ML082820486
| ML082820486 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| 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) | |
Text
ES-401 ~~ PWR Examination Outline Form ES401-2 Facilitv:
Salem Generating Station Printed : 08/06/2008 Date Of Exam: 08/25/2008
- 1. rmergenc:
& Abnormal Plant Evolutions - 2. Plant Systems - Note: RO WA Category Points 1 SRO-Only Points 1. 2. 3. 4. 5. 6. 7.* 9. 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). 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. 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 systemslevolutions that 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.
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.
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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories 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. 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 10 CFR 55.43. Limit SRO selections to K/As that are linked to ac'ility:
Salem Generating Station S - 401 E/APE # 1 Name J Safety Function PM'R KO Caaminttticm Outline K1 Ii2 IC? Al A2 G Emergenq and Abnormal Plant Evolutions - Tier 1 / Croup 1 0000 i 5l0000 i 7 RCF Maiiuncrions I 4 000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water i 8 000027 Pressurizer Pressure Control System Malfunction 13 000038 Steam Gen Tube Rupture I3 '000054 Loss of Mam Feedwater 4 I 000055 Station Blackout 6 000056 Loss of Off-site Power I 6 000058 Loss of DC Power ' 6 000065 Loss of Instrument Air 8 000077 Generator Voltage and Electric Grid Disturbances
/ 6 1' x X X X x x X X X X )00007 Reactor Trip - Stabilization - I I I 1x1, I ~ 2.4.13 - Knowledge of the bases for prioritizing emergenc!
procedure implementation during emergency operations.
3 '4 __ ~- 2 4 18 - Knowledge of the specific bases for EOPs 2 4.50 - Ability to veri6 system alarm setpoints and operate controls identified in the alarm response manual.
EKI 2- Normal. abnormal and - KA Topic 3.3 4.2 35 E;A I .04 - CVCS W/E04 LOCA Outside Containment
/ 3 WI'EOS inadequate Heat Transfer - Loss of SecondaQ Heat Sinh 14 ForrnES-401-2
--c , LZ-1 X x ~~ Imp. Containment EK2.2 - Facility's heat removal systems. 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 - 3.2 3.9 IX 1.02 - Use of steam tables 'EA I .07 - Containment isolation system AX!.C!I - Cause ofRCFJ fziltire 3 .cI I I -~~ ~ ~ AA1.05 - Limitations on LPI flon and temperature rates of change 3.1
- AA 1.07 - Flow rates to the components and systems that are serviced by the CCWS: interactions among the components 2.9 AI(2.03 - Controllers and positioners 2.6 EK3.06 - Actions contained in EOP for RCS water inventory balance, S/G tube rupture. and plant shutdown procedures AK I .02 - Effects of feedwater introduction on dry SiG 4.2 3.6 -k.8?- Temperatures displayed on I f: plant computer CRT monitor Al3.02 - Actions contained in EOP for loss of dc power E/APE # / Name / Safetj Function Imp. 3.9 I I 1 , I 3.3 K1 Points 1 I &'/El I Loss of Emergency Coolant Recirc.
1 I 1 li2 X K3 A1 A2 x' 3333 - G ~ EI(2.2 - Facility's heat removal systems, including primary coolant, emergency
' coolant, the decay heat removal
' systems, and relations between the proper operation of these systems to the operation of the facility KA Topic ~~ SM.2 - Normai, abnormal and 1 emergency operating procedures l issociated with Uncontrolled Depressurizaiton of all Steam Generators W/E12 - Steam Line Rupture - Excessive Heat Transfer / 4 WA Category Totals: 3 3 S - 401 EIAPE ## I Name f Safety Function K1 K3 A1 A2 G KATopic Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 )0000 1 Continuous Rod Withdrawal
/ 1 100037 Steam Generator Tube Leak I 3 10005 1 Loss of Condenser Vacuum I4 x AKI .03 - Relationship of reactivity and reactor power to rod movement AA7.14 - Actions to be taken if S!G goes solid and water enters steam lines .4K3 .0 I - Loss of steam dump x X , , cqahi!if?
