ML060820633

SONGS - 10-2005 - Final Outline

ML060820633
Person / Time
Site:	San Onofre
Issue date:	10/28/2005
From:	Operations Branch IV
To:	Southern California Edison Co
References
50-361/05-301, 50-362/05-301
Download: ML060820633 (23)

Text

ES-401 PWR Exami nation Outline Form ES-40 1-2 Facility:

SONGS Date of Exa m: 10/24/2005 RO K/A Cat egory Points SRO-Only P o ints T i e r G r o u p K 1 K 2 K 3 K 4 K 5 K 6 A 1 A 2 A 3 A 4 G* Total A 2 G* T o t a l 1 2 2 2 6 3 3 1 8 3 3 6 2 1 2 1 2 3 0 9 2 2 4 1. Emergency

& Abnormal Plant Evolutions Tier Totals 3 4 3 8 6 3 27 5 5 10 1 2 3 4 3 2 1 3 1 2 4 3 2 8 2 3 5 2 1 0 1 2 2 1 0 2 1 0 0 1 0 1 2 3 2.

Plant Sy stem s Tier Totals 3 3 5 5 4 2 3 3 3 4 3 3 8 3 5 8 1 2 3 4 1 2 3 4 3. Generic Knowledge and Abilities Cat egories 3 3 2 2 10 2 1 2 2 7 Note: 1. Ensu re that a t least two topics from eve r y applicable K/A category are sampl ed within ea ch ti er of the RO an d SRO-only outli nes (i.e., except for one ca tegory in Tier 3 of the SRO-only outline, the "Tier T o tals" i n each K/A category shall not be less th an two).

2. The point tota l for each g r o up and tier in the prop osed outline mu st match that sp ecified in the table. The final point total for each gro up and tier m a y deviate by 1 from that spe c ified in th e table ba sed o n NRC revi si ons. The fina l RO ex am m u st total 75 p o ints an d the SRO-only exam must total 25 points. 3. Systems/evol utions within each gro up a r e identified o n t he asso cia t ed outline; systems o r evolution s that do not appl y at the facility should b e d e leted an d ju stified; operationally import ant, site-spe cific systems that a r e not incl ude d on the outli ne sh ould b e adde d. Refer to ES-401, Attachment 2

, for guidan ce rega rdin g elim ination of in approp riate K/A statements.

4. Select topics from as m any system s and evolutions a s possible; sa mple every system or evolution in the gro up bef ore sele cting a se con d topi c for any sy stem or evoluti on. 5. Absent a pla n t specifi c prio rity, only those KAs having an importa nce rating (I R) o f 2.5 or highe r shall b e sel e cted. Use the RO an d SRO ratings fo r the RO an d SRO-only po rtio ns, re spe c tively. 6. Select SRO t opics for Tie r s 1 and 2 fr o m the shad ed system s and K/A categori e s. 7.* The gen eri c (G) K/As in Tiers 1 a nd 2 shall be sele cted from Se ction 2 of the K/A Catalog, bu t the topics must b e relevant to the appli c abl e evolution or system.

8. On the followi ng pag es, ent er the K/A numbers, a brief descriptio n o f each topi c, the topics' importa nce ra tings (I R) for t he appli c abl e licen se level, and the point totals (#) fo r each system and catego ry. Enter the group an d tier totals for ea ch catego ry in the table ab ove: if fuel handling equipm ent is sampl ed in ot her than Cate gory A2 or G* on the SRO-Only exam, enter it on the left side of colum n A2 for Tier 2, Grou p 2. Use du plicate page s for RO and SRO-onl y exams. 9. For Tie r 3, se lect topics fro m Section 2 o f the K/A Catalog, and e n ter the K/A numbers, descri p tion s, IRs, and p o in t totals (#) on Form ES-4 0 1-3. Limit SRO sele ction s to K/As that are linke d to 10CFR55.4 3 NURE G-10 21 1 ES-401 SONGS PWR Written Exa m ination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-40 1-2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s)

Imp. Q# 007 / Reactor Tri p - Stabilization - Recovery

/ 1 X 2.4.6 Emergenc y P r oc edures/Plan: Kno w ledg e of s y mpt o m based EOP mitigation strategies 4.0 7 6 015 / 17 / R C P M a lfunctions / 4 X 2.4.11 Emergenc y P r oc edures/Plan: Kno w ledg e of abno r m al condition procedures 3.6 7 7 022 / Loss of Rx Coolant Makeup

/ 2 X AA2.01 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the Loss of Reactor Coo l ant Pump Makeup:

Whether chargin g line leak exists 3.8 7 8 040 / Steam Line Rupture - Exces s ive Heat Transf e r / 4 X 2.4.16 Emergenc y P r oc edures / Plan Kn ow led ge of E O P implementation hierarch y a nd coo r dination w i th oth e r support proced ur es 4.0 7 9 056 / Loss of Off

-site Pow e r / 6 X AA2.57 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the Loss of Offsite Po w e r: RCS hot-leg a nd cold-leg temperatu r es 4.1 8 0 057 / Loss of Vital AC Inst. Bus / 6 X AA2.19 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the Loss of Vital AC Instrument Bus: Th e plant automatic actions that w ill occur on the loss of a vit a l ac electrical instrum ent bus 4.3 8 1 007 / Reactor Tri p - Stabilization - Recovery

/ 1 X EK2.02 Kno w ledge of th e interrelations b e tween a reactor trip and the follow i ng: B r e a kers, rela y s and disconnects 2.6 3 9 008 / Pressurizer Vapor Space Ac cident / 3 X AK1.02 Kno w ledge of th e operational imp lications of the follow i ng concepts as they appl y to a Pre ssurizer Vapor S pace Accident: Change in leak rate w i th change in pres sure 3.1 4 0 009 / Small Brea k LOCA / 3 X EA1.17 Ability to ope rate and monitor th e follow i ng as the y appl y to a small break LOCA: PR T 3.4 4 1 015 / 17 / R C P M a lfunctions / 4 X AA1.20 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to the Rea c tor Coolant Pu mp Malfunctions (Loss of RC Flo w): RCP b earing tempe r atu r e indicators 2.7 4 2 025 / Loss of RH R S y stem / 4 X AA1.08 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to the Loss of Residual Heat Removal S y st em: RHR cooler inlet and outlet tempe r ature indicators 2.9 4 3 026 / Loss of Co mponent Cooling Water / 8 X AA1.05 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to the Loss of Component Cooling Water: T he CCWS surge tan k , including leve l control and level alarms, and radi ation alarm 3.1 4 4 027 / Pressurizer Pressure Cont ro l Sy stem Malfunc tion / 3 X AA2.05 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the P r e ssurizer Pressure Control Malfun ctions: PZR Heate r setp oints 3.2 4 5 029 / ATWS / 1 X EK3.11 Kno w ledge of th e reasons for th e follow i ng respo n s es as the appl y to t he ATWS: Initiating emergenc y borat ion 4.2 4 6 NURE G-10 21 2 ES-401 SONGS PWR Written Exa m ination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 Form ES-40 1-2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s)

