ML17214A350

Dua 2017 Ile - Administered Exam Written Examination Handouts

ML17214A350
Person / Time
Site:	Duane Arnold
Issue date:	06/14/2017
From:	Bielby M Operations Branch III
To:	NextEra Energy Duane Arnold
Bielby M
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ML16308A454	List: ML17214A214 ML17214A232 ML17214A259 ML17214A295 ML17214A307 ML17214A350
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Download: ML17214A350 (50)

Text

1 Student Handout Index

1.

LCO 3.3.1.2 SRM Instrumentation [RO]

2.

LCO 3.6.1.1 Primary Containment [SRO]

3.

LCO 3.4.1 Recirculation Loops Operating [SRO]

4.

LCO 3.4.2 Jet Pumps [SRO]

5.

LCO 3.7.9 Control Building / Standby Gas Treatment (CB/SBGT) Instrument Air System [SRO]

6.

LCO 3.8.1 AC Sources Operating [SRO]

7.

EPIP Form EAL-01 Emergency Action Level Matrix [Hot]

[SRO]

8.

EPIP Form EAL-02 Emergency Action Level Matrix [Cold]

[SRO]

9.

EOP Graph 07 Drywell Spray Initiation Limit [SRO]

10.

LCO 3.2.2 MCPR [SRO]

11.

LCO 3.4.10 Reactor Steam Dome Pressure [SRO]

12.

LCO 3.5.1 ECCS Operating [SRO]

13.

LCO 3.1.3 Control Rod Operability [SRO]

14.

LCO 3.1.6 Rod Pattern Control [SRO]

15.

EOP Table 6 [RO/SRO]

16.

LCO 3.6.2.2 [SRO]

17.

EOP Graph 04 [RO/SRO]

18.

Table of RPV Pressure versus Saturation Temperature (AOP 915 Attachment 5) [RO]

19.

Core Spray NPSH Limit [RO]

20.

Core Spray Vortex Limit [RO]

21.

AOP 149 Appendix 1 Heatup Rate Curve -RPV Flooded

[RO]

22.

AOP 149 Appendix 2 Heatup Rate Curve -RPV Level at 200[RO]

SRM Instrumentation 3.3.1.2 2

3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor (SRM) Instrumentation LCO 3.3.1.2 The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.2-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required SRMs inoperable in MODE 2 with Intermediate Range Monitors (IRMs) on Range 2 or below.

A.1 Restore required SRMs to OPERABLE status.

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

Three required SRMs inoperable in MODE 2 with IRMs on Range 2 or below.

B.1 Suspend control rod withdrawal.

Immediately C.

Required Action and associated Completion Time of Condition A or B not met.

C.1 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)

SRM Instrumentation 3.3.1.2 3

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

One or more required SRMs inoperable in MODE 3 or 4.

D.1 Fully insert all insertable control rods.

AND D.2 Place reactor mode switch in the shutdown position.

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

One or more required SRMs inoperable in MODE 5.

E.1 Suspend CORE ALTERATIONS except for control rod insertion.

AND E.2 Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Immediately Immediately

4 SURVEILLANCE REQUIREMENTS

---

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.2

---

NOTES--------------------------

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is located in :

a.

The fueled region;

b.

The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c.

A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.3 Perform CHANNEL CHECK.

In accordance with the Surveillance Frequency Control Program SURVEILLANCE REQUIREMENTS (continued)

5 SURVEILLANCE FREQUENCY SR 3.3.1.2.4

---

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

Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

Verify count rate is 3.0 cps.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.5 Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.6

---

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

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST.

In accordance with the Surveillance Frequency Control Program SR 3.3.1.2.7

---

NOTES-----------------------------

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Program

Primary Containment 3.6.1.1 6

3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment LCO 3.6.1.1 Primary containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Primary containment inoperable.

A.1 Restore primary containment to OPERABLE status.

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

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours

Primary Containment 3.6.1.1 7

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and leakage rate testing except for primary containment air lock testing, in accordance with the Primary Containment Leakage Rate Program.

In accordance with the Primary Containment Leakage Rate Program.

SR 3.6.1.1.2 Verify suppression chamber pressure does not increase at a rate > 0.009 psi per minute tested over a 10 minute period at a differential pressure of > 1.0 psid.

