ML081370315

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Final Outlines (Folder 3)
ML081370315
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 03/25/2008
From: Todd Fish
Operations Branch I
To: Peter Dietrich
Entergy Nuclear Northeast
Hansell S
Shared Package
ML072850856 List:
References
50-333/08-301, U01684 50-333/08-301
Download: ML081370315 (27)
v • d • e


Text

2008 FitzPatrick NKC Exam Rev1 and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA category shall not be less than two).

The final point total for each group and tier may deviate by f l 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. Systemslevolutions 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 the elimination of inappropriate WA statements.

group before selecting a second topic for any system or evolution.

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

2. The point total for each group and tier in the proposed outline must match that specified in the table.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. The generic (G) WAS 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.
8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (1Rs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2
9. For Tier 3, select topics from Skcion 2 of the ri/A catalog, and enter the WA numbers, descriptions, IRs, an(

point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

Summary

Year Facility NRC Exam Rev 0 APES T1 G1

Facility NRC Exam Year Rev 0 EAPEs T1 G1

Year Facility NRC Exam EIAPE # I Name I Safety Function KIA Topic(s)

Rev 0 EAPEs T1 G1

Year Facility NRC Exam Rev 0 95034Seconda EAPEs T1 G2

D 0

-I- +

W 0

Year Facility NRC Exam Rev 0 SYSTEMS T2 G1

Year Facility NRC Exam Rev 0 SkSTEMs T2 G1

13 I1 SW3lSAS

I I'

q-

-+-

J J

n b

I I

I f

(c (E

(2 L

3 4

n i

Year Facility NRC Exam Rev 0 SYSTEMS T2 G2

Facility NRC Exam Year Rev 0 SYSTEMS T2 G2

Year Facility NRC Exam Rev 0 Category t-Generics

Year Facility NRC Exam Rev 0 Generics

Year Category Facility NRC Exam Rev 0 Generics

Year Facility NRC Exam Rev 0 Generics

Year T I GI T2 G2 T2 G I Facility NRC Exam 295038 G2.4.10 272000 A4.03 400000 G2.4.43 Generic dealt with use of ARPs for high off-site release rate, randomly selected another generic Unable to write discriminating question for this KIA, randomly selected another Tier 2 system Unable to write discriminating question for this KIA, randomly selected another generic Rev 0 Tierand I

I 1

Group I

Randomly Selected KIA Reason for Rejection 1

i ES 401-4

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1

, Facility:

FitzPatrick Examination Level (circle one): RO / SRO Date of Examination: 3/31/08 to 4/10/08 Operating Test Number:

1 Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Type Code*

N N

M Describe activity to be performed Manually Compute Average Drywell Air Temperature Work Hour Restrictions Complete a Tagout N/A

~~

ERO CallOut NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room (D)irect from bank (I 3 for ROs; I4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (< 1; randomly selected)

(S)imulator

ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility:

FitzPatrick Date of Examination: 3/31/08 to 4/10/08 Examination Level (circle one): RO / SRO Operating Test Number:

1 Administrative Topic (see Note)

Conduct of Operations Conduct of Operations I Equipment Control Radiation Control B

Emergency Plan Type Code*

N N

M Describe activity to be performed Manually Compute Average Drywell Air Temperature Work Hour Restrictions Complete a Tagout Canal Discharge Approval Post Scenario Event Classification Type Codes & Criteria: (C)ontrol room (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (-< 1 ; randomly selected)

(S)imulator

ES-301, Rev. 9 Control Room/ln-Plant Systems Outline Form ES-301-2 System / JPM Title

a. Component Cooling Water / Change In-Service RBCLC Pumps Type Code*

Safety Function A, N, s 8

b. Recirculation / Start Reactor Recirc Pump
c. High Pressure Coolant Injection /Shutdown HPCl
d. Main and Reheat Steam / MSlV Surveillance Test
e. Primary Containment System / Respond to High Drywell Temperature 11 f. Low Pressure Core Spray / Core Spray Surveillance Test

~~

A, N, S 1

A, D, S 2

N, s 3

A, N, S 5

4

h. APRM/LPRM / Restore Inoperable LPRM (1 g. Emergency Generators / Load Test of B Emergency Diesel I

D,L,S I

6 N, s 7

j. CRD Hydraulics / Change In-Service Flow Control Valves
k. Emergency Generators / SBO Start of EDG
1) i. Safety Relief Valves / Pull Fuses for Stuck Open SRV r

G r

~

D, E 1

N, E 6

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

(P)revious 2 exams (S)imulator 1 (C)ontrol room (R)CA 4-6 14-6 I 2-3 1 9 1 s a 1 ~ 4 2 1 I 2 1 / 2 1 21 I 2 1 121 2212212 1 5 3 I I 3 / I 2 (randomly selected) 2 1 1 2 1 1 2 1 I'

ES-301, Rev. 9 Control Room/ln-Plant Systems Outline Form ES-301-2 System / JPM Title

a. Component Cooling Water / Change In-Service RBCLC Pumps Type Code*

A, N, S 11 b. Recirculation / Start Reactor Recirc Pump

c. High Pressure Coolant Injection / Shutdown HPCi
d. Main and Reheat Steam / MSlV Surveillance Test
e. Primary Containment System / Respond to High Drywell Temperature
f. Low Pressure Core Spray / Core Spray Surveillance Test A, D, s N, s A, N, S N, L, S 11 g. Emergency Generators / Load Test of B Emergency Diesel I

