

1+5s 1+3s 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.

Watts Bar - Unit 2 3.3-22 (developmental) A

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 9 of 9)

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

Ts = A(P)3 + B(P)2 + C(P) + D Tm = EP ( )3 + F(P)2 + G(P) + H 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 Watts Bar - Unit 2 3.3-23 (developmental) A

ESFAS Instrumentation 3.3.2 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 A.1 Enter the Condition Immediately one or more required referenced in channels or trains Table 3.3.2-1 for the inoperable. channel(s) or train(s).

B. One channel or train B.1 Restore channel or train 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. to OPERABLE status.

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)

Watts Bar - Unit 2 3.3-24 (developmental) A

ESFAS Instrumentation 3.3.2 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

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)

Watts Bar - Unit 2 3.3-25 (developmental) A

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One Containment Pressure E.1 -------------NOTE------------

channel inoperable. 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 F.1 Restore channel or train 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable. to OPERABLE status.

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)

Watts Bar - Unit 2 3.3-26 (developmental) A

ESFAS Instrumentation 3.3.2 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

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)

Watts Bar - Unit 2 3.3-27 (developmental) A

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. One Steam Generator I.1 -------------NOTE------------

Water Level - High High One channel may be channel inoperable. 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 J.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Main Feedwater Pump trip OPERABLE status.

channel(s) inoperable.

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)

Watts Bar - Unit 2 3.3-28 (developmental) B

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. One P-11 interlock channel L.1 Verify interlock is in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. required state for existing unit condition.

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

Water Level - Low-Low One channel may be bypassed for channel inoperable. 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 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months protection set, set the Trip Time Delay (Ts) to match the Trip Time Delay (Tm).

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)

Watts Bar - Unit 2 3.3-29 (developmental) A

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. One Vessel T channel --------------------NOTE-------------------

inoperable. 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 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months threshold power level for (Ts) and (Tm) to 0%

power.

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

Level High channel The inoperable channel may be inoperable. 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 Watts Bar - Unit 2 3.3-30 (developmental) A

ESFAS Instrumentation 3.3.2 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)

Watts Bar - Unit 2 3.3-31 (developmental) B

ESFAS Instrumentation 3.3.2 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 18 months K603A, K603B, K604A, K604B, K607A, K607B, K609A, K609B, K612A, K625A, and K625B, 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 Watts Bar - Unit 2 3.3-32 (developmental) A

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 1 of 9)

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

1. Safety Injection

a. Manual Initiation 1, 2, 3, 4 2 B SR 3.3.2.8 NA NA

b. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays SR 3.3.2.7

c. Containment 1, 2, 3 3 D SR 3.3.2.1 1.6 psig 1.5 psig (b) (c)

Pressure - High SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 (a)

d. Pressurizer 1, 2, 3 3 D SR 3.3.2.1 > 1864.8 psig 1870 psig (b) (c)

Pressure - Low SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 (a) (d) (d)

e. Steam Line 1, 2, 3 3 per D SR 3.3.2.1 > 666.6 psig 675 psig (b) (c)

Pressure - Low steam line SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10

2. Containment Spray

a. Manual Initiation 1, 2, 3, 4 2 per train, B SR 3.3.2.8 NA NA 2 trains

b. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

c. Containment 1, 2, 3 4 E SR 3.3.2.1 < 2.9 psig 2.8 psig (b) (c)

Pressure - SR 3.3.2.4 High High 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)

Watts Bar - Unit 2 3.3-33 (developmental) B

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 9)

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

3. Containment Isolation

a. Phase A Isolation (1) Manual 1, 2, 3, 4 2 B SR 3.3.2.8 NA NA Initiation (2) Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic and SR 3.3.2.5 Actuation SR 3.3.2.7 Relays (3) Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Injection

b. Phase B Isolation (1) Manual 1, 2, 3, 4 2 per train, B SR 3.3.2.8 NA NA Initiation 2 trains (2) Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation SR 3.3.2.3 Logic and SR 3.3.2.5 Actuation SR 3.3.2.7 Relays (3) Containment 1, 2, 3 4 E SR 3.3.2.1 < 2.9 psig 2.8 psig (b) (c)

Pressure - SR 3.3.2.4 (b) (c)

High High SR 3.3.2.9 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.

