ML15148A355

2015-04 - Draft Outline Comments (with PVNGS Response on 9-29-14)

ML15148A355
Person / Time
Site:	Palo Verde
Issue date:	04/13/2015
From:	Vincent Gaddy Operations Branch IV
To:
References
Download: ML15148A355 (16)

Text

PV-2015 DRAFT OUTLINE COMMENTS (with PVNGS response - sent to NRC on 9-29-14))

Facility: PVNGS First Exam Date: 4/13/2015 Written Exam Outline (Sep 2, 2014)

Comment Resolution 1 (RO/SRO) Since NRC submitted Rev 0 to PV and Rev 0 was received Revision 0 is correct. When rejected K/As are from PV in the Integrated Outline submittal (title of file was Rev 1 but approved by the CE, Revision 1 will be issued.

footer of document has Rev 0), is it correct that no changes have been made to either RO or SRO written exam outline and the ES-401-4 forms either require no changes or the change(s) have not yet been incorporated?

2 (RO/SRO) Landscape format okay but each page must have a page Understood.

number and Tiers and Groups need to be identified.

(RO) On ES-401-4: Discuss with Chief Examiner prior to changing the Will discuss with CE prior to rejecting K/A.

KA of either Q31 or Q32. (Several systems in Tier 2/Group 1 have two questions since 28 questions required in this group.)

3 (SRO) ES-401-4: Do not replace Q6 without an attempt to locate a Will discuss with CE prior to rejecting K/A.

substantive report made by PV to the grid operator.

Contact the Chief Examiner prior to making this rejection.

4 (SRO) ES-401-4: Do not replace Q8 prior to discussing with Chief Will discuss with CE prior to rejecting K/A.

Examiner. Need to discuss PV indications available for power in the intermediate range.

5 (SRO) ES-401-4: Do not replace Q14 without an attempt to write an Will discuss with CE prior to rejecting K/A.

SRO level question - look at ESD event with RCS temp control following dryout or SGTR event with SG press control. Contact the Chief Examiner prior to making this rejection.

Administrative JPM Outline (Sep 2, 2014)

Comment Resolution 1 (RO/SRO) Ensure original JPMs are submitted with DRAFT Original JPM will be included and source NRC Exam has been exam submittal so level of modification can be determined. annotated.

Identify what NRC exam the original JPM was administered.

2 (RO) If reasonable, develop a JPM for RO responsibility in ROs at PVNGS have no specific E-plan duties, other than being the PV Emer Plan. This would replace Rad Con topic JPM. one of the board operators. A new Operations Department Practices (ODP-31) has been issued. We are still evaluating the scope and extent of its effect on the duties and responsibilities of ROs.

3 (RO) For A3 - the tagout needs to be prepared on a different Tagout for 2012 exam was for HPSI. The tagout for 2015 exam system than the one used for the 2012 NRC exam. Tagout is for DW - different system. Electrical and mechanical should include both mechanical and electrical components. components are included.

4 (RO) The summary for A4 states the SRO - typo? Looks Corrected typo. May be similar, but this is a modified JPM - not very similar to 2013 SRO admin JPM. taken directly from 2013 exam.

5 (SRO) The document has 3 pages, with pages 2 and 3 nearly The PDF submitted was compiled from multiple documents.

the same. Looks like page 2 should be deleted. Rev 1 will not contain duplicate information.

6 (SRO) The summary for A7 (on page 2) is exactly the Page 2 was inadvertently included in the submittal. It appears summary for A3, Tech Review of Clearance Tag Assignment, as though page 2 was in an interim state of revision (cut-n-paste including the word RO. The summary on page 3 has SRO from RO summary). Rev 1 will not contain this information. The and has additional verbiage. summary on page 3 is the correct version.

7 (SRO) The summaries for A4 and A8 (on page 2) are The original intent was to use the Radcon JPM as a common identical. The title on the SRO Form 301-1 includes and JPM for ROs and SROs. Since the NUREG does not require all Determine Who Makes Entry but looks like the summary admin JPMs be different for ROs and SROs, the Chief Examiner wasnt changed to reflect the added SRO task. provided his expectations. The summary for SRO A8 has been updated to reflect the additional SRO responsibility.

