ML052240151

Outline for NRC-Proposed Palisades Initial Examination - May 2005

ML052240151
Person / Time
Site:	Palisades
Issue date:	05/23/2005
From:	Palagi B NRC/RGN-III/DRS/OLB
To:	Nuclear Management Co
Shared Package
ML051930236	List: ML052240124 ML052240142 ML052240151 ML052240160 ML052240167 ML052240175 ML052240188
References
50-255/05-301 50-255/05-301
Download: ML052240151 (28)

Text

OUTLINE FOR NRC-PROPOSED PALISADES INITIAL EXAMINATION - MAY 2005

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: fa lis &des 2

Date of Examination:

1 L

c. Assess whether the outline over-emphasizes any systems. evoiutions. or generic topics.

Item Task Description a

1.

R I

T T

E N

2.

S I

M U

L A

T

a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401

b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.l of ES-401 and whether all KIA categories are appropriately sampled.

w is*

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria Specified on Form ES-301-4 and described in Appendix D.

d. Assess whether the justifications for deselected or rejected KIA statements are appropriate.

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients.

b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of applicants in accordance with the expected crew compOsition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario. that no Scenarios are duplicated from the applicants' audit test@), and that scenarios will not be repeated on subsequent days.

0 I

4 Clf'ed on Form ES-301.2 ana in-plant l a w lm ts spec4 ea on the tom imLms specheo on me form CA tasks meet the ci lei a a Aukhi:

b -ku@Reviewer (#

c NRC Chief Examiner (#)

d NRC Supervisor

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

Palisades Examination Level (circle one): RO Administrative Topic (see Note)

Equipment Control I

Radiation Control I1 Emergency Plan ll Type Code*

D. P, S or CL N, S or CL N.CL Date of Examination: May 2005 Operating Test Number:

Describe activity to be performed Determine Compensation Required for a Withdrawn, Inoperable Control Rod (KA 2.1.25 Ability to obtain and Interpret Station reference material)

