ML21302A214

301 Post Exam Comments

ML21302A214
Person / Time
Site:	Surry
Issue date:	10/29/2021
From:	Virginia Electric & Power Co (VEPCO)
To:	NRC/RGN-II
References
Download: ML21302A214 (26)

Text

ML21302A214 Surry Power Station 2021 NRC LICENSE EXAM POST EXAM COMMENTS

Surry 2021 NRC Exam Post Exam Comments Question 5 A. Post Exam Comments:

Source: Applicant: 55-75718 Question: Given the following:

Unit 1 is at 100% power.

The Unit 1 RO has just observed the following:

o Annunciators 1C-D3/-E3/-F3, RCP 1A/1B/1C SEAL WTR LO INJ FLOW, are all alarming.

o All Seal Injection flows indicate 2 gpm each.

o Charging flow has lowered from 88 gpm to 63 gpm.

o Charging Pump discharge pressure lowered to 2315 psig.

Which ONE of the following completes the statement below?

1) The abnormal Seal Injection flows are due to a __(1)__.

2) In accordance with 1-AP-8.00, LOSS OF NORMAL CHARGING FLOW, a manual Reactor Trip __(2)__ required.

A. 1) clogged Seal Injection filter

2) is not B. 1) Seal Injection piping break

2) is not C. 1) clogged Seal Injection filter

2) is D. 1) Seal Injection piping break

2) is Answer: B

Reference:

1-AP-8.00/1-AP-9.00 Comment: AP-9 requires a reactor trip with a loss of seal injection.

Facility Candidate appeared to confuse 1-AP-8.00 with 1-AP-9.00. AP-9.00 will require a Position: reactor trip if all seal injection is lost and Thermal Barrier CC flow is lost. The question is adequate as written, no change is required.

Change None required.

Surry 2021 NRC Exam Post Exam Comments Question 14 Source: Applicants: 55-72930, 55-75723 Question Initial Conditions:

Unit 1 and Unit 2 are operating at 100%.

Unit 1 Gen H2 pressure is at 60 psig, and stable.

The plant has been notified by SOC that there are significant grid instabilities.

The SOC has requested maximum power generation from both units.

The Operator observes rising MVARS, and is attempting to lower MVARS.

Current Conditions:

The following Annunciators are alarming:

o 1J-A8, OVER EXCITATION LIMIT.

o 1J-B7, VREG CHANNEL A LOCAL.

The BOP reports the following Unit 1 changes:

o Gen MWe lowered from 905 to 900 MWe.

o Gen MVARS rose from + 10 to +350 MVARS.

o Voltage Regulators have shifted and are as shown.

Which ONE of the following completes the statements below?

1) Based on the information given in the current conditions, the Main Generator limits __(1)__ being exceeded.

2) Per ARP 1J-A8, OVER EXCITATION LIMIT the operator should attempt to regain control of Generator Voltage using the __(2)__.

REFERENCE PROVIDED A. 1) are

2) Local RAISE/LOWER pushbuttons B. 1) are NOT

2) MCR Excitation Level Raise/Lower Switch C. 1) are

2) MCR Excitation Level Raise/Lower Switch D. 1) are NOT

2) Local RAISE/LOWER pushbuttons Answer: C

Surry 2021 NRC Exam Post Exam Comments Question 14

Reference:

DRP-003 Comment: The point looks to be right on the curve Facility The comment is regarding the point where current MW and VARs indication Position: intersect on the provided Generator Capability Curve (1-DRP-003 Att. 52).

Feedback during validation requested a larger and clearer curve. The curve used as an open reference was zoomed slightly larger than the curve on a printed version of 1-DRP-003. Precise analysis of the graph reveals the point to clearly be a reasonable distance from the curve. The question is adequate as written.

Change: None

Surry 2021 NRC Exam Post Exam Comments Question 21 Source: Applicant 55-75718 Question: Given the following:

Unit 2 is in Refueling Shutdown with core on-load in progress.

Reactor power is 222 cps as indicated on the Audio SR Count Drawer.

The following alarms and indications occur:

o 2G-A3, NIS SOURCE RNG LOSS OF DET VOLT, is LIT.

o Audio SR Count Drawer indication is 0 cps.

o N-31 benchboard indication is off-scale low.

o N-32 benchboard indication is approximately 200 cps.

Audible count rate in Unit 2 Containment has been lost.

The team has entered 1-AP-4.00, NUCLEAR INSTRUMENTATION MALFUNCTION.

Which ONE of the following completes both statements?

