ML082820486

From kanterella
Jump to navigation Jump to search
Operator Licensing Exam Final Outlines (Folder 3)
ML082820486
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/26/2008
From:
Public Service Enterprise Group
To: Brian Haagensen
Operations Branch I
Hansell S
Shared Package
ML080030005 List:
References
50-272/08-301, 50-311/08-301, U01686
Download: ML082820486 (22)
v • d • e


Text

~~

ES-401 PWR Examination Outline Form ES401-2 Facilitv: Salem Generating Station Printed: 08/06/2008 Date Of Exam: 08/25/2008 RO WA Category Points 1 SRO-Only Points 1.

rmergenc:

Abnormal Plant Evolutions 2.

Plant Systems 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 (i.e.,except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each K/A 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 i1 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. Systemdevolutionswithin 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 systemslevolutionsthat are not included on the outline should be added. Refer to Section D.l.b of ES401 for guidance regarding the elimination of inappropriate WA 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) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable WAS.
9. On the following pages, enter the K/A 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; 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 #I does not apply). Use duplicate pages for RO and SRO-only exams.

I, For Tier 3, select topics from Section 2 of the WA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3 Limit SRO selections to K/As that are linked to 10 CFR 55.43.

PM'R KO Caaminttticm Outline ac'ility: Salem Generating Station S - 401 Emergenq and Abnormal Plant Evolutions - Tier 1 / Croup 1 ForrnES-401-2 --c ,

LZ-1

~~

E/APE # 1 Name J Safety Function K1 Ii2 IC? A l A2 G K A Topic Imp.

)00007 Reactor Trip - Stabilization - I I I 1x1, I E;A I .04 - CVCS 3.2 I X 1.02 - Use of steam tables

'EA I .07 - Containment isolation system 0000 i 5l0000 i 7 RCF Maiiuncrions I 4 1' AX!.C!I - Cause ofRCFJ fziltire 3 .cI

-~~

I I

~ ~

000025 Loss of RHR System / 4 x AA1.05 - Limitations on LPI flon and 3.1

  • temperature rates of change 000026 Loss of Component Cooling Water i X AA 1.07 - Flow rates to the components 2.9 8 and systems that are serviced by the CCWS: interactions among the components 000027 Pressurizer Pressure Control System X AI(2.03 - Controllers and positioners 2.6 Malfunction 1 3 000038 Steam Gen Tube Rupture I 3 X EK3.06 - Actions contained in EOP for 4.2 RCS water inventory balance, S/G tube rupture. and plant shutdown procedures

'000054 Loss of Mam Feedwater 4 x AK I .02 - Effects of feedwater 3.6 I introduction on dry SiG

~

000055 Station Blackout 6 x 2.4.13 - Knowledge of the bases for 3 '4 I f:

prioritizing emergenc! procedure implementation during emergency operations.

000056 Loss of Off-site Power I 6 X - k . 8 ? - Temperatures displayed on plant computer CRT monitor 000058 Loss of DC Power ' 6 X A l 3 . 0 2 - Actions contained in EOP for loss of dc power

__ ~-

000065 Loss of Instrument Air 8 X 2 4 18 - Knowledge of the specific 3.3 bases for EOPs 000077 Generator Voltage and Electric Grid X 2 4.50 - Ability to veri6 system alarm 4.2 Disturbances / 6 setpoints and operate controls identified in the alarm response manual.

