ML12102A102

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Draft - Outlines (Folder 2)
ML12102A102
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 03/26/2012
From:
Constellation Energy Nuclear Group, EDF Development, Nine Mile Point
To: D'Antonio J
Operations Branch I
Jackson D
Shared Package
ML110030686 List:
References
TAC U01841
Download: ML12102A102 (34)
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Text

Administrative Topics Outline Facility: NMP2-NRC Date of Examination: March 2012 Examination Level: SRO Operating Test Number: NRC Administrative Topic Type Code'" Describe activity to be performed (see Note)

Determine Plant Impact for Inoperable Unit Cooler Given a failed closed service water inlet valve to 2HVC*UC107, determine the effect on the unit cooler and UPS2D operability per N2-0P-53E and Tech Specs.

N,R Conduct of Operations 2.1.32 (4.0) Ability to explain and apply system limits and precautions.

N2-0P-53E and Technical Specifications Determine Personnel Overtime Availability Given a list of personnel and their previous work hours, determine who is available for overtime and why others are not available, then complete a waiver for an individual to perform work beyond administrative work requirements based Conduct of Operations D,R on administrative requirements.

2.1.5 (3.9) Ability to use procedures related to shift staffing, such as minimum crew requirements, overtime limitations, etc.

CNG-SE-1.01-1002 Offsite Dose Calculation Manual (ODCM) Assessment for Inoperable Equipment Given conditions requiring removing Offgas radiation monitors OFG*RE13A and OFG*RE13B from service, the candidate D,R Equipment Control will determine the actions required by N2-0P-42, Offgas System and the ODCM.

2.2.38 (4.5) Knowledge of conditions and limitations in the facility license.

Radiological Requirements Related to Operator Inspection of High Radiation Areas Given radiological conditions related to an area where work is to be performed as shown on a survey map, and other applicable conditions such as the RWP, ensure the appropriate radiological aspects of the job are met prior to D,R sending the operator into the area.

Radiation Control 2.3.12 (3.7) Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc GAP-RPP-01, 02, 07 and 08; S-RAP-RPP-0703 Classify Emergency Event and Determine Protective Action Recommendations M,R The candidate wifl classify an emergency event and notify Emergency Plan offsite agencies with Protective Action Recommendations.

2.4.44 (4.4) Knowledge of emergency plan protective action recommendations NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when ailS are required.

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

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

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility: NMP2 - NRC Date of Examination: March 2012 Examination Level: RO Operating Test Number: NRC Administrative Topic Type Code* Describe activity to be performed (see Note)

Perform Jet Pump Flow Mismatch Checks lAW N2-0SP LOG-D001 Attachment 10 The candidate will calculate Jet Pump loop flow mismatch and identify a Jet Pump DP out-ot-spec.

Conduct of Operations M,R 2.1.18 (3.6) Ability to make accurate, clear, and concise logs, records, status boards and reports.

N2-0SP-LOG-D001, Attachment 4 Determine Heatup Rate During Startup Given turnover conditions during a plant startup, the candidate will interpret heatup data, calculate the heatup rate and take the appropriate actions.

Conduct of Operations N,R 2.1.43 (4.1) Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

N2-0SP-RCS-@001 Determine Adequacy of Clearance for SLC The candidate will review a proposed clearance for SLC and determine the adequacy of the clearance boundaries.

Equipment Control M,R 2.2.14 (3.9) Knowledge of the process for controlling equipment configuration or status.

CNG-OP-1.01-1007

Perform RO Actions for an Injured and Contaminated Person The candidate will perform EPIP-EPP-04 actions for a contaminated and injured person to be transported offsite.

Emergency Plan D,S 2.4.12 (4.0) Knowledge of general operating crew responsibilities during emergency operations.

EPIP-EPP-04 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 I Facili~: . Nine Mile Point Unit 2 NRC Date of Examination: March 2012 LExam Level: RO/SRO Operating Test No.:

Control Room Systems@ (8 for RO', 2 or 3 for SRO -U , including 1 ESF) i I I Type Code* Safety Function System 1 JPM Title I S-1 Align SBGTS Train "A" to reduce Drywell pressure 5 D,S CONTAIMENT The candidate will place Standby Gas Train "A" on the INTEGRITY Drywell in accordance with N2-0P-61A, Section H.1.0.

KIA 295024 EA1.20 3.5/3.6 I N2-0P-61A, H.1.0 r-'

S-2 Start RCIC in Reject to CST Mode (Tank to Tank) M,A,L,S 4 HEAT REMOVAL The candidate will start RCIC and place it in tank to tank FROM RXCORE mode for RPV pressure control lAW N2-EOP-HC. After RCIC is in service a high RCIC turbine exhaust pressure condition will occur and RCIC will fail to trip. The candidate will take manual action to trip the RCfC turbine.

KIA 217000, A4.04, 3.6/3.6 N2-EOP-HC S-3 Swap Instrument Air Compressors D,A,S 8 PLANT SERVICE The candidate will perform a swap of the Instrument Air SYSTEMS Compressors per N2-0P-19. After the compressors are swapped, the lead air compressor wi" trip requiring the operator to realign the system per N2-S0P-19.

KIA 295019 AA2.01 3.5/3.6 N2-0P-19 F.2.0; N2-S0P-19 I I S-4 Startup a Feedwater Pump following a Scram D,L,S 2 REACTOR WATER The candidate will restart Reactor Feed Pump A and raise INVENTORY RPV water level above 159 inches following a plant scram CONTROL lAW N2-S0P-101C.

KIA 259001 A4.023.9/3.7 I N2-S0P-101C S-5 Energizing 2ENS*SWG103 from Division II EDG & D,S 6 Energize NNS-SWG15 from SWG 103 ELECTRICAL The candidate will energize SWG 103 from the Div " EDG and SWG 15 from SWG 103 lAW N2-S0P-3 Sections 8.4 &

9.3 KIA 262001 A4.01 3.4/3.7 I N2-S0P-3 Sects. 8.4 & 9.3 I L

ES-301 _ _ _ _ _ _----'-Control Roomlln-Plant Sy__s_te__m_s'-O'-'-u_tli_n--.e_____F_o_r_m_E-'-S_-_3__0_1_-2_

S-6 Place the Standby Loop of SFC in Service. N,E,S 9 RO RADIOACTIVITY The candidate will respond to a loss of fuel pool cooling by RELEASE ONLY starting the standby train lAW N2-S0P-38.

KIA 233000 A2.04 2.6/2.7 N2-S0P-38 S-7 Transfer Recirculation Pump from Low Speed to High N,A,S 1 Speed REACTIVITY CONTROL The candidate will transfer RCS pump A from low to high speed operation lAW N2-0P-29. When the pump is shifted to high speed the FCV will slowly drift open requiring the candidate to lock up the FCV lAW N2-S0P-08 I

KIA 202002 A4.08, 3.3/3.3 N2-0P-29, N2-S0P-08 S-8 Venting the RPV to the Condenser D,A,L,S 3 REACTOR The candidate will line up to vent the Reactor to the Main PRESSURE Condenser through the MSIVs however the MSIVs will fail to CONTROL open and they must lineup the MSIV Drains lAW N2-EOP-6, Attachment 18.