~

~~~

~

Determine the Mechanical and Electrical isolation points for tag out of HP SI Pump (KIA 2.2.13 Knowledge of tagging and clearance procedures)

Determine if Workers can perform containment entry within dose limits (WA 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements)

Obtain Meteorological Data for Emergency Notification Form (WA 2.4.4 Obtain Meteorological Data for Emergency 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.

I 11

• Type Codes & Criteria:

(C)ontrol room (CL) Class r m m (D)irect from bank (s 3 for ROs: s 4 for SROs & RO retakes)

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

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

(S)imulator

ES-301 Administrative Topics Outline Form ES-301-1 Administrative Topic Type (see Note)

Code*

N, CL Conduct of Operations N, CL Conduct of Operations N, CL Equipment Control N, CL Radiation Control N, CL Emergency Plan Describe activity to be performed Determine Reportability of an Auxiliary Feedwater Pump Failure (WA 2.1.12 Ability to apply Technical Specifications and Determine Reportability )

Determine Shift Staffing Requirements following an illness (WA 2.1.5 Ability to locate and use procedures and directives related to shift staffing and activities)

Determine the Mechanical and Electrical isolation points for tag out of HF' SI Pump (WA 2.2.13 Knowledge of tagging and clearance procedures)

Determine if workers can perform containment entry within dose limits (WA 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements)

Classify a Security Event (WA 2.4.4 Knowledge of emergency action level thresholds and classifications)

• Type Codes & Criteria:

(C)ontrol room (CL) Class rmom (D)irect from bank (i 3 for ROs; 2 4 for SROs & RO retakes)

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

(P)revious 2 exams (5 I; randomly selected)

(S)imulator

ES-301 Control Roodln-Plant Systems Outline Form ES-301 Facility:

Palisades Date of Examinat on:

May 2005 Exam Level (circle one). RO Control Room Systems (8 for RO; 7 for SRO-I, 2 or 3 tor SRO-U)

Operating Test No - -

h. Set up Radwaste Discharge Monitor RIA-1049 for a release (068 Liquid Radwaste System K/A 4.02) n D, S 9

System I JPM Title

j. Start the M-696 Hydrogen Recombiner (028 HRPS WA A4.01)

k. Isolate and Locally start Diesel Generator 1-1 (064 EDG A4.01)

Type Code Function D, R 5

D 6

a. Respond to a Control Rods Out of Sequence alarm. (001 CRDS WA D, P, s A4.14)

b. Establish the Containment Sump as the ECCS suction source following and Large Break Loss of Coolant Accident (006 ECCS WA A4.05)

A, N, S, E C. Swapping Pressurizer Pressure Control Channels (01 0 PZR PCS WA Al.07)

A, N, S

d. Initiate Shutdown Cooling for the PCS (005RHRS WA A4.01)

e. Alignment of Containment Air Coolers (022 CCS WA A4.01)

1. Transfer Electrical Power from Start-up to Safeguard / Station Power

g. Initiate Containment Purge while in Mode 5 (029CPS KIA A1.02)

A, L, N, S A, N, S A. N, S, (062 AC Dist. Sys. WA A4.07)

A, N. S, L 1

2 3

4P 5

6 a

4 s I

i. Alignment of Fire Water to Auxiliary Feedwater Pumps P-8A & P-D.R (081 AFW WA A2.04)

I

ES-301 Control Roodln-Plant Systems Outline Form ES-301 I

System / JPM Title

a. Respond to a Control Rods Out of Sequence alarm. (001 CRDS KIA A4.14)

Facility:

Palisades Date of Examination:

Mav 2005 Exam Level (circle one): SRO-I Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

Operating Test No.:

Type Code Safety Function D, P, S 1

~~

C. Swapping Pressurizer Pressure Control Channels (010 PZR PCS KIA Al.07)

b. Establish the Containment Sump as the ECCS suction source following 2

and Large Break Loss of Coolant Accident (006 ECCS WA A4.05)

A, N, S 3

i. Alignment of Fire Water lo Auxiliary Feedwater Pumps P-EA & P-

j. Start the M-69B Hydrogen Recombiner (028 HRPS KIA A4.01)

D,R 88 (061 AFW WA A2.04)

D, R D

k. Isolate and Locally start Diesel Generator 1-1 (064 EDG A4.01) 11 d. h i a t e Shutdown Cooling for the PCS (005RHRS WA A4.01)

I A, L, N, S I 4P 4s 5

6 I

I

f. Transfer Electrical Power from Start-up to Safeguard / Station 1 A, N,S.

I 6

