ML21252A188

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Final Written Examination and Operating Test Outlines (Folder 3)
ML21252A188
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 09/03/2021
From: Todd Fish
Operations Branch I
To:
Talen Energy
Shared Package
ML20259A339 List:
References
EPID L-2021-OLL-0003
Download: ML21252A188 (26)
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Text

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Aeeendix D Scenario Outline Form ES-D-1

Facility: SSE*s Units 1 and 2 Scenario No.: SSES-2021 NRC-S1 Op-Test No.: LOC31

Examiners: Operators:

Initial Conditions: Unit 1 startup is in progress; currently at 30% power. APRM 13 is downscale and bypassed.

Turnover: Swap CRD Pumps, then continue startup beginning at GO-100-002 (Rev. 115) step 5.81 by withdrawing control rods.

Critical Tasks: See Page 2

II E1No. Type* Description vent Malf. No. Event Event

1 NIA N-BOP, Swap CRD Pumps SRO

NIA R-ATC, Continue Startup / Raise power by withdrawing rods 2 SRO N-ATC GO-100-002

3 M64A TS-SRO Technical Specifications MALF N APRM 11 Self-Test Fails

NB09Ul_L 4 ISB211N02 TS-SRO Level Instrument, LIS-821-1 N024C, fails high 4CTVSP

5 W29 SRO AR-122-001 (A02), ON-VACUUM-101, OP-142-001 MALF C C-BOP,. 'B' Circ Water Pump Trip

6/7 MALF T Main Turbine Trip / 2 Bypass Valves Fail open C04 C-AII ON-SCRAM-101, ON-TURBINE-101, OP-AD-300

8 HOS M-AII EO-100-102, EO-100-103 MALF E Small Steam Leak inside Drywall

9 H06 SRO OP-149-004 MALF E C-ATC, RHR F027A(B) failed closed

10 ]\\:IALF_M C-ATC, B(A) RHRSW Pp fails to start S32A SRO OP-116-001, OP-216-001

/

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

I Appendix D

Facility: SSES Units 1 and 2 Scenario No.: SSES 2021-NRC-S2 Op-Test No.: LOC 31

Examiners: Operators:

Initial Conditions: The plant is operating at approximately 100% power. 'D' RWMU Pump is out of service.

Turnover: Both Units are at rated power. 'D' RWMU Pump is out of service for motor replacement.

Place ESW in service for Unit 2 RCIC Surveillance.

Critical Tasks: See Page 2

Event Malf. No. Event Event No. Type* Description

1 NIA N-BOP Place ESW in service for Unit 2

2 RCASUl TS-SRO RClC Temperature switch K15TVSP fails high, Technical Specifications

NIA GCC requests Marketing Driven Unit 1 Power Reduction of 100 3 R-ATC, MWe. SRO GO-100-012, OP-AD-338 Att.

E, OI-AD-029 sso1u1_p. C-BOP,...., -**'

4 CV10726T SRO Steam Seal Evaporator PCV failure VFAILSP RD0lUl C-BOP, -

5 1F172TVZ SRO 'A' CRD Pump trips CLO TS-SRO (Low Suction Pressure), Accumulator Fault

RDBRRO C-ATC, 6 D 1803TF Multiple Control Rods Drift DRIFT! SRO RDBQRO 7 D 1811TF M-ALL Electrical ATWS I Hydraulic ATWS DRIFT!

RDBLRO C-BOP, 8 D 3447TF SRO SLC Pump trips DRIFT!

RPARUl 9 K23124AI C-ALL EHC pressure regulator output fails BICIDTV to zero SP

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Aeeendix D Scenario Outline Form ES-D-1

Facility: SSES Units 1 and 2 Scenario No.: SSES 2021-NRC-S3 Op-Test No.: LOC 31

Examiners: Operators:

Initial Conditions: Unit 1 is at 75o/o power with a shutdown in progress. Unit 2 is at rated power.

Turnover: Swap Service Water Pumps, then continue Unit 1 shutdown from GO-100-004 (Rev. 81)

Step 5.13.

I Critical Tasks: See Page 2

/

-,t Malf. No. Event Event No. Type* Description

1 SRO GO-100-004 NIA N-ATC, Continue shutdown, reducing power with Recirc.

I 2 1D274 TS-SRO Loss of 1 D27 4 ON-250VDC-101, Technical Specifications

MALF T R-ATC, EHC Oscillations 3 COi C-ALL,

  • - TS-SRO ON-PWR-101, ON-TURBINE-101 Technical Specifications

4 43A SRO OP-AD-300, EO-100-102 REM NB C-BOP, Both RRP speeds increase rapidly

5 REM NB Fuel Failure 43B C-ALL ON-OFFGASRAD-101

6 R29 M-ALL EO-100-104 ~ MALF R. Unisolable RWCU leak

7 U04. SRO ON-LVL-101, OP-145-006 MALF C C-ATC, LV-10641 fails closed

8 NIA M-ALL Offsite release limits (MIDAS)

EO-100-105, EO-100-112

  • (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1

Facility: SSES Units 1 and 2 Scenario No.: SSES 2021-NRC-S4 Op-Test No.: LOC 31

Examiners: Operators:

Initial Conditions: Unit 1 is operating at 90% power. HPCI is out of service. Unit 2 is in Mode 5.

\\

Turnover: Unit 1 is at 90% following performance of SO-193-001, Quarterly Turbine Valve Testing.

HPCI is out of service to replace Aux Oil Pump motor. LCO 3.5.1 Condition D was entered 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ago. Swap Service Water Pumps. Following that per Reactor Engineering, restore power to 100% at s 1 % / minute using Reactor Recirc. Once at rated power, swap EHC Pumps. Unit 2 is in Mode 5 with 2A RHR Pump in service for Shutdown Cooling.

Critical Tasks: See Page 2

Event Malf. No. Event Event No. Type* Description

1 SRO OP-.111-001 N/A N-BOP, Swap Service Water Pumps

2 \\ N/A R-ATC, Raise power with Recirc BOP GO-100-012, OP-AD:-338 \\

RC02U1_ RCIC Turbine Trip & Throttle Fails Closed 3 HV15012 TS-SRO _ATVFAI AR-108-001 {H01)

LSP

EEHQU0 C-BOP, 4 _0X203 - SRO ESS-201 (0X203} Winding Temp increasing CLCOPR OP-004-001 TDR TS-SRO

5 REM_GC C-ALL Stator Cooling Low Flow 04 ON-STATOR-101, EO-100-102

ANCZP0 6 M-ALL C653_AR Recirc Suction Break 015007T EO-100-102, EO-100-103 VFAIL

7 G07A SRO OP-183-001, EO-100-112 MALF M C-BOP, Auto ADS initiation fails

RHCZU1K6 RHR Valve HV-151-F015A Fails to Auto Open/ HV-151-F015B 6ATVSP 8 RHDCU1K6 C-ALL Partially Opens 6BTVSP EO-100-102, OP-AD-300

  • _ (N)ormal, (R)eactivity, ( I )nstrument, (C)omponent, (M)ajor ES-301 Administrative Topics Outline Form ES-301-1

Facility: Susguehanna Date of Examination: 7/26/2021

Examination Level: RO ~ SRO Operating Test Number: LOC 31

Administrative Topic (see Note) Type Describe activity to.be performed Code*

Completed Aborted Evolution Log

Conduct of Operations R, D

Perform LPRM Upscale Alarm Tracking

Conduct of Operations R,D

Perform Jet Pump Operability Check

Equipment Control R,M

Determine Radiological Requirements - Steam

Radiation Control R,M Leak in RCIC Room

,;, *h *: > > -~ > ~ > *>>., '; J' ~..... :,-> ', t'>,': >

l;merge119y_F'[ari. ? >>..

  • :,, '\\',; e > ** >

1 >,**<,,

  • );'.... >...