KIA 239001 A4.01 4.2/4.0, 239001, A4.02, 3.2/3.2 N2-EOP-6 Attachment 18 In-Plant Systems@ (3 for RO; 3 or 2 for SRO-U) 1 P-1 Aligning Service Water to SFC Heat Exchanger 1A D,E,R 8 PLANT SERVICE SYSTEMS The candidate will align Service Water to Spent Fuel Pool Heat Exchanger 1A, lAW N2-S0P-38 Attachment 5.

KIA 233000 2.1.30 4.4/4.0 N2-S0P-38 Attachment. 5 Vent the Control Rod Overpiston Volume D,E,L,R 1 P-2 REACTIVITY The candidate will insert control rod 26-59 to notch 00 by CONTROL locally venting its overpiston area lAW N2-EOP-6 Attachment 14 KA: 295015 AA1.01 3.8/3.9 N2-EOP-6, Attachment 14 Place Battery Charger 2BYS-CHGR1A1 in service. 6 P-3 D ELECTRICAL The candidate will place battery charger 2BYS-CHGR1C1 into service lAW N2-0P-73A.

KIA 263000 A1.01 N2-0P-73A i I II

@ 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.

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

  • Type Codes I Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank S9/s8/s4 (E)mergency or abnormal in-plant  :?!1/2:1 I:?! 1 (EN)gineered safety feature - I - 1 2:1 (control room system)

(L)ow-Power I Shutdown 2:1/:?!1/2:1 (N)ew or (M)odified from bank including 1(A) 2:2/2:2/2:1 (P)revious 2 exams S 31 S 3/ S 2 (randomly selected)

II (R)CA  :?!1/2:1/:?!1 II (S)imulator

Appendix D Scenario Outline Form ES-D-1

~-

Facility: Nine Mile Point 2 Scenario No.: NRC-1 Op-Test No: March 2012 Examiners: Operators:

Initial Conditions: Simulator IC-153

1. Reactor Power -100%
2. RHR Band LPCI COOS for Division II Workweek TurnolJ'er:
1. Swap Recirc Pump HPU Subloops Event Malf. No. Event Event No. Type* Description 1 N/A N (BOP) Swap Recirc Pump HPU subloops N (SRO)

N2-0P-29, Sect. F.2.0

~>*;,*r< .; '.'"~,,,;:r,,,,C U{i,. i . ir '5; ., .....*. '/.;; " '!'\.',\,,:. .**.*'.i: . "

2 RR15B R(RO) RRP B seal lower and upper seal leak requires shutting down and RR16B R (SRO) isolation of the pump.

C (BOP)

TS (SRO) N2-S0P-29, N2-S0P-29.1, N2-S0P-101D, T.S. 3.4.1 and T.S.

3.4.5 i,:,,?; .:{~. ;:::: L;;:2~:;~ i.' i,i:'f ,i',","'} . ,.), .:

r~ . '., . "r 3 NM19A I (BOP) RBM "An Inop requires bypassing I (SRO)

TS (SRO) ARPs, N2-0P-92, Tech Spec 3.3.2.1

.*f~:;i~i;'; .~! ,f~;;:;;i~;l~~r;.~

.;~.~i

...'1;': '. .>. .>, 'f'::.' i ...' .i* .c' ." .... :.

4 TC15A C(RO) Loss of EHC pumps results in Turbine and Bypass Valves failing TC15B C (SRO) closed requires reactor scram.

TC06 N2-S0P-23, N2-S0P-1 01 C

...... . i.,;  ;;< ,'\. ',.' . ' ,;' . .1 .. '>S'.i}r:;. ......... .... , .'. *. .:i e"'* . **., ,..... .i.

5 AD03B C (BOP) One Non-ADS SRV fails open Overrides C (SRO)

N2-S0P-34 I' ;:';j~ ;,;l,,: ~ * *.*J~i~i:j~~~ij~? .:.~;~.;'~';~.(/ ':ii;  :.;f;>:':.;:~:,r'2;. . > .*. . , ..... ., ."i';:**,:" . .,. :',

6 PC12 M (All) Suppression Pool rupture results in loss of inventory in the suppression pool, requires blowdown.

N2-EOP-RC N2-EOP-PC I******.*,):i.\~~,;  :: l ;:~it:~i..  ;!,~;s~ }:';:,.;'z.,'.; '.'.;} '.' ......;..... .,/~.;:l:?:,,.t, . . *r*: . .,'" i: .i***.**...* '-'*~~..r.* : : .. ' '.

  • 'i.

7 AD08A C (RO) Failure of the ADS pushbutton or key lock switches to actuate 7 AD08C C (SRO) ADS valves N2-EOP-C2

  • (N)ormal, (R)eactlvlty,

.. (I)nstrument, (C)omponent, (M)aJor NRC Scenario 1 March 2012

Facility: Nine Mile Point 2 Scenario No: NRC-1 Op-Test No: March 2012 TARGET QUANTITATIVE ATTRIBUTES ACTUAL (PER SCENARIO; SEE SECTION D.5.d) ATTRIBUTES

1. Total malfunctions (5-8) 6 Events 2,3,4,5,6,7
2. Malfunctions after EOP entry (1-2) 1 Event 7 J
3. Abnormal events (2-4) 2 Events 2,4
4. Major transients (1-2) 1 I

Event 6

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

Events 4, 6 EOP-RPV, EOP-PC  !

--s.EOP contingencies requiring substantive actions (0-2) 1 Event 7 EOP-C2

7. Critical tasks (2-3) 2 i

CRITICAI_ TASK DESCRIPTIONS: CRITICAL TASK JUSTIFICATION:

CT-1.0 Given a failure of 2RCS*P1 B pump seals, the crew will take This task is identified as critical because without action to trip and isolate 2RCS*P1 B lAW N2-50P-29.1 operator action to trip and isolate the Recirc pump, Drywell pressure would continue to rise until the reactor automatically scrams.

CT- 2.0 Gliven a lowering suppression pool level, the crew will open 7 This task is identified as critical because without SRVs per N2-EOP-C2 prior to suppression pool level reaching 192 feet operator action to blowdown the RPV prior level reaching 192 feet, the primary containment pressure limit could be exceeded due to a loss ofpressure suppression capability concurrent with pressure control via SRVs.

