IR 05000400/2004301

Feb-March 2004 Exam 50-400/2004-301 Draft Outlines

ML041170067
Person / Time
Site:	Harris
Issue date:	10/30/2003
From:	Ernstes M Operator Licensing and Human Performance Branch
To:	Scarola J Carolina Power & Light Co
References
50-400/04-301 50-400/04-301
Download: ML041170067 (23)

Text

ITIAL su HARRIS EXAM 50-40012004-301 FEBRUARY 23 - 27,2004

& MARCH 4,2004 (WRITTEN)

NR

ES-301 Administrative Topics Outline FORM ES-301-1 Describe Activity to be Performed (KA # - RO Imp 1 Si30 Imp)

Perform a manual Shutdown Margin Calculation per OST-1036 (2.1.25-NA13.1)

Date of Examination:

Examination Level:

SRO Operating Test Number:

i Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan VOTE: All items (5 total) are require1 Waking only the administrative topics, when 5 are require Determine Average RCS Boron Concentration per EOQ-EPP-002 (2.1.20 4.3 14.2)

Determine clearance requirements for a CSIP per OPS-NGGC-1301 (2.2.13 - 3.6 13.8)

Determine entry conditions for a High Radiation Area per AP-5(

(2.3.10 ~ 2.3 I 3.3)

Determine Protective Action Recommendations per PEP-1 10 (2.4.44 - NA 14.0)

ir SROs. RO applicants require only 4 items unless they are NUREG-?021, Draft Revision 9 Post Validation Revision

ES-301 Administrative Topics Outline FORM ES-301-1 Operating Test Number:

Describe Activity to be Performed (KA#-ROlmpISRBlrnp)

Administrative Topic Determine Reactor Vessel Head venting time per EOP-EPP-FR Conduct of Operations Determine Average RCS Boron Concentration per EOQ-EQP-Conduct of Operations Determine clearance requirements for a CSlP per OPS-NGGC-Equipment Control Determine entry conditions for a High Radiation Area per AP-50 Radiation Control (2.3.10 - 2.9 13.3)

MOP APPLICABLE FOR RO Emergency Plan NUREG-1021, Draft Revision 9 Post Validation Revision

FORM ES-3014 ES-301 Control Room / In-Plant Systems Outline Facility HARRIS Bate of Examination Examination Level RO Operating Test Number

Control Room Systems ( 8 for 80.7 for SRO-I, 2 or 3 for SRO-U)

SystemNPM Title N l A l S Transfer 6.9KV Buses from Unit Auxiliary Transformers to the Startup Auxiliary Transformers per OP-156.02 I DJS Perform Containment Cooling System Operability Test per OST-1090 Perform an Emergency Boration per WOP-002 Transfer SG Level Control to the Main Feedwater Regulating Bypass Valves per OP-134.01 Transfer to Cold beg Recirculation per EOP-EPP-010

D l A l S I

Perform Control Rod and Rod Position Indicator Exercise per OS-1005 Place Audio Count Rate Drawer in Service per OP-105 Align CCW to Support RHR System Operations per OP-145 In-Plant Systems (3 for RO; 3 for S80-I; 3 or 2 for SRO-U)

M I A I R I

Perform Mode 6 Inadvertent Dilution Component Lineup per OQ-107 J'

Perform local actions for placing an OTAT channel in Test per OWP-RP5I Locally operate 8 SG PORV per EOP-EPP-012 and OP-126 Safety Function (KAlb-KO Imp)

(06284.07 - 3.i)

(022A4.01 - 3.6)

(000024AA2.01 - 3.8)

(05984.03 - 2.9)

(006A4.05 - 3.9)

(OOlA2.11 - 4.4)

is (015A4.02 - 3.9)

(008A4.03 - 3.3)

(004A2.06 - 4.2)

(012A4.04 - 3.3)

(000074EAd.84 - 3.9)

'Type Codes: (8)irect from bank, (M)odified from bank, (N)@w, (A)lternate path, (C)ontrol Room, (S)imuBabar, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9 Development Rev. Date 12/08/03

ES-301 Control Room / In-Plant Systems Outline FORM ES-301-2 Facility:

HARRIS Date of Examination: &3/-

?/?/!zdq Examination Level, SRQ-U Operating Test Number

/

Control Room Systems (8 for WO; 7 for SRO-I; 2 or 3 for SRO-U) I System/JPM Tile I

Type Code" N I A I S Transfer 6.9KV Buses from Unit Auxiliary Transformers to the Startup Auxiliary Transformers per OP-156.02 NOT APPLICABLE FOR SRO-U Perform an Emergency Boration per AOP-002 NOT APPLICABLE FOR SRO-U NOT APPLICABLE FOR SRO-LJ I NOT APPLICABLE FOR SRO-U I

NOT APPLICABLE FOR SRO-U safety Function (KA#-SRO Imp)

(062A4.07 - 3.1)

(000024AA2.01 - i NOT APPLICABLE FOR SRO-'J In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRB-U)

I I

I (00442.06 - 4.3) Perform Mode 6 lnadveitent Dilution Component Lineup per BP-107 (012A4.04 - 3.3)

j'

Perform local actions for placing an QTAT channel in Test per OWP-RP-01 45 I D'R I (00O074EAl.04 -4.1)

Locally operate a SG PORV per EOP-EPP-012 and OP-126

"Type Codes: (D)irect from bank, (M)odified from bank, (N)ew. (A)lternate path, (C)ontroI Room, (S)imulato (L)ow-Power, (R)CA NUREG-1021, Drafi Revision 9 Development Rev. Date 12/08/03

Sininlator Scenario Outline FORM ES-D-1 Facility:

mKRIS Scenario Number:

Op-Tst Number:

Ex'miners Operators Initial Conditions: PC-14; 52% pow^^ EOL; AFW Pump A-SA 00s (CFW027 RACK-OUT); Ensure DEH HOLD button is illuminated. Ensure only one Condensate Pump and one Condensate Booster Pump is in service. Ensure a Reactivity Plan is provide The unit is at 52% power at EOL, 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a reactor startup from Xenon-free condition Boron concentration is 586 ppm. Bank D rods are at 167 step AFW F'ump 'A' was taken out of sewice 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for oil replacement due to contaminants and is expected to be returned to service within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Technical Spccification 3.7.1 2 has been entere Shift orders are to place the second Condensate Train in service and continue the power ramp to 90% power and restore W W Pump 'A' to service when it becomes zvailabl GP-005 is being performed per Step 5.0.133. The CPD Operator has informed you that sufficient CPDs are jn servic Turnover:

Page 1 of 26 SCENARIO #I wUlU3G-IO21, Revision 9, Draft Development KevDate 11/23/'03

Page 2 of26 SCENARIO ##l NUREG-1021, Revision 9, Draft Development Rev Date B 1 /23/03

Appendix L)

Simulator Scenario Outline FORM ES-D-I Facility:

FARRIS Scenario Number:

Op-Test Number:

Examiners Operators Initial Conditions: IC-18; 100% power BOL; AFW Pump A-SA 00s (CFW027 RACK-OUT); HLlP A 00s (CND065 RACK-OUT)

Turnover:

Event Number I

3

5 The unit is at 100% power at BOK., with equitibrium xenon condition Boron concentration is I238 ppm. Bank D rods are at 21 8 step AFW Pump 'A' was taken out of service 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for oil replacement due to contaminants and is expected to be returned to senice within the next 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Technical Specification 3.7.1.2 has been entere IIDP 'A' is tagged out of service for bearing rcpIacement and is not expected back for the next several day Shift orders are to maintain power at 100% and restore AFW Pump 'A' to service when it becomes available. GP-005 has been completed and the plant has bmn stable for 3 weeks Ll[alfunction Number P r : 3 0 8 ~ -

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1300 90 XB10007B OFF LT112 100

CRF3A 2 F2 NA mC-23A Event Type*

I (Imp)

I (SRO)

1 (W I (SROO)

Event Description S/G A PORV Pressure Transmitter PT-3Q8 fails high with failurc of S/G A PORV open indication LT-112, VCT Level, High Failure Dropped Control Rod F2 Power Reduction Boric Acid Pump Trip Page 1 of20 SCENARIO #2 NUREG-1021, Revision 9, Draft Development Rev Date B 1/24/03

~

Pressurizer Steam Space Break 600 NIS Intermediate Range Compensating Voltage I.ow Failure

• (N)ormai, (K)eactivity, mnstrument, (C)omponent, (M)ajor Page 2 of20 SCENAWO #2 NUREG-IO21, Revision 9, Draft Development Rev Date 11/24/03

Appendix D Simulator Scenario Outline FORM ES-D-i a

Facility:

HARRIS Scenario Number:

Op-Test Number:

Examiners Operators Initial Conditions: IC-20; 100% power EOL; AFW Pump

.. A-SA

..