1) 1-AP-4.00 __(1)__ contain steps for the operator to restore the audible count rate in containment without I&C support.

2) IF the audible count rate in containment is subsequently restored using N-32, THEN refueling operations __(2)__.

A. 1) does NOT

2) may continue B. 1) does NOT

2) are still NOT allowed C. 1) does

2) are still NOT allowed D. 1) does

2) may continue Answer: C

Reference:

1-AP-4.00, Tech Specs Comment: Underlined portion of Part 1 led me to the wrong answer.

Facility 1-AP-4.00 has directions for shifting the audible count rate in Containment. There are Position: other actions in AP-4.00 that do require I&C support, such as placing bistables in trip. The question is adequate as written.

Change None required.

Reference:

Surry 2021 NRC Exam Post Exam Comments Question 23 Source: Applicant: 55-75723 Question: Given the following:

Both units are at 100% power.

Annunciator 1-RMA-D6, VENT STACK #2 PART ALERT/HI, is alarming.

The High LED indicator is lit for 1-VG-RI-131B, VENT #2 NORMAL GAS INDICATOR.

The team is performing 0-AP-5.20, RADIATION MONITOR SYSTEM VENTILATION VENT HIGH ALARM.

Which ONE of the following completes the questions below?

1) In accordance with 0-AP-5.20, what action will the team direct to identify the leak location?

2) If the inlet flange of 1-GW-RV-111A, SAMPLE COMPRESSOR 1-GW-C-4A SUCTION RELIEF VALVE, is subsequently identified as the leak location, where must the team send a field operator to isolate the leak?

REFERENCE PROVIDED A. 1) Have HP sample the area for Iodine and Particulates.

2) Fuel Building.

B. 1) Align the affected area to Filtered Exhaust.

2) Fuel Building.

C. 1) Have HP sample the area for Iodine and Particulates.

2) PG Pump House.

D. 1) Align the affected area to Filtered Exhaust.

2) PG Pump House.

Answer: D

Reference:

0-AP-5.20, 11448-FM-090A Sheets 1 and 2

Surry 2021 NRC Exam Post Exam Comments Question 23 Comment: To align the affected area to filtered exhaust - how do you know the affected area - also, what does HP do when sent out?

Facility A caution at step 10 of 0-AP-5.20 outlines the overall strategy, stating the Position: following:

When the fans in Steps 8 and 9 are stopped, the vent vent activity will lower.

When the alignments are performed IAW Attachment 2 and the filtered exhaust fan is started, the vent vent radiation indication should rise for the area that caused the vent vent high alarm. If the activity does not rise within approximately 1 minute, the fan should be stopped and the next alignment should be performed.

If the area is not known, Step 10 RNO directs placing one area at a time on filtered exhaust, using a change in ventilation activity to determine which area is the affected area. The question is adequate as written.

Change None required.

Reference:

Surry 2021 NRC Exam Post Exam Comments Question 24 Source: Applicant: 55-75723 Question: 24 A Fuel Shuffle is being performed in the Spent Fuel pool, and a Fuel Assembly has just been seated. The following annunciators alarmed and were determined to be valid, i.e., not an instrument failure:

0-RM-C3, FUEL PIT BRDG ALERT/FAILURE.

0-RM-D3, 1-RM-RI-153 HIGH.

Spent fuel pool is stable/normal and no other abnormalities were observed or noted.

Which ONE of the following correctly completes both statements?

1) In accordance with 0-RM-C3 and D-3, the Fuel Building __(1)__ required to be immediately evacuated.

2) The Fuel Pit Bridge radiation detector is a/an __(2)__.

A. 1) is NOT

2) ion chamber B. 1) is NOT

2) geiger mueller C. 1) is

2) ion chamber D. 1) is

2) geiger mueller Answer: C

Reference:

ARP 0-RM-D3, 0-AP-22.00 Comment: Why are we not using the AP (0-AP-22.00)?

This question is using the ARP to determine if evacuation is necessary.

Facility 0-RM-D3 directs evacuation after verifying the alarm is valid, which is given in Position: the question stem. Additionally, 0-AP-22.00, FUEL HANDLING ABNORMAL CONDITIONS, states the same thing Evacuation is required. The question is adequate as written.

Change None required.

Reference:

Surry 2021 NRC Exam Post Exam Comments Question 28 Source: Applicants: 55-75720, 55-75722 Question: Initial Conditions:

Unit 1 Reactor startup was in progress following a Forced outage for RCP Corrective maintenance.

