ML060880007

From kanterella
Jump to navigation Jump to search
Outline Submittal and NRC Comments for the D.C. Cook Initial Examination - February 2006
ML060880007
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 02/06/2006
From: Bailey R
Indiana Michigan Power Co
To: Valos N
NRC/RGN-III
Shared Package
ML060670557 List:
References
Download: ML060880007 (37)
v • d • e


Text

OUTLINE SUBMITTAL AND NRC COMMENTS FOR THE DC COOK INITIAL EXAMINATION FEBRUARY 2006

October 26. 2005 U. S Nuclear Regulatory Commission ATTN: Mr. Nicholas A. Valos Region 111 Exanliner 2443 Waixnville Road, Suite 210 Lisle, IL 60532-4352 Donald C. Cook Nuclear Plant Units 1 and 2 2006 INITIAL LICENSE EXAMINATION OUTLINE Enclosed you will find a copy of the Initial License Examination Outline for the planned Fehruary 2006 Examination at Donald C. Cook Nuclear Plant (CNP). Also enclosed is the proposed examination schedule, based on 10 Senior Reactor Operator (SRO) (I) and S SRO ( U ) candidates.

The following items are eiiclosed in the sealed envelope:

1) Fonn ES-201-2, Examination Outline Quality Checklist
2) Foim ES-201-3, Examination Security Agreement
3) CNP 2006 NRC Operating Examination Overview
4) Draft CNP 2006 ILT Exam Detailed Schedule
5) Written Exam Saniple Methodology
6) Probabilistic Risk Assessriierit Input
7) Scenario Outlines Form ES-D- 1 a) COOK06-01 h) COOK06-02 c) COOK06-03 d) COOK06-04 e) COOK06-05 t) COOK06-06 (SPARE)
8) ES-301-4, Simulator Checklist Set 1
9) ES-301-4, Simulator Checklist Set 2
10) ES-301-4, Simulator Checklist Set 3
11) ES-301-5, Transient and Event Checklist Set 1
12) ES-301-5, Transient and Event Checklist Set 2
13) ES-301-5, Transient and Event Checklist Set 3
14) ES-301-6, Competencies Checklist Set 1
15) ES-301-6, Competencies Checklist Set 2
16) ES-301-6, Competencies Checklist Set 3

U. S. Nuclear Regulatory Commission October 26,2005 Page 2

17) ES-301-2, System JPM Outlines a) SRO (I) JPM Outline b) SRO (U) JPM Outline ES-301-1, SRO Admin JPM Outlines PWR Exam Outline, Form ES-401-2 (SRO)

Generic WA Outline, Form ES-401-3 (SRO)

PWR Exam Outline, Form ES-401-2 (RO)

Generic WA Outline, Form ES-401-3 (RO)

Form ES-401-4 Submittal (ROISRO)

SRO QuestioniKA to CFR Cross-reference A hard copy of all the examination materials is provided for your review. An electronic copy of documents without initials or signatures or other handwritten notations for the Public Document Room (ADAMS) has also been provided.

None of these materials are to go to the Public Document Room (ADAMS) until after the examination has been completed.

Should you have any questions, please contact Ron Bailey or Steve Pettinger at (269) 466-3364.

Sincerely, Qx+&A-wic3oa)re/\

Daniel R. Walter Facility Representative RMBIjen Enclosures

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility Date of Examination:

-Item 1.

~

Task DescripUon

a. Verify that the outilne(s) fit@) the appropriate model. In accordancewith ES401 W

R b Assess whether tne 0,ll.m was systematically and randomly prepared in accordance with Sect on D 1 of ES-401 and whether all NA categories are appropriately sampled I sad T

T c Assess whether the ouli ne over-emphas20s any systems. evoIutions. or generic topics I kWl aeb E

- N 2.

d. Assess whether the justifications for deselected or rejected KIA statements are appropriate.
a. Using Form ES-301-5, verify that the proposedscenario sets wver the required number 3G6 of normal evolutions. instrument and component failures. technical specifications.

S and major transients.

I M b. Assess whether there are enough scenario sets (and spares) to test the projected number U and mix of applicants In accordancewith the expected crew composition and rotation schedule L without wmprornising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario. that no scenarios are duplicated *@

T from the aoplicants' audit test(sl, and that scenarios will not be repeated on subsequent days.

0 c. To the extent possible, assess whether the outllne(s) conform(s) with the qualitative R and quantitative criteria specified on Form ES-3014 and described in Appendix D.

3. a. Verify that the systems walkthrough outline meels the uiteria specified on Form ES-301-2:

(1) the outline(s) contain@)the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition fmm the last two NRC examinationsis wilhin the limils spear%& on the form T (3) no tasks are duplicated from the applicants' audit test(+ 84V (4) the number of new or modfied tasks meek or exceeds the minimums specifmd on the form (51 the number of alternate oath. low-oower.emernencv. and RCA tasks meet the criteria

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) 81least one task is new or significantly modified (3) no more than one task is repeated from the lasl two NRC licensing examinations c Delermm I there are enough different outmes to tes1the projected number ana mlx 01 apPllcants and ensure that no Rems are duplicated on SubseqJent days

4. a Assess whether plamspecfic pr.onties (induding PRA and IPE insghts) are wvered n tne aopropnateexam sect ons G 0 AsSeSS wnether the 10 CFR 55 41/43 and 53 45 samplmg E appropriate E

N c Ens-re that KIA importance rat ngs (except for plant.specfic prlorit es) are at least 2 5 & w e../

E R d Check for duplication an0 overlap among eram sedlons A L Td rtru A e. Check the entire exam for balance of coverage.

