ML101520160

Initial Exam 2010-301 Post Exam Comments

ML101520160
Person / Time
Site:	Farley
Issue date:	05/28/2010
From:	NRC/RGN-II
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Download: ML101520160 (55)

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Original question: #43 062A 1.01 062A1.0l Question 43 Recommend deIetin the question Reason:

The intent of this question was to ask how energizing the Heater Group for A Train would affect the loading of the small Diesel Generator (DG). This question has a typographical error that actually asks how energizing a B Train Heater Group would affect the loading an A Train DG. The question also asks if energizing this heater group is allowed by procedure.

First part of the question asks, IF the PRZR HTR GROUP BACKUP is energized, THEN the 1C DG 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load rating will/will not be exceeded.

The answer to this question is the 1 C DG will NOT be affected since the load that is being started is on the opposite train. The problem with this statement is that the load cannot be energized since there is no power to B Train anyway. That train is de energized due to the I B DG being tripped.

The second part of the question asks if, energizing the I B PRZR HTR GROUP BACKUP IS/IS NOT allowed lAW EEP-l, Loss of Reactor or Secondary Coolant.

This question is irrelevant since the load in question has no power and cannot be energized at this point in time. An assumption would have to be made that power can be made available. Appendix E does not allow the candidate to make that assumption since that information is not stated in the stem. The candidate is left to answer this question based solely on the information given. (See Appendix E excerpt below)

Further information In the answer to the first part of the question, the choices of C and D would be the only viable choices since the load on the 1 C DG is not affected by a component on the other train. This eliminates choices A and B as a correct answer. Further, choices C and D can NOT be considered correct for the following reasons:

1. For C to be correct, the candidate has to ignore the fact that the lB heater Group has no power available. Operating the handswitch for the lB PRZR Heater Group is allowed in EEP- 1.0, but technically the candidate would NOT be energizing the heater group by operating the handswitch since there is no power source to this set of heaters.

2. For D to be correct, energizing the heater is technically allowed by EEP- 1.0, but the heater cannot be energized at this time since the bus is de-energized. EEP- 1 does not have a step to start the 2C DG and the 2C DG would have to be started to allow this heater group to be energized. So while it is allowed it cannot be accomplished completely in EEP- 1.0. Therefore the candidate would have to assume the 2C DG is started to allow D to be correct.

Page 1 of4

Original question: #43 062A1 .01 Appendix E When answering a question, do not make assumptions reardina conditions that are not specified in the question unless they occur as a consequence of other conditions that are stated in the question. For example, you should not assume that any alarm has activated unless the question so states or the alarm is expected to activate as a result of the conditions that are stated in the question. Similarly, you should assume that no operator actions have been taken, unless the stem of the question or the answer choices specifically state otherwise. Finally, answer all questions based on actual plant operation, procedures, and references. If you believe that the answer would be different based on simulator operation or training references, you should answer the question based on the actual plant.

ES-403 paae 3 of 6 D.1.c

c. If it is determined that there are two correct answers, both answers will be accepted as correct. If. however both answers contain conifictina information, the question will likely be deleted. For example, if part of one answer states that operators are required to insert a manual reactor scram, and part of another answer states that a manual scram is not required, then it is unlikely that both answers will be accepted as correct, and the question will probably be deleted.

If three or more answers could be considered correct or there is no correct answer, the question shall be deleted.

Background:

A typographical error was missed during the review and validation of this question.

Conclusion The facility recommends deleting the question from the exam since there is no correct answer.

Page2of4

Original question: #43 062A 1.01 Table I Power Supphes Load Pressurizer Heater Group A 600V LC A (Normal) 4160V D 600V LC A (Emergency) 41 60V F Pressurizer Heater Group B 600V LC C (Normal) 4160V E 600V LC C (Emergency) 41 60V G Load center A is an A Train Load Center powered by 1C DG.

Load center C is a B Train Load Center powered by 2C or lB DG.

Page 3 of4

Original question: #43 062A1 .01 OpsEpsO52 lB UAXFMR Not Electrically To Systen Page4of4

QUESTIONS REPORT for 9 Questions that need work

1. 062A1.O1 OO1/#43/RO/C/A 3.4/3.8ININ/4/CVR/SAT Unit I has had a LOSP followed by a SBLOCA, and the following conditions exist:

• The l-2A DG is tagged out.

• The lB DG is tripped.

• The IC DG is supplying power to the A Train busses.

• The load on the IC DG is 2.860 MW.

Which one of the following describes whether or not the 2000 amp hour rating on the 1 C DG will be exceeded if the 1 B PRZR HTR GROUP BACKUP is energized?

E the PRZR HTR GROUP BACKUP is energized, THEN the IC DG 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load rating (1) be exceeded, and energizing the 18 PRZR HTR GROUP BACKUP (2) allowed lAW EEPl, Loss of Reactor or Secondary Coolant.

(1) (2)

A. will is B will is NOT C. will NOT is D. will NOT is NOT Note: in this alignment the IC DG has been manually aligned to the iF bus.

A Incorrect. The first part is correct (see B). The Second part is incorrect (see B).

Plausible since the procedure does state that in an emergency, the design of the electrical system has determined that a slight overload may exist after a LOSP and a LOCA. This is acceptable as long as the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating is not exceeded. Also, the Basis of TS 3.8.3 allows the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> limit to be exceeded for up to 300 hour0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> per year but EEP-I forbits exceeding the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> limit. Confusion may exist as to which one or if both the continuous and/or the 2000 ratings may be exceeded for a period of time. Also, the continuous load limit and the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating values may not be remembered properly. However, the procedure states that MANUAL loading above EITHER the continuous or 2000 rating is not allowed. Confusion could exist as to what the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load allows, i.e. it does not allow overloading above the limit for any period of time as the continuous load limit does.

B Correct. The continuous load limit is 2.850 MW, and the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load limit is 3.100 MW. 2.860+0.30=3.16MW > continuous load limit. EEP-1 APP 4, Step I caution states Do NOT manually load diesel generators above 2000 hr. load limit.

Per EEP-1, Aft. 4: ... continuous load ratinq limit (i.e. 2.85 MW for small DGs, 4.075 MW for Friday, April 16, 2010 10:01:44 AM

QUESTIONS REPORT for 9 Questions that need work large DG5). Under these circumstances, diesel generator loading may be raised not to exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load rating limit (i.e. 3.1 MW for small DGs, 4.353 MW for large DGs...).

C - Incorrect. The first part is incorrect. Plausible, since the continuous load limit and the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating may not be remembered properly, and/or the load in MW of the przr heaters may be confused with other smaller loads. The large DGs have a higher load limit of 4.075 & 4.353 MW for continuous and 2000 hr rating respectively. The second part is incorrect (see A).

D - Incorrect. The first part is incorrect (see C). The second part is correct (see B).

Plausible, since the continuous load liming is already exceeded, and manual loading above the continuous load is not allowed, even though automatic loading above the continuous load limit is allowed in an emergency.

FSD, Diesel Generator System 3.1.6 Interface Requirements The only time during operation (other than design basis accidents) that the diesel is intentionally loaded above its continuous rating is during Technical Specification surveillance testing when the diesels are loaded to their 2000h ratings (4353 KW for the large diesels and 3100 KW for the small diesels).

APPENDIX B STATiC LOADING OF THE DIESEL GENERATORS 8.

2.0 INTRODUCTION

During some design basic events, diesel generator 1 C is loaded above its continuous rating by less than 5%. However, this calculated loading above the continuous rating is acceptable since the diesel loading still meets the criteria contained in Position C.2 of Safety Guide 9 (Reference 6.7.028).

G.4.3 Potential Diesel Generator Overload ed by The potential exists for DG overload if the LOSP is follow has been energiz ed. In a LOCA after step 2 of the LOSP sequencer those cases, the DG will be loaded with the Reacto r Cavity n to the Cooling Fan (13 Kw) and the CRDM fan (84 1(w) in additio d loads if ESS loads, and the operator may have to remove selecte n does the DG is loaded above its rated capacity. This situatio in the not constitute a concern given the existing guidance which provid es the operato r with guidan ce for plant procedures reducing the DG loading if it is above rated capacity.