Watts Bar - Unit 2 3.3-34 (developmental) B

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 3 of 9)

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

4. Steam Line Isolation (e) (e)

a. Manual Initiation 1, 2 ,3 1/valve F SR 3.3.2.8 NA NA (e) (e)

b. Automatic 1, 2 ,3 2 trains G SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (e) (e)

c. Containment 1, 2 ,3 4 E SR 3.3.2.1 < 2.9 psig 2.8 psig (b) (c)

Pressure - SR 3.3.2.4 High High SR 3.3.2.9 (b) (c)

SR 3.3.2.10

d. Steam Line Pressure (e) (a)(e) (d) (d)

(1) Low 1, 2 ,3 3 per D SR 3.3.2.1 > 666.6 psig 675 psig (b) (c) steam line SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 (e)(f) (g) (g)

(2) Negative 3 3 per D SR 3.3.2.1 < 108.5 psi 100 psi (b) (c)

Rate - High steam line SR 3.3.2.4 (b) (c)

SR 3.3.2.9 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.

Watts Bar - Unit 2 3.3-35 (developmental) B

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 9)

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

5. Turbine Trip and Feedwater Isolation (h) (h)

a. Automatic 1, 2 ,3 2 trains H SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (h) (h)

b. SG Water Level - 1, 2 ,3 3 per SG I SR 3.3.2.1 < 83.1% 82.4%

(b) (c)

High High (P-14) SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10

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

(h)(i)

d. North MSV Vault 1, 2 3 per O SR 3.3.2.6 < 5.31 inches 4 inches (b) (c)

Room Water vault room SR 3.3.2.9 Level - High (h)(i)

e. South MSV Vault 1, 2 3 per O SR 3.3.2.6 < 4.56 inches 4 inches (b) (c)

Room Water vault room SR 3.3.2.9 Level - High (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.

Watts Bar - Unit 2 3.3-36 (developmental) B

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 9)

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

6. Auxiliary Feedwater

a. Automatic 1, 2, 3 2 trains G SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

b. SG Water Level 1, 2, 3 3 per SG M SR 3.3.2.1 > 16.4% 17.0%

(b) (c)

- Low Low SR 3.3.2.4 (b) (c)

SR 3.3.2.9 SR 3.3.2.10 Coincident with:

(b) (c)

1) Vessel T 1, 2 3 N SR 3.3.2.4 Vessel T Vessel T (b) (c)

Equivalent to SR 3.3.2.9 variable input variable input power 52.6% RTP 50% RTP 50% RTP With a time 1.01 Ts Ts delay (Ts) if (Note 1, (Note 1, one SG is Page 3.3-40) Page 3.3-40) affected Or A time delay 1.01 Tm Tm (Tm) if two or (Note 1, (Note 1, more SGs Page 3.3-40) Page 3.3-40) are affected OR (b) (c)

2) Vessel T 1, 2 3 N SR 3.3.2.4 Vessel T Vessel T (b) (c) equivalent to SR 3.3.2.9 variable input variable input power 52.6% RTP 50% RTP

> 50% RTP with no time delay (Ts and Tm = 0)

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.

Watts Bar - Unit 2 3.3-37 (developmental) B

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 6 of 9)

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

6. Auxiliary Feedwater (continued)

d. Loss of Offsite 1, 2, 3 4 per bus F Refer to Function 4 of Table 3.3.5-1 for SRs and Power Allowable Values.