upori loss of condenser vacuum 300059 Accidental Liquid RadWaste ReI. I X AKl.O1 - Types of radiation, their units of intensity and the location of the sources of radiation in a nuclear power plant 9 000067 Plant Fire On-site / 9 000069 Loss of CTMT integrity I 5 000074 had. Core Cooling 14 W/E03 LOCA Cooldown - Depress. / 4 X X AK1.O1 - Fire classifications, by type AKl .O1 - Effect of pressure on leak rate EA2.03 - Availability ofturbine bypass EK2.1 - Components, and functions of X valves for cooldown X 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 during abnormal and emergency situations IUA Category Totals: 4 1 1 1 2 0 Group Point ~ ~ ~~~~ ~~~~~~ ~~~~~~
rd Form ES-401-2 Imp. Points 3.9 1 4 .0 1 2.8* 1 2.7 1 2.9 1 2.6 I 3.8 1 3.6 1 3.5 1 Total: 9 1 Facility: Salem Generating Station Plant Systems - Tier 2 Croup I ES - 401 Sys/Evol fr I Name K1 K2 K3 K4 KS k6 A1 A2 A3 A4 G KA Topic 003 Reactor Coolant Pump x K4 07 - Minimizing RCS leabage (mechanical seals) 003 Reactoi Coolanl Pump x AI 05 - RCS flow X A:! 19 - High \econdan and 004 Chemical and Volume Control primary concentrations of chloride, fluoride, sodium and solids and temperature control valves K5 09 - Dilution and 005 Residual Heat Removal boration considerations A? OS - Safet) Injection 006 Emergency Core Cooling Pumps X K6.05 - HPULPI cooling 006 Emergency Core Cooling water 007 Pressurizer Relief/Quench X K5.03 - Method of formmg a steam bubble in the PZR Tank 008 Component Cooling Water tasks performed outside the main control room dunng an emergenc) and the resultant operational effects K4 08 - Lo&ic matrix teshng r A4 OS - Letdown pressure ,,I XI 004 c!:eE!c2!
2nd VO!?LFlP Cnntrol 1 X x X 2 4 34 - Knowledge of RO X K3.01 - RCS 0 1 0 Pressuruer Pressure Control 0 11 Reactor Protection 0 12 Reactor Protection 0 13 Engineered Safe0 Features Actuation 072 Contament Cooling 026 Containment Spray 039 Main and Reheat Steam 039 Main and Reheat Steam 059 Main Feedwater X X K5.01- Power dens15 X A I .09 hot X E.01 - Containment cooling fans A2.02 - Failure of automatic recirculation transfer A4.07 - Steam dump valves Ki3 03 - AFW pumps feedwater reduction on plant trip x X X X K4 18 - Automatic X K6.02 - Puinps 06 1 AuxiliarqEmergency Feedwater 062 AC Electrical Distribution x Kl 02 - ED/G 062 AC Electrical Dismbution X K 1.03 - DC distribution X A1.01 - Grounds 063 DC Electrical Distribution 063 DC Electrical Distribution X 2 1 15 - Knowledge of administrative requirements foi temporar) management duectrves, such as standing orders, night orders, 08/06/2008 65756 pm A- Form CS-401-2 imp. Points 1 I La 3.4 ' 2-7 A? 30 31 3A 3 .2 2.8 1 3.6 1 I 3.2 4.2 3 .O 3.1 4.2 I ' 33 ' 3it 3s 3.8 1 36 2.8* 1 36 3.1* I 34 3.0* 4.2* 1 qS 2.8* 1 99 l4a 44 3.2* 1 50 5, 2.8" 1 lsa 3.5 ' -54 7.6 41 1 53 3.5 I 5s 17 1 56 I PW'R RO Examination Outline Facility:
Salem Generating Station ES - 401 I 1 Sys/Evol#
/ Name Kl I 064 Emergencj Diesel Generator 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 103 Containment K/A Category Totals: Plant Systems - Tier 2 /Group 1 ! X X' 2333223233 Printed: 08i06,'2008
@*sf\& d Form ES-403-2 L__ Operations memos, etc. K2.02 - Fuel oil pumps 2.1.39 - Knowledge of conservative decision makine oractices.
