ML031190755

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Final - Outlines (Change Summaries - Optional)
ML031190755
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 04/01/2003
From: Wilson F
Entergy Nuclear Northeast
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-247/03-301
Download: ML031190755 (38)
v • d • e


Text

IP2 written changes. 2/10/03 Q17 Check to see if appealable based on fact that SDB is not usually moved at power.

SME says okay Q. No change. SUBSEQUENTLY REPLACED Q19 Made changes on distractor wording. SUBSEQUENTLY REPLACED Q23 Checked Double Jeopardy with JPM P3. Deemed okay.

Q24 Check if air start in some way could be considered and cause 2 correct answers.

SME says Q okay. Enhanced distractors A and B Q28 Discuss with SRO. Discriminatory? Modified question to raise discriminatory level as per SRO SME suggestion Q31 Check KA match. Can recorders be used to check Ctmt pressure for recombiner operation? Yes, but recombiners not used in that way anymore. Talk to Chief Examiner, possibly keep Question for different topic. Put actual KA on topic, makes it 013 A4.03. This will keep the ES-401-4 criteria to within the +/- 1 limit on each outline. Tier 2 Group 1 for RO and SRO will have 1 item more than required. Tier 2 Group 2 for SRO and tier 2 Group 3 for RO will have 1 item less than required.

Q32 Added information to distractor C to make symmetrical.

Q44 Added information to A to clarify R79 Changed A to clarify and remove chance of partial correct.

R82 Too easy. Made more difficult by requiring knowledge of additional sources.

R83 Question about pump auto start. Whether D would be a correct answer. Joe D had comments, check with him. Did not update. Check with Chief Examiner.

Added clarifying information to explanation and checked with SRO SME to check validity of question. Says okay R84 Replaced based on IP3 review comment (Common between plants.) Used new KA and developed new question R93 Look at, maybe C is correct. Yes, changed answer key.

R97 Question may not have good discriminatory value. Maybe make like IP3 question. Will modify R99 See if expert thinks too easy. Possible replace with PSP. SME does not think too easy. No change

S73 Minor enhance S75 See expert to see if good SRO question. Possible replace if not SRO. Replaced with new topic, same generic KA. Changed system. Used significantly modified facility bank question S76 Simple theory, not SRO? We did not take credit for. No change necessary S81 Direct lookup? Change procedural conditions, give whole procedure as a reference.

S84 Simple theory, not SRO. We did not take credit for SRO. No change.

S85 Does not like the question. Change KA and get a new SRO question. Replaced with new topic 2.4.4 and Vendor Bank question previously used on NRC exam S86 Who is actually responsible, HP or an SRO? SME says to replace. Replaced with new KA topic 2.4.6, used vendor bank question previously used on NRC exam S97 Minor enhance S99 Minor enhance distractor B S100 Changed distractors to be more plausible. Made change to test item, changed correct answer after Audit exam review revealed item too close to item on Audit exam IP2 Written changes completed 2/27/2003 Cl Modified stem to change answer C2 Changed all distractors and correct answer C3 Changed conditions in stem to change correct answer C4 Changed question. Used Vendor Bank question C5 Changed question. Used Vendor Bank question C6 Changed question. Used Vendor Bank question C7 Changed conditions and distractors to yield different answer C8 Changed question. Used Modified Facility Bank question

C9 Changed question. Developed new question CI 0 Changed conditions to change answer ClH Changed context of question, same topic C12 No change necessary, item NOT compromised C13 Changed question based on NRC feedback from IP3. This item was NOT compromised and was not replaced with the 2/27 changes.

C14 Changed conditions to change answer C15 Changed context. Same topic C16 Changed correct answer to another selection C 17 Changed question. Used Modified Facility Bank question C 18 Changed question. Changed context same topic C 19 Changed conditions to change correct answer C20 Changed conditions to change correct answer C21 Changed conditions and distractors to change correct answer C22 Changed context. Same topic C23 No change required. Item NOT compromised C24 No change required. Item NOT compromised C25 Changed question. New KA topic selected, used Vendor Bank question

Initial NRC License Examination Indian Point Unit 2 Written Test Item Summary Senior Reactor Operator Question K/A Source Cognitive Comments 1 003 A3.04 New Higher 2 003 K4.04 Bank Higher 3 004 K6.17 Bank Higher 4 013 Al.01 Bank Memory 5 015 K5.02 Bank Higher 6 017 A4.01 Bank Memory 7 022 A4.04 New Memory 8 059 K4.19 Modified Higher 9 059 A4.03 New Memory 10 061 K6.02 Bank Higher 11 071 K5.04 Modified Memory 12 072 A3.01 New Memory 13 006 K2.04 Modified Higher 14 010 A3.02 New Higher 15 0 1K2.02 New Memory 16 012 K5.01 Bank Memory 17 014 A4.01 Modified Higher 18 026 Al.01 New Memory 19 033 A2.02 New Higher 20 035 G2.4.4 New Higher 21 039 KI.06 Bank Higher 22 055 K3.01 Modified Higher 23 063 K1.03 New Memory 24 063 K3.02 Bank Higher 25 064 A1.08 Bank Higher 26 062 K1.03 Bank Higher 27 012 G2.4.12 New Memory 28 079 K1.01 New Higher 29 086 K4.07 Bank Memory 30 005 A2.02 Modified Higher 31 013 A4.02 New Memory 32 034 K4.02 New Memory 33 041 A3.03 New Higher 34 G2.1.8 Bank Memory 35 G2.2.13 Bank Memory 36 G2.2.33 Modified Higher 37 G2.2.2 Modified Higher 38 G2.3.9 New Memory 39 G2.4.19 New Memory 40 G2.4.29 Bank Memory 41 005 AK1.03 Bank Higher 42 E09 EK3.1 Bank Memory 43 024 AA2.04 Bank Higher 44 026 AK3.03 Bank Memory 45 027 AA2.15 New Higher 46 040 AK1.06 Bank Higher 47 040 EA1.2 Bank Memory 48 051 AA1.04 Bank Higher 49 055 EA2.01 Bank Higher 50 057 AK3.01 New Higher Confidential Page 1 2/28/2003 Final Draft

Initial NRC License Examination Indian Point Unit 2 Written Test Item Summary Senior Reactor Operator 51 062 AA2.01 Bank Higher 52 015/017 AA1.22 Bank Higher 53 074 EK1.05 Modified Higher 54 074 EK1.3 Modified Memory 55 075 EA1.2 Bank Memory 56 076 AA2.02 Bank Memory 57 001 AA1.05 New Memory 58 003 AK2.05 New Higher 59 008 AK2.02 Bank Higher 60 009 EA118 New Higher 61 O11EA1.01 Modified Memory 62 EO1/EO2 EK3.2 Bank Memory 63 022 AA1.08 Bank Higher 64 025 AA2.07 Bank Memory 65 054 G2.4.2 Bank Higher 66 065 G2.1.2 New Memory 67 058 AA2.03 Modified Memory 68 061 AA1.01 Bank Higher 69 038 EK3.01 Bank Memory 70 028 AK3.02 New Higher 71 036 AA2.51 New Higher 72 054 G2.2.25 New Memory SRO 73 001 A2.03 Bank Higher SRO 74 056 A2.04 New Higher SRO 75 003 G2.4.31 Bank Higher SRO 76 016 G2.1.28 Bank Higher 77 062 G2.1.33 New Higher SRO 78 008 A2.02 New Higher SRO 79 078 G2.1.23 New Higher SRO 80 G2.1.11 Bank Higher SRO 81 G2.1.20 Modified Higher SRO 82 G2.2.6 New Memory SRO 83 G2.2.22 Bank Memory SRO 84 G2.2.34 Bank Higher 85 G2.4.4 Bank Higher SRO 86 G2.4.6 Bank Higher SRO 87 G2.4.45 Bank Higher SRO 88 G2.4.24 New Higher SRO 89 G2.4.12 Bank Memory SRO 90 E09 G2.4.50 Bank Higher SRO 91 029 EA2.02 New Higher SRO 92 E08 EA2.1 Bank Higher SRO 93 059 AA2.02 New Memory SRO 94 069 AA2.02 Bank Higher SRO 95 007 G2.1.14 New Higher SRO 96 E03 EA1.02 Bank Higher 97 033 AA2.10 New Higher SRO 98 037 G2.2.22 Modified Higher SRO 99 E11 EK1.2 Bank Higher 100 036 G2.2.28 Bank Higher SRO Confidential Page 2 2/28/2003 Final Draft

ES-401 Written Examination Form ES-401-7 Quality Checklist Facility: IP2 Date of Exam: 3/15/2003 Exam level: RO Item Description Initial