In accordance with the Surveillance Frequency Control Program

Recirculation Loops Operating 3.4.1 8

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched pump speeds shall be in operation with core flow as a function of THERMAL POWER outside the Exclusion Region specified in the COLR.

OR One recirculation loop may be in operation with core flow as a function of THERMAL POWER outside the Exclusion Region specified in the COLR and with the following limits applied when the associated LCO is applicable:

a.

LCO 3.2.1, AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR), single loop operation limits specified in the COLR;

b.

LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR),

single loop operation limits specified in the COLR; and

c.

LCO 3.3.1.1, Reactor Protection System (RPS)

Instrumentation, Function 2.b (Average Power Range Monitors Flow Biased High Scram), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

No recirculation loops in operation.

A.1 Place the reactor mode switch in the Shutdown position.

Immediately (continued)

Recirculation Loops Operating 3.4.1 9

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One or two recirculation loops in operation in the Exclusion Region of the power/flow map described in the Core Operating Limits Report.

B.1 Initiate action to exit the Exclusion Region.

Immediately C.

Recirculation pump speed mismatch not within limits.

C.1 Trip one recirculation pump.

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

Requirements of the LCO not met for reasons other than Conditions A, B or C.

D.1 Satisfy requirements of the LCO.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> E.

Required Action and associated Completion Time of Condition C or D not met.

E.1 Be in MODE 3.

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

Recirculation Loops Operating 3.4.1 10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1

---

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

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after both recirculation loops are in operation.

Verify recirculation pump speed mismatch with both recirculation pumps at steady state operation is as follows:

a. The speed of the faster pump shall be 135%

of the speed of the slower pump when operating at < 69.4 % RTP.

b. The speed of the faster pump shall be 122% of the speed of the slower pump when operating at 69.4 % RTP.

In accordance with the Surveillance Frequency Control Program SR 3.4.1.2 Verify core flow as a function of core THERMAL POWER is outside the Exclusion Region shown in the COLR.

In accordance with the Surveillance Frequency Control Program

Jet Pumps 3.4.2 11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 Jet Pumps LCO 3.4.2 All jet pumps shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more jet pumps inoperable.

A.1 Be in MODE 3.

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

Jet Pumps 3.4.2 12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1

---

NOTES-------------------------------

1.

Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the associated recirculation loop is in operation.

2.

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after > 21.7% RTP.

3.

Criterion c is only applicable when pump speed is 60% rated speed.

Verify at least one of the following criteria (a, b or c, as applicable) is satisfied for each operating recirculation loop:

a.

Recirculation pump flow to speed ratio differs by 5% from established patterns, and jet pump loop flow to recirculation pump speed ratio differs by 5% from established patterns.

b.

Each jet pump diffuser to lower plenum differential pressure differs by 20% from established patterns.

c.

The recirculation pump flow to speed ratio, jet pump loop flow to recirculation pump speed ratio, and jet pump diffuser to lower plenum differential pressure ratios are evaluated as being acceptable.

In accordance with the Surveillance Frequency Control Program

CB/SBGT Instrument Air System 3.7.9 13 3.7 PLANT SYSTEMS 3.7.9 Control Building/Standby Gas Treatment (CB/SBGT) Instrument Air System LCO 3.7.9 Two CB/SBGT Instrument Air subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One CB/SBGT Instrument Air subsystem inoperable.

A.1 Declare required feature(s), supported by the inoperable CB/SBGT Instrument Air subsystem, inoperable when the redundant required feature(s) are inoperable.

AND A.2 Restore the CB/SBGT Instrument Air subsystem to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition A concurrent with inoperability of redundant required feature(s) 7 days B.

Required Action and Associated Completion Time of Condition A not met.

OR Both CB/SBGT Instrument Air subsystems inoperable.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours

CB/SBGT Instrument Air System 3.7.9 14 CONDITION REQUIRED ACTION COMPLETION TIME

CB/SBGT Instrument Air System 3.7.9 15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 Operates each CB/SBGT Instrument Air compressor for 20 minutes.

In accordance with the Surveillance Frequency Control Program SR 3.7.9.2 Verify each CB/SBGT Instrument Air subsystem actuates on an actual or simulated initiation signal and maintains air pressure 75 psig in the receiver.

In accordance with the Surveillance Frequency Control Program

AC Sources Operating 3.8.1 16 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a.

Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and

b.

Two diesel generators (DGs).

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

---

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

LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One offsite circuit inoperable.