Imp. Q# 038 / Steam Gen. Tube Ru pture / 3 X EA1.39 Ability to ope rate and monitor th e follow i ng as the y appl y to a SGTR: : D r aw ing S G into th e RCS, using the "Feed and Bleed" meth od 3.6 4 7 040 / Steam Line Rupture - Exces s ive Heat Transf e r / 4 X AA1.09 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to the St e a m Line Ruptu r e: Setpoints of main steam safet y and PORVs 3.4 4 8 054 / Loss of Main Feed water / 4 X AK1.01 Kno w ledge of th e operational imp lications of the follow i ng concepts as they appl y to Loss of Main Feed wat e r (MFW): M F W line break dep ressurizes the S/G (similar to a steam line brea k) 4.1 4 9 055 / Station Blackout / 6 X EA2.05 Ability to dete r mi ne or interp ret th e follow i ng as th e y appl y to a Station Blackout: When batte r y is appro a ching fully discharged 3.4 5 0 056 / Loss of Off

-site Pow e r / 6 X AA2.83 Ability to dete r mi ne and interp ret t he follow i ng as t h e y appl y to the Loss of Offsite Po w e r: Instrument air pressure gaug e 2.7 5 1 057 / Loss of Vital AC Inst. Bus / 6 X 2.4.6 Emergenc y P r oc edures / Plan Kn ow led ge s y mpto m based EOP mitigation strategies.

3.1 5 2 062 / Loss of Nu clear Svc. Water / 4 X 2.4.4 Emergenc y P r oc edures / Plan Ability to recognize abnormal indications for s y stem o perating pa ramet e rs w h ich ar e entr y-l evel c onditions f o r emer genc y an d abnormal ope rati ng procedu res. 4.0 5 3 065 / Loss of Instrument Air / 8 X 2.4.46 Emergenc y P r oc edures / Plan Ability to verif y that alarms are consistent w i th plant conditions 4.3 5 4 E02 / Reactor T r i p - Stabilization -

Recovery / 1 X EK3.2 Kno w ledge of th e reasons for th e follow i ng respo n s es as the y ap pl y to the (Reactor Trip Re cover y) N o rmal, abnormal and e m ergenc y operat ing procedures associated w i th (R eactor T r ip Rec o ver y). 2.8 5 5 E06 / Loss of Main Feed w a te r / 4 X EK2.2 Kno w ledge of th e interrelations b e tween the (Loss of Feed w a t e r) and t he follow i ng: Facility's heat remov a l sy stems, including primar y coolant , emergenc y coolant, the deca y h eat r e moval sy stems, and relations bet w e en the prope r ope rat i on of these s y stems to the oper a t ion of the facility

. 3.5 5 6 K/A Categor y Poi n t Totals:

3/3 2 2 2 6 3/3 Grou p Point Tota l: 18/6 NURE G-10 21 3 ES-401 SONGS PWR Written Exa m ination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-40 1-2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s)

Imp. Q# 003 / Dro pped C ontrol Rod / 1 X 2.2.25 Equipment Contr o l: Know ledg e of bases in technical specificat ions for LCOs and safet y limits 3.7 8 2 024 / Emerge nc y Boration / 1 X 2.4.4 Emergenc y P r oc edures / Plan Ability to recognize abnormal indications for s y stem o perating pa ramet e rs w h ich ar e entr y l e vel conditions f o r emer genc y an d abnormal ope rati ng procedu res 4.3 8 3 A13 / Natural Circulation / 4 X AA2.1 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the Natu ral Circul ation Operations: Facility conditions and selection of appro p riate procedu re s during abnormal and e m ergenc y operat ions. 3.7 8 4 A16 / Excess RC S Leakage / 2 X AA2.2 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the (Exc ess RCS Leakage) Adher ence to approp riate proc edures and o per ation w i thin the limitations in the facility

's license and amendme n t s. 3.7 8 5 024 / Emerge nc y Boration / 1 X AA1.25 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to the Em ergenc y Bo ration: Boration valve indicators 3.4 5 7 028 / Pressurizer Level Malfunctio n / 2 X AA2.06 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the P r e ssurizer Level Control Malfunctions:

Letdo w n flo w indi cator 2.7 5 8 051 / Loss of Co ndenser Vacuum

/ 4 X AK3.01 Kno w ledge of th e reasons for th e follow i ng respo n s es as the y ap pl y to the Loss of Condens er Vacuum: Loss of steam dump capability on loss of vacuum 2.8 5 9 037 / Steam Gen e rator Tube L eak / 2 X AA2.12 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the St ea m Gene rator Tub e Leak: Flo w ra te of leak 3.3 6 0 061 / ARM S y ste m Alarms / 7 X AA2.03 Ability to deter mi ne and inter p r e t the follow i ng as they appl y to the A r e a Radiation Moni toring (ARM) S y s t em Alarms: Setpoints for alert and hi gh alarms 3.0 6 1 074 / Inad. C o re Cooling / 4 X EK1.08 Kno w ledge of th e operational imp lications of the follow i ng concepts as they appl y to the Ina dequate Co re Co oling : Definition of subcooled liquid 2.8 6 2 A11 / RCS Overcooling - PTS / 4 X AA1.3 Ability to ope rate and / or mo nitor the follow i ng as t h e y appl y to the (RC S Overcooling) D e sired operating results during abno rmal and emerg enc y s i tuations.

