ML051890094

Final Outlines (Folder 3)

ML051890094
Person / Time
Site:	Crane
Issue date:	03/24/2005
From:	Olive H AmerGen Energy Co
To:	D'Antonio J Operations Branch I
Conte R
References
Download: ML051890094 (9)

Text

March 24,2005 Joe DAntonio US NRC Region I 475 Allendale Road King of Prussia PA 19406 Attached are the applicable pages for the sample plan items that have been revised since the original submittal along with a summary page.

Sincerely, Howard K Olive II TMI Facility Representative

TMI 2005 NRC EXAMINATION SAMPLE PLAN CHANGES 0

Change Simulator JPM ES-301-2.d to: Initiate a natural circulation cooldown using the OTSG Atmospheric Dump Valves (ADV). Reason:

The original JPM (take corrective action for a failure of the Main Generator to trip) could not be validated. A plant design change provides a backup method to reverse power sensing in order to ensure the generator breakers open following a turbine trip. There is no simulator malfunction that can prevent the generator breakers from opening.

0 Minor change to Simulator JPM ES-301-2.f: Change voltage malfunction to frequency malfunction. Reason: Avoid leaving then returning to the control room to complete the JPM. SBO Diesel Generator voltage must be adjusted locally but frequency can be adjusted from the control room.

Written Examination WA 073 K5.03 changed to 073 K3.01. Reason: A question with an answer that is verifiable against plant references could not be developed using the original WA.

0 Written examination WA 022 A2.01 changed to 022 A2.06. Reason: An RO-level question could not be developed using the original WA.

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Facility:

Three Mile Island Date of Examination:

05/09/2005 Exam Level (circle one):

RO / SRO( I) I SRO (U)

Operating Test No.:

Type Code*

p, s System / JPM Title Transfer the Group 6 control rods from the Auxiliary Power Supply to the Normal Power Supply in accordance with (IAW)

OP-TM-622-451, Transferring Rods to Auxiliary Power Supply.

APE 003 AA1.02 (3.6 13.4)

I Initiate HPllLPl IAW OP-TM-EOP-010, Emergency Rules Guides and Graphs, Guide 2 - HPVLPI initiation.

006 A4.07 (4.4 14.4)

I Place the Decay Heat Removal (DHR) System in operation and establish a cooldown in accordance with OP-TM-212-111, Shifting DHR Train A from DHR Standby to DHR Operating Mode.

005 A4.01 (3.6 / 3.4)

Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

d. Initiate a natural circulation cooldown using the OTSG 041 A4.06 (2.913.1)

Initiate RB Emergency Cooling with RR-P-1A and the A Cooler IAW 1104-38, Reactor Building Emergency Cooling Water System.

022 A4.04 (3.1 13.2)

A, N, S Atmospheric Dump Valves (ADV).

A, D, s Energize 1C 4160V Bus using the SBO Diesel IAW OP-TM 864-901, Loss of Station Power.

APE 056 AA2.37 (3.7 13.3)

A, D, S Reset RPS Channel A IAW OP-TM-641-421, Tripping and Resetting RPS Channels.

012 A4.04 (3.3 13.3)

NIA (SRO-I Candidates)

Safety Function 1

2 4P 4s 5

6 7

NUREG-I 021, Revision 9

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Type Codes In-Plant Systems* (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

Criteria for RO I SRO-I I SRO-U I

P,E Respond to a loss of "A" DC Distribution IAW 1202-9A, Loss of

" A DC.

i. I System 063 KIA 2.1.30 (3.9 13.4)

N, R Terminate an approved waste gas release IAW 1102-27, Waste Disposal - Gaseous, due to an unexplained pressure drop in a tank not being released.

System 071 WA2.1.30 (3.9 13.4) 6 9

Establish 81h stage heating following a reactor trip IAW OP-TM-421-102, Placing 8th Stage Feedwater String A In Service.

System 071 K/A 2.1.30 (3.9 13.4)

k.

4s I

All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 14-6 12-3 91 a / 4 11 I/ 1 1 1 1 / 1 21 21 1 3 I 3 I 2 (randomly selected) 11 11 1 NUREG-1021, Revision 9

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

a. Transfer the Group 6 control rods from the Auxiliary Power Supply to the Normal Power Supply in accordance with (IAW) OP-TM-622-451, Transferring Rods to Auxiliary Power Supply. Randomly selected repeat from the 2001 NRC Examination (B.l.c). (BANK JPM 013)

b. Initiate HPVLPI IAW OP-TM-EOP-010, Emergency Rules Guides and Graphs, Guide 2 HPVLPI initiation. Alternate Path: ESAS actuation required at the component level.