- c. A4.01 - SWS pumps 2.9 I A3.01 - Air pressure 3.1 1 E3.03 I io!js of containmenr 3.7 i integrity under reheling operations Group Point Total: 28 I I 5-7 bo 08/06/2008 6:57:56 prn 2 SydEvol # I Name 01 1 Pressurizer Level Control 014 Rod Position lndication K1 0 16 Non-nuclear Instrumentation 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 034 Fuel Handling Equipment t I I 07 1 Waste Gas Disposal x 1 072 Area Radiation Monitoring 086 Fire Protection WA Category Totals: Printed: 06: '06 'X08 PM'R KO Examination Outline I Plant Systems Tier 2 /Group 2 ' ?44 13,- 4 Form ES-401-2 X 01 K6 AI A2 A3 A4 G KA Topic Imp. Points X 3.4.23 - Knowledge of the 3.4 1 bases for prioritizing emergency procedure implementation during emergency operations.
mode-select switch X A4.03 - Control rad 3.4 I X A 1 .OX - Changes in RCS 3.3* 17 111111 Group Point Total: 10 OR10612008 6:58:03 Dm I Generic Knowledge and Abilities Outline (Tier 3) clear, and concise 3.9 t 1 NrR RO Examination Outline Printed: 08/06/2008 requirements.
Facilitv:
Salem Generating Station Form ES-401-3 Equipment Control 2.2.23 Ability to track 'Technical Specification limiting conditions for operations.
2.2.36 Abiljty to analyze the effect of maintenance activities.
such as degraded power sources, on the status of limiting conditions for operations.
Generic Category Conduct of Operations - 3.1 1 3.1 1 Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 2.3.1 1 Abilit). to control radiation releases.
3.8 2.3.14 Knowledge of radiation or contamination hazards 3.4 normal or emergent!'
conditions.
that ma!' arise during normal. abnormal.
or emergency conditions or activities.
2.1 27 I Knowledge of system purpose and/or function.
I 3.9 I I I 1 I 1 ~ ~- 2.4.14 2.4.25 ~ Knowledge of general guidelines for EOP usage. 3.8 1 Knowledge of fire protection procedures.
3.3 I Emergency ProceduresPlan I I c3-7 713 72- 71 73 74 Generic Total: 10
~ ~ ~~ ~~ -~ ~ ~ ~__ - -~ _~_ ES-40 1 PWR Examinahon Odtline Form ES401-2 u Faciliw Salem Generating Station Printed 08/06/2008 Date Of Exam 08/25/2008 k based on NRC revisions.
The final RO exam must total 75 points and the SRO-only exam must total 25 points. Systems/evolutions 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/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. 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. 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 WA 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. 1 3. 4. 5. I I I RO K/A Category Points 1 SRO-Only Points 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, 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 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 Qd(c3r PM'R SKO Lxxmirration OutIine Printed: 08Kh'2OOS 4 Facility:
Salem Generating Station ES - 401 Emergency and Abnorma E/APE # /Name / Safer:, Function KI U K3 AI 000007 Reactor Trip - Stabilization - Recovery / 1 i 10000?? Loss of Kx Coolant Makeup / 2 I I I I I000026 Loss of Component Cooling Water I Is 000027 Pressurizer Pressure Control System I Malfunction
/ 3 000040 Steam Line Rupture - Excessive Heat Transfer / 4 000056 Loss of Off-site Power / 6 I I I t K/A Category Totals: 1 0 I 0 0 I 0 Pla A2 - I X X I I X t Evolutions - Tier 1 / Group I Form ES-401-2 --- C I(A Topic Imp. Points guidelines, or limitations associated AA2.02 - Charging pump problems I I M.07 - The cause of possible CCW j loss J AA2.07 - Makeup flow indication 3.1 '6 X 2.1.45 - Ability to identifir and interprel 4.3 diverse indications to validate the response of another indication.