(1 Power (062 AC Dist. Sys. WA A4.07) 11 g. Initiate Containment Purge while in Mode 5 (029 CPS WA A1.02) I A, N, S, L I 8

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

(P)revious 2 exams IRICA 4-6 / 4-6 / 2-3 i 9 / <

E / < 4

> l / > l i 2 1 L 1 / 2 1 / L 1 22/22/21 s 3 / s 3 / < 2 (randomly selected) 2 l I > 1 / 2 1 I.,-..

(S)imulator 1

/-

ES-301 Transient and Event Checklist Form ES-301-5 E

Scenanos V

Circle the applicant level and enter the operating test number and Form ESD-1 event numbex for each event type; TS are not applicable for RO applicants. ROs must serve in both the.at-thecontmls (ATC) and balanopofplant (BOP) positions; Instant SROs must do one scenario, including at least two instrument or mmponent (IIC) malfunctbns and one major lamienf. in the ATC psilion.

Reactivity manipulations may be conducted under normal or contmlled abnmal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D.

• Reactivity and normal evolutions may be replaced Mth additional instrument or component malfunctions on a 1-fw-1 basis.

NRC Reviewer:

ES-301, Page 26 of 27

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

Palisades Date of Exam: 5/23/05 I

I Note:

1.

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 7ier Totals in each WA category shall not be less than two).

The point total lor 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 +I 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.

Systemdevolutions within each group are identified on the asscciated outline; Systems or ewlutions 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.

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 WAS 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.

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA 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 WA numbers, a brief description of each topic, the topics importance ratings (IRs) 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 duplicate pages for RO and SRO-only exams.

2.

3.

4.

5.

6.

7.

8.

9 For Tier 3, se ect topics from Sect on 2 of the U A catalog an0 enter Ine K A nLmoers descriptions IRs and PO nl totals ( R J on Form ES 401.3 Lim I SRO selections 10 WAS Ihal are n6ed 10 10 CFR 55 43

ES-401 2

Form ES-401-2 IR 4 3 39 3 5 2 6 3 1 30 3 3 39 3 1 4 1 4 5 4 5 3 4 2 9 3 5 3 4 3 5 x

1 I

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 E/APE # I Name I Safety Function 000007 (BWlE028E10: CE/E02) Reactor Trip - Stabilization - Recovery I 1 000008 Pressurizer Vapor Space Accident 13 K

K K

A A

G WA Topic@)

1 2

3 1

2 X

Ability to determine or interpret the following as they apply to a RX trip: Occurrence of a Rx trip (EA2.06)

Ability to pedorm specific system and integrated piant procedures during all modes of operation (2.1 23) x 000009 Small Break LOCA 1 3 X

Knowledge oi the Operational lmpilcalions of the following concept as they apply to a SBLOCA Use of Sleam tables (EKI 02) 00001 1 Large Break LOCA I 3 X

Knowledge ot the interrelations between the foilowing and a LBLOCA: Pumps Knowledge of the reason for the following as they apply to a 000015117 RCP Malfunctions 14 X

Knowledge of the reasons lor the following respanses as the apply to the RCP malfunctions (Loss 01 RC flow): Reduction 01 pawer to below the steady ~tate pawer-to-flow limit (AK3.04) 000022 -0% 01 Rx Coo ant Mac3i.p 1 2 X

AD I ty lo aperale anam mon81r I lne lo1 ow rig as lney app y 10 the LOSS 01 Rx Coa ant Mare.p CVCS cnarg ng low lloll alarm sensor. and ~1 cal on (AAI 02, 000025 Loss 01 RHR System 1 4 X

Abllity lo determine and interpret the following as they apply lo the Loss of RHR System Location and #solability of leaks (AA2 04) 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pressure Control System Malfunction 1 3 000029 ATWS I1 000038 Steam Gen. Tube Rupture 1 3 x

Ability to locate and operate companents, including local CO"llOlS (2.1.30)

X Knowledge of the Operational implications of the following concept as it applies lo Prr Pressure Control malfundons:

Definition 01 Saturation temperature (AK1 01)