A.1 Perform SR 3.8.1.1 for OPERABLE offsite circuit.

AND A.2 Restore offsite circuit to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Prior to entering MODE 2 from MODE 3 or 4 (continued)

AC Sources Operating 3.8.1 17 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One DG inoperable.

B.1 Perform SR 3.8.1.1 for OPERABLE offsite circuit(s).

AND B.2 Declare required feature(s), supported by the inoperable DG, inoperable when the redundant required feature(s) are inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from discovery of Condition B concurrent with inoperability of redundant required feature(s)

(continued)

AC Sources Operating 3.8.1 18 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.3 Determine OPERABLE DG is not inoperable due to common cause failure.

AND

---

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

Not required to be performed when the cause of the inoperable DG is pre-planned, preventive maintenance and testing.

B.4 Perform SR 3.8.1.2 for OPERABLE DG.

AND B.5 Restore DG to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 7 days AND 8 days from discovery of failure to meet LCO expect for Condition A C.

Two offsite circuits inoperable.

C.1 Declare required feature(s) inoperable when the redundant required feature(s) are inoperable.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from discovery of Condition C concurrent with inoperability of redundant required feature(s)

(continued)

AC Sources Operating 3.8.1 19 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

AND C.2 Restore one offsite circuit to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND 8 days from discovery of failure to meet LCO except for Condition A D.

Two DGs inoperable.

D.1 Restore one DG to OPERABLE status.

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

Required Action and Associated Completion Time of Condition A, B, C, or D not met.

E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours F.

Three or more AC sources inoperable.

F.1 Enter LCO 3.0.3.

Immediately

AC Sources Operating 3.8.1 20 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated power availability for each offsite circuit.

In accordance with the Surveillance Frequency Control Program SR 3.8.1.2

---

NOTES-----------------------------

1.

All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

2.

A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

3.

When a DG is placed in an inoperable status solely for the performance of testing required by Required Actions B.3 or B.4, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Verify each DG starts from standby conditions and achieves steady state voltage 3744v and 4576v and frequency 59.5Hz and 60.5Hz.

In accordance with the Surveillance Frequency Control Program (continued)

AC Sources Operating 3.8.1 21 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.3

---

NOTES----------------------------

1.

DG loadings may include gradual loading as recommended by the manufacturer.

2.

Momentary transients outside the load range do not invalidate this test.

3.

This Surveillance shall be conducted on only one DG at a time.

4.

This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each DG is synchronized and loaded and operates for 60 minutes at a load 2750kw and 2950kw.

In accordance with the Surveillance Frequency Control Program SR 3.8.1.4 Verify each tank contains 220 gal of fuel oil.

In accordance with the Surveillance Frequency Control Program SR 3.8.1.5 Check for the presence of water in the fuel oil in each day tank and remove water as necessary.

In accordance with the Surveillance Frequency Control Program (continued)

AC Sources Operating 3.8.1 22 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.6 Verify the fuel oil transfer system operates to transfer fuel oil from storage tank to the day tank.

In accordance with the Surveillance Frequency Control Program SR 3.8.1.7

---

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

All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition and achieves:

a. in 10 seconds, voltage 3744V and frequency 59.5Hz; and

b. steady state, voltage 3744V and 4576V and frequency 59.5Hz and 60.5Hz.

In accordance with the Surveillance Frequency Control Program SR 3.8.1.8

---

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

The Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify automatic slow transfer of AC power supply from the Startup Transformer to the Standby Transformer.

In accordance with the Surveillance Frequency Control Program (continued)

AC Sources Operating 3.8.1 23 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9

---

NOTE---------------------------This Surveillance shall not be performed in MODE 1 or 2. However, credit may be taken for unplanned events that satisfy this SR.

Verify each DG rejects a load greater than or equal to its associated single largest post-accident load, and:

a.

Following load rejection, the frequency is 64.5Hz.

b.

Within 1.3 seconds following load rejection, the voltage is 3744V and 4576V.

c.

Within 3.9 seconds following load rejection, the frequency is 59.5Hz and 60.5Hz.

In accordance with the Surveillance Frequency Control Program SR 3.8.1.10 ----------------------------NOTE---------------------------

This Surveillance shall not be performed in MODE 1, 2 or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify each DGs automatic trips are bypassed on an actual or simulated Loss of Offsite Power (LOOP) signal or on an actual or simulated ECCS initiation signal except:

a.