1. Questions and answers technically accurate and applicable to the facility _ _
2. NRC K/As referenced for all questions Facility learning objectives referenced as available 0z4 .
3. RO/SRO Overlap is no more than 75%, and SRO questions are appropriate per Section D.2.d of ES-401 Gh
4. Question selection and duplication from the last 2 NRC licensing exams appears to be consistent with a systematic sampling process AW
5. Question duplication from the license screeninglaudit exam was controlled as indicated below (check the item that applies and appears appropriate:

. The audit exam was systematically and randomly developed; or

. The audit exam was completed before the license exam was started; or

  • The examinations were developed independently; or

. The licensee certifies that there is no duplication: or

  • Other (explain)
6. Bank use meets limits (no more than 75% from the bank Bank Modified New and at least 10 new, and the rest modified); enter the actual question distribution at right 50 18 32 Jv h
7. Between 50 and 60 percent of the questions on the exam Memory C/A (including 10 new questions) are written at the comprehension/analysis level; enter the actual question 47 X distribution on the right
8. References/handouts do not give away answers
9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are ,

justified HAi-&

10. Question psychometric quality and format meet ES, Appendix B, guidelines
11. The exam contains 100, one-point, multiple choice items; the total is correct and agrees with value on cover sheet Printed Name/Signature Date a.Author c-SEP/J 6 ,5c zz,
b. Facility Reviewer(*) / a
c. Chief Examiner (#)
d. NRC Regional Supervisor Note: ^ The facility reviewer's initial/signature are not applicable for NRC-developed examinations
  1. Independent NRC reviewer initial items in column 'c', Chief Examiner concurrence required NUREG-1021, Revision 8, Supplement 1

Initial NRC License Examination Indian Point Unit 2 Written Test Item Summary Reactor Operator Question K/A Source Cognitive Comments 1 003 A3.04 New Higher 2 003 K4.04 Bank Higher 3 004 K6.17 Bank Higher 4 013 Al.01 Bank Memory 5 015 K5.02 Bank Higher 6 017 A4.01 Bank Memory 7 022 A4.04 New Memory 8 059 K4.19 Modified Higher 9 059 A4.03 New Memory 10 061 K6.02 Bank Higher 11 071 K5.04 Modified Memory 12 072 A3.01 New Memory 13 006 K12.04 Modified Higher 14 010 A3.02 New Higher 15 011 K2.02 New Memory 16 012 K5.01 Bank Memory 17 014 A4.01 Modified Higher 18 026 A1.01 New Memory 19 033 A2.02 New Higher 20 035 G2.4.4 New Higher 21 039 K1.06 Bank Higher 22 055 K3.01 Modified Higher 23 063 K1.03 New Memory 24 063 K3.02 Bank Higher 25 064 A1.08 Bank Higher 26 062 K1.03 Bank Higher 27 012 G2.4.12 New Memory 28 079 K1.01 New Higher 29 086 K4.07 Bank Memory 30 005 A2.02 Modified Higher 31 013 A4.03 New Memory 32 034 K4.02 New Memory 33 041 A3.03 New Higher 34 G2.1.8 Bank Memory 35 G2.2.13 Bank Memory 36 G2.2.33 Modified Higher 37 G2.2.2 Modified Higher 38 G2.3.9 New Memory 39 G2.4.19 New Memory 40 G2.4.29 Bank Memory 41 005 AK1.03 Bank Higher 42 E09 EK3.1 Bank Memory 43 024 AA2.04 Bank Higher 44 026 AK3.03 Bank Memory 45 027 AA2.15 New Higher 46 040 AK 1.06 Bank Higher 47 040 EA1.2 Bank Memory 48 051 AAI.04 Bank Higher 49 055 EA2.01 Bank Higher 50 057 AK3.01 New Higher Confidential Page 1 2/28/2003 Final Draft

Initial NRC License Examination Indian Point Unit 2 Written Test Item Summarv Reactor Operator 51 062 AA2.01 Bank Higher 52 015/017 AA1.22 Bank Higher 53 074 EK1.05 Modified Higher 54 074 EK1.3 Modified Memory 55 075 EA1.2 Bank Memory 56 076 AA2.02 Bank Memory 57 001 AA1.05 New Memory 58 003 AK2.05 New Higher 59 008 AK2.02 Bank Higher 60 009 EA1.18 New Higher 61 011 EAL.01 Modified Memory 62 E01/E02 EK3.2 Bank Memory 63 022 AA1.08 Bank Higher 64 025 AA2.07 Bank Memory 65 054 G2.4.2 Bank Higher 66 065 G2.1.2 New Memory 67 058 AA2.03 Modified Memory 68 061 AA.01 Bank Higher 69 038 EK3.01 Bank Memory 70 028 AK3.02 New Higher 71 036 AA2.51 New Higher 72 032 AA2.04 New Higher 73 001 K4.02 Bank Higher 74 004 K5.19 Modified Higher 75 013 A2.01 Modified Higher 76 015 K4.03 Bank Memory 77 017 Kl.01 Modified Higher 78 001 A3.05 Bank Higher 79 056 G2.1.2 New Memory 80 061 K4.04 Bank Memory 81 068 A3.02 Bank Memory 82 068 K1.07 Bank Memory 83 056 K1.03 New Memory 84 002 K4.02 Modified Higher 85 016 K3.04 Bank Higher 86 029 A1.02 New Memory 87 076 K3.07 Bank Higher 88 045 A1.06 Bank Higher 89 076 K2.01 New Memory 90 008 K3.01 Modified Higher 91 G2.1.2 Bank Memory 92 G2.2.12 Bank Memory 93 G2.1.18 New Memory 94 G2.3.4 Bank Memory 95 G2.4.14 Bank Higher 96 G2.4.34 Modified Memory 97 E04 EK1.3 Bank Higher 98 EOI/EO2 EA2.2 Bank Memory 99 058 AK3.02 New Memory 100 E05 G2.4.6 Bank Higher Confidential Page 2 2/28/2003 Final Draft

ES-401 PWR SRO Examination Outline Form ES-401-3 Facility: Indian Point Units 2 & 3 Date of Exam: 3/8/2003 Exam Level: SRO l K/A Category Point Point Tier Group K K K K K K A A A A G Total

_ 2 3 4 _ 6 1 -- 43 4 1 1 4 1 4 6 8 1 24 Emergency & 2 1 1 1 4 4 5 16 Abnormal Plant 3 0 0 1 0 1 1 3 Evolutions . l Totals 5 2 6 10 13 7 43

2. 1 1 0 1 2 2 2 2 2 2 5 1 20*

Plant 2 3 2 1 2 1 0 1 1 1 0 4 16*

Systems 3 0 0 0 00 0 2 10 1 4 Tier 4 2 2 4 3 2 3 5 4 5 6 4

__ _ _ Totals 42 4 3 3 5 5 1 4

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 3 6 1 7 417 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A 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 exam must total 100 points.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/A's below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
  • See Note 2 Above Page 1 of 14 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR SRO Examination Outline Form ES-401-3 Facility: Indian Point Units 2 & 3 Date of Exam: 3/8/2003 Exam Level: SRO

[ K/A Category Point Point Tier Group K K K K K K A A A A G Total

_ l 2 3 4 5 6 1 l2 3 4

  • 1 4 1 4 _ 6 8 1 24
1. _ _

Emergency & 2 1 1 1 4 4 = 5 16 Abnormal Plant 3 0 0 1 0 1 1 3 Evolutions Tier Totals 5 2 6 10 13 7 43 1 1 0 1 2 2 2 2 2 25 1 20*

Plant 2 3 2 1 2 1 0 1 1 1 0 4 16*

Systems 3 0 00 0 0 002 1 0 1 4 Systems Totals 4 2 2 4 3 2 3 5 4 5 6 40

3. Generic Knowledge and Abilities Cat 1 lCat2 Cat3 lCat4 1 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the "Tier Totals" in each K/A 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 exam must total 100 points.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/A's below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
  • See Note 2 Above Page 1 of 14 NUREG-1021, Revision 8, Supplement 1

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE #Name I Safety Function I1 lK2 K3 Al A2 G Number K/A Topic(s) Imp. Q#

000001 / Continuous Rod Withdrawal / 1 X AA1.05 Ability to operate and / or monitor the following as they apply to 4.2 57 the Continuous Rod Withdrawal: Reactor trip switches.

000003 / Dropped Control Rod / 1 x AK2.05 Knowledge of the interrelations between the Dropped Control 2.8 58 Rod and the following: Control rod drive power supplies and logic circuits.

000005 / Inoperable/Stuck Control Rod / I X AK1.03 Knowledge of the operational implications of the following 3.6 41

.. __ .___..___ concepts as they apply to the stuck rod: Xenon transient.