Power was at 1 x 10 -8 amps and holding for Critical Rod data.

The crew has entered 1-AP-9.00, RCP ABNORMAL CONDITIONS, due to rising temp. and vibration trends, and has suspended any further power increase.

Current Conditions (10 minutes):

The RO has plotted the most limiting 1-RC-P-1A parameters over the last 10 minutes and are as follows:

Parameter Initial Reading Current Reading (10 min)

Lower Thrust bearing 110 oF 145 oF RCP Shaft vibration 9 mils 15.5 mils Which ONE of the following completes the statements below?

1) Based on these trends, and assuming the trends continue at the same rate, the first parameter that will require the pump to be shutdown is the __(1)__.

2) In accordance with the annunciator procedures and 1-AP-9.00, at this power level, a manual reactor trip __(2)__ required before the RCP is shutdown.

A. 1) Lower Thrust bearing

2) is B. 1) Lower Thrust bearing

2) is NOT C. 1) RCP Shaft vibration

2) is NOT D. 1) RCP Shaft vibration

2) is Answer: D

Reference:

1-AP-9.00 Comment: Step 19 of 1-AP-9.00 only directs a reactor trip if the unit is online.

Surry 2021 NRC Exam Post Exam Comments Question 28 Facility In this question, the unit is critical, but not online. While the applicant is correct in that Position: Step 19 directs a reactor trip (without first securing the RCP) if the unit is not online, a note at the beginning on 1-AP-9.00 states the following:

If an RCP needs to be tripped with the Reactor critical, a Reactor trip must be performed before securing the RCP. Tech Specs also states that the reactor shall not be brought critical with less than three pumps (RCPs) in non-isolated loops. This is required RO knowledge.

The question is adequate as written.

Change None required.

Reference:

Surry 2021 NRC Exam Post Exam Comments Question 48 Source: Applicant: 55-24574 Question: Given the following:

Unit 2 is at 25% power.

A loss of the Unit 2 A DC bus occurs.

A loss of offsite power also occurs.

Which ONE of the following completes the statements below?

1) The #2 EDG ___(1)___ automatically load onto the 2H bus.

2) If an automatic turbine trip occurred, Main Generator excitation ___(2)___

remain energized with no operator action.

A. 1) will NOT

2) will NOT B. 1) will

2) will NOT C. 1) will NOT

2) will D. 1) will

2) will Answer: C

Reference:

2-AP-10.06, ND-90.3-LP-6, 125v DC Distribution System Comment: I confused the output breaker with excitation status.

Facility This question tests the applicants knowledge on the plant effects for a loss of Position: Unit 2 A DC bus. The specific knowledge items tested are major effects of a loss of the A DC bus. The question is adequate as written, no change is required.

Change None Reference

Surry 2021 NRC Exam Post Exam Comments Question 67 Source: Applicant: 55-75723 Question: Given the following:

Unit 1 is at 25% power.

Unit 1 is preparing to perform SI Accumulator recirculation and sampling per 1-OP-SI-002, SAFETY INJECTION ACCUMULATORS.

Administrative control will be required for two manual valves, both located in the Auxiliary Building.

Which ONE of the following completes the following statements in accordance with SUADM-O-26, ADMINISTRATIVE CONTROL OF OPERATIONAL COMPONENTS, and 1-OP-SI-002?

1) One operator __(1)__ permitted to be assigned administrative control of both manual valves.

2) It __(2)__ acceptable for an operator assigned to the Fire Team to also have an administrative control function.

A. 1) is NOT

2) is NOT B. 1) is NOT

2) is C. 1) is

2) is NOT D. 1) is

2) is Answer: B

Reference:

SUADM-O-26, 1-OP-SI-002 Comment: Part 2 was a recent procedure change that the class did not get - look for date of change. Part 2 is minutia.

Facility This revision was verified to have been made in October 2019. The facility Position: does not agree that this aspect of administrative control responsibilities is minutia. The question is adequate as written.

Reference None required.

Surry 2021 NRC Exam Post Exam Comments Question 70 Source: Applicants: 55-75722, 55-24252 Question: Given the following:

1B Waste Gas Decay Tank (WGDT) is in service on the A oxygen analyzer.

Preparations are being made to place the B WGDT on holdup for release in accordance with OP-23.2.1, PUTTING WGDT 1B ON HOLDUP AND WGDT 1A IN SERVICE.

Initial Hydrogen concentration in B WGDT is 8.1%.

B WGDT pressure is 115 psig.

