ML13028A066

2012 Point Beach Nuclear Plant Initial License Examination Proposed Written Exam Handouts

ML13028A066
Person / Time
Site:	Point Beach
Issue date:	12/17/2012
From:	NRC/RGN-III
To:
Zoia, Charles
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ML11354A219	List: ML13028A065 ML13028A066 ML13028A069 ML13028A070 ML13028A074 ML13035A236
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Download: ML13028A066 (1)

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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 * * [44%] 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. I' " I 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

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

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

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

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

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

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

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. T avg 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 (F Q (Z), FH N) At Power Levels > 85% Of Rated Power And Bank D Demand < 215 Steps Withdrawn ALIGNMENT LIMITS (STEPS)* REQUIRED MARGIN TO FH NLIMIT (%)

REQUIRED MARGIN TO F Q(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 (F Q (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 F Q(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