I NRC Scenario 1 March 2012

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point 2 Scenario No: NRC-2 Op-Test No: March 2012 Examiners: Operators:

Initial Conditions: Simulator IC-154

1. Reactor Power *~92%
2. RCIC is out of service
3. A momentary loss of power signal caused lockup of LV-10A last shift.

Turnover:

1. Reset LV-1CA Lockup lAW N2-S0P-06, Attachment 1.
2. After the valve has been reset and back in automatic, restore power to 100%.

I Event No.

Malt. No. Event Type" Event Description I

1 N/A N (BOP) Reset a LV-10A Lockup and place the valve back in automatic N (SRO)

N2-S0P-6 2 I I N/A R (SRO) Raise reactor power to 100%

! R (RO)

N2-0P-101D I'; . :;ri';:J'i~ *10';.J:;;~./C.)":~;~, ';~r~; !0;~. \:r': .' "(, ,'. ,\;;; .:~,< I i . .... .  ;.. "

. " .. './: .. , ' .......

3 CU08 I (BOP) RWCU fails to automatically isolate on RWCU flow mismatch I (SRO) caused by cleanup RWCU non-regen heat exchanger tube leak.

TS (SRO)

ARPs, T.S. 3.3.6.1

. . ,X,::;,;:' *. :, ".. ;(.l':~;;~~:.,'!.;t: ,:f .*  ;'.:,. "~" .... I,* ... ) , . ,:" .

4 RD18 C (RO) CRD P1A suction filter clog causes pump trip. After the pump is C (SRO) restarted, a Control Rod Drive Accumulator will fail to recharge.

TS (SRO)

N2-S0P-30, T.S. 3.1.5 I 'i/'i> 1:::,;' ,) ;1;, ~: ~.;;~~:-? ., .*:....... . I'" ....  :.'"

..' T ..

5 CW26 C (BOP) Lowering service water intake bay level with failure of CW09 C (SRO) 2SWP*MOV77AlB to automatically open on the lowering level.

Crew will be required to manually open M0V77AlB to restore level.

N2-S0P-11

, . ,;,;,' ;';,;J~'.";'.<. '.!: '. .. ; ...... :. '.: ' < , ; ' <.,i;~  :< .:.:..... J. 'i 6 FW01A, B, C (All) Loss of aU Condensate pumps results in loss of Feed and manual and C scram.

N2-S0P-101C N2-EOP-RPV, N2-EOP-PC I'\.':'I~ :fii;3';JI*~;I;:\;~Tlj . t!;;:;~;;~jl~'~.).~; ... .

.
, .' :;.,,} i' .;;~\~5;t\t),:;!z'i~;;;.': ,,,.j'j~.;; . * "\';:' (.e"., .... ',.' /  :.

7 RR20 M (All) Small Primary System leak inside the drywell EOP-PC

. ";":; l~*~*'~§;;'~~;!.*;;#i;<1l?,; 'c,~;~,~~~i;':\ '; '.'., .:.1,*;*,'>';'>("/:"" " ..... '; .;. . " " '.' / ....

8 ED05B C (BOP) Bus fault when HPCS starts, CRD pump P1A electrical fault, SL03B C (RO) Liquid Poison pump fails to start. Loss of adequate high pressure RD12 C (SRO) injection sources requires RPV blow down to restore adequate core cooling.

N2-EOP-C2 I

" (N)ormal, (R)eactlVlty, (I)nstrument, (C)omponent, (M)ajor NRC Scenario 2 March 2012

l

! Facility: Nine Mile Point 2 Scenario No.: NRC-2 Op-Test No.: March 2012 TARGET QUANTITATIVE ATIRIBUTES ACTUAL (PER SCENARIO; SEE SECTION D.5.d) ATIRIBUTES

1. Total malfunctions (5-8) 6 Events 3,4,5,6.7.8
2. Malfunctions after EOP entry (1-2) 1 Events II
3. Abnormal events (2-4) 4 Events 3, 4, 5, 6,
4. Major transients (1-2) 1

~~

Event 7

5. EOPs entered/requiring sUbstantive actions (1-2) 2 Events 7, 8 EOP-RPV, EOP-PC
6. EOP contingencies requiring substantive actions (0-2) 1 Event 8 EOP-C2
7. Critical tasks (2-3) 2 CRITICAL TASK DESCRIPTIONS: CRITICAl TASK JUSTIFICATION:

CT-1.0 Given service water intake bay level less than 234 ft and a This task ;s identified as critical because without failure of 2SWP*MOV77A & 77B to automatically open, the crew will operator action the plant will lose its ultimate take action to manually open 2SWP*MOV77A & 77B per N2-50P-11 heat sink.

CT-2.0 Given RPV level at or below the TAF but above the MSCWl, the This task is identified as critical because without crew will open 7 ADS valves lAW N2-EOP-C2 operator action, RPV level will continue to tower untit the fuel is no tonger adequately cooled.

'--~

NRC Scenario 2 March 2012

Appendix D Scenario Outline Form ES-D-1 Facility: Nine Mile Point 2 Scenario No.: NRC-3 Op-Test No.: March 2012 Examiners: Operators: _ _ _ _ _ _ _ _ __

Initial Conditions: Simulator IC-155

1. Reactor Power -63%
2. Reactor shutdown is in progress Turno'lter:
1. Place the "cn heater drain pump in recirculation mode lAW N2-0P-8, Section G.1.
2. Lower power using recirculation flow to 58%.

3 N/A C ( SRO) Control Rod drift.

C (RO)

TS (SRO) ARPs, N2-S0P-8, T.S. 3.1.3 4 CS01 B C (BOP) Inadvertent initiation of HPCS due to high drywell pressure.

C (SRO)

TS (SRO) N2-0P-33, T.S. 3.S.1

. .;~.'~ *?,
~.~,c,,:;.. \.'.:;:;'., ..... .... .... '. .*.... . ..... > ." ..*. . . . . .....5 .**. ."

5 RP06A C (BOP) Loss of normal power to RPS Bus B, after initial actions RPS is C (SRO) recovered N2-S0P-97 5' .?:~;.,.*~::,>I;':;(~I:*:;;;ii;;yt* . ~:.~;*\f*:~ ~*;,*."; *. d\....;;~> . . .* ........*... " . ' . *.*.

6 FW31 C (All) Loss of instrument air requires a scram N2-S0P-19, N2-S0P-101C 7 RD17 M (All) Hydraulic ATWS RP02 RP14A, B N2-EOP-RPV, N2-EOP-CS, 8 I (RO) RRCS fails to automatically initiate requiring manual initiation and RP12A I (SRO) manual insertion of Control Rods.

