ML103090350

Draft - Outlines (Folder 2)

ML103090350
Person / Time
Site:	Nine Mile Point
Issue date:	08/10/2010
From:	Dean R Operations Branch I
To:	Todd Fish Constellation Energy Nuclear Group
Hansell S
Shared Package
ML101900588	List: IR 05000220/2010301 ML103050559 ML103090325 ML103090350 ML103090375 ML103500252 ML103500258 ML103500278 ML103500290 ML110110530
References
TAC U01797 50-220/10-301
Download: ML103090350 (38)

Text

ES-401 Written Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit 1 Date of Exam : November 2010 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4

• 1.

1 3 3 3 4 4 3 20 3 4 7 Emergency

&

2 1 1 1 1 2 1 7 2 1 3 Plant Evaluations Tier 4 4 4 5 6 4 27 5 5 10 Totals 1 2 2 2 2 2 2 3 3 3 3 2 26 2 3 5 2.

2 1 2 1 1 1 1 1 1 1 1 1 12 0 1 2 3 Plant Systems Tier 3 4 3 3 3 3 4 4 4 4 3 38 3 5 8 Totals

3. Generic Knowledge & Abilities 1 2 3 4 10 1 2 3 4 7 2 2 3 3 2 2 1 2 Note 1. Ensure that at least two topics from every applicable KIA 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 KIA 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 1 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. 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 that are not included on the outline should be added . Refer to section D.1.b of ES-401 , for guidance regarding elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution .

5. Absent a plant specific priority, only those KAs having an importance rating (IR) of 2.5 or higher shall be selected . Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7.* The generic (G) KlAs 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-40 1 for the applicable KIA's B. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply) . Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA Catalog , and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10CFR55.43

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Exam ination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function KIA Topic(s)

EA2.02 - Ability to determine and/or interpret the following 295024 High Drywell X as they apply to HIGH 4.0 76 Pressure / 5 DRYWELL PRESSURE:

Drywell temperature AA2.04 - Ability to determine and/or interpret the following 295004 Partial or Total as they apply to PARTIAL X 3.3 77 Loss of DC Pwr / 6 OR COMPLETE LOSS OF D.C. POWER: System lineups AA2.02 - Ability to determine and/or interpret the following 295001 Partial or Complete as they apply to PARTIAL Loss of Forced Core Flow X OR COMPLETE LOSS OF 3.2 78 Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION: Neutron monitoring 295038 High Off-site 2.4.18, Knowledge of the Release Rate / 9 X specific bases for EOPs.

4.0 79 2.2.38 - Equipment Control:

295026 Suppression Pool Knowledge of conditions and X 4.5 80 High Water Temp. /5 limitations in the facility license.

2.2.39 - Equipment Control:

295037 SCRAM Conditions Knowledge of less than or Present and Reactor Power X equal to one hour technical 4.5 81 Above APRM Downscale or specification action Unknown /1 statements for systems.

2.2.37 - Equipment Control:

Ability to determine 295005 Main Turbine X operability and / or 4.6 82 Generator Trip / 3 availability of safety related equipment.

EK1 .03 - Knowledge of the operational implications of the following concepts as 295030 Low Suppression X they apply to LOW 3.8 39 Pool Water Level / 5 SUPPRESSION POOL WATER LEVEL: Heat capacity

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function I K1 I K2 I K3 I A 1 I A2 I G KIA Topic(s)

EK1.01 - Knowledge ofthe operational implications of the following concepts as 295024 High Drywell Pressure 15 x they apply to HIGH 4.1 40 DRYWELL PRESSURE:

Drywell integrity: Plant Specific AK1.03 - Knowledge of the operational implications of the following concepts as 295005 Main Turbine Generator Trip I 3

.x "2""'10">1 they apply to MAIN 3.5 41 TURBINE GENERATOR TRIP: Pressure effects on reactor level EK2.04 - Knowledge of the interrelations between HIGH 295028 High Drywell Temperature I 5 x DRYWELL TEMPERATURE 3.6 42 and the following: Drywell ventilation AK2.06 - Knowledge of the interrelations between 295006 SCRAM I 1 4.2 43 SCRAM and the following:

Reactor ower EK2.01 - Knowledge of the 295025 High Reactor interrelations between HIGH Pressure 13 x REACTOR PRESSURE and 4.1 44 the followin : RPS AK3.02 - Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE 700000 Generator Voltage AND ELECTRIC GRID and Electric Grid x DISTURBANCES: Actions 3.6 45 Disturbances contained in abnormal operating procedure for voltage and grid disturbances.

AK3.02, Knowledge of the reasons for the following responses as they apply to 295004 Partial or Total Loss of DC Pwr I 6 x PARTIAL OR COMPLETE 2.9 46 LOSS OF D.C. POWER:

Ground isolation/fault determination.