Annunciator 0-WD-D9, WASTE GAS DECAY TANKS HI O2, is LIT and verified at the alarm setpoint.

Which ONE of the following completes both statements?

1) In accordance with OP-23.2.1, release of B WGDT __(1)__ permitted.

2) In accordance with TS 3.11.B, Gas Storage Tanks, the maximum curie content in each gas storage tank is limited to a maximum of __(2)__ in order to limit the total body exposure to an individual at the exclusion boundary.

A. 1) is

2) 24,600 curies B. 1) is NOT

2) 24,600 curies C. 1) is

2) 12,300 curies D. 1) is NOT

2) 12,300 curies Answer: A

Reference:

OP-23.2.1 Comment: Do not believe that the referenced procedure provides adequate guidance to answer this question.

Surry 2021 NRC Exam Post Exam Comments Question 70 Facility We agree with the Applicants comments.

Position: Problem Statement:

Question part 1 references OP-23.2.1 (PUTTING WGDT 1B ON HOLDUP AND WGDT 1A IN SERVICE). Review of this document reveals that there is no guidance, nor any associated limitations, related to the release of a WGDT (see reference below).

Trainees answered the question based on the knowledge that this procedure contained no guidance related to release. All candidates therefore selected B as the correct answer.

Proposed Resolution: Change the correct answer to B.

Reference OP-23.2.1 SU-PROC-000-OP-2 3.2.1.pdf

Surry 2021 NRC Exam Post Exam Comments Question 76 Source: Applicants: 55-75720, 55-75723 Question: 76 Initial Conditions:

Unit 1 is at Hot Shutdown.

The A Reactor Coolant Pump (1-RC-P-1A) is secured, B and C RCPs are running.

The crew is lowering RCS boron concentration to Hot Zero Power Boron Concentration per 1-GOP-1.3, UNIT STARTUP, RCS HEATUP FROM 345oF TO HSD.

Current Conditions:

The following conditions exist for the B Reactor Coolant Pump (1-RC-P-1B) :

1C-B5, RCP 1B SEAL 2 LO INLET PRESS, is LIT.

1C-E4, RCP 1B SEAL LEAKOFF LO FLOW, is LIT.

RCP B SEAL PRESS 1-CH-PI-1155A is 1150 psig.

RCP SEAL LEAKOFF FLOW on 1-CH-FR-1190 is 0.00 gpm.

Which ONE of the following completes the following statements?

1-RC-P-1B is experiencing a __(1) __.

After securing 1-RC-P-1B, there __(2) __ be sufficient forced RCS flow to provide adequate boron mixing in the RCS per Tech Spec 3.1.A.1, Reactor Coolant Pumps Basis.

A. 1) failure of #3 seal

2) will B. 1) blockage in the seal return line

2) will not C. 1) failure of #3 seal

2) will not D. 1) blockage in the seal return line

2) will Answer: A

Reference:

1-AP-9.00 Comment: A #3 RCP seal failure would not lower all the way to 0 gpm; it still reads a low flow in the simulator.

Surry 2021 NRC Exam Post Exam Comments Question 76 Facility After the exam review, a #3 seal failure was run on the reference simulator.

Position: Indicated Seal Leakoff flow lowered to 0.00 gpm as stated in the stem. In addition, it was verified that 1-CH-PI-1155A lowered to ~1150 psig. A seal return line blockage was also run on a separate RCP: Although seal return flow lowered to 0.00 gpm, the Seal Pressure indication rose to full RCS pressure, as expected for seal return line blockage or closure of the seal return control valve.

Candidates comments are accurate for a partial #3 seal failure. The question is adequate as written Change None required Reference

Surry 2021 NRC Exam Post Exam Comments Question 79 Source: Applicant: 55-24251 Question: Initial Conditions (at time 0030):

Both units are at 100% power.

The AAC Diesel Generator is tagged out.

Security reported a tornado touched down in the switchyard and traveled across the Condensate Polishing Building.

A loss of all offsite power occurred on both units.

1. 1 EDG failed to start and is not available.

Current Conditions (at time 0047):

Breaker 15J3 (#3 EDG to 1J Bus) cannot be closed.

CETC Temperature is 702°F and rising.

RVLIS Full Range is 98% and stable.

Which ONE of the following is the highest required EAL classification for this event?

REFERENCE PROVIDED A. General Emergency B. Notification Of Unusual Event C. Alert D. Site Area Emergency Answer: D

Reference:

EAL Matrices Comment: I requested the EAL basis document during the exam. I did not have enough information to rule out one bullet in EAL MG-1.1.