EEP-1 LOSS OF REACTOR OR SECONDARY COOLANT Revision 29 ATTACHMENT 4 VERIFYING 4160 V BUSSES ENERGIZED I Verify 4160 V busses energized.

manual loads CAUTION: IF a DG is already operating above its continuous load rating, THEN additional may dictate the need to load the should not be added. Unanticipated plant emergency conditions load rating limit (i.e. 2.85 MW for small DGs, 4.075 emergency diesel generators above the continuous circumstance s, diesel generator loading may be raised not to MW for large DGs). Under these 2

Friday, April 16, 2010 10:01:44 AM

QUESTIONS REPORT for 9 Questions that need work exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load rating limit (i.e. 3.1 MW for small DGs, 4.353 MW for large DGs). Diesel loading should be reduced within the diesel generator continuous load rating limit as soon as plant conditions allow.

CAUTION: To prevent diesel generator overloading, at least 0.3 MW of diesel generator capacity must be available prior to energizing a group of pressurizer heaters.

1.7.4 RNO Energize pressurizer heater group I B as required.

Previous NRC exam history if any:

062A1 .01 062 A.C. Electrical Distribution Al Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: (CFR: 41.5 /45.5)

A1.01 Significance of D/G load limits 3.4 3.8 Match justification: In this question parameters are provided which must be evaluated to predict if the DG will be overloaded if a load is manually started. The size of the load in MWs must be known and the load limit must be know to predict if the load may be started and if it will exceed the design limits. The significance of the load limits must be understood, since the continuous limit may be exceeded in an emergency without expected damage to the DG, but the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> load limit may not be exceeded for any reason.

Objective:

2. RELATE AND IDENTIFY the operational characteristics including design features, capacities and protective interlocks for the components associated with the Diesel Generator and Auxiliaries System, to include the following (OPS-40102C02):

a. PC2 Diesel, including capacity

b. FM Diesel, including capacity Friday, April 16, 2010 10:01 :44 AM 3

Original question: #68 G2.4. 16 G2.4.16 Question 68 Recommend acceQting A and B as correct answers Reason:

Choice A is a subset of Choice B since ECP-O.O step 24 through 28 conducted in both cases and the nex would be t encounter with the direction to M the Critical Safety Function Status tree ONITOR s is only after ECP-O.O is complet entirety. At no time during the per ed in its formance of ECP-O.O would a new to MONITOR the CSF Status Trees inst ruction be encountered.

Background:

In the stem of the question, the foll owing information is provided:

Attempts to restore power to any 416 0V bus from any source per the step, Restoration of power to any emergency bus, have all been unsuccessful.

This statement establishes that all acti ons of step 5 have been completed success; therefore continuance wit without hin ECP-O.O until a transition to ECP-O ECP-O.2 is directed when power is rest .1 or ored. The initial conditions provid establish the position within the proced ed ure to be at a step below the Cau above step I that provides the initia tion l guidance to monitor the CSF stat for information only. us trees Step 6, then establishes a Continuing Action that Step 24 should be implem upon a restoration of any bus. Steps ented 6 through 23 will be repeated until pow restored OR conditions have degrad er is ed to a condition were SAMG entry required. is When power is restored steps 24-29 are completed and ECP-O.O is exited.

If power is never restored or restoration is significantly delayed, then steps 11-are repeated until either entry into SA 24 CRG-1 is required or power is restore additional instructions to monitor CSF d. No status trees are provided while wit DO-Loop. Therefore, ECP-O.O actions hin this would continue until power is restored, in which case a transition to step 24 would occur and step 24-would be completed and ECP-O.O wou 29 ld be exited. This endpoint is the condition resulting from the conditions same in choice A.

It is only upon entry into ECP-O.I or EC P-O.2 that the NEXT instruction to monitor CSF status trees would be encountered. That instruction is provid the CAUTION prior to the first step at ed in the beginning of both procedures, EC and ECP-O.2. (See caution below) P-O.1 Page 1 of3

Original question: #68 G2.4.16 CAUTION: Critical cafety function tatua treea chould be monitored for information only. No Function Rect oration Procedure chould be Implemented until completion of otep 12.

This is the NEXT encounter with instruction to monitor CSF status trees, therefore the resultant flowpath would have been a continuation of ECP-O.O until instructed to monitor CSF status trees.

Under both circumstances, ECP-O.O actions wou ld continue and complete step 24 through 29. Under both circumstances the trans ition to the subsequent Stabilization/Contingency procedures occurs.

Choice B encompasses the same steps intended by answer choice A.

REFERENCES:

FNP-l-ECP-O.O, ver 22 FNP-1-ECP-O.1, ver 18 FNP-1-ECP-O.2, ver 18 FNP-1-SACRG-1.O, ver 4 Definition: UNTILpreposition used as a function word to indicate continuance (as of an action or condition) to a specified time <stayed until morning>

http:Ilwww. merriam-webster.com/dictionary/unti l

onward to or till (a specified time or occurrence) http://dictionary.reference.com/browse/until Further Information:

ES-403 pane 3 of 6 D.1.c

c. If it is determined that there are two correct answ ers, both answers will be accepted as correct. If however, both answers contain conflicting information, the question will likely be deleted. For example, if part of one answer states that operators are required to insert a manual reactor scram, and part of another answer states that a manual scram is not required, then it is unlikely that both answers will be accepted as correct, and the question will probably be deleted.

Answer choices A and B are not conflicting, which do not mandate question deletion.

Page 2 of 3

Original question: #68 G2.4. 16 The targeted KJA, G2.4. 16 is still tested in identifyi ng that the ERG Contingency procedure has priority over the Functional Rest oration Procedures in this circumstance.

G2.4. 16 Knowledge of EOP implementatio n hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

Original question:

G2.4.16 Question 68 Unit I was at 100% power when a Large Brea k LOCA and a subsequent LOSP occurred. The following conditions exist:

• The crew is performing the actions of ECP

-0.O, Loss of ALL AC Power.

• Attempts to restore power to any 41 60V bus from any source per the step, Restoration of power to any emergency bus

, have all been unsuccessful.

• ALL Core Exit Thermocouples (CETCs) read 725°F and are increasing.

Which one of the following is the required proc edural flowpath?

A. Continue in ECP-0.0 until power is restored to at least one emergency bus.

B. Continue in ECP-O.0 until instructed to mon itor CSF status trees.

C. Immediately transition to FRP-C.2, Response to Degraded Core Cooling, from any step of ECP-O.0.

D. Immediately transition to FRP-C.1, Response to Inadequate Core Cooling, from any step of ECP-O.0.

Ouestion IMPROVEMENT suaestion: (to match origi nal intent)

Change A: Continue in ECP-0.0 until power is restored to at least one emergency bus then transition to ECP-O. 1.

Change B: Continue in ECP-0.0 until power is restored to at least one emergency bus then transition immediately to FRP-C.2 Page 3 of 3

1. G2.4.16 OO1/#68/RO/C/A 3.5/4.4/N/N/31N0 CHANGE OKJFIX Two answers A and B Unit 1 was at 100% power when a Large Brea k LOCA and a subsequent LOSP occurred. The following conditions exist:

• The crew is performing the actions of ECP-0.0,

• Loss of ALL AC Power.

Attempts to restore power to any 4160V bus from any source per the step, Restoration of power to any emergency bus

, have all been unsuccessful.

• ALL Core Exit Thermocouples (CETCs) read 725°F and are increasing.

Which one of the following is the required procedural flowpath?

A Continue in ECP-0.O until power is restored to at least one emergency bus.

B. Continue in ECP-0.0 until instructed to mon itor CSF status trees.

C. Immediately transition to FRP-C.2, Response to Degraded Core Cooling, from any step of ECP-O.0.

D. Immediately transition to FRP-C.1, Response to Inadequate Core Cooling, from any step of ECP-O.0.

Rewrote per CE suggestion to ensure on the RO level.

A Correct. Remaining in ECP-0.O until power is restored is correct since there are nn CSFs required to be entered while in ECP-0 per the caution at the beginning of the procedure.