RP12B N2-EOP-6, Att 14

'* {N)ormal, {R)eactivity, (I)nstrument, (C}omponent, (M)aJor NRC Scenario 3 March 2012

Facility: Nine Mile Point 2 Scenario No.: NRC-3 Op-Test No.: March 2012 TARGET QUANTITATIVE ATTRIBUTES ACTUAL (PER SCENARIO; SEE SECTION D.5.d) ATTRIBUTES

1. Total malfunctions (5-8) I 6 Events 3,4,5,6,7,8
2. Malfunctions after EOP entry (1-2) 1 Events 8
3. Abnormal events (2-4) 4 Events a, 4,~ 6
4. Major transients (1-2) 1 Event 7
5. EOPs entered/requiring substantive actions (1-2) 1 Events 7 EOP*RPV
6. EOP contingencies requiring substantive actions (0-2) 1 Event 7 EOP*C5
7. Critical tasks (2-3) 3 CRITICAL TASK DESCRIPTIONS: CRITICAL TASK JUSTIFICATION:

--cr:::i~.0 Given a failure of the reactor to SCRAM the crew will inhibit ADS This task is identified as critical because without per N2*EOP*C5 operator action to inhibit ADS prior to manually lowering RPV level, the reactor could experience a rapid and uncontrolled cooldown and subsequent injection of cold water which will dilute boron concentrations and add positive reactivity to the reactor if level were lowered below Level 1.

CT*2.0 Given a failure of the reactor to SCRAM, power above 4%, and This task is identified as critical because without RPV water level above 100 inches, the crew will terminate and prevent operator action to terminate and prevent all injection except SLS, CRD and RCIC per N2*EOP-C5 injection, the reactor could experience large irregular neutron flux oscillations induced by neutroniclthermal-hydraulic instabilities.

CT*3.0 Given a failure of the reactor to SCRAM, the crew will insert This task is identified as critical because without control rods per N2*EOP-6, Attachment 14 operator action to insert control rods, the reactor will remain susceptible to inadvertent power generation due to potential boron dilution or displacement NRC Scenario 3 March 2012

ES-401 BWR Examination Outline Form ES-401-1 NMP Unit 2 NRC Date of Exam: 03/19/2011 RO KIA Category Points Tier Group K K K K K K A A A A G Total Total 1 2 3 5 6 1 2 3 4 3 4 4 3 7 Emergency 2 1 2 3 Plant Evaluations 6 4 5 5 5 10 1 2 2 2 3 5 2.

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

3. Generic Knowledge & Abilities* 1 2 3 4 10 1 2 3 4 7 2 3 2 3 2 1 2 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-401 for the applicable KlA's

8. 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

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#lName Safety Function I ~ I K3 I A 1 I A2 I G

~---r.--~TO#l KIA Topic(s) ._ _. I Imp. ~

EA2.04 - Ability to determine and/or interpret the following 295028 High Drywell as they apply to HIGH 4.2 76 Temperature /5 DRYWELL TEMPERATURE: Drywell AA2.05 - Ability to determine and/or interpret the following 295005 Main Turbine as they apply to MAIN 3.9 77 Generator Trip / 3 TURBINE GENERATOR TRIP: Reactor AA2.09 - Ability to determine and/or interpret the following as they apply to 700000 Generator Voltage GENERATOR VOLTAGE and Electric Grid AND ELECTRIC GRID 4.3 78 Disturbances DISTURBANCES:

Operational status of emergency diesel 2.4.41 - Emergency Procedures I Plan:

295003 Partial or Complete Knowledge of the 4.6 79 Loss of AC / 6 emergency action level thresholds and classifications.

295037 S RAM Conditions 2.4.18 - Emergency Present and Reactor Power Procedures / Plan:

4.0 80 Above APRM Downscale Knowledge of the specific Unknown 11 bases for EOPs.

2.4.11 - Emergency 295016 Control Room Procedures / Plan:

4.2 81 Abandonment / 7 Knowledge of abnormal condition nl""/~Qrll EA2.04 - Ability to determine and/or interpret the following 295025 High Reactor as they apply to HIGH 3.9 82 Pressure 13 REACTOR PRESSURE:

S level

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function J K1 1K21 K3 : A1iAiJ}3'-1 ---- KIA Topic(s) -~~.

limp. [Q#l EK1.06 - Knowledge of the operational implications of the following concepts as 295037 SCRAM Conditions they apply to SCRAM Present and Reactor Power X CONDITION PRESENT 4.0 39 Above APRM Downscale or AND REACTOR POWER Unknown 11 ABOVE APRM DOWNSCALE OR UNKNOWN: Cooldown r------~--- __+----+--+_-+_-t-~+=_'_+-e::.:,ff:..:_=e~ct~on reactor power AK1.01 - Knowledge of the operational implications of Yo"<<'<! y', the following concepts as 295001 Partial or Complete they apply to PARTIAL OR Loss of Forced Core Flow X 3.5 40 COMPLETE LOSS OF Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION: Natural

~~--~~------t---t--+-+--t-~~~~-:-.--=---:

circulation AK1.03 - Knowledge of the operational implications of 295006 SCRAM 11 X the following concepts as they apply to SCRAM:

_+--.-t----+_+--t-~~~__:Reactivity conto--;ro_I-;------:;-c AK2.06 - Knowledge of the interrelations between 700000 Generator Voltage GENERATOR VOLTAGE and Electric Grid X 3.9 42 AND ELECTRIC GRID Disturbances DISTURBANCES and the 101l0wing: R~~ctor P<?Y!'_E:!,~'---i---i--+---i AK2.02 - Knowledge of the interrelations between 295018 Partial or Total PARTIAL OR COMPLETE X 3.4 43 Loss of CCW I 8 LOSS OF COMPONENT COOLING WATER and the following: Plant operation~-+_-+-~

EK2.02 - Knowledge of the interrelations between SUPPRESSION POOL 295026 Suppression Pool X HIGH WATER 3.6 44 High Water Temp. 15 TEMPERATURE and the following: Suppression pool

____~~_~~__~~~~~~s~p~ra~y_:~P~la~ntSLpe~c~ifi~lc~__~__~~

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE#/Name Safety Function lK1~~fK2TK:q A1] A2 GI = = K 1 A Topic(s) -----1 Imp. I I Q#

~-~-~--r--'-,--.--T-;7';;":-cT-..,.-;;AK3. 03 - Knowledge of the reasons for the following 295016 Control Room responses as they apply to Abandonment / 7 x CONTROL ROOM 3.5 45 ABANDONMENT: Disabling control room controls EK3. 08-- Knowledge-'-o-:f;-:-:th:-e~---I---t--1 reasons for the following responses as they apply to 295025 High Reactor Pressure /3 x HIGH REACTOR 3.5 46 PRESSURE:

Reactor/turbine pressure re ulating system opera;:;.t;:-:io~n'--!-._._-t---j AK3.03 - Knowledge of the reasons for the following responses as they apply to 295019 Partial or Complete Loss of Inst. Air /8 x PARTIAL OR COMPLETE 3.2 47 LOSS OF INSTRUMENT AIR: Service air isolations:

~r=PI~a~nt-Specifip~________T-*__t __~

EA 1.01 - Ability to operate and/or monitor the following 295028 High Drywell as they apply to HIGH Temperature 1 5 x DRYWELL 3.8 48 TEMPERATURE: Drywell s ra : Mark-I&II AA 1.03 - Ability to operate and/or monitor the following 295021 Loss of Shutdown as they apply to LOSS OF Cooling 14 x SHUTDOWN COOLING:

3.1 49 Component cooling water s stems: P/ant-S ecific

~~-:"7'"7 AA1. 02 - Ability to operate and/or monitor the following as they apply to PARTIAL 295004 Partial or Complete Loss of DC Pwr 16 x OR COMPLETE LOSS OF 3.8 50 D.C. POWER: Systems necessary to assure safe lant shutdown

-I--I---+--t--t-~~~E:::-A-;-;2.01 - Ability to determine and/or interpret the following 295031 Reactor Low Water as they apply to REACTOR 4.6 51 Level 12 LOW WATER LEVEL:

_ _ _ _._ _ _ _ _ _ Reactor

..L.-.----L---'~-1-.--'-_..:......_'_'__'___'___ ___water

_ _level

______ -'--~_L--J

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 KIA Topic(s}

Mi.01 ~ Ability to determine 3.61 295023 Refueling Accidents I 8 I

f - - - - - - - - ---+--+-t-+---t'rr~4 EA2.04 _Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS:

Area radiation le__v:--=e:..:::.ls~---:_t-_r--j and/or interpret the following 1

295038 High Off-site as they apply to HIGH OFF- 4.1 53 Release Rate I 9 SITE RELEASE RATE:

Source of off-site releaSr1

~---~~-l-+--+-~-R~~~,:;2;-':.4;:.:-.4-;;6;~-'Er=:m~er=g=ency Procedures I Plan: Ability to 54, 295030 Low Suppression verify that the alarms are 4.2 Pool Water Levell 5 consistent with the plant

~",+-:c::-o-:-n.ditions_.--'--'-~-+--r---i 2.4.31 - Emergency Procedures / Plan:

295005 Main Turbine Knowledge of annunciator 4.2 55 Generator Trip I 3 alarms, indications, or res onse roce~ures ~-----1---t---j 2.1.23 - Conduct of Operations: Ability to 295024 High Drywell perform specific system and 4.3 56 Pressure 15 integrated plant procedures during all modes of plant o eration .._._ --,:---7'":':---t----t'.-,

AK3.04 - Knowledge of the reasons for the following responses as they apply to 600000 Plant Fire On-site I X PLANT FIRE ON SITE: 2.8 57 8

Actions contained in the abnormal procedure for plant fire on si~___ --",,-,--+--1--"1

---~~'---------+--+-r--r--I-~~--t---;A;-;-K 1.01 - Knowledge of the operational implications of the following concepts as 295003 Partial or Complete X they apply to PARTIAL OR 2.7 58 Loss of AC /6 COMPLETE LOSS OF A.C.

POWER: Effect of battery

~----1---4-+--3+'--t--+-~~t""t

~~~~90ry Tota~_-1_ _ _

~discharge r_ate on capaci!y_

.....l-----l._..L.----"'",",,",-"'"'"""-_ _ _

Group Point Total:

~_ _ _ _ _ _ _ _ _ _ __

1 2017 I

ES-401 Form ES-401-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 AA2.02 - Ability to determine andlor interpret the following 295008 High Reactor as they apply to HIGH 3.4 83 Water Levell 2 REACTOR WATER LEVEL:

Steam flowlfeedflow mismatch 2.1.20 - Conduct of 295020 Inadvertent Cont. Operations: Ability to 4.6 84 Isolation I 5 & 7 interpret and execute 2.1.23 - Conduct of Operations: Ability to 295009 Low Reactor Water perform specific system and 4.4 85 Level 12 integrated plant procedures during all modes of plant on.

AK1.01 - Knowledge of the operational implications of 295022 Loss of CRD the following concepts as Pumps 11 x they apply to LOSS OF CRD 3.3 59 PUMPS: Reactor pressure vs. rod insertion AK2.01 - Knowledge of the interrelations between HIGH 295012 High Drywell Temperature 15 x DRYWELL TEMPERATURE 3.4 60 and the following: Drywell ventilation AK3.02, Knowledge of the reasons for the following responses as they apply to 295009 Low Reactor Water Level/2 x LOW REACTOR WATER 2.7 61 LEVEL: Reactor feed pump runout flow control: Plant-EA1.01 - Ability to operate and/or monitor the following as they apply to 295035 Secondary SECONDARY Containment High x CONTAINMENT HIGH 3.6 62 Differential Pressure I 5 DIFFERENTIAL PRESSURE: Secondary containment ventilation

ES-401 Form ES-401-1 Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2

~--- -----~----~

EA2.01 - Ability to determine and/or interpret the following 295033 High Secondary as they apply to HIGH Containment Area SECONDARY 3.8 63 Radiation Levels / 9 CONTAINMENT AREA RADIATION LEVELS: Area

---~

radiation levels 2.4.34 - Emergency Procedures / Plan:

Knowledge of RO tasks 295008 High Reactor performed outside the main 4.2 64 Water Levell 2 control room during an emergency and the resultant o erational effects.

AK1.03 - Knowledge of the operational implications of 295002 Loss of Main the following concepts as X 3.6 65 Condenser Vac I 3 they apply to LOSS OF MAIN CONDENSER VACUUM: LOSS_ofheat~;;l CategoryTotals 2 Group Point Total: 7~

--~------ ~-

ES-401 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1

_ _Kl_A_Top_ic<_sl_ _ ~lmp*1 Q# I A2.04 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based 209001 LPCS 3.0 86 on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or nn.:.rl:lT1ons: D.C. failures A2.05 - Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those 261000 SGTS 3.1 87 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or nne>rl:ltions: Fan tri 2.1.7, Conduct of Operations: Ability to evaluate plant performance and make 209002 HPCS operational judgments 4.7 88 based on operating characteristics, reactor behavior, and instrument 2.2.44 - Equipment Control: Ability to interpret control room indications to verify the 262001 AC status and operation of a Electrical 4.4 89 system, and understand Distribution how operator actions and directives effect plant and system conditions.

ES-401 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 2.4.9 - Emergency Procedures / Plan:

Knowledge of low power

/ shutdown implications 239002 SRVs 4.2 90 in accident (e.g., loss of coolant accident or loss of residual heat removal) m on es.

K1.01 - Knowledge of the physical connections 400000 Component and / or cause-effect 3.2 1 Cooling Water relationships between CCWS and the following:

Service water C'"C"'.....

K1.05 - Knowledge of the physical connections and/or cause- effect relationships between 2150031RM INTERMEDIATE 3.3 2 RANGE MONITOR

. (lRM) SYSTEM and the following: Display control

"'\1"*'0"': Plant-S c K2.03 - Knowledge of 203000 RHRlLPCI: electrical power supplies Injection Mode x to the following: Initiation 2.7 3 c

K2.01 - Knowledge of 262001 AC electrical power supplies Electrical x to the following: Off-site 3.3 4 Distribution sources of r K3.01, Ability to 211000 SLC x shutdown the reactor in 4.3 5 certain conditions K3.20 - Knowledge of the effect that a loss or malfunction of the PRIMARY 223002 CONTAINMENT PCIS/Nuclear Steam Supply x ISOLATION 3.3 6 SYSTEM/NUCLEAR Shutoff STEAM SUPPLY SHUT OFF will have on following: Standby gas treatment c:t\/c:tlr.:om

ES-401 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1

.,..---r-,--~-.~-,____r_ ~.."...., --,---,----,,..-:-:-~

K4.02 - Knowledge of EMERGENCY GENERATORS (DIESEUJET) design 264000 EDGs x feature(s) and/or 4.0 7 interlocks which provide for the following:

Emergency generator tri s emer enc /LOCA K4.06 - Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) design 217000 RCIC x feature(s) and/or 3.5 8 interlocks which provide for the following: Manual

---~~~~~~+-~~~-4~~.

initiation

.--------~~--_+~

K5.02 - Knowledge of the operational implications of the following concepts as 205000 Shutdown Cooling x they apply to 2.8 9 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING

~~~~~M~O~D~E~:V~a=l~eoper~~io_n+ __+-~

K5.05 - Knowledge of the operational

. implications of the following concepts as 209001 LPCS x they apply to LOW 2.5 10 PRESSURE CORE SPRAY SYSTEM:

S stem venting ~_-+-~_+-~

K6.13 - Knowledge of the effect that a loss or 300000 Instrument malfunction of the Air x following will have on the 2.8 11 INSTRUMENT AIR

~-~------.--~~~~~~~~~~~-~---

SYSTEM: Filters

ES-401 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1

[~~t:m_#l_Na_m_e_---LfK_1-L!K2_'_K3.. 1

. .~~ K61 A 11 A2 iAH~G~-I-~ATOPiC(S)-~~m~ i Imp. TO#]

K6.02 Knowledge of the effe ct that a loss or 263000 DC malfunction of the Electrical x followin g will have on the 2.5 12 Distribution D.C. ELECTRICAL DISTRI BUTION: Battery f--------~--_l_--+-__+_+__+__+_+__+~..::.,t____r__+~_+_',=-:=

ventilation A1.02 - Ability to predict' and/or monitor changes in parameters associated with 261000 SGTS operating the STANDBY 3.1 13 GASTREATMENT SYSTEM controls including: Primary containment eressure A3.01, Ability to monitor automatic operations of the 262002 UPS UNINTERRUPTABLE 2.8 14 (AC/DC) POWER SUPPLY (A.C.lD.C.) including:

Transfer from preferred to altern ate source.

  • -----*-**----i--t--f--i--t--i-+-+~'-+-*-+--+-~r-A'-::'-2~.11 _

Ability to (a) predict the impacts of the folio wing on the HIGHPRESSURE CORESPRAY SYSTEM (HPCS) ; and (b) based onthose predictions, use 209002 HPCS 3.3 15 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low suppression pool level:

-~~.~-~~.~.~~--~~~~~

BWR-5 &~--. -.. ~

ES-401 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1 KJA Topic(s) Gp*IQ#1

, --r--,----

A2.05 - Ability to (a)

'<'i;,1 predict the impacts of

'/'i,. I',

the following on the RELIEF/SAFETY VALVES; and (b) based i,'

~~;

I.: on those predictions, use 239002 SRVs " 3.2 16

! ..*. procedures to correct, S~~\ .'. control, or mitigate the i .* consequences of those

. abnormal conditions or

.... operations: Low reactor il .; .*..

_.\ -' pressure A3.02 - Ability to monitor automatic operations of 215004 Source Range Monitor I/'~k the SOURCE RANGE MONITOR (SRM) 3.4 17

i. SYSTEM including:

., Annunciator and alarm

,,: signals

..* '~>'.' ...

A3.01 - Ability to monitor automatic operations of the AUTOMATIC

~~

218000 ADS X 4.2 18 DEPRESSURIZATION

  • . <c' SYSTEM including: ADS
".~~ r*. ". valve operation

.J';. ':' A4.03 - Ability to manually operate and/or 215005 APRM /

f ,'< monitor in the control X 3.2 19 LPRM room
APRM back panel

.. ;.~ switches, meters and

~ I ' ,..." .. ' indicating lights A4.08 - Ability to

\;. manually operate and/or monitor in the control 212000 RPS X '.

3.4 20

, .' room: Individual system relay status: Plant-

'.} Specific

.": 2.4.4, Ability to I*

, recognize abnormal

"," indications for system 259002 Reactor . operating parameters Water Level Control X that are entry level 4.5 21

, ....*.. conditions for

.'. emergency and

\

....._ - - - abnorm~rocedures .

ES-401 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 1

[ system#/Name~K¥\?[K4fK5JK6IA11 A2 13MI G_T--'-___KlA_TO_P_iC(S)

.-.-.-~~_r_.-T~~_r-y~---.~*-------------~-~*

2.4.49 - Emergency Procedures / Plan:

Ability to perform without reference to procedures 262002 UPS those actions that 4.6 22 (AC/DC) require immediate operation of system components and

--~-----+--+-+--+--+--l-I--f..:;J.;.~--Ir--~~-=':

controls.____~----:-.,----t-- --t---i A2.04 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM)

SYSTEM; and (b) based 215004 Source on those predictions, use 3.5 23 Range Monitor procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Up scale and

___~____+-4-~~~-+-+~~~-+~~~_~d~ow __ns~ca_le~tr~ips

__ _____~__~~

A 1. 02 - Ability to predict and/or monitor changes in parameters associated with operating the 2150031RM INTERMEDIATE 3.7 24 RANGE MONITOR (IRM) SYSTEM controls including: Reactor power indication response to f - - - - - - - - - - - _ _-+---+--t---+-+---r~_!--~---t---li-'-"-:,-,+_ro.~osition changes A4.05 - Ability to manually operate and/or 239002 SRVs 4.3 25 monitor in the control

_-+--+-+_-+--+---t_I--t---t--l__t---t~ro.om: React~.i...P!essure 2.2.42 - Equipment Control: Ability to recognize system 211000 SLC 3.9 26 parameters that are entry-level conditions for Technical Specifi~atio_ns_.-,--..--.i..-...--;

KIA Category Totals Group Point Total: 26/5

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

A2.04 - Ability to (a) predict the impacts of the following on the ROD WORTH MINIMIZER SYSTEM (RWH)

(PLANT SPECIFIC) ;

and (b) based on those 201006 RWM 3.3 91 predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck rod:

Not 2.4.6 - Emergency 202001 Procedures / Plan:

4.7 92 Recirculation Knowledge of EOP miti ies.