L

- I. Assess whether the exam fits the appropriatejob level (RO or SRO).

a Aulhor b Facllity Revlewer v) c NRC Chief Examiner ( X ) 5-d NRC Supervisor

~~

ES-201, Page 25

ESdOl Administrative Topics Outline Form ES-301-1

acility: DC Cook Date of Examination: 02/06/06 ixamination Level: RO 0 SRO@ Operating Test Number-Administrative Topic Type, Describe activity to be performed Code (See Note)

Conduct of Operations N, R NO6SRO-a Calculate Reactor Thermal Power-PPC derived with Loss of LEFM<48hours KA: SYSOl5 Al.01 3.513.8 (02-OHP.4030-214-029 Attachment 2)

Conduct of Operations D. R NO6SRO-b Review AFD Log KA: 2.2.23 2.6/3.8 8 SYSOl5 A1.05 3.713.9 (01-OHP-4024-110 Drop 44 Attachment A)

Equipment Control NO6-SRO-c Verify Clearance Permit For East ESW Pump (NRC 2002 Exam)

KA 2.2.13 3.6/3.8 (12-OHP-2110-CPS-001)

Radiation Control N. R NO6-SRO-d Respond to a High SJAE Radiation Alarm (Graph Leakrate & Determine Actions)

KA: 2.3.10 2.9/3.3 8 APE037 AK3.05 3.714.0 (12-OHP-4024-139 Drop 25)

Emergency Plan D. R NO6SRO-e Prepare Prompt NRC Notification Worksheet (SFIFW flow trip, safety stuck open)

KA: 2.4.30 223.6 (PMP-7030401 Data Sheet 1) 4OTE: All items (5 total) are required for SROs. RO appiicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (0)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 2 1)

(P)revious 2 exams ( 5 1; randomly selected)

NUREG-1021Revision 9

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: DC COOK 2006 ILT Date of Examination: 02/06/06 Exam Level: RO u S R O ( I M SRO(U) 0 Operating Test No.:

Control Room Systems @ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System I JPM Title Type Code* Safety Function

~

a. NRC2006-SIM01 -Perform Emergency Boration Step of 02-OHP-4023-FR-S.l ATWS (Boric Acid Pumps fail -

~ l iRWST) KA EPE 024 A1.17 3.9/3.9, SYS 004 A2.14 I 1 3.833.9.

b. NRC2006-SIM02 - Shift Operating Charging Pumps KA SYS 006 A4.01 4.113.9
c. NRC2006-SIM03 - Maximize Containment Cooling per 02-OHP-4021-028-001 KA SYS 022 A4.01 3.613.6
d. NRC2006-SIM04 - Re-Energize RCP Buses 2A & 28 from Reserve Feed per 02-OHP-4023-SUP-002. KA SYS 062 A4.07 3.113.1.
e. NRC2006-SIM05 - Control Room Ventilation Alignment for Unit 1 Safety Injection per OHP-4021.028.014 Attachment 13 and OHP-4024.201 Drop 59 (Charcoal filter fire after fan start) KA 072 A3.01 2.913.1
f. NRC2006-SIM06 - Perform Turbine Driven AFW Pump N,S I 45 Trip & Throttle Valve Operability Surveillance 02-OHP-4030-STP-017TV. KA SYS 061 K4.07 3.113.3.
g. NRC2006-SIM07 - Start a RCP per 02-OHP-4023-SUP- ALMS 4P 010 & 0071CCW isolated - Restore) KA SYS 003 A4.08 In-Plant Systems@ (3 for RO; 3 for SRO-I: 3 or 2 for SRO-U)
i. NRC20064NP01 Locally Control the VCT Makeup Valve (QRV-400) per 402543-1 2-18 KA APE 068 AA1.22 D,E.R 2 4.014.3
j. NRC20061NP02 Local Operation of SG PORVs per 4025-LS-4-3 KA APE 068 AA1.01 4.314.5 D,E.R 4s
k. NRC2006-1Np03 Restore N Train Battery Charger per OHP 4021.082.015 and OHP 4024.115 Drop 57 (In-Service A,D,E,P,R 6 Charger fails, align Standby) KA APE 058 AA1.01 3.413.5 7007

@ I All RO and SRO-I control room land in-plant1 systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for ROISRO-IISRO-U (AIltemate Dath 4-6 i4-6 12-3 icjontrol mom (0)irect from bank 59/58/54 (E)mergency or abnormal in-plant 2 1 / 2 1/ 2 1 (L)ow-Power / Shutdown >1/>1/21 (N)ew or (M)odified from bank including 1(A) 22/22/21 (P)revious 2 exams 5 3 Is 3 Is 2 (randomly selected)

WCA 2 112 1 / 2 1

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2

'acility: DC Cook Nuclear Plant Date of Exam: 2/20/2006 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

  • Total 2.

Plant Systems Vote: 1. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one cateeory in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than rW0).