CAUTION: Critical safety function status trees should be monitored for information only. No restoration or other procedure should be impl function emented during a loss of all AC power.

B Incorrect, there is no step in ECP 0 that direc ts monitoring CSF5.

C Incorrect. See A above D Incorrect. See A above SOP-O.8, Emergency Response Procedure User s Guide, Version 18.0 4.2 Applicability [of the CSFSTs: FRPsI The user should begin monitoring the CSFSTs when directed by EEP-0 or upon transition from EEP-0. The CSFSTs are not monitored initially beca use the ERPs are already directing the initial action required to protect the barriers. If the user enters ECP-0.0. the CSFSTs should be monitored for information only. The Function Restoration Procedures assume that at least one train of safeguards busses is available. If all AC power has been lost, ECP-0.0 will provide the appropriate actions to protect the barriers.

Page: 1 of 2 4/16/2010

Previous NRC exam history if any:

G2.4.16 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating proced ures, abnormal operating procedures, and severe accident management guidelines.

(CFR: 41.10 I 43.5 145.13) RO 3.5 SRO 4.4 Match justification: This question requires knowledge of the EOP hierarchy to answer correctly. The EOP heirarchy involves the FRPs being implemented as the highest priority procedures except in certain cases (early in E-0 and during loss of all AC they are not implemented), also, in the event of SAMG entry requirements, there are only a few entry points from the ERG network, and the transition is directed at the specific procedure steps. When SAMG entry is required, it takes priority over the EOPs and FRPs.

Comment: RO Knowledge of basic high level EOP priorit ies is being tested with this question.

Objective:

1. EVALUATE plant conditions and DETERMINE if entry into (1) ECP0.0, Loss of All AC Power; andIor (2) ECP-0.l, Loss of All AC Power Recov ery, Without SI Required; andlor (3) ECP-0.2, Loss of All AC Power Recovery, With SI Required is required.

(OPS-52532A02)

2. LIST AND DESCRIBE the sequence of major actions, when and how continuous actions will be implemented, associated with (1) ECP-0.0, Loss of All AC Power; (2)

ECP-0.1, Loss of All AC Power Recovery, Without SI Required; (3) ECP-0.2, Loss of All AC Power Recovery, With SI Required. (OPS-52532A04)

3. ANALYZE plant conditions and DETERMINE the successful completion of any step in (1) ECP-O.0, Loss of All AC Power; (2) ECP-0.l, Loss of All AC Power Recovery, Without SI Required; (3) ECP-0.2, Loss of All AC Power Recov ery, With SI Required.

(OPS-52532A07)

Page: 2 of 2 4/16/2010

FNP-l-ECP-O.0 4-20-2007 Revision 22 FARLEY NUCLEAR PLANT EMERGENCY CONTINGENCY PROCEDURE FNP-l-ECP-0.0 LOSS OF ALL AC POWER S

A PROCEDURE USAGE REQUIREMENTS-per F FNP-0-AP-6 SECTIONS E Continuous Use T Remainder of Y Procedure Reference Use Steps 1-2 R Information Use E L

A T

E D

Approved:

Jim L. Hunter (for)

Operations Manager Date Issued: 04/23/07

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Table of Contents Procedure Contains Number of Pages Body 40 Attachment 1 1 Attachment 2 3 Attachment 3 2 Attachment 4 5 Attachment 5 4 Page 1 of 1

FNP-l-ECP-O.O LOSS OF ALL AC POWER Revision 22 A. Purpose This procedure provides actions to respond to a loss of all AC power.

B. Symptoms or Entry Conditions I. This procedure is entered when all AC power has been lost: from the following:

a. Operator determination that both trains of 4160 V emergency busses (A Train: 1F and 1K, B Train: 1G and 1L) are deenergized.

b. FNP-l-EEP-O, REACTOR TRIP OR SAFET Y INJECTION, step 3. on the indication that all AC emergency buss es are deenergized.

Page 1 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I

• • • • • • a*************

• • • • • • • • • • • ** *******a************

CAUTION: Critical safety funétion status trees should be monitored for:

information only No function restoration or other proc be implemented during a loss of all edure should AC power.

flir,-tinn in kAEkIiT

° to initial condtion NOTE:

• This procedure is applicable in modes 1 thru 4 only.

FNP-l--AOP-5.O. LOSS OF A OR B TRAIN ELECTRICAL POWER, is applicable for all other plant modes.

• Steps 1 and 2 are IMMEDIATE ACTIO N steps.

• The Plant Emergency Alarm cannot be activated until AC power is restored.

1 Check reactor tripped.

1.1 Check reactor trip and reactor 1.1 Perform the following.

trip bypass breakers OPEN.

1.1.1 Manually trip reactor.

H Reactor trip breaker A

[] Reactor trip breaker B 1.1.2 any reactor trip breaker

[] Reactor trip bypass breaker A open or any reactor

[] Reactor trip bypass breaker B trip bypass breaker open, THEN locally open affected breaker. (121 ft. AUX BLDG rod control room) 1.2 Check nuclear power - FALLING.

PR1 (2,3,4)

PERCENT FULL POWER

[1 NI 41B

[1 NI 42B

[] NI 43B

[1 NI 44B IR1 (2)

CURRENT

[1 NI 35B

[1 NI 36B Page Completed Page 2 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I 2 Check turbine tripped.

2 Place MAIN TURB EMERG TRIP switch to TRIP for at least

[] TSLB2 14-1 lit 5 seconds.

H TSLB2 14-2 lit H TSLB2 14-3 lit

[1 TSLB2 14-4 lit 3 Verify RCS isolated.

3.1 WHEN RCS pressure less than 2335 psig, THEN verify both PRZR PORVs closed.

3.2 Verify normal letdown 3.2 Perform the following.

isolated.

3.2.1 Verify all letdown line a) Locally close letdown orifice isolation valves line penetration room isolation valves. (121 CLOSED.

ft. AUX BLDG rad side at LTDN ORIF ISO PRIP) 45 GPM LTDN LINE

[1 Q1E21HV8149A PENE RN ISO LTDN ORIF ISO [1 Q1E21HV8175A 60 GPM [1 Q1E21HV8175B

[1 Q1E21HV8149B H Q1E21HV8149C OR b) Locally close LTDN REHT OR HX TCV inlet iso and 3.2.2 REHEAT HX BYPASS TCV Verify letdown line BYPASS. (100 ft. AUX BLDG isolation valves CLOSED.

storage room across from lB Charging pump room)

LTD LINE iso

[1 01E21LCV459 H Q1E21V145 F] Q1E21LCV46O [] Q1E21V348 3.3 Verify excess letdown line -

ISOLATED.

EXC LTDN ISO VLV

[1 QIE21HV8153 closed

[] Q1E21HV8154 closed Step 3 continued on next page.

Page Completed Page 3 of 40

FNP-l-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I 3.4 Verify all reactor vessel head vent valves - CLOSED.

RX VESSEL HEAD VENT OUTER ISO

[] Q1B13SV2213A

[1 Q1B13SV2213B RX VESSEL HEAD VENT INNER ISO

[] Q1B13SV2214A

[] Q1B13SV2214B

• ** ***a***************************

CAUTION: The TDAFWP will become unreliable with in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> following a loss of all AC power, unless power is restored.

This will occur due to a loss of air to the steam supply valves and a loss of control power from the UPS.

4 Verify total AEW flow GREATER 4 Verify proper AFW alignment.

THAN 395 gpm.

4.1 Verify TDAFWP running.

AFW FLOW TO 1A(1B.1C) SC TDAFWP STM SUPP

[1 Fl 3229A FROM 1B(1C) SC

[] Fl 3229B

[1 MLB-4 1-3 lit

[1 Fl 3229C

[1 MLB-4 2-3 lit AFW

[1 MLB-4 3-3 lit TOTAL FLOW TDAFWP SPEED

[1 Fl 3229

[1 SI 341lA > 3900 rpm TDAFWP SPEED CONT H SIC 3405 adjusted to 100%

4.2 TDAFWP running, locally verify TDAFWP TRIP THROTTLE VLV Q1N12MOV34O6 open. (100 ft. AUX BLDG TDAFWP room)

Step 4 continued on next page.

