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{{#Wiki_filter:file:///Gl/...Proposed/Written%20Exam/written%20exam%20references/RO%20Provided%20to%20examinees/Steam%20Table%20Mollier.txt[1/4/2013 8:22:36 AM]
{{#Wiki_filter:file:///Gl/...Proposed/Written%20Exam/written%20exam%20references/RO%20Provided%20to%20examinees/Steam%20Table%20Mollier.txt[1/4/2013 8:22:36 AM]
POINT BEACH NUCLEAR PLANT                                     EOP-3 UNIT 1 EMERGENCY OPERATING PROCEDURE                                  SAFETY RELATED Revision 4 3 11/2011 STEAM GENERATOR TUBE RUPTURE                                  Page 28 of 44 lsTEPI        ACTION/EXPECTED RESPONSE I I      RESPONSE NOT OBTAINED I
 
POINT BEACH NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE
* 37 Control RCS Pressure And Charging Flow To Minimize RCS To S/G Leakage:
: a. Perform appropriate action(s) from table:
RUPTURED S/G LEVEL PZR LEVEL RISING LOWERING OFF SCALE HIGH LESS THAN 0 Raise charging Raise charging 0 Raise charging OR EQUAL TO flow flow flow
[ 4 4 % ] 24%
0 Depressurize 0 Maintain RCS and RCS using ruptured S/G Step 38 pressures equal BETWEEN Depressurize Turn on Maintain RCS and
[44%] 24%
RCS using PZR heaters ruptured S/G AND 50%
Step 38 pressures equal BETWEEN 0 Depressurize Turn on Maintain RCS and 50% AND RCS using PZR heaters ruptured S/G
[60%1 68%
Step 38 pressures equal 0 Reduce charging flow GREATER THAN Reduce Turn on PZR Maintain RCS and OR EQUAL TO charging flow heaters ruptured S/G
[60%] 68%
pressures equal STEAM GENERATOR TUBE RUPTURE EOP-3 UNIT 1 SAFETY RELATED Revision 43 11/2011 Page 28 of 44 lsTEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I
I I
CAUTION RCS and ruptured S/G pressures must be maintained less than 1050 psig.
CAUTION RCS and ruptured S/G pressures must be maintained less than 1050 psig.
I'                                                                                   " I
I'  
* 37 Control RCS Pressure And Charging                                                  *
" I  
* Flow To Minimize RCS To S/G Leakage:                                          *
 