Administrative JPM Outline (Sep 2, 2014)

Comment Resolution 8 (SRO) A9 on the last 2 NRC exams appear to be the same Would like to discuss further during subsequent telecons with task as this exam - classify an event and make PARs. While CE.

the Direct from bank JPM is allowed, the task is becoming predictable. Discuss with the Chief Examiner on developing a NEW task related to the EP. Does PV have a toxic gas or chemical Emer Plan?

9 (SRO) Identify JPMs like the RO - A5, not A-5; either format RO and SRO JPMs now designated consistently (without is fine if the same. dashes)

Control Room / In-Plant System JPM Outline (Sep 2, 2014)

Comment Resolution 1 S1 - change title on form to match title on summary page: Titles changed on all 301-2s.

CIAS Actuation/Verification 2 S2 - what is the reference for the time critical portion? Is it a Time Critical nature is described in the body of the JPM and time period specified in a regulation or a facility commitment incorporated into the Task Standard. This task has been time-to the NRC? It needs to be identified in the body of the validated.

JPMand specifically validated (per Appendix C).

3 S3 - why not designate this JPM as L like S4 since they Although this JPM is run simultaneously with a low power JPM, will be performed simultaneously? this JPM is not dependent on low power conditions. The actions for this JPM are identical whether the task is performed at power or in Mode 5.

4 S5 - Does the RO need specific direction (cue) to perform For this JPM, since it begins with the alarm already in, we felt it the ARP or should they conclude that on their own? was appropriate to cue the RO to respond IAW the ARP.

5 S5 - Ensure original JPM is submitted with DRAFT exam Original JPM was from 2010 NRC Exam and will be included in submittal so level of modification can be determined. Identify the exam material submittal. This is now identified in the JPM what NRC exam the original JPM was administered. Summary.

6 S5 - on 301-2 form, Type Code column, the KA is K/A corrected.

027AA.01, not A.01.

7 S6 - repeat from 2012 NRC exam. However, it was This JPM is not dependent on low power conditions. The identified as L,D,A and for this exam its neither L or A. How actions for this JPM are identical whether the task is performed possible? at power or in Mode 5. In 2012, the Chief Examiner accepted this as an Alternate Path JPM, but he considered it a weak one. We have elected to remove the Alternate Path designation.

8 P1 - what is the reference for the time critical portion? Is it a Reference (40OP-DG02 [OP])is now included in body of JPM.

time period specified in a regulation or a facility commitment to the NRC? It needs to be identified in the body of the JPM and specifically validated (per Appendix C).

Control Room / In-Plant System JPM Outline (Sep 2, 2014)

Comment Resolution 9 P2 - Under Type Code - Why is A16, Excess RCS Leakage K/A changed to 3.1 004 A2.14, Emergency Boration (3.8/3.9).

identified for KA? Why is SF 1, Reactivity Control, identified? This is more consistent with SF 1.

10 P2/P3 - on RO ES-301-2, P2 and P3 are swapped (P2 is Corrected on Rev 1.

P3,P3 is P2).

11 P3 - does PV have a mock up of the AFW pump overspeed PVNGS has a mockup. We would like to discuss this further trip mechanism that would allow a hands-on JPM? with the CE.

Simulator Scenario Outline Comments (Sep 2, 2014)

Comment Resolution 1 All - add a third column to the Critical Tasks table: 3rd column added. Where applicable, populated with reference References. Populate with all Licensing Basis documents or to CE CT list, PVNGS CT list, and bases documents.

procedures or CEOG CT list (see example below).

2 All - simply D-1s by moving all detail to the summary. (See All details moved to Narrative Summary.

markup of Scenario #1) All info in brackets can be removed from the D-1. Open to discussion with Chief Examiner.

3 All - CREW HANDOUT / TURNOVER - why both copies Redundancy removed - now only a Turnover. Editorial when they are identical? Also, several editorial comments to comments incorporated.

be discussed during phone discussion. (see attached) 4 All - identify the CEOG CT number for all Critical Tasks and CE CTs identified where applicable.

record in third column.

5 All - provide a list of all events that are repeats from the 2012 List provided at the end of this response.

and 2013 NRC exams.

Scenario 1 Comment Resolution 1 Event 3 - transfer actions are performed by the RO? Limit RO will perform the actions. Prompts for AO are limited to those the prompts given by the Booth Operator to only those specified in the ARP. Control Room has a copy of the local identified in the procedure. Does the CRS have the alarm response procedure.

procedure with Operator Action 4 in the Control Room?