Engine overspeed; and

b.

Generator lockout.

In accordance with the Surveillance Frequency Control Program (continued)

AC Sources Operating 3.8.1 24 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11

---

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

This Surveillance shall not be performed in MODE 1, 2 or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify under manual control each DG:

a.

Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b.

Transfers loads to offsite power source; and

c.

Returns to ready-to-load operation.

In accordance with the Surveillance Frequency Control Program SR 3.8.1.12

---

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

This Surveillance shall not be performed in MODE 1, 2 or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load block is 2 seconds.

In accordance with the Surveillance Frequency Control Program (continued)

AC Sources Operating 3.8.1 25 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13

---

NOTES---------------------------

1.

All DG starts may be preceded by an engine prelube period.

2.

This Surveillance shall not be performed in MODE 1, 2, or 3. However, credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of offsite power signal in conjunction with an actual or simulated ECCS initiation signal:

a.

De-energization of essential buses;

b.

Load shedding from essential buses; and

c.

DG auto-start from standby condition and:

1.

energizes permanently connected loads in 10 seconds,

2.

energizes auto-connected emergency loads in the proper timed

sequence,

3.

achieves steady state voltage 3744V and 4576V,

4.

achieves steady state frequency 59.5Hz and 60.5Hz, and

5.

supplies permanently connected and auto-connected emergency loads for 5 minutes.

In accordance with the Surveillance Frequency Control Program

26 0

50 100 150 200 250 300 350 400 0

2 4

6 8

10 12 14 16 18 20 Average Drywell Air Temperature (°F)

Drywell Pressure (psig)

Graph 7: Drywell Spray Initiation Limit Do not initiate drywell sprays in shaded area 11.4 3.0

MCPR 3.2.2 27 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

APPLICABILITY:

THERMAL POWER 21.7% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Any MCPR not within limits.

A.1 Restore MCPR(s) to within limits.

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

Required Action and associated Completion Time not met.

B.1 Reduce THERMAL POWER to < 21.7%

RTP.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to the limits specified in the COLR.

Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after 21.7% RTP AND In accordance with the Surveillance Frequency Control Program (continued)

MCPR 3.2.2 28 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.2.2 Determine the MCPR limits.

Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1.4.1 AND Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1.4.2.

Reactor Steam Dome Pressure 3.4.10 29 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be 1025 psig.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Reactor steam dome pressure not within limit.

A.1 Restore reactor steam dome pressure to within limit.

15 minutes B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

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 3.4.10.1 Verify reactor steam dome pressure is 1025 psig.

In accordance with the Surveillance Frequency Control Program

ECCS Operating 3.5.1 30 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of four safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except High Pressure Coolant Injection (HPCI) is not required to be OPERABLE with reactor steam dome pressure 150 psig and ADS valves are not required to be OPERABLE with reactor steam dome pressure 100 psig.

ACTIONS

---

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

LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One Residual Heat Removal (RHR) pump inoperable.

A.1 Restore RHR pump to OPERABLE status.

30 Days B.

One low pressure ECCS subsystem inoperable for reasons other than Condition A.

B.1 Restore low pressure ECCS subsystem to OPERABLE status.

7 days C.

One Core Spray subsystem inoperable.

AND One or two RHR pump(s) inoperable.

C.1 Restore Core Spray subsystem to OPERABLE status.

OR C.2 Restore RHR pump(s) to OPERABLE status.

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

Both Core Spray subsystems inoperable.

D.1 Restore one Core Spray subsystem to OPERABLE status.

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

ECCS Operating 3.5.1 31 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

Required Action and associated Completion Time of Condition A, B, C, or D not met.

E.1 Be in MODE 3.

AND E.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours F.

HPCI System inoperable.

F.1 Verify by administrative means RCIC System is OPERABLE.

AND F.2 Restore HPCI System to OPERABLE status.

Immediately 14 days G.

HPCI System inoperable.

AND One RHR pump inoperable.

G.1 Restore HPCI System to OPERABLE status.

OR G.2 Restore RHR pump to OPERABLE status.

7 days 7 days H.

HPCI System inoperable.

AND One low pressure ECCS subsystem is inoperable for reasons other than Condition A.

H.1 Restore HPCI System to OPERABLE status.

OR H.2 Restore low pressure ECCS subsystem to OPERABLE status.