000011 / Large Break LOCA / 3 X EA1.01 Ability to operate and monitor the following as they apply to a 3.8 61 Large Break LOCA: Control of RCS pressure and temperature to avoid violating PTS limits.

W/E04 / LOCA Outside Containment / 3 W/EO1 & E02 / Rediagnosis & SI Termination! 3 X EK3.2 Knowledge of the reasons for the following responses as they 3.9 62 apply to the (Reactor Trip or Safety Injection/Rediagnosis):

Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection/Rediagnosis).

000015 / 17 RCP Malfunctions /4 X AA1 .22 Ability to operate and/or monitor the following as they apply to 4.2 52 the RCP malfunctions: RCP seal failure/malfunction BW/E09; CE/Al 3; W/E09 & El0 / Natural Circ. / 4 X EK3.1 Knowledge of the reasons for the following responses as they 3.6 42 apply to the (Natural Circulation Operations): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.

BW/E09; CE/A13; W/E09 & El0 Natural Circ. /4 X 2.4.50 Emergency Procedures/Plan: Ability to verify system alarm 3.3 90 setpoints and operate controls identified in the alarm response manual.

000024 / Emergency Boration / 1 X AA2.04 Ability to determine and interpret the following as they apply to 4.2 43 the Emergency Boration: Availability of BWST.

000026 / Loss of Component Cooling Water / 8 X AK3.03 Knowledge of the reasons for the following responses as they 4.2 44 apply to the Loss of Component Cooling Water: Guidance and actions contained in EOP for Loss of CCW/nuclear service water.

000029 / Anticipated Transient w/o Scram / I X EA2.02 Ability to determine or interpret the following as they apply to 4.4 91 ATWS: Reactor trip alarm.

000040 (BW/E05; CE/E05; W/E1 2) / Steam Line X AK1.06 Knowledge of the operational implications of the following 3.8 46 Rupture - Excessive Heat Transfer / 4 ^ concepts as they apply to Steam Line Rupture: High-energy steam line break considerations.

000040 (BW/E05; CE/E05; W/E1 2) / Steam Line X EA1 .2 Ability to operate and/or monitor the following as they apply to 3.7 47 Rupture - Excessive Heat Transfer / 4 the (Uncontrolled Depressurization of all Steam Generators):

Operating behavior characteristics of the facility.

NUREG-1021, Revision 8, Supplement 1 Page 2 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE #Name / Safety Function KI K2 K3 A A2 lG Number KIATopic(s) Imp. l Q#

CE/Al1; W/E08 / RCS Overcooling - PTS / 4 X EA2.1 Ability to determine and interpret the following as they apply to 4.2 92 the (Pressurized Thermal Shock): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

000051 / Loss of Condenser Vacuum / 4 X AA1.04 Ability to operate and / or monitor the following as they apply to 2.5 48 the Loss of Condenser Vacuum: Rod position.

000055/ Station Blackout /6 X EA2.01 Ability to determine or interpret the following as they apply to a 3.7 49 Station Blackout: Existing valve positioning on a loss of instrument air system.

000057 / Loss of Vital AC Elec. Inst. Bus / 6 X AK3.01 Knowledge of the reasons for the following responses as they 4.4 50 apply to the Loss of Vital AC Instrument Bus: Actions contained

__ in EOP for loss of vital AC electrical instrument bus.

000059 / Accidental Liquid Radwaste Rel. / 9 X AA2.02 Ability to determine and interpret the following as they apply to 3.9 93 the Accidental Liquid Radwaste Release: The permit for liquid l _ __ radioactive-waste release.

000062 / Loss of Nuclear Service Water / 4 X AA2.01 Ability to determine and interpret the following as they apply to 3.5 51 the Loss of Nuclear Service Water: Location of a leak in the

_ _ __ _ _ _ _ __ _ __ _ _ _ __ _ _ _ _C_ _ CW S.

000067 / Plant Fire On-site / 9 000068 (BW/A06) / Control Room Evac. /8 000069 (W/E14) / Loss of CTMT Integrity / 5 X AA2.02 Ability to determine and interpret the following as they apply to 4.4 94 the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity.

000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EK1.05 Knowledge of the operational implications of the following 3.2 53 concepts as they apply to the Inadequate Core Cooling:

Definition of saturated liquid.

000074 (/E06 & E07) / Inad. Core Cooling /4 X EK1.3 Knowledge of the operational implications of the following 3.9 54 concepts as they apply to the (Degraded Core Cooling):

Annunciators and conditions indicating signals, and remedial I _ __ actions associated with the (Degraded Core Cooling). l 000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EA1.2 Ability to operate and/or monitor the following as they apply to 3.7 55 the (Saturated Core Cooling): Operating behavior characteristics of the facility.

BW/E03 / Inadequate Subcooling Margin / 4 000076 / High Reactor Coolant Activity / 9 X AA2.02 Ability to determine and interpret the following as they apply to 3.4 56 the High Reactor Coolant Activity: Corrective actions required

__ for high fission product activity in RCS.

BW/A02 & A03 / Loss of NNI-X/Y / 7 K/A Category Point Totals: 4 1 4 6 8 1 Group Point Total: 24 NUREG-1021, Revision 8, Supplement 1 Page 3 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 EIAPE #Name I Safety Function K1 K2 K3 Al A2 G Number K/A Topic(s) Imp, l G 000007 (BW/EO2 & El 0; CE/E02) / Reactor Trip - X 2.1.14 Conduct of Operations: Knowledge of system status criteria, 3.3 95 Stabilization - Recovery / 1 which require the notification of plant personnel.

BW/A0l / Plant Runback / 1 BW/A04 / Turbine Trip / 4 000008 / Pressurizer Vapor Space Accident / 3 X AK2.02 Knowledge of the interrelations between the Pressurizer Vapor 2.7 59 Space Accident and the following: Sensors and detectors.

000009 / Small Break LOCA / 3 X EAl .18 Ability to operate and monitor the following as they apply to a 3.2 60 small break LOCA: Balancing of HPI loop flows.

BW/E08; W/E03 / LOCA Cooldown - Depress. /4 X EA1.02 Ability to operate and/or monitor the following as they apply to 3.9 96 the (LOCA Cooldown and Depressurization): Operating behavior characteristics of the facility.

W/E1 1 / Loss of Emergency Coolant Recirc. /4 X EK1.2 Knowledge of the operational implications of the following 4.1 99 concepts as they apply to the (Loss of Emergency Coolant Recirculation): Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation).

000022 / Loss of Reactor Coolant Makeup / 2 X AA1.08 Ability to operate and/or monitor the following as they apply to 3.3 63 the Loss of Reactor Coolant Pump Makeup: VCT level.

000025 / Loss of RHR System / 4 X AA2.07 Ability to determine and interpret the following as they apply to 3.7 64 the Loss of Residual Heat Removal System: Pump cavitation.

000027 / Pressurizer Pressure Control System X AA2.15 Ability to determine and interpret the following as they apply to 4.0 45 Malfunction /3 the Pressurizer Pressure Control Malfunctions: Actions to be taken if PZR pressure instrument fails high.

000032 / Loss of Source Range NI / 7 000033 / Loss of Intermediate Range NI / 7 X AA2.10 Ability to determine and interpret the following as they apply to 3.8 97 the Loss of Intermediate Range NI: Tech Spec limits if both IR channels have failed 000037 / Seam Generator Tube Leak / 3 X 2.2.22 Equipment Control: Knowledge of limiting conditions for 4.1 98 operations and safety limits.

000038 / Steam Generator Tube Rupture / 3 X EK3.01 Knowledge of the reasons for the following responses as they 4.3 69 apply to the Steam Generator Tube Rupture: Equalizing pressure on primary and secondary sides of ruptured SG 000054 (CE/E06) / Loss of Main Feedwater / 4 X 2.4.2 Emergency Procedures/Plan: Knowledge of system setpoints, 4.1 65 interlocks, and automatic actions associated with EOP entry conditions 000054 (CE/E06) / Loss of Main Feedwater / 4 X 2.2.25 Equipment Control: Knowledge of bases in technical 3.7 72 specifications for limiting conditions for operations and safety limits.

BW/E04; W/E05 / Inadequate Heat Transfer -

Loss of Secondary Heat Sink / 4 I NUREG-1021, Revision 8, Supplement 1 Page 4 of 14

INDIAN POINT UNITS 2 & 3 1 ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE Name / Safety Function K1 K2 K3j AII A2 G Number K/A Topic(s) Imp. Q#

000058 / Loss of DC Power /8 X AA2.03 Ability to determine and interpret the following as they apply to 3.9 67 the Loss of DC Power: DC loads lost, impact on ability to operate and monitor plant systems 000060 / Accidental Gaseous Radwaste Rel. / 9 000061 / ARM System Alarms / 7 X AA1.01 Ability to operate and/or monitor the following as they apply to 3.6 68 the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation.