2 Event 5 - what if applicants screw up Event 1? Can Event 1 If an applicant fails to properly return RPCB to service in Event set something else besides MFP trip? SBCS has steam 1, the crew would have to manually initiate the RPCB in Event pressure setpoint at power? If we expect Boron 5. Event 1 sets both MFP Trip and Large Load Rejection.

equalization,add the RO to Event Type column. RO added to Event Type column.

3 Event 7 - summary should describe expected operator In Narrative Summary, removed discussion about actions so either indicate that FRP will be selected or delete implementation/actions of Loss of Vacuum AOP. Level of the discussion from this event. Also, if it is expected that any details in D-2 can be determined during NRC Validation Week SF will require contingency action, it would be identified or after submittal of exam materials. Currently, ARP and AOP (notsay if required). steps are included (up to the point of Rx Trip). In the D-2, if any step in the SPTAs requires a Contingency Action, the CA is addressed as a separate line item.

4 Event 8 - termination criteria not correct. Event 9 is not OR at the discretion of theLead Examiner termination criteria Attachment 6 OBDI 202 - IOLE Process Rev 0 contingent on used instead.

Chief Examiner initiation.

Dont understand Attachment 6 OBDI 202 - IOLE Process Rev 0

5 Event 9 - if loss of AFN-P01 occurs at Step 9, how does CRS initially diagnosed the event when he/she transitioned CRS rediagnose the event since he hasnt diagnosed it yet? to40EP-9EO02, Reactor Trip. After the initial diagnosis and Is the CRS expected to start SPTAs over at Step 1 or transition to 40EP-9EO02, the LOAF occurs, which requires Step 7, RCS Heat Removal? rediagnosis. The CRS is not required, or expected, to re-enter SPTAs.

6 Event 9 - Is the Operations Director/Unit Manager okay with An Operations Manager was involved with the initial validation a CRS that goes to EO06 first? Has someone asked of this scenario. He concurred that transition to either 9EO06 or Operations Department management about their expectation 9EO09 was acceptable.

of a competent operator?

7 Add an END POINT to the summary like Scenario 2 has. END POINT added.

Scenario 2 Comment Resolution 1 For Critical Task Start CS Pump A prior to exiting the PVNGS considers it an acceptable practice to link CTs to SPTAs - the use of procedure transitions for CTs was procedural steps. The station maintains an Ops-approved CT identified during 2013 NRC exam. PVAR 4476152 was list. Although used primarily for LOCT, these CTs sometimes written to address this issue - what was the resolution to the form the bases for specific CTs developed for the initial PVAR? Is this practice allowed? licensing exams. Several of the LOCT CTs contain bounding criteria such as prior to exiting the SPTAs or before exiting Step XYZ.

2 For Critical Task Control primary and secondary CT has been reworded. Included solid PZR and Post-Accident systemsthe justification contains other limitations than just P/T Limits (Standard Appendix 2, Figures).

lifting primary safeties - why not include these in the CTstatement? (solid PZR, PTS, Post-Accident P/T Limits) 3 Event 6 - why not split event into two separate events since Event 6 split as suggested.

there are two separate component failures?

4 How are there 3 malfunctions after EOP entry? 1) Train Actual Attribute reduced to 2.

Asequencer fails, 2) AFB-P01 fails to start. The tripping of CS Pump B has no corrective actions other than responding to Train A sequencer failure.

5 Should isolating SG #1 be considered a Critical Task? We did not consider isolating the SG critical since initiation of Should it be isolated prior to dryout? MSIS will isolate feedwater, the SG will blow down, and will have no further effect on safety or mitigation strategy.

6 Event 6 - the discussion beginning When the SPTAs are When the SPTAs are complete wasnt the most appropriate complete - shouldnt this go under Event 5? As a wording. Removed.

minimum, it should be separated from Event 6/7.

Doesnt belong in Event 5 because SPTAs are not entered until the crew initiates a manual trip.

Scenario 3 Comment Resolution 1 Both Critical Tasks are linked to exiting a PVNGS considers it an acceptable practice to link CTs to procedural steps.

procedure or procedure step. See Comment The station maintains an Ops-approved CT list. Although used primarily for

1. 1 from Scenario 2 - is this practice allowed? LOCT, these CTs sometimes form the bases for specific CTs developed for the initial licensing exams. Several of the LOCT CTs contain bounding criteria such as prior to exiting the SPTAs or before exiting Step XYZ. For some CTs, such as the manual Reactor Trip CT of this scenario, it is nearly impossible to develop a meaningful bounding condition based on a parameter.