Page Completed Page 4 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I 4.3 Verify AFW flow path to each SC.

TDAFWP FCV 3228

{] RESET reset TDAFWP TO 1A(lB.1C) SC

[1 Q1N23HV3228A in MOD

[1 Q1N23HV3228B in MOD

[1 Q1N23HV3228C in MOD TDAFWP TO 1A(lB.lC) SC FLOW CONT

[1 HIC 3228AA open

[1 HIC 3228BA open

[1 HIC 3228CA open

• • • a***************a*

CAUTION: j power is not restored to the 125 V DC battery chargers on each train within 30 minutes. THEN there may not be enough DC capacity to start a DG and sequence needed loads.

5 [CAl Restore power to any emergency bus.

5.1 Verify supply breakers for major loads on emergency 4160 V busses - OPEN.

[1 BKR DFO1 (1A S/U XFMR TO IF 4160 V BUS)

[1 BKR DF15 (lB S/U XFMR TO 1F 4160 V BUS)

[] BKR DF-l3-l (lF 4160 V BUS TIE TO lH 4160 V BUS) ii BKR DCO1 (lA S/U XFMR TO 1C 4160 V BUS)

[1 BKR DG15 (lB s/u XFMR TO 1G 4160 V BUS Step 5 continued on next page.

Page Completed Page 5 of 40

FNP-1ECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I

[] 1A BATT CHARGER BKR ED-O4-1

[1 1C BATT CHARGER A TRN BKR ED-09-1

[1 1C BATT CHARGER B TRN BKR EE-06-1 LI lB BATT CHARGER BKR EE-05-1 H 1C CCW PUMP BKR DF-04-1

[1 lB CCW PUMP BKR DF-05-1 H lB CCW PUMP BKR DG-05-1

[1 1A CCW PUMP BKR DG-04-1 H 1A SW PUMP BKR DK-03-1 LI lB SW PUMP BKR DK-04-1 LI 1C SW PUMP BKR DK-05-1

[1 1C SW PUMP BKR DL-05-l

[1 1D SW PUMP BKR DL-03-1

[] 1E SW PUMP BKR DL-04-1

[] #4 RW PUMP BKR DJ-03-1

[1 #5 RW PUMP BKR DJ-04-1

{] #8 RW PUMP BKR DH-03-1

[] #9 RW PUMP BKR DH-04-1

[1 #10 RW PUMP BKR DH-05-1

[] lB CRDM CLG FAN BKR ED-il-i

[] 1A CRDM CLG FAN BKR EE-13-1

[] 1A CS PUMP BKR OF-li-i

[] lB CS PUMP BKR DG-11-1

[1 1A RHR PUMP BKR DF-09-1 H lB RHR PUMP BKR DG-09-i H 1A CHG PUMP BKR DF-06-i H lB CHG PUMP A TRN BKR DF-07-1

[1 lB CHG PUMP B TRN BKR DG-07-i H 1C CHG PUMP BKR DG-06-1 LI 1A MDAFWP BKR DF-10-1 LI lB MDAFWP BKR DG-i0-i Step 5 continued on next page.

Page Completed Page 6 of 40

FNPl-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I CAUTION: A running diesel generator will overheat if adequate SW flow is not provided within 3 minutes. Steps 5.3 through 5.7 must be performed immediately to verify adequate SW flow once a diesel genera tor has been started.

NOTE: With the exception of the battery chargers, load shed of bus loads must be completed prior to closing the output breaker for any diesel generator.

5.2 Check l-2A. 1C or 18 diesel 5.2 Perform the following:

generator running for Unit 1.

5.2.1 Perform 2C DC SBO start as

• Check DIESEL SPEED follows.

indication - GREATER THAN O rpm. 5.2.1.1 Verify 2C DC MODE SELECTOR switch in MODE 1.

• Check FREQUENCY METER 5.2.1.2 Place 2C DC UNIT indication - GREATER THAN SELECTOR switch in UNIT 58 Hz. 1.

OR 5.2.1.3 WHEN load shed verified, THEN depress 2C DC

• Check DIESEL AT SYN SPEED DIESEL START pushbutton.

light - LIT.

5.2.1.4 Verify 2C DG starts.

Step 5 continued on next page.

Page Completed Page 7 of 40

FNP-l-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I NOTE: The LOSP sequencer should run when output breake r closes, if no SI signal is present. If an SI signal is present. neither sequencer will run and SI loads must be started manually.

5.2.1.5 Verify Unit 1 2C DC output breaker DJO6 closes.

5.2. 1.6 Verify breaker DG13 closed. (1C 4160 V bus tie to 1J 4160 V BUS) 5.2.1.7 Verify breaker DGO2 closed. (10 4160 V bus tie to 1L 4160 V bus) 5.2.1.8 IF 10 4160V bus energized.

THEN proceed to step 5.7.

Step 5 continued on next page.

Page Completed Page 8 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I NOTE:

• Starting 1-2A or lB diesel generator should be attemp ted first.

Any attempted start of a diesel generator which has autom atically tripped should be performed locally in Mode 4.

5.2.2 IF unable to start 2C diesel generator energize 1G 4l6OV bus.

THEN Start any diesel generator.

5.2.2.1 Start diesel generator from EPB in Mode 2 using START pushbutton.

OR 5.2.2.2 Direct diesel operator to start diesel generator in MODE 4 using FNP-O--SOP-38.1.

EMERGENCY STARTING OF A DIESEL GENERATOR.

OR 5.2.2.3 Direct diesel operator to perform a manual emergency start of 1-2A or lB diesel generator using FNP-O-SOP-38.1, EMERGENCY STARTING OF A DIESEL GENERATOR.

OR 5.2.2.4 j. attempts to start a diesel generator fail.

THEN proceed to Step 5.9.

Step 5 continued on next page.

Page Completed Page 9 of 40

FNP-l-ECP-0.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I NOTE: Diesel generator and diesel generator output breake r must be controlled locally (DG BLDG) while diesel generator is in MODE 4.

5.3 Check 1-2A. lC or lB diesel 5.3 Restore diesel generator generator output. field.

5.3.1 Verify diesel generator a) Locally reset exciter. (DG frequency 62 Hz. BLDG at local control panel) 5.3.2 Verify diesel generator voltage - 4.0-4.3 kV. b) j diesel generator frequency indicates 58-62 Hz AND diesel generator voltage indicates 4.0-4.3 kV.

THEN proceed to step 5.4, IF NOT, verify diesel generator DC control power breakers closed. (121 ft.

AUX BLDG battery charger rooms)

Running DG l-2A lC lB 2C Battery Supply H BKR LAO5 [] BKR LAO5 [1 BKR LB18 [1 BKR LB18 DG Control [1 BKR LA17 [1 BKR LAO6 [1 BKR LB19 Panel Supply H BKR LBll c) IF unable to restore excitation to diesel generator.

THEN secure the diesel generator using ATTACHMENT 1, SECURING A DIESEL GENERATOR WITH AN AUTOMATIC START SIGNAL PRESENT proceed to step 5.6.

Step 5 continued on next page.

Page Completed Page 10 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I 5.4 Check 1-2A, 1C or lB diesel 5.4 Close diesel generator output generator output breaker breaker.

closed.

5.4.1 Place mode selector switch in MODE 2.

Running DG 12A lB 1C BKR [1 DFO8 [1 DGO8 [1 DHO7 5.4.2 Place SYNCH SWITCH in MAN.

5.4.3 WHEN load shed verified.

Thi1 close running diesel generator output breaker ANI2 proceed to step 5.5.

Running DG 1-2A lB lC BKR [1 DFO8 [1 DGO8 [] DHO7 5.4.4 IE running diesel generator output breaker can NOT be closed diesel generator is NI supplying Unit 2.

THEN secure the diesel generator using ATTACHMENT

1. SECURING A DIESEL GENERATOR WITH AN AUTOMATIC START SIGNAL PRESENT AND proceed to step 5.6.

Step 5 continued on next page.

_Page Completed Page 11 of 40

FNP-1-ECP-O.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I 5.5 iF 4160 V bus energized, 5.5 1C diesel generator running THEN proceed to step 5.7. for Unit 1, THEN perform the following.

