ML060230012
| ML060230012 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/07/2005 |
| From: | Nuclear Management Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML053610144 | List: |
| References | |
| 50-266/05-301, 50-301/05-301 50-266/05-301, 50-301/05-301 | |
| Download: ML060230012 (30) | |
Text
EXAMINATION OUTLINE FOR THE POINT BEACH INITIAL EXAMINATION - NOVEMBER 2005
Point Beach Nuclear Plant Commitled lo Nuclear Excellence Operated by Nuclear Management Company, LLC August 18,2005 NRC 2005-0101 Mr. Hironori Peterson, Branch Chief Operator Licensing U. S. Nuclear Regulatory Commission 2443 Warrenville Road, Suite 210 Lisle, IL 60532-4352 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 License Nos. DPR-24 and DPR-27 Initial ODerator License Examination Outline
Reference:
NRC to NMC Letter dated July 13, 2005 In accordance with the requirements listed in the referenced letter, Nuclear Management Company, LLC (NMC) is submitting the initial license examination outline for the Point Beach Nuclear Plant. This submittal is made in accordance with the provisions of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors," Revision 9. The initial license examination is scheduled for November 7-18, 2005. The following materials are included in the
Enclosure:
One Form ES-201-2, Examination Outline Quality Checklist and associated Explanation of Random Generation Technique One Form PBF-6805, Examination Security Agreement (Form ES-201-3 equivalent)
Two Forms ES-301-1, Administrative topics Outline (Reactor Operator [RO] and Senior Reactor Operator [SRO])
Three Forms ES-301-2, Control Room/ln-Plant Systems Outline (RO. SRO and Upgrade SRO)
Five Forms ES-301-5, Transient and Event Checklist (one for each proposed crew)
Four Forms ES-D-1, Scenario Outline (one for each projected scenario)
One Form ES-401-2, PWR Examination Outline One Form ES-401-3, Generic Knowledge and Abilities Outline (Tier 3)
One Form ES-401-4, Record of Rejected WAS 6610 Nuclear Road Two Rivers, Wisconsin 54241-9516 Telephone: 920.755.2321
Document Control Desk Page 2 Pursuant to the provisions of NUREG-1021, Revision 9, these materials shall be withheld from public disclosure until after the examinations are complete.
Please contact Paul Smith at (920) 755-6416 if you have any questions regarding this submittal.
This letter contains no new commitments and no revisions to existing commitments MD Dennis L. Koehl Site Vice-president, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosure
ENCLOSURE POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 INITIAL LICENSE EXAMINATION OUTLINE 26 Pages Follow
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Date of Examination:
-Item Task Description a
1.
W
- a. Verify that the outline(s) fit@)the appropriate model. in accordance with ES401 /i&
~~
R b Assess whetner the out1 ne was systemat ca..y an0 randomly preparea n accaraance mth I S e a m D 1 01 ES-401 ana whetner al &/A wtegorres are appropriately sample0 T
c ASSCSS melner the ortlme over-empnaszes any systems evol.lfons or generc t0p.c~
T E
- N d Assess whether the )ustlflcatlons for deselected or rejected KIA Statements are appropriate I,(-,
- 2. 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, S and major transients.
4- I I
M b. Assess whether there are enough scenaio sets (and spares) to test the projected number U and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromisingexam integrity. and ensure that each applicant can be tested using 2-1 A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants' audit test(s1. and that scenarh will no1 be repsated on subsequent days.
0 c. To the extent possible. assess whether the wtline(s) canform(s) with the qualitative R and quantitative criteria specified on Form ES-3014 and described in Appendix D. i *I
- 3. a. Verify that the systems walk-through outline meets the criteria specifled on Form ES-301-2:
(1) the outline(s) contain(s) the required numberof control r m and in-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants' audit test(s)
(4) the number d new or modified lasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power,emergency, and RCA tasks meet the criteria on the form.
- b. Verily that the administrative outline meets the criteria specified on Form ES-301-1 (1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified l?-t (3) no more than one task IS repeated from the last two NRC licensing examinations
- c. Determine if there are enough different outlines to test the projected number and mix 1-j
- of applicants and ensure that no items are duplicated on subsequent days.