It would have to be linked to something like fuel temperature, which is impractical to measure on the simulator and is lacking in CT attributes, such as feedback and cues. Linking the CT to Step 2 provides a link to the bases behind why the Reactor must be tripped (to remove heat input). Proceeding beyond Step 2 of the SPTAs, without first tripping the Reactor, would violate the bases of the Technical Guideline for the SPTAs.

2 Event 1 - action to enter Blowdown Constants Common steps in events in different scenarios should not preclude the use of

- is this a repeat of Scenario 1, Event 6? If either event. Common steps, or sequence of steps, occur frequently in a yes, replace this Normal Evolution (preferably scenario set, especially when implementing EOPs. If Form ES-301-5 holds with an RO evolution since first 3 events are true, only one of the RO applicants (R10) will be evaluated as BOP in both BOP). Scenario 1 and Scenario 3. If we removed one of the events, all Applicants will still complete the minimum number of events for the simulator evaluation.

3 Event 6 - what are the BOP verifiable actions 40AO-9ZZ14, Section 8.0, Instruction 2 - Operate ADVs as necessary to in order to receive credit for this event? maintain steam generator pressure. (mostly manifested after Reactor Trip) 40AO-9ZZ14, Section 8.0, Instruction 4 - Ensure CEDMCS is NOT selected to Auto Sequential AS.

4 Event 7 - consider failing the Manual Rx Trip Requiring RO to open breakers for L03 and L10 was used on 2013 NRC pushbuttons causing applicants to open Exam, Scenario 4.

supply breakers.

5 End Point - terminate once RCS cooldown Termination criteria (End Point) for all scenarios are now consistent - Lead has been initiated or at the discretion of the Examiner vs Chief Examiner.

Lead Examiner. (all end points are Lead Examiner, not Chief Examiner - also fix Scenarios 2 and 4)

Scenario 4 Comment Resolution 1 Event 1 - Turnover says EDG B is out of service for surveillance. Based on feedback from validation, Turnover has been If so, has a TS been entered? Needs to be identified on the revised.

Turnover / Crew Handout. Is this TS the same that the CRS would identify during the event?

2 Event 1 - the RO will unload the EDG? Yes.

3 Event 6 - Stuck Rods is missing from D-1 (so Events 6 and 7 will Based on validation and feedback from the Ops Rep, stuck need to be Events 7 and 8). Also, consider normal path for rods were removed from the scenario.

Emergency Boration fails and use of alternate path is required.

4 Critical Task to start >26 gpm boration is missing from D-1 This CT was removed when we removed the stuck rods.

Attachment 6 OBDI 202 - IOLE Process Rev 0 and from CT table on page 2. Also, multiple CEAs sticking out on 2013 NRC exam had CT of >44 gpm boration which is the correct number?

5 Event 7 - similar question as before - is it expected that CRS will 40DP-9AP16, EOP Users Guide, does not require CRS to start SPTAs from Step 1 after LOOP? Also, D-1 shows both C restart SPTAs. Also, it is not an Ops expectation that and M for this event. Delete C from D-1. SPTAs are started over when conditions change. May be a good practice, but not required. C has been deleted from D-1.

6 Event 8 - since this will occur after transition to EO-7, Changed Target Quantitative Attributes table, item 5, from LOOP/LOFC, entry into EO-8, Blackout, counts for second EOPs 1 to 2.

entered/requiring substantive actions - so for #5 in Target Quantitative Attributes table, page 2, change from 1 to 2.

General:

1. Several difficulties were found when attempting to copy reference material from the CDs provided. A list of files that could not be copied will be supplied in a separate document.

We will resend the referenced documents.

2. What type of document are the Adobe ES-301-1s? Are they form field type documents? Are these the only two in the outline submittal? The files submitted to the NRC should not be modifiable - we need to discuss this for all files submitted during exam process.

The forms used for the 301-1s have been changed. They are now in a Word format and will be converted to a un-modifiable PDF for the next submittal.

3. With the addition of summary descriptions of JPMs, JPM titles can be shortened to bullet style formats. Example:

A1 - Determine Ability to Stand Shift A4 - Perform RO Radiological Tasks A5 - Ensure Compliance with Fatigue Rule Program A6 - Review Shutdown Margin Calculation A7 - Review Surveillance Test A8 - Perform SRO Radiological Tasks A9 - Classify Event and Make PARs JPM titles have been changed as suggested, on both the 301-1 and the JPM Summary.