(j) (k)

e. Trip of all 1, 2 1 per pump J SR 3.3.2.8 > 48 psig 50 psig (b) (c)

Turbine Driven SR 3.3.2.9 Main Feedwater SR 3.3.2.10 Pumps

f. Auxiliary 1, 2, 3 3 F SR 3.3.2.6 A) > 0.5 psig A) 1.2 psig (b) (c)

Feedwater SR 3.3.2.9 Pumps SR 3.3.2.10 B) > 1.33 psig B) 2.0 psig Train A and B Suction Transfer on Suction Pressure - Low

7. Automatic Switchover to Containment Sump

a. Automatic 1, 2, 3, 4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays

b. Refueling Water 1, 2, 3, 4 4 K SR 3.3.2.1 > 155.6 inches 158 inches (b) (c)

Storage Tank SR 3.3.2.4 from from (RWST) SR 3.3.2.9 (b) (c) Tank Base Tank Base Level - Low SR 3.3.2.10 Coincident with Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Safety Injection And Coincident with 1, 2, 3, 4 4 K SR 3.3.2.1 > 37.2 inches 38.2 inches (b) (c)

Containment SR 3.3.2.4 above above Sump SR 3.3.2.9 (b) (c) el. 702.8 ft el. 702.8 ft Level - High 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.

Watts Bar - Unit 2 3.3-38 (developmental) B

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 8 of 9)

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

8. ESFAS Interlocks

a. Reactor Trip, P-4 1, 2, 3 1 per train, F SR 3.3.2.11 NA NA 2 trains

b. Pressurizer Pressure, P-11 (1) Unblock 1, 2, 3 3 L SR 3.3.2.1 < 1975.2 psig 1970 psig (b) (c)

(Auto Reset SR 3.3.2.4 (b) (c) of SI Block) SR 3.3.2.9 (2) Enable 1, 2, 3 3 L SR 3.3.2.1 > 1956.8 psig 1962 psig (b) (c)

Manual SR 3.3.2.4 (b) (c)

Block of SI SR 3.3.2.9 (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.

Watts Bar - Unit 2 3.3-39 (developmental) B

ESFAS Instrumentation 3.3.2 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:

Ts = A(P)3 + B(P)2 + C(P) + D Tm = EP ( )3 + F(P)2 + G(P) + H 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 Watts Bar - Unit 2 3.3-40 (developmental) A

PAM Instrumentation 3.3.3 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---------------- A.1 Restore required channel 30 days Not applicable to Functions to OPERABLE status.

3, 4, 14, and 16.

One or more Functions with one required channel inoperable.

B. Required Action and B.1 Initiate action in Immediately associated Completion Time accordance with of Condition A not met. Specification 5.9.8.

(continued)

Watts Bar - Unit 2 3.3-41 (developmental) B

PAM Instrumentation 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. C.1 Restore one channel to 7 days OPERABLE status.

One or more Functions with two required channels inoperable.

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

D. Required Action and D.1 Enter the Condition Immediately associated Completion Time referenced in of Condition C not met. Table 3.3.3-1 for the channel.

E. As required by Required E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action D.1 and referenced in Table 3.3.3-1. 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 F.1 Initiate action in Immediately Action D.1 and referenced accordance with in Table 3.3.3-1. Specification 5.9.8.

Watts Bar - Unit 2 3.3-42 (developmental) B

PAM Instrumentation 3.3.3 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 31 days instrumentation channel that is normally energized.

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 Watts Bar - Unit 2 3.3-43 (developmental) B

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 1 of 3)

Post Accident Monitoring Instrumentation APPLICABLE CONDITION MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS / REQUIRED FUNCTION CONDITIONS TRAINS 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 1, 2, 3 1 per loop E Temperature (T-Hot)

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 1, 2, 3 2 E Range)

8) Containment Lower Comp. 1, 2, 3 2 E Atm. Temperature

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 E penetration flow path (d)(i) 2 upper

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

13) RCS Pressurizer Level 1, 2, 3 3 E

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

(continued)

Watts Bar - Unit 2 3.3-44 (developmental) B

PAM Instrumentation 3.3.3 Table 3.3.3-1 (page 2 of 3)

Post Accident Monitoring Instrumentation APPLICABLE CONDITION MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS / REQUIRED FUNCTION CONDITIONS TRAINS ACTION E.1

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

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 1, 2, 3 2 E Margin Monitor (h)

23) Refueling Water Storage Tank Water 1, 2, 3 2 E Level

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

25) Auxiliary Building Passive Sump Level (j) 1, 2, 3 2 E Watts Bar - Unit 2 3.3-45 (developmental) B

PAM Instrumentation 3.3.3 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.