WIE16 / High Containment Radiation /9 000065/ Loss of Instrument Air / 8 X 2.1.2 Conduct of Operations: Knowledge of operator responsibilities 4.0 66 during all modes of plant operation.

CE / E09 / Functional Recovery I K/A Category Point Totals: 1 1 1 4 4 5 Group Point Total: 16 NUREG-1021, Revision 8, Supplement 1 Page5 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3

< Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE #I Name / Safety Function K l K2 K3 Al A2 G I NumberTl K/A Topic(s) Imp 000028 / Pressurizer Level Malfunction / 2 X AK3.02 Knowledge of the reasons for the following responses as they 3.2 70 apply to the Pressurizer Level Control Malfunctions:

Relationships between PZR pressure increase and reactor makeup/letdown imbalance.

000036 (BW/A08) / Fuel Handling Accident /8 X 2.2.28 Equipment Control: Knowledge of new and spent fuel 3.5 100 movement procedures 000056 / Loss of Off-site Power / 6 X AA2.51 Ability to determine and interpret the following as they apply to 3.4 71 the Loss of Offsite Power: AT, (core, heat exchanger, etc.)

BW/E13 & E14 / EOP Rules and Enclosures BW/A05 / Emergency Diesel Actuation / 6 CE/Al 6 / Excess RCS Leakage / 2 W/E1 3 / Steam Generator Over-pressure /4 W/E15 / Containment Flooding /5 I ._

K/A Category Point Totals: 0 0 1 0 1 1 Group Point Total:3 NUREG-1021, Revision 8, Supplement 1 Page 6 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System #I Name l Ki l K2 l K3 K4 K5 K6 lA A2 A3 A4 G Number K/A Topic(s) Imp. Q#

001 Control Rod Drive X A2.03 Ability to (a) predict the impacts of the following 4.2 73 malfunction or operations on the CRDS- and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of stuck rod or Misaligned rod.

003 Reactor Coolant Pump X A3.04 Ability to monitor automatic operation of the 3.6 1 RCPs, including: RCS flow.

003 Reactor Coolant Pump X K4.04 Knowledge of RCPs design feature(s) and/or 3.1 2 interlock(s) which provide for the following:

Adequate cooling of RCP motor and seals.

003 Reactor Coolant Pump X 2.4.31 Emergency Procedures / Plan: Knowledge of 3.4 75 annunciators alarms and indications, and use of the response instructions.

004 Chemical and Volume Control X K6.17 Knowledge of the effect of a loss or malfunction 4.6 3 of the following will have on the CVCS: Flow paths for emergency boration 013 Engineered Safety Features Actuation X A1.01 Ability to predict and/or monitor changes in 4.2 4 parameters (to Prevent exceeding design limits) associated with operating the ESFAS controls including: RCS pressure and temperature.

013 Engineered Safety Features Actuation X A4.03 Ability to manually operate and/or monitor in 4.7 31 the Control Room: ESFAS Initiation.

014 Rod Position Indication X A4.01 Ability to manually operate and/or monitor in 3.1 17 the control room: Rod selection control.

015 Nuclear Instrumentation X K5.02 Knowledge of the operational implications of 2.9 5 the following concepts as they apply to the NIS:

Discriminator/compensation operation.

017 In-Core Temperature Monitor X A4.01 Abilityto manually operate and/or monitor in 4.1 6 the control room: Actual in-core temperatures.

022 Containment Cooling X A4.04 Ability to manually operate and/or monitor in 3.2 7 the control room: Valves in the CCS.

025 Ice Condenser SUPPRESSED 026 Containment Spray X A1.01 Ability to predict and/or monitor changes in 4.2 18 parameters (to prevent exceeding design limits) associated with operating the CSS controls

_ __ . _including: Containment pressure.

NUREG-1021, Revision 8, Supplement 1 Page 7 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 System# / Name lK11 l 2 l3 1(4 lK5 lK6 Al A2 A3 A4 G Number KIA Topic(s) Imp. Q#

056 Condensate x A2.04 Ability to (a) predict the impacts of the following 2.8 74 malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps.

059 Main Feedwater X K4.19 Knowledge of MFW design feature(s) and/or 3.4 8 interlock(s), which provide for the following:

Automatic feedwater isolation of MFW.

059 Main Feedwater X A4.03 Ability to manually operate and monitor in the 2.9 9 control room: Feedwater control during power increase and decrease.

061 Auxiliary / Emergency Feedwater X K6.02 Knowledge of the effect of a loss or malfunction 2.7 10 of the following will have on the AFW components: Pumps.

063 DC Electrical Distribution X K3.02 Knowledge of the effect that a loss or 3.7 24 malfunction of the DC electrical system will have on the following: Components using DC control power.

063 DC Electrical Distribution X K1.03 Knowledge of the physical connections and/or 3.5 23 cause-effect relationships between the DC distribution system and the following systems:

_ __ Battery Charger and battery 068 Liquid Radwaste 071 Waste Gas Disposal X K5.04 Knowledge of the operational implication of the 3.1 11 following concepts as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.

072 Area Radiation Monitoring X A3.01 Ability to monitor automatic operation of the 3.1 12 ARM system, including: Changes in ventilation alignment.

K/A Category Point Totals: 1 0 1 2 2 2 2 2 2 5 1 Group Point Total: 20*

NUREG-1021, Revision 8, Supplement 1 Page8 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 System #/Name Kil K2l K3 K4 K5 K l Al A2 A3 A4 G Number= K/A Topic(s) Imp. Q#

002 Reactor Coolant 006 Emergency Core Cooling X K2.04 Knowledge of bus power supplies to the 3.8 13 following: ESFAS-operated valves.

010 Pressurizer Pressure Control X A3.02 Ability to monitor automatic operation of the 3.5 14 PZR PCS, including: PZR pressure.

011 Pressurizer Level Control X K2.02 Knowledge of bus power supplies to the 3.2 15 Ifollowing: PZR heaters.

012 Reactor Protection X K5.01 Knowledge of the operational implications of 3.8 16 the following concepts as they apply to the I _.__ RPS: DNB.

012 Reactor Protection X 2.4.12 Emergency Procedures/Plan: Knowledge of 3.9 27 general operating crew responsibilities during emergency operations 016 Non-nuclear Instrumentation X 2.1.28 Conduct of Operations: Knowledge of the 3.3 76 purpose and function of major system l _ __ _ _ _ _components and controls.

027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling X A2.02 Ability to (a) predict the impacts of the following 3.0 19 malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SFPCS.

034 Fuel Handling Equipment X K4.02 Knowledge of design features and/or interlocks 3.3 32 which provide for the following: Fuel movement 035 Steam Generator X 2.4.4 Emergency Procedures/Plan: Ability to 4.3 20 recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

039 Main and Reheat Steam X K1.06 Knowledge of the physical connections and/or 3.0 21 cause-effect relationships between the MRSS and the following systems: Condenser steam l _ _ __ _ _dump.

NUREG-1021, Revision 8, Supplement 1 Page 9 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR S--RO Examination Outline Form ES-401-3 Plant S':ystems - Tier 2/Group 2 system #1Name Ki K2 K3 K4 JK5 K Al A2 IA3 A4 C Number K/A Topic(s)Im. Q 055 Condenser Air Removal X K3,01 Knowledge of the effect that a loss or 2.7 22 malfunction of the CARS will have on the following: Main condenser.

062 AC Electrical Distribution X 2.1 .33 Conduct or Operations: Ability to recognize 4.0 77 indications for system operating parameters which are entry level conditions for Technical

___________________________________Specifications 062 AC Electrical Distribution X Ki1.03 Knowledge of the physical connections and/or 4.0 26 cause-effect relationships between the AC distribution system and the following systems:

DC Distribution 064 Emergency Diesel Generator X Al .08 Ability to predict and/or monitor changes in 3.4 25 parameters associated with operating the Emergency Diesel Generator (ED/G) System controls including: Maintaining minimum load on ED/G (to prevent reverse power) 073 Process Radiation Monitoring 075 Circulating Water 079 Station Air X K1i01 Knowledge of the physical connections and/or 3.1 28 cause-effect relationships between the SAS and the following systems: lAS.

086 Fire Protection X K4,07 Knowledge of design feature(s) and/or 2.8 29 interlocks) which provide for the following:

MT/G and T/G protection.

