IR 05000400/2004301
| 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
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FEBRUARY 23 27,2004
& MARCH 4,2004 (WRITTEN)
NR
ES-301 Administrative Topics Outline FORM ES-301-1 Date of Examination:
Examination Level: SRO Operating Test Number: i Describe Activity to be Performed Administrative Topic (see Note)
Perform a manual Shutdown Margin Calculation per OST-1036 Conduct of Operations (2.1.25-NA13.1)
Determine Average RCS Boron Concentration per EOQ-EPP-002 Conduct of Operations (2.1.20 4.3 14.2)
Determine clearance requirements for a CSIP per OPS-NGGC-1301 Equipment Control (2.2.13 - 3.6 13.8)
Determine entry conditions for a High Radiation Area per AP-5(
Radiation Control (2.3.10 2.3 I 3.3)
~
Determine Protective Action Recommendations per PEP-110 Emergency Plan (2.4.44 - NA 14.0)
VOTE: All items (5 total) are require1 ir SROs. RO applicants require only 4 items unless they are Waking only the administrative topics, when 5 are require 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 Administrative Topic (KA#-ROlmpISRBlrnp)
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
ES-301 Control Room / In-Plant Systems Outline FORM ES-3014 Facility HARRIS Bate of Examination Examination Level RO Operating Test Number 1 Control Room Systems ( 8 for 8 0 . 7 for SRO-I, 2 or 3 for SRO-U)
Safety SystemNPM Title Function (KAlb- KO Imp) Transfer 6.9KV Buses from Unit Auxiliary Transformers to the 6 NlAlS Startup Auxiliary Transformers per OP-156.02 (06284.07 - 3.i) Perform Containment Cooling System Operability Test per OST-1090 I DJS
(022A4.01 - 3.6) Perform an Emergency Boration per WOP-002
(000024AA2.01 - 3.8)
Transfer SG Level Control to the Main Feedwater Regulating 45 Bypass Valves per OP-134.01 (05984.03 - 2.9) Transfer to Cold beg Recirculation per EOP-EPP-010 (006A4.05 - 3.9)
Perform Control Rod and Rod Position Indicator Exercise per OS-1005 I DlAlS (OOlA2.11
- 4.4)
is Place Audio Count Rate Drawer in Service per OP-105 (015A4.02 - 3.9) Align CCW to Support RHR System Operations per OP-145 (008A4.03 - 3.3)
In-Plant Systems (3 for RO;3 for S80-I; 3 or 2 for SRO-U)
J'
Perform Mode 6 Inadvertent Dilution Component Lineup per OQ-107 I MIAIR
(004A2.06- 4.2)
Perform local actions for placing an OTAT channel in Test per 7 OWP-RP5I (012A4.04 - 3.3) Locally operate 8 SG PORV per EOP-EPP-012 and OP-126
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(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)
System/JPM Tile I I
Type Code" safety Function ( K A # - S R O Imp) Transfer 6.9KV Buses from Unit Auxiliary Transformers to the 6 NIAIS Startup Auxiliary Transformers per OP-156.02 (062A4.07 - 3.1) NOT APPLICABLE FOR SRO-U Perform an Emergency Boration per AOP-002 (000024AA2.01 - NOT APPLICABLE FOR SRO-U NOT APPLICABLE FOR SRO-LJ NOT APPLICABLE FOR SRO-U I
NOT APPLICABLE FOR SRO-U I
NOT APPLICABLE FOR SRO-'J i
In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRB-U)
I I Perform Mode 6 lnadveitent Dilution Component Lineup per BP-107 I 1 (00442.06- 4.3)
j' Perform local actions for placing an QTAT channel in Test per OWP-RP-01 (012A4.04 - 3.3) Locally operate a SG PORV per EOP-EPP-012 and OP-126 I D'R I 45 (00O074EAl.04 -4.1)
"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: 1 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 P u m p and one Condensate Booster Pump is in service. Ensure a Reactivity Plan is provide Turnover: T h e 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 service.