NOTE: All items (five total) are required for SR Os. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

(P)revious 2 exams(::, 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1

Facility: Susguehanna Date of Examination: 7/26/2021 Examination Level: RO SRO ~ Operating Test Number: LOC 31

Administrative Topic (see Note) Type Describe activity to be performed Code*

Perform Validation of Heat Balance

Conduct of Operations R,M

Perform LPRM Upscale Alarm Operability

Conduct of Operations R,D Tracking and Determine Required Actions

Determine Operability of MSIV Isolation

Equipment Control R,D Actuation

Determine LCO Applicability and Ability to

Radiation Control R,D Bypass Secondary Containment Zone 2

Isolation

Classify an Emergency Condition and Complete

Emergency Plan R,N an Emergency Notification Report

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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

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

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

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

Facility: Susguehanna Date of Examination: 7/26/2021 Exam Level: RO ~ SRO-I SRO-U Operating Test Number: LOC 31

Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U

System/JPM Title Type Code* Safety Function

a. Reset Recirc Lim 2 Runback M,S,A 1
b. Reactor Feed Pump Post Scram Recovery L,M,S,A 2
c. Open MSIVs During Reactor S/U (All rods in) D,EN,L,S,P 3
d. Shutdown Cooling Temperature Control A,M,L,S. 4
e. Reset Drywell Cooling Isolation D,EN,S 5
f. Synchronize the B Diesel Generator D,S 6
g. APRM Gain Adjust D,S 7
h. Place Alternate TBCCW Pump 1/S A,D,S 8

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. Hydraulically Remove HCU From Service D,R 1
j. Start RPS MG Set 2S237A Locally D,R 7
k. Manually Burst Rupture Disc D,E 5
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

I

  • Type Codes I Criteria for R /SRO-I/SRO-U I

(A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank :5 9/:5 8/:54 (E)mergency or abnormal in-plant ~1,~1,~1 (EN)gineered safety feature ~ 1/~ 1/~ 1 (control room system)

(L)ow-Power/Shutdown ~1,~1,~1 (N)ew or (M)odified from bank including 1 (A) ~ 2/~ 2/~ 1 (P)revious 2 exams :5 3/:5 3/:5 2 (randomly selected)

(R)CA ~ 1/~ 1/~ 1 (S)imulator ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility: Susguehanna Date of Examination: 7/26/2021 Exam Level: RO SRO-I [X] SRO-U Operating Test Number: LOG 31

Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U

System/JPM Title Type Code* Safety Function

a. Reset Recirc Lim 2 Runback M,S,A 1
b. Reactor Feed Pump Post Scram Recovery L,M,S,A 2
c. Open MSIVs During Reactor S/U (All rods in) D,EN,L,S,P 3
d. Shutdown Cooling Temperature Control A,M,L,S. 4
e. Reset Drywell Cooling Isolation D,EN,S 5

f.

g. APRM Gain Adjust D,S 7
h. Place Alternate TBCCW Pump I/S A,D,S 8

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. Hydraulically Remove HCU From Service D,R 1
j. Start RPS MG Set 2S237A Locally D,R 7
k. Manually Burst Rupture Disc D,E 5
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for R /SRO-1/SRO-U

(A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank s 9/:5 8/:5 4 (E)mergency or abnormal in-plant ;::11;:;1/;:;1 (EN)gineered safety feature ;:; 1/;:; 1/;:; 1 (control room system)

(L)ow-Power/Shutdown ~ 1/~ 1/~ 1 (N)ew or (M)odified from bank including 1 (A) ;:; 21;:; 2/~ 1 (P)revious 2 exams s 3/:5 3/:5 2 (randomly selected)

(R)CA ;::1/~1/;:;1 (S)imulator ES-301 Control Room/In-Plant Systems Outline Form ES-301-2

Facility: Susguehanna Date of Examination: 7/26/2021 Exam Level: RO SRO-I SRO-U [Z] Operating Test Number: LOC 31

Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U

System/JPM Title Type Code* Safety Function

a.

b. Reactor Feed Pump Post Scram Recovery L,M,S,A 2
c. Open MSIVs During Reactor S/U (All rods in) D,EN,L,S,P 3
d. Shutdown Cooling Temperature Control A,M,L,S. 4

e.

f.

g.

h. Place Alternate TBCCW Pump 1/S

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. Hydraulically Remove HCU From Service D,R 1

j.

k. Manually Burst Rupture Disc D,E 5
  • All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.
  • Type Codes Criteria for R /SRO-1/SRO-U

(A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank :=; 9/:5 8/:5 4 (E)mergency or abnormal in-plant ;::11;::11;::1 (EN)gineered safety feature ;:: 1/;:: 1/;:: 1 (control room system)

(L)ow-Power/Shutdown ;::1/;::1/;::1 (N)ew or (M)odified from bank including 1 (A) ;:: 2/;:: 2/;:: 1 (P)revious 2 exams :=; 3/:5 3/:5 2 (randomly selected)

(R)CA ;::11;::1/;::1 (S)imulator I

Facility: Susquehanna 1 &2 Rev. 0 Date of Exam: 07/26/2021 RO KIA Category Points SRO-Only Points I Tier Group 1al K1 K2 K3 K4 KS K6 A 1 A2 A3 A4 G* Total A2 G* TotI

1. 1 3 4 4 3 3 3 20 3 4 11 Emergency and 2 0 2 2 1 1 1 7 1 2 31 Abnormal Plant I

Evolutions Tier Totals 3 6 6 4 4 4 27 4 6 10 I

2. 1 3 2 2 3 3 3 3 3 1 1 2 26 2 3 51 Plant 2 1 1 1 1 1 1 1 1 2 1 1 12 1 I 1 1 31 Systems Tier Totals 4 3 3 4 4 4 4 4 3 2 3 38 4 4 s:I
3. Generic Knowledge and Abilities Categories 10 I: 1 2 3 4 2 3 4 7

3 3 2 2 2 1 2 I I I I I Note: 1. Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and ~RO only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each KIA category shall not be less than two). (One Tier 3 radiation control KIA is allowed if it is replaced by a KIA from l another Tier 3 category.).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final p int total for each group and tier may deviate by +/-1 from that specified in the table based on NRG revisions. The finJ1 RO exam must total 75 points, and the SRO-only exam must total 25 points. I
3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not,1 included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the 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 KIAs having an importance rating (IR) of 2.5 or higher shall be select9d.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively. I

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA catalog, but the topics must b, relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable Kl As.
8. On the following pages, enter the KIA numbers, a brief description of each topic, the topics' I Rs for the applicab e 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 a category 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, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

G* Generic KIAs

  • These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the KIA catalog.
    • These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. I

Page 1 of 15 ES-401 BWR Examination Outline (Susquehanna 1 &2) Form ES-401-r Emergency and Abnormal Plant Evolutions-Tier 1/Group 1 (RO/SRO)

E/APE # / Name/

Item# Safety Function K1 K2 K3 A1 A2 Gt KIA Topic(s) IR Qt,-

4 29§QQ1 (-6,Pes ~) (29§QQMA~.Qel) Al:Jility le eJ:JeFale amlteF meAiteF 11:!e felle*NiA§ &.a 4Q PaFtial eF GeFRJ:Jlete as ti:ley aJ:JJ:JIY le PAR+IAb QR GQMPbes+e bQ:i,:i, Qp FGRGeQ II,..,,,..,..,,....,: r-.. - J r- *- ('("\\QC Cl ("\\\\JI.I f'IDf""l - - - -11 /\\_Tlr"\\"'- 1r,.r-....... AA "7 AC'~*.-..,.,.,_,,:J Flew GiFGulatieA / 1 ~

&-4 1 295001 (APE 1) X (295001AA1.05) Ability to operate and/or monitor the following 3.3 10*

Partial or Complete as they apply to PARTIAL OR COMPLETE LOSS OF FORCED Loss of Forced Core CORE FLOW CIRCULATION (CFR: 41.7 / 45.6): Recirculation Flow Circulation / 1 flow control system:

&4 2 295001 (APE 1) X (295001AA2.06) Ability to determine and/or interpret the 3.3 83' Partial or Complete following as they apply to PARTIAL OR COMPLETE LOSS Loss of Forced OF FORCED CORE FLOW CIRCULATION (CFR: 41.10 / 43.5 Core Flow / 45.13): Nuclear boiler instrumentation Circulation/ 1 & 4

3 295003 (APE 3) X (295003AK3.06) Knowledge of the reasons for the following 3.7 62 Partial or Complete responses as they apply to PARTIAL OR COMPLETE LOSS Loss of AC Power / OF A.C. POWER (CFR: 41.5 I 45.6): Containment isolation 6

4 295004 (APE 4) X (295004AA2.02) Ability to determine and/or interpret the 3.5 58 Partial or Total Loss following as they apply to PARTIAL OR COMPLETE LOSS OF of DC Power/ 6 D.C. POWER (CFR: 41.10 / 43.5 / 45.13): Extent of partial or complete loss of D.C. power 5 295004 (APE 4) X (295004G2.1.23) PARTIAL OR TOTAL LOSS OF DC POWER 4.4 85 Partial or Total / 6: G2.1.23 - Conduct of Operations: Ability to perform Loss of DC Power I specific system and integrated plant procedures during all 6 modes of plant operation (CFR: 41.10 / 43.5 / 45.2 / 45.6).