W/E04 LOCA Outside Containment / 3 X EKI 2 - Normal. abnormal and 35 Containment WI'EOS inadequate Heat Transfer - Loss of x EK2.2 - Facility's heat removal systems. 3.9 SecondaQ Heat Sinh 14 including primarj coolant. emergenc?

coolant. the decay heat removal systems. and relations between the pi ope1 operation of these systems to the operation of the facility

E/APE # / Name / Safetj Function K1 li2 K3 A1 A2 G KA Topic Imp. Points

&'/El I Loss of Emergency Coolant Recirc. 1 I X ~ EI(2.2 - Facility's heat removal systems, 3.9 1 1 including primary coolant, emergency I

' coolant, the decay heat removal I

' systems, and relations between the 1 proper operation of these systems to the operation of the facility I

~~

W/E12 Steam Line Rupture - Excessive x' SM.2 - Normai, abnormal and 3.3 I Heat Transfer / 4 1 emergency operating procedures l issociated with Uncontrolled Depressurizaitonof all Steam Generators WA Category Totals: 3 3 3 3 3 3

S - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 EIAPE ## IName f Safety Function K1 K3 A1 A2 G KATopic Imp. Points

)0000 1 Continuous Rod Withdrawal / 1 x AKI .03 - Relationship of reactivity and 3.9 1 reactor power to rod movement 100037 Steam Generator Tube Leak I 3 x AA7.14 - Actions to be taken if S!G 4 .0 1 goes solid and water enters steam lines 100051 Loss of Condenser Vacuum I 4 X .4K3.0I - Loss of steam dump 2.8* 1

, ,cqahi!if? upori loss of condenser vacuum 300059 Accidental Liquid RadWaste ReI. I X AKl.O1 - Types of radiation, their units 2.7 1 9 of intensity and the location of the sources of radiation in a nuclear power rd plant 000067 Plant Fire On-site / 9 X AK1.O1 - Fire classifications, by type 2.9 1 000069 Loss of CTMT integrity I 5 X AKl .O1 - Effect of pressure on leak rate 2.6 I 000074 h a d . Core Cooling 1 4 X EA2.03 - Availability ofturbine bypass 3.8 1 valves for cooldown W/E03 LOCA Cooldown - Depress. / 4 X EK2.1 - Components, and functions of 3.6 1 control and safety systems, including instrumentation. signals, interlocks, failure modes, and automatic and manual features PIE09 Natural Circ. / 4 X EA 1.3 - Desired operating results 3.5 1 during abnormal and emergency situations IUA Category Totals: 4 1 1 1 2 0 Group Point Total: 9

~ ~ ~~~~ ~~~~~~ ~~~~~~

1

Facility: Salem Generating Station A-Plant Systems - Tier 2 Croup I Form CS-401-2 ES - 401 1 Sys/Evol fr I Name K1 K2 K3 K4 KS k6 A 1 A2 A3 A4 G K A Topic imp. Points 003 Reactor Coolant Pump x K 4 07 - Minimizing RCS leabage (mechanical seals) 3 .2 I La 003 Reactoi Coolanl Pump x AI 05 - RCS flow 3.4 2-7 004 Chemical and Volume Control X A:! 19 - High \econdan and 2.8 1 primary concentrations of chloride, fluoride, sodium A?

and solids r

004 c!:eE!c2! 2nd VO!?LFlP Cnntrol , , I X I A4 OS - Letdown pressure 3.6 I

1 30 1 and temperature control valves X K5 09 - Dilution and 3.2 005 Residual Heat Removal boration considerations 31 006 Emergency Core Cooling x A? OS - Safet) Injection 4.2 3A Pumps 006 Emergency Core Cooling X K6.05 - HPULPI cooling water 3 .O 33 007 Pressurizer Relief/Quench Tank X K5.03 - Method of formmg a steam bubble in the PZR 3.1 3it 008 Component Cooling Water X 2 4 34 - Knowledge of RO 4.2 I tasks performed outside the main control room dunng an 3s emergenc) and the resultant operational effects 0 1 0 Pressuruer Pressure Control X K3.01 - RCS 3.8 1 36 0 11 Reactor Protection X K4 08 - Lo&icmatrix teshng 2.8* 1 36 0 12 Reactor Protection X K5.01- Power dens15 3.1* I 0 13 Engineered Safe0 Features X A I .09 hot 34 l 4 a Actuation 072 Contament Cooling X E . 0 1 - Containment 3.0*