* a. Perform appropriate action(s)                                              *
MFIVs, MFRVs, and MFRV Bypass Valves 3.7.3 Point Beach 3.7.3-1 Unit 1 - Amendment No. 241 Unit 2 - Amendment No. 245 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves LCO 3.7.3 Main Feedwater Isolation shall be OPERABLE.
* from table:                                                              *
APPLICABILITY:
* RUPTURED S/G LEVEL                                *
MODES 1, 2, and 3.
* PZR LEVEL                                                                            *
ACTIONS  
* RISING        LOWERING      OFF SCALE HIGH                *
* LESS THAN          0 Raise charging Raise charging Raise charging 0                                *
* OR EQUAL TO          flow            flow            flow                          *
* [ 4 4 % ] 24%                                                                        *
* 0 Depressurize                  0 Maintain RCS and              *
* RCS using                        ruptured S/G                  *
* Step 3 8                        pressures equal                *
* BETWEEN          Depressurize    Turn on          Maintain RCS and              *
*    [ 4 4 % ] 24%      RCS using      PZR heaters      ruptured S/G                  *
* AND 50%          Step 3 8                        pressures equal                *
* BETWEEN        0 Depressurize    Turn on          Maintain RCS and              *
* 50% AND          RCS using      PZR heaters      ruptured S/G                  *
*    [60%1 6 8 %        Step 3 8                        pressures equal                *
* 0 Reduce                                                          *
* charging flow                                                  *
* GREATER THAN Reduce                  Turn on PZR      Maintain RCS and              *
* OR EQUAL TO          charging flow heaters            ruptured S/G                  *
* [60%] 68%                                              pressures equal
* MFIVs, MFRVs, and MFRV Bypass Valves 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves LCO 3.7.3               Main Feedwater Isolation shall be OPERABLE.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS
--------------------------------------------------NOTE-----------------------------------------------------
--------------------------------------------------NOTE-----------------------------------------------------
Separate Condition entry is allowed for each valve.
Separate Condition entry is allowed for each valve.
CONDITION                             REQUIRED ACTION                     COMPLETION TIME A. One or more MFIVs                     A.1         Close or isolate MFIV.          72 hours inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
AND A.2         Verify MFIV is closed or Once per isolated.                        7 days B. One or more MFRVs                     B.1         Close or isolate MFRV.          72 hours inoperable.
One or more MFIVs inoperable.
AND B.2         Verify MFRV is closed           Once per or isolated.                     7 days C. One or more MFRV                     C.1       Close or isolate MFRV             72 hours Bypass Valves                                Bypass Valve inoperable.
A.1 Close or isolate MFIV.
AND C.2       Verify MFRV Bypass               Once per 7 days Valve is closed or isolated Point Beach                                        3.7.3-1                  Unit 1 - Amendment No. 241 Unit 2 - Amendment No. 245
AND A.2 Verify MFIV is closed or isolated.
72 hours Once per 7 days B.
One or more MFRVs inoperable.
B.1 Close or isolate MFRV.
AND B.2 Verify MFRV is closed or isolated.
72 hours Once per 7 days C. One or more MFRV Bypass Valves inoperable.
C.1 Close or isolate MFRV Bypass Valve AND C.2 Verify MFRV Bypass Valve is closed or isolated 72 hours Once per 7 days


MFIVs, MFRVs, and MFRV Bypass Valves 3.7.3 ACTIONS (continued)
MFIVs, MFRVs, and MFRV Bypass Valves 3.7.3 Point Beach 3.7.3-2 Unit 1 - Amendment No. 241 Unit 2 - Amendment No. 245 ACTIONS (continued)
CONDITION                     REQUIRED ACTION               COMPLETION TIME D. Two valves in the same       D.1     Isolate affected flow       8 hours flowpath inoperable.                path E. Required Action and           E.1     Be in MODE 3.               6 hours associated Completion Time not met.              AND E.2     Be in MODE 4.               12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE                                     FREQUENCY SR 3.7.3.1       Verify each MFIV, MFRV, and MFRV bypass               18 months valve, actuate to the isolation position on an actual or simulated actuation signal.
CONDITION REQUIRED ACTION COMPLETION TIME D. Two valves in the same flowpath inoperable.
SR 3.7.3.2       Verify each MFIV, MFRV, and MFRV Bypass               In accordance Valve isolation time is within limits.                 with the Inservice Testing Program Point Beach                              3.7.3-2            Unit 1 - Amendment No. 241 Unit 2 - Amendment No. 245
D.1 Isolate affected flow path 8 hours E.
Required Action and associated Completion Time not met.
E.1 Be in MODE 3.
AND E.2 Be in MODE 4.
6 hours 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify each MFIV, MFRV, and MFRV bypass valve, actuate to the isolation position on an actual or simulated actuation signal.
18 months SR 3.7.3.2 Verify each MFIV, MFRV, and MFRV Bypass Valve isolation time is within limits.
In accordance with the Inservice Testing Program  


Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4               All shutdown and control rods shall be OPERABLE, with individual rod positions within limits.
Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and control rods shall be OPERABLE, with individual rod positions within limits.
APPLICABILITY:           MODES 1 and 2.
APPLICABILITY:
ACTIONS
MODES 1 and 2.
ACTIONS  
----------------------------------------------------NOTE---------------------------------------------------
----------------------------------------------------NOTE---------------------------------------------------
One hour is allowed following rod motion prior to verifying rod operability and group alignment limits.
One hour is allowed following rod motion prior to verifying rod operability and group alignment limits.
CONDITION                               REQUIRED ACTION                             COMPLETION TIME A. One or more rod(s)                 A.1.1     Verify SDM to be within           1 hour inoperable.                                  the limits provided in the COLR.
CONDITION REQUIRED ACTION COMPLETION TIME A.
OR A.1.2     Initiate boration to             1 hour restore SDM to within limit.
One or more rod(s) inoperable.
AND A.2       Be in MODE 3.                     6 hours (continued)
A.1.1 Verify SDM to be within the limits provided in the COLR.
Point Beach                                        3.1.4-1                  Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
OR A.1.2 Initiate boration to restore SDM to within limit.
AND A.2 Be in MODE 3.
1 hour 1 hour 6 hours (continued)  


Rod Group Alignment Limits 3.1.4 ACTIONS (continued)
Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS (continued)
CONDITION               REQUIRED ACTION                       COMPLETION TIME B. One rod not within B.1     Restore rod to within         1 hour alignment limits.          alignment limits.
CONDITION REQUIRED ACTION COMPLETION TIME B.
OR B.2.1.1 Verify SDM to be within       1 hour the limits provided in the COLR.
One rod not within alignment limits.
OR B.2.1.2 Initiate boration to         1 hour restore SDM to within limit.
B.1 Restore rod to within alignment limits.
AND B.2.2   Reduce THERMAL               2 hours POWER to 75% RTP.
OR B.2.1.1 Verify SDM to be within the limits provided in the COLR.
AND B.2.3   Verify SDM to be within       Once per the limits provided in       12 hours the COLR.
OR B.2.1.2 Initiate boration to restore SDM to within limit.
AND B.2.4   Perform SR 3.2.1.1 and       72 hours SR 3.2.1.2.
AND B.2.2 Reduce THERMAL POWER to 75% RTP.
AND B.2.5   Perform SR 3.2.2.1.           72 hours AND (continued)
AND B.2.3 Verify SDM to be within the limits provided in the COLR.
Point Beach                    3.1.4-2              Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
AND B.2.4 Perform SR 3.2.1.1 and SR 3.2.1.2.
AND B.2.5 Perform SR 3.2.2.1.
AND 1 hour 1 hour 1 hour 2 hours Once per 12 hours 72 hours 72 hours (continued)  


Rod Group Alignment Limits 3.1.4 ACTIONS CONDITION                   REQUIRED ACTION                     COMPLETION TIME B.   (continued)             B.2.6 Re-evaluate safety           5 days analyses and confirm results remain valid for duration of operation under these conditions.
Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-3 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.
C. Required Action and     C.1   Be in MODE 3.                 6 hours associated Completion Time of Condition B not met.
(continued)
D. More than one rod not   D.1.1 Verify SDM to be within       1 hour within alignment limit.        the limits provided in the COLR.
B.2.6 Re-evaluate safety analyses and confirm results remain valid for duration of operation under these conditions.
OR D.1.2 Initiate boration to         1 hour restore required SDM to within limit.
5 days C. Required Action and associated Completion Time of Condition B not met.
AND D.2   Be in MODE 3.                 6 hours Point Beach                        3.1.4-3              Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206
C.1 Be in MODE 3.
6 hours D. More than one rod not within alignment limit.
D.1.1 Verify SDM to be within the limits provided in the COLR.
OR D.1.2 Initiate boration to restore required SDM to within limit.
AND D.2 Be in MODE 3.
1 hour 1 hour 6 hours  