6 295005 (APE 5) X (295005AA2.07) Ability to determine and/or interpret the 3.6 99 Main Turbine following as they apply to MAIN TURBINE GENERATOR Generator Trip / 3 TRIP (CFR: 41.10 / 43.5 / 45.13): Reactor water level

7 295005 (APE 5) X (295005AK3.06) Knowledge of the reasons for the following 3.3 69 Main Turbine responses as they apply to MAIN TURBINE GENERATOR Generator Trip / 3 TRIP (CFR: 41.5 I 45.6): Realignment of electrical distribution

8 295006 (APE 6) X (295006AA2.06) Ability to determine and/or interpret the 3.5 30 Scram/ 1 following as they apply to SCRAM (CFR: 41.10 / 43.5 / 45.13):

Cause of reactor SCRAM g 29sQ1 i (APe ~ i) (29sQ1 iG2.~.19) GQ~l+RGb RQQM Ale!ANQQNMe~l+ / 7: ~ ;u GeAtFel Reem G2.U9 GeAElust ef GJ:JeFalieAs: Al:Jilily le use J:JlaAl semJ:)uteFs Al:JaAEleAFAeAt t + le evaluate system eF semJ:JeAeAt status (GFR: 4~.rn t 4a.~2).

9 295016 (APE 16) X (29501682.1.28) CONTROL ROOM ABANDONMENT/ 7: 4.1 25 Control Room G2.1.28 Knowledge of the purpose and function of major Abandonment/ 7 system components and I controls. (CFR: 41.7) I

10 295018 (APE 18) X (295018AK2.01) Knowledge of the interrelations between 3.3 4$

Partial or Complete PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING I Loss of CCW / 8 WATER and the following (CFR: 41.7 / 45.8): System loads 11 295018 (APE 18) X (295018G2.4.21) PARTIAL OR COMPLETE LOSS OF CCW / 4.6 8 Partial or Complete 8: G2.4.21 - Emergency Procedures/ Plan: Knowledge of Loss of CCW / 8 the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc (CFR: 41.7 / 43.5 / 45.12).

II

Page 2 of 15 12 295019 (APE 19) X (295019M 1.01) Ability to operate and/or monitor the following 3.5 5( '

Partial or Complete as they apply to PARTIAL OR COMPLETE LOSS OF Loss of Instrument INSTRUMENT AIR (CFR: 41.7 I 45.6): Backup air supply Air/ 8 43 295019 (.A,Pe 19). (295019G2.4.9) PAR+l,ll,b GR GGMPbe+e bGSS GF 4-.2 Q..

n- *.I --- INS+RYMeN+ AIR! II: G:!.4.9 emeFgeRsy*PFesed11i:es !

bass ef IRStFYmeRt F!laR: KRewledge ef law peweFtslmtde*,¥R implisc!tieRs iR Ail'-1-3 assideRt (e.g., less ef seelaRt assideRt eF less of Fesid11al l:leat Femeval) mitigatieR strategies (GFR: 41-10 ! 43.5 !

~

13 295019 (APE 19) X 295019G2.4.35 Partial or Complete Loss of Instrument Air 4.0 9~

Partial or Complete Knowledge of local auxiliary operator tasks during an Loss of Instrument emergency and the resultant operational effects. (CFR:

Air/ 8 41.10 / 43.5 / 45.13) 14 295021 (APE 21) X (295021AK2:07) Knowledge of the interrelations between LOSS 3.1 71 Loss of-Shutdown OF SHUTDOWN COOLING and the following (CFR: 41.7 /

Cooling/ 4. 45.8): Reactor recirculation 15 295023 (APE 23) X * (295023M 1.03) Ability to operate and/or monitor the following 3.3 241 Refueling Accidents as they apply to REFUELING ACCIDENTS (CFR: 41.7 / 45.6):

I 8. Fuel handling equipment 16 295024 (EPE 1) X (295024EK1.01) Knowledge of the operational implications of 4.1 51 High Drywell the following concepts as they apply to l;-IIGH DRYWELL Pressure/ 5 PRESSURE (CFR: 41.8 to 41.10): Drywell integrity: Plant-Specific I 4+ 29aQ:!a (ePe 2) (:!9§Q:!§G:!.:!.4Q) FIIGFI Re,A,G+GR PReSSbJRe,la: G:!.:!.4Q M 7 lcligl:I ReasteF eEJYi13FfleRt GeRtrnl: Al:Jility te a1313ly +esl=misal S13esifisatieRs feF PFeSSYFe,l a a systeFfl (GFR 4UQ t 4:il.:!,l 4a.a l 4a.a).

17 295025 (EPE 2) *X (2~5025G2.2.39)HIGH REACTOR PRE$SURE / 3: G2.2.39 - 3.9 70 High Reactor Equipment Control: Knowledge of less than or equal to one Pressure I 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> Technical Specification action statements for systems. I

. (CFR: 41.7 / 41.10 / 43.2 / 45.13)

.:i.g :!9aG:!e (ePe a) (:!9§Q:!ieK:!.Q1) KRewleElge ef tl:le iRteFfelatieRs l:JetweeR &9 ~

SY1313FessieR Peel SbJPPReSSIGN PGGb lcllGFI WA+eR +eMPeRA+IJRe aREI Migl:! WateF tl:!e fellewiRg (GFR 41.7 l 4§.3): SY1313FessieR 13eel seeliRg

+BFfl!3eFatYFe t § 18 295026 (EPE 3) X (295026EK2.06) Knowledge of the interrelations between 3.5 65 Suppression Pool SUPPRESSION POOL HIGH WATER TEMPERATURE and High Water the following (CFR: 41. 7 / 45.8): Suppression pool level Temperature I 5

19 295028 (EPE 5) X (295028EK2.01) Knowledge of the interrelations between HIGH 3.7 16 High Drywell DRYWELL TEMPERATURE and the following (CFR: 41.7 /

Temperature (Mark I 45.8): Drywell spray:Mark-1&11 and Mark II only)/ 5

  • w
    !9aQ:i!Q (ePe 7) (:!9§Q:i!QG:!.:!.1:!) bGW SbJPPReSSIG~J. PGGb WA+eR beVeb ~ 2;/

bew SY!3!3FessieR ta: G:!.2.12 eEJYi13FfleRt GeRtrnl: KRewleElge ef SYFVeillaRse Peel i.ii.iateF bevel t a !3F86eEIYFes (GFR 41.1Q,l 4§.1:il).

20 295030 (EPE 7) X (29503082.1.20) LOW SUPPRESSION'POOL WATER LEVEL 4.6 27i Low Suppression / 5: 2.1.20 Ability to interpret and execute procedure steps.

Pool Water Level / 5 (CFR: 41.10 / 43.5/45.13).