cooling fans 44 026 Containment Spray x A2.02 - Failure of automatic 4.2* 1 qS recirculation transfer 039 Main and Reheat Steam X A4.07 - Steam dump valves 2.8* 1 99 039 Main and Reheat Steam X Ki3 03 - AFW pumps 3.2* 1 50 059 Main Feedwater X K4 18 - Automatic 2.8 1 feedwater reduction on plant 5, trip 06 1 AuxiliarqEmergency X K6.02 - Puinps 7.6 l s a Feedwater 062 AC Electrical Distribution x K l 02 - ED/G 41 1 53 062 AC Electrical Dismbution X K 1.03 - DC distribution 3.5 -54 063 DC Electrical Distribution X A1.01 - Grounds 3.5 I 5s 063 DC Electrical Distribution X 2 1 15 - Knowledge of 17 1 administrative requirements foi temporar) management 56 duectrves, such as standing orders, night orders, 08/06/2008 65756 pm I

PWR RO Examination Outline Printed: 08i06,2008 Facility: Salem Generating Station @*sf\&

Plant Systems - Tier 2 /Group 1 d

ES 401 Form ES-403-2 L__

I 1 Sys/Evol# / Name Kl I Operations memos, etc.

K2.02 - Fuel oil pumps 064 Emergencj Diesel Generator 5-7 2.1.39 - Knowledge of 073 Process Radiation Monitoring conservative decision bo makinec.

oractices.

076 Service Water A4.01 - SWS pumps 2.9 I 078 Instrument Air X

! X A3.01 - Air pressure E3.03 io!js of containmenr 3.1 3.7 1

i 103 Containment I integrity under reheling operations K/A Category Totals: 2 3 3 3 2 2 3 2 3 3 Group Point Total: 28 I

I 08/06/2008 6:57:56 prn 2

PM'R K O Examination Outline Printed: 06:'06 ' X 0 8

?44 13,-

Plant Systems Tier 2 /Group 2 ' Form ES-401-2 4 SydEvol # I Name K1 K6 AI A2 A3 A4 G KA Topic Imp. Points 01 1 Pressurizer Level Control X 3.4.23 - Knowledge of the 3.4 1 bases for prioritizing emergency procedure implementation during emergency operations.

014 Rod Position lndication X A4.03 - Control rad 3.4 I mode-select switch X A 1 .OX - Changes in RCS 3.3* 17 0 16 Non-nuclear Instrumentation X 027 Containment Iodine Removal x t

028 Hydrogen Recombiner and Purge Control 034 Fuel Handling Equipment I 07 1 Waste Gas Disposal I

1 072 Area Radiation Monitoring 086 Fire Protection WA Category Totals: I 0 1 1 1 1 1 1 1 Group Point Total: 10 OR10612008 6:58:03Dm I

Generic Knowledge and Abilities Outline (Tier 3 )

t N r R RO Examination Outline Printed: 08/06/2008 Facilitv: Salem Generating Station Form ES-401-3 Generic Category Conduct of Operations clear, and concise 3.9 1 2.1 2 7 I Knowledge of system purpose and/or function. I 3.9 I I I requirements.

Equipment Control 2.2.23 Ability to track Technical Specification limiting 3.1 1 conditions for operations. c3-7 2.2.36 Abiljty to analyze the effect of maintenance 3.1 1 activities. such as degraded power sources, on the status of limiting conditions for operations.

Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergent!' conditions.

713 2.3.1 1 Abilit). to control radiation releases. 3.8 I 72-2.3.14 Knowledge of radiation or contamination hazards 3.4 1 that ma! arise during normal. abnormal. or 71 emergency conditions or activities.

~ ~- ~

I Emergency ProceduresPlan 2.4.14 Knowledge of general guidelines for EOP usage. 3.8 1 73 I 2.4.25 Knowledge of fire protection procedures.