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function KIA Topic(s)

AK3.03 - Knowledge of the reasons for the following 295016 Control Room responses as they apply to Abandonment /7 CONTROL ROOM ABANDONMENT: Disabling control room controls EA 1.10 - Ability to operate and/or monitor the following 295031 Reactor Low Water i as they apply to REACTOR 3.6 48 Level/2 LOW WATER LEVEL:

Control rod drive EA 1.10 - Ability to operate and/or monitor the following as they apply to SCRAM 295037 SCRAM Conditions CONDITION PRESENT Present and Reactor Power AND REACTOR POWER 3.7 49 Above APRM Downscale or ABOVE APRM Unknown 11 DOWNSCALE OR UNKNOWN: Alternate boron injection methods: Plant-S ecific AA1.02 - Ability to operate and/or monitor the following 295021 Loss of Shutdown as they apply to LOSS OF 3.5 50 Cooling 14 SHUTDOWN COOLING:

RHRlshutdown coolin AA2.04 - Ability to determine and/or interpret the following 295003 Partial or Complete as they apply to PARTIAL 3.5 51 Loss of AC 16 OR COMPLETE LOSS OF A.C. POWER: System lineu s AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL 295019 Partial or Total OR COMPLETE LOSS OF 3.5 52 Loss of Inst. Air / 8 INSTRUMENT AIR:

Instrument air system pressure EA2.03 - Ability to determine and/or interpret the following as they apply to 295026 Suppression Pool SUPPRESSION POOL 3.9 53 High Water Temp. /5 HIGH WATER TEMPERATURE: Reactor pressure

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function I K1 I K2 . K3 I A1 I A2 I G KIA Topic(s) 2.4.21 - Emergency Procedures / Plan:

Knowledge of the parameters and logic used to assess the status of safety 295023 Refueling functions, such as reactivity 4.0 54 Accidents I 8 control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

2.4.46 - Emergency Procedures / Plan: Ability to 295018 Partial or Total verify that the alarms are

• 4.2 55 Loss of CCW / 8 consistent with the plant conditions.

2.1.27 - Conduct of 295038 High Off-site Operations: Knowledge of 3.9 56 Release Rate / 9 system purpose and / or function.

AA1.09 - Ability to operate and / or monitor the following

• 600000 Plant Fire On-site / i as they apply to PLANT 2.5 57 8 FIRE ON SITE: Plant fire zone panel (including detector location AA2.06 - Ability to determine and/or interpret the following 295001 Partial or Complete as they apply to PARTIAL Loss of Forced Core Flow OR COMPLETE LOSS OF 3.2 58 Circulation /1 & 4 FORCED CORE FLOW CIRCULATION: Nuclear boiler instrumentation KIA CategoryTotals 3 3 3 Group Point Total: 20n

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#/Name Safety Function KIA Topic(s)

AA2.03 - Ability to determine and/or interpret the following 295020 Inadvertent Cont. as they apply to X 3.7 83 Isolation 1 5 & 7 INADVERTENT CONTAINMENT ISOLATION: Reactor power 295007 High Reactor 2.4.6, Knowledge of EOP X 4.7 84 Pressure 13 mitigation strategies.

AA2.03 - Ability to determine and/or interpret the following 295014 Inadvertent as they apply to X 4.3 85 Reactivity Addition 1 1 INADVERTENT REACTIVITY ADDITION:

Cause of reactivity addition AK1 .02 - Knowledge of the operational implications of the following concepts as 295017 High Off-site X they apply to HIGH OFF- 3.8 59 Release Rate 1 9 SITE RELEASE RATE:

Protection of the general public AK2 .01 - Knowledge of the interrelations between LOW 295009 Low Reactor Water X REACTOR WATER LEVEL 3.9 60 Level/2 and the following: Reactor water level indication EK3.01 - Knowledge of the reasons for the following responses as they apply to 295032 High Secondary HIGH SECONDARY Containment Area X 3 .5 61 CONTAINMENT AREA Temperature 1 5 TEMPERATURE:

Emergency/normal depressurization EA1.04 - Ability to operate and/or monitor the following as they apply to 295036 Secondary SECONDARY Containment High X 3.1 62 CONTAINMENT HIGH Sump/Area Water Level 15 SUMP/AREA WATER LEVEL: Radiation monitoril}R Plant-Specific

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE#lName Safety Function I K1 I §JmK.~3......l-1A_1-lI_A_2----1...I_G_L...-_ _ _Kl_A_T_O_Pi_C<_S>_ _

AA2.01 - Ability to determine and/or interpret the following 1295012 Hi9: Drywell as they apply to HIGH Temperature /5 DRYWELL 3.8 *63 TEMPERATURE: Drywell

. tern erature 2.4.1 - Emergency Procedures / Plan:

295029 High Suppression Knowledge of EOP entry 4.6 *64 Pool Water Level!5 conditions and immediate action ste s.

AA2.01 - Ability to determine and/or interpret the following 295002 Loss of Main as they apply to LOSS OF 2.9 65 Condenser Vac / 3 MAIN CONDENSER VACUUM: Condenser vacuum/absolute pressure KiA CategoryTotals Group PointTotal: 7/3

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

A2 .07 - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) based 259002 Reactor X on those predictions, use 2.5 86 Water Level Control procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of comparator bias signal A2.07 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those 211000 SLC X predictions, use 3.2 87 procedures to correct, control , or mitigate the consequences of those abnormal conditions or operations: Valve closures 2.2.12 - Equipment 205000 Shutdown X Control: Knowledge of 4.1 88 Cooling surveillance procedures.

2.1.32 - Conduct of Operations: Ability to 264000 EDGs X explain and apply all 4.0 89 system limits and precautions.

2.2.25 - Equipment Control: Knowledge of 207000 Isolation bases in technical (Emergency) X 4.2 90 specifications for limiting Condenser conditions for operations and safety limits.

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

I K1.02 - Knowledge of I

I I ,~

'.' the physical connections

'. and/or cause- effect 262001 AC relationships between Electrical X 3.3 1

A.C. ELECTRICAL Distribution '.

DISTRIBUTION and the Y"

,', " following: D.C. electrical

~

"i," " distribution K 1.02 - Knowledge of

"

I'" ':' the physical connections I "

,.. and/or cause- effect

" relationships between 1212000 RPS X REACTOR 3.7 2

~- .... f~~, .* . PROTECTION SYSTEM and the following:

Nuclear boiler

,. *.*;,F,t* instrumentation

.. , K2.02 - Knowledge of electrical power supplies 300000 Instrument ,'

Air X r~0'~:/ to the following: 3.0 3 f;~2~~:>';J Emergency air r:. .* compressor i"

K2.01 - Knowledge of I electrical power supplies 206000 HPCI X . 3.2 '4

".

