ML22140A134

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Attachment 2 - Proposed Technical Specification Changes (Mark-Up)
ML22140A134
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/20/2022
From:
Point Beach
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22140A131 List:
References
NRC 2022-0007
Download: ML22140A134 (15)
v • d • e


Text

Point Beach Nuclear Plant, Units 1 and 2 NRC 2022-0007 Docket Nos. 50-266 and 50-301 Page 12 of 136 ATTACHMENT 2 Point Beach Units 1 and 2 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b Proposed Technical Specification Changes (Mark-Up)

(45 pages follow)

Completion Times 1.3 1.3 Completion Times Point Beach 1.3-13 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.

INSERT new Completion Time Example 1.3-8 from next 2 pages.

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RPS Instrumentation 3.3.1 Point Beach 3.3.1-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1 The RPS 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 or trains inoperable.

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

Immediately B.

One Manual Reactor Trip channel inoperable.

B.1 Restore channel to OPERABLE status.

OR B.2 Be in MODE 3.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 54 hours C. One Manual Reactor Trip channel inoperable.

C.1 Restore channel to OPERABLE status.

OR C.2 Open reactor trip breakers (RTBs).

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 49 hours (continued)

[OR In accordance with the Risk Informed Completion Time Program]

RPS Instrumentation 3.3.1 Point Beach 3.3.1-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One channel inoperable.

D.1 Place channel in trip.

OR D.2 Be in MODE 3.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours E.

One channel inoperable.

E.1 Place channel in trip.

OR E.2 Reduce THERMAL POWER to < P-7.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours F.

One Intermediate Range Neutron Flux channel inoperable.

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

OR F.2 Increase THERMAL POWER to > P-10.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours G. Two Intermediate Range Neutron Flux channels inoperable.

G.1 Suspend operations involving positive reactivity additions.

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

Immediately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> H. One Source Range Neutron Flux channel inoperable.

H.1 Suspend operations involving positive reactivity additions.

Immediately (continued)

[OR In accordance with the Risk Informed Completion Time Program]

RPS Instrumentation 3.3.1 Point Beach 3.3.1-3 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I.

Two Source Range Neutron Flux channels inoperable.

I.1 Open RTBs.

Immediately J.

One Source Range Neutron Flux channel inoperable.

J.1 Restore channel to OPERABLE status.

OR J.2 Open RTBs.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 49 hours K.

One channel inoperable.

K.1 Place channel in trip.

OR K.2 Reduce THERMAL POWER to < P-7.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours L.

One Reactor Coolant Flow-Low (Single Loop) channel inoperable.

L.1 Place channel in trip.

OR L.2 Reduce THERMAL POWER to < P-8.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 hours M. One Reactor Coolant Pump Breaker Position (Single Loop) channel inoperable.

M.1 Restore channel to OPERABLE status.

OR M.2 Reduce THERMAL POWER to < P-8.

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

[OR In accordance with the Risk Informed Completion Time Program]

RPS Instrumentation 3.3.1 Point Beach 3.3.1-4 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. One inoperable channel.

N.1 Restore channel to OPERABLE status.

OR N.2 Reduce THERMAL POWER to < P-7.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours O. One turbine trip channel inoperable.

O.1 Place channel in trip.

OR O.2 Reduce THERMAL POWER to < P-9.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 5 hours P.

One train inoperable.

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

One train may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing provided the other train is OPERABLE.

P.1 Restore train to OPERABLE status.

OR P.2 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours (continued)

[OR In accordance with the Risk Informed Completion Time Program]

RPS Instrumentation 3.3.1 Point Beach 3.3.1-5 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Q. One RTB inoperable.

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

One RTB may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided the other RTB is OPERABLE.

Q.1 Restore RTB to OPERABLE status.

OR Q.2 Be in MODE 3.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours R. One or more channel(s) inoperable.

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

OR R.2 Be in MODE 3.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours S.

One or more channel(s) inoperable.

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

OR S.2 Be in MODE 2.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours T.

One RTB or trip mechanism for one RTB inoperable.

T.1 Restore RTB or RTB trip mechanism to OPERABLE status.