103 Containment K/A Category Point Totals: 3 2 1 2 1 0 1 1 1 0 4 Group Point Total: 16*

NUREG-1 021, Revision 8, Supplement 1Pae1of4 Page 10 of 14

INDIAN POINT UNITS 2 & 3 ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 System # Name K_ K2 K3 K4 K5 K6 Al A2 A3 A4 G Number K/A Topic(s) Imp. Q# .

005 Residual Heat Removal x A2.02 Ability to (a) predict the impacts of the following 3.7 30 malfunctions or operations on the RHRS, and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown.

007 Pressurizer Relief / Quench Tank 008 Component Cooling Water X A2.02 Ability to (a) predict the impacts of the following 3.5 78 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: Consequences of High/Low Surge Tank Level 041 Steam Dump/Turbine Bypass Control X A3.03 Ability to monitor automatic operation of the 2.8 33 SDS, including: Steam flow.

045 Main Turbine Generator 076 Service Water 078 Instrument Air X 2.1.23 Conduct of Operations: Ability to perform 4.0 79 specific system and integrated plant procedures during all modes of plant operation.

K/A Category Point Totals: l0l 0 0 0 0 0 0 2 1 l0 Group Point Total: 4 NUREG-1021, Revision 8, Supplement 1 Page 11 of 14

P ant-Specific Priort es

=~~~~~~~~ - - - - -._

,=__

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? __ _ _ _ _ == _ _ =-

System XTopic Recommended Replacement for .. Reason Points APE 054 G2 4.2 (Question 65) EPE 038EK1.04 High PRA importance, Event as well as mitigating system 1

_ _ I _ __, __ . _ ___

_I APE 058 AA2.03 (Question 67) APE 060AK2.01 High PRA importance; Loss of high importance system 1 SYS 004 K6.17 (Question 3) SYS 004K2.04 High PRA importance; Risk significant post-accident human error 1 APE 015/017 AA1.22 (Question 52) APE 068 AAI.20 High PRA importance; Risk significant post-accident human error 1 EPE 038 EK3.01 (Question 69) EPE E16 EK3.4 High PRA importance; Event as well as risk significant post- 1 accident human error SYS 012 Generic 2.4.12 (Question 27) SYS 075 Generic 2.4.30 High PRA importance; Event as well as mitigating systems 1 Plant-Specific Priority Total: (limit 10) [ 6 NUREG-1021, Revision 8, Supplement 1 Page 12 of 14

and Abilities Outline (Tier 3) Form ES-401-5 ES-401_

ES-401 Generic Knowledge Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Indian Point Units 2 & 3 Date of Exam: 3/8/2003 Exam Level: SRO Category K/A # Topic Imp. Q 2.1.11 Knowledge of less than one hour technical 3.8 80 specification action statements for systems. __

Conduct of 2.1.20 Ability to execute procedure steps. 4.2 81 Operations 2.1.8 Ability to coordinate personnel activities outside 3.6 34 the control room.

Total 3 2.2.6 Knowledge of the process for making changes in 3.3 82 procedures as described in the safety analysis report. l 2.2.22 Knowledge of LCOs and Safety Limits 4.1 83 2.2.34 Knowledge of the process for determining the 3.2 84 internal and external effects on core reactivity.

Equipment 2.2.33 Knowledge of control rod programming. 2.9 36 Control 2.2.2 Ability to manipulate the console controls as 3.5 37 required to operate the facility between shutdown and designated power levels. I 2.2.13 Knowledge of tagging and clearance procedures. 3.8 35_

Total 6 Radiation 2.3.9 Knowledge of the process for performing a 3.4 38 Control l containment purge. __

Total 1 2.4.45 Ability to prioritize and interpret the significance 3.6 87 of each annunciator or alarm.

2.4.4 Ability to recognize abnormal indications for 4.3 85 system operating parameters which are entry level conditions for emergency and abnormal operating priocedurestl 2.4.6 Knowledge of symptom based EOP mitigation 4.0 86 strategies.

2.4.24 Knowledge of loss of cooling water procedures. 3.7 88 Emergency 2.4.12 Knowledge of general operating crew 3.9 89 Procedures / responsibilities during emergency operations. I Plan 2.4.29 Knowledge of the emergency plan. 4.0 40 2.4.19 Knowledge of EOP layout, symbols, and icons. 3.7 39 l Total 7 Tier 3 Point Total SRO 17l NUREG-1021, Revision 8, Supplement 1 Page 13 of 14

ES-401 Record of Rejected K/As Form ES-401-10 Tier/ Group Randomly Selected K/A Reason for Rejection 2/1 (Question 23) 063 A4.03 No indication available for applicable topic in control room at facility. Replaced with randomly selected 063 K1.03.

1/2 (Question 97) 033 AA2.11 Redundant Topic (Double Jeopardy) with SYS 015K5.02 (Question 5). Replaced with manually selected 033 AA2.10.

1/3 (Question 100) 036 AA1.04 Would not yield 10CFR55.43(b) question for SRO. Replaced with manually selected Generic topic 2.2.28 to ensure coverage of 10CFR55.43(b) item 6 and/or 7 for SRO. (Was not randomly selected as part of generic tier 3).

2/2 (Question 26) 073 A1.01 Controls of PRM system are not operated in a manner that will cause change in the plant condition required by the topic. Replaced with randomly generated 062 K1.03 3 (Question 82) 2.1.18 Topic switched for RO 2.2.6 (RO 93) for SRO Only application 2/1 (Question 4) 013 A1.09 No suitable test item. Manually selected closest suitable KA to the selected topic l_ (013A1.01) 1/1 (Question 41) 005 AK2.01 No suitable test item. Randomly selected topic in 005 area (005 AK1.03) 2/2 (Question 77) 062 A2.12 No suitable test item. Manually selected Generic topic 2.1.33 to ensure 10CFR55.43(b) coverage for SRO 2/3 (Question 78) 008 A2.07 No suitable test item. Manually selected 008 A2.02 in same topic area 1/2 (Question 98) 037 G2.1.30 Not suitable for SRO. Manually selected Generic topic 2.2.22 to ensure 10CFR55.43 (b) coverage for SRO 1/2 (Question 99) E05 G2.1.27 Too many similar topics. Randomly selected El 1 EK1.2 to replace 2/2 (Question 32) 034 K6.02 Too many similar topics. Randomly selected 034 K4.02 to replace 2/2 (Question 25) 064 K3.03 Post - review removal. No suitable replacement. Replaced with 064 A1.08 2/2 (Question 13) 006 K2.02 No suitable test item >LOD 1. Replaced per NRC Review comment. (006 K2.04) 2/1 (Question 75) 068 G2.4.31 Replaced at Chief Examiner request. Used same topic in 003 area 3/3 (Question 85) G2.3.10 Replaced at Chief Examiner request. Used topic 2.4.4 3 ion 86) G2.3.2 Replaced at Chief Examiner request. Used topic 2.4.6 NUREG-1021, Revision 8, Supplement 1 Page 14 of 14

ES-40 1 PWR RO Examination Outline Form ES-401-4 ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Indian Point 2 & 3 Date of Exam: 3/8/2003 Exam Level: RO K/A Category Point Point Tier Group K K K K K K A A A A G Total 2 3 4 5 6 1 2 3 4 _L 1 4 0 3 _ 4 5 0 16 Emergency & 2 1 2 3 5 4 2 17 Abnormal Plant 3 0 0 1 0 1 1 3 Evolutions Tier Totals 5 2 7 9 10 3 36 1 3 0 0 5 3 2 1 1 4 4 1 24 l 2.

Plant 2 4 2 3 1 1 1 3 1 1 1 2 20 Systems 3 0 1 2 0 0 0 1 1 1 1 0 7*

Ti__er__ 7 3 5 6 4 3 5 3 6 6 3 51

3. Generic Knowledge and Abilities Cat Cat Cat 3 l Cat 4 13 3 4 214 _

Note: 1. Ensure that at least two topics from every KIA category are sampled within each tier (i.e., the "Tier Totals" in each K/A 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 exam must total 100 points.

3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.

6.* The generic K/As in tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system

7. On the following pages, enter the K/A numbers, a brief description of each tonic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/A's below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
  • See Note 2 above IP 2 & 3 - RO Outline Rev 0.doc Page I of 15 NUREG-1021, Revision 8, Supplement 1

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-4(1-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # Name / Safety Function Ki K2 K3 Al A2 G Number K/A Topic(s) Imp. Q#

00005 Inoperable/Stuck Control Rod / 1 X AK1.03 Knowledge of the operational implications of the following 3.2 41 concepts as they apply to the stuck rod: Xenon transient.