3.0 6 3 A13 / Natural Circ. / 4 X AK2.1 Kno w ledge of th e interrelations b e tween the (Natu r al Circulation Oper ations) and the f o llow i ng: Comp o n ents, and functions of control and safet y s y stems, including instrumentation, signals, in terlocks, failure modes, and automatic and m anual features.

3.0 6 4 NURE G-10 21 4 ES-401 SONGS PWR Written Exa m ination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 Form ES-40 1-2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s)

Imp. Q# A16 / Excess RC S Leakage / 2 X AK2.2 Kno w ledge of th e interrelations b e tween the (Exc ess RCS Leakage) a nd the follo w i ng: Facility's heat re moval sy stems, including primar y coolant , emergenc y coolant, the deca y h eat r e moval sy stems, and relations bet w e en the prope r ope r at ion of these s y stems to the oper a t ion of the facility

. 3.0 6 5 K/A Categor y Poi n t Total: 0/2 1 2 1 2 3/2 Grou p Point Tota l: 9/4 NURE G-10 21 5 ES-401 SONGS PWR Written Exa m ination Outline Plant Systems - Tier 2 Group 1 Form ES-40 1-2 S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 008 Compon ent Cooling Water X A2.08 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the CCWS, and (b) based on those p r edictions, us e procedures to corr ect, control, or mitigat e the consequen ces of those malfunctions or operations: Effects of shutting (automatically or other w i se) the is olation valves of the letdown cooler 2.7 8 6 013 Engineered Safet y F eatur es Actuation X A2.01 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the ESFAS; and (b) based Ability on t hose predict ions, use procedures to correct, control, or mitigat e the co nsequences of th ose malfunctions or operations; LOCA 4.8 8 7 062 AC Electrical Distribution X 2.1.11 Conduct of Oper ations: Know ledg e of les than 1 ho ur technical specif ication action statements for s y stem s 3.8 8 8 064 Emergenc y Diesel Generato r X 2.1.14 Conduct of Oper ations: Know ledg e of s y stem statu s criteria which req u ire the notification of plant perso nnel. 3.3 8 9 103 Containment X 2.1.12 Conduct of O perations: Ability to appl y technical specificat ions for a s y stem 4.0 9 0 003 Reactor Coo l ant Pump X A4.08 Ability to manu ally ope rate and/or monitor in the co ntrol room: RCP Cooling Water Suppl y 3.2 1 003 Reactor Coo l ant Pump X K4.03 Kno w ledge of R C PS design feat ure(s) a nd/or interlock(s) w h ic h provide for th e follow i ng: Adequ ate lubrication of the RCP 2.8 2 004 Chemical an d Volume Control X K2.01 Kno w ledge of bu s pow e r supplies to the follo w i ng: Boric Acid Makeup Pumps 2.9 3 004 Chemical an d Volume Control X A3.13 Ability to monito r automatic operati on of the CVCS, including: RCS temperatu r e and pressure 3.4 4 005 Residual He at Removal X A1.01 Ability to predict and/or monito r changes in param e ters (to prevent exce eding design limits) associated w i t h operating the RH RS controls inclu d ing: Heatup/cooldo wn rate 3.5 5 005 Residual He at Removal X K5.09 Kno w ledge of th e operational imp lications of the follow i ng concept s as the y appl y t he RHRS: Dilutio n and boration con s iderations 3.2 6 006 Emergenc y Core Co oling X A1.16 Ability to predict and/or monito r changes in param e ters RCS temper atur e, including superheat, satur a tion, and subcooled 4.1 7 007 Pressurizer Relief/Quench Tank X A4.10 Ability to manu ally ope rate and/or monitor in the co ntrol room: Recognitio n of a leaking PORV/code safet y 3.6 8 NURE G-10 21 6 ES-401 SONGS PWR Written Exa m ination Outline Plant Systems - Tier 2 Group 1 Form ES-40 1-2 S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 008 Compon ent Cooling Water X A2.01 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the CCWS, and (b) based on those p r edictions, us e procedures to corr ect, control, or mitigat e the consequen ces of those malfunctions or operations: Loss of CCW pump 3.3 9 010 Pressurizer Pressure Cont rol X K5.01 Kno w ledge of th e operational imp lications of the follow i ng concept s as the appl y to the PZR PCS:

Determination of condition of fluid in PZR, using steam tables 3.5 1 0 010 Pressurizer Pressure Cont rol X 2.2.22 Equipment Contr o l Know ledg e of limiting conditions for operations and s a fet y limits. 3.4 1 1 010 Pressurizer Pressure Cont rol X K2.01 Kno w ledge of bu s pow e r supplies to the follo w i ng: PZR heaters 3.0 1 2 012 Reactor P r ot ection X K2.01 Kno w ledge of bu s pow e r supplies to the follo w i ng: RPS channels, components, and interc onnections 3.3 1 3 013 Engineered Safet y F eatur es Actuation X K3.01 Kno w ledge of th e effect that a loss or malfunction of the ESF AS w ill have on the follow i ng: F uel 4.4 1 4 022 Containment Cooling X A4.01 Ability to manu ally ope rate and/or monitor in the co ntrol room: CCS f ans 3.6 1 5 026 Containment Spra y X A1.02 Ability to predict and/or monito r changes in param e ters (to prevent exce eding design limits) associated w i t h operating the CS S controls including: Containment temperatu r e 3.6 1 6 039 Main and Re heat Steam X 2.1.30 Conduct of O perations: Ability to locate and ope rat e components, including local controls.

3.9 1 7 059 Main Feed w a ter X K3.02 Kno w ledge of th e effect that a loss or malfunction of the MF W w ill have on the follow i ng: A F W s y stem 3.6 1 8 061 Aux illary/Em e rgenc y Feed w a t e r X K6.01 Kno w ledge of th e effect of a loss or malfunction of the follow i ng w ill have on the AFW co mponents: Cont rollers and positioners 2.5 1 9 062 AC Electrical Distribution X 2.4.6 Emergenc y P r oc edures / Plan Kn ow led ge s y mpto m based EOP mitigation strategies.