4. How did PV complete ES-201-2, Exam Outline Quality Checklist, 4.a Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections? Consider adding a section in your outline submittal that identifies what parts of the exam include PRA and IPE.

Our JPM Cover Sheet includes an item to identify (Yes/No) if a JPM is PRA-Related.

Giving consideration to PRA important items is an integral part of the PVNGS safety culture. The Nuclear Safety section of our Standards and Expectations Manual is a constant reminder to value the importance of PRA. This section contains the following topics:

o Know the Challenges to Plant Operation (Contribution to Core Damage Frequency) o Know the Key Operator Actions (Risk Reduction with Perfect Performance) o Typical Risk Increase for Key Equipment Out of Service.

o Know the Baseline Risk Risk, as it relates to PRA, is part of each turnover for the dynamic simulator scenarios. For example, for 3 out of 4 scenarios, we start the session off with Auxiliary Feedwater Pump A OOS, which results in an ORANGE Risk Management Level.

Some of the procedures used during the dynamic simulator evaluation contain the following NOTE: KEY OPERATOR ACTION - Perfect performance of this Appendix will significantly reduce plant risk. (Scenario 1, Event 9). For these events, the D-2 contains an Examiner Note, which references the Key Operator Action.

We will consider enhancements to our submittal to better reflect incorporation of PRA.

5. Provide a copy of the resolution to the following PVARs from the 2013 NRC exam:

PVAR 4477615 - reactivity manipulations PVAR 4476184 - overlap issues PVAR 4476152 - critical tasks not tied to physical parameters PVAR 4480931 - procedure enhancements PVAR 4479704 - operating test weaknesses PVAR 4481035 - general content issues with examination PVARs and DRC listed in Simulation Facility Performance section of Exam Report (see attached table)

Response/status is outlined in the table below:

PVAR NRC Description Resolution 4477615 reactivity manipulations Benchmark conducted with other utilities (447615 - SA)

Revised the LOIT RO and Instant SRO JQCs Significant Control (Reactivity) Manipulations instructions and documentation chart actions to provide better directions, including updated examples and specifying required training progress prior reactivity manipulations.

Revised the Reactor Operator / Senior Reactor Operator Training Program Description to include Appendix L, Significant Control (Reactivity)

Manipulations, to provide better directions; including updated examples, specifying required training progress prior reactivity manipulations, and documentation.

4476184 overlap issues Revised 15DP-0OT01 to require IV of procedures used/reviewed Revised 15DP-0OT06 to encourage use of parameters to bound CTs Better defined Audit Exam methodology 4476152 critical tasks not tied to Revised 15DP-0OT06 to encourage use of parameters to bound CTs physical parameters For 2015 exams, provided NRC with references commensurate with NUREG-1021, ES-201.

PV forms revised to include Exam Value and Applicants Score 4480931 procedure enhancements Rapid Power Change section of 40OP-9ZZ05 now contains prompts to perform Appendix E, Power Change Worksheet, and Appendix N, Site MW Loading with Three Palo Verde Units Online

PVAR NRC Description Resolution 4479704 operating test weaknesses Problems with Fill SIT JPM were determined to be JPM construction/design/administration problems. JPM has been removed from service.

LOIT JPM Brief Lesson Plan (NKASMB00100) developed. This L.P.

emphasizes being confident, and reminds applicants to preview new RP requirements (such as frisking).

CHB-TT-221 failure added to scenario SES204W.

TCW failure will be included - it is being tracked by CRAI 4488564.

RCS Leak admin JPM was revised to prompt applicant that another operator will perform RCS Volume Change calculation. This should eliminate confusion and reduce JPM administration time.

4481035 general content issues with After further discussion with CE and completing an internal evaluation, no examination problems with selection of JPMs were identified. No additional actions taken.

PVARs and DRC listed in Simulation Facility Performance section of Exam Report PVAR Description Disposition 4476190 Condensate Pump C Fixed under DRC 2013-3618 and closed on 5/21/2014 Upper Thrust Bearing Temperature 4476190 Containment Temp and DRC-2013-2616 issued and open. This DR is part of the Containment Model NCW Outlet Temp Upgrade Project.

N/A SG Blowdown Constants DRC-2013-3612 fixed this. Closed on 5/13/14.