- 4. a. Assess whether plant-specificpriorities (including PRA and IPE insights) are covered in the appropriate exam sections. l+I G b. Assess whether the 10 CFR 55.41143 and 55.45 samolina is aDDrooriate. ,?.I E
N c. Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5. rl-i E
R d. Check for duplication and overlap among exam sections. )-I A e. Check the entire exam lor balance of coverage. Rcl L
- 1. Assess whether the exam fits the appropriatejab level (RO or SRO). (? L- I
- 3. Author 3, Facility Reviewer (+)
- 3. NRC Chief Examiner (
- 3. NRC Supervisor ES-201,Page 25 of 27
-~
ES-301 Administrative Topics Outline Form ES-301-1 Date of Examination: 1117-11/18/2005 Operating Test Number: 2005301 Describe activity to be performed:
Perform Quadrant Power Tilt Calculation (2002 NRC Conduct of Operations P, D, S Exam)
Perform Initial Conditions for Reactor Startup Conduct of Operations N, S Procedure Equipment Control N, S Test High Flux at Shutdown Alarm Review Release Permit (Forced Vent Interruption and Radiation Control D,R Restart)
Emergency Plan M,R Emergency Plan Classification
~~
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (53 for ROs; (4 for SROs and RO retakes)
(N)ew or (M)odified from bank (?I)
(P)revious 2 exams (51; randomly selected)
ES-301, Page 22 of 27
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Point Beach Nuclear Plant Date of Examination: 1117-11/18/2005 Examination Level: RO Operating Test Number: 2005301 Describe activity to be performed:
f i Perform Quadrant Power Tilt Calculation (2002 NRC Conduct of Operations P, D, S Exam)
Perform Initial Conditions for Reactor Startup Conduct of Operations N, S Procedure Equipment Control N, S Test High Flux at Shutdown Alarm D, R (2000 Radiation Control Operate Tech Support Center Ventilation System NRC Exam)
!I ES-301, Page 22 of 27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 iacility: Point Beach Nuclear Plant Date of Examination: 1117-1 1/18/2005 Exam Level : RO Operating Test No: 2005301 Iontrol Room Systems"o (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, Including I ESF)
Safety System / JPM Title Type Code*
Function I. Control Roil Drive System / Rod Exercise Test. A, N, S 1
.I. Cltemiccrl& Volume Control Sy.srent / Establish Excess Letdown. D, S 2
~~
- , Pressurizer Pre,ssure Coulrol System / Place LTOP in-service. A. L, M, S 3 4
3 . Mrriu Feerlwuler System / Respond to a Loss of Secondary Heat Sink. A, M, S (Secondary)
E. Contninment Sprrty Sy.slem / Adjust Containment Sump pH. N, S 5 f:AC Eleclricul DMribulion i Perform Transfer of 4 kV Non-Vital Bus D, S 6 between Transformers.
- 9. Nucleur Inslrumcnlulion Syslent i Adjust Nuclear Instruments. D, S 7
- 11. Contponent Cooling Water Sy.vtem / Respond to a Loss of Component A, D,P, S 8 Cooling Water. (2002 NRC Exam) i.kmergency Cnre Coolitig Systenr / Makeup to RWST during Loss of Sump D,E, P, R 2 Recirc Capability (2002 NRC Exam)
- i. Emergency Diesel Cenercrlors / Locally fast start EDG. (2002 NRC Exam) A, D, E, P 6 k . Residual Heul ReniovulSysleni / Perform CCW HX alignment during Loss E, L, N, R 8 of Shutdown Cooling.
ES-301, Page 23 of 27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Point Beach Nuclear Plant Date of Examination: 11/7-11/18/2005 Exam Level : SRO-I Operating Test No: 2005301 Control Rooin Systems"" (8 for KO); (7 for SRO-I); (2 or 3 for SRO-U, Including 1 ESF)
T I
~~ ~ ~~
I System / JPM Title Typecode' Safety Function 11 a. Control Rod Drive.Yy.stem / Rod Exercise Test. I A.N,S I I 11 b. Cltemical & Volume Control Sy.sfeni / Establish Excess Letdown. I D,S I 2
- c. Pre.ssurizer Pressure Control Systeni / Place LTOP in-service. A, L, M, S 3 4
- d. Mrtiu Feedwafer Sysfem / Respond to a Loss of Secondary Heat Sink. A, M, S (Secondarv) e . Confiiiituienf Sprriy System / Adjust Containment Sump pH. N,S 5 f: AC Electrical Distrihutioit / Perform Transfer of 4 kV Non-Vital Bus D, s 6 between Transformers.