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

HPCI System inoperable.

AND One ADS valve inoperable.

I.1 Restore HPCI System to OPERABLE status.

OR I.2 Restore ADS valve to OPERABLE status.

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

ECCS Operating 3.5.1 32 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J.

Required Action and associated Completion Time of Condition F, G, H, or I not met.

J.1 Be in MODE 3.

AND J.2 Reduce reactor steam dome pressure to 150 psig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours K.

One ADS valve inoperable.

K.1 Restore ADS valve to OPERABLE status.

30 days L.

One ADS valve inoperable.

AND One low pressure ECCS subsystem inoperable for reasons other than Condition A.

L.1 Restore ADS valve to OPERABLE status.

OR L.2 Restore low pressure ECCS subsystem to OPERABLE status.

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

Two or more ADS valves inoperable.

OR Required Action and associated Completion Time of Condition K or L not met.

M.1 Be in MODE 3.

AND M.2 Reduce reactor steam dome pressure to 100 psig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours (continued)

ECCS Operating 3.5.1 33 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N.

Two or more low pressure ECCS subsystems inoperable for reasons other than Condition C or D.

OR HPCI System and two or more ADS valves inoperable.

OR HPCI System and two or more low pressure ECCS subsystems inoperable.

OR One ADS valve and two or more low pressure ECCS subsystems inoperable.

OR One ADS valve and HPCI System and one low pressure ECCS subsystem inoperable.

N.1 Enter LCO 3.0.3.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program (continued)

ECCS Operating 3.5.1 34 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.2

---

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

The low pressure coolant injection (LPCI) system may be considered OPERABLE during alignment and operation for decay heat removal in MODE 3, if capable of being manually realigned and not otherwise inoperable.

---

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

Not required to be met for system vent flow paths opened under administrative control.

Verify each ECCS injection/spray subsystem power operated and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.3 Verify a 100 day supply of nitrogen exists for each ADS accumulator.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.4 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure.

SYSTEM HEAD NO. CORRESPONDING OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray 2718 gpm 1 113 psig LPCI 4320 gpm 1 20 psig In accordance with the Inservice Testing Program (continued)

ECCS Operating 3.5.1 35 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.5

---

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

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 1025 and 940 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.

In accordance with the Inservice Testing Program SR 3.5.1.6

---

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

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 160 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.7

---

NOTES--------------------------

1.

Vessel injection /spray may be excluded.

2.

For the LPCI System, the Surveillance may be met by any series of sequential and/or overlapping steps, such that the LPCI Loop Select function is tested.

Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.

In accordance with the Surveillance Frequency Control Program (continued)

ECCS Operating 3.5.1 36 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.8

---

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

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated automatic initiation signal.

In accordance with the Surveillance Frequency Control Program SR 3.5.1.9 Verify each ADS valve actuator strokes when manually actuated.

In accordance with the Inservice Testing Program

Rod Pattern Control 3.1.6 37 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 OPERABLE control rods shall comply with the requirements of the Banked Position Withdrawal Sequence (BPWS).

APPLICABILITY: MODES 1 and 2 with THERMAL POWER 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more OPERABLE control rods not in compliance with BPWS.

A.1

---

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

Rod Worth Minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1, Control Rod Block Instrumentation.

Move associated control rod(s) to correct position.

OR A.2 Declare associated control rod(s) inoperable.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8 hours (continued)

Rod Pattern Control 3.1.6 38 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Nine or more OPERABLE control rods not in compliance with BPWS.

B.1

---

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

Rod Worth Minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1.

Suspend withdrawal of control rods.

AND B.2 Place the reactor mode switch in the Shutdown position.

Immediately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply with BPWS.

In accordance with the Surveillance Frequency Control Program

Control Rod OPERABILITY 3.1.3 39 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

---

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

Separate Condition entry is allowed for each control rod.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One withdrawn control rod stuck.

---

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

Rod Worth Minimizer (RWM) may be bypassed as allowed by LOC 3.3.2.1, Control Rod Block Instrumentation, if required, to allow continued operation.

A.1 Verify stuck control rod separation criteria are met.

AND A.2 Disarm the associated Control Rod Drive (CRD).

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

Control Rod OPERABILITY 3.1.3 40 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.3 Perform SR 3.1.3.2 for each withdrawn OPERABLE control rod.