3.1 2 0 063 DC Electrical Distribution X A4.01 Ability to manu ally ope rate and/or monitor in the co ntrol room: Major b r ea kers and control po w e r fuses 2.8 2 1 064 Emergenc y Diesel Generato r X K1.03 Kno w ledge of th e ph y s ical connections and/or cause-effect relationships between the ED/G s y stem a n d the follow i ng s y stem s: Diesel fuel oil supply s y st em 3.6 2 2 NURE G-10 21 7 ES-401 SONGS PWR Written Exa m ination Outline Plant Systems - Tier 2 Group 1 Form ES-40 1-2 S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 073 Process Rad i ation Monitoring X K1.01 Kno w ledge of th e ph y s ical connections and/or cause-effect relationships between the PRM s y stem and the follow i ng s y stem s: Those s y stem s served b y PRM s 3.6 2 3 073 Process Rad i ation Monitoring X K4.01 Kno w ledge of P R M s y stem design feature (s) and/or inter l ocks w h ich pr ovide for the follow i ng: Release termination w hen radiation exceed s setpoint 4.0 2 4 076 Service Water X A3.02 Ability to monito r automatic operati on of the SWS, including: Emergenc y heat loads 3.7 2 5 078 Instrument A i r X K4.01 Kno w ledge of IA S design feature(s) and/or inte rlock(s) w h ich pr ovide for the follow i ng: M anual/automatic transfers of contr o l 2.7 2 6 078 Instrument A i r X K3.01 Kno w ledge of th e effect that a loss or malfunction of the IAS w ill have on the follow i ng: Containment air s y stem 3.1 2 7 103 Containment X K3.01 Kno w ledge of th e effect that a loss or malfunction of the containment s y stem w ill have on the follow i ng: Loss of containment integrit y und er shutd o wn conditions 3.3 2 8 K/A Categor y Poi n t Totals:

3/3 2 3 4 3 2 1 3 1/2 2 4 Grou p Point Tota l: 28/5 NURE G-10 21 8 ES-401 SONGS PWR Written Exa m ination Outline Plant Systems - Tier 2 Group 2 Form ES-40 1-2 NURE G-10 21 S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 041 Steam Dum p/Turbine B y pas s Control X 2.1.33 Conduct of O perations: Ability to recognize indications for system oper ating p a ramete rs which are entr y-level co nditions fo r technical specificat ions. 4.0 9 1 002 Reactor Coo l ant S y stem X 2.2.25 Equipment Contr o l Know ledg e of bases in technical specificat ions for limiti ng condit i ons for operations and safet y limits. 3.7 9 2 071 Waste Gas Disposal X A2.09 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on th e Waste Gas Disposal Sy stem ; and (b) based on those predictions, use procedures to co rrect, control, o r mitigate the consequences of thos e malfunctions or operations: Stuc k open relief 3.5 9 3 001 Cont rol Rod Drive X K6.13 Kno w ledge of th e effect of a loss or malfunction on the follow i ng CR DS components:

Location and operation of RPI S 3.6 2 9 002 Reactor Coo l ant S y stem X A3.03 Ability to monito r automatic operati on of the R C S, including: Pressu re, tempe r ature , and flo w s 4.4 3 8 011 Pressurizer Level Control X K5.09 Kno w ledge of th e operational imp lications of the follow i ng concept s as the y appl y t o the PZR L C S Reason for ma nu ally cont rolling PZR level 2.6 3 0 014 Rod Position Indication X A2.04 Ability to (a) predict the impacts of the follow i ng malfunctions or operations on the RPIS; and (b) based on those o n those pr edictions, use procedur es to correct, contro l, or mitigate the consequences of those malfunctions or operations:

Misaligned rod 3.4 3 1 015 Nuclear Instr u mentation X K4.06 Kno w ledge of NI S design feature(s) and/or interlock(s) provide for the f o llow i ng: Reactor t r ip by passes 3.9 3 2 016 Non-Nuclear Instrumentation X K1.02 Kno w ledge of th e ph y s ical connections and/or cause-effect relat i onships betw e e n the NNIS an d t he follow i ng s y stem s: PZR LCS 3.4 3 3 029 Containment Purge X K3.01 Kno w ledge of th e effect that a loss or malfunction of the Containment Purge S y stem w i ll have on the follow i ng: Con t ainment para m eter s 2.9 3 4 035 Steam Gene rator X A2.04 Ability to (a) predict the im pacts of the follow i ng mal-functions or oper ations on the S/GS; and (b) b a sed on those predictions, use procedu r es to correct, control, or mitigat e the consequen ces of those malfunctions or operations: Steam flow/fe ed mismatch 3.6 3 5 9 ES-401 SONGS PWR Written Exa m ination Outline Plant Systems - Tier 2 Group 2 Form ES-40 1-2 NURE G-10 21 S y stem #/Nam e G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A T opics Imp. Q# 041 Steam Dum p/Turbine B y pas s Control X K5.01 Kno w ledge of th e operational imp lications of the follow i ng concept s as the appl y to the SDS: Relationship of no-load T

-ave. to saturation pressu re relief setting on valves 2.9 3 6 045 Main Tu rbine Gene rator X K4.42 Kno w ledge of M T/G s y stem design feature (s) and/or inter-lock(s) w h ich provide for th e follow i ng: Oper ation of SD S (turbine b y pas s) in event of load loss or plant trip 2.8 3 7 K/A Categor y Poi n t Totals:

0/2 1 0 1 2 2 1 0 2/1 1 0 Grou p Point Tota l: 10/3 10 ES-401 Generic Knowledge and Abilities Outl ine (Tier3)

Form ES-40 1-3 Facilit y: SONGS Date of Exam:

10/24/2 0 0 5 RO SRO-Only Categ o r y K/A # T o p i c I R Q# I R Q# 2.1.5 Abilit y to loc a te and use proce dures a nd directiv es relat ed to shi ft staffing and activities.