X Knowledge of the reasons lor the following as it applies lo a SGTR: Criteria for securing I thronling ECCS (EK3.09) 000058 Loss of DC Power 16 X

Knowledge 01 the reasons lor the following responses a6 11 applies to a Loss 01 DC power Use 01 DC control pawer by DIGS (AK3 01)

~ n o w k d g e 01 the reasons for the followjng responses as II applies to the Loss 01 Nuclear Service Water Effect On the nuclear service water discharge flow header of a loss 01 000062 Loss of Nuclear Svc Water I 4 X

5

000065 Loss of Instrument Air I 8 W/EI 1 Loss of Emergency Coolant Recirc. / 4 BW/EO4; WlE05 Inadequate Heat Ability to operate or monitor the following as It applies to a Loss of Instrument Air components served by IA to minimize drain an System (AAl 02)

I WA Category Totals:

I 21 1 2 6 1

Group Point Total:

18

WOO03 Dropped Control Rod I 1 x

ow005 InoperablelStuck Control Rod I t WOO24 Emergency Boration I 1 x

OOW28 Pressurizer Level Malfunction I 2 Woo32 Loss of Source Range NI 17 WOO03 Dropped Control Rod I 1 x

ow005 InoperablelStuck Control Rod I t WOO24 Emergency Boration I 1 OOW28 Pressurizer Level Malfunction I 2 Woo32 Loss of Source Range NI 17 I I I l x Knowleage 01 tne reawns lor me lo1 ow ng responses as I appi es lo a aropped rW Cr ler a tar fnOperaDle coiilro mas (AA3 08 ES-401 3

Form ES-401-2 Abilily lo operate or monitor the following as it applies to Emergency Boration: Perlormance of the letdown system during emergency boration (AAI.05)

Abilily to determine and interpret the IOllowing as it applies to a Loss of Swrce Range NI: Salsladory source range I intermediate range overlap (AA2 04)

WOO33 Loss of Intermediate Range NI 17 WOO36 (BWlAO8) Fuel Handling Accident I 8 ooW37 Steam Generator Tube Leak I 3 I I x I Ability10 explain and apply all system limits and

~

000051 LOSS of Condenser vacuum 14 x

WOO59 Accidental Liquid RadWaSte Rel. I 9 x

WOO60 Accidental Gaseous Radwaste Rei. I 9 Knowledge of the reasons lor the following responses as it applies lo a Loss of Condenser Vacuum: Loss of steam dump capabilily upon a loss of condenser vacuum (AK3.01)

Knowledge 01 the interrelations between the Accidental Liquid Radwaste Release and the following: Radioactive-liquid moniIOr5 (AK2.01)

Knowledge of the reasons lor the following response as it applies to an Accidental Gasous Radwaste Release: lmplementation of the E-plan Ablily lo operate or monitor the following as it applies to Area Radiation Monitoring System Alarms. Automatic ACtUationS (AAt 01)

I I

I I

x Conective actions required for high fission product adivily !n PCS (AA2 02)

I I I

1 I

I I

I I I I

4 Form ES-401-2 ESdOl ES-401 Form ES-401-2 PWR Examination Outline t Systems.

1 1 (RO)

KIA Topic@)

Knowledge 01 the e n d Of a IOSS Or malfunction on the following will have On the RCPS: RCP seals and seal water supply (K6.02)

Ability to manually operate 01 monitor in the control rwm. RCP seal leakage detection instrumentation (A4 05)

Ability to predict or monitor changes in parameters (to prevent exceeding design limits) associated with Operating CVCS including: Tavg and Tret (Al.02)

Knowledge of surveillance procedures relating 10 the CVCS (2.2.12)

Knowledge of the physical connections or cause-enect relationships between the RHR system and the tollawing: CCW system(Kl 01)

Ability to predict the impacts 01 the following malfunctions an the RHR sys. and based on those predictions, use procedures to correct.

control, or mitigate the consequences of this malfunction or operation: RHR pumpimotor mallunction (A2 03)

Knowledge 01 bus power supplies lo the following: ESFAS operated valves (K2 04)

Ability to monitor automatic operation of the ECCS including: Safety injection pumps (A3.05)

Knowledge Of the effect that a IOSS Or malfunction of the PRT will have on Containment (K3 01)

Knowledge of CCW design features and interlocks which provide tor the following:

Automatic Stan of standby pump (K4 01)

Knowledge of the Operational implications Of the fallowing concepts as it applies to the PZR PCS: Determination of conditions 01 fluid in Pzr using steam tables (K5.01)

Knowledge 01 the en&

01 a loss or malfunction 01 the following will have on the RPS: Trip setpoint calcuiators (K6 I t )

