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)
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Text

Point Beach Nuclear Plant, Units 1 and 2 NRC 2022-0007 Docket Nos. 50-266 and 50-301 Attachment 2 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)

INSERT new Completion Time Completion Times Example 1.3-8 from next 2 pages. 1.3 1.3 Completion Times IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.

Point Beach 1.3-13 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

INSERT these next pages (2) before "Immediate Completion Time" definition.

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RPS Instrumentation 3.3.1 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. [OR ACTIONS In accordance with the Risk Informed Completion Time Program]

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

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table required channels or 3.3.1-1 for the trains inoperable. channel(s) or train(s).

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

OR B.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> C. One Manual Reactor Trip C.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> channel inoperable. OPERABLE status.

OR C.2 Open reactor trip 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> breakers (RTBs).

(continued)

Point Beach 3.3.1-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

[OR RPSwith In accordance Instrumentation the Risk Informed Completion Time3.3.1 Program]

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One channel inoperable. D.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR D.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> E. One channel inoperable. E.1 Place channel in trip. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OR E.2 Reduce THERMAL 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> POWER to < P-7.

F. One Intermediate Range F.1 Reduce THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Neutron Flux channel POWER to < P-6.

inoperable.

OR F.2 Increase THERMAL 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> POWER to > P-10.

G. Two Intermediate Range G.1 Suspend operations Immediately Neutron Flux channels involving positive inoperable. reactivity additions.

AND G.2 Reduce THERMAL 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> POWER to < P-6.

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

(continued)

Point Beach 3.3.1-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

RPS Instrumentation 3.3.1

[OR ACTIONS (continued) In accordance with the Risk CONDITION REQUIRED ACTION COMPLETION Informed Completion TimeTIME Program]

I. Two Source Range I.1 Open RTBs. Immediately Neutron Flux channels inoperable.

J. One Source Range J.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Neutron Flux channel OPERABLE status.

inoperable.

OR J.2 Open RTBs. 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> K. One channel inoperable. K.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OR K.2 Reduce THERMAL 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> POWER to < P-7.

L. One Reactor Coolant L.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Flow-Low (Single Loop) channel inoperable. OR L.2 Reduce THERMAL 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> POWER to < P-8.

M. One Reactor Coolant M.1 Restore channel to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Pump Breaker Position OPERABLE status.

(Single Loop) channel inoperable. OR M.2 Reduce THERMAL 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> POWER to < P-8.

(continued)

Point Beach 3.3.1-3 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

[OR RPS Instrumentation 3.3.1 In accordance with the Risk Informed Completion Time Program]

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. One inoperable channel. N.1 Restore channel to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OPERABLE status.

OR N.2 Reduce THERMAL 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> POWER to < P-7.

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

OR O.2 Reduce THERMAL 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> POWER to < P-9.

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

OR P.2 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)

Point Beach 3.3.1-4 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

[OR RPS Instrumentation 3.3.1 In accordance with the Risk Informed Completion Time Program]

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

OR Q.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> R. One or more channel(s) R.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit conditions.

OR R.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> S. One or more channel(s) S.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit conditions.

OR S.2 Be in MODE 2. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> T. One RTB or trip T.1 Restore RTB or RTB 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> mechanism for one RTB trip mechanism to inoperable. OPERABLE status.

OR T.2 Open RTBs. 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> (continued)

Point Beach 3.3.1-5 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

[OR RPS Instrumentation 3.3.1 In accordance with the Risk Informed Completion Time Program]

ACTIONS (continued)

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

OR U.2 Be in MODE 3. 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> V. One reactor trip bypass V.1 Restore RTBB or RTBB 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> breaker (RTBB) or trip trip mechanism to mechanism for one OPERABLE status.

RTBB inoperable.

OR V.2 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> W. One reactor trip bypass W.1 Restore RTBB or RTBB 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> breaker (RTBB) or trip trip mechanism to mechanism for one OPERABLE status.

RTBB inoperable.

OR W.2 Open RTBs and 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> RTBBs.

X. One train inoperable. X.1 Restore train to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> OPERABLE status.

OR X.2 Open RTBs. 49 hours5.671296e-4 days <br />0.0136 hours <br />8.101852e-5 weeks <br />1.86445e-5 months <br /> INSERT NEXT PAGE Point Beach 3.3.1-6 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206

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

Z. Required Action and Z.1 Reduce THERMAL associated Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> POWER to < P-7.

Condition E, K or N not met.

AA. Required Action and AA.1 Reduce THERMAL associated Completion Time 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> POWER to < P-8.

of Condition L or M not met.

BB. Required Action and BB.1 Reduce THERMAL associated Completion Time 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> POWER to < P-9.

of Condition O not met.