Rod Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                 FREQUENCY SR 3.1.4.1 Verify individual rod positions are within the       12 hours following alignment limits:
Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-4 Unit 1 - Amendment No. 212 Unit 2 - Amendment No. 217 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions are within the following alignment limits:
: a.   +/- 18 steps of demanded position (as allowed by Table 3.1.4-1) in MODE 1 > 85 percent RTP when bank demand position is < 215 steps; AND
: a.  
: b.   +/- 24 steps of demanded position (as allowed by Table 3.1.4-2) in MODE 1 > 85 percent RTP when bank demand position is 215 steps; AND
+/- 18 steps of demanded position (as allowed by Table 3.1.4-1) in MODE 1 > 85 percent RTP when bank demand position is < 215 steps; AND
: c.   +/- 24 steps of demanded position in MODE 1 85 percent RTP or in MODE 2.
: b.  
SR 3.1.4.2 Verify rod freedom of movement (trippability) by     92 days moving each rod not fully inserted in the core 10 steps in either direction.
+/- 24 steps of demanded position (as allowed by Table 3.1.4-2) in MODE 1 > 85 percent RTP when bank demand position is 215 steps; AND
SR 3.1.4.3 Verify rod drop time of each rod, from the fully     Prior to reactor withdrawn position, is 2.2 seconds from the         criticality after beginning of decay of stationary gripper coil         each removal of voltage to dashpot entry, with:                       the reactor head
: c.  
: a. T avg  500&deg;F; and
+/- 24 steps of demanded position in MODE 1 85 percent RTP or in MODE 2.
: b. All reactor coolant pumps operating.
12 hours SR 3.1.4.2 Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.
Point Beach                          3.1.4-4            Unit 1 - Amendment No. 212 Unit 2 - Amendment No. 217
92 days SR 3.1.4.3 Verify rod drop time of each rod, from the fully withdrawn position, is 2.2 seconds from the beginning of decay of stationary gripper coil voltage to dashpot entry, with:
: a.
Tavg 500&deg;F; and
: b.
All reactor coolant pumps operating.
Prior to reactor criticality after each removal of the reactor head


Rod Group Alignment Limits 3.1.4 Table 3.1.4-1 N
Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-5 Unit 1 - Amendment No. 212 Unit 2 - Amendment No. 217 Table 3.1.4-1 Allowable Alignment Limits As A Function Of Measured Peaking Factor Margin (FQ(Z), FH N )
Allowable Alignment Limits As A Function Of Measured Peaking Factor Margin (FQ(Z), FH )
At Power Levels > 85% Of Rated Power And Bank D Demand < 215 Steps Withdrawn ALIGNMENT LIMITS (STEPS)*
At Power Levels > 85% Of Rated Power And Bank D Demand < 215 Steps Withdrawn ALIGNMENT LIMITS              REQUIRED MARGIN TO            REQUIRED MARGIN TO N
REQUIRED MARGIN TO FH N LIMIT (%)
(STEPS)*                      FH LIMIT (%)                  FQ(Z) LIMIT (%)
REQUIRED MARGIN TO FQ(Z) LIMIT (%)
12                              0.00                          0.00 13                              0.33                          0.83 14                              0.67                          1.67 15                              1.00                          2.50 16                              1.33                          3.33 17                              1.67                          4.17 18                              2.00                          5.00
12 0.00 0.00 13 0.33 0.83 14 0.67 1.67 15 1.00 2.50 16 1.33 3.33 17 1.67 4.17 18 2.00 5.00
* Between the bank demand position and the RPI System.
Table 3.1.4-2 N
Allowable Alignment Limits As A Function Of Measured Peaking Factor Margin (FQ(Z), FH )
At Power Levels > 85% Of Rated Power And Bank D Demand 215 Steps Withdrawn ALIGNMENT LIMITS               REQUIRED MARGIN TO            REQUIRED MARGIN TO N
(STEPS)*                     FH LIMIT (%)                 FQ(Z) LIMIT (%)
12                               0.00                           0.00 13                               0.33                           0.83 14                               0.67                           1.67 15                               1.00                           2.50 16                               1.33                           3.33 17                               1.67                           4.17 18                               2.00                           5.00 19                              2.33                          5.83 20                              2.67                          6.67 21                              3.00                          7.50 22                              3.33                          8.33 23                              3.67                          9.17 24                              4.00                          10.0
* Between the bank demand position and the RPI System.
* Between the bank demand position and the RPI System.
Point Beach                                        3.1.4-5               Unit 1 - Amendment No. 212 Unit 2 - Amendment No. 217
Table 3.1.4-2 Allowable Alignment Limits As A Function Of Measured Peaking Factor Margin (FQ(Z), FH N )
At Power Levels > 85% Of Rated Power And Bank D Demand 215 Steps Withdrawn ALIGNMENT LIMITS (STEPS)*
REQUIRED MARGIN TO FH N LIMIT (%)
REQUIRED MARGIN TO FQ(Z) LIMIT (%)
12 0.00 0.00 13 0.33 0.83 14 0.67 1.67 15 1.00 2.50 16 1.33 3.33 17 1.67 4.17 18 2.00 5.00 19 2.33 5.83 20 2.67 6.67 21 3.00 7.50 22 3.33 8.33 23 3.67 9.17 24 4.00 10.0
* Between the bank demand position and the RPI System.