D, L, S

i. Safety Relief Valves / Pull Fuses for Stuck Open SRV
j. CRD Hydraulics / Change In-Service Flow Control Valves Safety Function D, R 3

D, E 1

8

k. Emergency Generators / SBO Start of EDG

~

1 N, E 6

2 3

5 4

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

(P)revious 2 exams

( W A (S)imulator 4-6 14-6 12-3 191sa/s4 2 1 12 1 / 2 1 1 1 / 2 1 / 2 1 2 2 / 2 2 / 2 1 2 3 / 2 3 15 2 (randomly selected) 2 1 / 2 1 / 2 1

Appendix D Scenario Outline Form ES-D-I Event No.

1 2

3 4

5 6

7 8

Facility: -FitzPatrick Scenario No.:

1 Op-Test No.:

Examiners: Fish Fuller (UI)

Operators:

Johnson Presby Malf.

Event Event No.

Type*

Description Trigger 1 N (RO)

Swap in service CRD pumps.

Trigger 2 Trigger 3 Trigger 4 Trigger 5 Trigger 6 Trigger 7 Trigger 8 c (BOP)

R(R0) 5% power reduction.

C (BOP)

C(ALL)

M(ALL) c(B0P)

C (BOP)

RClC controller failure.

HPCl Aux Oil Pump breaker failure.

'A' RFP trip and failure of Recirc runback.

Loss of all CRD pumps ATWS due to RPS failure.

Main turbine trip, loss of Auxiliary busses Initial Conditions: -87% power -(MOL)

M (ALL)

Trigger 9 9

Turnover: -Operating normally at 87%' after assuming shift will continue to 65% in preparation for cleaning condenser water boxes; Perform a swap of CRD pumps to allow maintenance t o record vibration data on the 'B' CRD pump Emergency Depressurization (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-I Event Malf.

Event No.

No.

Type*

1 Trigger 1 I (RO) 2 Trigger2 N(ALL)

Trigger 3 3

Trigger 4 4

Trigger 5 5

R(R0)

C (BOP)

C (BOP)

(SRO)

C (ALL)

Trigger 6 6

Event Description APRM instrument failure.

Restoration of busses 10200 and 10400 to T4.

Raises power with control rods Failure of LPCl inverter Inadvertent HPCl initiation Unisolable leak on Instrument Air header M (ALL)

C(ALL)

M (ALL)

Trigger 7 Trigger 8 Trigger 9 7

8 9

II I

I I

SBLOCA on.recirc line, containment spray required Spray torus, both loop of RHR fail Spray Torus/Drywell with RHR SW (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility: -FitzPatrick Scenario No.:

4 Op-Test No.:

Examiners: Fish Fuller (U/)

Operators:

Johnson Presby Initial Conditions: 92% (MOL Turnover: 92% CTP, pulling rods to 103% rod line and 96% CTP, then hold for one hour prior to proceeding to 100% CTP using recirc flow.

Rod pull sheet step 65. Next rod will be rod 18-15. rod pull from 12 - 16 Crew will swap TBCLC pumps in preparation for maintenance.

Event Malf.

Event I

1 Trigger 1 C (BOP)

Trigger 2 Trigger 3 Trigger 4 Trigger 5 Trigger 6 Trigger 7 Trigger 8 R (RO) c (RO) 2 3

4 5

6 7

8 N (BOP)

C (BOP)

C (ALL)

C (ALL)

C (BOP)

M (ALL)

Trigger 8 9

(N)ormal, (R)eactivity, (I)nstrument, (C)ornponent, (M)ajor Event Description Trip of B Service Water pump. Manual start of A SW pump.

Raise power by withdrawing control rods Stuck control rod Swap TBCLC pumps Loss of level control 6A FW heater.

Both Feed pumps trip.

Condensate pumps trip.

RClC starts then trips after t w o minutes.

HPCl fail to auto start.

Recirc loop break in drywell. Containment sprays required.

Appendix D Scenario Outline Form ES-D-1 1

2 3

4 5

6 7

8 9

Facility: -FitzPatrick Scenario No.:

5 Op-Test No.:

Trigger 1 Trigger 2 Trigger 3 Trigger 4 Trigger 5 Trigger 6 Trigger 7 Trigger 8 Trigger 9 Examiners: Fish Fuller (U/)

Operators:

Johnson Presby Initial Conditions: 50% (MOL)

Turnover: Drywell is being purged IAW OP-37 D.6.11. SBGT'A' is running to vent torus. 'C' Condensate pump is running in preparation for securing 'B' condensate pump for maintenance Control rods are at Step 47.

Event Type*

C (BOP)

N (BOP)

C (ALL)

C (ALL)

C (BOP)

C (BOP)

M (ALL)

M (ALL)

Event Description

'A' Standby Gas Treatment fan trip.

Normal shutdown of 'B' condensate pump.

Failure of 'B' NR level instrument upscale, level transient.

Fuel clad failure ATWS due to RPS 'A' failure.

FW startup level control valve failure RWCU failure to isolate Steam leak in Reactor Building resulting in rad release.

Reactor depressurization.

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

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