' " I .. '.' to the following: System r.o::'.i. t*",> valves: BWR-2,3,4 t'i;::~"  :,f K3.03 - Knowledge of

.'

the effect that a loss or malfunction of the 1239002 SRVs " RELIEF/SAFETY X 4.3 5 VALVES will have on following: Ability to

"'y ."

, f-;}~:,~

rapidly depressurize the reactor

~~Y'; ;1 K3.08 - Knowledge of

.>

," I the effect that a loss or

..... malfunction of the 262002 UPS UNINTERRUPTABLE X 2.7 6 (ACID C) !J' POWER SUPPLY

, .. f'.:, '.; (A.C.lD.C.) will have on

',4i:~

following: Computer

~~

0J2..eration: Plant-Specific

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 System #lName KJA Topic(s)

K4.09 - Knowledge of REACTOR WATER LEVEL CONTROL SYSTEM design 259002 Reactor feature(s) and/or X 3.1 7 Water Level Control interlocks which provide for the following: Single element control (reactor water level provides the onl in ut K4.01 - Knowledge of CCWS design feature(s) 1400000 Component and or interlocks which X 3.4 8

'Cooling Water provide for the following:

Automatic start of standb urn K5.01 - Knowledge of

" '

the operational implications of the following concepts as 215005 APRM I they apply to AVERAGE X 2.8 9 LPRM POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM:

LPRM detector 0 eration K5.03 - Knowledge of the operational implications of the 207000 Isolation following concepts as (Emergency) X they apply to

• Condenser , ISOLATION (EMERGENCY)

CONDENSER: Heat transfer: BWR-2,3 K6.02 - Knowledge of

, '. the effect that a loss or malfunction of the following will have on the 205000 Shutdown X SHUTDOWN COOLING 2.7 11

• Cooling SYSTEM (RHR SHUTDOWN COOLING MODE): D.C. electrical

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

, ......

K6.01 - Knowledge of the effect that a loss or I

.r,~ malfunction of the 215004 Source X

• following will have on the. 3.2 12 Range Monitor

,}"i t>;: SOURCE RANGE MONITOR (SRM) c.: . *. SYSTEM:RPS

,. '.

A1.01 - Ability to predict

',' and/or monitor changes

' in parameters associated

'" ..

263000 DC with operating the D.C.

Electrical X E~'.. ELECTRICAL  ! 2.5 .13 f~"<

'.

I Distribution DISTRIBUTION controls i

k'* '. including: Battery l~(; I,

'<~,

charging/discharging rate

........ "!;". A1.06 - Ability to predict and/or monitor changes

~j/t lji1',;<~,

in parameters associated with operating the STANDBY GAS 261000 SGTS X 2.7 .14

!

,"

TREATMENT SYSTEM I:  ;','j>. controls including:

Drywell and suppression

~;,;:?(;l chamber differential

"',0;P' pressure: Mark-I p.: A2.06 - Ability to (a)

, predict the impacts of the I.;.l.*****.**

~;E. following on the LOW PRESSURE CORE

.'. SPRAY SYSTEM; and

!

, . (b) based on those 209001 LPCS X predictions, use 3.2 15

. .*....>..

procedures to correct, control, or mitigate the consequences of those i: '.' abnormal conditions or operations: Inadequate I I

• system flow

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 System #!Name KiA Topic(s)

,,: A2.05 - Ability to (a) i, predict the impacts of the following on the

.

:. ...., INTERMEDIATE

'.' RANGE MONITOR

.. ',

(IRM) SYSTEM; and (b)

I; based on those 2150031RM .X;"'**" predictions, use 3.3 16 procedures to correct, I', ~.;,;

control, or mitigate the

consequences of those I abnormal conditions or

' operations

Faulty or erratic operation of

~; . '.

l

>.;'~ detectors/system A3.04 - Ability to monitor r>1}' automatic operations of the AUTOMATIC

. ;'

218000 ADS  : X 11,;';: . . . DEPRESSURIZATION 3.7 17 SYSTEM including:

k . . ; Primary containment

. pressure li.

A3.02 - Ability to monitor automatic operations of the PRIMARY 223002 ',i I',,;;;.

CONTAINMENT PCIS/Nuclear I .. X lr;;;>~

ISOLATION 3.5 18 Steam Supply

. SYSTEM/NUCLEAR Shutoff i STEAM SUPPLY SHUT I

[. ... OFF including: Valve closures

'.'> A4.05 - Ability to I

211000 SLC i

'.'

,

X i*';:! manually operate and/or monitor in the control 4.1 19.

'<'.

.

• room: Flow indication:

I~H;;

. Plant-Specific A4.01 - Ability to

. .... manually operate and/or *

.,

264000 EDGs i

X . \ monrtor in the control

. room: Adjustment of 3.31 20

.;

I I I sr;. exciter voltage I

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 System #lName KJA Topic(s) limp. I Q# I

.'

2.4.8 - Emergency

,

Procedures I Plan:

' .. '

Knowledge of how 218000 ADS X abnormal operating 3.8 21 procedures are used in i , " conjunction with EOP's. i 2.4.4 - Emergency I' ,'.' Procedures / Plan: Ability to recognize abnormal indications for system 209001 LPCS 1

X operating parameters 4.5 22

• 1 which are entry-level

,

conditions for emergency and abnormal operating

,; procedures.