3.4 9 4 2.1.33 Abilit y to reco g n ize i ndic a tio n s for sy stem oper ating para m eters w h ic h a r e entr y-l ev el cond itions for techn i cal sp ecifi c ations. 4.0 9 5 2.1.19 Abilit y to use p l ant computer t o obtai n an d eval uate p a ra metric informat i on o n s y stem or compo nent ST AT US 3.0 6 6 2.1.16 Abilit y to op era t e plant p hon e, pagi ng s y stem , and t w o-w a y ra dio. 2.9 6 7 2.1.22 Abilit y to deter mine Mo de of Operatio

n. 2.8 68 1. Con duct of Operatio ns S u b t o t a l 3 2 2.2.29 Kno w l e d ge of SRO fuel han dl ing res pons ib ili ties. 3.8 9 6 2.2.13 Kno w l e d ge of tagg ing and cl e a ranc e proce dures. 3.6 6 9 2.2.27 Kno w l e d ge of the refu e lin g pr ocess. 2.6 70 2.2.34 Kno w l e d ge of the proc ess for determi nin g intern al an d e x ternal effe cts on core reactiv i ty 2.8 7 1 2. Equi pment Co ntrol S u b t o t a l 3 1 2.3.4 Kno w l e d ge of r adi ation e x pos ure limits a nd contami natio n control, inc l ud i ng perm i ssib l e levels i n e x ces s of those auth o rize d. 3.1 9 7 2.3.1 Kno w l e d ge of 10 CFR: 20 an d relate d facilit y radi ation co ntrol req u irem ent s 3.0 9 8 2.3.2 Kno w l e d ge of facilit y ALA R A progr am. 2.5 72 2.3.10 Abilit y to perfor m proced ures to reduc e exc e ssiv e leve l s of radiatio n a nd gu ard a gai n s t perso nne l e x p o sure. 2.9 7 3 3. Radi atio n Co ntrol S u b t o t a l 2 2 2.4.41 Kno w l e d ge of the emer ge nc y action l e vel th re sh ol d s an d classifications.

4.1 9 9 2.4.29 Kno w l e d ge of the emer ge nc y pla n. 4.0 1 0 0 2.4.39 Kno w l e d ge of the RO' s respo n sibi liti e s in emerg enc y pl a n impl ementati on. 3.3 7 4 2.4.46 Abilit y to verif y that the alarms are consiste nt w i t h the pl ant c ond itions. 3.5 7 5 4. Emerge nc y Proced ures / Plan S u b t o t a l 2 2 T i er 3 Point T o tal 10 7 NURE G-10 21 11 ES-401 Record of Rejected K/As Form ES-40 1-4 Tier / Grou p Ran domly Selec t ed K/A Reason for Rejection 1 / 1 027 AA2.14 Facility doe s not have RCP Injection flow 1 / 1 029 EK3.05 Facility doe s not have Ce n t rifugal Ch arg i ng Pump s 1 / 1 065 G2.2.2 5 No Te chni cal Specification s asso ciate d with Instrume nt Air 2 / 1 004 K2.07 No Heat Tra c e asso ciated with CVCS at this facility 2 / 2 055 A3.03 CARS exha u s t doe s not a u tomatically d i vert at this facility 1 / 1 024 2.4.30 KA did not fit topic for ge ne ric. Wo uld be no o ff-s i te notific a tions di rec t ly related to the APE. Only w a y to o it would be to classif y an event related to APE, and 2 cla ssif i cat i on s alre ady ex is t. 1 / 1 060 AA2.04 Impossible to prepa re a p sychomet ricall y wri tten sou nd test item for sel e cte d topic. Coul d not de velop a test item above LO D 1 2 / 1 007 A4.01 Facility doe s not have a sp ray valve for the Que n ch Tank 2 / 2 071 A2.07 Coul d not de velop a psy c h o metri c ally so und written SRO test item for topic. No sup portin g proce dural informati on is avai lable for this event 2 / 2 028 K1.01 System aban done d in pla c e, removed from TS and EOIs 2 / 1 003 A4.07 No RCP se al bypass at faci lity. Resel e ct ed 003 A4.08 2 / 1 005 A1.06 No procedu re or evolution that perfo rm s this functio n at facility. Resele cted 0 05 A1.01 1 / 1 038 EA1.15 KA not suitable for written t e st item. Fac ility has a 15 minute JPM f o r this topi c, coul d not sho r ten to make a p s ychometri cally sound te st item. Resele cte d 038 EA1.39 1 / 1 007 G2.1.3 0 No rel a tion to 10CF R 55.4 3 (b) item s for SRO. Re sele cted 00 7 G2.4.6 1 / 1 015 G2.1.3 0 No rel a tion to 10CF R 55.4 3 (b) item s for SRO. Re sele cted 01 5 G2.4.11 1 /1 040 G2.4.3 1 No rel a tion to 10CF R 55.4 3 (b) item s for SRO. Re sele cted 04 0 G2.4.16 1 / 2 003 G2.1.1 4 Coul d not de velop an SRO test item above LO D 1. Same gene ri c KA used o n another event. Resel e cted 0 03 G2.2.25 2 / 1 103 G2.1.3 0 No rel a tion to 10CF R 55.4 3 (b) item s for SRO. Re sele cted 10 3 G2.1.12 2 / 1 062 G2.4.5 0 No rel a tion to 10CF R 55.4 3 (b) item s for SRO. Re sele cted 06 2 G2.1.11 2 / 2 056 G2.2.2 5 System has n o relation to the gen eri c topic sele cted. Re sele cted system 002 1 / 2 036 AK3.03 Not RO level kno w le dge. Repl aced wit h 051 AK3.01 1 / 2 060 AA2.06 Coul d not de velop a test item that woul d adeq uately meet the KA.

Submitted item reje cted. Re placed with 0 37 AA2.12 3 / 2 G2.2.23 Not RO level kno w le dge. Repl aced wit h 2.2.34 1 / 2 068 AA2.09 Coul d not de velop an ad e quate SRO le vel item for the KA. Submitted item reje cted. Repl aced wit h A13 AA2.1 NURE G-10 21 12 ES-301 Administrative Topics Outline Form ES-30 1-1 Facility:

SONGS Date of Exa m ination: 10/24/2005 Exa m ination Level RO Operating Test Number:

NRC Administrative Topic (se e Note) Type Cod e* De scribe a c ti vity to be perf o rme d Con d u c t of Operatio ns M, R 2.1.25 Ability to obta i n and interpret station refe ren c e material s such as graph s, nomog ra ph s, and table s whi c h contain performan ce data (2.8)

JPM: Determine ti me until Shutdown Co oling is requi re d (J0 53A) Con d u c t of Operatio ns M, R 2.1.23 Ability to perform spe c ific system and int egrate d plant pro c e d u r es d u ri ng all mode s of pla n t operation (3.9)