Surry 2021 NRC Exam Post Exam Comments Question 79 Facility The bullet referenced is the following:

Position: Long-term RCS heat removal capability is not likely to be established and maintained per procedure. In this scenario, the event has only been in progress for 17 minutes; there has not been adequate time to determine whether station procedures will successfully restore cooling (including FLEX strategies per the EAL basis document). The candidate did request the EAL Basis document but after discussions with the Chief NRC Examiner it was determined that there was adequate information to answer the question. The question is adequate as written, no change required.

Change None Reference

Surry 2021 NRC Exam Post Exam Comments Question 80 Source: Applicants: 55-75723, 55-24252 Question: Initial Conditions:

Unit 1 is at Hot Shutdown, Unit 2 is shutdown with fuel offloaded.

Today is Wednesday.

1410: Annunciator 1D-G5, SW OR CC PPS DISCH TO CHRG PPS LO PRESS is in alarm.

The crew enters 0-AP-12.00, SERVICE WATER SYSTEM ABNORMAL CONDITIONS.

Current Conditions (10 minutes later):

The RO starts recording Unit 1 operating CHG pump bearing temperatures.

o 1420 = 170 oF o 1430 = 175 oF o 1440 = 180 oF o 1450 = 185 oF o 1500 = 190 oF 1500: All Unit 1 Charging pumps are declared inoperable.

Based on the current conditions which ONE of the following answers the questions below?

1) In accordance with 0-AP-12.00, the earliest time the operating charging pump is required to be shifted is __(1)__.

2) The latest time Unit 1 is required to be in Cold Shutdown is __(2)__.

A. 1) 1440

2) Friday at 0300 B. 1) 1450

2) Thursday at 2100 C. 1) 1450

2) Friday at 0300 D. 1) 1440

2) Thursday at 2100 Answer: D

Reference:

0-AP-12.00, Tech Specs Comment: The referenced procedure is vague and ambiguous.

Surry 2021 NRC Exam Post Exam Comments Question 80 Facility We agree with the Applicants position.

Position:

Problem Statement:

Question part 1 refers to AP-12.00 Step 3 and the associated CAUTION and NOTES (see below).

The issue with this question is the ambiguity of the procedural guidance.

Consider the following:

o ILT Training Materials (Lesson plan ND-95.3-LP-2 page 4) defines the following terms:

o Shall - Mandatory Requirements o Should - Non-mandatory, preferred or suggested.

o The procedure states (via NOTE) that Preparations should be made to shift charging pumps if bearing temperatures exceed 180°F.

o The CAUTION states that charging pumps should be secured if bearing temperatures reach 185°F.

o Therefore, what actions are required if bearing temps are 181°F?

o Is it time for the team to make preparations, or to shift pumps?

o Performing step 3 would direct the operators to the RNO, which directs Shift CHG pumps as necessary. The words as necessary indicates that although bearing temps are not less than 180°F, shifting of pumps is not mandatory.

Clear guidance does not exist when shifting of charging pumps is REQUIRED (shall) as asked in the question.

1) In accordance with 0-AP-12.00, the earliest time the operating charging pump is required to be shifted is __(1)__.

Surry 2021 NRC Exam Post Exam Comments Question 80 Proposed Resolution: Remove this question from the exam.

References:

SU-PROC-000-0-AP- ND-95.3-LP-2, EP 12.00[r015.00].pdf Writer Format Rev 18.doc

Surry 2021 NRC Exam Post Exam Comments Question 94 Source: Applicant: 55-24252 Question: 94 Per LI-AA-700, Fatigue Management and Work Hour Limits for Covered Workers, which ONE of the following completes the statements below?

1) During online operations, and without issuance of a waiver, ensure the individual does not work more than weekly average of __(1)__ hours over a 6-week period.

2) The Operations Shift Manager __(2)__ requisite signature authority to sign for Approval of Attachment 2, 10 CFR 26 Limits Waiver.

A. 1) 72

2) has B. 1) 54

2) has C. 1) 54

2) does NOT have D. 1) 72

2) does NOT have Answer: C

Reference:

LI-AA-700 Comment: LI-AA-700 states the Shift Manager does have the authority to approve a waiver.

Surry 2021 NRC Exam Post Exam Comments Question 94 Facility LI-AA-700 p.24 has the following information:

Position:

Although the Shift Manager is responsible for initiation of the waiver, a Site Senior-Level Manager is required to approve the waiver. No change is required, the question is adequate.