000015/17 RCP Malfunctions/ 4 X AA1.22 Ability to operate and/or monitor the following as they apply to 4.0 52 the RCP malfunctions: RCP seal failure/malfunction BW/E09; CE/Al 3; W/E09 & 10 Natural Circ./ 4 X EK3.1 Knowledge of the reasons for the following responses as they 3.3 42 apply to the (Natural Circulation Operations): Facility operating characteristics during transient conditions, Including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for

.__ _ _these operating characteristics.

000024 Emergency Boration / 1 X AA2.04 Ability to determine and interpret the following as they apply to 3.4 43

___the Emergency Boration: Availability of BWST.

000026 / Loss of Component Cooling Water / 8 X AK3.03 Knowledge of the reasons for the following responses as they 4.0 44 apply to the Loss of Component Cooling Water: Guidance and actions contained in EOP for Loss of CCW/Nuclear Service Water.

000027 / Pressurizer Pressure Control System X AA2.15 Ability to determine and interpret the following as they apply to 3.7 45 Malfunction / 3 the Pressurizer Pressure Control Malfunctions: Actions to be l taken if PZR pressure instrument fails high.

000040 (BW/E05; CE/E05; W/E1 2) / Steam Line X AK1.06 Knowledge of the operational implications of the following 3.7 46 Rupture - Excessive Heat Transfer / 4 concepts as they apply to Steam Line Rupture: High-energy steam line break considerations.

000040 (BW/E05; CE/EO5; W/E1 2) / Steam Line X EAI.2 Ability to operate and/or monitor the following as they apply to 3.6 47 Rupture - Excessive Heat Transfer / 4 the (Uncontrolled Depressurization of all Steam Generators):

Operating behavior characteristics of the facility. l CE/Al1; W/E08 / RCS Overcooling - PTS / 4 000051 / Loss of Condenser Vacuum / 4 X AA1.04 Ability to operate and / or monitor the following as they apply to 2.5 48 the Loss of Condenser Vacuum: Rod position.

000055/ Station Blackout / 6 X EA2.01 Ability to determine or interpret the following as they apply to a 3.4 49 Station Blackout: Existing valve positioning on a loss of l _ __ instrument air system.

000057 / Loss of Vital AC Elec. Inst. Bus / 6 X AK3.01 Knowledge of the reasons for the following responses as they 4.1 50 apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.

000062 / Loss of Nuclear Service Water /4 X AA2.01 Ability to determine and interpret the following as they apply to 2.9 51 the Loss of Nuclear Service Water: Location of a leak in the CCWS.

000067 / Plant Fire On-site / 9 000068 (BW/A06) / Control Room Evac. /8 l000069 (WE_14) / Loss of CTMT Integrity /5 I

NUREG-1021, Revision 8, Supplement 1 Page 2 of 15

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K1I K2 K3 Al A2 G Number 1 K/A Topic(s) Imp. #

000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EK1.05 Knowledge of the operational implications of the following 2.8 53 concepts as they apply to the Inadequate Core Cooling:

Definition of saturated liquid.

000074 (W/EO6 & E07) / Inad. Core Cooling / 4 X EK1.3 Knowledge of the operational implications of the following 3.7 54 concepts as they apply to the (Degraded Core Cooling):

Annunciators and conditions indicating signals, and remedial actions associated with the (Degraded Core Cooling).

000074 (W/E06 & E07) / Inad. Core Cooling / 4 X EA1.2 Ability to operate and/or monitor the following as they apply to 3.2 55 the (Saturated Core Cooling): Operating behavior I _characteristics of the facility.

BW/EO3 / Inadequate Subcooling Margin / 4 000076 / High Reactor Coolant Activity / 9 X AA2.02 Ability to determine and interpret the following as they apply to 2.8 56 the High Reactor Coolant Activity: Corrective actions required for high fission product activity in RCS.

BW/A02 & A03 / Loss of NNI-X/Y / 7 K/A Category Point Totals: 4 0 3 4 5 0 . Group Point Total: 16 NUREG-1021, Revision 8, Supplement 1 Page 3 of 15

INDIAN POINT UNITS 2 & 3 1 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE #/ Name / Safety Function K K2 K3 Al. A2 G Number K/A Topic(s) Imp. i 000001 / Continuous Rod Withdrawal /1 X AA1.05 Ability to operate and / or monitor the following as they apply to 4.3 57

__ the Continuous Rod Withdrawal: Reactor trip switches.

000003 / Dropped Control Rod / 1 X AK2.05 Knowledge of the interrelations between the Dropped Control 2.5 58 Rod and the following: Control rod drive power supplies and logic circuits.

000007 (BW/E02 & El0; CE/E02) / Reactor Trip -

Stabilization - Recovery /1 BW/A0l / Plant Runback / 1 BW/A04 / Turbine Trip / 4 000008 / Pressurizer Vapor Space Accident /3 X AK2.02 Knowledge of the interrelations between the Pressurizer Vapor 2.7 59 Space Accident and the following: Sensors and detectors.

000009 / Small Break LOCA / 3 X EA1.18 Ability to operate and monitor the following as they apply to a 3.4 60 small break LOCA: Balancing of HPI loop flows.

000011 / Large Break LOCA / 3 X EA1.01 Ability to operate and monitor the following as they apply to a 3.7 61 Large Break LOCA: Control of RCS pressure and temperature I to avoid violating PTS limits.

W/E04 / LOCA Outside Containment / 3 X EK1.3 Knowledge of the operational implications of the following 3.5 97 concepts as they apply to the (LOCA Outside Containment):

Annunciators and conditions indicting signals, and remedial actions associated with the (LOCA Outside Containment).

BW/E08; W/E03 / LOCA Cooldown / Depress. / 4 W/El1 / Loss of Emergency Coolant Recirc. /4 WE/01 & 02 / Rediagnosis & SI Termination / 3 X EK3.2 Knowledge of the reasons for the following responses as they 3.0 62 apply to the Reactor Trip or Safety Injection/Rediagnosis:

Normal, abnormal and emergency operating procedures associated with (Reactor Trip or Safety Injection/Rediagnosis).

WE/01 & 02 / Rediagnosis & SI Termination / 3 X EA2.2 Ability to determine and interpret the following as they apply to 3.3 98 the (SI Termination): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

000022 / Loss of Reactor Coolant Makeup /2 X AA1.08 Ability to operate and/or monitor the following as they apply to 3.4 63

___ _the Loss of Reactor Coolant Pump Makeup: VCT level.

000025 / Loss of RHR System / 4 X AA2.07 Ability to determine and interpret the following as they apply to 3.4 64 the Loss of Residual Heat Removal System: Pump cavitation.

000029 / Anticipated Transient w/o Scram /1 000032 / Loss of Source Range NI / 7 X AA2.04 Ability to determine and interpret the following as they apply to 3.1 72 the Loss of Source Range instrumentation: Satisfactory Source Range/Intermediate Range overlap 000033 / Loss of Intermediate Range NI /7 7

000037 / Steam Generator Tube Leak / 3 IUE- 021 Reiso 8,Splmn 1Pg-f1 NUREG-1021, Revision 8, Supplement 1 Page 4of 15

_ _ -INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # Name / Safety Function K1 K2 K3 Al A2 G i Number K/A Topic(s) Imp. Q#

000038 / Steam Generator Tube Rupture / 3 X EK3.01 Knowledge of the reasons for the following responses as they 4.1 69 apply to the Steam Generator Tube Rupture: Equalizing pressure on primary and secondary sides of ruptured SG 000054 (CE/E06) / Loss of Main Feedwater / 4 X 2.4.2 Emergency Procedures/Plan: Knowledge of system setpoints, 3.9 65 interlocks, and automatic actions associated with EOP entry conditions BW/E04; W/EO5 / Inadequate Heat Transfer - X 2.4.6 Emergency Procedures/Plan: Knowledge of symptom based 3.1 100 Loss of Secondary Heat Sink / 4 EOP mitigation strategies 000058 / Loss of DC Power / 8 X AA2.03 Ability to determine and interpret the following as they apply to 3.5 67 the Loss of DC Power: DC loads lost. Impact on ability to operate and monitor plant systems 000058 / Loss of DC Power / 8 X AK3.02 Knowledge of the reasons for the following responses as they 4.0 99 apply to the Loss of DC Power: Actions contained in EOP for loss of DC power.

000059 / Accidental Liquid Radwaste Rel. / 9 000060 / Accidental Gaseous Radwaste Rel. / 9 000061 / ARM System Alarms / 7 X AA1.01 Ability to operate and/or monitor the following as they apply to 3.6 68 the Area Radiation Monitoring (ARM) System Alarms: Automatic actuation.