OR T.2 Open RTBs.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 49 hours (continued)

[OR In accordance with the Risk Informed Completion Time Program]

RPS Instrumentation 3.3.1 Point Beach 3.3.1-6 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS (continued)

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

U.1 Restore inoperable trip mechanism to OPERABLE status.

OR U.2 Be in MODE 3.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 54 hours V.

One reactor trip bypass breaker (RTBB) or trip mechanism for one RTBB inoperable.

V.1 Restore RTBB or RTBB trip mechanism to OPERABLE status.

OR V.2 Be in MODE 3.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7 hours W. One reactor trip bypass breaker (RTBB) or trip mechanism for one RTBB inoperable.

W.1 Restore RTBB or RTBB trip mechanism to OPERABLE status.

OR W.2 Open RTBs and RTBBs.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 49 hours X.

One train inoperable.

X.1 Restore train to OPERABLE status.

OR X.2 Open RTBs.

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 49 hours INSERT NEXT PAGE

[OR In accordance with the Risk Informed Completion Time Program]

INSERT - Section 3.3.1, RPS Instrumentation ACTIONS Y. Required Action and associated Completion Time of Condition B, D, P, Q, or U not met.

Y.1 Be in MODE 3 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Z. Required Action and associated Completion Time of Condition E, K or N not met.

Z.1 Reduce THERMAL POWER to < P-7.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> AA. Required Action and associated Completion Time of Condition L or M not met.

AA.1 Reduce THERMAL POWER to < P-8.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> BB. Required Action and associated Completion Time of Condition O not met.

BB.1 Reduce THERMAL POWER to < P-9.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

RPS Instrumentation 3.3.1 Point Beach 3.3.1-13 Unit 1 - Amendment No. 239 Unit 2 - Amendment No. 243 Table 3.3.1-1 (page 1 of 8)

Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

1.

Manual Reactor Trip 1,2 3(a), 4(a), 5(a) 2 2

B C

SR 3.3.1.13 SR 3.3.1.13 NA NA NA NA

2.

Power Range Neutron Flux

a.

High

b.

Low 1,2 1(b),2 4

4 D

D SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7(m)

SR 3.3.1.11(m)

SR 3.3.1.1 SR 3.3.1.8(m)

SR 3.3.1.11(m) 108% RTP 27% RTP 106% RTP 20% RTP

3.

Intermediate Range Neutron Flux 1(b), 2(c) 2 F,G SR 3.3.1.1 SR 3.3.1.8(m)

SR 3.3.1.11(m) 43% RTP 25% RTP

4.

Source Range Neutron Flux 2(d) 3(a), 4(a), 5(a) 2 2

H,I I,J SR 3.3.1.1 SR 3.3.1.8(m)

SR 3.3.1.11(m)

SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m)

< 3.0 E5 cps

< 3.0 E5 cps 1.5 E5 cps 1.5 E5 cps

5.

Overtemperature T

1,2 4

D SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7(m)

SR 3.3.1.11(m)

Refer to Note 1 (Page 3.3.1-18)

Refer to Note 1 (Page 3.3.1-18)

6.

Overpower T 1,2 4

D SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m)

Refer to Note 2 (Page 3.3.1-19)

Refer to Note 2 (Page 3.3.1-19)

(continued)

(a)

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

(b)

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

(c)

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

(d)

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

(m)

Table 3.3.1-1 Notes 3 and 4 are applicable Page is for information only. No changes proposed on this page.

RPS Instrumentation 3.3.1 Point Beach 3.3.1-14 Unit 1 - Amendment No. 239 Unit 2 - Amendment No. 243 Table 3.3.1-1 (page 2 of 8)

Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

7.

Pressurizer Pressure

a.

Low

b.

High 1(e) 1,2 4

3 K

D SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m)

SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m)

> 1860 psig

< 2380 psig 1925 psig 2365 psig

8.

Pressurizer Water Level High 1(e) 3 K

SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m) 85%

80%

9.

Reactor Coolant Flow-Low

a.

Single Loop

b.

Two Loops 1(f) 1(g) 3 per loop 3 per loop L

K SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m)

SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m) 91%

91%

93%

93%

10.