2. The point total for each group and tler in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by f l from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systemstevolutions within each group are identified on the associated outline: systems or evolutions that do not apply at the facility should be deleted and justifled: operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
7. *The generic (G) WAS in Tiers 1 and 2 shaii be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.
8. On the following pages, enter the KIA numbers. a brlef descripllon of each topic, the topics' importance ratings (iRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above: if fuel handling equipment is sampled in other than Category A2 or G' on the SRO-only exam, enter it on the left side of Column A2 for Tier 2. Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-oniy exams.
9. For Tier 3, select topics from Section 2 of the WA catalog. and enter the KIA numbers. descriptions, IRs.

and point totals (#)on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

~ -

ES-401 PWR Examination Outline Form ES-401-2 Faeilitv: DC Cook Nuclear Plant Printed 1011812005

- Date Of Exam: 02/20/2006 I SRO-Only Points

- Tier 1.

mergenc) 4bnormal Plant ivolutions 2.

Plant Systems Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (i.e.. except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two).
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by h l from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified: operationally important. site-specific systems that are not included on the the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA statements.

t

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.' The generic (G)WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to theapplicable evolution or system.

8. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topices from Section 2 of the WA catalog, and enter the KIA numbers.

descriptions, IRs. and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

1

PWR RO Examination Outline Printed: lO/l8/2005 Facility: DC Cook Nuclear Plant ES - 401 -

Emergency and Abnormal Plant Evolutions Tier 1 /Group 1 Form ES-401-2 K1 "P.

E/APE # / N a m e / Safety Function 4.0 300007 Reactor Trip - Stabilization -

Recovery / 1 000008 Pressurizer Vapor Space Accident / AK2.03 - Controllers and positioners 2.5 3

3.0 300009 Small Break LOCA / 3 3.4 300015/000017 RCP Malfunctions / 4

-3.2 2.6 300025 Loss of RHR System / 4 7

000026 Loss of Component Cooling Water /

000027 Pressurizer Pressure Control System X 3.2'

-2.6 c

Malfunction / 3 000029 ATWS / 1 37-oooO38 Steam Gen. Tube Rupture I 3 X

-3.2

-4.4 000054 Loss of Main Feedwater / 4 loss conditions

-2.6 000055 Station Blackout / 6

-3.7 000056 Loss of Off-site Power / 6 X AKl.01 -Principle of cooling by natural convection

-2.5 000058 Loss of DC Power / 6 administrative requirements.

-4.0 000062 Loss of Nuclear Svc Water / 4 AK3.03 - Guidance actions contained in EOP for Loss of nuclear service water WIE04 LOCA Outside Containment / 3 EA2.1 - Facility conditions and 3.4 selection of appropriate procedures during abnormal and emergency operations

-3.9 WIE05 Inadequate Heat Transfer - Loss of EK2.2 -Facility's heat removal systems, Secondary Heat Sink / 4 including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the I operation of the facility

-3.4 WIE12 - Steam Line Rupture - Excessive EA1.3 -Desired operating results Heat Transfer / 4 during abnormal and emergency situations I