JPM: Cal c ulate a m a ke up to the RWST (J215 A) Equipme n t Control - Radi ation Co ntrol M, P, R 2.3.10 Ability to perform pr ocedures to re duce excessive levels of radi ation and g u a r d agai nst pe rson nel exposure (3.3) JPM: Determine stay time for work to b e perf o rme d and take a c tion fo r cha nge in ra diologi cal con d itions (J2 16A) Emerge ncy P l an C, D, S 2.4.39 Knowle dge of the RO re sp onsi b ilities in emergen cy plan imple m e n tation (3.3) JPM: Perform the Siren an d PA Coordinatio n (J15 7A) NOTE: All items (5 to tal) are requi red for SRO

s. RO appli c a n ts req u ire only 4 items unle ss they a r e retaki ng only the admini s trative topics, whe n 5 are re quire d. *Type Co de s & Criteria:

(C)ontrol ro o m (D)ire ct from ban k ( 3 for ROs

for 4 for SROs

& RO retak e s) (N)e w or (M)odified from b ank (> 1) (P)reviou s 2 exams ( 1; randomly sele cted) (S)imul a tor C l as s(R)oo m NURE G-10 21, Revision 9 Administrative Topics Outline Task Summary A.1.a Unit 2 has e x perienced a Loss of Fo rced Circula t ion/Loss of Offsite Power. Recovery actions hav e commenc ed and SO23-12-7, Loss of Forced Circulation/Lo ss of Offsite Power, is in progress. Cooldown and Depressurization, Atta chment 3 of SO23-12-11 , has been st arted. The candidate will use Atta ch ment 16 of SO23-12-11 , EOI Suppo rting Attachments, to determine the time until Shutdown Cooling is required. Th e critica l tasks include dete r mining amo unt of water required an d net feedwater available for the cooldown. T h is is a modified bank JP M. A.1.b The candida te is directe d to perform a blended makeup to the RWSTs at a total flo w of 40 gpm. The Plant Monitoring System is not available. The candidate will determine the required Boric Acid Flow Rate and PMW Flow Rate for the r equired RWST make up.

The critica l t a sks in clude determining Primary Water and Boric Acid flowr a tes and completing Prerequisite s for Attach ment 14. This is a modified bank JP M. A.2 N/A A.3 The candida te will deter mine stay time for work to be performed and take action for a change in ra diologica l co nditions. Th e critica l task is to select the correct REP for the work to be performed and determine stay time for the operato

r. This is a modified bank JPM used on the 2003 NRC Exa m. A.4 The candida te will perfor m the Siren and PA Coo r dination dur ing the Emergency Plan.

The critica l t a sks in clude proper form preparation as well as o perating the siren and public addre ss system consoles that were recently upgraded. This is a ba nk JPM. NURE G-10 21, Revision 9 ES-301 Administrative Topics Outline Form ES-30 1-1 Facility:

SONGS Date of Exa m ination: 10/24/2005 Exa m ination Level SRO(I) & (U) Operating Test Number:

NRC Administrative Topic (see Note)

Type Code* Describe act i vity to be performed Con d u c t of Operatio ns C, M, S 2.1.20 Ability to exe c ut e procedure steps (4.2)

JPM: Revie w Re actor Powe r Cal c ulatio n (J20 7A) Con d u c t of Operatio ns M, R 2.1.23 Ability to perform spe c ific system and int egrate d plant pro c e d u r es d u ri ng all mode s of pla n t operation (4.0)

JPM: Cal c ulate a m a ke up to the RWST (J215 A) Equipme n t Control M, R 2.2.24 Ability to analyze the affect of maintenan ce activities on L C O statu s (3.8) JPM: Perform a L C OAR for TSP Dod e cahydra t e (J1 64A) Radi ation Co ntrol M, P, R 2.3.10 Ability to perform pr ocedures to re duce excessive levels of radi ation and g u a r d agai nst pe rson nel exposure (3.3) JPM: Determine stay time for work to b e perf o rme d and take a c tion fo r cha nge in ra diologi cal con d itions (J2 16A) Emerge ncy P l an N, R 2.4.41 Knowle dge of emerg e n c y action level thresh old s and cl assifica tions (4.1) JPM: Cla ssify an e m erg e n c y event (Ne w) NOTE: All items (5 to tal) are requi red for SRO

s. RO appli c a n ts req u ire only 4 items unle ss they a r e retaki ng only the admini s trative topics, whe n 5 are re quire d. *Type Co de s & Criteria:

(C)ontrol ro o m (D)ire ct from ban k ( 3 for ROs

for 4 for SROs

& RO retak e s) (N)e w or (M)odified from b ank (> 1) (P)reviou s 2 exams ( 1; randomly sele cted) (S)imul a tor C l as s(R)oo m NURE G-10 21, Revision 9 Administrative Topics Outline Task Summary A.1.a Unit 2 has b een operatin g for several days at a st eady state power level greater than 20%. A reactor power calculation (M anual Method) has been performed due to COLSS Primary calculation bein g unavailable. As the Control Room Supervisor, review the Reactor Power Calculation (Manual Method) IAW SO23-3-3

.38. The critical task is to locate and correct calcu l ation errors and final po wer level. This is a modified bank JP M. A.1.b The candida te is directe d to perform a blended makeup to the RWSTs at a total flo w of 40 gpm. The Plant Monitoring System is not available. The candidate will determine the required Boric Acid Flow Rate and PMW Flow Rate for the r equired RWST make up.

The critica l t a sks in clude determining Primary Water and Boric Acid flowr a tes and completing Prerequisite s for Attach ment 14. This is a modified bank JP M. A.2 The candida te will compl e te a manual Limiting Condition for Operation ACTION Requiremen t (LCOAR) for Trisodium Phosphate Dodecahydrate. The critical task is to choose the correct Tech n ical Specification ACTION(s) and properly complete the paperwork for a manual LCOAR. This is a modified bank JP M. A.3 The candida te will deter mine stay time for work to be performed and take action for a change in ra diologica l co nditions. Th e critica l task is to select the correct REP for the work to be performed and determine stay time for the operato

r. This is a modified bank JPM used on the 2003 NRC Exa m. A.4 A Security Safeguards Contingency event is in p r ogress. Th e candidate will perform an EPIP classification. The critica l task is to pr operly classify the event. This is a new JPM.