controlling equipment configuration or status. x 2.2.14 - Knowledge ofthe process for 4.3 31 Group Point Total: 6 I I Prmted. OS'06'2001; PU'R SRO Examination Outline Fs'cility:
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 i 000033 Loss of lritemediate Range Nl '7 000059 Accidental Liquid RadWaste Rel. I 9 1 000069 Loss of CTMT lntegrity t' 5 W/E02 Si Termination
/ 3 KI KA Topic /Imp* M.01- Equivalency between 3.5 source-range, intermediate-range, and ----I-- power-range channel readings 2.4.21 - Knowledge of the parameters 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 release control, etc. AA2.02 - Verification of automatic and manu1 means of restoring integrity conditions for operations and safety limits. 4.6 4.4 2.2.22 - Knowledge of limiting 4.7 Grom Point Total: 4 I 1 PV'R SRO Examination Outline Fbcility:
Salem Generating Station Plant Systems - Tier 2 /Croup 1 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 Farm ES-401-2 0003002 Group Point Total: 5 06/06/2008 6:51:14 pm
~~ #& - I - - PWR SRO Examination Outline Printed. 08'06,'2008 Facility:
Saleni Generating Station w 10 ES - 401 SyslEvol # /Name K1 Ei? K3 K4 lis K6 A1 A2 A3 A4 G KATopic Imp. 0 1 1 Pressurizer Level Control 029 Containment Purge
- X A2.05 - Loss of PZR heaters 3.7 X 2.3.14 - Knowledge of 3.8 radiation or contammation hazards that may arise during normal, abnormal, or emergency conditions or activities.
recirculation prior to release 068 Liquid Radwasre I1 XI I A2.02 - Lack of tank 2.8* Points I 1 1 d WACategory Totals: 0 0 0 0 0 0 0 2 0 0 08/06/2000 6:51:20 pm 1 Group Point Total: 3 1 PM7R SHO Examination Outline Facility: Salem Generating Station Generic c ,ateeo~ K9 KA Tonic Conduct of Operations 2.1.34 Knov. ledge of primag and seLoiidar) plan1 Knowledge of conservative decision making chemistrj Iimirs 2,1.39 practices Printed: OSf06/2006 Form ES-401-3 ?U%h 0 '0 4- Ima. Points 3.5 1 4.3 I Equipment Control 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations.
such as risk assessments, work prioritization.
etc. 3.9 1 Radiation Control 2.3.13 L 2.3.4 ~~ ~- Knowledge of radiation exposure limits under normal or emergency conditions.
Knowledge of radiological safe8 procedures pertaining to licensed operator duties. such as response to radiation monitor alarms, containment entc requirements, fuel handlmg responsibilities, access to locked high-radiation areas. aligning fdters. etc. Emergency ProceduredPlan 3.4.26 Knowledge of facilic protection requirements, including fire brigade and portable fire fighting i 3.6 1 -~ Category Total: 2.4.28 2 equipment usage. Knowledge of procedures relating to a security event (non-safeguards information).
25 4.1 Categoq Total: 2 d 1 TierIG rou p Randomly Reason for Rejection Selected K/A 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 RO Ill RO 112 022 AKI .02 WE01 2.1.75 Sampled on CERT Exam NA to WE01 (Rediagnosis)
RO 112 RO 211 RO 211 RO 211 protection. Salem does not have fail open control room access doors. Sampled on CERT Exam Too similar to RO Tier 1 Group 1 KIA for 006 AI .07 Too similar to RO Tier 1 Group I KIA FOR 008 AK1.01 on CERT Exam( constant 068 K3.16 007 K3.01 008 AI .01 010 K5.02 1 RO 211 1 076 K1 .I 5 I No physical connection or cause/effect relationship between service water and Fire RO 211 enthalpy throttling characteristics 025 K1.O1 Salem does not have Ice Condenser
~~ RO 211 RO 211 RO 211 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 WAS were replaced with randomly selected WAS by the Exam Generation software.