W/E16 / High Containment Radiation / 9 CE/EO9 / Functional Recovery - - _ =_

K/A Category Point Totals: 1 2 3 5 4 2 Group Point Total: 17 NUREG-1021, Revision 8, Supplement 1 Page 5 of 15

11 INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE # / Name / Safety Function KI K2 K3 Al A2 G Number K/A Topic(s) Imp. 0411 000028 / Pressurizer Level Malfunction / 2 X AK3.02 Knowledge of the reasons for the following responses as they 2.9 70 apply to the Pressurizer Level Control Malfunctions:

Relationships between PZR pressure increase and reactor makeup/letdown imbalance, 000036 (BW/A08) / Fuel Handling Accident /8 000056 / Loss of Off-site Power / 6 X AA2.51 Ability to determine and interpret the following as they apply to 3.3 71 the Loss of Offsite Power: AT, (core, heat exchanger, etc.)

000065 / Loss of Instrument Air /8 X 2.1.2 Conduct of Operations: Knowledge of operator responsibilities 3.9 66 during all modes of plant operation.

BW/E13 & E14 / EOP Rules and Enclosures BW/A07 / Flooding / 8 CE/Al 6 / Excess RCS Leakage / 2 W/E13 / Steam Generator Over-pressure /4 W/E15 / Containment Flooding / 5 K/aegr oint Totals: 0 0 1 0 1 1 Group Point Total: 3 NUREG-1021, Revision 8, Supplement 1 Page 6of 15

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System Name K1I K2 K3 K4 K5 K6,A1A2A3A4 GNumber, KAtopic(s)Imp 001 Control Rod Drive X K4.02 Knowledge of CRDS design feature(s) and/or 3.8 73 interlock(s) which provide for the following:

Control rod mode select control (movement control).

001 Control Rod Drive X A3.05 Ability to monitor automatic operation of the 3.5 78 CRDS, including: Individual versus group Iposition ____

003 Reactor Coolant Pump X A3.04 Ability to monitor automatic operation of the 3.6 1 RCPS, including: RCS flow.

003 Reactor Coolant Pump X K4.04 Knowledge of RCPS design feature(s) and/or 2.8 2 interlock(s) which provide for the following:

Adequate cooling of RCP motor and seals.

004 Chemical and Volume Control X K5.19 Knowledge of the operational implications of 3.5 74 the following concepts as they apply to the CVCS: Concept of SDM.

004 Chemical and Volume Control X K6.17 Knowledge of the effect of a loss or malfunction 4.4 3 of the following will have on the CVCS: Flow paths for emergency boration 013 Engineered Safety Features Actuation X A2.01 Ability to (a) predict the impacts of the following 4.6 75 malfunctions or operations on the ESF Actuation System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: LOCA 013 Engineered Safety Features Actuation X A1.01 Ability to predict and/or monitor changes in 4.0 4 parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including: RCS pressure and temperature.

013 Engineered Safety Features Actuation X A4.03 Ability to manually operate and/or monitor in 4.5 31 the Control Room: ESFAS Initiation.

015 Nuclear Instrumentation X K5,02 Knowledge of the operational implications of 2.7 5 the following concepts as they apply to the NIS:

Discriminator/compensation operation.

015 Nuclear Instrumentation X K4.03 Knowledge of NIS design feature(s) and/or 3.9 76 interlock(s) provide for the following: Reading of source range/intermediate range/power range outside Control Room.

017 In-Core Temperature Monitor X K1.01 Knowledge of the physical connections and/or 3.2 77 cause/effect relationship between the TM system and the following: Plant computer NUREG-1021, Revision 8, Supplement 1 Page 7of 15

INDIAN POINT UNITS 2 & 3 ES-401 PWR PO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System , Name K1 K2 K3 K4 K5 6 Al A2 3 4 #

017 In-Core Temperature Monitor X A4.01 Ability to manually operate and/or monitor in 3.8 6 the Control Room: Actual in-core temperatures.

022 Containment Cooling X A4.04 Ability to manually operate and/or monitor in 3.1 7 the Control Room: Valves in the CCS.

025 Ice Condenser SUPPRESSED 056 Condensate X K1.03 Knowledge of the physical connections and/or 2.6 83 cause-effect relationships between the Condensate system and the following systems:

MFW 056 Condensate X 2.1.2 Conduct of Operations: Knowledge of operator 3.3 79 responsibilities during all modes of plant operation.

059 Main Feedwater X K4.19 Knowledge of MFW design feature(s) and/or 3.2 8 interlock(s) which provide for the following:

Automatic feedwater isolation of MFW.

059 Main Feedwater X A4.03 Ability to manually operate and monitor in the 2.9 9 Control Room: Feedwater control during power increase and decrease.

061 Auxiliary / Emergency Feedwater X K6.02 Knowledge of the effect of a loss or malfunction 2.6 10 of the following will have on the AFW components: Pumps.

061 Auxiliary / Emergency Feedwater X K4.04 Knowledge of AFW design feature(s) and/or 3.1 80 interlock(s) which provide for the following:

Prevention of AFW runout by limiting AFW flow.

068 Liquid Radwaste X A3.02 Ability to monitor automatic operation of the 3.6 81 Liquid Radwaste System including: Automatic isolation.

068 Liquid Radwaste X K1.07 Knowledge of the interrelations and/or cause- 2.7 82 effect relationships between the Liquid Radwaste System and the following: Sources of liquid waste for LRS.

071 Waste Gas Disposal x K5.04 Knowledge of the operational implication of the 2.5 11 following concepts as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.

072 Area Radiation Monitoring X A3.01 Ability to monitor automatic operation of the 2.9 12 ARM system, including: Changes in ventilation alignment. I NUREG-1021, Revision 8, Supplement 1 Page 8 of 15

_ ==. __, = ._= =, - .

i INDIAN POINT UNITS 2 & 3 II ES-401 PWR RO Examination Outline FDrm ES-401-4 Plant Systems - Tier 2/Group 1

__ = _ _ _

i System #, Name K1 K2 K3 K4 I K5 K6 Al i A2 A3 A4 G Number K/A Topic(s) Imp. Q K/A Category Point Totals: 3 1 0 1 0 1 5 3 2 1 1 4 4 1 1 Group Point Total: _ 24*

NUREG-1021, Revision 8, Supplement 1 Page 9of 15

F INDIAN POINT UNITS 2 & 3 X ES-401 PWR RO Examination Outline Form ES-401-4 E - -Plant Systems - Tier 2/Group 2 System # Name K1 K2 K3 K4 KS K6 Al A2 A3 A4 G Number K/A Topic(s) Imp Q#

002 Reactor Coolant X K4.02 Knowledge of RCS design features and/or 3.5 84 interlocks which provide for the following:

Monitoring reactor vessel level 002 Reactor Coolant X K6.02 Knowledge of the effect of a loss or malfunction 3.6 86 on the following will have on the Reactor Coolant System (RCS): RCP 006 Emergency Core Cooling X K2.04 Knowledge of bus power supplies to the 3.6 13 following: ESFAS-operated valves.

010 Pressurizer Pressure Control X A3.02 Ability to monitor automatic operation of PZR 3.6 14 PCS, including: PZR pressure.

011 Pressurizer Level Control X K2.02 Knowledge of bus power supplies to the 3.1 15 following: PZR heaters.

012 Reactor Protection X K5.01 Knowledge of the operational implications of 3.3 16 the following concepts as they apply to the RPS: DNB.

012 Reactor Protection X 2.4.12 Emergency Procedures/Plan: Knowledge of 3.4 27 general operating crew responsibilities during emergency operations 014 Rod Position Indication X A4.01 Ability to manually operate and/or monitor in 3.3 17 the Control Room: Rod selection control.

016 Non-nuclear Instrumentation x K3.04 Knowledge of the effect that a loss or 2.6 85 malfunction of the NNIS will have on the

______ following: MFW system.

026 Containment Spray X A1.01 Ability to predict and/or monitor changes in 3.9 18 parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment pressure.

029 Containment Purge 033 Spent Fuel Pool Cooling X A2.02 Ability to (a) predict the impacts of the following 2.7 19 malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SFPCS.

035 Steam Generator X 2.4.4 Emergency Procedures/Plan: Ability to 2.5 20 recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

NUREG-1021, Revision 8, Supplement 1 Page 10 of 15

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 Systemi Name K K2 K K4 K K6 A A2 A3 A4 G0 Number KIA Topic(s) imp. Q#

039 Main and Reheat Steam X K1.06 Knowledge of the physical connections and/or 3.1 21 cause-effect relationships between the MRSS and the following systems: Condenser steam dump.

055 Condenser Air Removal X K3.01 Knowledge of the effect that a loss or 2.5 22 malfunction of the CARS will have on the following: Main condenser.