WA Category Totals: I 3 Total:

~~~~ ~~~~

PWR RO Examination Outline Printed 10/18/2005 Facility: DC Cook Nuclear Plant ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 I

-?

Y

PWR RO Examination Outline Printed: I011812005 Facility: DC Cook Nuclear Plant Plant Systems -Tier 2 I Group 1 Form ES-401-2 ES - 401 I I IO3 Reactor Coolant Pump IO4 Chemical and Volume Control IO5 Residual Heat Removal amps, motor temperature,

)06 Emergency Core Cooling X 107 Pressurizer ReliefiQuench rank

)07 Pressurizer ReliefiQuench rank

)08 Component Cooling Water

)lo Pressurizer Pressure Control

)IO Pressurizer Pressure Control X 112 Reactor Protection X 4ctuation temperature and pressure in containment after a LOCA by condensing steam, to corrosion dama Feedwater

PWR RO Examination Outline Printed: 1Oil 8/2005 Facility: DC Cook Nuclear Plant ES - 401 -

Plant Systems Tier 2 I Group 1 Form ES-401-2

KATopic Imp.

RCS heat transfer A2.08 - Consequences of 2.7 exceeding voltage limitations A3.04 - Operation of 2.1 inverter (e.g., precharging synchronizing light, static transfer)

K4.04 -Trips 2.6?

A1.08 - Maintaining 3.1 minimum load on ED/G (to prevent reverse power)

K3.01 - Radioactive effluent 3.6 releases

< 2.1.33 -Ability to recognize 3.4 indications for system operating parameters which are entry-level conditions for technical specifications.

K2.04 - Reactor building 2.5*

closed cooling water A3.01 - Air pressure 3.1 K4.06 - Containment 3.1 isolation system 3 Group Point Total:

2

PWR RO Examination Outline Printed: 1011812005 Facility: DC Cook Nuclear Plant Plant Systems -Tier 2 I Group 2 Form ES-401 KA Topic Imp.

A1.06 - Reactor power 4.1 K6.07 -Pumps 2.5 K3.02 - RCS 3.5 K4.03 - Reading of source 3.9' rangelintermediate range/power range outside control room K2.01 -Hydrogen 2.5' recombiners 2.4.31 - Knowledge of 3.3 annunciators alarms and indications, and use of the response instructions.

A4.01 - Shift of SIG 3.7 controls between manual and automatic control, by bumpless transfer K1.02 - SIG level 2.7 A2.04 - Loss of condensate 2.6 Pumps A3.02 -Automatic isolation 3.6 Group Point Total:

1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 1Oil Si2005 Fncility: DC Cook Nuclear Plant Form ES-401-3 Conduct of Operations 2.1.12 Ability to apply technical specifications for a 2.9 1 system.

2.1.19 Ability to use plant computer to obtain and 3.0 1 evaluate parametric information on system or component status.

2.1.29 Knowledge of how to conduct and verify valve 3.4 1 lineups.

Category Total: 3 Equipment Control 2.2.11 Knowledge of the process for controlling 2.5 1 temporary changes.

2.2.27 Knowledge of the refueling process. 2.6 1 I

r Cateeorv Total: 2 1 Radiation Control 2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized.

2.3.9 Knowledge of the process for performing a 2.5 1 containment purge.

2.3.10 Ability to perform procedures to reduce 2.9 1 excessive levels of radiation and guard against personnel exposure.

Category Total: 3 1 Emergency Proceduresmlan 1 2.4.29 Knowledge of the emergency plan. 2.6 1 2.4.50 Ability to verify system alarm setpoints and 3.3 1 operate controls identified in the alarm response manual.

I Category Total: 2 1 Generic Total: 10 1

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facilltv: D C Cook Nuclear Plant Date of Exam: 212012006 SRO-Only Points Total 10 5 3 8

3. Generic Knowledge a n d Ablllties 1 2 3 4 1 0 1 2 3 4 7 Categories 2 2 2 1 Note: 1 Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (Le.. except f w me category in Tier 3 of the SRO-only outline, the 'Tier Totals" in each WA category shall not be less than two).
2. The point total for each group and tier in me proposedouUine must match that Specified in the table.

The final point total for each group and tier may deviate by flfrom that spedfied in the table based on NRC revisions The final RO exam must total 75 points and Ihe SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identifiedon the asscciated outline; systems or evolutions that do not apply at the facility should be deleted and justified: operationally Important, site-specificsystems that are not included on the outline should be added. Refer lo ES-401,Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
4. Select topics from as many systems and evOlUtlonS as possible; sample every system or evolution in the group before selecting a second topic for any system or evoIuUon.
5. Absent a plant-specific priority. only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions. respectively.

6. Select SRO topics for Tiers 1 and 2 t o m the shaded systems and WA categories.
7. *The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.
8. On the f o l l o ~ n gpages. enter the KJA numbers. a M e f descriptionof each topic. the topics' importance ratings (IRs) for the applicable license level. and the polnt totals (#)for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G' on the SRO-only exam, enter it on the lefl side of Column A2 for Tier 2, Group 2 (Note I+ 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9 For Tier 3, Select topics From Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, iRs.

and point totals (#)on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

PWR SRO Examination Outline Printed: 10/18/2005 Facility: DC Cook Nuclear Plant ES - 401 Emergency and Abnormal Plant Evolutions -Tier 1 I Group 1 Form ES-401-2 EiAPE # / Name / Safety Function Heat Transfer / 4 I I I re from pressure and WlEl 1 Loss of Emergency Coolant Recirc. /

4 I I I I WACategory Totals: I 0 I 0 I 0 I 0 1

PWR SRO Examination Outline Printed 10/18/2005 Facility: DC Cook Nuclear Plant ES - 401 Emergency and Abnormal Plant Evolutions -Tier 1 /Group 2 Form ES-401-2 K1 K2 K3 A1 A2 G KATopiC Imp. Points EiAPE # / Name / Safety Function 000033 Loss of Intermediate Range NI I 7 X 2.4.46 - Ability to verify that the alarms 3.6 I are consistent with the plant conditions.