KIA's removed or changed from exam per NRC direction were manually replaced with WA's approved by the NRC. Manually replaced WA's are identified as such on this form, all others were randomly replaced.
ES-401, Page 27 of 33 059 2.4.27 062 2.2.23 Not specific to Main Feedwater (knowledge of fire in the plant procedure)
Oversampling of Generic 2.2.23 (Ability to track TSAS) (also in Tier 3) 073 AI .01 Sampled on CERT Exam . _. RO 212 SRO 112 SRO 211 SRO 211 SRO 212 RO 112 RO 212 Protection systems Sampled on CERT Exam Chemistry limits NA to Loss of SR Nls Over sampling of ECCS system (3 on entire exam) Security event NA to RPI system. Manually replaced with same system, AKI .03 to match question developed per NRC direction.
055 K3.01 032 2.1.34 103 2.3.5 Not SRO level 006 A2.1 1 014 2.4.28 001 AK2.01 , 059 AK3.02 , Manually replaced with same system, AKI .01, to allow a question to be written that is not RO 112 SRO 212 SR03 Level of difficulty 5 as originally submitted. Manually replaced with same system EA1.3 to allow a question to be written. Manually replaced with same system, A221 to allow for SRO question to be written. Manually replaced with 2.3.1 3 to allow SRO level question to be selected.
EO9 2.1 .I4 064 A2.10 2.3.1 5 ES-30 1 Ad minis t ra t ive Topics Out I i ne Form ES-301-1 Facility:
SALEM Examination Level:
RO SRO Administrative Topic (See Note) Conduct of Operations Conduct of Operations A Equipment Control I Radiation Control TY Pe Code* NS NA Date of Examination:
08/25/2008 Operating Test Number:
07-01 NRC Describe activity to be performed Calculate Shutdown Margin 2.1.25 Ability to interpret reference materials such as graphs, curves, tables, etc..
RO 3.9 Verify qualifications prior to assuming Licensed Operator Duties.
2.1.3 Knowledge of Shift or short term relief turnover practices.
RO 3.7 Perform Subcooling Margin Monitor System operations (determine if displayed Subcooling is correct) 2.2.44 RO 4.2 (IC-171) 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:
07-01 NRC Administrative Topic (See Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code* Describe activity to be performed Verify shift operators are qualified to perform specified duties (From list of operators assigned to shift, which of them can take vibration data.)
2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc. SRO 3.9 Review calculated head vent time in FRCI-3 2.1.20 Ability to interpret and execute procedure steps SRO 4.6 Initiate an OTSC to an Implementing Procedure 2.2.6 Knowledge of the process for making changes in procedures . SRO 3.6 Review a radioactive gaseous waste release form. 2.3.6 Ability to approve release permits. SRO 3.8 Classify Emergency I Non-Emergency Events, and complete the ICMF. 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 a. Respond to Main Turbine Runback with malfunctioning Auto Rod Control (IC 1, 145) S,NA 1 Facility:
SALEM Exam Level : RO X SRO-I SRO-U b. Respond to VCT level channel failure and perform a manual makeup to the VCT (IC-141) t Respond to PZR spray valve failure (IC-142) Date of Examination:
08/25/08 SD 2 S,L,D,A 3 Operating Test No.:
07-01 ILT NRC Exam d. Swap operating RHR loops with one loop aligned for ECCS injection in MODE 4 (IC-I 72) Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF) I I S,L,N 4 (Pro System I JPM Title g. Respond to loss of Source Range Nuclear Instrumentation during refueling
I Type Code*
I Safety Function S,N 7 SLDA 8 i. Locally manually isolate seal injection during LOPA R, D,P j. Locally start 23 AFP and feed SGs during CR evacuation R,D,E 4 (Pro 4 (sec) k. Commence a liquid waste release, and respond to high activity during the release R,MA 9 11 f. Failure of 2C 4KV Vital Bus to Transfer to the Alternate Source (IC144) 1 S,D,A I 6 @ 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 ll the control room. *Type Codes