(BANK JPM 165)

c. Place the Decay Heat Removal (DHR) System in operation and establish a cooldown IAW OP-TM-212-111, Shifting DHR Train A from DHR Standby to DHR Operating Mode.

Candidate will place one loop of DHR in service for a normal plant cooldown. (Modified BANK JPM 01 5 to include cooldown initiation)

d. Initiate a natural circulation cooldown using the OTSG Atmospheric Dump Valves (ADV).

Alternate Path: ADV fails to respond to signals from normal control - candidate must utilize backup loader controller. (NEW JPM)

e. Initiate RB Emergency Cooling with RR-P-1A and the A Cooler IAW 1104-38, Reactor Building Emergency Cooling Water System. Respond to rising containment temperature caused by a small steam leak. Alternate Path: MANUAL control of cooling water pressure. (BANK JPM 079)

Energize 1C 4160V Bus using the SBO Diesel Generator (DG) IAW OP-TM 864-901, Loss of Station Power. Initial conditions place the candidate at the point for energizing 1C 4160V Bus. The candidate must open major load breakers, start the SBO DG, energize 1C 4160V Bus, energize 1 J 480V Bus and start GN-P-1 (Seal Oil Pump).

Alternate Path: MANUAL control of the SBO DG frequencyktart GN-P-1. (BANK JPM 131)

g. Reset RPS Channel A IAW OP-TM-641-421, Tripping and Resetting RPS Channels.

Given the plant in a stable condition following a reactor trip, the candidate will reset RPS Channel A. (BANK JPM 124)

h. Not required - only SRO(I) candidates on this examination.

i. Respond to a loss of A DC Distribution IAW 1202-9A, Loss of A DC. Perform the immediate actions of 1202-9A at the Emergency Diesel Generator. Randomly selected repeat from the 2001 NRC Examination (B.2.b). (BANK JPM 067)

Terminate an approved waste gas release IAW 1 104-27, Waste Disposal - Gaseous, due to an unexplained pressure drop in a tank not being released. While completing for a waste gas release, the candidate will be cued that pressure is lowering in a tank not being released. (NEW JPM)

k. Establish 8 stage heating following a reactor trip IAW OP-TM-421-102, Placing 8h Stage Feedwater String A In Service. Perform the local actions to place 8h Stage Feedwater String A in service. (BANK JPM 099)

f.

j.

NUREG-1021, Revision 9

ES-401 PWR Examination Outline Form ES-401-2

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Note:

1

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Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

4.

5.

2.

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

Absent a plant specific priority, only those 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.

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 ES-401, Attachment 2, for guidance regarding elimination of inappropriate K/A statements.

II I 6. I Select SRO toDics for Tiers 1 and 2 from the shaded svstems and K/A categories.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.

On the following pages, enter the K/A 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. Use dudicate Daaes for RO and SRO-onlv exams.

9 For Tier 3, select topics from Section 2 of the WA Catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10CFR55.43 NUREG-1021 1

I ES-401 Three Mile Island PWR Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 1 System #/Name

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Knowledge of the operational implications of the Constant enthalpy expansion through a valve Separation of control and protection circuits following concepts as the apply to the PZR PCS:

Knowledge of RPS design feature(s) andlor interlock(s) 2.6 10 2,8 11

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Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct. control, or mitigate the consequences of those malfunctions or operations: Highllow surge tank level 3.2 9

008 Component Cooling Water 01 0 Pressurizer Pressure Control X

012 Reactor Protection X

X Knowledge of ESFAS design feature(s) andlor interlock(s) which provide for the following MFW isolationlreset Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or ooerations: Loss of CCS PumD 12 013 Engineered Safety Features Actuation 3.7 2.8 022 Containment Cooling Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: Containment pressure 3.6 14 Al.02 022 Containment Cooling 026 Containment Spray Ability to monitor automatic operation of the CSS.

including: Pump starts and correct MOV positioning Knowledge of the physical connections andlor cause-effect relationships between the CSS and the following systems: ECCS A3.01 K1.01 026 Containment Spray X