WIE07 had. Core Cooling / 4 X EA2.1 - Facility conditions and 4.0 I selection of appropriate procedures during abnormal and emergency operations WIE13 Steam Generator Over-pressure / 4 x 2.1.7 - Ability to evaluate plant 4.4 1 performance and make operational judgments based on operating characteristics, reactor behavior, and inshument interpretation.

WIEIS Containment Flooding / 5 X procedures and operation within the limitations in the facility's license and amendments WACategory Totals: 0 0 0 0 2 2 Group Point Total: 4 1

PWR SRO Examination Outline Printed: 1011812005 Facility: DC Cook Nuclear Plant Plant Systems -Tier 2 /Group 1 Form ES-401-2 3S - 401 2

Sys/Evol # / Name 006 Emergency Core Cooling 008 Component Cooling Water 025 Ice Condenser 2.4.35 - Knowledge of local 3.5 1 auxiliary operator tasks during emergency operations including system geography and system implications.

026 Containment Spray A2.08 - Safe securing of 3.1 1 containment spray (when it can be done) 06 1 AuxiliaryiEmergency A2.03 - Loss of dc power 3.4 1 Feedwater K I A Category Totals:

PWR SRO Examination Outline Printed: 1011812005 Facility: DC Cook Nuclear Plant ES - 401 Plant Systems - Tier 2 /Group 2 Form ES-401-2 g

SydEvol # I Name KI KZ K3 K4 K5 K6 AI A2 A3 A4 G KATopic Imp. Points 016 Non-nuclear Instrumentation X 2.2.18 -Knowledge ofthe 3.6

- 1 process for managing maintenance activities during shutdown operations.

034 Fuel Handling Equipment X A4.01 - Radiation levels 3.7

- I 075 Circulating Water A2.02 - Loss of circulating 2.7

- 1 water pumps WACategory Totals: 0 0 0 0 0 1 1 Group Point Total: 3

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed. 1011812005 Fncility: DC Cook Nuclear Plant Form EMOI-3 Generic Category Conduct of Operations 2.1.4 Knowledge of shift staffing requirements. 3.4 1 2.1.13 Knowledge of facility requirements for 2.9 1 controlling vital I controlled access.

Equipment Control report.

activities on LCO status.

I Category Total:

Radiation Control 2.3.6 Knowledge of the requirements for reviewing 3.1 1 and approving release permits.

2.3.8 Knowledge of the process for performing a 3.2 1 planned gaseous radioactive release.

Emergency ProceduresIPlan 2.4.28 Knowledge of procedures relating to emergency 3.3 1 response to sabotage.

Category Total: 1 1

ES-301, Rev. 9 Transient and Event Checklist Form ES-301-5

DC Cook Date of Exam: 2/6/2006 Operating Test No.: (Set 1 ) ICrew s 1.2.31 Instructions:
1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must sefve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. p) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.
3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

ES-301, Rev. 9 Transient and Event Checklist Form ES-301-5 Facility: DC Cook Date of Exam: 2/6/2006 Operating Test No.: [Set 2 ) C r e w 41 istructions:

Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (IC) malfunctions and one major transient, in the ATC position.

Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.

Whenever practical. both instrument and component malfunctions should be included: only those that require verifiable actions that provide insight to the applicant's competence count toward the minimurr requirements specified for the applicant's license level in the right-hand columns.

ES-301, Rev. 9 Transient and Event Checklist Form ES-301-5 Facility: DC Cook Date of Exam: 2/6/2006 Operating Test No.: (Set 31 (Crew 51 I : I F 1 Scenarios T M P E COOk06-03 COOk06-04 Cook06-01 L N 0 I CREW CREW CREW CREW T N I T POSITION POSiTlON POSITION POSITION A C I A T M N V U M(*)

RO TS I 1.2 2 RX 5 1 0

SRO-I NOR 0 SRO-U I/C 1,4 1,3 1,2. 8 3,4 0

MAJ 5 6 5 3 RO TS 1 1,4 I 2 n RX 3 1 i/c SRO-U MAJ Tf Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-I event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"

and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a I-for-I basis.
3. Whenever practical. both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence wunt toward the rninimui requirements specified for the applicant's license level in the right-hand columns.

Cook Plant Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK06-01 Op-Test No.:

Examiners: Operators:

Initial Conditions: IC-37, MOL; 74% power, 941 pprn Boron, 8 GWD Turnover: PRZ PORV NRV-153 leakage with Block valve NMO-153 closed Event Malf. No. Event Event No. Type' Description 1 RX04A @ 1700 I-RO Pressurizer Pressure Channel NPP-151 Fails Low TS 2 FW34A C-BOP North CB pump trip; Middle CB pump fails to start in AUTO FW58B 3 cvo4c C-RO 75 qDm Letdown Orifice Isolation Valve QRV-162 Fails Closed 4 RX23B @ 0 I-BOP #21 SG level Transmitter fails LOW over 30 sec TS 5 MSOl D @ 20 M Steam Line Break inside Containment (#24 SG) 2 rnin ramp 6 RP07A C-BOP Steam Line Isolation fails to AUTO actuate RP07B 7 RP16B C-RO CTS Train B - fails to actuate (AUTO/MANUAL)

__ RP17B 8 RP19J C-RO RPS relay K626-X3 failure (2East CTS pump fails to start)

-(N)ori I, (R)eactivity, )nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & Unit 2 NUREG-1021,Revision 9 Page 1 of 2

Summary The first event will involve will involve the Pressurizer Pressure Controlling Channel, NPP-15 1, failing LOW. The RO will be required to take manual control of Pressurizer Pressure Master Controller and restore normal pressure control. The Crew will implement the Abnormal Operating Procedure, address Technical Specifications, select an operable channel, and restore pressure control to automatic.

The second event a trip of the North Condensate Booster pump. This will result in reduced feedwater capability. BOP will be required to manually start the Middle Condensate Booster pump. Crew will be required to implement compensatory actions to stabilize the plant.