Watts Bar - Unit 2 3.3-46 (developmental) B

Remote Shutdown System 3.3.4 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 A.1 Restore required 30 days Functions inoperable. Function to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Watts Bar - Unit 2 3.3-47 (developmental) A

Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.4.2 Verify each required control circuit and transfer 18 months switch is capable of performing the intended function.

SR 3.3.4.3 -------------------------------NOTE----------------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION for each required 18 months instrumentation channel.

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

Watts Bar - Unit 2 3.3-48 (developmental) B

Remote Shutdown System 3.3.4 Table 3.3.4-1 (page 1 of 1)

Remote Shutdown System Instrumentation and Controls FUNCTION/INSTRUMENT REQUIRED OR CONTROL PARAMETER 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 1 or RCS Wide Range Pressure Indication

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

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 1 per SG and AFW Flow Indication

e. SG Tsat Indication 1 per SG

5. Decay Heat Removal via RHR System

a. RHR Flow Control 1

b. RHR Temperature Indication 1 Watts Bar - Unit 2 3.3-49 (developmental) A

LOP DG Start Instrumentation 3.3.5 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 --------------------NOTE-------------------

one channel per bus Enter applicable Conditions and inoperable. 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OPERABLE status.

B. One or more Functions with B.1 Restore all but one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months two or more channels per channel to OPERABLE bus inoperable. status.

(continued)

Watts Bar - Unit 2 3.3-50 (developmental) A

LOP DG Start Instrumentation 3.3.5 ACTIONS continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Enter applicable Immediately associated Completion Condition(s) and Time not met. Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.

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 Watts Bar - Unit 2 3.3-51 (developmental) A

LOP DG Start Instrumentation 3.3.5 Table 3.3.5-1 (page 1 of 1)

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

1. 6.9 kV Emergency Bus Undervoltage (Loss of Voltage)

a. Bus Undervoltage 3 SR 3.3.5.1 5994 V and 5967.6 V SR 3.3.5.2 6006 V

b. Time Delay 2 SR 3.3.5.3 0.73 sec and 0.58 sec and 0.77 sec 0.94 sec

2. 6.9 kV Emergency Bus Undervoltage (Degraded Voltage)

a. Bus Undervoltage 3 SR 3.3.5.1 6593.4 V and 6570 V SR 3.3.5.2 6606.6 V

b. Time Delay 2 SR 3.3.5.3 9.73 sec and 9.42 sec and 10.27 sec 10.49 sec

3. Diesel Generator Start 2 SR 3.3.5.1 4733.4 V and 2295.6 V with SR 3.3.5.2 4926.6 V with an internal time an internal time delay of delay of 0.56 sec at 0.46 sec and zero volts 0.54 sec

4. Load Shed 4 SR 3.3.5.1 4733.4 V and 2295.6 V with SR 3.3.5.2 4926.6 V with an internal time an internal time delay of delay of 3.3 sec at zero 2.79 sec and volts.

3 21 sec Watts Bar - Unit 2 3.3-52 (developmental) A

Containment Vent Isolation Instrumentation 3.3.6 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 A.1 Restore the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months channel inoperable. channel to OPERABLE status.

(continued)

Watts Bar - Unit 2 3.3-53 (developmental) A

Containment Vent Isolation Instrumentation 3.3.6 ACTIONS (continued)

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

Only applicable in MODE 1, One train of automatic actuation 2, 3, or 4. 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 One or more Functions with Surveillance testing provided the one or more manual or other train is OPERABLE.

automatic actuation trains -----------------------------------------------

inoperable.