A2.06 - Ability to (a)

, . predict the impacts of the I' following on the i**.**,*.* PRIMARY

. '

CONTAINMENT I.

ISOLATION 223002 SYSTEM/NUCLEAR PCIS/Nuclear STEAM SUPPLY SHUT Steam Supply X OFF; and (b) based on 3.0 23 Shutoff Ii those predictions, use procedures to correct,

,:.

I "  ! control, or mitigate the i

i I

consequences of those abnormal conditions or operations: Containment ,

i\

I I*} '. instrumentation failures .

A3.02 - Ability to monitor 1*'*/** automatic operations of 300000 Instrument I*

Xi the INSTRUMENT AIR 2.9 24 Air SYSTEM including: Air

<', l~i~.:iit temperature

! .

i A4.01 - Ability to manually operate and/or 262002 UPS monitor in the control i

X 2.8 25 I(ACIDCl room: Transfer from

JJ alternative source to preferred source I

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name KIA Topic(s)

A 1.05 - Ability to predict

....*.. and/or monitor changes

.". in parameters associated f

i; . with operating the 2150031RM X \

INTERMEDIATE 3.9 26 i'it RANGE MONITOR

,

" (JRM) SYSTEM controls .

including: SCRAM and I I .... rod block trip setpoints J KIA Category Totals I 2[ 2 21 2 2, 2[ 3 *'*312 3 3:213 Group Point Total:

I 26/5

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KIA Topic(s)

A2.08 - Ability to (a) predict the impacts of the following on the FI RE PROTECTION SYSTEM; and (b) based 286000 Fire on those predictions, use X 3.3 91 Protection procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when r~uired 2.4.31 - Emergency Procedures / Plan:

201003 Control Rod Knowledge of and Drive X 4.1 92 annunciator alarms, Mechanism indications, or response procedures.

2.1.32 - Conduct of Operations: Ability to 234000 Fuel Handling Equipment X explain and apply all 4.0 93 system limits and precautions.

K1.05 - Knowledge of the physical connections and/or cause- effect 259001 Reactor relationships between X 3.2 27 Feedwater REACTOR FEEDWATER SYSTEM and the following :

Condensate system 219000 RHR/LPCI: K2.01 - Knowledge of Torus/Pool Cooling X electrical power supplies 2.5 28 Mode to the following: Valves K3 .01 - Knowledge of the effect that a loss or malfunction of the 271000 Off-gas X 3.5 29 OFFGAS SYSTEM will have on following:

Condenser vacuum

ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KJA Topic(s)

K4.03 - Knowledge of RADIATION "II MONITORING System

,

t design feature(s) and/or 272000 Radiation interlocks which provide X ,'" 3.B 30 Monitoring for the following: Fail safe tripping of process

,::,,' "

radiation monitoring logic

~

during conditions of

',~." ..,.:, instrument failure

'

"':1.

I, KS.01 - Knowledge of

[i.,;' ",.Sf the operational f~~'"~'*,, ri implications of the 288000 Plant following concepts as X 3.1 31 Ventilation they apply to PLANT VENTILATION SYSTEMS: Airborne

"" ""', contamination control

,i

,.' KB.01 - Knowledge of the effect that a loss or

["'Ye!;

~L malfunction of the 201002 RMCS X """

~i

!:' following will have on the 2.S 32 i ',;;' REACTOR MANUAL i}(.;

r CONTROL SYSTEM:

l,::ie~.""", Select matrix power f

"

A1.03 - Ability to predict

'"

I

,',. and/or monitor changes

• in parameters associated with operating the 204000 RWCU X , REACTOR WATER 2.8 33 CLEANUP SYSTEM

,;, controls including:

Reactor water

.' temperature i":;

i. A2.04 - Ability to predict

~;i and/or monitor changes in parameters associated 201003 Control Rod with operating the and Drive X" 3.S 34 CONTROL ROD AND Mechanism DRIVE MECHANISM controls including: Single i I  : control rod SCRAM

• ES-401 Form ES-401-1 Nine Mile Point Unit 1 Written Examination Outline Plant Systems - Tier 2 Group 2 System #/Name KJA Topic(s)

A3.05 - Ability to monitor automatic operations of the PRIMARY i223001 Primary CONTAINMENT 4.3  ! 35 CTMT and Aux.

SYSTEM AND AUXILIARIES including:

Dwell ressure A4.04 - Ability to manually operate and/or .

monitor in the control i201006 RWM 3.3  ! 36 room: Rod withdrawal error indication: P S ec Not-8WR6 2.2.44 - Equipment Control: Ability to interpret control room indications to verify the status and operation of a 214000 RPIS 4.2 37 system, and understand how operator actions and directives affect plant and system conditions.

K2.01 - Knowledge of 256000 Reactor electrical power supplies ' 2.7 38

!X Condensate to the following: System KJA Category Totals 1 2 1 Group Point Total: 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Nine Mile Point Unit 1 Date: November 2010 Category KA# Topic RO SRO-Only IR Q# IR Q#

Knowledge of primary and secondary 2.1.34 2.7 66 plant chemistry limits.

Ability to coordinate personnel activities 2.1.8 3.4 67 outside the control room.

1. Conduct of Operations Knowledge of refueling administrative 2.1 .40 3.9 94 requirements Knowledge of facility requirements for 2.1. 13 3.2 98 controlling vital/controlled access.

Subtotal 2 2 Knowledge of tagging and clearance 2.2.13 4.1 68 Iprocedures.

Knowledge of the process for managing 2.2.20 2.6 69 troubleshooting activities.