NURE G-10 21, Revision 9 ES-301 Control Room/In-Plant Systems Outline Form ES-30 1-2 Facilit y: S O N G S Date of Exami natio n: 10/24/2 0 0 5 Exam Leve l (ci r cle on e): RO / SRO(I)

/ SRO (U) Operatin g T e st No.: NRC Contro l Room S y stems@ (8 for RO; 7 for SR O-I; 2 or 3 for SRO-U, inclu d i ng 1 ESF) Sy stem / JPM T i tle T y pe Code

• Safet y F uncti o n S-1 041 Steam Bypass Co ntrol System Verify corre c t SG isolated f o llowin g SGT R A, M, S 4-S S-2 005 Shutdo w n Cooling Sy stem Place Shutd o w n Cooling Sy stem in s e rv ice L, S 4-P S-3 0 1 3 E S F A S Perform Rec i rculation Ac tua t ion Signal actions A, N, S 2 S-4 008 Compo n ent Cooli ng Wate r Place the T r a i n A CCW/SWC Critical L oop in Stand by D, S 8 C-5 EPE 055 Station Blackou t Perform Co n t rol Building Ventilation Emergenc y Actio n s A, C, D, E 6 S-6 001 Control Rod Drive System Dampen ASI oscillation A, D, P, S 1 S-7 0 0 6 E C C S Rais e Safety Injec t ion Tank press u re D, S 3 S-8 022 Contain m ent Cooli n g System (RO only) Initiate Contai nment Co olin g System A, N, S 5 In-Plant Systems

@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

P-1 015 Nu clear Instrumen t a t ion Sy stem Align G005 to Essential Plant Param e ter s Monito ring Panel E, D, R 7 P-2 064 Emergen cy Die s el Ge nerato r Locally start the Emerg e n cy Diesel G e n e rato r D, E 6 P-3 068 Co ntr o l Room Ev acuation Align CVCS from outside the Con t rol Room A, D, E, R 1 NURE G-10 21, Revision 9 ES-301 Control Room/In-Plant Systems Outline Form ES-30 1-2 @ All RO and SR O-I control roo m (and in-p la nt) s y stems mu st be different a n d serve differe nt safet y functi ons; all 5 SRO-U s ystems must serve different saf e t y f uncti ons; i n-pl ant s y stem s and functi ons ma y ov erla p those tested i n the control ro o m.

• T y pe Codes Criteria for RO / SRO-I

/ SRO-U (A)lternate p a th 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9 / 8 / 4 (E)merge n c y o r abnorm a l in-p lant 1 / 1 / 1 (L)o w-Po w e r 1 / 1 / 1 (N)e w or (M)odified from bank including 1(A) 2 / 2 / 1 (P)revious 2 e x ams 3 / 3 / 2 (rand oml y sel e cted) (R)CA 1 / 1 / 1 (S)imulator NURE G-10 21, Revision 9 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NUREG-1021, Revision 9 JPM NRC Examination Summary Description S-1 The candidate will verify the correct SG is isolated following a Steam Generator Tube Rupture. The alternate path requires that the candidate recognize that the wrong SG was isolated and re-aligns for the ruptured SG. This is a modified JPM that requires the operator to use an alternate means of SG pressure control due to a Main Steam Isolation Signal. This is a Steam Bypass System - Secondary System Heat Removal from Reactor Core safety function.

S-2 The candidate will perform the actions required to place the Shutdown Cooling System in a single pump/single heat exchanger lineup. This is a low power JPM under the Residual Heat Removal System - Primary System Heat Removal from Reactor Core safety function.

S-3 The candidate will align for sump recirculation per Emergency Operating Instructions. The alternate path requires manual actions to contend with Containment Sump blockage.

This JPM was developed for new Floating Step and Attachment criteria established by EOI procedure revision.

This is a new JPM under the Emergency Core Cooling System - Reactor Inventory Control safety function. This is a PRA significant action.

S-4 The candidate must place the Component Cooling Water Train A CCW/SWC Critical Loop in standby. This is a Component Cooling Water Sy stem- Plant Service Systems safety function.

C-5 The candidate will perform Control Building Ventilation Emergency Actions. The alternate path is performed when the normal cooling system is not available during a Station Blackout. This is a JPM under the Plant Service Systems safety function. This is a PRA significant action.

S-6 The candidate will use the Control Rod Drive System to dampen an Axial Shape Index oscillation. The alternate path requires a Reactor trip when two rods fall into the core. This is a Control Rod Drive System - Reactivity Control safety function.

S-7 The candidate will perform actions to raise Safety Injection Tank pressure using S023-3-2.7.1, Safety Injection Tank Operations. This is a JPM under the Emergency Core Cooling System - Reactor Pressure Control safety function.

S-8 The candidate will be required to initiate a Containment Cooling Actuation Signal (CCAS). The alternate path requires that the candidate start the Train A Containment Emergency Cooling Fans and the Train A Containment Dome Air Fans when it is determined that the components have not started. This is a new JPM under the Containment Cooling System - Containment Integrity safety function.

P-1 The candidate will align G005 to the Essential Plant Parameters Monitoring Panel (EPPM). This is a Nuclear Instrumentation System - Instrumentation safety function. This is a PRA significant action. P-2 The candidate will perform Emergency Diesel Ge nerator duties of the Assistant Control Operator during AOI SO23-13-2. This is an Emergency Diesel Generators - Electrical Systems safety function.

P-3 The candidate will align Emergency boration and Saltwater Cooling flowpaths from outside the Control Room. The alternate path requires the candidate to align a Saltwater Cooling overboard valve when it is determined that the normal flowpath is not available. This is a Chemical and Volume Control System - Reactivity Control safety function. This is a PRA significant action.

Facility: San Onofre Scenario No.: 1 Op Test No.:

NRC Examiners:

Operators:

Initial Conditions: 100% power - RCS Boron is 888 ppm by Chemistry Sample Train A Component Cooling Water Pump (P-025) in service Train A Auxiliary Feedwater Pump (P-141) OOS Train A High Pressure Safety Injection (P-017) OOS Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Maintain steady-state power conditions.

Critical Tasks: Establish RCS temperature control (Turbine fails to trip).

Trip any RCP not satisfying RCP operating limits.