Generic Total:

3.3 I 10 74

~ -~ _ ~ _ ~~ -~ ~ ~ ~ _ _

- ~ ~~

ES-40 1 PWR Examinahon Odtline Form ES401-2 u

Faciliw Salem Generating Station Printed 08/06/2008 Date Of Exam 08/25/2008 I I I RO K/A Category Points 1 SRO-Only Points k

based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

1

3. Systems/evolutionswithin 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/evolutions that are not included on the outline should be added Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate WA 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-specificpriority, 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) K/As in Tiers 1 and 2 shall be selected from Section 2 of the W A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES401 for the applicable WAS.

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, iffuel handling I

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 #I does not apply) Use duplicate pages for RO and SRO-only exams

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

~

- -. ^. 1

PMR SKO Lxxmirration OutIine Printed: 08Kh2OOS Q d ( c 3 r Facility: Salem Generating Station ES - 401 Emergency and Abnorma Pla t Evolutions - Tier 1 / Group I Form ES-401-2 ---4 E/APE # /Name / Safer:, Function KI U K3 AI A2 C I(A Topic Imp. Points 000007 Reactor Trip - Stabilization -

Recovery / 1 guidelines, or limitations associated i

I I I I I

10000?? Loss of Kx Coolant Makeup / 2 X AA2.02 - Charging pump problems I

I I M . 0 7 - The cause of possible CCW I000026 Loss of Component Cooling Water I Is X

I j loss J

I 000027 Pressurizer Pressure Control System Malfunction / 3 X AA2.07 - Makeup flow indication 3.1 000040 Steam Line Rupture - Excessive X 2.1.45 - Ability to identifir and interprel 4.3 Heat Transfer / 4 diverse indications to validate the 6 response of another indication.

000056 Loss of Off-site Power / 6 x 2.2.14 - Knowledge ofthe process for 4.3 controlling equipment configuration or status.

t I I I K/A Category Totals: 1 0I0 0 I 0 31 Group Point Total: 6 I I

PUR SRO Examination Outline Prmted. OS062001; Fscility: Salem Generating Station b&Jr ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 {Group 2 Form ES-401-2 &

I I EIAPC ## / Name /Safety Function KI KA Topic i /Imp*

000033 Loss of lritemediate Range Nl 7 000059 Accidental Liquid RadWaste Rel. I

-I M . 0 1 - Equivalency between source-range, intermediate-range, and power-range channel readings 2.4.21 - Knowledge of the parameters 3.5 4.6 9 and logic used to assess the status of safety fimctions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity 1 000069 Loss of CTMT lntegrity t 5 release control, etc.

AA2.02 - Verification of automatic and 4.4 manu1 means of restoring integrity W/E02 Si Termination / 3 2.2.22 - Knowledge of limiting 4.7 conditions for operations and safety limits.

Grom Point Total: 4 I 1

PV'R SRO Examination Outline Fbcility: Salem Generating Station Plant Systems - Tier 2 /Croup 1 Farm ES-401-2 ES - 401 Sys/Evol# / Name K1 K2 1(3 K4 026 Containment Spray 059 Main Feedwater 054 Emergency Diesel Generator 073 Process Radiation Monitoring 078 Instrument Air IUACategory Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 06/06/2008 6:51:14pm

- I -- ~~ #&

PWR SRO Examination Outline Printed. 0806,2008 Facility: Saleni Generating Station wd 10 ES - 401 SyslEvol # /Name K1 Ei? K3 K4 lis K6 A1 A2 A3 A4 G KATopic Imp. Points 0 1 1 Pressurizer Level Control X A2.05 - Loss of PZR heaters 3.7 I 029 Containment Purge X 2.3.14 - Knowledge of 3.8 1 radiation or contammation hazards that may arise during normal, abnormal, or emergency conditions or activities.