24 2115030 (ePe ii (:!!15030G:!.4.3) bQ\\llJ SIJPPRESSIQN PQQb l,ll,l,l!i+ER bEVEb t 3.9 96 bew S11ppFessieR 5: G:!.4.3 emeFgeRsy Prnsed11Fes,! Pfam: Ahili~* te iEleRtify Peel INateF bevel ! pest assideRt iRstrnmeRtatieR (GFR: 41.6 ! 45.4).

a

21 295030 (EPE 7) X. (295030G2.4.6) LOW SUPPRESSION POOL WATER LEVEL 4;7 96 Low Supp_ression / 5: G2.4.6 Knowledge of EOP mitigation strategies. I (CFR:,. 41.10 / 43.5 / 45.13)

Pool Water Level / 5

II

Page 3 of 15 22 295031 (EPE 8) X (295031 EK1.03) Knowledge of the operational implications of 3.7 13 Reactor Low Water the following concepts as they apply to REACTOR LOW Level/ 2 WATER LEVEL (CFR: 41.8 to 41.10): Water level effects on reactor power 23 295037 (EPE 14) X (295037EA2.07) Ability to determine and/or interpret the 4.2 941 Scram Condition following as they apply to SCRAM CONDITION PRESENT Present and AND REACTOR POWER ABOVE APRM DOWNSCALE OR Reactor Power UNKNOWN (CFR: 41.10 / 43.5 / 45.13): Containment AboveAPRM conditions/isolations Downscale or Unknown/ 1 24 295037 (EPE 14) X (295037EK3.07) Knowledge of the reasons for the following 4.2 53 Scram Condition responses as they apply to SCRAM CONDITION PRESENT Present and Reactor AND REACTOR POWER ABOVE APRM DOWNSCALE OR Power Above APRM UNKNOWN (CFR: 41.5 / 45.6): Various alternate methods of Downscale or control rod insertion: Plant-Specific Unknown/ 1

2e 29a0a!l (el=le 1 a) (29a0a!leA2.02) Aeility te aetem1iAe aA8f9F iAteF13Fel ll=le 2-,.a 4 Fli§R Gffsite felle,... iA§ as U1ey a1313ly le FIIGFI GFF ~ITe RebeA~E R".Te Raaieaslivily (CFR 41.1 o I 4a.a t 4a.1 a): Tetal AumeeFef suFies mleasea Release Rate t 9 25 295038 (EPE 15) X (295038EA2.04) Ability to determine and/or interpret the 4.1 1 High Offsite following as they apply to HIGH OFF-SITE RELEASE RATE Radioactivity (CFR: 41.10 / 43.5 / 45.13): Source of Off-site release Release Rate I 9 26 600000 (APE 24) X (600000AK3.04) Knowledge of the reasons for the following 2.8 63 Plant Fire On Site I responses as they apply to PLANT FIRE ON SITE (CFR: 41.5 I 8 45.6): Actions contained in the abnormal procedure for plant fire on site 27 700000 (APE 25) X (700000AK1.02) KNOWLEDGE RO Knowledge of the 3.3 28 Generator Voltage operational implications of the following concepts as they apply and Electric Grid to GENERATOR VOLTAGE AND ELECTRIC GRID Disturbances/ 6 DISTURBANCES: Overexcitation (CFR: 41.4, 41.5, 41.7, 41.10

/ 45.8) 295027 (EPE 4)

High Containment Temperature (Mark Ill Containment Only)/ 5 IKJA Category Totals: I 3 I 4 I 4 I 3 I 6 I 7 !Group Point Total: I 271 I

ES-401 BWR Examination Outline (Susquehanna 1 &2) Form ES-401-r Emergency and Abnormal Plant Evolutions-Tier 1/Group 2 (RO/SRO)

E/APE #/Name I I Item# Safety Function K1 K2 K3 A1 A2 G* KIA Topic(s) IR Q#,

28 295002 (APE 2) X (295002AK2.03) Knowledge of the interrelations between LOSS 3.5 43 Loss of Main OF MAIN CONDENSER VACUUM and the following (CFR:

Condenser Vacuum 41.7 / 45.8): PCIS/NSSSS

/3 29 295009 (APE 9) X (29500982.4.2) LOW REACTOR WATER LEVEL/ 2: G2.4.2 - 4.6 35 Low Reactor Water Emergency Procedures / Plan: Knowledge of system set points, Level/ 2 interlocks and automatic actions associated with EOP entry conditions (CFR: 41. 7 / 45. 7 / 45.8).

30 295012 (APE 12) X (295012AA2.01) Ability to determine and/or interpret the 3.8 High Drywell following as they apply to HIGH DRYWELL TEMPERATURE 61 Temperature/ 5 (CFR: 41.1 0 / 43.5 / 45.13): Drywell temperature 31 295013 (APE 13) X (295013AK3.01) Knowledge of the reasons for the following 3.6 8 High Suppression responses as they apply to HIGH SUPPRESSION POOL Pool Temperature. I TEMPERATURE (CFR: 41.5 / 45.6): Suppression pool cooling 5 operation 32 295014 {.O,F!e H) {295014G2.4.2) INACVeRTeNT ReACTIVIT¥ ACCITIGN / 1: 4.6 8-i:

IAaEl\\<eFteAt G2.4.2 emeF§eAsy F!FeseEluFes,1 F!laA: KAewleEl§e ef Reasti\\<it}' AEIElitieA system set )aleiAts, iAteFlesks aAEI autematis astieAs 1-assesiateEI witl=l eGF! eAtiy seAaitieAs {CFR: 41.7 / 45.7 /

~

Page 4 of 15 32 295014 (APE 14) X (295014G2.4.41) INADVERTENT REACTIVITY ADDITION/ 1: 4.6 871 Inadvertent G2.4.41 - Knowledge of the emergency action level Reactivity Addition thresholds and classifications. I (CFR: 41.10 / 43.5 / 45.11)

/ 1

33 295017 (APE 17) X (295017G2.4.47) ABNORMAL OFFSITE RELEASE RATE/ 9: 4.2 80' Abnormal Offsite G2.4.47 - Emergency Procedures/ Plan: Ability to diagnose Release Rate / 9 and recognize trends in an accurate and timely manner.

utilizing the appropriate control room reference material (CFR: 41.10 / 43.5 / 45.12).

M 29aQ22 (APis: 22) (29aQ22AKJ.Q2) KAowleEl§e of U1e FeasoAs feF tl,e fellowiA§ 2-,-9 Jg boss of CoAtrnl Roe rnspoAses as they apply to bOSS OF CRD PUMPS (CFR: 41.a DFive P1c1FApS t 1 t 4a.e): GROM hi§h teFApeFat1c1Fe

34 295022 (APE 22) X 295022AK3.01 Knowledge of the reasons for the following 3.7 38 Loss of Control Rod responses as they apply to LOSS OF CRD PUMPS (CFR: 41.5 Drive Pumps / 1 I 45.6): Reactor Scram

~ 29aQJJ (is:Pis: 1 Q) (29aQJJ!s:K1.QJ) KAowleEl§e of tl=le opeFatioAal iFAplisatioAs of J,.9 ~

l=li§R SesoAElaFY the fellowiA§ soAsepts as tl=ley apply to l=IIGl=I Sls:GONDAR¥ CoAtaiAFAeAt AFea cmJT/1.INM!s:NT AR!s:A RADIATION bls:VRS (CFR: 41.!l to RaEliatioA bevels t 9 4 U Q): RaElialioA rnleases

~ 295QJ:;! (ls:Pls: 1Q) (295Qaals:K1.Q2) KmiwleEl§e of the opeFatioAal iFAplisatioAs of J,.9 ~

l=li§h SesoAElaFY the fellowiA§ soAsepts as they apply to l=IIGl=I Sls:CmJDAR¥ GoAtaiAFAeAt AFea GONTAINM!s:NT AR!s:A RADIATlmJ bls:VRS (CFR: 41.!l to RaEliatioA bevels t 9 41.1Q): PeFSOAAel prntestioA

~ aQQQQQ (is:Pis: 1 a) (aQQQQQ ls:K1.Q1) KAowleEl§e of tl=le opeFatioAal iFAplisatioAs of ~ l l=li§h CoAtaiAFAeAt the fellowiA§ soAsepts as they apply to l=IIGl=I GON+.".l~JM!s:~J+

i=lyeFO§eA 1=1¥DROG!s:N GONG!s:N+RA+IONS: CoAtaiAFAeAt iAle§Fity GOASeAtFatioA t a

35 500000 (EPE 16) X (500000 EK2.03) Knowledge of the interrelations between 3.3 36 High Containment HIGH CONTAINMENT HYDROGEN CONCENTRATIONS the Hydrogen following: Containment Atmosphere Control System Concentration / 5

36 295035 (EPE 12) X (295035EA 1.02) Ability to operate and/or monitor the following 3.8 31,.