4476190 ERFDADS RCS Leak Rate DRC-2013-3620 was issued. It was closed on 2/18/14. This included 3 runs on each simulator. (The NRC requested us to run the same malfunction several times to see if RCS leakrate is repeatable.)

4477166 Multiple TCW Alarms DRC-2014-3628, DRC-2014-3626 issued for this. They are still open.

4476283 Control Channel Gain Pots CRAI 4477220 added this to the Unit Differences (SOC approved). This was 4476289 done on 10/29/13.

Comparison of Duplicate Scenario Events Between 2015 and 2012/2013 NRC Exams 2015 Scenario/Event 2012 or 2013 Scenario Comments Scenario 1 - Inadvertent 2012, Scenario 3 (Success Path HR-2 via In 2012, Success Path recovered AFB. In 2015, AFAS Train B (Pump B 86 MVAC) Success Path is via Condensate Pumps.

L/O)

Scenario 1 - Loss of Vacuum 2012, Scenario 3 Identical. In 2012 (Scenario 3) and 2015, no (SEVERE LOSS) 2012, Scenario 4 (downpower) - Did substantive actions taken in AOP - just the Trip NOT Use Initiator.

Scenario 1 - 86 L/O Aux Feed 2013, Scenario 2 In 2012 & 2013, Success Path recovered AFB. In N 2012, Scenario 3 2015, Success Path is via Condensate Pumps.

Scenario 2 - SIT-1A Gas 2013, Scenario 4 - Did NOT Use Identical Leak Scenario 3 - CEDM Fans Trip 2012, Scenario 4 -Did NOT Use Identical Scenario 3 - UV-1 LOV Relay 2012, Scenario 2 Identical Failure (2012-2)

Scenario 3 - RCS Leak 2012, Scenario 2 Identical, although size of leak different. In 2012, leak was 16 gpm. In 2015, leak is 4 gpm.

Scenario 3 - LOCA (Steam 2012, Scenario 2 - although NOT PZR In 2012, this event was a simple RCS leak. In 2015, Space) Stm Space the PZR Steam Space LOCA provides different indications and different responses.

2015 Scenario/Event 2012 or 2013 Scenario Comments Scenario 3 - ATWS Similar to 2013, Scenario 4 Different Success Paths. In 2013, Success Path was open breakers for L03/L10. In 2015, Success Path is B05 pushbuttons.

Scenario 3 - HPSI Trip/Fail to 2013, Scenario 3 Identical Auto-Start - Critical Task 2012, Scenario 1 Scenario 4 - Inadvertent Train Similar to 2013, Scenario 4 - NOT used In 2013, this event was a straight-forward B CSAS, NC valve fail to Inadvertent CSAS (no additional failures). In 2015, open the failure of the NC containment return valve is the Trip Initiator.

Scenario 4 - LOOP 2012, Scenario 4 - NOT used Different Success Paths. In 2012, Success Path was FRP (MVAC-3). In 2015, Success Path is Blackout.

Scenario 4 - Loss of DG A 2012, Scenario 4 - NOT used Different Success Paths. In 2012, Success Path was FRP (MVAC-3). In 2015, Success Path is Blackout.

Conclusions/Observations:

Scenario Breakdowns:

o Scenario 1 has 9 events o Scenario 2 has 7 events o Scenario 3 has 8 events o Scenario 4 has 6 events o Total # events = 30 6/30 events (20%) are basically identical to events run in either 2012 or 2013 No scenarios are identical (to those scenarios run in 2012/2013, or to PVNGS bank scenarios) and all scenarios satisfy the following criteria from NUREG-1021, ES-301:

The simulator operating tests (i.e., scenario sets) will be constructed by selecting and modifying scenarios from existing facility licensee or NRC scenario banks and by developing new scenarios.

In order to maintain test integrity, every applicant shall be tested on at least one new or significantly modified scenario that he or she has not had the opportunity to rehearse or practice. A significant modification means that at least one condition or event has been substantively changed to alter the course of action in the scenario. Furthermore, any other scenarios that are extracted from the facility licensees bank must be altered to the degree necessary to prevent the applicants from immediately recognizing the scenarios based on the initial conditions or other cues.

5/30 (16%) events are the same, or similar, to events from 2012/2013, but have different Success Paths.

1/30 (3.3%) events (LOCA) is similar, but with different indications/symptoms (PZR Steam Space vs. Cold Leg Break)

All of the scenarios meet the 50% criteria that  cøoµØ-~4*I¥ ÑÃ