IF NOT, proceed to step 5.6.

5.5.1 .. SI signal present.

THEN reset SI.

[1 MLB-1 1-1 not lit

[1 MLB-1 11-1 not lit 5.5.2 j SI signal was present, THEN reset B1F sequencer.

(139 ft. AUX BLDG A train SWGR room) 5.5.3 Place BKR DF13 SYNCH SWITCH in MAN.

NOTE: The LOSP sequencer may run when breaker is closed.

5.5.4 WHEN load shed verified, THEN close BKR DF13 (iF 4160 V bus tie to 1H 4160 V bus).

5.5.5 Verify BKR DFO2 closed.

(iF 4160 V bus tie to 1K 4160 V bus) 5.5.6 Monitor 1C diesel generator load, voltage and frequency.

5.5.7 iF 4160 V bus energized.

THEN proceed to step 5.7.

Step 5 continued on next page.

Page Completed Page 12 of 40

FNP-1-ECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained r I I 5.6 Check 1C 4160 V bus -

5.6 IF 2C DG available for SBO ENERGIZED, start, THEN perform 2C DC SBO start as follows.

IF NOT, proceed to step 5.8 5.6.1 Verify 2C DG MODE SELECTOR SWITCH in MODE 1.

5.6.2 Place 2C DC UNIT SELECTOR SWITCH in UNIT 1.

5.6.3 WHEN load shed verified, THEN depress 2C DC DIESEL START pushbutton.

5.6.4 Verify 2C DC starts.

NOTE: The LOSP sequencer should run when output breaker closes, if no SI signal is present. If an SI signal is present. neither sequencer will run and SI loads must be started manually.

5.6.5 Verify UNIT 1 2C DC output BKR DJO6 closes.

5.6.6 Verify BKR DG13 closed.

(1C 4160 V bus tie to 1J 4160 V bus) 5.6.7 Verify breaker DCO2 closed.

(1C 4160 V bus tie to 1L 4160 V bus) 5.6.8 Monitor 2C diesel generator load, voltage and frequency.

Step 5 continued on next page.

Page Completed Page 13 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained r

5.7 Verify adequate SW flow.

5.7.1 Verify two SW PUMPS in energized train - RUNNING.

LI A Train (lA. lB or 1C)

LI B Train (1D, 1E or 1C) 5.7.2 A train energized, THEN verify SW TO/FROM DG BLDG - A HDR Q1P16V519/537 open.

5.7.3 j B train energized.

THEN verify SW TO/FROM DG BLDG - B HDR Q1P16V518/536 open.

Step 5 continued on next page.

Page Completed Page 14 of 40

FNP-l-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained F I I 5.7.4 Check no running diesel 5.7.4 Isolate non essential SW.

generator lube oil temperature annunciator in 5.7.4.1 Close the following SW alarm. (155 ft. DG BLDG valves.

local control panel)

SW TO TURB BLDG ISO A TRN

[1 Q1P16V515

[1 Q1P16V516 SW TO TURB BLDG ISO B TRN F] Q1P16V517 F] Q1P16V514 SW FROM TURB BLDG A HDR ISO F] Q1P16V54O H Q1P16V542 SW FROM TURB BLDG B HDR ISO

[1 Q1P16V543 F] Q1P16V541 SWTORCP MTR AIR CLRS F] Q1P16MOV3135 SW TO BLDN HX

& BTRS CHLR F] Q1P16MOV3149 5.7.4.2 diesel generator lube oil temperature still in alarm, i2iN evaluate stopping affected diesel generator.

Step 5 continued on next page.

Page Completed Page 15 of 40

FNPl-ECP-0.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I CAUTION: i both Unit 1 and Unit 2 B Train 4160 THEN one attempt per unit sho V busses become de-energized.

uld be made to restore power one units B Train 4160 V bus to at least by starting DG lB or 2B.

AND IF power cannot be restored usin g either lB or 2B DOs. THEN DO should be immediately alig the SBO ned and started to provide units B Train 4160 V bus. power to one 5.8 IF iF OR 10 4160 V bus 5.8 Continue efforts to start at energized.

THEN go to procedure and step least one diesel generator.

in effect and implement function restoration procedures as necessary.

Step 5 continued on next page.

Page Completed Page 16 of 40

FNP-1ECP0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained i I I I 5.9 Restore offsite power to any 5.9 Continue efforts to energize emergency bus.

any 4160 V emergency bus and proceed to Step 6. OBSERVE 5.9.1 Request Shift Manager NOTE PRIOR TO STEP 6.

coordinate efforts to restore offsite power to at least one startup transformer.

5.9.2 Consult the Power Coordination Center (PCC) to ensure that the grid is stable and reliable prior to realigning emergency buses to offsite power.

NOTE:

• Closing the alternate output breaker from a startup transformer may cause safety related AC power to be cross connected.

• The SYNCH BYPASS switch must be held in the BYPASS position when performing the following step.

5.9.3 WHEN any startup transformer energized.

THEN close associated startup transformer output breaker.

S/U XFMER 1A lB 4160 V BUS iF lG BKR [1 DFO1 [1 DG15 Step 5 continued on next page.

.Page Completed Page 17 of 40

FNP-1-ECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I

5.9.4 j any startup transformer energized its normal 4160 V bus unavailable, THEN close associated startup transformer alternate output breaker.

S/U XFMER lB 1A 4160 V BUS iF 10 BKR [1 DF15 [1 DGO1 NOTE: To manually close the river water bus breaker the associated SYNC SWITCH must be placed in MAN.

5.9.5 WHEN iF or 10 4160 V bus energized from any startup transformer.

THEN verify the associated river water bus breaker closed.

4160 V BUS iF 10 BKR [1 DF13 [1 DG13 5.9.6 IF iF OR 1G 4160 Vbus energized, THEN go to procedure and step in effect and implement function restoration procedures as necessary.

\ Question Initial conditions positions the user here Page Completed Page 18 of 40

FNP-1ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I 1 I NOTE: Step 6 ensures that proper recovery actions are taken in a timely manner.

6 Perform the following.

THEN proceed to :tep 24 6.2 [CA] WHEN an SI signal is present.

nUnuIn Action step that transidons to step 24

]

THEN reset SI signal.

CAUTION: Service water pumps must be kept available for auto start to provide diesel cooling.

CAUTION: Steps 7 and 8 should be performed simultaneously.

7 Defeat auto start of safeguards equipment using ATTACHMENT 2.

8 Isolate RCP seals using ATTACHMENT 3.

9 Locally close IIOTWELL FILL INLET ISO N1P11V5O1 and HOTWELL FILL MAN BYP N1P11V5O6. (137 ft. TIJRB BLOG)

Page Completed Page 19 of 40

FNP-l-ECP-O.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I 10 Check SC status.

10.1 Verify main steam isolation 10.1 Locally close main steam line and bypass valves - CLOSED. isolation and bypass valves.

lA(lB,1C) SG 10.1.1 Vent air from main steam MSIV - TRIP line isolation and bypass

[1 Q1N11HV3369A valve actuators using

[1 Q1N11HV3369B Attachment 1 of

[1 Q1N11HV3369C ENP-l-SOP-l7.O, MAIN AND

[1 Q1N11HV337OA REHEAT STEAM.

[1 Q1N11HV337OB

[1 Q1N11HV337OC lA(1B.lC) SG MSIV - BYPASS

[1 Q1N11HV3368A

[] Q1N11HV3368B

[1 Q1N11HV3368C

{] Q1N11HV3976A

[1 Q1N11HV3976B

[] Q1N11HV3976C Step 10 continued on next page.

Page Completed Page 20 of 40

FNP-1-ECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained 1 I 10.2 Verify main feedwater flow 10.2 Locally isolate main feedwater control and bypass valves - flow path(s).

CLOSED.

• Locally close main feedwater 1A(1B,1C) SG stop valves with handwheels.