. OOS

..

.. (CFW027

..

.. KACK-OUT);

.

HDP A 0 0 s (CND065 RACKLOW)

The unit is at 100% power at EOL, with equilibrium xenon condition Boron concentration is 3M ppm. Bank D rods are at 218 step AFW Pump 'A' was taken out of service 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for oil replacement due to contaminants and is expected to he returned to service withixi the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Technica Specification 3.7.1.2 has been entere HIP 'A' is tagged out of service for bearing replacement and is not expected back for thc next several day Shift orders are to maintain power at 100%, restore AFW Pump 'A' to sewice when it becomes available, and shift operating CSPs for inspection of C S l p 'A' bearing. GP-005 has been completed and the plant has heen stable for 3 week Turnover:

Shift Operating CXP Page 1 of I8 SCENARIO #3 NUREG-1021, Revision 9, Draft Development Rev Date 12/03/03

• (N)onnaI, (R)eactivity, (Qnstment, (C)omponent, (M)ajor Page2of18 SCENARIO #3 NUKEG-1021, Revision 9, Draft Development Rev Date 12/03/03

ES-401 PWR Examination Outline Form ES-401-2 Date ofExam ~T/.&J{

Faclllty HAKRlS Notes:

I

3

5 6%

8

Ensure that at least two topics from eveiy KL4 category are sampled within each tier of the KO outline (i.c.* the Tier Totals in each KIA category shall not be less than two). Refer to Section D. I.c. for additional guidance regarding SRO samplin The point total for each group and tier in the proposed outline musf 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 KO exam must total 75 points and the SKC)-only exam must total 25 point Select topics from many systems; avoid selcc.ting more than two W.4 topics froni a given or evolution unless they relate to plant-specific piioritie Systems!evolutions within each gronp are identified on the associated outlin The shaded areas ore not applicable to the categoryhie The genei~ic ((3) KiAs in Tiers I and 2 shall he selected from Section 2 of the KiA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO KiAs must also be linked to iOCEK55.43 or an SKO-level learning objectiv On the following pages, enter the W A numbers, a brief description of each topic, the topics importance ratings [IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table abuw; surnrnarize all the SRO-only knowledge and non-A2 ability categories in the column labeled K and A. IJse duplicate pages for RO and SRO-only exani Foi Tier 3. enter the KIA numbers, descriptions, importance ratings. and poincs totals on Form ES-401-Krfer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate KIA setcementa NUREG-IO2 I Dreft Revision 9

PWR Examination Outluic Folm ES-401-Emergenc)

ecoveryl I I

Pressurizer Vapor Space A labnormal operating procedures I

I I

l l

AK3.01 - Reasons for the following: Shift to 1 I Pressure Control Malfunctions and Controllers !

n IKeactor iiuclear instrumentation

-

.

r

I I

IGZ I.36 - Operate 1 monitor the following:

I 4.3 I

I\\

ICooldown of RCS to specified temperature I

I I

I I

I I

WEI2.EK2.I - Knterrelations hetween I 3.4 I I

I!iicontrolled Depressurization of all SGs and I

I I I Components 1 functions of control and safety following: ERects of feedwatcr introduction on I

I I

I I

I I

_ _

EA1.07 - Operate 1 monitor the following:

I I procedures I

I I

I I

I I

EKI. I - Opetational implications of the I

following: Components, capacity, 1 function of NUREG 102 1. Draft Revision 9

PWR rxamination Outline Form tS-40 I -

Emergency and Abnq

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0003s Steam Gen. Tube Rupture 13 I

l l

00062 I oss of Nuclear Svc Water 1 I I I

mi iga iiin s ra egies etermine ! interpret t n lsafety iimits I

I 2.2.25 -Rases in technical specifications for I

I NUREG 102 I 1)rilft Revision 9

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Form I:S-40 I lks-401 PWR Examination Outline

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00060 Accidental Gaseous

....

ooling 4 (PSA)

High Reactor Coolant I

L

........