The third event will involve the letdown orifice valve will fail closed after the secondary plant has been stabilized. The RO will need to restore Letdown through a different valve.

The #21 Steam Generator Level instrument (BLP-Ill) failing LOW. This results in a feedwater flow and Steam Generator level rise. BOP will be required to take manual control and restore normal level. Crew will be required to implement AOP actions to stabilize the plant and address Technical Specifications.

The main event will involve a Main Steamline Break inside containment on the #24 SG. The unit will trip and a Safety Injection will actuate. Failure of the Main Steamline Isolation actuation circuit will require a manual actuation. As the crew performs the actions of E-0, they should identify the Main Steamline Break inside containment on the #24 SG. The crew will transition to E-2 to isolate #24 SG. Containment Pressure will raise and CTS fails to Actuate. The crew may be required to transition to FR-Z.l to restore CTS. The scenario will terminate when the crew has transitioned to ES-1.1.

Critical Tasks Isolate #24 Steam Generator ActuatdAlign CTS Procedures E-0, Reactor Trip or Safety Injection E-2, Faulted Steam Generator Isolation Z. 1, Response to High Containment Pressure Cook Plant Unit 1 &Unit 2 NUREG-1021, Revision 9 Page 2 of 2

Cook Plant Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK06-02 Op-Test No.: ___

Examiners: Operators:

Initial Conditions: IC- 37, MOL; 74% power, 941 ppm Boron, 8GWD Turnover: Reduce power to remove the West FWP from service due to an oil leak.

Event Malf. No. Event Event No. Type* Description

~ ~

1 RCR20 @ 3 C-RO PRZ PORV (NRV-153) Leak by (3 gpm)

TS 2 RX19A@O I-RO Turbine Impulse Transmitter (MPC-253) fails LOW TS 3 R Reduce reactor power and turbine load for West FWP

~ ~ ~

4 RC23B@30 M SGTR on #22 SG (300 gpm) 5 min ramp 5a I RPIOA RPllC 1 C-RO Train A Safety Injection signal failure to actuate in AUTO or Manual mode (PRZ panel only)

Train B Safety Injection signal failure to actuate in AUTO or RPllB C-BOP Manual mode R X I I B @lOO% C-BOP SG #22 PORV Controller Failure I I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 &Unit 2 NUREG-1021, Revision 9 Page 1 of 2

Summarv The Scenario stam with the plant at 74% power with directions to begin a ramp down to take the west main FW pump offline due to a small oil leak.

The first event will involve the Pressurizer PORV NRV-153drifting partially open. The crew will need to close Block valve (NMO-153) to stop NRV-153 leakage. Crew will be required to address PORV Technical Specifications.

After the crew addresses the PORV failure, the Turbine Impulse instrument (MPC-253) will fail LOW. This results in a control rod insertion if they are in Auto. RO will be required to place rod control in manual. Crew will be required to implement AOP actions to stabilize the plant and address Technical Specifications.

If required allow the crew to continue the power reduction The main event will involve a Steam Generator Tube Rupture. The SGTR will build in to 300 gpm over 15 minutes.

The crew will perform a Reactor Trip and Safety Injection. As the crew performs the actions of E-0, Safety Injection signal will fail to AUTO actuate. Train A Safely Injection can be actuated only from the SIS panel switch.

The crew should identify the Steam Generator Tube Rupture on #22 SG. The crew will transition to E-3 to isolate

  1. 22 SG. The crew should identify the failure of SG #22 PORV controller (PORV Opens) and take manual control and close the PORV. The scenario will terminate when the crew has completed the cooldown.

Critical Tasks Manually actuate at least one train of SI before completion of E-0, Step 5 .

Isolate #22 Steam Generator Cooldown RCS Depressurize RCS to stop #22 SGTR leakage Procedures E-0, Reactor Trip or Safety Injection E-3, Steam Generator Tube Rupture Cook Plant Unit 1 & Unit 2 NUREG-1021,Revision 9 Page 2 of 2

e _ _

Form FS D 1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK06-03 Op-Test No.: -

Examiners: Operators:

Initial Conditions: IC 36 MOL, 51% power, 1015 ppm Boron, 8 GWD burnup Turnover: 2W MDAFW 00s for Oil Change. The 2W MFP has just been returned to service following repair of an oil leak.

Event Descrintion CCOIA, C-BOP 2E CCW pump Trips ( 2 W CCW [Standby] Fails CC02B - t o Auto Start)

Preload LOOP 2 Hot Leg NTP-121 Temperature Transmitter Fails High 3 1 Raise Turbine and Reactor Power MFC-1 1 0 Main Steam Flow Transmitter Fails High on 21 SG RCIOD to Major Loop 4 Cold Leg Primary Coolant System 60% 600gpm Leak inside Containment over 5 minutes C-BOP Failure of Automatic Phase A Actuation RP13B -

Preload RPISG, Slave Relay failures: High Head Charging SI RP20G - valves fail t o align Preload RP20B - C-BOP Slave Relay failure: DG 2AB fails t o auto start Preload (& High Head Charging Valve)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Cook Plant Unit 1 & 2 NUREG-1021, Revision 9 Page 1 of 2

Summary The Component Cooling Water (CCW) pump will trip. The BOP will have to start the standby pump manually (auto start failure).

AAer the Crew has addressed the Technical Specification for the tripped CCW pump, the Loop 2 Hot Leg NTP-121 Temperature Transmitter fails high. The rods will insert and power will have to be restored. The crew will need to enter an Abnormal Operating Procedure, defeat the failed channel, address Technical Specifications, and restore rod control to auto. If required , the crew will be directed by the ShiA Manager to raise power to 70%.