POINT BEACH NUCLEAR PLANT                                               CSP-ST.0 UNIT 1 CRITICAL SAFETY PROCEDURe                                               SAFETY RELATED Revision 6 11/2011 CRITICAL SAFETY FUNCTION STATUS TREES                                   Page 8 of 11 FIGURE 3 S T - 3 HEAT S I N K I
POINT BEACH NUCLEAR PLANT CSP-ST.0 UNIT 1 CRITICAL SAFETY PROCEDURe SAFETY RELATED Revision 6 11/2011 CRITICAL SAFETY FUNCTION STATUS TREES Page 8 of 11 FIGURE 3 ST-3 HEAT SINK I
TOTAL         NO FEEDWATER
TOTAL FEEDWATER FLOW TO SIGs GREATER THAN 230 GPM NO YES
                                                            ........Q
........Q GO TO  
                  - FLOW TO SIGs GREATER THAN 230 GPM YES GO TO
--I CSP-H.2 NARROW RANGE LEVEL IN ANY SIG PRESSURE IN BOTH SIGs NO GREATER THAN
* CSP-H.2 NARROW       NO                                        NO PRESSURE IN RANGE LEVEL BOTH SIGs
[51%] 29%
  --IIN ANY SIG LESS THAN GREATER THAN 1105 PSlG
NO YES LESS THAN 1105 PSlG YES me*aaa Q ::;:3 NARROW RANGE LEVEL IN BOTH SlGs LESS THAN [85%] 91 %
[51%] 29%   YES                                     YES me*aaa Q   3:;::
NO YES....o GO CSP-H.4 TO PRESSURE IN BOTH SlGs LESS THAN 1085 PSlG NO YES GO TO 1
NARROW           NO RANGE LEVEL IN BOTH SlGs LESS
1 CSP-H.5 NARROW RANGE LEVEL IN BOTH SGs GREATER THAN [51%] 29%
                                                                      ....o THAN [85%] 91% YES
NO YES}}
* CSP-H.4 GO TO NO PRESSURE IN BOTH SlGs LESS THAN 1085 PSlG YES GO TO 1     1         CSP-H.5 NARROW             NO RANGE LEVEL IN BOTH SGs GREATER THAN [51%] 29%   YES}}

Latest revision as of 11:35, 11 January 2025

2012 Point Beach Nuclear Plant Initial License Examination Proposed Written Exam Handouts
ML13028A066
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 12/17/2012
From:
NRC/RGN-III
To:
Zoia, Charles
Shared Package
ML11354A219 List:
References
Download: ML13028A066 (1)
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Text

file:///Gl/...Proposed/Written%20Exam/written%20exam%20references/RO%20Provided%20to%20examinees/Steam%20Table%20Mollier.txt[1/4/2013 8:22:36 AM]