Secondary as they apply to SECONDARY CONTAINMENT HIGH Containment High DIFFERENTIAL PRESSURE (CFR: 41.7 / 45.6): SBGT/FRVS Differential Pressure I

/5 I 37 295035 (EPE 12) X (295035EA2.02) Ability to determine and/or interpret the 2.8 8 Secondary following as they apply to SECONDARY CONTAINMENT Containment High HIGH DIFFERENTIAL PRESSURE (CFR: 41.10 / 43.5 / 45.13):

Differential Off-site release rate: Plant-Specific Pressure/ 5 295007 (APE 7)

High Reactor Pressure/ 3 I 295008 (APE 8)

High Reactor Water Level/ 2 I 295010 (APE 10)

High Drywell Pressure/ 5 295015 (APE 15)

Incomplete Scram I 1

295020 (APE 20)

Inadvertent Containment Isolation / 5 & 7 295029 (EPE 6)

High Suppression Pool Water Level / 5

Page 5 of 15 295032 (EPE 9)

High Secondary Containment Area Temperature/ 5 295034 (EPE 11)

Secondary Containment Ventilation High Radiation I 9 295036 (EPE 13)

Secondary Containment High Sump/Area Water Level/ 5 500000 (EPE 16)

High Containment Hydrogen Concentration / 5 jKJA Category Totals: I 0 I 2 I 2 I 1 I 2 I 3 !Group Point Total: I 1Q I

ES-401 BWR Examination Outline (Susquehanna 1 &2) Form ES-401r Emergency and Abnormal Plant Evolutions-Tier 2/Group 1 (RO/SRO)

Item# System I Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* KIA Topic(s) JR oJ, 38 203000 (SF2, SF4 X (203000K4.09) Knowledge of 3.1 51 RHR/LPCI) RHR/LPCl:INJECTION MODE RHR/LPCI: (PLANT SPECIFIC) design I Injection Mode feature(s) and/or interlocks which provide for the following (CFR: 41. 7):

Surveillance for all operable components 39 205000 (SF4 SGS) X (205000K5.03) Knowledge of the 3.1 4, Shutdown Cooling operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) (CFR: 41.5 / 45.3): Heat removal mechanisms 40 205000 (SF4 SGS) X (205000K6.02) Knowledge of the 2.7 1 Shutdown Cooling effect that a loss or malfunction of the following will have on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) (CFR: 41.7 / 45.7): D.C.

electrical power 41 206000(SF2,SF4 X (206000K3.02) Knowledge of the 3.8 6' HPCIS) effect that a loss or malfunction of High-Pressure the HIGH PRESSURE COOLANT Coolant Injection INJECTION SYSTEM will have on following (CFR: 41.7 / 45.4): Reactor pressure control:BWR-2,3,4

42 209001 (SF2, SF4 X (209001A4.02) LOW PRESSURE 3.4 LPCS) CORE SPRAY SYSTEM: Ability to Low-Pressure Core manually operate and/or monitor in Spray the control room (CFR: 41. 7 / 45.5 to 45.8): Suction valves 1 43 211000 (SF1 SLCS) X (211 000A 1.09) Ability to predict 4.1 49 Standby Liquid and/or monitor changes in Control parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including (CFR: 41.5 / 45.5): SBLC II system lineup

Page 6 of 15 44 211000 (SF1 SLCS) X (211000G2.4.20) STANDBY LIQUID 3.8 76 Standby Liquid CONTROL: G2.4.20 - Emergency Control Procedures/ Plan: Knowledge of the operational implications of EOP warnings, cautions, and notes (CFR: 41.10 / 43.5 / 45.13).

  1. 212QQQ (SF7 RPS) (212QQQKa.Q1) KAewleege ef ti=le 67- +4 Reacter PrntectieA ei::ieratieAal imf)licatieAs ef li=le rollewiAg C9AGef)tS as li=ley ai::ii::ily le ReAG+GR PRG+eG+IQ~j S¥S+eM tr""r-.-..,,4,j CI AC::")\\, r,,_I *-* ":--

WflStam 45 212000 (SF7 RPS) X (212000K5.02) Knowledge of the 3.3 741 Reactor Protection operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM (CFR: 41.5 / 45.3): Specific logic arrangements

46 215003 (SF7 IRM) X (215003K5.03) Knowledge of the 3.0 661 Intermediate-Range operational implications of the Monitor following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM (CFR: 41.5 / 45.3):

Changing detector position

4-7 21iQQ4 (SF7 (21 aQQ4 Kl.Q1) KAewleege ef li=le ~ J

~ effect ti=lal a less er malf1mctieA ef Seurce RaAge li=le fellewiAg will i=lave GA ti=le Mooitef SGblRGe RA~JGe MGM+GR (SRFI)

S¥S+eM (GFR: 41.7 /. 4 a.7): RPS 47 215004 (SF7 X (215004K6.02)Knowledge of the 3.1 3 SRMS) effect that a loss or malfunction of Source-Range the following will have on the Monitor SOURCE RANGE MONITORING SYSTEM(CFR 41.7/45.7): 24/48 volt DC power

48 215005 (SF7 X (215005K2.02) AVERAGE POWER 2.8 2(

PRMS) Average RANGE MONITOR/LOCAL POWER Power Range RANGE MONITOR SYSTEM:

Monitor/Local Power Knowledge of electrical power Range Monitor supplies to the following (CFR:

41.7): APRM channels 49 217QQQ (SF2, si;:4 (217QQQK1.Q4) KAewleElge efli=le 2-.,e 7'J RGIG) Reacler Gere i::il=lysieal ceAAeclieAs aAEl/.er cause lselatieA GeeliAg effect relatieAsi=lif)S belweeA Re,l>,G+GR GGRe ISGbA+IQ~j GGGbl~JG S¥S+eM (RGIG) aAEl ti=le fellewiAg (GFR: 41.2 le 41.9,1 4 a.719 4a.lil): MaiA C9A9eAser

49 217000 (SF2, SF4 X (217000K1.03) Knowledge of the 3.6 7J RCIC) Reactor Core physical connections and/or cause-Isolation Cooling effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8):Suppression Pool

Page 7 of 15 50 218000 (SF3 ADS) X (218000A2.02) Ability to (a) predict 3.6 a:

Automatic the impacts of the following on Depressurization the AUTOMATIC DEPRESSURIZATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR:

41.5 / 45.6): Large break LOCA

51 218000 (SF3 ADS) X (218000K4.02) Knowledge of 3.8 26 Automatic AUTOMATIC DEPRESSURIZA TION Depressurization SYSTEM design feature(s) and/or interlocks which provide for the following (CFR: 41.7): Allows manual initiation of ADS logic e2 223002 (SF5 PCIS) (223002Aq.03) Al:Jility te pFeEliet &.e wi J2i:imar:y-aRElteF F!19RiteF GAaR§leS iR CeRtaiRFfleRt paFaF11eteFs asseeiateEl witA lselatieR,l~JueleaF epeFatiR§I tAe PRIMAR¥ SteaFfl Supply CONTAINMEMT ISOLATlmJ Slwteff S¥STEMt~l6JCbeAR STeAM S6JPPb¥ SFl6JT OFF GeRtrnls iReluEliR§I (CFR 4q.5 /. 45.5):

SPQSteRIStCRlblStGQS: PlaRt

~

52 223002 (SF5 PCIS) X (223002A 1.02) Ability to predict 3.7 561 Primary and/or monitor changes in Containment parameters associated with Isolation/Nuclear operating the PRIMARY Steam Supply CONTAINMENT ISOLATION Shutoff SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including (CFR: 41.5 I 45.5): Valve Closures

53 223002 (SF5 PCIS) X (223002G2.2.12) PRIMARY 3.7 10!1 Primary CONTAINMENT Containment ISOLATIONINUCLEAR STEAM lsolation!Nuclear SUPPLY SHUTOFF: G2.2.12 -

Steam Supply Equipment Control: Knowledge of Shutoff surveillance procedures (CFR:

41.10145.13).