2. Equipment Ability to recognize system parameters Control 2.2.42 that are entry-level conditions for 4.6 95 Technical Specifications.

Ability to apply technical specifications 2.2.40 4.7 100 for a system.

Subtotal 2 2 Ability to use radiation monitoring systems, such as fixed radiation 2.3.5 monitors and alarms, portable survey 2.9 70 instruments, personnel monitoring equipment, etc.

Knowledge of radiation or contam ination hazards that may arise 2.3.14 3.4 71 during normal, abnormal, or emergency

3. Radiation conditions or activities.

Control Knowledge of radiation exposure limits 2.3.4 3.2 75 under normal or emergency conditions.

2.3.11 Ability to control radiation releases. 4.3 96 Subtotal 3 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401 -3 Knowledge of the emergency action 2.4.41 2.9 72 level thresholds and classifications.

Ability to prioritize and interpret the 2.4.45 significance of each annunciator or 4.1 73 alarm .

Knowledge of RO tasks performed outside the main control room during an 2.4.34 4.2 74 emergency and the resultant

4. Emergency operational effects.

Procedures I Plan Knowledge of facility protection 2.4.26 requirements, including fire brigade and 3.6 97 portable fire fighting equipment usage.

Knowledge of EOP terms and 2.4.17 4.3 99 definitions.

Subtotal 3 2 Tier 3 Point Total : 10 7

ES-401 Record of Rejected KIA's Form ES-401-4 Randomly Selected Tier / Group Reason for Rejection KA Question 76, Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE:

Containment radiation levels: Mark-III. Nine Mile Point Unit 1 has a Mark-I containment, not a Mark-III containment.

1/ 1 295024/ EA2.07 Randomly selected EA2.02 - Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell temperature.

Question 44, Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following : RCIC:

Plant-Specific. Nine Mile Point Unit 1 does not have RCIC.

1 11 295025/ EK2 .07 Randomly selected EK2.01 - Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: RPS.

Question 2, Knowledge of the physical connections and/or cause- effect relationships between REACTOR PROTECTION SYSTEM and the following : Relief/safety valves (low-low-set logic): Plant-Specific. Nine Mile Point Unit 1 does not have low-low set logic associated with 2/1 2120001 K1 .07 relief/safety valves .

Random ly selected K1 .02 - Knowledge of the physical connections and/or cause- effect relationships between REACTOR PROTECTION SYSTEM and the following :

Nuclear boiler instrumentation.

Question 15, Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control , or mitigate the consequences of those abnormal conditions or operations:

Loss of fire protection: BWR-1. Nine Mile Point Unit 1 is a BWR-2, not a BWR-1.

2/ 1 209001 1 A2 .11 Randomly selected A2 .06 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ; and (b) based on those predictions, use procedures to correct, control , or mitigate the consequences of those abnormal conditions or operations:

Inadequate system flow.

ES-401 Record of Rejected KIA's Form ES-401-4 Question 79, Conduct of Operations: Ability to locate and operate components, including local controls (High Off-site Release Rate). This KIA involves asking an SRO about the location and operation of local controls. Writing a 1/ 1 295038/2 .1.30 question on this topic and meeting SRO question requirements would be difficult.

Randomly selected 2.1.6 - Conduct of Operations: Ability to manage the control room crew during plant transients.

Question 14, Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including: Primary containment oxygen level : Mark-I&II. This KIA involves the relationship between SGTS Controls and 02 levels. There is no procedural reference available to write a question on 2/1 261000 / A 1.05 this relationship.

Randomly selected A 1.06 - Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including :

Drywell and suppression chamber differential pressure:

Mark-I.

Question 93, Conduct of Operations: Ability to use plant computers to evaluate system or component status (Fuel Handling Equipment). This KIA involves the relationship between Fuel Handling Equipment and the plant process 2/2 234000 / 2.1.19 computer. There is no direct relationsh ip at Nine Mile Point Unit 1.

Randomly selected 2.1.32 - Conduct of Operations: Abil ity to explain and apply all system limits and precautions.

Question 90, Equipment Control: Knowledge of conditions and limitations in the facility license (Instrument Air). There is no direct relationship between Instrument Air and the facility license. Additionally, this is one of four Instrument Air KlAs.

2/1 300000/2 .2.38 Randomly selected 207000 Isolation (Emergency)

Condenser, 2.2.25 - Equipment Control: Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

ES-401 Record of Rejected KIA's Form ES-401-4 Question 27, Knowledge of the physical connections and/or cause- effect relationships between ROD BLOCK MONITOR SYSTEM and the following : LPRM: BWR-3, 4,

5. Nine Mile Point Unit 1 does not have a Rod Block Monitor.

2/2 2150021 K1 .02 Randomly selected anothe'r Tier 2 System and KIA.

259001 Reactor Feedwater, K1 .05 - Knowledge of the physical connections and/or cause effect relationships between REACTOR FEEDWATER SYSTEM and the following: Condensate System .

Question 70, Ability to control radiation releases. This KIA is identical with the KIA for question 96. This topic is also covered in other KlAs in the exam . To prevent a potential double jeopardy question for an SRO candidate another Generic KIA will be randomly added .

3/3 G3/2 .3. 11 Randomly selected 2.3.5, Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Question 79, Conduct of Operations: Ability to manage the control room crew during plant transients. This is not an acceptable KIA for a Tier 1 or Tier 2 topic.

1 11 295038/2 .1.6 Randomly selected 2.4.18, Knowledge of the specific bases for EOPs.

ES-401 Record of Rejected KIA's Form ES-401-4 Question 46, Knowledge of the reasons for the fo llowing responses as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Reactor SCRAM: Plant-Specific.