062 AC Electrcal Distribution X K1.03 Knowledge of the physical connections and/or 3.5 26 cause-effect relationships between the AC distribution system and the following systems:

DC Distribution 063 DC Electrical Distribution X K1.03 Knowledge of the physical connections and/or 2.9 23 cause-effect relationships between the DC distribution system and the following systems:

Battery Charger and battery 063 DC Electrical Distribution X K3.02 Knowledge of the effect that a loss or 3.5 24 malfunction of the DC Electrical System will have on the following: Components using dc; control power.

064 Emergency Diesel Generator X A1.08 Ability to predict and/or monitor changes in 3.1 25 parameters associated with operating the Emergency Diesel Generator (ED/G) System controls including: Maintaining minimum load on ED/G (to prevent reverse power) 073 Process Radiation Monitoring 075 Circulating Water 079 Station Air X K1.01 Knowledge of the physical connections and/or 3.0 28 cause-effect relationships between the SAS and the following systems: IAS.

086 Fire Protection X K4.07 Knowledge of design feature(s) and/or 2.5 29 interlock(s) which provide for the following:

MT/G and T/G protection.

KIA Category Point Totals: 4 2 3 1 1 1 3 1 1 1 2 Group Point Total: 20 NUREG-1021, Revision 8, Supplement 1 Page 11 of 15

INDIAN POINT UNITS 2 & 3 ES-401 PWR RO Examination Outline Form E-S401-4 1:

Plant Systems - Tier 2/Group 3 Il System #/ Name K1 K2 K3 K4 KS K6 Al A2 A3 A4 G LNumber KA Topic(s) Imp O 005 Residual Heat Removal X A2.02 Ability to (a) predict the impacts of the following 3.5 30 malfunctions or operations on the RHRS, and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown.

007 Pressurizer Relief/Quench Tank 008 Component Cooling Water X K3.01 Knowledge of the physical connections and/or 3.4 90 cause-effect relationships between the CCWS and the following: Loads cooled by CCWS 027 Containment Iodine Removal X A4.01 Ability to manually operate and/or monitor in 3.3 32 the Control Room: CIRS controls.

028 Hydrogen Recombiner and Purge Control 034 Fuel Handling Equipment 041 Steam Dump/Turbine Bypass Control X A3.03 Ability to monitor automatic operation of the 2.7 33

____ __ SDS, including: Steam flow.

045 Main Turbine Generator X A1.06 Ability to predict and/or monitor changes in 3.3 88 parameters (to prevent exceeding design limits) associated with operating the MT/G system controls including: Expected response of secondary plant parameters following T/G trip.

076 Service Water X K2.01 Knowledge of bus power supplies to the 2.7 89 following: Service water.

076 Service Water X K3.07 Knowledge of the effect that a loss or 3.7 87 malfunction of Service Water will have on the following: ESF loads 078 Instrument Air 103 Containment lACategorPoint Totals: 0 1 2 0 0 0 1 1 1 1 0 Group Point Total: 7*

NUREG-1021, Revision 8, Supplement 1 Page 12 of 15

Plant-Specific Priorities r _ . _ _ _ _ . _ . ., _ _

_ I System Iopic Recommended Replacement for Reason Points i APE 054 G2 4 2 (Question 65) EPE 035EK1 04 High PRA Importance, Event as well as mitigating system _ 1 APE 058 AA2 03 (Question 67) APE 060AK2.01 High PRA importance; Loss of high importance system 1 EPE E05 G2.4.6 (Question 100) APE 059AA2.02 High PRA importance; Event as well as mitigating systems 1 SYS 004 K6.17 (Question 3) SYS 004K2.04 High PRA importance; Risk significant post-accident human error 1 APE 015/017 AA1.22 (Question 52) APE 068 AA1.20 High PRA importance; Risk significant post-accident human error 1 EPE 038 EK3.01 (Question 69) EPE E16 EK3.4 High PRA importance; Event as well as risk significant post- 1 accident human error SYS 008 K3.01 (Question 90) SYS 103 A4.01 High PRA importance; Risk significant post-accident human error 1 SYS 012 Generic 2.4.12 (Question 27) SYS 075 Generic 2.4.30 High PRA importance; Event as well as mitigating systems 1 Plant-Specifc Priority Total: (limit 10) 8 NUREG-1021, Revision 8, Supplement 1 Page 13 of 15

and Abilities Outline (Tier 3) Form F-4fl1-B ES-401 ES-401 Generic Knowledge Generic Knowledge and Abilities Outline (Tier 3) ,

Form ESc-401-5

, v s Facility: Indian Point Units 2 & 3 Date of Exam: 3/8/2003 Exam Level: RO Category K/A # Topic Imp. C I +/- _________________________________________________________ . C --

2.1.2 Knowledge of operator responsibilities during all 3.0 91 modes of plant operation. l l

I I

I I _ . .

2.1.18 Ability to make accurate, clear and concise logs, 2.9 93 records, status boards, and reports.

I --l ~

Conduct of 2.1.8 Ability to coordinate personnel activities outside 3.8 34 Operations the Control Room.

Total 33 I - - - I 2.2.12 Knowledge of surveillance procedures. 3.0 91 Equipment 2.2.13 Knowledge of tagging and clearance procedures. 3.6 3; Control 2.2.33 Knowledge of control rod programming. 2.5 3E2 2.2.2 Ability to manipulate the console controls as 4.0 7 required to operate the facility between shutdown and designated power levels. I Total 4 1 r .- t 2.3.4 Knowledge of radiation exposure limits and 2.5 94 contamination control, including permissible levels in excess of those authorized.

l l Radiation I 2.3.9 Knowledge of the process for performing a 2.5 38 Control containment purge.

I Total 2 2.4.14 Knowledge of general guidelines for EOP 3.0 95 flowchart use.

Emergency 2.4.34 Knowledge of RO tasks performed outside the 3.8 9E Procedures I main control room during emergency operations Plan including system geography and system implications.

2.4.19 Knowledge of EOP layout, symbols, and icons. 2.7 39 3

2.4.29 Knowledge of the emergency plan. 2.6 4C Total 4 Tier 3 Point Total RO 13".

I NUREG-1021, Revision 8, Supplement 1 Page 14 of 15

ES-401 Record of Rejected K/As Form ES-401-10 Tier / Group Randomly Selected K/A Reason for Rejection 1/2 (Question 72) 054 G2.2.25 No connection to 10CFR55.41 for RO. Replaced with randomly generated 032 AA2.04 2/2 (Question 23) 063 A4.03 No indication available for applicable topic in control room at facility. Replaced with randomly generated 063 K1.03.

2/1 (Question 78) 056 G2.2.22 No connection to 10CFR55.41 for RO and no TS connection to system. Replaced with randomly generated 001 A3.05 2/1 (Question 83) 071 A4.27 No indication or control available in control room. Replaced with randomly generated 056 K1.03 2/1 (Question 75) 013 K4.17 Operation not performed at facility. Replaced with randomly generated 013 A2.01 2/1 (Question 74) 004 K5.02 Potential Double Jeopardy with 071K5.04. Replaced with manually selected 004 K5.19.

(Manually selected the next topic with same KA importance value) 2/2 (Question 26) 073 A1.01 Controls of PRM system are not operated in a manner that will cause change in the plant condition required by the topic. Replaced with randomly generated 062 K1.03 3 (Question 93) 2.2.6 Not RO level topic. Replaced by trading topic with SRO 2.1.18 (SRO 82) 2/1 (Question 4) 013A1.09 No suitable test item. Manually selected closest suitable KA to the selected topic (013A1.01) 1/1 (Question 41) 005 AK2.01 No suitable test item. Randomly selected topic in 005 area (005 AK1.03) 2/1 (Question 77) 017 K4.02 No suitable test item. Randomly selected topic in area (017 K1.01) 2/3 (Question 87) 007A2.06 No suitable test item. Randomly selected topic in area (076 K3.07) 2/2 (Question 86) 029 A1.02 No suitable test item. Randomly selected topic in area (002 K6.02) 2/3 (Question 32) 034 K6.02 Related item on exam. Randomly selected topic in area (027 A4,01) 2/1 (Question 82) 068 A2.04 Related item on exam. Randomly selected topic in area (068 K1.07) 2/3 (Question 31) 028 A4.01 No suitable test item. Randomly selected topic in area (028 K6.01) 2/2 (Question 13) 006 K2.02 No suitable test item >LOD 1. Replaced per NRC Review comment. (006 K2.04) 2/2 (Question 84) 002 K5.19 No suitable test item operationally oriented. Replace d per NRC review comment (002 K4.02) 2/2 (Question 25) 064 K3.03 Post - review removal. No suitable replacement. Replaced with 064 A1.08 NUREG-1021, Revision 8. Supplement 1 Page 15 of 15

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