M 239002 (SF3 SRV) (239002G2.2.4) SAFeT¥ RebleF M ~

Safety Relief Valves VAbVeS: G2.2.4 e<:iuipF11eRI CeRlrnl: (F!1ulti uRit lieeRse) Al:Jility le explaiR IAe vaFiatieRs.,,.,~ iR eeRtrnl iRStFUF!18RtatieR, aREl prneeEluFal aetieRs l:JetweeR URits at a faeility (CFR 4H!t4q_:;zt4U0t45.q,1

~

54 239002 (SF3 SRV) X (23900282.1.32) SAFETY RELIEF 3.8 5!

Safety Relief Valves VALVES: G2.1.32 -Ability to explain and apply system limits and precautions. CFR: 41.10 / 45.12).

M 259002 (SF2 (259002A3.07) Al:Jility te FfleRiteF ~ M RWbCS) ReaeleF auteF11alie epeFatieRs ef tAe WaleF bevel CeRlrnl ReACTOR lAl.0,TeR beVeb CO~ITROb S¥STeM iRGluEliR§I

II (CFR 4q_7 t 45.7): Fl#RV lee~up

Page 8 of 15 55 259002(SF2 X (259002A3.06) Ability to monitor 3.0 45 RWLCS) Reactor automatic operations of the Water Level Control REACTOR WATER LEVEL CONTROL SYSTEM including (CFR: 41.7 I 45.7): Reactor water level setpoint setdown following a reactor scram: Plant0 Specific w 2!i9QQ2 (SP:2 (2a9QQ2K.2.Q2) Re.'\\G+GR lJVA+eR M ~

Rl,O,lbGS) ReasteF beVH GGN+RGb S¥S+eM:

WateF bevel Gentrnl Knmvledge ef elestFisal peweF Sllpplies te Uie fellewing (GP:R:

4 ~.7): P:eedwateF seelant injestien f P:WGI) initiatien legis:P:lJIJGltFlJ;iGI 56 259002 (SF2 X (259002K1.08 REACTOR WATER 3.2 46 RWLCS) Reactor LEVEL CONTROL SYSTEM:

Water Level Control '. Knowledge of the physical '

connections and/or cause effect relationships between REACTOR WATER LEVEL CONTROL s'YSTEM and the following: Recirculation system:

Plant-Specific (CFR: 41.2 to 41.9 / 45.7 to 45.8)

1....,...... ---,.......-,.......,. *c, (2e1 QQQ.A.1 a7 -- -,.Q,7) Al:Jility te pFedist,2-,g 2, Standl:Jy Gas andteF meniteF sl:langes in neatment paFameteFs assesiated witl:l epeFating tl:le S+,A,~JQB¥ GAS

+ReA+Me~J+ S¥S+eM sentrnls inslllding (GP:R 41.!i / 4a.a): SBG+S tFain tempeFatllFe

57 261000 (SF9 SGTS) X (261 000A 1.02) Ability to predict 3.1 2 Standby Gas and/or monitor changes in Treatment parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including (CFR: 41.5 / 45.5): Primary containment pressure 58 261000 (SF9 SGTS) X (261 000K3.02) Knowledge of the 3.6 61, Standby Gas effect that a loss or malfunction of Treatment the STANDBY GAS TREATMENT SYSTEM will have on following (CFR: 41.7 /45.4): Off-site release rate 59 262001 (SF6 AC) X (262001A2.05) Ability to (a) predict 2.9 681 AC Electrical the impacts of the following on the Distribution AC. ELECTRICAL DISTRIBUTION; and (b) base~ on those predictions, use procedu~es to correct, control, or mitigate the consequences of those abnormal coriditions or operations (CFR: 41.5 /.45.6): Bus grounds

60 262001 (SF6 AC) X (262001A2.q6) Ability to (a) predict 2.9 7 AC Electrical the impacts of the following on the Distribution AC. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 /,45.6): Deenergizing a plant bus

Page 9 of 15 61 262001 (SF6 AC).X (262001A2.11) Ability to (a) predict 3.2 81 AC Electrical the impacts of the following on Distribution the A.C. ELECTRICAL DISTRIBUTION; and (bj based on those predictions, use procedures to correct, control, or mitigate.the consequences of those abnormal conditions or operations (CFR:

41.5 / 45.6): [)egraded*system voltages I

~ 2i2QQ2 (SP:e blPS) (2i2QQ2A4.Q1) &.8 ~

bJRiRleFFuplallle bJNIN+eRRbJP+.'\\Bbe PGlA!eR PoweF Supply* SbJPPb¥ ~11,.~.tl;J.G.): Allility lo_

~ mamJally opemle aRdtoF moRiloF iR

  • -r-n. A-1 7 / Ai:;. I:;: j,...,....

4§.8): +FaRsfeF fl:em alternative SOUFGe lo pFE:!feFFed SOUFGe 62 262002 (SF6 UPS) X 262002K1.06 Knowledge of the 2.6 3r Uninterruptable physical connections and/or cause-Power Supply effect relatio~ships between (AC/DC) UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) and the following: (CFR: 41.2 to 41.9 / 45.7 to 45.8): Unit Computer: Plant-Soecific 63 262002 (SF6 UPS) X (262002K4.~1) Knowledge of 3.1 1, Uninterruptable UNINTERRUPTABLE POWER Power Supply SUPPLY (A.p.!D.C.) design (AC/DC) feature(s) and/or interlocks which provide for tne following (CFR: 41. 7):

  • Transfer from preferred power to alternate power supplies e4 2iJQQQ (SP:e l;JG) (2iJQQQAJ.Q~) Allility to moRitoF ~ ~

l;JG elestFisal automatis opemlioRs of the l;J.G.

l;JislFillulioR ebeG+RIGAb l;)IS+RIBbJ+lml iRsludiR§J (G~R: 41.7 t 4 §.7): MeleFS, dials, resord~Fs, alaFms, aRd iRdisatiR§l li§Jhts 64 263000 (SF6 DC) X 263000.K6.02 Knowledge of the 3.2 29 DC Electrical effect that a loss or malfunction of Distribution the following:will have on the D.C.

ELECTRICAL DISTRIBUTION: AC.

electrical distribution

65 263000 {SJ;:6 DG) {263000G2.4.6) DG ebeG+RIG,6..b 3,7 9'.i DG lileotFioal DIS+RIBl.l+IQN: G2.4.6 DistFib1Jtion limeFgeRsy F!rnsed11Fes,1 Plan:

Knowledge of eGP mitigation strategies {GJ;:R: 41.10 ! 43.5 !

4M3}. :

65 263000 (SF6 DC) X 263000G2.4.4 DC ELECTRICAL 4.7 91 DC Electrical DISTRIBUTION: 2.4.4 Ability to Distribution recognize abnormal indications for system operating I parameters that are entry-level conditions for emergency and abnormal operating p~ocedures.

Page 10 of 15 66 264000 (SF6 EGE) *x (264000A2.06) Ability to (a) predict 3.4 3 Emergency the impacts of the following on the Generators EMERGENCY GENERATORS (Diesel/Jet) EOG (DIESEUJET); and (b) based on

  • those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 /

45.6): Opening normal and/or alternate power to emergency bus

67 300000 (SF8 IA) X ' (300000K2.01) INSTRUMENT AIR 2.8 6 Instrument Air SYSTEM: Knowledge of electrical power supplies to the following (CFR: 41.7): Instrument air compressor 68 400000 (SF8 CCS) X (40000082.1.31) COMPONENT 4.6 11i Component Cooling COOLING WATER: G2.1.31 -

Water Conduct of Operations: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup (CFR: 41.10

/ 45.12).

207000 (SF4 IC)

Isolation (Emergency)

Condenser 209002 (SF2, SF4 HPCS) High-Pressure Core Spray KIA Category Totals: I 3 I 2 I 2 I 3 I 3 I 3 I 3 I 5 I 1 I 1 I 5 !Group Point Total: I 311 I

ES-401 BWR Examination Outline (Susquehanna 1 &2) Form ES-401 1 Emergency and Abnormal Plant Evolutions-Tier 2/Group 2 (RO/SRO)

Item# System I Name K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G* KIA Topic(s) IR Q; 69 201006 (SF? X (201006A4.02) ROD WORTH 2.9 3!