B.1 Enter applicable Immediately OR Conditions and Required Actions of LCO 3.6.3, Two radiation monitoring "Containment Isolation channels inoperable. Valves," for containment purge and exhaust OR isolation valves made Required Action and inoperable by isolation associated Completion instrumentation.

Time of Condition A not met.

(continued)

Watts Bar - Unit 2 3.3-54 (developmental) A

Containment Vent Isolation Instrumentation 3.3.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. --------------NOTE-------------- C.1 Place and maintain Immediately Only applicable during containment purge and movement of irradiated fuel exhaust valves in closed assemblies within position.

containment.

OR One or more Functions with C.2 Enter applicable Immediately one or more manual or Conditions and Required automatic actuation trains Actions of LCO 3.9.4, inoperable. "Containment Penetrations," for OR containment purge and exhaust isolation valves Two radiation monitoring made inoperable by channels inoperable. isolation instrumentation.

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

Watts Bar - Unit 2 3.3-55 (developmental) A

Containment Vent Isolation Instrumentation 3.3.6 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)

Watts Bar - Unit 2 3.3-56 (developmental) B

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

Containment Vent Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)

Containment Vent Isolation Instrumentation REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 2 SR 3.3.6.6 NA

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

3. Containment Purge 2 SR 3.3.6.1 8.41E-02 Ci/cc(a)

Exhaust Radiation Monitors SR 3.3.6.4 (3.43x104 cpm)

SR 3.3.6.7 < 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.

Watts Bar - Unit 2 3.3-58 (developmental) B

CREVS Actuation Instrumentation 3.3.7 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 A.1 Place one CREVS train in 7 days one channel or train emergency radiation inoperable. protection mode.

(continued)

Watts Bar - Unit 2 3.3-59 (developmental) A

CREVS Actuation Instrumentation 3.3.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with B.1.1 Place one CREVS train in Immediately two channels or two trains emergency radiation inoperable. protection mode.

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

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A or B AND not met in MODE 1, 2, 3, or 4. 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 D.1 Suspend movement of Immediately associated Completion irradiated fuel Time for Condition A or B assemblies.

not met during movement of irradiated fuel assemblies.

E. Required Action and E.1 Initiate action to restore Immediately associated Completion one CREVS train to Time for Condition A or B OPERABLE status.

not met in MODE 5 or 6.

Watts Bar - Unit 2 3.3-60 (developmental) A

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

CREVS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page 1 of 1)

CREVS Actuation Instrumentation REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Manual Initiation 2 trains SR 3.3.7.3 NA

2. Control Room Radiation 2 SR 3.3.7.1 9.45E-05 C/cc Control Room Air Intakes SR 3.3.7.2 (3,308 cpm)

SR 3.3.7.4

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

Watts Bar - Unit 2 3.3-62 (developmental) A

ABGTS Actuation Instrumentation 3.3.8 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 A.1 Place one ABGTS train in 7 days one channel or train operation.

inoperable.

B. One or more Functions with B.1.1 Place one ABGTS train in Immediately two channels or two trains operation.

inoperable.

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

Watts Bar - Unit 2 3.3-63 (developmental) A

ABGTS Actuation Instrumentation 3.3.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Place both trains in Immediately emergency radiation protection mode.

C. Required Action and C.1 Suspend movement of Immediately associated Completion irradiated fuel assemblies Time for Condition A or B in the fuel handling area.

not met during movement of irradiated fuel assemblies in the fuel handling area.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A or B AND not met in MODE 1, 2, 3, or 4. 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)

Watts Bar - Unit 2 3.3-64 (developmental) A

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

ABGTS Actuation Instrumentation 3.3.8 Table 3.3.8-1 (page 1 of 1)

ABGTS Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS 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 (a) 2 SR 3.3.8.1 1161 mR/hr Radiation Monitors SR 3.3.8.2 SR 3.3.8.4

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

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

Watts Bar - Unit 2 3.3-66 (developmental) A

ML100550451

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