~ (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (S)imulator (R)CA Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2 e9 158 154 >I I >.I 121 - I - I 2 1 (control room system) - >I 121 I ,I >2 I 22121 - < 3 I 5 3 7 5 2 (randomly selected) - >I I ~1/>.1 -
___I_ ES-301 Control Room S ystemdl n- Plan t System Out I ine Form ES-301-2 ,- ~ ~ System I JPM Title a. Respond to Main Turbine Runback with malfunctioning Auto Rod Control b. Respond to VCT level channel failure and perform a manual makeup to the VCT c. Respond to PZR spray valve failure 1 Facility:
SALEM Date of Examination:
08/25/08 T~~~ Code* Safety Functior S,NA 1 S,D 2 S,L,D,A 3 l Exam Level
- RO SRO-1 x SRO-U I d. Swap operating RHR loops with one loop aligned for ECCS injection in S,L,N Operating Test No.: 07-01 ILT NRC Exam 4 (Pro Perform a CFCU Operability and Service Water Flow Verification (UNIQUE) f. Failure of 2C 4KV Vital Bus to Transfer to the Alternate Source S,N, A 5 S,D,A 6 ~- I I I. Locally manually isolate seal injection during LOPA D,P,R 4 (Pro 11 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 1 R,M,A 9 release i @? 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 (C)ontrol room (D)irect from bank (Qmergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power
/ Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams 4-6 I 4-6 I 2 <9 118 154 - >I I >I 121 - I - I 11 (control room system) - >I / 11 I ,I >2 I L212-I - +c 3 I 5 3 7 5 2 (randomly selected) - >I I F11~1
_________~
~ Appendix D Scenario Outline Form ES-D-1 N,R CRSIROIPO I CRSIRO~O Facility: SALEM 1 & 2 Scenario No.: NRC ESG-1 Op-Test No.:
07-01 NRC Power reduction for Condensate Pump emergent maint. EDG oil leak (TS) PZR level channel failure, letdown isolation, letdown re establish (TS) Note: The RO will provide the PZR level channel failure initial response, the PO will restore letdown)
Examiners:
Operators:
C Initial Conditions:
Turnover:
preparation for removing a Condensate Pump from service.
100% Rated Thermal Power Unit at 100% power. 22 AFW pp is C/T.
Lower power to 85% at 20% per hour in I SG Atmospheric relief fails partially open I Event Type*
Event Description u Steam Generator Tube Leak (TS) CRSIROIPO M I ... Steam Generator Tube Rupture CRSIROIPO 1 I C I SEC activated equipment fails to start I (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 2 3 4 Facility: SALEM 1 & 2 Scenario No.: NRC ESG-2 Op-Test No.: 07-01 NRC I/ C CRS/RO/PO C M CRSlRO C D VIB deenergizes causing no Auto or Manual rod control just as Rx is entering POAH (TS) 1 of 2 operating MDAFW pps trip on Rx trip. RCS leak progressing to LBLOCA w Auto SI failure. Various SEC initiated components malfunction (RHR pp fail to start, no auto CS) 2 3 4 5 C Loss of Emergency Recirc Examiners: Operators:
Initial Conditions: Turnover: Raise power to 3-4%. 1X108 Amps for critical data. I I I Event Description I I Raise Rx power to 3-4% R 1 CRSlRO 1 1 ll 1 IR NI fails IOW (TS) I CRSiRO 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 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) ~~~~ ~ - ~~ ~ Facility: SALEM 1 & 2 Scenario No.: NRC ESG-3 Op-Test No.: 07-01 NRC Event No. ' Examiners: Operators:
I Malf. No. Event Type* Event Description Raise Rx power N,R CRS/RO/PO I CRSIROIPO
.- MT Steamline Inlet Pressure Transmitter fails high (TS) 5 SGFP oil leak, trip with no auto MT runback L/K CRSIROIPO I C Single 4KV Group bus fails to transfer 1131 Feedwater rupture on common SGFP discharge header, CRS/~o,PO 1 MSLl failure, AmT 4 /I I C 1 SG Code Safety fails open post trip Appendix D, Page 38 of 39