RWMS) Rod Worth MINIMIZER SYSTEM (RWM)

Minimizer (PLANT SPECIFIC): Ability to manually operate and/or monitor in the control room (CFR: 41. 7 / 45.5 to 45.8): Pushbutton indicating switches:P-Spec(Not-BWR6) 70 204000 (SF2 X (20400082: 1.19) REACTOR 3.8 6(

RWCU) Reactor WATER CLEANUP: G2.1.19-Water Cleanup Conduct of Operations: Ability to use plant computers to evaluate system or component status (CFR: 41.10 /

45.12).

71 214000 (SF? RPIS) X (214000K5.01) Knowledge of the 2.7 37.

Rod Position operational implications of the Information following concepts as they apply to ROD POSITION INFORMATION SYSTEM (CFR: 41.5 / 45.3): Reed switches 72 215001 (SF? TIP} X (215001A3.03) Ability to monitor 2.5 5!

Traversing In-Core automatic operations of the Probe TRAVERSING IN-CORE PROBE including (CFR: 41.7 / 45.7): Valve operation:Not-BWR1

Page 11 of 15 73 216000 (SF? NBI) X (216000K1.14) Knowledge of the 4.1 H Nuclear Boiler physlcal connections and/or cause-Instrumentation effect relatio~ships between NUCLEAR E3OILER INSTRUMENTATION and the following (CFR: 41.2 to 41.9 / 45. 7 tci 45.8): High pressure coolant injection: Pl~nt-Specific 74 219000 (SFS RHR -X (219000K3.01) Knowledge of the 4.1 H SPC) RHR/LPCI: effect that a loss or malfunction of Torus/Suppression the Pool Cooling Mode RHR/LPCl:TORUS/SUPPRESSION POOL COOl,.ING MODE will have on following (CFR: 41.7 / 45.4):

Suppression' pool temperature control 75 226001 (SFS RHR X (226001 K2.02) 2.9 5 CSS) RHR/LPCI: RHR/LPCl:CONTAINMENT SPRAY Containment Spray SYSTEM MODE: Knowledge of Mode electrical power supplies to the following (CFR: 41.7): Pumps 76 230000 (SFS RHR X -. (230000A1.0,4) Ability to predict 3.2 751 SPS) RHR/LPCI: and/or monitor changes in Torus/Suppression parameters associated with Pool Spray Mode. operating the RHR/LPCl:TpRUS/SUPPRESSION POOL SPRAY MODE controls including (CFR: 41.5 / 45.5): System flow

77. 233000 (SF9 X (233000A2.02) Ability to (a) predict 3.1 47 FPCCU) Fuel Pool the impacts of the following on the 1COOLING AND Cooling/Cleanup FUEL POOL CLEAN-UP; and (b) based on those predictions, yse procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR: 41.5 /

. 45.6): Low pool level

78 234000 (SF8 FH) X (234000K4.02) Knowledge of FUEL 4.1 98 Fuel-Handling HANDLING EQUIPMENT design Equipment feature(s) and/or interlocks which,. provide for the following (CFR:

41.7): Prevention of control rod movement during core alterations

79 2J9QQJ isi;:9 (2J9QQJK4.Q~) KRewleEl!Je ef MSll.-1 M 52 MSVbGS) MaiR beAK.A,Ge GpN+RGb S¥S+eM Steam lselatieR desi!JR feature(s) aREl/er iRterleoks Valve beaka!Je .. '.. /f'C:O*.. - ****v,-

GootFel 4 ~.7): PerfermaRoe ef its safety fuRotieR fellewiR!l a less ef effsite

  • 13ewer:Bl,ll-1R 4,§,e(P S13eo)

79 201003 Control Rod X (201003K4.04) Knowledge of 3.6 SL and Drive CONTROL ROD AND DRIVE Mechanism (SF1) MECHANISM design feature(s) and/or interlocks which provide for the following: (CFR: 41.7) The use of either accumulator or reactor water to SCRAM the control rod.

Page 12 of 15 00 241000 (SF3 (241 000Kl.1, l) KRewleElge ef tl=le 2-,9 +<

RWRS) effest tl=lat a less eF FRalflJRGtieR ef ReaGteFJ+lJFBiRe tl=le fellewiRg will l=lave eR tl=le PFesslJFe ReglJlatiRg ReAG+QR,q:bJRBl~IE PReSSbJRe

' ReGldbA+ING S¥S+eM (GFR 41.7 / 45.7): StateF wateF seeliRg systeFR:

PlaRt S13esifis 80 241000 (SF3 X 241000K6.12 Knowledge of the 3 73 RTPRS) effect that a loss or malfunction of Reactor/Turbine the following,will have on the Pressure Regulating REACTOR/1:URBINE PRESSURE REGULATIN,G SYSTEM: (CFR:

41.7 / 45.7) Control/governor valves 3 268000 (Sf9 RW) (268000G2.2.3+) RADl,ll,'AS+E: 4.6 -7Q RaEl*Jiaste G2.2.3+ Equipment Control:

Ability to Ele,termine eperabilit}*

  • -L~l~.a..,,.,.,& __ -£_&.. - - __..,

- - *- ***--,1 - --

equipment (CfR: 41.+ I 43.5.'

~

81 201001 (SF1 X (201001 G2.2.37)CRD Hydraulic: 4.6 79 CRDH)CRD Equipment Control: Ability to Hydraulic determine operability and/or 82 286000 (SF8 FPS) X (286000A3.04) Ability to monitor 3.2 21 Fire Protection automatic operations of the FIRE PROTECTION SYSTEM including (CFR: 41. 7 / 45. 7): System initiation 83 290002 (Sf4 R\\ll) 1nnnnnn A",,.,.., A.. *-,_, 4.0 94 - *-*-,-, *-***-, --,...

Reastor Vessel tt:Ie impasts: of tile following on Internals tile REACTOR VESSEL INTERNALS; anEI (b) baseEI on to sorrest, c;ontrol, or mitigate tile sonsequenses of those abnermal sonElitions ~F operations (CfR:

41.5.' 45.6): E*GeeEling safety timits

83 290002 (SF4 RVI) X 290002A2.0~ Ability to (a) predict 4.2 91 Reactor Vessel the impacts 'of the following on Internals the REACTOR VESSEL INTERNALS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations (CFR:

41.5 / 45.6): Exceeding thermal limits

201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CROM) Control Rod and Drive Mechanism 201004 (SF? RSCS)

Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 202001 (SF1, SF4 RS) Recirculation..

Page 13 of 15 202002 (SF1 RSCTL)

Recirculation Flow Control 215002 (SF7

  • RBMS) Rod Block Monitor 223001 (SF5 PCS)

Primary Containment and Auxiliaries 239001 (SF3,SF4 MRSS) Main and Reheat Steam 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS)

Condensate 259001 (SF2 FWS)

Feedwater 271000 (SF9 OG)

Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 288000 (SF9 PVS)

Plant Ventilation 290001 (SF5 SC)

Secondary Containment 290003 (SF9 CRV)

Control Room Ventilation IKIA Category Totals: I 1 I 1 I 1 I 1 I 1 I 1 I 1 I 2 I 2 I 1 I 2 !Group Point Total: I 141 I

Page 14 of 15 ES-401 BWR Examination Outline (Susquehanna 1 &2) Form ES-401t3 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)

I Facility: Susquehanna 1 &2 Date of Exam: 07/26/2021 I I RO SRO-Only I Category KIA# Topic Item# IR Q# IR Of!-

1. Conduct of G2.1.1 Conduct of Operations: Knowledge of conduct of operations 3.8 41 I Operations requirements (CFR: 41.1 O / 45.13).

G2.1.39 Conduct of Operations: Knowledge of conservative decision 3.6 34 I making practices (CFR: 41.1 O / 43.5 I 45.12).

Conduct of Operations: Ability to use procedures to determine G2.1.43 the effects on reactivity of plant changes, such as reactor 4.1 12 coolant system temperature, secondary plant, fuel depletion, etc (CFR: 41.10 / 43.6 / 45.6).