AND A.4 Perform SR 3.1.1.1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from discovery of Condition A concurrent with THERMAL POWER greater than the Low Power Setpoint (LPSP) of the RWM.

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

Two or more withdrawn control rods stuck.

B.1 Be in MODE 3.

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

One or more control rods inoperable for reasons other than Condition A or B.

C.1

---

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

RWM may be bypassed as allowed by LCO 3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.

Fully insert inoperable control rod.

AND 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (continued)

Control Rod OPERABILITY 3.1.3 41 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2 Disarm the associated CRD.

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

---

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

Not applicable when THERMAL POWER

> 10% RTP.

Two or more inoperable control rods not in compliance with Banked Position Withdrawal Sequence (BPWS) and not separated by two or more OPERABLE control rods.

D.1 Restore compliance with BPWS.

OR D.2 Restore control rod to OPERABLE status.

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

Required Action and associated Completion Time of Condition A, C, or D, not met.

OR Nine or more control rods inoperable.

E.1 Be in MODE 3.

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

Control Rod OPERABILITY 3.1.3 42 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 3.1.3.1 Determine the position of each control rod In accordance with the Surveillance Frequency Control Program SR 3.1.3.2

---

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

Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than 20% RTP.

Insert each withdrawn control rod at least one notch.

In accordance with the Surveillance Frequency Control Program SR 3.1.3.3 Verify each control rod scram time from fully withdrawn to notch position 04 is 7 seconds.

In accordance with SR 3.1.4.1 and SR 3.1.4.2 SR 3.1.3.4 Verify each withdrawn control rod does not go to the withdrawn overtravel position.

Each time the control rod is withdrawn to full out position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling (continued)

43 Table 6 Secondary Containment Limits Parameter and Areas Max Normal Operating Limit Max Safe Operating Limit Value/Trend Temperature Area/Location Indicator

°F

°F A RHR-SE Corner Room Area RHR SE CORNER ROOM AMBIENT RHR SE CORNER ROOM DIFFERENTIAL TR/TDR 2000A Ch 1 TR/TDR 2000A Ch 2 130 50 140 N/A B RHR-NW Corner Room Area RHR NW CORNER ROOM AMBIENT RHR NW CORNER ROOM DIFFERENTIAL TR/TDR 2000B Ch 1 TR/TDR 2000B Ch 2 130 50 140 N/A HPCI Room Area HPCI EMER COOLER AMBIENT HPCI ROOM AMBIENT HPCI ROOM DIFFERENTIAL TR/TDR 2225A[B] Ch 1 TR/TDR 2225A Ch 2 TR/TDR 2225A[B] Ch 4[3]

175 175 50 310 310 N/A RCIC Room Area RCIC EMER COOLER AMBIENT RCIC ROOM AMBIENT RCIC ROOM DIFFERENTIAL TR/TDR 2425A[B] Ch 1 TR/TDR 2425A Ch 2 TR/TDR 2425A[B] Ch 4 175 175 50 300 300 N/A Torus Area TORUS CATWALK NORTH AMBIENT TORUS CATWALK WEST AMBIENT TORUS CATWALK SOUTH AMBIENT TORUS CATWALK EAST AMBIENT TORUS CATWALK EAST DIFF TORUS CATWALK WEST DIFF TORUS CATWALK SOUTHWEST DIFF TORUS CATWALK SOUTH DIFF TR/TDR 2425A Ch 3 TR/TDR 2425B Ch 2 TR/TDR 2225A Ch 3 TR/TDR 2225B Ch 2 TR/TDR 2425A Ch 5 TR/TDR 2425B Ch 5 TR/TDR 2225A Ch 5 TR/TDR 2225B Ch 4 150 150 150 150 50 50 50 50 165 165 165 165 N/A N/A N/A N/A RB 786 South Area RWCU PUMP ROOM AMBIENT RWCU HX ROOM AMBIENT TR/TDR 2700A[B] Ch 1 TR/TDR 2700A[B] Ch 2,3 130 130 212 212 RB 757 South Area RWCU ABOVE TIP ROOM AMBIENT TR/TDR 2700A[B] Ch 4,5 111.5 150 Steam Tunnel Area STEAM TUNNEL AMBIENT STEAM TUNNEL DIFFERENTIAL TR/TDR 2425B Ch 3 TR/TDR 2225B Ch 5 160 70 300 N/A Radiation Area/Location Indicator mR/hr mR/hr RB 757 South Area RB RAILROAD ACCESS AREA SOUTH CRD MODULE AREA TIP ROOM RI 9167 RI 9169 RI 9176 10 10 60 100 100 600 RB 757 North Area NORTH CRD MODULE CRD REPAIR ROOM RI 9168 RI 9170 10 15 100 150 RB 786 North Area RWCU SPENT RESIN ROOM RWCU PHASE SEP TANK RI 9173 RI 9177 100 20 103 200 RB 786 South Area RWCU PUMP ROOM RWCU HX ROOM RI 9156 RI 9157 103 103 104 104 RB 812 North Area MAIN PLANT EXHAUST FAN ROOM JUNGLE ROOM RI 9171 RI 9155 60 60 600 600 Refuel Floor Area NEW FUEL VAULT AREA NORTH REFUEL FLOOR SOUTH REFUEL FLOOR SPENT FUEL POOL AREA RI 9153 RI 9163 RI 9164 RI 9178 10 10 10 100 100 100 100 103 Water Level Area/Location Indicator inches inches HPCI ROOM LI 3768 2