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

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 8)

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

1. Manual 1,2 2 B SR 3.3.1.13 NA NA Reactor Trip 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 3.3.1.1 108% RTP 106% RTP SR 3.3.1.2 (m)

SR 3.3.1.7 (m)

SR 3.3.1.11

b. Low 1 (b) ,2 4 D SR 3.3.1.1 (m) 27% RTP 20% RTP SR 3.3.1.8 SR 3.3.1.11 (m)
3. Intermediate 1 (b) , 2 (c) 2 F,G SR 3.3.1.1 (m) 43% RTP 25% RTP Range Neutron SR 3.3.1.8 (m)

Flux SR 3.3.1.11

4. Source Range 2(d) 2 H,I SR 3.3.1.1(m) < 3.0 E5 cps 1.5 E5 cps Neutron Flux SR 3.3.1.8 (m)

SR 3.3.1.11 3(a), 4(a), 5(a) 2 I,J SR 3.3.1.1(m) < 3.0 E5 cps 1.5 E5 cps SR 3.3.1.7 SR 3.3.1.11(m)

5. Overtemperature 1,2 4 D SR 3.3.1.1 Refer to Note 1 Refer to Note 1 T SR 3.3.1.3 (Page 3.3.1-18) (Page 3.3.1-18)

SR 3.3.1.6(m)

SR 3.3.1.7 (m)

SR 3.3.1.11

6. Overpower T 1,2 4 D SR 3.3.1.1(m) Refer to Note 2 Refer to Note 2 SR 3.3.1.7 (Page 3.3.1-19) (Page 3.3.1-19)

SR 3.3.1.11(m)

(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 Point Beach 3.3.1-13 Unit 1 - Amendment No. 239 Unit 2 - Amendment No. 243

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

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 8)

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

7. Pressurizer Pressure
a. Low 1(e) 4 K SR 3.3.1.1(m) > 1860 psig 1925 psig SR 3.3.1.7 SR 3.3.1.11(m)
b. High 1,2 3 D SR 3.3.1.1(m) < 2380 psig 2365 psig SR 3.3.1.7 SR 3.3.1.11(m)
8. Pressurizer 1(e) 3 K SR 3.3.1.1(m) 85% 80%

Water Level SR 3.3.1.7 High SR 3.3.1.11(m)

9. Reactor Coolant Flow-Low
a. Single Loop 1(f) 3 per loop L SR 3.3.1.1(m) 91% 93%

SR 3.3.1.7 SR 3.3.1.11(m)

b. Two Loops 1(g) 3 per loop K SR 3.3.1.1(m) 91% 93%

SR 3.3.1.7 (m)

SR 3.3.1.11

10. Reactor Coolant Pump (RCP)

Breaker Position

a. Single Loop 1(f) 1 per RCP M SR 3.3.1.13 NA NA
b. Two Loops 1(g) 1 per RCP N SR 3.3.1.13 NA NA
11. Undervoltage 1(e) 2 per bus K SR 3.3.1.9 (m) 3120 V 3170 V Bus A01 & A02 SR 3.3.1.10 (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 Point Beach 3.3.1-14 Unit 1 - Amendment No. 239 Unit 2 - Amendment No. 243

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

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 8)

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

12. Underfrequency 1(e) 2 per bus E SR 3.3.1.10(m) 55.0 Hz 57 Hz Bus A01 & A02
13. Steam Generator 1,2 3 per SG D SR 3.3.1.1(m) 29.5% 31%

(SG) SR 3.3.1.7 Water Level SR 3.3.1.11(m)

Low Low

14. SG Water 1,2 2 per SG D SR 3.3.1.1(m) > 11% 31%

Level Low SR 3.3.1.7 SR 3.3.1.11(m)

Coincident with 1,2 2 per SG D SR 3.3.1.1(m) 1 E6 lbm/hr 0.8 E6 lbm/hr Steam SR 3.3.1.7 Flow/Feedwater SR 3.3.1.11(m)

Flow Mismatch

15. Turbine Trip
a. Low 1(j) 3 O SR 3.3.1.14 NA NA Autostop Oil Pressure
b. Turbine 1(j) 2 O SR 3.3.1.14 NA NA Stop Valve Closure
16. Safety Injection 1,2 2 trains P SR 3.3.1.13 NA NA (SI) Input from Engineered Safety Feature Actuation System (ESFAS)

(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 Point Beach 3.3.1-15 Unit 1 - Amendment No. 239 Unit 2 - Amendment No. 243

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

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 8)

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

17. Reactor Trip System Interlocks
a. Intermediate 2(d) 2 R SR 3.3.1.11 > 4E-11 amp 1E-10 amp Range Neutron SR 3.3.1.12 Flux, P-6
b. Low Power Reactor Trips Block, P-7 (1) Power 1 4 S SR 3.3.1.11 < 13% RTP 10% RTP Range SR 3.3.1.12 Neutron Flux (2) Turbine First 1 2 S SR 3.3.1.11 < 12.8% 10% turbine power Stage SR 3.3.1.12 turbine power Pressure
c. Power Range 1 4 S SR 3.3.1.11 < 38% RTP 35% RTP Neutron Flux, P-8 SR 3.3.1.12
d. Power Range 1(k) 4 S SR 3.3.1.11 (h) (i)

Neutron Flux, P-9 SR 3.3.1.12

e. Power Range 1,2 4 R SR 3.3.1.11 > 6% RTP and 9% RTP Neutron Flux, P-10 SR 3.3.1.12 < 12% RTP
18. Reactor Trip 1,2 2 trains Q SR 3.3.1.4 NA NA Breakers (RTBs) 3(a), 4(a), 5(a) 2 trains T SR 3.3.1.4 NA NA
19. Reactor Trip Breaker 1,2 1 each per U SR 3.3.1.4 NA NA Undervoltage and Shunt RTB Trip Mechanisms 3(a), 4(a), 5(a) 1 each per T SR 3.3.1.4 NA NA RTB (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.

Point Beach 3.3.1-16 Unit 1 - Amendment No. 239 Unit 2 - Amendment No. 243

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