There are no procedural references regarding a loss of DC and a reactor scram.

1/ 1 295004/ AK3.03 Randomly selected AK3.02 , Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Ground isolation/fault determination.

Question 36, Ability to monitor automatic operations of the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) including: Pushbutton indicating switches.

Based on limited function of RWM pushbutton indicating switches at Nine Mile Point Unit 1, this KIA has low 2/2 201006 / A4 .02 operational validity.

Randomly selected A4.04, Ability to monitor automatic operations of the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) including: Rod withdrawal error indication: P-Spec (Not-BWR6).

Question 84, Emergency Procedures / Plan: Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material (High Drywell Temperature) . This is the 4th KIA dealing with High Drywell Temperature (Questions 42, 63 and 76). Since Drywell Cooling, HCTL and CSIL have all 1 /2 295012/2.4.47 been tested, there is not a suitable SRO question to match the KIA.

Randomly selected from the untested Tier 1 Group 2 KlAs; 295007, High Reactor Pressure, 2.4.6, Knowledge of EOP mitigation strategies.

Question 99, Knowledge of fire protection procedures.

This is the third fire protection KIA on the SRO exam (also

1. 91 and #97) . Re-sampling for better balance of coverage.

3/4 G3 / 2.4.25 Randomly selected 2.4.17 - Knowledge of EOP terms and definitions.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point Unit 1 Date of Examination: 11/10 Examination Level: RO. SRO D Operating Test Number: 1 Administrative Topic Type Code'" Describe activity to be performed (see Note)

PERFORM RPV LEVEL INSTRUMENT CHECKS PER N1 ST-DO, DAILY CHECKS Take control room reactor water level instrument readings for various daily checks required by Technical Specifications, enter the instrument readings into the applicable sections of the Daily Checks and take appropriate actions based on those Conduct of Operations M,S checks.

2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

N1-ST-DO PERFORM OWED AND DWFD LEAK RATE CALCULATIONS USING INTEGRATOR READINGS Given the DWED and DWFD integrator readings determine the identified and unidentified leak rates lAW Att 6 of N1-0P 8.

Conduct of Operations M,R 2.1.1S (3.6) Ability to make accurate, clear, and concise logs, records, status boards, and reports.

N1-0P-S PREPARE A TAGOUT FOR RBCLC PUMP 13 Identify the isolations required to tagout RBCLC pump 13 for the shaft seal replacement. Record the required isolations using CNG-OP-1.01-1007 attachmentS.

Equipment Control N,R 2.2.13 (4.1) Knowledge of tagging and clearance procedures.

CNG-OP-1.01-1007, N1-0P-11, P&ID C-1S022-C, EWD C-19436-C

ACTIONS FOR EXTERNAL SECURITY THREATS Given plant conditions, respond to a security threat per EPIP EPP-10, Attachment 2, Security Contingency Event (CSa Checklist)

Emergency Plan M,S 2.4.28 (3.2) Knowledge of procedures relating to a security event (non-safeguards information).

EPIP-EPP-10 Attachment 2 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (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)

E5-301 Administrative Topics Outline Form E5-301-1 Facility: Nine Mile Point Unit 1 Date of Examination: 11/10 Examination Level: RO SRO

• Operating Test 1 Administrative Topic Type Code* Describe activity to be performed (see Note)

DETERMINE THERMAL LIMITS WITH INOPERABLE PRESSURE REGULATOR Given plant parameters including an inoperable reactor pressure regulator, determine the adjusted thermal limit values. Core Operating Limit Report graphs and a 3D Monicore printout are used to evaluate conditions against the Conduct of Operations D,R adjusted thermal limits.

2.1.19 (3.8) Ability to use plant computers to evaluate system or component status.

N 1-RESP-1, Core Operating Limits Report, Technical Specifications ASSESS REPORTABILITY REQUIREMENTS Given a series of plant events, determine the reporting requirements per 10 CFR 50.72.

Conduct of Operations M,R 2.1.18 (3.8) Ability to make accurate, clear, and concise logs, records, status boards, and reports.

10 CFR 50.72, NUREG 1022, CNG-NL-1.01-1004 EVALUATE A COMPLETED SURVEILLANCE TEST AND TAKE THE REQUIRED ACTIONS Given a completed Surveillance Test, N1-ST-M1A, Liquid Poison Pump #11 Operability Test, complete the "Acceptance Equipment Control D,R Criteria" and "SM Review" sections.

2.2.12 (4.1) Knowledge of surveillance procedures.

N1-ST-M1A, Technical Specifications

GENERATE AND APPROVE AN EMERGENCY EXPOSURE AUTHORIZATION Given a work activity, area dose rates and personnel dose history, determine the need for an emergency exposure authorization and select the appropriate person to perform the Radiation Control D,R task.

2.3.4 (3.7) Knowledge of radiation exposure limits under normal and emergency conditions.

EPIP-EPP-15 CLASSIFY EMERGENCY EVENT AND PERFORM INITIAL NOTIFICATIONS Given plant conditions, determine event classification and complete initial notifications.

Emergency Plan M,R 2.4.41 (4.6) Knowledge of the emergency action level thresholds and classifications.

EAL Matrix, EPIP-EPP-18, EPIP-EPP-20 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (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/In-Plant Systems Outline Form ES-301-2 Facility: Nine Mile Point Unit 1 Date of Examination: November 2010

. Exam Level: RO/SRO Operating Test No.: 1 Control Room Systems@ (8 for RO; 2 or 3 for SRO-U, including 1 ESF) II System 1 JPM Title S-1 Respond to a Loss of Service Water D,A,S 8 PLANT SERVICE SYSTEMS The candidate will start the standby Service water pump.