FW FLOW (127 ft. AUX BLDG main steam

[] FCV 478 valve room)

LI FCV 488

[1 FCV 498 Affected SC 1A lB 1A(1B.1C) SC MAIN FW TO FW BYP FLOW 1A(1B.1C) SG

[] FCV 479 STOP VLV

[1 FCV 489 Q1N21MOV []3232A []3232B {]3232C

[1 FCV 499 OR

• Locally close affected main feedwater flow control or bypass manual inlet isolation valves. (127 ft.

AUX BLDG main steam valve room)

[1 N1N21V5O7A

[] N1N21V5O7B

[1 N1N21V5O7C

[1 N1N21VOO9A

[1 N1N21VOO9B

[1 N1N21VOO9C Step 10 continued on next page.

Page Completed Page 21 of 40

FNP1ECPO.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I 10.3 Verify blowdown ISOLATED. 10.3 Perform the following.

1A(1B.1C) SGBD 10.3.1 Locally close blowdown line ISO isolation valves. (121 ft.

[1 Q1G24HV7614A closed AUX BLDG rad side at PRIP)

[1 Q1G24HV7614B closed

[1 Q1G24FIV7614C closed 1A(1B,lC) SGBD PENE RM ISO

[1 Q1G24HV7697A

[j Q1G24HV7697B El Q1G24HV7698A

[] Q1G24HV7698B

[1 Q1G24HV7699A

[1 Q1G24HV7699B 10.3.2 Close SGBD inlet filter inlet and bypass valves.

(130 ft. AIJX BLDG rad side SGBD area corridor)

[1 N1G24VOO7

{] N1G24VOO5 Page Completed Page 22 of 40

FNP1-ECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I CAUTION: A faulted or ruptured SC that is isolated should remain isolated.

The TDAFWP will not be available if both steam supplies are isolated.

At least one steam supply must remain aligned to ensure an adequate heat sink is available.

11 Check SGs not faulted.

11.1 Check no SC pressure - FALLING 11.1 Isolate all faulted SGs.

IN AN UNCONTROLLED MANNER OR LESS THAN 50 psig. 11.1.1 Locally close faulted SC AFW flow control valves.

Faulted SC lA lB 1C MDAFWP TO 1A(1B.1C) SC Q1N23HV []3227A {]3227B {]3227C TDAFWP TO lA(lB.lC) SC Q1N23HV []3228A []3228B {]3228C 11.1.2 Locally close faulted SC steam supply to TDAFWP.

(127 ft. AUX BLDG main steam valve room)

Faulted SG 1A lB 1C STM LINE lB(lC)

TO TDAFWP ISO VLV Q1N12V []0O6A []OO5B Key Z-130 Z-132 Step 11 continued on next page.

Page Completed Page 23 of 40

FNP-1-ECPO.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I 11.1.3 Manually close faulted SC atmospheric relief.

Faulted SC 1A(1B,lC) ATMOS 1A I 1C REL VLV PCV []337lA [j337lB [}3371C 11.1.4 Locally unlock and close one isolation valve for any failed atmospheric relief.

(127 ft. AIJX BLDG main steam valve room)

Faulted SC 1A lB 1C Q1N11V []OO4A []004C []0O4E

[]OO4B [1004D []004F Key Z-l31 Z-125 Z-123 Z126 Z-124 Z-122 2age Completed Page 24 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I

• ft * * * ** ** * * **

• ft * * * ** *

• ft * *** * * * * *** ******

• ** ***

• ft ft * * *** ft ** *

• ft * *

• ft *

• ft * * * *

• * **** ft *

• ft ft ft ft CAUTION: A faulted or ruptured SG that is isolated should remain isolated.

The TDAFWP will not be available if both steam supplies are isolated.

At least one steam supply must remain aligned to ensure an adequate heat sink is available.

• • • • ft******** ********ftft***********

• • *ft******************************

• • ft******* ********

12 Check SGs not ruptured. 12 ruptured SG(s) identified, isolate all ruptured SGs.

• Check no SG level - RISING IN AN UNCONTROLLED MANNER. 12.1 Locally close ruptured SG AFW flow control valves.

OR

• Direct HP to monitor main Ruptured SC lA lB lC steam lines for high radiation using FNP-O-RCP-25, MDAFWP TO HEALTH PHYSICS ACTIVITIES lA(lB.1C) SC DURING A RADIOLOGICAL Q1N23HV []3227A []3227B []3227C ACCIDENT.

TDAFWP TO 1A(lB,1C) SC Q1N23HV []3228A [13228B []3228C 12.2 Locally close ruptured SC steam supply to TDAFWP. (127 ft. AUX BLDG main steam valve room)

Ruptured SC 1A lB 1C TDAFWP STM SUPP FROM 1B(1C) SC Q1N12HV {]3235A []3235B 12.3 Verify ruptured SC atmospheric relief valves aligned.

Ruotured SC 1A lB lC 1A(1B,1C) MS ATMOS REL VLV PC []3371A [13371B [13371C 8.25 in 8.25 in 8.25 in AUTO AUTO AUTO Step 12 continued on next page.

Page Completed Page 25 of 40

FNP-1-ECP-O.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I 12.4 WHEN ruptured SG pressure less than 1035 psig associated atmospheric relief valve MIA station demand signal greater than zero.

THEN locally unlock and close one isolation valve.

Ruptured SG 1A lB 1C Q1N11V []004A []004C []OO4E

[1004B []004D []004F Key Z-131 Z-l25 Z-l23 Z-l26 Z-124 Z-l22 13 Check intact SG levels.

13.1 Check intact SG narrow range 13.1 Maintain maximum AFW flow to level - GREATER THAN 31%{48%1. intact SOs until narrow range level greater than 31%{48%) in at least one SG.

TDAFWP SPEED CONT

[1 SIC 3405 adjusted to 100%

13.2 [CA] WHEN intact narrow range 13.2 the TDAFWP can be SG level greater than operated normally due to loss 31%{48%1 , of control power, THEN maintain intact SG narrow THEN control the TDAFWP range level 31%-65%{48%-65%}. manually using FNP-1-SOP-22.0 AUXILIARY FEEDWATER SYSTEM, 13.2.1 Control TDAFWP speed. Appendix I.

TDAFWP SPEED CONT

[] SIC 3405 adjusted 13.2.2 Control TDAFWP flow control valves with handwheels.

Intact SG lA lB 1C TDAFWP TO lA(lB.1C) SG Q1N23HV []3228A [132288 []3228C Page Completed Page 26 of 40

FNP-1-ECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I

14 Minimize DC loads.

14.1 Deenergize non-essential DC loads using ATTACHMENT 4.

14.2 Direct electrical maintenance personnel to calculate remaining battery capacity using FNP-O-EMP-134O.10.

AUXILIARY BUILDING BATTERY CAPACITY CALCULATION FOR EMERGENCY DISCHARGE CONDITIONS.

15 Monitor CST level.

CST LVL

[1 LI 4132A

[1 LI 4132B 15.1 [CA] WHEN CST level less than 5.3 ft.

THEN align AFW pump suction to alternate source.

15.1.1 Place SW to AFW pump valve switches to OPEN. (BOP key operated switches)

MDAFWP SW SUPP

[] Q1N23MOV32O9A

[1 Q1N23MOV32O9B 15.1.2 Locally open SW to AFW pump valves.

MDAFWP SW SUPP

[1 Q1N23M0V3209A (100 ft. AUX BLDG 1A MDAFWP room)

MDAFWP SW SUPP

[] Q1N23MOV32O9B (100 ft. AUX BLDG lB MDAFWP room)

TDAFWP SW SUPP

[1 Q1N23MOV3216 (100 ft. AUX BLDG outside TDAFWP room)

Step 15 continued on next page.

Page Completed Page 27 of 40

FNP-1-ECP0.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I

15.2 1CA} WHEN CST level less than 3 ft.

THEN align TDAFWP suction to B train SW.

15.2.1 Unlock and open B train SW valves.

SW TO AFW PUMP XCON H Q1N23VO15D (Key Z-149)

(100 ft. AUX BLDG lB MDAFWP room)

SW TO AFW PUMP XCON H Q1N23VO15C (Key Z-158)

(100 ft. AUX BLDG above AEW pump rooms) 15.2.2 Unlock and close A train SW valve.