068 Liquid Radwasre I 1 XI I A2.02 - Lack of tank 2.8* 1 recirculation prior to release WACategory Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 08/06/2000 6:51:20 pm 1

PM7R SHO Examination Outline Printed: OSf06/2006 Facility: Salem Generating Station Form ES-401-3 ?U%h 0 '0 4-Generic c, a t e e o ~ K9 KA Tonic Ima. Points Conduct of Operations 2.1.34 Knov. ledge of primag and seLoiidar) plan1 3.5 1 chemistrj Iimirs 2,1.39 Knowledge of conservative decision making 4.3 I practices Equipment Control 2.2.18 Knowledge of the process for managing 3.9 1 maintenance activities during shutdown operations. such as risk assessments, work prioritization. etc.

~~ ~-

i Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

L 2.3.13 Knowledge of radiological safe8 procedures pertaining to licensed operator duties. such as response to radiation monitor alarms, containment e n t c requirements, fuel handlmg responsibilities, access to locked high-radiation areas. aligning fdters. etc.

-~

Category Total: 2 Emergency ProceduredPlan 3.4.26 Knowledge of facilic protection requirements, 3.6 1 including fire brigade and portable fire fighting equipment usage.

2.4.28 Knowledge of procedures relating to a security 4.1 event (non-safeguards information). 25 Categoq Total: 2 d

1

TierIG roup Randomly Reason for Rejection Selected K/A RO Ill 022 AKI .02 Sampled on CERT Exam RO 112 WE01 2.1.75 NA to WE01 (Rediagnosis) 1 RO 112 1 024 AAI .08 1 Pump speed control is for recirc (slow) and boration (high) and is not related to seal I protection.

RO 112 068 K3.16 Salem does not have fail open control room access doors.

RO 211 007 K3.01 Sampled on CERT Exam RO 211 008 A I .01 Too similar to RO Tier 1 Group 1 KIA for 006 A I .07 RO 211 010 K5.02 Too similar to RO Tier 1 Group IKIA FOR 008 AK1.01 on CERT Exam( constant enthalpy throttling characteristics RO 211 025 K1.O1 Salem does not have Ice Condenser ~~

RO 211 059 2.4.27 Not specific to Main Feedwater (knowledge of fire in the plant procedure)

RO 211 062 2.2.23 Oversampling of Generic 2.2.23 (Ability to track TSAS) (also in Tier 3)

RO 211 073 A I .01 Sampled on CERT Exam . _.

1 RO 211 1 076 K1. I 5 I No physical connection or cause/effect relationship between service water and Fire Protection systems RO 212 055 K3.01 Sampled on CERT Exam SRO 112 032 2.1.34 Chemistry limits NA to Loss of SR Nls SRO 211 103 2.3.5 Not SRO level SRO 211 006 A2.1 1 Over sampling of ECCS system (3 on entire exam)

SRO 212 014 2.4.28 Security event NA to RPI system.

RO 112 001 AK2.01 Manually replaced with same system, AKI .03 to match question developed per NRC direction.

RO 212 , 059 AK3.02 , Manually replaced with same system, AKI .01, to allow a question to be written that is not Level of difficulty 5 as originally submitted.

RO 112 EO9 2.1 . I 4 Manually replaced with same system EA1.3 to allow a question to be written.

SRO 212 064 A2.10 Manually replaced with same system, A221 to allow for SRO question to be written.

SR03 2.3.1 5 Manually replaced with 2.3.1 3 to allow SRO level question to be selected.

NOTE: All rejected WAS were deleted from Outline. Replacement WAS were then selected by generating a random exam with the remaining WAS still inserted. All deleted WASwere replaced with randomly selected WAS by the Exam Generation software. KIAs removed or changed from exam per NRC direction were manually replaced with WAs approved by the NRC. Manually replaced WAs are identified as such on this form, all others were randomly replaced.

ES-401, Page 27 of 33

ES-301 Ad minist rat ive Topics OutIi ne Form ES-301-1 Facility: SALEM Date of Examination: 08/25/2008 Examination Level: RO SRO Operating Test Number: 07-01 NRC Administrative Describe activity to be performed Topic (See Note) TY Pe Code*

Calculate Shutdown Margin Conduct of Operations 2.1.25 Ability to interpret reference materials such as graphs, curves, tables, etc..