6 RCIC ROOM LI 3769 3

6 A RHR & CS SECR LI 3770 2

10 B RHR & CS NWCR LI 3771 2

10 TORUS AREA LI 3772 2

12

Suppression Pool Water Level 3.6.2.2 44 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be 10.11 ft and 10.43 ft.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Suppression pool water level not within limits.

A.1 Restore suppression pool water level to within limits.

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

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is within limits.

In accordance with the Surveillance Frequency Control Program

45 Graph 4: Heat Capacity Limit 0

120 RPV Pressure (psig)

Torus Water Temperature (°F) 100 200 300 400 500 600 700 800 900 1000 1100 130 140 150 160 170 180 190 200 210 220 230 240 50 Action is required Bounding curve for torus levels between 8 ft and 13 ft

46 Table of RPV Pressure Versus Saturation Temperature psig Temp (°F) psig Temp (°F) psig Temp (°F) 1100 558 680 502 280 415 1080 556 660 499 260 409 1060 553 640 495 240 402 1040 551 620 492 220 395 1020 549 600 488 200 387 1000 546 580 485 180 380 980 542 560 481 160 371 960 541 540 477 140 361 940 539 520 474 120 350 920 536 500 470 100 338 900 534 480 466 80 324 880 531 460 461 60 307 860 528 440 457 40 287 840 526 420 452 20 259 820 523 400 448 0

212 800 520 380 443 780 517 360 438 760 514 340 431 740 511 320 427 720 508 300 421 700 505

47 Figure 1: Core Spray NPSH Limit 100 120 140 160 180 200 220 240 260 0

1000 2000 3000 4000 5000 CS PUM P FLOWRATE (gpm)

• torus pressue

• 15 psig

• 10 psig

• 5 psig

• 0 psig Do NOT operate CS pumps above these curves unless directed by EOPs 100 120 140 160 180 200 220 240 260 0

1000 2000 3000 4000 5000 CS PUM P FLOWRATE (gpm)

• torus pressue

• 15 psig

• 10 psig

• 5 psig

• 0 psig Do NOT operate CS pumps above these curves unless directed by EOPs

48 Figure 2: Core Spray Vortex Limit 0

2 4

6 8

10 12 0

500 1000 1500 2000 2500 3000 3500 4000 4500 CS LOOP FLOW (gpm)

Do NOT operate CS pumps in this area unless directed by EOPs 0

2 4

6 8

10 12 0

500 1000 1500 2000 2500 3000 3500 4000 4500 CS LOOP FLOW (gpm)

Do NOT operate CS pumps in this area unless directed by EOPs

49 APPENDIX 1 HEATUP RATE CURVE - RPV FLOODED NOTE CAUTION 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 0

10 20 30 40 50 60 70 80 90 100 Heatup Rate (Deg F/hr)

Time Since Shutdown (Days)

RFO-25 Vessel Water Heatup Rate (Floodup Condition)

50 APPENDIX 2 HEATUP RATE CURVE - RPV LEVEL AT 200" CAUTION 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 0

10 20 30 40 50 60 70 80 90 100 Heatup Rate (Deg F/hr)

Time Since Shutdown (Days)

RFO-25 Vessel Water Heatup Rate (Water Level = 200 )