2.4.30 - Emergency Procedures I Plan; Knowledge of events related to system operation / status that 290002 Reactor must be reported to 4.1 93 Vessel Internals internal organizations or external agencies, such as the state, the NRC, or the transmission system K1.02 - Knowledge of the physical connections and/or cause-effect 201003 Control Rod relationships between and Drive X 2.9 27 CONTROL ROD AND Mechanism DRIVE MECHANISM and the following:

Reactor water K2.03 - Knowledge of electrical power supplies 215002 RBM X 2.8 28 to the following: APRM channels: 5

ES-401 Form ES-401-1 Written Examination Outline Plant Systems - Tier 2 Group 2

[ System #fName KIA Topic(s) r--'

.,\: K3.01 - Knowledge of

/,~;" the effect that a loss or

~~.;;

230000 RHRlLPCI:

Torus/Pool Spray X

,r ' i~
if, 1 i.-;:,;,

.... : malfunction of the RHRlLPCI:

TORUS/SUPPRESSION 3.7 29 Mode ...*..... " POOL SPRAY MODE

,':< '.' will have on following:

' Suppression chamber pressure

~~

"'\

K4.10 - Knowledge of CONTROL ROD DRIVE HYDRAULIC SYSTEM V" design feature(s) and/or 201001 CRD X  :'". interlocks which provide 3.1 30 Hydraulic for the following: Control of rod movement (HCU

~

directional control

~t" valves)

.\;!

it~

KS. 0 1 - Knowledge of

': ;.;1 the operational implications of the 290002 Reactor X ....:.. following concepts as 3.5 31 Vessel Internals they apply to REACTOR

.. VESSEL INTERNALS:

-. '.;~: y. Thermal limits

""~l; K6.08 - Knowledge of

.,.\ ".

the effect that a loss or malfunction of the 219000 RHRILPCI: following will have on the Torus/Pool Coaling X

, . RHRlLPCI:

  • 2.7 32 Mode TORUS/SUPPRESSION

,:: POOL COOLING

'. MODE: ECCS room

> cooling

). A 1.06 - Ability to predict and/or monitor changes

    • ).'

, in parameters 233000 Fuel Pool associated with X 2.5 33 Cooling/Cleanup operating the FUEL POOL COOLING AND

., CLEAN-UP controls

,/

including: System flow

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

I:"

t~f A2.08 - Ability to (a)

,L predict the impacts of the following on the

,,' 1.< FIRE PROTECTION ll:.}.i:::ii SYSTEM; and (b) based 286000 Fire on those predictions, use fit"f:;;; 3.2 34 Protection procedures to correct, r n: control, or mitigate the consequences of those

.iY'~r.' ,;"'.; abnormal conditions or operations: Failure to

~*h* 1,'(l" actuate when required

?J~ I'~ii; A3.01 - Ability to monitor automatic operations of 216000 Nuclear
  • . ~~:\  :

the NUCLEAR BOILER Instrumentation

X including
Relationship 3.4 35 Boiler Inst.

';'. between meter/recorder

" ': readings and actual parameter values:

204000 RWCU I .

}'

X I<,~~'h

',{,i Plant-Specific A4.08 - Ability to manually operate and/or monitor in the control room: Reactor water level 3.4 36 2.1.7 - Conduct of

"~:. Operations: Ability to 256000 Reactor

..  ; I'.)~ evaluate plant performance and make

\ operational judgments 4.4 37 Condensate

'" based on operating characteristics, reactor behavior, and instrument

. ' . interpretation.

......  : A4.03 - Ability to 215001 Traversing

..( r* manually operate and/or X . monitor in the control 3.0 38 In-core Probe room: Isolation valves:

.: Mark-I&II(Not-BWR1)

KIA Category Totals 1 1 1 1 1 1 1 ,.'

1/4 1 2"12 Group Point Total: I 12/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date:

Category KA# Topic RO SRO-Only IR Q# IR Q#

Knowledge of new and spent fuel 2.1.42 2.5 66 movement procedures.

Knowledge of individual licensed operator responsibilities related to shift 2.1.4 staffing, such as medical requirements, 3.3 67 "no-solo" operation, maintenance of active license status, 10CFR55, etc.

1. Conduct of Operations Knowledge of facility requirements for 2.1.13 3.2 94 controlling vital/controlled access.

Knowledge of criteria or conditions that require plant-wide announcements, 2.1.14 3.1 99 such as pump starts, reactor trips, mode changes, etc.

Subtotal 2 2 Knowledge of the process for 2.2.7 2.9 68 conducting special or infrequent tests.

Ability to apply technical specifications 2.2.40 3.4 69 for a system.

Ability to determine operability and I or 2.2.37 3.6 75 availability of safety related equipment.

2. Equipment Control Knowledge of limiting conditions for 2.2.22 4.7 95 operations and safety limits.

Subtotal 3 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 r-Knowledge of radiation monitoring systems, such as fixed radiation 2.3.15 monitors and alarms, portable survey 2.9 70 instruments, personnel monitoring equipment, etc.

Ability to comply with radiation work 2.3.7 permit requirements during normal or 3.5 71

~--

abnormal requirements.

r-

3. Radiation I Control 2.3.11 Ability to control radiation releases. 4.3 96 J Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment 2.3.12 3.7 100 entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Subtotal 2 2 Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, 2.4.21 core cooling and heat removal, reactor 4.0 72 coolant system integrity, containment conditions, radioactivity release control, etc.

Knowledge of the operational 2.4.20 implications of EOP warnings, cautions, and notes.

3.8 I 73

4. Emergency Knowledge of EOP mitigation Procedures I 2.4.6 3.7 74 I-----

strategies.

Plan Knowledge of EOP entry conditions and 2.4.1 4.8 971 f-o-immediate action steps.

Knowledge of low power I shutdown implications in accident (e.g., loss of 2.4.9 4.2 98 coolant accident or loss of residual heat removal} mitigation strategies.

c-

~ Subtotal 3 2 I Tier 3 Point Total: 10 7

ES-401 Record of Rejected KIA's Form ES-401-4 Randomly Selected Tier I Group Reason for Rejection KA Question 81, 2.4.31 - Emergency Procedures 1 PI.in: Knowledge 295016/2431 of annunciator alarms, indications, or response procedures.

Tier 1 / Group 1 I d *th '295016 There is no link to 50.43 because control room abandonment is rep ac~ 2w.; 11 an SOP and there are no annunciators associated with it

. . Randomly selected 2.4.11, Knowledge of abnormal condition rocedures.