The pump then trips, requiring override actions lAW N1-S0P 18.1.

KIA 295018 AA.01 (3.3/3.4) 5-2 Bypass LPRM Input To APRM D,S 7 INSTRUMENTATION The candidate will bypassLPRM 20-25A input to its associated APRM lAW N1-0P-38C.

KIA 215005 A4.04 (3.2/3.2)

S-3 Synchronize Main Generator to Grid, Main Generator M,A,S 4 Locks Out HEAT REMOVAL FROM CORE The candidate will complete synchronizing the Main Generator to the grid lAW N1-0P-32 and a generator lockout will occur, requiring N1-S0P-31.1 actions.

KIA 245000 A4.02 (3.1/2.9)

S-4 Rapid RWCU System Restoration for Level Control 0, L, S 2 REACTOR WATER INVENTORY The candidate will perform rapid RWCU system restoration CONTROL for RPV level control and establish reject flow to the condenser to lower level lAW N1-0P-3.

KIA 204000 A4.06 (3.0/2:9) I S-5 Start the RB Emergency Ventilation System Loop D,EN,S 9 11 RADIOATIVITY RELEASE The candidate will manually start Reactor Building Emergency Ventilation System Loop 11 lAW N1-0P-10.

i KIA 288000 A4.01 (3.1/2.9) I

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S-6 MSIV Stroke Test and Limit Switch Test P,S 3 REACTOR PRESSURE The candidate will perform the MSIV Stroke Test and Limit CONTROL Switch Test lAW N1-ST-Q26 for MSIV 112.

KIA 239001 A4.01 (4.2/4.1)

NRC 2009 S-7 Perform Rod Block Withdrawal Test N,A, L,S 1 REACTIVITY CONTROL The candidate will select and withdraw a control rod and perform an over-travel check lAW N1-ST-R4. The rod will be uncoupled. The candidate will re-couple the control rod lAW N1-0P-5 and complete the test.

KIA 201003 A2.02 (3.7/3.8)

I S-8 Vent the Drywell Prior to Personnel Entry N,S 5 PRIMARY CONTAINMENT The candidate will lineup and vent the Drywell to lower SYSTEM AND pressure prior to personnel entry lAW N1-0P-9. AUXILIARIES KIA 223001 A4.03 (3.4/3.4)

In-Plant Systems@ (3 for RO; 3 or 2 for SRO-U)

P-1 Lineup Lake Water to Supply the Emergency M,A,E,R I 4 Condenser Makeup Tanks using the Electric Fire HEAT REMOVAL Pump FROM REACTOR CORE The candidate will attempt to lineup the Diesel Fire Pump to supply lake water to the Emergency Condenser Makeup Tanks lAW N1-S0P-21.2. The Diesel Fire Pump will fail, requiring use of the Electric Fire Pump.

KIA 207000 2.1.30 (4.4/4.0)

P-2 Transfer RPS Bus 11 from UPS 162A to UPS 162B D,R 6 ELECTRICAL The candidate will place UPS 1628 in service and place UPS 162A in standby lAW N1-0P-40.

i KIA 262002 2.1.20 (4.6/4.6)

P-3 Inject Boron Into the Reactor Using the Hydro Pump D,E,R 1 REACTIVITY The candidate will lineup and inject boron using the Hydro CONTROL Pump lAW N1-EOP-3.2.

KIA 295037 EA1.10 (3.7/3.9)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

@ 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 / SRO-I / SRO-U (A)lternate path 4-6 1 4-6 12-3 (C)ontrol room (D)irect from bank ~9/~8/~4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 ~1 (control room system)

(L)ow-Power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams ~ 3 1 ~ 3 1 ~ 2 (randomly selected)

(R)CA ~1/~1/~1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-01 Op-Test No.: 11/10 Examiners: Operators: _ _ _ _ _ _ _ _ __

Initial Conditions: Simulator IC-1S1

1. Reactor power is approximately 85%

2. APRIVI 14 is bypassed

3. CRD Pump 11 is out of service Turnover:

1. Return APRM 14 to service

2. Raise to 100% with recirculation flow Malt. No. Event Event Type*

1 2

(M)ajor NRC Scenario 1 November 2010

Facility: Nine Mile Point Unit 1 Scenario No.: NRC-01 Op-Test No.: 11/10

1. Total malfunctions (5-8) 7 Events 3-9

2. Malfunctions after EOP entry (1-2) 2 Events 8 and 9

3. Abnormal events (2-4) 4 Events 3-6

4. Major transients (1-2)

Event 7

".

5 EOPs entered/requiring substantive actions (1-2) 2 I Events 6-9 (EOP-2, EOP-4)

6. EOP contingencies requiring substantive actions (0-2) 1 Events 8 and 9 (EOP-8) J

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1.0 Given a LOCA in the Drywell, the crew will initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N1-EOP-4.

CT-2.0 Given a lowering torus water level, the crew will execute N1-EOP-8, RPV Slowdown, when it is determined Torus water level cannot be maintained above eight (8) feet, in accordance with N1-EOP-4.