Reactor Coolant Pump (RCP)

Breaker Position

a.

Single Loop

b.

Two Loops 1(f) 1(g) 1 per RCP 1 per RCP M

N SR 3.3.1.13 SR 3.3.1.13 NA NA NA NA

11.

Undervoltage Bus A01 & A02 1(e) 2 per bus K

SR 3.3.1.9 SR 3.3.1.10(m) 3120 V 3170 V (continued)

(e)

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

(f)

Above the P-8 (Power Range Neutron Flux) interlock.

(g)

Above the P-7 (Low Power Reactor Trips Block) interlock and below the P-8 (Power Range Neutron Flux) interlock.

(m)

Table 3.3.1-1 Notes 3 and 4 are applicable Page is for information only. No changes proposed on this page.

RPS Instrumentation 3.3.1 Point Beach 3.3.1-15 Unit 1 - Amendment No. 239 Unit 2 - Amendment No. 243 Table 3.3.1-1 (page 3 of 8)

Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

12.

Underfrequency Bus A01 & A02 1(e) 2 per bus E

SR 3.3.1.10(m) 55.0 Hz 57 Hz

13.

Steam Generator (SG)

Water Level Low Low 1,2 3 per SG D

SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m) 29.5%

31%

14.

SG Water Level Low Coincident with Steam Flow/Feedwater Flow Mismatch 1,2 1,2 2 per SG 2 per SG D

D SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m)

SR 3.3.1.1 SR 3.3.1.7(m)

SR 3.3.1.11(m)

> 11%

1 E6 lbm/hr 31%

0.8 E6 lbm/hr

15.

Turbine Trip

a.

Low Autostop Oil Pressure

b.

Turbine Stop Valve Closure 1(j) 1(j) 3 2

O O

SR 3.3.1.14 SR 3.3.1.14 NA NA NA NA

16.

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

SR 3.3.1.13 NA NA (continued)

(e)

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

(j)

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

(m)

Table 3.3.1-1 Notes 3 and 4 are applicable Page is for information only. No changes proposed on this page.

RPS Instrumentation 3.3.1 Point Beach 3.3.1-16 Unit 1 - Amendment No. 239 Unit 2 - Amendment No. 243 Table 3.3.1-1 (page 4 of 8)

Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE NOMINAL TRIP SETPOINT

17.

Reactor Trip System Interlocks

a.

Intermediate Range Neutron Flux, P-6

b.

Low Power Reactor Trips Block, P-7 (1)

Power Range Neutron Flux (2)

Turbine First Stage Pressure

c.

Power Range Neutron Flux, P-8

d.

Power Range Neutron Flux, P-9

e.

Power Range Neutron Flux, P-10 2(d) 1 1

1 1(k) 1,2 2

4 2

4 4

4 R

S S

S S

R SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.11 SR 3.3.1.12

> 4E-11 amp

< 13% RTP

< 12.8%

turbine power

< 38% RTP (h)

> 6% RTP and

< 12% RTP 1E-10 amp 10% RTP 10% turbine power 35% RTP (i) 9% RTP

18.

Reactor Trip Breakers (RTBs) 1,2 3(a), 4(a), 5(a) 2 trains 2 trains Q

T SR 3.3.1.4 SR 3.3.1.4 NA NA NA NA

19.

Reactor Trip Breaker Undervoltage and Shunt Trip Mechanisms 1,2 3(a), 4(a), 5(a) 1 each per RTB 1 each per RTB U

T SR 3.3.1.4 SR 3.3.1.4 NA NA NA NA (continued)

(a)

With the RTBs closed and the Rod Control System capable of rod withdrawal.

(d)

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

(h)

< 38% RTP for full design power Tavg < 572°F or < 53% RTP for full design power Tavg > 572°F. For EOC coastdown, P-9 is not reset if Tavg decreases to < 572°F.

(i) 35% RTP for full design power Tavg < 572°F or 50% RTP for full design power Tavg > 572°F. For EOC coastdown, P-9 is not reset if Tavg decreases to < 572°F.

(k)

With 1 of 2 circulating water pump breakers closed and condenser vacuum 22 Hg.

Page is for information only. No changes proposed on this page.

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