RO 3.9 Conduct of Verify qualifications prior to assuming Licensed Operator Duties.

Operations 2.1.3 Knowledge of Shift or short term relief turnover practices. RO 3.7 A Perform Subcooling Margin Monitor System operations (determine if displayed I Equipment Control NS Subcooling is correct) 2.2.44RO 4.2 (IC-171)

Radiation Control NA NA Perform the duties of the Secondary Communicator during an Alert 2.4.39 Knowledge of ROs responsibilities in Emergency Plan implementation.

RO 3.9 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (3 for ROs; 4 for SROs & RO retakes)

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

(P)revious 2 exams (I;randomly selected)

ES-301 Administrative Torics Outline Form ES-301-1 Facility: SALEM Date of Examination: 08/25/2008 Examination Level: RO SRO Operating Test Number: 07-01 NRC Administrative Describe activity to be performed Topic (See Note) TY Pe Code*

Verify shift operators are qualified to perform specified duties (From list of operators assigned to shift, which of them can take vibration data.)

Conduct of Operations 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. SRO 3.9 Conduct of Review calculated head vent time in FRCI-3 Operations 2.1.20 Ability to interpret and execute procedure steps SRO 4.6 Initiate an OTSC to an Implementing Procedure Equipment Control 2.2.6 Knowledge of the process for making changes in procedures . SRO 3.6 Review a radioactive gaseous waste release form.

Radiation Control 2.3.6 Ability to approve release permits. SRO 3.8 Classify Emergency I Non-Emergency Events, and complete the ICMF.

Emergency Plan 2.4.29 Knowledge of the Emergency Plan SRO 4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (3 for ROs; 4 for SROs & RO retakes)

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

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

ES-301 Control Room Systemdln-Plant System Outline Form ES-301-2 Facility: SALEM Date of Examination: 08/25/08 Exam Level : RO X SRO-I SRO-U Operating Test No.: 07-01 ILT NRC Exam Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System I JPM Title I I

Type Code* I I

Safety Function 1, a. Respond to Main Turbine Runback with malfunctioning Auto Rod Control (IC 145) S,NA 1 t b. Respond to VCT level channel failure and perform a manual makeup to the VCT (IC-141)

Respond to PZR spray valve failure (IC-142)

d. Swap operating RHR loops with one loop aligned for ECCS injection in MODE 4 (IC-I 72)

SD S,L,D,A S,L,N 2

3 4 (Pro 1 f. Failure of 2C 4KV Vital Bus to Transfer to the Alternate Source (IC144) 1 S,D,A I 6

g. Respond to loss of Source Range Nuclear Instrumentation during refueling operations. S,N 7
h. Start 21 CCW pump IAW APPX-1 (IC-143) SLDA 8
i. Locally manually isolate seal injection during LOPA R, D,P 4 (Pro
j. Locally start 23 AFP and feed SGs during CR evacuation R,D,E 4 (sec)
k. Commence a liquid waste release, and respond to high activity during the release R,MA 9 l @ All RO and SRO-I control room (and in plant) 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 RO I SRO-I I SRO-U

~

(A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank e9

- 1 5 8 154 (E)mergency or abnormal in-plant >

- I I >.I 121 (EN)gineered safety feature - I - I 2 1 (control room system)

(L)ow-Power I Shutdown >I1 2 1 I ,I (N)ew or (M)odified from bank including 1 (A) >2 I 22121 (P)revious 2 exams <3 I 53

- 7 5 2 (randomly selected)

(R)CA ->II ~ 1 / > . 1 (S)imulator

___I_

ES-301 Control Room Systemdln-Plant System OutIine Form ES-301-2 1 Facility: SALEM Date of Examination: 08/25/08 l Exam Level : RO SRO-1 x SRO-U Operating Test No.: 07-01 ILT NRC Exam I