SW TO AFW PUMP XCON

[1 Q1N23VO15B (Key Z-159)

(100 ft. AUX BLDG above AFW pump rooms)

Page Completed Page 28 of 40

FNP-iECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I CAUTION: Accumulator nitrogen injection into the RCS may result from reduction of SC pressure to less than 100 psig.

NOTE: Reduction of intact SCs pressure should continue even if pressurizer level is lost or reactor vessel head voiding occurs.

Reduce intact SGs pressure to 200 psig.

16.1 Check at least one intact SC 16.1 Perform the following:

narrow range level CREATER THAN 31%(48%}. 16.1.1 Maintain maximum AFW flow to intact SCs until narrow range SC level greater than 31%{48% in at least one SC.

TDAFWP SPEED CONT

[] SIC 3405 adjusted to 100%

16.1.2 WHEN narrow range level in at least one intact SC is greater than 31%{48%}.

perform steps 16.2 through 16.7.

16.1.3 Proceed to step 17.

Step 16 continued on next page.

Page Completed Page 29 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained 16.2 WHEN P-12 light lit, THEN perform the following.

16.2.1 Block low steam line pressure SI.

STM LINE PRESS SI BLOCK - RESET

[1 A TRN to BLOCK

[1 B TRN to BLOCK 16.2.2 Verify blocked indication.

BYP & PERMISSIVE STM LINE ISOL.

SAFETY INJ.

[] TRAIN A BLOCKED light lit

[1 TRAIN B BLOCKED light lit 16.3 WHEN pressurizer pressure less than 2000 psig, THEN perform the following.

16.3.1 Block low pressurizer pressure SI.

PRZR PRESS SI BLOCK - RESET

[1 A TRN to BLOCK

[1 B TEN to BLOCK 16.3.2 Verify blocked indication.

BYP & PERMISSIVE PRZR. SAFETY INJECTION

[1 TRAIN A BLOCKED light lit

[1 TRAIN B BLOCKED light lit Step 16 continued on next page.

Page Completed Page 30 of 40

FNP-1-ECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained 16.4 Dump steam from intact SGs at maximum controllable rate.

16.4.1 Locally control intact SG atmospheric relief valves with handwheel. (127 ft.

AUX BLDG main steam valve room)

I Intact Sd 1A I {] 1C I Q1N11PCV [1 3371A Li 3371B 1 1 3371C(

16.5 Maintain at least one intact 16.5 IF all intact SC narrow range SC narrow range level -

levels less than 31%(48%},

GREATER THAN 31%{48%}. 3j perform the following.

16.5.1 Control TDAFWP speed. a) Locally close intact SC atmospheric relief valves TDAFWP with handwheels.

SPEED CONT Ii SIC 3405 adjusted Intact SCI 1A I lB I lC 16.5.2 Control TDAFWP flow control valve with manual Q1N11PCV lu 3371A F] 3371B1 Li 3371C handwheels.

b) WHEN at least one intact SC narrow range level I SG I 1A I lB ) lC I greater than 31%(48%).

TDAFWP THEN continue dumping TO lA(lBlC) SC steam from intact SGs.

Q1N23HV []3228A []3228B []3228C 16.6 Check RCS cold leg 16.6 Perform the following.

temperatures - GREATER THAN 2800F{2800F} 16.6.1 Locally control intact SG atmospheric relief valves RCS COLD LEG TEMP with handwheels to stop SG F] TR 410 pressure reduction.

Intact SG 1A lB 1C Q1N11PCV [1 3371A F] 3371B [1 3371C 16.6.2 Proceed to step 17.

Step 16 continued on next page.

Page Completed Page 31 of 40

FNP1-ECP-O.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained 16.7 Check intact SG pressures -

16.1 Perform the following.

LESS THAN 200 psig.

16.7.1 WUJJ intact SG pressures less than 200 psig.

THEN perform step 16.8.

16.7.2 Proceed to step 17.

16.8 Locally control intact SC atmospheric relief valves wit h

handwheels to maintain intact SG pressure at 200 psig.

Intact SC 1A lB 1C Q1N11PCV [] 3371A {j 3371B [1 3371C 17 Check startup rate LESS 17 Establish subcriticality.

THAN OR EQUAL TO ZERO.

17.1 Locally control intact SC SRi (2)

S/U RATE atmospheric relief valves wit h

handwheels to raise SG

[] NI 31D

[] NI 32D pressure.

IR1 (2)

S/U RATE IQ Intact 501 1A I lB I 1C

[1

[]

NI 35D NI 36D I 3371A H 3371BJ Ii 3371C1 17.2 startup rate less than or equal to zero.

THEN locally control intact SG atmospheric relief valves wit h

handwheels to maintain stab le pressure in all intact SGs.

Intact SC 1A lB 1C Q1N11PCV {] 3371A [1 3371B [1 3371C Page Completed Page 32 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I NOTE: Depressurization of SGs will resu lt in SI actuation. Resetting SI defeats automatic loading of the emer gency busses to allow only manual starting of loads by the oper ator.

_18 Check SI signal status.

18.1 Check SI HAS BEEN ACTUATED 18.1 Perform the following.

[1 MLB-1 1.-i on (A TRN) 18.1.1 WHEN SI actuated.

[] MLB-1 11-1 on (B TRN) perform Steps 18.2.

19. 20 and 21.

18.1.2 Proceed to Step 22.

18.2 Verify SI RESET.

18.2 any train will reset using the MCB SI RESET

[1 MLB-i 1-1 off (A TRN) pushbuttons,

[] MLB-1 11-1 off (B TRN) j place the affected train S82l RESET switch to RESET.

(SSPS TEST CAB.)

Verify PHASE A CT14T ISO.

19.1 Verify PHASE A CTMT ISO -

ACTUATED.

1 MLB-2 1-1 lit 1 MLB-2 11-1 lit 19.2 Check all MLB-2 lights LIT.

19.2 Verify PHASE A CTMT ISO alignment using ATTACHMENT 5, PHASE A CONTAINNENT ISOLATION.

Page Completed Page 33 of 40

FNP-l-ECP-0.0 LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I

__20 Verify containment ventilation isolation.

20.1 Verify containment purge 20.1 Locally close accessible dampers CLOSED.

dampers by failing air supply.

[1 3197 PURGE EXHAUST (121 ft. PPR)

[1 3198D H 3l98A

[1 3l98C LI 3196 PURGE SUPPLY (121 ft. PPR)

[1 3l98A

[] 3198D

[1 3198B PURGE EXHAUST FAN INTAKE (155 ft. PURGE VENT EQUIP RM)

[1 3l98B PURGE SUPPLY FAN EXH (155 ft. CTMT AIR EQUIP RM)

[1 3198C 20.2 Verify containment mini purge 20.2 Locally close accessible dampers CLOSED.

dampers by failing air supply.

(121 ft. PPR)

CTMT PURGE DMPRS MINI-2866C & 2867C CTMT MINI PURGE FULL-3198A & 3l98D SUPPLY DMPR F] 2866C F] 2866C

[] 2867C CTMT MINI PURGE CTMT PURGE DMPRS EXHAUST DAMPER MINI-2866D & 2867D FULL-3196 & 3197 F] 2867C BOTH-3198B & 3198C F] 2866D F] 2867D 20.3 Stop MINI PURGE SUPP/EXH FAN.

_Page Completed Page 34 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I 21 Check PHASE B CTMT ISO not required.

21.1 Check containment pressure 21.1 Verify PHASE B CTMT ISO.

HAS REMAINED LESS THAN 27 psig. 21.1.1 Verify PHASE B CTMT ISO actuated.

1 MLB-3 1-1 not lit

[1 MLB-3 6-1 not lit 21.1.2 Verify PHASE B CTMT ISO alignment.

CCW FROM RCP THRM BARR H Q1P17HV3O45 closed

[] Q1P17HV3184 closed CCW FROM RCP OIL CLRS

[1 Q1P17MOV3182 closed

[1 Q1P17MOV3O46 closed CCW TO RCP CLRS

[1 Q1P17M0V3052 closed IA TO CTMT El Q1P19HV3611 closed (BOP) 21.1.3 Reset containment spray signal.