y . Compoiteitr Cooling Water System / Respond to a Loss of Component A, D, P, S 8 Cooling Water (2002 NRC Exam)
I Emergency Core Coolin# Sysfem / Makeup to RWST during Loss of Sump D, E, P, R 2 Recirc Capability (2002 NRC Exam) 11;. Enrergency Die.se/ Gencrdms / Locally fast start EDG. (2002 NRC Exam) I A, D, E. P 1 6
- k. Resiiluul H e d RemovulSystem / Perform CCW HX alignment during Loss of Shutdown Cooling. I E, L, N, R
<9 / 58 / j-4 (E)mergency or abnormal in-plant >I /?I /?I (L)ow-power / Shutdown >I/ ? I />I (N)ew or (M) from bank includiny I(A) >2 / >2 / ?I (P)revious 2 exams <3 / 53 / 3 (randomly selected)
>I
- />I /?I ES-301, Page 23 of 27
ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Point Beach Nuclear Plant Date of Examination: 11/7-11/18/2005 Exam Level : SRO-U Operating Test No: 2005301 Control Room Systems@'(8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, Including 1 ESF)
~ ~
System / JPM Title 1 Typecode*
I Safety Function
- a. Pre.FFurizer Pre.?.sureConirol Sy.Wm / Place LTOP in-service. A, L. M,S 3 4
- h. Main Feedwater Sysiem / Respond to a Loss of Secondary Heat Sink A, M, S (Secondary)
- c. Coniainmenf Spmy Sy.sfem / Adjust Containment Sump pH. N. S 5 (EW e.
f.
s-h.
In-Plant Svstemr'"' ( 3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
I. Residual Heai Removal Sysiem / Perform CCW HX alignment during Loss E, L, N, R 8 of Shutdown Cooling.
- i. Emerpenc.p Die.sel Cenerafnrs / Locally fast start EDG. (2002 NRC Exam) A, D, E. P 6 I I
- Type Codes Criteria for RO / SRO-I / SRO-U (Allternate path I 4-6 / 4-6 / 2-3 icjontroi rdom (D)irect from hank ~<9 / 58 / 54 (E)mergency or abnormal in-plant > I />I/'I (L)ow-power / Shutdown >I/ > I/ > I (N)ew or (M) from hank including I(A) 22 / 2' / >I (P)revious 2 exams -<3 / 53 / 52 (randomly selected)
(R)CA > I />I/>I (S)imulator ES-301, Page 23 of 27
CREW 'A' ES-301 Transient and Event Checklist Form ES-301-5 acl!lly A E Scenarios P V I I I P E 1 2 3 4 L N I T C CREW CREW CREW
.~
A T POSITION CREW POSITION POSITION POSITION N Y S A 6 S A B S A E S A E T P R T O R T O R T O R T O E O C P 0 C P O C P O C P MAJ I I I I I I I I I I I I TS istructions:
Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"
and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (IC) malfunctions and one major transient. in the ATC position.
Reactivity manipulations may be conducted under normal or controlled abnormal 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 with additional instrument or component malfunctions on a I-for-I basis.
Whenever practical, both instrument and component malfunctions should be included: only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
CREW 'B' ES-301 Transient and Event Checklist Form ES-301-5 Date of Exam 11/7/2005 Operating Test No 200530, RX NOR 8RO-I I/C
-2)
TZir TS RX NOR
!O 1-2) I MAJ
/c TS RX NOR
,RO-U I/C J-2' NlAJ TS RX NOR I/C MAJ TS istructions:
Check the applicant level and enter the operating test number and Form ES-0-1 event numbers for eacl event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"
and "balance-of-plant (BOP)"positions; Instant SRGs must do one scenario, including at least two instrument or component [ I C ) malfunctions and one major transient. in the ATC position.
Reactivity manipulations may be conducted under normal or controlled abnormal conditions [refer to Section D.5.d) but must be significant per Section C.2.a ofAppendix 0. r) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
Whenever practical, both instrument and component malfunctions should be included: only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
CREW 'C' ES-301 Transient and Event Checklist Form ES-301-5 acltlly A
P P
L I
C A
N T
- RO-I 1-3) 10 R-3) 10 R-4)
- 1s:
nstruct Check the applicant level and enter the operating test number and Form ES-0-1 event numbers for eact event type: TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)"
and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (IC) malfunctions and one major transient. in the ATC position.
?. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. r) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-I basis.
- 3. Whenever practical, both instrument and component malfunctions should be included, only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level In the right-hand columns
CREW 'D' ES-301 Transient and Event Checklist Form ES-301-5 A E Scenarios P V T M P E 1 2 3 4 0 I L N I T T N C CREW CREW CREW CREW A I A T POSITION POSITION POSITION POSITION L M N Y S A B S A B S A B S A B U T P R T O R T O R T O R T O M E o c P o c P o c P o c P R I U Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section 0.5.d) but must be significant per Section C.2.a of Appendix 0. r) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.
Whenever practical, both instrument and component malfunctions should be included: only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
CREW 'E' ES-301 Transient and Event Checklist Form ES-301-5 acltlry A E Scenarios P v i I I P
L I
C A M N
T M iRO-l 1-5) 10 R-6) 1 1 1
- ~
j-4j-y 0 2 2 nstruct 1s:
Check the applicant level and enter the operating test number and Form ES-0-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (VC)malfunctions and one major transient. in the ATC position.
!. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. r) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a I-for-I basis.
- 3. Whenever practical. both instrument and component malfunctions should be Included: oniy those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
ESd01 PWR Examination Outline FORM ES-401-2 IlFacilitv Narne:Point Beach Nuclear Date of Exam11/7/05 II
- 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 *Ifrom 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 inappropriateWA statements
- 4. 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.
- 5. Absent a plant-specificpriority, 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.
- 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
7.' The generic (G)WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevan to the applicable evolution or system.
- 8. On the following pages, enter the KIA 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; if fuel handling equipment is sampled in other than Category A2 or G'on the SRO-only exam enter it on the len side of Column A2 for Tier 2, Group 2 (Note #I does not apply). Use duplicate pages for RO and SRO only exams.
- 9. For Tier 3, select topics from Secfion 2 of the WA catalog. and enter the WA numbers. descriptions, IRs. and point totals
(#) on Form ES-401-3. Limit SRO selections to WASthat are linked to 10 CFR 55.43.
I
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Svstems -Tier 2IGrouo 1 lROI KIA Topic@)
I IIR # I Relalionship beween t~mporaluieand p r ~ ~ s u m r eCVCS 004 Chemical and Volume Control mmponsnls durlng SOlld plan1OPerBtRn Conlmlhrnand elief/Quench Tank Conlainmen1 Moniloring wench lank IernpBrature "p 5e PO," a ,YS men 022 Containment Cooling Contaiornentcooling after LOCA dWroys venlilsli~nduel 039 Main and Reheat Steam with plan1 equipment that could affect r ES-401, Page 24 of 33
~
5 Form ES-401-2 ES-401, Page 25 of 33
ES-401 7 Form ES-401-2 000007 Reactor Trip Stabilization - Recovery I 1 00015 RCP MalfUnCtiOnS i 4 00022 Loss of Rx Coolant Makeup 1 2 00026 Loss Of Component Cooling Water i 8 E12 Unconltiolled Depreessurizatian Of all Steam ES-401 22 of 33
ES401, Page 24 of 33 ES-401 5 Form ES-401-2 72 Area Radiation Monltorlng 079 Station Air
ES-401, Page 26 of 33 1 Annendix D Scenario Outline Form ES-D-I I Facility: Point Beach Scenario No.: I OP-Test No.:
Examiners: Operators:
Initial Conditions: Unit I is at 75% uower. Power was stabilized aooroximatelv 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago after reducing load at
-12%/hour at the request ofthe Power Svstem Suoervisor. Boron Concentration is 815 PPM. Xenon is building in slightly. Unit 2 is at 100% power.
Turnover: G O I EDG is out of service for annual maintenance. It was taken out of service 3 days ago and is exoected to be returned to service in 3 daw. 3-02 is aligned to 4.16 kV buses IA-05 and 2A-05 IAW 01-35A.
ITE-404, Loop 5 Hot Lee Temperature Element has failed hieh and has been removed from service IAW I-SOP-IC-001 Yellow.
I RC-5 15, Block valve for I RC-43 IC is closed due to PORV leakace. Tech Spec 3.4. I I . Required Action A. I has been comuleted.
lRPl is selected to alternate Dower (IYO21 due io planned breaker reolacement on I YO6 (Bkr 2 1 ).