,- ~ ~

System I JPM Title T~~~ Code* Safety Functior

a. Respond to Main Turbine Runback with malfunctioning Auto Rod Control S,NA 1
b. Respond to VCT level channel failure and perform a manual makeup to the VCT S,D 2
c. Respond to PZR spray valve failure S,L,D,A 3
d. Swap operating RHR loops with one loop aligned for ECCS injection in S,L,N 4 (Pro Perform a CFCU Operability and Service Water Flow Verification (UNIQUE) S,N, A 5
f. Failure of 2C 4KV Vital Bus to Transfer to the Alternate Source S,D,A 6

~-

I I I. Locally manually isolate seal injection during LOPA D,P,R 4 (Pro 1 j. Locally start 23 AFP and feed SGs during CR evacuation 1 R,D,E

k. Commence a liquid waste release, and respond to high activity during the release 1

i R,M,A 9

@? All RO and SRO-I control room (and in plant) 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 RO I SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank <9 1 1 8 154 (Qmergency or abnormal in-plant > II >I

- 121 (EN)gineered safety feature - I - I 1 1 (control room system)

(L)ow-Power / Shutdown >I/

- 11 I ,I (N)ew or (M)odified from bank including 1 (A) >2 I L212-I (P)revious 2 exams +c 3 I 5 3

- 7 52 (randomly selected)

> I I

- F 1 1 ~ 1

_ _ _ _ _ _ _ _ _ ~ ~

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: N R C ESG-1 Op-Test No.: 07-01 NRC Examiners: Operators:

Initial Conditions: 100% Rated Thermal Power Turnover: Unit at 100% power. 22 AFW pp is C/T. Lower power to 85% at 20% per hour in preparation for removing a Condensate Pump from service.

I Event Type*

I Event Description N,R Power reduction for Condensate Pump emergent maint.

CRSIROIPO EDG oil leak (TS)

PZR level channel failure, letdown isolation, letdown r e I

establish (TS) Note: The RO will provide the PZR level CRSIRO~O channel failure initial response, the PO will restore letdown) u Steam Generator Tube Leak (TS)

CRSIROIPO M I 1

Steam Generator Tube Rupture CRSIROIPO C I SEC activated equipment fails to start I

C SG Atmospheric relief fails partially open I

(I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 I/ Facility:

Examiners:

SALEM 1 & 2 Scenario No.:N R C ESG-2 Operators:

Op-Test No.: 07-01 NRC Initial Conditions: 1 X 1 0 8Amps for critical data.

Turnover: Raise power to 3-4%.

I I I Event I I Description 1 R CRSlRO 1 Raise Rx power to 3-4%

l l 1 I CRSiRO 1 IR NI fails IOW (TS)

C D VIB deenergizes causing no Auto or Manual rod control 2 2 CRS/RO/PO just as Rx is entering POAH (TS) 3 C 1 of 2 operating MDAFW pps trip on Rx trip.

M 3 4 RCS leak progressing to LBLOCA w Auto SI failure.

CRSlRO Various SEC initiated components malfunction (RHR pp fail C

to start, no auto CS) 4 5 C Loss of Emergency Recirc fl

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1

- ~~ ~~~~ ~

~ Facility: SALEM 1 & 2 Scenario No.: NRC ESG-3 Op-Test No.: 07-01 NRC I

Examiners: Operators:

1 Initial Conditions: 80% power for last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I

Turnover: Raise power to 90% @ 3% per hour. (Power ascension ramp limit is 3%/hr)

Event Malf. No. Event Type* Event No. Description N,R Raise Rx power CRS/RO/PO I MT Steamline Inlet Pressure Transmitter fails high (TS)

CRSIROIPO L/K CRSIROIPO I SGFP oil leak, trip with no auto MT runback 1131 CRS/~o,PO 1 Feedwater rupture on common SGFP discharge header, MSLl failure, A m T

/I I 4 C 1 SG Code Safety fails open post trip 5 C Single 4KV Group bus fails to transfer Appendix D,Page 38 of 39

Retrieved from "https://kanterella.com/w/index.php?title=ML082820486&oldid=2566326"