When the RCS Temperature has been restored or a short ramp has been performed, MFC-I IO, the #21 S/G Main Steam Flow transmitter will fail high. This failure will also raise FW pump speed (apparent steam flow rise tries to maintain a higher DP). The BOP will need to take manual control of the MFP DP and Feedwater Regulating Valve FRV-210 to restore level. The crew will need to enter an Abnormal Operating Procedure, address Technical Specifications, and transfer to operable channel, and return to the FRV-210 to auto.

When the SG level has stabilized, a 600 gpm Primary System Leak in Containment will occur requiring a Reactor Trip and SI.

On the SI, various slave relay failures will cause the High Head Charging SI injection flowpath to fail to align and the 2AB DG to fail to auto start. The RO will need to manually align the High Head Injection Valves. The auto Phase A Isolation will also fail requiring manual actuation to align Phase A equipment. The crew should progress through E-0 to E-1 to ES-1.2. The scenario will terminate once a transition has been made to ES-1.2.

Critical Tasks Restore High Head Injection Trip RCPs Procedures E-0 Reactor Trip or Safety Injection E-1 Loss of Reactor or Secondary Coolant Cook Plant Unit 1 & 2 NUREG- 1021, Revision 9 Page 2 of 2

S e i n e Form FS_ D_ 1 Facility: Cook Plant Unit 1 8, Unit 2 Scenario No.: COOK06-04 Op-Test No.: -

Examiners: Operators:

Initial Conditions: IC 37, 74% power, 941 ppm Boron, 8 GWD Turnover: 2CD DG is tagged out for oil change.

Event No. Malf. No Event Event Type* Description 1 RXO5A @ I-RO Controlling Pressurizer Level Channel (NLP-151) 0 fails LOW TS 2 RX17J to I-BOP SG Pressure Channel MPP-240 Fails Low 0Yo 3 Global 101 BAP4 TS C-RO I Boric Acid Pump Trip 4a FW38 to C- Loss of condenser vacuum Ramp in over 15 35% BOP minutes to 35%

5 R Power reduction 1 Reduce Turbine Load 4b FW38 to Condenser vacuum degrades requiring a Reactor 100% Trio. Ramo in over 5 minutes to 100%

6 ED01 Major Loss of all AC power (345kv & 765kv lines) causing entry into ECA-0.0 ED25 6a EG08A - C-BOP 2 AB DG Speed Governor failure: DG will not Preload reach rated speed resulting in Incomplete Sequence.

7 RC17A to C-RO Pressurizer PORV (NRV-151 will stick open @

m o /.-

n 50% upon reactor trip.)

Cook Plant Unit 1 & Unit 2 NUREG-1021, Revision 9 Page 1 of 2

Summary The first event will involve the controlling Pressurizer Level channel instrument (NLP-15 1) failing LOW. This results in charging flow rising, pressurizer level rising, pressurizer heaters OFF, and letdown isolation. RO will be required to restore normal letdown and charging flow conditions. Crew will be required to implement AOP actions to stabilize the plant and address Technical Specifications.

When the VCT is stabilized, the SG Pressure Channel MPP-240 fails low. The BOP will be required to take manual control SG 24 Feedwater Regulating Valve FRV-240 to stabilize level.

The crew will address the failure with an Abnormal Operating Procedure, address Technical Specifications., select an operable channel, and restore automatic control.

After SG level is restored the Boric Acid pump will trip. The crew will be required to address the Technical Requirements manual and select the Standby Boric Acid pump.

A loss of Condenser Vacuum will occur. The crew will take actions to stabilize vacuum but will need to reduce power due to loss Feedwater Pump capacity.

After power has been reduced, the vacuum leak will worsen, requiring a reactor trip.

Upon the reactor trip a loss of all AC power will occur. The crew will enter ECA-0.0, Loss of All AC Power and take action to stabilize the plant. . A failed open (50%) Pressurizer PORV (NRV-151) will result in a Safety Injection Actuation.

The crew should proceed through ECA-0.0. and take actions to restore power. Power will be made available via Emergency Power (Supplement 9). The crew will energize the vital buses, isolate the stuck PORV, and transition ECA-0.2, Loss of A11 AC Power Recovery with SI. The scenario ends after the transition to ECA-0.2.

Critical Tasks Isolate Pressurizer PORV Restore Emergency Power Procedures E-0 Reactor Trip or Safety Injection ECA-0.0 Loss of All AC Power Cook Plant Unit 1 & Unit 2 NUREG-1021,Revision 9 Page 2 of 2

Appendix D Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK06-05 Op-Test No.:

Examiners: Operators:

Initial Conditions: IC 37 , 74% power, 941 pprn Boron, 8 GWD Turnover: Raise Power to 100%. 2W MDAFP 00s.

Event No. Malf. No. Event Event Type* Description 1 NIIOB @

200 I I Power Range N142 fails HIGH 2 10IACRA1 I C-BoP I Loss of Control Room North Air Handling Unit 3

(Global)

CVO5 @

20%

I TS C-RO I Letdown Heat Exchanger leak (to CCW) 4 RX18 to 0 I-BOP Main Steam Turbine Bypass Header Pressure UPC-101 Fails Low (Steam Input to FWP Delta-P) 5 RP08A I Major I Spurious Feedwater Isolation 6 RPOIA, Reactor Fails to Automatically Trip RPOI B.

Preload 7a CVOI 38 2W Centrifugal Charging Pump Trip (fail t o start) 7b EDO5H C-BOP Loss of 4KV Bus T 2 1 D (Loss of E CCP and E MDAFP) on the Reactor Trip 8 FW46C C-BOP Turbine Driven AFW pump Trips on Reactor Trip -Loss of Heat Sink criteria established (N)ormal, Cook Plant Unit 1 & 2 NUREG-1021, Revision 9 Page 1 o f 2

Summary The Scenario begins a t 74% with directions t o raise power t o 1 0 0 % following a forced outage.

After the crew has assumed the watch, NPP-151 Pressurizer Pressure Channel fails low. The RO will need t o take manual control. The crew will implement an Abnormal Operating Procedure, address Technical Specifications, select an operable channel, and restore pressure control t o automatic.

The second event is a trip of the North Control Room Air Handling Unit. The crew will need t o investigate the cause, start the South Air Handling Unit, and address Technical Specifications.

After the South Control Room Air Handling Unit is started, a letdown heat exchanger leak will occur. The crew will need t o address CCW in-leakage, implement an Abnormal Operating Procedure, isolate Letdown, and establish excess letdown.