CS RESET

[1 A TRN

[1 B TRN

__22 [CA] Locally monitor spent fuel pool level. (155 ft. AUX BLDG spent fuel room) 22.1 Check spent fuel pool level - 22.1 Consult TSC staff to determine GREATER THAN 153 ft. spent fuel pool makeup requirements.

23 Check core exit T/Cs - LESS 23 IF fifth hottest core exit T/C THAN 1200°F. greater than 1200°F rising, go to FNP-1-SACRG-1.

SEVERE ACCIDENT CONTROL ROOM GUIDELINE INITIAL RESPONSE.

Page Completed Page 35 of 40

FNP-l-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I

CAUTION: Bus failure could result from starting loads in excess of the capacity of the power source.

STARThereafterpowerrest

_24 Check at least one 4160 V ESF busses of ENERGIZED 24 Return to Step 11 OBSERVE ored J

CAUTION PRIOR TO STEP 11

[1 A Train (F & K) power availab le lights lit

[] B Train (G & L) power available lights lit 25 Verify SW system operating.

25.1 Verify at least one SW train -

HAS TWO SW PUMPs RUNNING.

[1 A Train (1A.1B or 1C)

[1 B Train (lD1E or 1C) 25.2 Verify SW flow through at least one train of containment coolers - GREATER THAN 0 gpni.

SW THROUGH CTMT CLRS INLET

[] Fl 3O13A

[1 Fl 3O13B 25.3 Verify SW to DG BLDG valves OPEN.

SW TO/FROM DG BLDG - A HDR

[] 01P16V519/537 SW TO/FROM DC BLDG - B HDR

[1 Q1P16V518/536

_Page Completed Page 36 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I I

__26 Verify electrical alignment.

26.1 Verify battery charger in at 26.1 Verify battery charger supply least one train - ENERGIZED, breaker in at least one train closed.

[] A Train (1A or 1C) amps > 0

[] B Train (lB or 1C) amps > 0

[] A Train (BKR EDO4-1)

[] B Train (BKR EEO5-l) 26.2 IF A train 4160 V buses NOT energized, THEN proceed to step 27.

C UTION: To ensure adequate supply voltage to all class lE loads and to meet short circuit analysis constraints, only one air compressor, lC (preferred) or lA, should be powered from the diesel generator. Each air compressor will consume 0.16 MW of diese l generator load.

26.3 Verify 1C air compressor in 26.3 Align 1A air compressor for service, service.

2 .3.1 1D 4160 V BUS a) Verify lC air compressor energized, handswitch in OFF.

THEN verify lA 600 V LC emergency section energized b) Verify SI RESET.

from 1D 600 V LC.

26.3.1.1

[1 MLB-1 1-1 not lit Verify open BKR EAO8-1.

[1 MLB-1 11-1 not lit 26.3.1.2 Verify closed BKRs c) Verify B1F sequencer EDO8-1 and EAO9-l. RESET. (139 ft. AUX BLDG A train SWGR room) 26.3.2 Verify 1C air compressor handswitch in AUTO after Verify BKR DF13 closed.

d)

START/RUN.

(lF 4160 V bus tie to 1H 4160 V bus) 26.3.3 Verify 1C air compressor started. e) IF 1H 4160 V bus energized.

THEN energize 10 600 V LC from normal supply.

[1 BKR DHO1 closed

[1 BKR EGO2-1 closed f) Start 1A AIR COMPRESSOR.

Page Completed Page 37 of 40

FNP-1-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I - 1 2 [CA] Maintain intact SG pressures stable at current value.

7.1 Restore SC atmospheric relief 27.1 Perform the following.

relief valve jacking devices to NEUTRAL position. 27.1.1 Locally control intact SC atmospheric relief valves 1A(1B.1C) MS ATMOS with handwheels to maintain REL VLV intact SG pressure stable LI PC 3371A at current value.

PC 3371B PC 3371C Intact Sd 1A I [I lB I [I 1C I Q1N11PCV I H 3371AI 3371B1 3371CI 27.1.2 Proceed to step 28.

27.2 Control SC atmospheric relief valves to maintain intact SC pressure stable at current value.

1A(1B,1C) MS ATMOS REL VLV Li PC 3371A adjusted

[1 PC 3371B adjusted

[I PC 3371C adjusted

.28 Restore intact SG AEW flow control valve jacking devices to normal position.

Intact SC 1A lB 1C IDAFWP TO 1A(1B.1C) SC flN23HV LI 3227A LI 3227B [I 3227C AFWP TO A(1B.1C) SC flN23HV [I 3228A [1 3228B [I 3228C Page Completed Page 38 of 40

FNP-i-ECP-O.O LOSS OF ALL AC POWER Revision 22 Step Action/Expected Response Response NOT Obtained I I NOTE: If RCP seal cooling was previously isola ted, further cooling of the RCP seals will be established by natural circulation cooldown as directed in subsequent procedures.

Evaluate plant conditions.

29.1 Check SI not required. ,ØøO*29.1 Go to FNP-l-ECPO.2, LOSS OF ALL AC POWER RECOVERY WITH SI

• Check SUB COOLED MARGIN REQUIRED.

MONITOR indication - GREATER than l6°F{45°F} SUBCOOLED IN CETC MODE.

Transition made out of ECP.O.O

• Check pressurizer level -

GREATER THAN l3%(43%}.

• Check SI equipment -

ACTUATED UPON AC POWER HAS NOT RESTORATION such that SI flow occurred.

29.2 Go to FNP-l-ECP-O.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED.

-END Page 39 of 40

FNP-l-ECP-O.l LOSS OF ALL AC POWER RECOVERY WITH OUT SI REQUIRED Revision 18 Step Action/Expected Response Response NOT Obtained 1 1 I

• • • • ***a****************

CAUTION: [CA] Ji an SI signal is actuated prior to performing step 7 of this procedure. jjJ it should be rese t to permit manual loading of equipment. SI

• *a* a *** *** *******

• • • • *** a CAUTIONt Critical: safety function status tréé s shoiild be inonitred foz information only No Function Restoration Procedur implemented until completion of e should be step 12

• * * * *

• a a * * *a** * * * * * * * * * * * *

• 1 Check RCP Seal Isolation wed direction to MONITOR CSP it Status: P-ti 1 1.1 Check RCP seal injection 1.1 IF isolation valves - CLOSED known, (139 ft. AUX BLDG rad side THEN check charging filter room) pump status:

SEAL WATER INJ 1.1.1 CHG PUMP FILTER A INLET running.

jj go to Step 2.

[j Q1E21V127A closed

[1 Q1E21V127C closed 1.1.2 11 CHG PUMP NQI running.

manually close valves SEAL WATER INJ before starting CHG PUMP.

FILTER B INLET

[1 Q1E21V127B closed

[1 Q1E21V127D closed Step 1 continued on next page.

.Page Completed Page 2 of 28

FNP-i-ECP-O.2 LOSS OF ALL AC POWER RECOVE RY WITH SI REQUIRED Revision 18 Step Action/Expected Response Response NOT Obtained I I CAUTIONr Critical safety fthctionst atus trees should be monito information only. No Functio redfor n Restoration Procedure sho implemented until complet uld be ion of step 13.

• * * * *,__-I____________. * * * * * * * * *

• 1 Reset SI signals.

1.1 Verify SI - RESET.

1 MLB-1 1-1 not lit (A TRN

)

[1 MLB-1 11-1 not lit (B TRN

)

Lile 1iL S821 RESET switch to RESET.

(SSPS TEST CAB.)

1.2 Reset B1F sequencer. (139 ft.

AUX BLDG A train SWGR room

)

1.3 Reset BiG sequencer. (121 ft.

AUX BLDG B train SWGR room

)

2 [CA] Check RWST level - GREATER 2 Establish cold leg THAN 12.5 ft.

recirculation alignment by RWST performing the following.

LVL 2.1 Verify recirculation valve

[1 LI 4075A disconnects closed using

[1 LI 4075B ATTACHMENT 2.

2.2 Verify ECCS aligned for recirculation using ATTACHMENT 3.

2.3 Go to Step 4.

Page Completed Page 2 of 15