POINT BEACH NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE

  • 37 Control RCS Pressure And Charging Flow To Minimize RCS To S/G Leakage:
a. Perform appropriate action(s) from table:

RUPTURED S/G LEVEL PZR LEVEL RISING LOWERING OFF SCALE HIGH LESS THAN 0 Raise charging Raise charging 0 Raise charging OR EQUAL TO flow flow flow

[ 4 4 % ] 24%

0 Depressurize 0 Maintain RCS and RCS using ruptured S/G Step 38 pressures equal BETWEEN Depressurize Turn on Maintain RCS and

[44%] 24%

RCS using PZR heaters ruptured S/G AND 50%

Step 38 pressures equal BETWEEN 0 Depressurize Turn on Maintain RCS and 50% AND RCS using PZR heaters ruptured S/G

[60%1 68%

Step 38 pressures equal 0 Reduce charging flow GREATER THAN Reduce Turn on PZR Maintain RCS and OR EQUAL TO charging flow heaters ruptured S/G

[60%] 68%

pressures equal STEAM GENERATOR TUBE RUPTURE EOP-3 UNIT 1 SAFETY RELATED Revision 43 11/2011 Page 28 of 44 lsTEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

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CAUTION RCS and ruptured S/G pressures must be maintained less than 1050 psig.

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MFIVs, MFRVs, and MFRV Bypass Valves 3.7.3 Point Beach 3.7.3-1 Unit 1 - Amendment No. 241 Unit 2 - Amendment No. 245 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs) and MFRV Bypass Valves LCO 3.7.3 Main Feedwater Isolation shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more MFIVs inoperable.

A.1 Close or isolate MFIV.

AND A.2 Verify MFIV is closed or isolated.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days B.

One or more MFRVs inoperable.

B.1 Close or isolate MFRV.

AND B.2 Verify MFRV is closed or isolated.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days C. One or more MFRV Bypass Valves inoperable.

C.1 Close or isolate MFRV Bypass Valve AND C.2 Verify MFRV Bypass Valve is closed or isolated 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Once per 7 days

MFIVs, MFRVs, and MFRV Bypass Valves 3.7.3 Point Beach 3.7.3-2 Unit 1 - Amendment No. 241 Unit 2 - Amendment No. 245 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two valves in the same flowpath inoperable.

D.1 Isolate affected flow path 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> E.

Required Action and associated Completion Time not met.

E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify each MFIV, MFRV, and MFRV bypass valve, actuate to the isolation position on an actual or simulated actuation signal.

18 months SR 3.7.3.2 Verify each MFIV, MFRV, and MFRV Bypass Valve isolation time is within limits.

In accordance with the Inservice Testing Program

Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-1 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and control rods shall be OPERABLE, with individual rod positions within limits.

APPLICABILITY:

MODES 1 and 2.

ACTIONS

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

One hour is allowed following rod motion prior to verifying rod operability and group alignment limits.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more rod(s) inoperable.

A.1.1 Verify SDM to be within the limits provided in the COLR.

OR A.1.2 Initiate boration to restore SDM to within limit.

AND A.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 /> 1 hour 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (continued)

Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-2 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One rod not within alignment limits.

B.1 Restore rod to within alignment limits.

OR B.2.1.1 Verify SDM to be within the limits provided in the COLR.

OR B.2.1.2 Initiate boration to restore SDM to within limit.

AND B.2.2 Reduce THERMAL POWER to 75% RTP.

AND B.2.3 Verify SDM to be within the limits provided in the COLR.

AND B.2.4 Perform SR 3.2.1.1 and SR 3.2.1.2.

AND B.2.5 Perform SR 3.2.2.1.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 2 hours Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)

Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-3 Unit 1 - Amendment No. 201 Unit 2 - Amendment No. 206 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.2.6 Re-evaluate safety analyses and confirm results remain valid for duration of operation under these conditions.