Ability to predict 01 monitor changes in parametem (to prevent exceeding design limits) associated with operation of the ESFAS controls including Containment press. temp.

and humidity (At 02)

Ability to a) predict the impacts 01 the following malfunctions or operations on the Cnmt Cooling sys; b) based on those predictions.

use procedures to correct. control. or mitigate the consequences of the following mallunction or operation Loss of service water (A2 04) q 3.0 32 29 3 6 3 4 3 3 3.1 35

x Abiljly to manipulate the Controls as required to operate the faciiily between Shutdown and designate power levels (2.2.2)

Knowledge 01 the physical Wnnections or cause-eflect relationship between the MFW sys and the following system. RCS (K1 05)

Knowledge of bus power supplies to the fallowing: AFW electric driven pumps (K2.02)

Knowledge of the eftect that a loss or malfunction 01 the AC distribution System will have on the following: D/Gs (K3.02)

Knowledge 01 DC electrical System design features or interlocks which provide for the following, ManuaVAutOmatic transfer 01 control Knowledge of the e n m of a loss or malfunction of the following will have an the DIGS: Fuel ail storage tanks (K6.06)

Knowledge of the operational implications as they apply to concepts invoivtng the PrOCeSS Radiation Monitoring system: Radiation intensity changes with source distance (K5 02)

Knowledge of the eflect that a IOSS or malfunction 01 the Sewice water System will have on the following: ESF loads (K3.07)

Ability to predict or monitor changes in parameters (to prevent exceeding design limits) assmiat& with operating the Service water system controls including: Rx and turbine bldg closed cooling water temps.

I (K4.01)

I (A1 42)

Knowledge of IA system design features or intedocks which provide for the following' Systems having pneumatic valves and contro1s (K4.02)

Ability to monitor automatic operation of the IA system including: air pressure (A3.01)

Knowledge of Cnml system design IeStureS or interlocks Which provide for the following.

Containment Isolation system (K4.06)

Ability lo monitor automatic operation Of the containment system including. Containment iSolation (A3 01) 4 0 3 1 3 7 4 1 2 7 3 2 2 5 3 7 2 6 3 4 3 1 3 1 3 9 1

1 1

1 1

1 1

2 2

2 2

2 Group Point Total:

28

KJA Categorv Point Totals:

1 1 1 1 ) 1 ) 11 0 ) 1 ) 11 1 ) 1 ) 1 ) 2 ) GrwpPoinlTalal:

11

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 ermissible levels in

~

ES-401 2

Form ES-401-2 WOO38 Steam Gen Tube Rupture I 3 ES-401 PWR Examination Outline Form ES-401-2 X

Knowledge 01 radiation emsure limits and contamination 3.1 1

control. including permissible levels in excess of those authorized ( 2.3.4) mMD (BwlEo5: CWE05. WIE12) Steam Line Rupture. Excessive Heat Transfer I 4 X

Ability lo determine and interpret the following as 11 applies 4 2 1

to a steamline rupture: Adherence to appropriate procedures and operation within the limitations in the tacilivs license and amendments (EA2.2) 000056 Loss 01 On-site Power I 6 X

Ability to determine and interpret the following as it applies 4 6 1

to the Loss 01 OH-Site Power. Operational Status 01 Emerge-DIGS (AA2.14) forthe Sewice I l l I I I

I WA CateQOry Totals:

I I

I I

I 3 1 3 I Group Point Total:

1 6

ES-401 3

Form ES-401-2 lions in the facililfs license and

CElAl6 Excess RCS Leakage I 2 CEIEOS Funcllonal Recoven/

KIA Category Point Totals 2

2 Group PoinITatal 4

4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 063 DC Electrical Distribution

ES-401 5

Form ES-401.2

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility:

Palisades Date of Exam:

5/23/05 I

12 133 I

+

! 4.0 I 1

Appendix D Scenario Outline FOITII ES-D.

Event No.

I Facility: PALISADES Scenario No.: 1 Op-Test No.: I Examiners:

Operators:

Initial Conditions:

Turnover:

60% power. P-7B Service Water Pp. is out of service.

Shift orders are to alternate Component Cooline Water Pumus, and then continue a power ascension.

Malf. No.

Event Event Type*

Description SRo (N)

RO (N)

SRO (N)

Alternate operating CCW pps.