Reference None

Surry 2017 NRC Exam Post Exam Comments EXAM ANALYSIS Q99 Source: Applicants: 55-75723; 55-24574; 55-75720 Question: 99 Initial Conditions:

Unit 1 was at 100%.

A Reactor Tip and Safety Injection occurred.

A field operator reports water and steam coming from the Unit 1 Safeguards Valve Pit door.

The team entered 1-E-0, REACTOR TRIP OR SAFETY INJECTION.

The Assistant RO performed Attachment 1, SYSTEM ALIGNMENT VERIFICATION.

At Attachment 1 Step 12, CHECK SI FLOW, Safety Injection was reset.

Current Conditions:

The SRO incorrectly transitioned from 1-E-0, to 1-E-1, LOSS OF REACTOR OR SECONDARY COOLANT.

The team is at 1-E-1, Step 2, CHECK IF SGs ARE NOT FAULTED.

The SRO identifies that the team should be in 1-ECA-1.2, LOCA OUTSIDE CONTAINMENT.

A Safety Injection re-initiation occurs.

Which ONE of the following completes both statements in accordance with OP-AP-104, EMERGENCY AND ABNORMAL OPERATING PROCEDURES?

3) After the SRO exited 1-E-0, the team ___(1)___ permitted to reset SI again, using Step 12 of 1-E-0 Attachment 1.

4) In order to transition to 1-ECA-1.2, from 1-E-1 step 2, the SRO should __(2)__ .

A. 1) is NOT

2) go directly to 1-E-1, step 18, INITIATE EVALUATION OF PLANT STATUS B. 1) is

2) go directly to 1-E-1, step 18, INITIATE EVALUATION OF PLANT STATUS C. 1) is NOT

2) go to 1-ES-0.0, REDIAGNOSIS D. 1) is

2) go to 1-ES-0.0, REDIAGNOSIS Answer: D

Reference:

OP-AP-104 Comment: The Answer is incorrect. The correct answer should be C.

Surry 2017 NRC Exam Post Exam Comments EXAM ANALYSIS Q99 Facility We agree with the Applicants. After reviewing the referenced procedures again we Position: determined the following.

Problem Statement:

Question part 1 asks:

After the SRO exited 1-E-0, the team ___(1)___ permitted to reset SI again, using Step 12 of 1-E-0 Attachment 1.

This question is evaluating the candidates application of the second note prior to step 12.

The concern with this question is whether this NOTE persists in subsequent procedures (outside of 1-E-0). Note that step 12 is NOT a continuous action step (no *).

From OP-AP-104 concerning NOTES:

3.4.1 REVIEW the following for NOTEs and CAUTIONs:

• NOTE or CAUTION are considered part of the step that it precedes.

• Unless stated otherwise, NOTEs and CAUTIONs apply throughout the procedure. If an operator returns to a procedure, any applicable NOTEs or CAUTIONs within that procedure are once again in effect.

• NOTEs and CAUTIONs may also be used to provide a contingent transition based on changes in plant conditions. Passive action statements may be used when continuous monitoring of a specific plant condition and an associated action is required.

• NOTEs and CAUTIONs before the first step of a procedure typically apply to the entire procedure.

Surry 2017 NRC Exam Post Exam Comments EXAM ANALYSIS Q99 The highlighted text above indicates that NOTE and CAUTIONS do not carry forth into subsequent procedures. This directly contradicts Part 1 question.

Note that continuous action steps may transfer from EOP to EOP. OP-AP-104 contains the following NOTE prior to step 3.4.6:

NOTE: Continuous Action Steps may transfer from EOP to EOP. One example is RCS Temperature control. Temperature control guidance is applicable from the initial instructions on how and at what values to maintain RCS temperature until another EOP changes the temperature band.

But this note is not applicable as step 12 is not a CAS (as indicated by absence of

• ).

From ND-95.3-LP-2 (page 16): The Continuous Action Steps, those denoted by an

"*", should be read as, "Bill, this is a Continuous Action Step - CHECK IF LHSI PUMPS SHOULD BE STOPPED."

Since step 12 is not denoted as a continuous action step, there is no procedural guidance within OP-AP-104 that would direct that step 12 would be applicable outside the procedure in which it is contained.

Proposed Resolution: Change the correct answer to C.

References:

ND-95.3-LP-2, EP SU-PROCSU-ADM- SU-PROC-000-1-E-0.

Writer Format Rev 18.doc OP-AP-104[r004].pdf pdf