5 days C. Required Action and associated Completion Time of Condition B not met.

C.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 /> D. More than one rod not within alignment limit.

D.1.1 Verify SDM to be within the limits provided in the COLR.

OR D.1.2 Initiate boration to restore required SDM to within limit.

AND 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 /> 1 hour 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-4 Unit 1 - Amendment No. 212 Unit 2 - Amendment No. 217 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions are within the following alignment limits:

a.

+/- 18 steps of demanded position (as allowed by Table 3.1.4-1) in MODE 1 > 85 percent RTP when bank demand position is < 215 steps; AND

b.

+/- 24 steps of demanded position (as allowed by Table 3.1.4-2) in MODE 1 > 85 percent RTP when bank demand position is 215 steps; AND

c.

+/- 24 steps of demanded position in MODE 1 85 percent RTP or in MODE 2.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.1.4.2 Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.

92 days SR 3.1.4.3 Verify rod drop time of each rod, from the fully withdrawn position, is 2.2 seconds from the beginning of decay of stationary gripper coil voltage to dashpot entry, with:

a.

Tavg 500°F; and

b.

All reactor coolant pumps operating.

Prior to reactor criticality after each removal of the reactor head

Rod Group Alignment Limits 3.1.4 Point Beach 3.1.4-5 Unit 1 - Amendment No. 212 Unit 2 - Amendment No. 217 Table 3.1.4-1 Allowable Alignment Limits As A Function Of Measured Peaking Factor Margin (FQ(Z), FH N )

At Power Levels > 85% Of Rated Power And Bank D Demand < 215 Steps Withdrawn ALIGNMENT LIMITS (STEPS)*

REQUIRED MARGIN TO FH N LIMIT (%)

REQUIRED MARGIN TO FQ(Z) LIMIT (%)

12 0.00 0.00 13 0.33 0.83 14 0.67 1.67 15 1.00 2.50 16 1.33 3.33 17 1.67 4.17 18 2.00 5.00

  • Between the bank demand position and the RPI System.

Table 3.1.4-2 Allowable Alignment Limits As A Function Of Measured Peaking Factor Margin (FQ(Z), FH N )

At Power Levels > 85% Of Rated Power And Bank D Demand 215 Steps Withdrawn ALIGNMENT LIMITS (STEPS)*

REQUIRED MARGIN TO FH N LIMIT (%)

REQUIRED MARGIN TO FQ(Z) LIMIT (%)

12 0.00 0.00 13 0.33 0.83 14 0.67 1.67 15 1.00 2.50 16 1.33 3.33 17 1.67 4.17 18 2.00 5.00 19 2.33 5.83 20 2.67 6.67 21 3.00 7.50 22 3.33 8.33 23 3.67 9.17 24 4.00 10.0

  • Between the bank demand position and the RPI System.

POINT BEACH NUCLEAR PLANT CSP-ST.0 UNIT 1 CRITICAL SAFETY PROCEDURe SAFETY RELATED Revision 6 11/2011 CRITICAL SAFETY FUNCTION STATUS TREES Page 8 of 11 FIGURE 3 ST-3 HEAT SINK I

TOTAL FEEDWATER FLOW TO SIGs GREATER THAN 230 GPM NO YES

........Q GO TO

--I CSP-H.2 NARROW RANGE LEVEL IN ANY SIG PRESSURE IN BOTH SIGs NO GREATER THAN

[51%] 29%

NO YES LESS THAN 1105 PSlG YES me*aaa Q ::;:3 NARROW RANGE LEVEL IN BOTH SlGs LESS THAN [85%] 91 %

NO YES....o GO CSP-H.4 TO PRESSURE IN BOTH SlGs LESS THAN 1085 PSlG NO YES GO TO 1

1 CSP-H.5 NARROW RANGE LEVEL IN BOTH SGs GREATER THAN [51%] 29%

NO YES

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