NRC Scenario 1 November 2010

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-02 Op-Test No.: 11/10 Examiners: _ _ _ _ _ _ _ __ Operators: _ _ _ _ _ _ _ _ __

Initial Conditions: Simulator IC-152

1. Reactor power is approximately 100%

2. EDG 102 is ready for start Turnover:

1. Complete surveillance test N1-ST-M4A

2. lower power to 95% with recirculation flow Malf. No. Event Event Type*

C (BOP) 2  ! Override I C (SRO)

TS (SRO) ST-M4A, TS 3.6.3 lower power to 3 N/A NRC Scenario 2 November 2010

Facility: Nine Mile Point Unit 1 Scenario No.: NRC-02 Op-Test No.: 11/10

1. Total malfunctions (5-8) 7 Events 2, 4-9

2. Malfunctions after EOP entry (1-2)

Event 9

3. Abnormal events (2-4) 4 Events 4-7

4. Major transients (1-2)

Event 8

5. EOPs entered/requiring substantive actions (1-2)

Event 7 and 8 (EOP-2) 6 EOP contmgencles requmng su bstantlve actions 0-2) 1 Events 8 and 9 (EOP-3) i

7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS:

CT-1.0 Given lowering CRD system air pressure, the crew will insert a manual reactor scram before control rods begin drifting, in accordance with N1 ARP-F3 and/or N1-S0P-20.1.

CT-2.0 Given a failure of the reactor to scram with power above 6% and RPV water level above-41 inches, the crew will terminate and prevent all injection except boron and CRD, in accordance with N1-EOP-3.

CT-3.0 Given a failure of the reactor to scram with power above 6%, the crew will lower reactor power by inserting control rods or injecting boron, in accordance with N1-EOP-3.

NRC Scenario 2 November 2010

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-03 Op-Test No.: 11/10 Examiners: Operators: _ _ _ _ _ _ _ _ __

Initial Conditions: Simulator IC-153

1. Reactor power is approximately 100%

Turnover:

1. Transfer Powerboard 101 supply from R1014 to R1011 in accordance with N1-0P-30 section H.8.0. Previous shift has completed step H.8.1.

2. Feedwater 11 is out of service for maintenance.

Event Malf. No. Event No.

Transfer Powerboard 101 supply from R1014 to R1011 N (BOP)

N/A N (SRO)

OP-30 C (BOP) Powerboard 101 fault 2 ED06 C (SRO)

TS RBCLC Temperature Controller fails to minimum cooling 7 C (ALL)

EOP-2 EOP-8

• (N}ormal, (R)eactivity, {I)nstrument, {C)omponent, (M)ajor NRC Scenario 3 November 2010

Facility: Nine Mile Point Unit 1 Scenario No.: NRC-03 Op-Test No.: 11120/10

1. Total malfunctions (5-8) 6 Events 2-7

2. Malfunctions after EOP entry (1-2) 1 I Event 7 i

3. Abnormal events (2-4) 4 Events 2-5 I

4. Major transients (1-2)  ! 1 Event 6

5. EOPs entered/requiring substantive actions (1-2) 2 Events 6 and 7 (EOP-2, EOP-4)

6. EOP contingencies requiring substantive actions (0-2) 1 Event 7 (EOP-8)

7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS:

CT-1.0 Given an inadvertently open ERV at power, the crew will close the ERV or insert a manual scram prior to torus temperature exceeding 110°F, in accordance with N1-S0P-1.4.

CT-2.0 Given a LOCA in the Drywell, the crew will initiate Containment Sprays prior to exceeding the Pressure Suppression Pressure limit, in accordance with N1-EOP 4.

CT-3.0 Given a LOCA with degraded high pressure injection capability, the crew will depressurize the RPV and inject with Preferred and Alternate Injection Systems to restore and maintain RPV water level above -84 inches. in accordance with N1-EOP-2.

NRC Scenario 3 November 2010

Appendix 0 Scenario Outline Form ES-O-1 Facility: Nine Mile Point Unit 1 Scenario No.: NRC-04 Op-Test No.: 11/10 Examiners: Operators: _ _ _ _ _ _ _ _ __

Initial Conditions: Simulator IC-154

1. Reactor power is approximately 85%

2. Containment Spray Pump 122 is OOS for repair (TS 3.3.7.b, day 1 of 15 day LCO).

Turnover:

1. Shutdown Condensate Pump 13 for maintenance due to a motor oil leak

2. Perform a Rod Event Malf. No. Event No. Descn Condensate Pump 13 must be shutdown for maintenance due to N (BOP) a motor oil leak 1 N/A N (SRO)

TS (SRO)

R(RO) 2 N/A R (SRO)

C (RO) 3 EG02 C (SRO)

RWCU break in the Secondary Containment requiring scram 6 M (ALL)

EOP-2 EOP-S Failure of the RWCU Isolation Valves to automatically isolate, manual isolation will also fail 7 C (ALL)

Turbine Bypass Valves fail to open 8

EOP-2

• (N)ormal, (I)nstrument, (C)omponent. (M)ajor NRC Scenario 4 November 2010

Facility: Nine Mile Point Unit 1 Scenario No.: NRC-04 Op-Test No.: 11/10

1. Total malfunctions (5-8) 6 Events 3-8

2. Malfunctions after EOP entry (1-2) 2 Events 7 and 8

3. Abnormal events (2-4) 3 Events 3-5

4. Major transients (1-2) 1 Event 6 i 5. EOPs entered/requiring substantive actions (1-2) 2 Events 6 and 7 (EOP-2, EOP-5) i I 6. EOP contingencies requiring substantive actions (0-2) 1 Event 7 (EOP-8)

I

7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS:

CT-1 ,0 Given an un-isolable RWCU leak outside primary containment and one general area temperature above the maximum safe limit. the crew will insert a manual reactor scram, in accordance with N1-EOP-S.

CT-2.0 Given an un-isolable RWCU leak outside primary containment and two general area temperatures above the maximum safe limit, the crew will execute N1-EOP-8, RPV Slowdown, in accordance with N1-EOP-5, I

NRC Scenario 4 November 2010