G2.1.1 4.2 86 Conduct of Operations: Knowledge of conduct of I operations requirements (CFR: 41.10 / 45.13). I

GeAehrnt ef Q(:leFatieAs: Ability te l!Se (:llaAt 69ffi(:lllteFS te I

~ ~ 73 evalllate system eF sem(:leAeAt statlls {GP:R: 4~.rn t 4!U2). I

G2.1.40 Knowledge of refueling administrative requirements. (CFR: 3.9 78 41.10 / 43.5 / 45.13). I

Subtotal 3 21

2. Equipment G2.2.21 Equipment Control: Knowledge of pre-and post-maintenance 2.9 42 Control operability requirements (CFR: 41.10 / 43.2).

G2.2.22 Equipment Control: Knowledge of limiting conditions for 4.7 22 operations and safety limits (CFR: 41.5 / 43.2 / 45.2).

G2.2.6 changes to procedures (CFR: 41.10 / 43.3 / 45.13). 3 40 I Equipment Control: Knowledge of the process for making I

Equipment Control: (multi-unit license) Ability to explain J

G2.2.4 the variations in control board/control room layouts, 3.6 systems, instrumentation, and procedural actions between units at a facility (CFR: 41.6 / 41.7 / 41.10 / 45.1 / 45.13).

I Equipment Control: Knowledge of the process for I G2.2.7 conducting special or infrequent tests (CFR: 41.1 0 / 43.3 / 2.9 95 I 45.13). I Subtotal 3 21

3. Radiation G2.3.11 Radiation Control: Ability to control radiation releases (CFR: 3.8 23 I Control 41.11 / 43.4 / 45.10).

Radiation Control: Ability to comply with radiation work permit I G2.3.7 requirements during normal or abnormal conditions (CFR: 41.12 3.5 19

/ 45.10). I G2-..3.44 {GP:R: 4~.n t 43.4 t 45.rnJ. 4,-3 -171 RaaiatieA GeAtFel: Ability te seAtFel FaaiatieA Feleases I

I G2.3.4 emergency I conditions. I (CFR: 41.12 / 43.4 / 45.10) 3.7 171 Knowledge of radiation exposure limits under normal or

I Subtotal 2 1:

4. Emergency G2.4.3 Emergency Procedures/ Plan: Ability to identify post-accident 3.7 9 I Procedures/Plan instrumentation (CFR: 41.6 / 45.4).

emeFgeRsy PreseEIYFes t PlaR: Aeility te aiagRese aRa

@.447. Fe69QRize, __ -,_,,~~~.AS at, I A'> r: / tFeR95 iR aR aGGYFate aRa timely maRReF YtiliziRg the ~ &1-

~

G2.4.17 Knowledge of EOP terms and definitions.I (CFR: 41.10 / 45.13) 3.9 51 emeF9eAsy PFeseal!Fes t PlaA: KAewlea9e ef epeFateF

~ FespeAse te less ef all aAAllAGiateFs {GP:R: 4~.rn t 43.5 t 46.43r-Knowledge of events related to system operation/status ~

G2.4.30 that must be reported to internal organizations or external 4.1 agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 / 43.5 / 45.11)

Emergency Procedures I Plan: Knowledge of SRO 901 G2.4.40 responsibilities in emergency plan implementation (CFR: 4.5 I 41.10 / 43.5 / 45.11). I I

Subtotal 2 21 Page 15 of 15 ES-401 Record of Rejected K/As Form ES-401-4

Tier/ Randomly Reason for Rejection Group Selected KIA 1/1 (1) 295038 EA2.02 Unable to develop an operationally valid test item for 295038EA2.02.

295038 EA2.04 randomly reselected as a replacement.

2/1 (3) 215004 K6.01 Unable to develop an operationally valid test item for 215004 K6.0l.

215004 K6.02 randomly reselected as a replacement.

1/1 (25) 295016.02.1.19 02.1.19 is oversampled (Questions 55, 60, 78) Randomly reselected 02.1.28 as a replacement.

2/1 (33) 262002A4.01 262002A4.01 is too similar to already sampled 262002.K4.0l. Since there are no other A4 items to sample. Randomly reselected 262002.Kl.06 as replacement.

1/2 (38) 295022AK3.02 Unable to develop an appropriately challenging test item to 295022AK3.02. Selected only other AK3 item, 295022AK3.01 as a replacement.

3 (51) 2.4.47 2.4.47 is oversampled (Question 80). Randomly reselected 2.4.17 as a replacement.

2/2 (52) 239003K4.01 239003 MSIV Leakage Control Systems not installed at Susquehanna.

Randomly reselected 201003 as replacement system and randomly selected K4.04.

2/1 (55) 23900202.2.4 No significant variations exist between unit 1 and 2 SRVs. Randomly reselected 239002.02.1.32 as replacement.

2/1 (56) 223002Al.03 Unable to develop a test question for 223 002A 1.03. Randomly reselected 223002 Al.02 as replacement.

1/1 (65) 295026EK2.0l Double Jeopardy with closely related KA 295013AK3.0l which is sampled on 08. Randomly reselected 295026.EK2.06 as replacement.

1/1 (70) 29502502.2.40 Unable to develop a RO level test item to 29502502.2.40. Randomly reselected 29502502.2.39 as a replacement.

2/1 (72) 217000K 1.04 Not applicable to the station. Randomly reselected 217000.Kl.03 as a replacement.

2/2 (73) 241000K6.16 Not applicable to the station. Randomly reselected 241 000.K6.12 as a replacement.

2/1 (74) 212000K5.01 Unable to develop a test item to 212000K5.0l. Selected the only remaining knowledge in K5, 212000.K5.02 as a replacement.

3 (77) 02.3.11 02.3.11 is oversampled (Q23). Randomly reselected 02.3.4.

3 (78) 02.1.19 02.1.19 is oversampled (Questions 25, 55, 60), randomly reselected 02.1.40 from 02.1 items.

3 (84) 02.4.32 There is no procedure for Loss of All Annunciators. Randomly reselected 02.4.30 as a replacement.

1/2 (87) 29501402.4.2 02.4.2 is oversampled. (Question 29). Randomly selected 02.4.41 as a replacement.

2/2 (91) 290002A2.06 Safety Limits already tested on Q22. Randomly reselected 290002.A2.05 as a replacement.

ES-401 Record of Rejected K/As Form ES-401-4

1/1 (92) 295019G2.4.9 Unable to develop a question to 295019.G2.4.9. Randomly reselected 295019.G2.4.35 as a replacement.

1/1 (96) 295030G2.4.3 G2.4.3 is oversampled (Sampled on Q9). Randomly reselected G2.4.6 as a replacement.

2/1 (97) 263000G2.4.6 Unable to develop a test item to 263000G2.4.6. Randomly reselected 2.4.4 as a replacement.

1/1 (10) 29500 lAAl.08 Unable to develop a test item to 295001AA1.08. Randomly reselected 295001AA1.05 as a replacement.

1/1 (27) 295030G2.2.12 G2.2.12 is oversampled (Sampled on QlO0). Randomly reselected G2. l.20 as a replacement.

1/2 (36) 295033EK1.03 Unable to develop a test item to 295033EK1.03. Reselected 295033EK1.02 as a replacement.

2/1 (45) 259002A3.07 Not applicable to the station. Randomly reselected 259002A3.06 as a replacement.

2/1 (46) 259002K2.02 Not applicable to the station. Since no other K2 with greater than 2.5 importance, randomly reselected 259002Kl.08 as a replacement.

2/1 (2) 261000Al.07 Unable to develop an appropriately challenging test item to 261000Al.07.

Randomly reselected 261000Al.02 as replacement.

2/1 (29) 263000K6.02 Unable to develop an an appropriately challenging test item to 263000A3.0l. Since A3.0l is the only A3 Item Randomly reselected 263000.K6.02 as a replacement.

1/2 (36) 295033EK1.03 Unable to develop a test item to 295033EK1.02. Reselected 500000 as a replacement since unable to develop test item to any 295033EK1 topics.

500000EK1.01 selected as a replacement.

2/2 (79) 268000G2.2.3 7 Unable to develop a safety related question for Radwaste (268000).

Randomly reselected 201001 as a replacement system.

1/2 (36) 500000EK1.01 Unable to develop a test item to reselected 500000EK1.0l. Randomly selected new category, as 500000EK1 contained only one topic. New KA is 500000EK2.03.

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