After excess letdown is established, the Main Steam Turbine Bypass Header Pressure UPC-101 Fails Low (Steam Input t o FWP Delta-P) causing the FW pumps t o slow down. The BOP will need t o take manual control of FW Pump Speed t o establish the proper DP t o continue feeding the SGs.

A spurious Feedwater Isolation will require a reactor trip. The automatic Reactor Trip fails requiring the RO t o manually trip the Reactor.

On the Reactor trip, a fault occurs on bus T21 D and, separately, the TDAFP trips on mechanical overspeed. The BOP must shutdown the CD DG t o prevent the cyclic loading attempts.

The crew will implement E-0 and transition t o FR-H.l loss of Heat Sink within the first few steps. Once FR-H.l is implemented, the crew will be required t o trip the RCPs and initiate feed and bleed. The crew will direct actions t o restore FW and should dispatch an operator t o reset and start the TDAFP. The scenario will terminate once flow is restored t o the SGs.

Critical Tasks Trip Reactor Establish RCS Feed and Bleed Establish FW Flow before SGs Dry out.

Procedures E-0 Reactor Trip or Safety Injection FR-H.l Response t o Loss of Heat Sink Cook Plant Unit 1 & 2 NUREG-1021,Revision 9 Page 2 of 2

Cook Plant Scenario Outline Form ES-D-1 Facility: Cook Plant Unit 1 & Unit 2 Scenario No.: COOK06-06 Op-Test No.: SPARE Examiners: Operators:

Event Malf. No. Event Event

-No.

1

-- Type*

N Description Start South NESW pump and Stop North NESW pump 2 I CVl6A@100 I I-RO I VCT Level Transmitter (QLC-451) fails HIGH 3 CVO9@5o"F C-RO Letdown Temperature Controller fails LOW 4 RX21C@2 I-BOP SG Feed Flow Instrument (FFC-220) fails LOW TS 5 I RC19A @ 100% 1 M I Pressurizer Safety Valve Fails Open 6 TC03 RP07A I C-BOP I Failure of Main Turbine Auto Trip (With SLI failure)

RP07B I I Cook Plant Unit 1 &Unit 2 NUREG- 1021, Revision 9 Page 1 o f 2

Summary The crew is directed to start the South NESW Pump and shutdown the North NESW Pump while maintaining reactor power at 74%.

The first event will involve the VCT Level instrument (QLC-451) failing HIGH. This will result in the VCT High Level alarm, full divert, and loss of auto makeup. The crew will be required to enter the AOP and address the Technical Requirements Manual. The RO will be required to perform a manual blend to RCS.

The second event will involve the Letdown Temperature Controller failing LOW in AUTO. This will result in the loss of letdown cooling. RO will he required to take manual control of CRV-470 and restore temperature to normal band.

The third event will involve a failure of #22 Steam Generator Feed Flow instrument (FFC-220) LOW. This will result in a rise in feedwater flow to #22 SG with corresponding SG level rise. The BOP will be required to take manual control of FRV-220. Crew will be required to implement AOP actions to stabilize the plant and address Technical Specifications.

The major event will involve the opening ofNRV-153 to full open. A unit trip will be required. As the crew performs the actions of E-0, the Main Turbine will fail to automatically trip. The crew will transition to E-1. The scenario will terminate when the crew has transitioned to ES-1.2 for Post LOCA cooldown.

Critical Tasks Manually trip the Turbine prior to a transition to ECA-2. I Stop all running RCPs when RCS pressure is below 1300 psig Procedures E-0, Reactor Trip or Safety Injection E-I, Loss of Reactor or Secondary Coolant Cook Plant Unit 1 & Unit 2 NUREG-1021,Revision 9 Page 2 of 2

DC COOK 2006 INITIAL LICENSE EXAM OPERATING OUTLINE COMMENTS Source 1 Comment Resolution Admin JPM A There is no KIA listed associated with Section 2.1 of Replaced JPM A with one the WA catalog. Admin JPMs are required to have a to review a completed WA from Section 2 of the WA catalog (per page 11 of SDM calculation (KIA ES-303-1). 2.1.25).

[Admin JPM A was initially Unsatisfactorvl Admin JPM B The WA listed is associated with Section 2.2 of the The WA was changed t o WA catalog. JPMs associated with Conduct of WA2.1.12.

ODerations need to have a WA from Section 2.1.

Admin JPM A Both Admin JPM A and Admin JPM B are associated Replaced JPM A with one Admin JPM B with the same system (Nuclear Instrumentation). This to review a completed creates the possibility of "double jeopardy" if a SDM calculation candidate is weak on one system. The JPMs should (KIA 2.1.25).

come from different systems.

Control Room Editorial: The WA for this JPM should be APE 024 Comment incorporated.

JPM A A1.17(not EPE024A1.17).

Control Room The WA for this JPM is associated with the ECCS Replaced JPM B with one JPM B system, but this evolution is for a normal swap of the to raise SI accumulator charging pumps. Thus, the evolution should be level.

associated with the CVCS system. This makes [Control Room JPM B was Control Room JPMs A and B both associated with the initially Unsatisfactory]

CVCS system, which is prohibited per page 14 of ES-301 (each Control Room JPM must come from a different system).

Scenario #3 Since the crew may not want to raise Reactor Power Changed Scenario #3 so with the failed Hot Leg temperature instrument, add that the crew initially information for the Simulator Booth to call back as the raises Reactor Power Load Dispatcher to raise power (if necessary). before any malfunction event occurs.

Scenario #5 On the Summary sheet attached to the Scenario Comment incorporated.

Outline, it states that Event 1 is a failure low of PZR Pressure channel NPP-151. However, the Scenario Outline sheet specifies that Event 1 is a failure high of Power Range channel N142. Change the Summary sheet to reflect a failure high of Power Range channel N142.

Retrieved from "https://kanterella.com/w/index.php?title=ML060880007&oldid=2586442"