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: 2 Op-Test Number:
Examiners Operators Initial Conditions: IC-18; 100% power BOL; AFW Pump A-SA 0 0 s (CFW027 RACK-OUT); HLlP A 00s (CND065 RACK-OUT)
Turnover: 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 P u m p 'A' to service when it becomes available. GP-005 has been completed and the plant has bmn stable for 3
- weeks Event Number I
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Ll[alfunction Number Pr:308~
1300 90 Event Type*
I (Imp)
I (SRO)
Event Description S/G A PORV Pressure Transmitter PT-3Q8 fails high with failurc of S/G A PORV open indication XB10007B OFF 2 LT112 100 1 (W LT-112,VCT Level, High Failure 0 I (SROO)
3 CRF3A 2 Dropped Control Rod F2 F2 4 NA Power Reduction 5 mC-23A Boric Acid Pump Trip Page 1 o f 2 0 SCENARIO #2 NUREG-1021, Revision 9, Draft Development Rev Date B 1/24/03
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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
a Appendix D Facility: HARRIS Simulator Scenario Outline Scenario Number: 3 Op-Test Number:
FORM ES-D- i Examiners Operators Initial Conditions: IC-20; 100% power EOL; AFW Pump . . A-SA
.. . OOS
. . . . (CFW027
.. . . KACK-OUT);
. HDP A 0 0 s (CND065RACKLOW)
Turnover: 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 n e x t 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 n o t 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 Shift Operating CXP Page 1 of I 8 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 Faclllty HAKRlS Date ofExam ~T/.&J{
Notes:
I 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 K O 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 iOCEK55.43or 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 lAK3.01 - Reasons for the following: Shift to 1 I Pressure Control Malfunctions and Controllers !
n IKeactor iiuclear instrumentation r.- I IIGZ I .36 - Operate 1monitor the following: I I 1 I\
ICooldown of RCS to specified temperature I I I I I I I WEI2.EK2.I - Knterrelations hetween I I I I II I I!iicontrolled Depressurization of all SGs and Components 1 functions of control and safety following: ERects of feedwatcr introduction on I I I I __ I I IEA1.07 - Operate 1monitor the following: I I procedures I I I I I I IEKI. 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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mi iga iiin s ra egies 0003s Steam Gen. Tube Rupture 1 3 etermine ! interpret t n
lsafety iimits I I 2.2.25 -Rases in technical specifications for I I I l l 00062 I oss of Nuclear Svc Water 1 I I I N U R E G 102 I 1)rilft Revision 9
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lks-401 PWR Examination Outline Form I:S-40 I
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Controls i components necessary to recover rod 00060 Accidental Gaseous
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X I I l O p e d n g behavior characteristics of thc faciiit>1 1 ooling 4 (PSA)
High Reactor Coolant I I I L .........- ........
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l ~ , > l ......
3:
.
. i l . : 11....
.i NURT:G-IO?I, Draft Revision 9
PWK E~aininationOutline 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 Iparameters including: RCP vibration I l lAl.06 - Predict! monitor changes in - I I 2 lparameters including: VCT level I l lA2.06 - Control / mitigate Inadvertent I lresult o f a safety injection sign1 I l lK I .06 - Cause-effect relationships I I I lbetween PZK PCX and cvcs I K2.01 - Power supplies to RPS channels I I Ithe following: Containment 1 ~ 6 . 0-1~ffeccofloss imalfunction on I IESFAS: Sensors and detectors I I on ammeii I I __ 1 2 . 1 . 2 ~- Purpose 1 functioii of major 2 A
I l lsystem components icontrols I I
_,
A IA4.08 - Operate imonitor: F e d I I 2 lregulating valve controller IK4.19 - Design feature(s) 1 interlock(s) I lintensity changes with source distance I I l lKl. IS Connections icausc-effect I I Irelationships between S W S and IPS K3.02 - Effect of loss imalhnction (!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 I I I Steam DunipITurbine I I I IA3.02 - Automatic isolation of Liquid I 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 1 2 I 1 b
12. I Ability to perform p r e s t a m p procedures, including I 3.1 I
E S - ~ dA&S Record of Rejected KlAs ddL4 Form ES-401-4
-.. ....
Randomly Selected IGA Reaon for Rqjection
.. .
.
000005AK2.03 Selected - Replaced due to S m P P not having a metroscope. Replaced by next randomly ordered 00000SA4K2item (000005AK2.02)
1 2/1 076K1.08 NOT Selected .. Same system & category previously selected (076K1.15)
I 211 076K1.21 ~.
KOT Selected - - Same systeni & category previously selected (076K1.15)
059.44.01 Selected - Replaced due to SHhPP not having turbine driven feed pumps. Replaced by next randomly ordered 059.44
~.
item
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(059A4.08) .......
026.42.02 Selected - Replaced due to SHNPP not having auto transfer of CS. Replaced by next randomly ordered 026.42 item..........
~~
(026A2.08)
028G2.4.49 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- 1021, Draft Revision 9
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HARRIS 2804 INITIAL LICENSE NRC EXAM 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 replaced.
..... ..-
....
Question H on Exam
, ..
~
C : u r r e n t K / T - % a s i s for neTded replacemen(
5
......
Generic 2. There is no 43(b) tie to this WA I
Generic 2. The SRO population does not prepare nor approve RWPs. There is no 43(b) tie to this WA
.
24 000058G2.2.25
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No information is in our Technical
--I 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