N/A 2

3 4

5 6

NIA RO (R)

Power ascension.

BOP (N)

SRo (I)

BOP (I)

RP24 SRo (')

CC02 CC13 RO (C)

SRo (')

RO (C)

CC03 SRo (')

RO (C)

Cold Leg #I RTD fails high.

CCW pp. trips; standby fails to start.

CCW system leak (isolable per OW-6.2).

P-50A PCP bearing high temperature. Requires manual reactor trip.

RC09A 7

8 SRo BOP (C)

SRO (M)

Main Turbine Fails to Auto or Manually Trip.

TC02 MS03A RO (M)

Main Steam Line Break Inside Containment (EOP-6.0).

9 I

SRo I Containment Spray Fails to Auto Actuate.

RO (C)

CH05

~~

10 I

SRo (')

1 Containment Isolation Fails to Auto or Manual Actuate RO (C)

CH05

Form ES-D-3pendix D Scenario Outline

-acility: PALISADES Scenario No.: 2 Op-Test No.:

1 Ixaminers:

Operators:

nitial Conditions:

rurnover:

86% power. P-8B AFW Pp. is out of service.

Shift orders are to Test Cycle Cont. Spray Valves, per SOP-4.

Event No.

1 -

2 3

4 -

5 6 -

7 -

8 9 -

Vlalf. No.

NIA RX09 NIA OVRD OVRD FTOl N B OVRD ED12B IAl7NC FW16NC SRO (T)

SRO (C)

BOP (C)

SRO (C)

BOP (C)

RO (R)

SRO (C)

BOP (C)

SRO (M)

BOP (M)

~

Event Description Test Cycle Containment Spray Valves (SOP-4).

PZR Normal Level Control signal fails low.

Report of Lube Oil Inventory Low Turbine Bypass Valve fails open (ONP-9).

Cooling Tower Pp. P-39A trips (ONP-14), and Rapid Downpower (due to degrading vacuum). (ONP-26).

BOTH Main Feedwater Pps. trip, requiring Manual Reactor Trip.

Safety Bus 1 D deenergizes, and DIG 1-2 fails to auto start.

Instrument Air Compressors fail to auto start.

P-8A AFW Pp. trips, P-8C will not start. (EOP-7.0).

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

Appendix D Scenario Outline Form ES-D-1 Event Malf.

Event No.

No.

Type*

1 N/A RO(R)

SRO(N) 2 RX06B RO(I)

SRO(l) 3 RXlOA BOP(I)

SRO(l) 4 SWO4B BOP( C)

SRO( C) 5 RC03 RO( C)

SRO( C) 6 OVRDs BOP/RO

( C)

SRO( C) 7 RC04 RO(M)

BOP(M)

SRO(M)

Facility:

Palisades Scenario No.:

NRC 2005-3 Op-Tesl No.:

Event Description Increase Rx power from 86% power PZR Press Controller output Fails Low S/G 'A' Level Transmitter LT-701 output Fails Low.

Service Water Pump P-7B Trips (P-7C will need to be manually started to increase SW pressure)

PCS leak (25 gpm) (Tech Spec).

Severity =25 Initiate Rx Trip per ONP-23.1, Failure of Rx to Trip from either Rx Trip pushbuttons.

Small Break LOCA (250gpm)

Value = 25%

Examiners:

Operators:

a 9

I I

ED1 3A I B S107AI B

SI01 A SRO (.

c>

BOP( C )

SRO( C)

Failure of SlAS to automatically or manually actuate.

P-66A Trips on ground over-current when manually started (no HPSl flow available).

I I

II I

I I

(N)ormai. (R)eactivity.

(i)nstrument, (Qomponent.

(M)ajor

Scenario Outline Form ES-D.

Facility:

Palisades Scenario No.:

NRC 2005-4 p-Test No.:

Examiners:

Operators:

Initial Conditions:

IC-1 7 100% Dower, MOL. D/G 1 - 1 taaaed out of service.

Turnover:

100% Dower, MOL. D/G 1-1 taaaed out of service for a aovernor reDlacement and is scheduled to be returned in 3 days. Boron 770 DDm. AS1

+0.014. S/G blowdown flow 20K Der S/G, Offaas flow is 2.0 cfm.

Event No.

1 2

3 4

5 6

7 a

Malf.

No.

RX07B OVRD S

CV06 CH06 A

EGO4 OVRD SGOl A

S MS06B xmal, 0 Event Type RO (C)

SRO(C)

BOP(I)

SRO(l)

RO(I)

SRO(l)

SRO BOP (C)

SRO BOP( C)

SRO( C) cr.c>

RO(M)

BOP(M)

SRO(M)

?activiW. (I)

Event Description Pressurizer Level Transmitter LT-0101 B fails low.

LIC-0702 output fails low in automatic. Feed Reg Valve closes and must be re-opened by taking manual control of LIC-0702.

PT-0202 fails low which causes letdown pressure controller PIC-0202 to close letdown control valve. This causes letdown line relief valve to oi3en. Uech Spec)

Earthquake reported b y Outside AO.

Determines Control Room HVAC unit tripped Qech Spec).

Generator Voltage Regulator failure causes Main Generator voltage to increase.

A Steam Generator tube leak starts at 10 gpm.

SRO to determine PCS leakage Tech. Spec. is being exceeded and a Rx Trip is required gech Spec).

B Steam Generator fault occurs due to a Main Steam Line Code Safety valve failing open.

~

~

~

~

trument, (C)ornDonent, (Mhor. Oech SDec