........

.....

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1 l

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,

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l

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.

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Controls i components necessary to recover rod

1

X I I l O p e d n g behavior characteristics of thc faciiit>

I I

NURT:G-IO?I, Draft Revision 9

PWK E~ainination Outline Form tS-40 I Emergency and Ahnormal Pli e ernline, in I

I I

NUKEG-I021, Di-aft Kevisiori 9

'S-401 PWR Examination Outline Form ES-401 on ammeii Iparameters including: RCP vibration I

l l

Al.06 - Predict! monitor changes in I I

lparameters including: VCT level -

I l

l

A2.06 - Control / mitigate Inadvertent I lresult ofa safety injection sign1 I

l l

KI.06 - Cause-effect relationships I 2.9 I I

lbetween PZK PCX and cvcs I K2.01 - Power supplies to RPS channels 3.3 I I

Ithe following: Containment 1 ~ 6. 0 1

- ~ffecc ofloss i malfunction on I IESFAS: Sensors and detectors I

I I

I

_ _ 12.1.2~

- Purpose 1 functioii of major

I l

l

A system components i controls I

I

_, IA4.08 - Operate i monitor: F e d I 3.0 I

A lregulating valve controller IK4.19 - Design feature(s) 1 interlock(s) I lintensity changes with source distance I

I l

l

Kl. IS Connections i causc-effect I I Irelationships between SWS and IPS K3.02 - Effect of loss i malhnction (!n I I I

NIJRECi-102 I. Draft Revision 9

I >

I s-401 Form FS-401-2 I

Plant Syster elief'0uench Tank Component Cooliiig

- Contro ! niltigate NUREG-l02L, Draft Revision 9

s-40 I PU'R Examination Outline Form FS-401-015 Xuc ear lnstrunientatioi Steam DunipITurbine I

I I

I I

I IA3.02 - Automatic isolation of Liquid I 3.6 I I

NITKEG-102 I. Draft Kwision 9

NUREG-I02 I, Draft Revision 9

5.401 beneric Knowledge and Ahilihes Outline (Tier 3)

Form FS-401-2 (Subtotal b

1

I 12. I Ability to perform prestamp procedures, including I 3.1 I

E S - ~

dA&S Record of Rejected KlAs d d L 4 Form ES-401-4

2 / 1 I

211 Randomly Selected IGA

..

000005AK2.03 076K1.08 076K1.21

~.

059.44.01 026.42.02 028G2.4.49

.............

-..

....

Reaon for Rqjection

..

Selected - Replaced due to S m P P not having a metroscope. Replaced by next randomly ordered 00000SA4K2 item (000005AK2.02)

NOT Selected.. Same system & category previously selected (076K1.15)

KOT Selected - - Same systeni & category previously selected (076K1.15)

Selected - Replaced due to SHhPP not having turbine driven feed pumps. Replaced by next randomly ordered 059.44 item (059A4.08)

Selected - Replaced due to SHNPP not having auto transfer of CS. Replaced by next randomly ordered 026.42 item (026A2.08)

Selected - Replaced due to no immediate actions associated with this system. Replaced by next randomly ordered 028G item (02862.2.22)

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SUREG-102 1, Draft Revision 9

~

HARRIS 2804 INITIAL LICENSE NRC EXAM Generic 2. To Jerry Laska and Lee Miller:

The following table describes the question number on the SRO Written Exam and the reason that tlmc (3) SRO KAs that were chosen randomly on the Sample Plan need to be replace The SRO population does not prepare nor approve RWPs. There is no 43(b) tie to this WA

.....

..-

Question H on Exam

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....

..

,

......

.

1 C : u r r e n t K / T - % a s i s for neTded replacemen(

Generic 2. There is no 43(b) tie to this WA I

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--I 000058G2.2.25 No information is in our Technical Specifications or bases related to 1 the loss of DC Per our discussion on 1/27/04 you will he providing the replacement WA Thank you, Harner Carter Supervisor Operator Initial Programs Page 1 of 1 2/5/2004