Stabilize RCS temperature/pressure following loss of heat removal from the faulted Steam Generator.

Event No.

Malf. No.

Event Type*

Event Description 1 + 5 min FW23 C (ACO, CRS) Partial loss of Condenser vacuum @ 3%.

2 + 10 min R (CO) N (ACO, CRS) Downpower for Condenser Backpressure.

3 + 20 min CV17A CV17B C (CO, CRS)

TS(CRS) Both BAMU Pumps trip.

4 + 25 min TS (CRS) Main Steam and Main Feedwater Isolation Valves declared inoperable.

5 + 30 min RD2103 C (CO, ACO, CRS) TS (CRS) Dropped CEA #21.

6 + 50 min MS03B M (ALL) ESDE on E089 inside Containment.

7 +50 min TU07 C (ACO) Turbine auto trip failure, manual trip required. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications

SCENARIO

SUMMARY

NRC #1 The crew will assume the watch at 100% power and maintain steady-state conditions per SO23-5-1.7, Power Operations.

When turnover is complete, a partial loss of vacuum will occur. The crew will respond per the Annunciator Response Procedures (ARP) and AOI SO23-13-10, Loss of Condenser Vacuum and lower power level until the Turbine Vacuum Limit is in the Area of Unrestricted Operation.

When the CO initiates RCS boration for the power reduction, the in-service and standby Boric Acid Makeup Pumps (BAMU) will trip, requiring gravity feed from the BAMU tanks for boration. The CRS will evaluate Technical Specifications.

Once the plant is stabilized, the Main Steam and Main Feedwater Isolation Valves will be

declared inoperable due to improper hydraulic fluid. The CRS will evaluate Technical Specifications.

This is followed by a dropped CEA and requires crew actions per the ARPs and AOI SO23-13-13, Misaligned or Immovable Control Element Assembly.

The EOP entry point is caused by an ESDE on E089 inside Containment. The crew performs SO23-12-1, Standard Post Trip Actions and diagnoses an ESDE. The crew will transition to SO23-12-5, Excess Steam Demand Event and perform necessary actions to stabilize RCS temperature.

During this event the Turbine fails to trip requiring manual actions on the part of the ACO.

The scenario is terminated when the crew stabilizes RCS temperature/pressure following pressure following loss of heat removal from the faulted Steam Generator.

Risk Significance:

Risk important components out of service: HPSI P-017, AFW P-141 Failure of risk important system prior to trip: Loss of BAMU Pumps Risk significant core damage sequence: ESDE with Turbine trip failure Risk significant operator actions:

Failure to trip Main Turbine Stabilize RCS temperature following ESDE Facility: San Onofre Scenario No.: 3 Op Test No.:

NRC Examiners:

Operators:

Initial Conditions: 30% power - RCS Boron is 1237 ppm by Chemistry Sample Train A Component Cooling Water Pump (P-025) in service Train A Auxiliary Feedwater Pump (P-141) OOS Train A High Pressure Safety Injection (P-017) OOS Condenser Air Ejector Low Range Radiation Monitor (RM-7818) OOS Turnover: Boration and downpower as directed by Operations Management.

Critical Tasks: Energize at least one vital electrical AC bus and associated 480 V 1E bus. Restore flow to the Component Cooling Water Non-Critical Loop (RCPs operating).

Event No.

Malf. No.

Event Type*

Event Description 1 + 15 min R (CO) N (ACO, CRS) Boration and downpower at 10%/hr.

2 + 20 min NI08B I (CO, CRS)

TS (CRS) NI Channel B Upper Detector failure.

3 +30 min PG22 PG23 C (ACO, CRS)

TS (CRS) Degraded grid voltage to Sustained Degraded Voltage Setpoint.

4 +45 min I (CO, CRS) Letdown Pressure instrument fails low (2PIC-0201 B-CR58-

MOI). 5 +55 min FW18A I(ACO, CRS) SG E089 Feed Flow Transmitter fails high.

6 + 65 min PG24 TU08 M (ALL) Loss of Offsite Power.

Turbine trip.

7 + 66 min ED03B M (ALL) 2A06 Bus Fault.

8 +67 min EG08A C (ACO) EDG 2G002 mechanical failure.

9 +70 min PG57 M (ALL) Loss of SDG&E Switchyard. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specifications

SCENARIO

SUMMARY

NRC #3 The crew will assume the watch with a boration requested by Reactor Engineering (to obtain calorimetric data at 25% power) per SO23-5-1.7, Power Operations.

After the crew has demonstrated control of the power change, a Nuclear Instrument Upper Detector failure will occur. The crew will respond per the Annunciator Response Procedures (ARP) and Abnormal Operating Instruction (AOI) SO23-13-18, Reactor Protection System Failure. The CRS will evaluate Technical Specifications.

This is followed by a frequency drop and grid voltage decrease to the Sustained Degraded Voltage Signal (SDVS) for 110 seconds that will require crew response and entry into AOI SO23-13-4, Operation during Major System Disturbances. The ACO will be required to adjust Main Generator MVARs and restart a CCW Pump. The CRS will evaluate Technical Specifications.

With the plant stable, the crew will respond to a Letdown Pressure Instrument failure. This will require action per the Annunciator Response Procedures and SO23-3-2.1, CVCS Charging and Letdown Operations.

Once Letdown is restored, a feed flow transmitter will fail high on SG E089. The crew will regain control of feedwater flow per Annunciator Response Procedures and AOI SO23-13-24, Feedwater Malfunctions.

When the crew has stabilized feedwater flow, a Loss of Offsite Power will occur along with a mechanical failure of 2G002 and 2A06 Bus fault. The crew will perform SO23-12-1, Standard Post Trip Actions and during the SPTAs the ACO will take action associated with the mechanical failure of EDG 2G002. The crew will then transition to SO23-12-8, Station Blackout and attempt to restore offsite power.

Event termination will occur once an offsite line is restored and aligned to 1E Bus 2A04 with plant conditions stable.

Risk Significance:

Risk important components out of service: HPSI P-017, AFW P-141 Failure of risk important system prior to trip: Loss of CCW Pump Risk significant core damage sequence: LOOP with loss of EDGs Risk significant operator actions: Restore Non-Critical Loop Recover Offsite Power in 60 minutes