X 1

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A2 01 Ability to (a) predict the impacts of the following mal-functions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Flow paths of steam during a LOCA X

3.1 17 039 Main and Reheat Steam E

Conduct of Operations: Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to corred, control, or mitigate the consequences of those malfunctions or operations: Startup of MFW pump during AFW operation 18 2.1.23 3.9 2.5 059 Main Feedwater 061 AuxillarylEmergency Feedwater 19 A2.01 7

NUREG-1021

ES-401 Three Mile Island PWR Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2 Group 1 Ability to predict andlor monitor changes in parameters operating the ANV controls including: SlG level Al.01 (to prevent exceeding design limits) associated with 3.9 Form ES-401-2 K4.03 A3.01 Knowledge of ac distribution system design feature(s) andlor interlock(s) which provide for the following:

Interlocks between automatic bus transfer and breakers Abiltty to monitor automatic operation of the dc electrical system, including: Meters, annunciators, dials, recorders. and indicatina liahts 2.8 2.7 Abillty to predict and/or monitor changes in parameters Al

.ol 2.5 associated with operating the dc electrical system controls including: Battery capactty as it is affected by discharge rate K6.07 K3.01 Knowledge of the effect of a loss or malfunction of the following will have on the EDlG system: Air receivers Knowledge of the effect that a loss or malfunction of the PRM system will have on the following: Radioactive effluent releases.

2.7 3.6

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Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based A2.01 on those predictions, use procedures to correct, control, 3.5 or mitigate the consequences of those malfunctions or operations: Loss of SWS Kl.04 A4 04 Knowledge of the physical connections andlor cause-effect relationships between the IAS and the following systems: Cooling water to compressor Ability to manually operate andlor monitor in the control room: Phase A and phase B resets 2.6 3.5 Group Point Total: 1 20 21 22 23 24 26 27 28 2815 NUREG-I021 8

I ES-401 Reason for Rejection Tier /

Randomly Group Selected K/A 2 / 1 059 12.4.30 It isn't possible to prepare a psychometrically sound question related to the subiect WA.

Record of Rejected WAS

[ Form ES-401-4 1 I 2 / 1 I 003 / K4.11 I The subject WA isn't relevant at the subject facility.

2 / 1 2 / 1 004 / K2.07 006 / K4.02 The subject KIA isn't relevant at the subject facility.

Double jeopardy with audit exam item r

2 / 1 2 / 1 007 / A4.01 026 / A3.02 The subject WA isn't relevant at the subject facility.

The subject WA isn't relevant at the subject facility.

2 / 1 2 / 1 2 I 1 2 / 1 059 / 2.1.30 061 / Al.03 073 / A2.01 078 / K1.03 Topic better suited for In-Plant JPM The subject WA isn't relevant at the subject facility.

Double Jeopardy with audit exam question The subject WA isn't relevant at the subject facility.

2 / 1 211 001 / K2.02 086 12.4.6 Double jeopardy with question 29.

The subject KIA isn't relevant at the subject facility.

I 2 / 2 I 028 / K1 F l T h e s u b j e Z WA isn't relevant at the subject facility.

3 I 3 I G3 12.3.6 I Double jeopardy with audit exam JPM It isn't possible to prepare a psychometrically sound question related to the subject K/A.

It isn't possible to prepare a psychometrically sound question related to the subject K/A.

G4 2.4'21 025 2'4.4 314 111 1 / 1 I 027 I AA2.13 1 The subject KIA isn't relevant at the subject facility 1 / 1 I 025 / AK2.01 I Double jeopardy with question 5 It isn't possible to prepare a psychometrically sound question related to the sub.ect K/A, It isn't possible to prepare a psychometrically sound question related to the sub.ect K/A.

It isn't possible to prepare a psychometrically sound question related to the sub.ect K/A.

1 12 028 I AA2.06 1 12 059 I AA2.03 1 I 2 A07 I 2.1.23

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It isn't possible to prepare a psychometrically sound question related to the sub.ect K/A, 1 / 2 103 / 2.4.49 2 12 1 071 I A2.03 I System over sampled It isn't possible to prepare a psychometrically sound question related to the sub.ect K/A, 073 I K5.03

( 2 / 1 1 I 022 I A2.01 I Question matching K/A could not be written for the RO level.

NUREG-1021 11