+::-

Question 39, EK1.04 - Knowledge of the operational implications 2950371 EK1 04 of the following concepts as they apply to SCRAM CONDITION

. . PRESENT AND REACTOR POWER ABOVE APRM Tier 1 I Group 1 replaced wIth 295037 DOWNSCALE OR UNKNOWN: Hot shutdown boron weight:

1 EK1.06 Plant-Specific. NMP 2 does not use Hot shutdown boron weight Randoml selected EK1.06, Cooldown effects on reactor pow~r.

- i Question 44, EK2.05 - Knowledge of the interrelations between 2950261 EK2. 05 SUPPRESSION POOL HIGH WATER TEMPERATURE and the Tier 1 1 Group 1 replaced with 295 026 following: Containment pressure: Mark-III. This KIA does not 1 EK2.02 apply to NMP 2 which has a Mark II Containment. Randomly selected EK2.02, Suppression pool spray: Plant Specific ~.~--;

Question 53, EA2.02 - Ability to determine and/or interpret the 295038 I EA2. 02 following as they apply to HIGH OFF-SITE RELEASE RATE:

Tier 1 1 Group 1 replaced with 295 038 Total number of curies released. This is not a function of the RO I EA2.04 licensed position at NMP 2. Randomly selected EA2.04, Source of off-site release.

- Question 55, 2.4.3 - Emergency Procedures I Plan: Ability to 295005 I 2.4. 3 identify post-accident instrumentation. There are no post Tier 1 1 Group 1 replaced with 295 005 accident instruments associated with a main turbine generator 12.4.31 trip at NMP 2. Randomly selected 2.4.31, Knowledge of

'-~ ~~

annunciator aLarms, in<:lication~.1 or response procedur-=e~s,-.-;--~-l Question 84, 2.1.30 - Conduct of Operations: Ability to locate and operate components, including local controls. There is an 295020/2.1.3 o SOP 83 for primary containment isolations but there are no local Tier 1 1 Group 2 replaced with 29 5020 operations for an SRO to direct. Additionally there are no local 12.1.20 operations in response to inadvertent isolations in the EOPs.

Unable to write an effective question, randomly selected 2.1.20,

,...... ~- -~-~~---~~~.

_-+::Ability to interpret and execute Qrocedure steps.

Question 85, 2.1.28 - Conduct of Operations: Knowledge of the 8 purpose and function of major system components and controls.

295009 1 2.1.2 5020 Could not write an SRO question to meet 10CFR50.43 Tier 1 1 Group 2 replaced with 29 requirements. Randomly replaced with 2.1.23, Ability to perform 12.1.23 specific system and integrated plant procedures during all

-~.---.---

mode~of plant operation._~~_~_~ ._.___ ~ ___

Question 86, A2.11 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and 2090011 A2.1 1 (b) based on those predictions, use procedures to correct, Tier 2 1 Group 1 replaced with 20 900'1 control, or mitigate the consequences of those abnormal 1 A2.04 conditions or operations: Loss of fire protection: BWR-1. NMP 2 is not a BWR-I this KIA does not apply, randomly selected I _-LA2:...::~04, D.C. failures _ _ _ _ __

ES-401 Record of Rejected KIA's Form ES-401-4 Question 5, K3.03 - Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following: Core plate differential pressure'mdication.

211000/ K3.03 NMP 2 SLC discharges into the HPCS spray ring in the top of Tier 2 I Group 1 replaced with 211000 the core there is no relationship between a loss or malfunction of

/ K3.01 SLC and Core plate differential measurement. Randomly selected K3.01, Ability to shutdown the reactor in certain conditions i---- - - Question 6, K3.13 - Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISO LATION 223002 / K3.13 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OF Fwill have on Tier 2 1 Group 1 replaced with 223002 following: Isolation Condenser: Plant-Specific. NMP2 does not

/ K3.20 have isolation condensers, randomly selected K3. 20 Standby gas treatment system r--------- ,-

Question 11, K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the INSTRUMENTAIR 300000 I K6.04 SYSTEM: Service air refusal valve. NMP 2 does not have a Tier 2 / Group 1 replaced with 300000 refusal valve, additionally if this KIA was used to w rite a question

/ K6.13 on an isolation valve it would be very similar to another KIA on the NRC exam. Randomlt selected K6.13, Filters Question 14, A 1.02 - Ability to predict and/or monitor changes in parameters associated with operating the UNINTE RRUPTABLE POWER SUPPLY (A.C.lD.C.) controls including: Motor generator outputs. NMP 2 does not have any motor generators 2620021 A1.02 that are UPS. All NMP 2s UPS units have inverters. Could not Tier 2 I Group 1 replaced with 262002 select another A 1 KIA because the remaining importance was

/ A3.01 less than 2.5. Randomly selected A3.01, Ability to monitor automatic operations of the UNINTERRUPTABLE POWER SUPPLY (A.C.lD.C.) including: Transfer from preferred to alternate source. -~--~-~-~---

Question 21, 2.4.30 - Emergency Procedures / Pia n; Knowledge of events related to system operation / status that must be reported to internal organizations or external agencies, such as 259002 / 2.4.30 the state, the NRC, or the transmission system operator. There Tier 2 / Group 1 replaced with 259002 are no RO responsibilities regarding Reactor Wate r Level

/2.4.4 Control and reporting to internal organizations or external agencies. Randomly selected 2.4.4, Ability to recognize abnormal indications for system operating parameters that are entry level conditions for emergenct and abnorma I procedures.

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Question 71, 2.3.11 - Ability to control radiation rei eases. This same KIA is used for Question 96. To prevent adouble jeopardy Tier 31 2.3.11 replaced with question randomly selected 2.3.7, Ability to compl y with radiation Category 3 2.3.7 work permit requirements during normal or abnormal requirements. ..,...-;----

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Question 73, 2.4.9 - Knowledge of low power / shu tdown implications in accident (e.g., loss of coolant accid ent or loss of Tier 31 2.4.9 replaced with residual heat removal) mitigation strategies. This same KIA is Category 4 2.4.20 used for Question 98. To prevent a double jeopardy question randomly selected 2.4.20, Knowledge of the opera tional I Iimplications of EOP warnings, cautions, and notes ----

ES-401 Record of Rejected KIA's Form ES-401-4

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Question 100, 2.3.15 - Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. This Tier 31 2.3.15 replaced with same KIA is used for Question 70. To prevent a double jeopardy Category 3 2.3.12 question randomly selected 2.3.12, Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities,

~_~~~_ ~.<::cess to locked high-radiatic.>fl.areas, aligning filters-,~!~"-~_~~_

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Question 88, 2.4.3 - Emergency Procedures 1 Plan: Ability to identify post-accident instrumentation. There is no HPCS post 209002 1 2.4.3 accident instrumentation. Randomly replaced with 2.1.7, Tier 2 1 Group 1 replaced with 209002 Conduct of Operations: Ability to evaluate plant performance and 12.1.7 make operational judgments based on operating characteristics, I CC2I..LVI behavior, and instrument II IlCI 1-" ClCHII.>n.

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