Today is Sunday, uresent clock time is real time. An RP Tech and Chemistrv Tech are on-site. ERO Maintenance personnel are workine on GO I .
The obiective of the shift is to maintain stable olant conditions until the Power Svstem Suoervisor reauests Dower be returned to 100%. OP- IC, Startuu to Power Ooeration. has been ureoared.
P-28B Main Feed Pumo Bearing Failure (OverheatYPower Reduction 4 M -ALL Main Feedwater Line Break inside Containment 5 C-RO Reactor Trip manual push buttons on IC04 fail to operate 1 I I I 1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9
1 Auoendix D Scenario Outline Form ES-D-I I Facility: Point Beach Scenario No.: 2 OP-Test No.:
Examiners: Operators:
Initial Conditions: Unit 1 is at 100% Dower, MOL. eauilibrium xenon conditions. Boron Concentration is 813 PPM.
Unit 2 is at 100% power.
Turnover: G-01 EDG is out ofservice for annual maintenance. It was taken out of service 3 days ago and is expected to be returned to service in 3 days. (3-02 is aliened to 4.16 kV buses IA-05 and 2A-05 IAW OI-35A.
ITE-404, Loop B Hot Ley Temperature Element has failed high and has been removed from service IAW I-SOP-IC-001 Yellow.
1 RC-5 15. Block valve for I RC-43 1 C is closed due to PORV IeakaEe. Tech SDec 3.4. I I . Reauired Action A. 1 has been completed.
IRPl is selected to alternate power (IYO2) due to planned breaker replacement on 1YO6 (Bkr 2 I ) .
Today is Sunday. uresent clock time is real time. An RP Tech and Chemistrv Tech are on-site. ERO Maintenance personnel are workine on GO I .
The objective of the shift is to lower uower to 90% for Atmospheric DumD Valve (ADV) testin&
Lower power for ADV testing.
N - SRO I Ro 2 Power Range NI Channel 41 Summing and Level Amp fails low.
~
SRO(T)
I-3 1 LT-461, 'A' Steam Generator Level Transmitter fails low.
SRO(T) 4
~ Ro '9' RCP #2 Seal Fails
~~
SRO 5 M - ALL 'B' RCP Seal Packare fails I 1,
~
6 I
~
TC-t;:
dI\"
pumps fail to auto start on SI signal Two Containment Rad Monitor Containment Isolation Valves fail to shut on CI 7
I I (N)ormal. (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9
1 Appendix D Scenario Outline Form ES-D-I Facility: Point Beach Scenario No.: 2 OP-Test No.: -
Examiners: Operators:
Initial Conditions: Unit I is at -6.5% power following a Reactor TriD recovery startuD. Turbine is off line. Unit 1 is at MOL (8001 MWDIMTU). Xenon is building in slowlv. Boron Concentration is 673 PPM. Currentlv in OP-IC, Startup to Power Operation. at step 5.26. Steo 5.22 is being held open. pending shift to Main Feed Regulating Valves.
Unit 2 is at 100% power.
Turnover: G-0 I EDG is out of service for annual maintenance. It was taken out of service 3 davs ago and is exDected to be returned to service in 3 davs. G-02 is aligned to 4.16 kV buses IA-05 and 2A-05 IAW 01-35A.
ITE-404. Loop B Hot Leg Temperature Element failed high after entry into MODE I and removal from service JAW 0-SOP-IC-001 Yellow has iust been accomplished. I&C Dlans to repair the channel during 28% chemistrv hold.
I RC-5 15, Block valve for I RC-43 IC is closed due to PORV leakaee. Tech Spec 3.4. I I. Reauired Action A.l has been completed.
IRPl is selected to alternate power ( 1 Y02) due to planned breaker re~lacementon I YO6 (Bkr 2 1).
Todav is Sundav, Dresent clock time is real time. An RP Tech and Chemistrv Tech are on-site. ERO Maintenance personnel are workine on G01.
The obiective of the shift is to raise power and roll the Main Turbine. Approved Reactivitv Plan desimates that power should be raised using Control Rods.
NUREG-1021, Revision 9
Appendix D Scenario Outline Form ES-D-I
'acility: Point Beach Scenario No.: 4 OP-Test No.:
txaminers: Operators:
nitial Conditions: Unit I is at 28% power for chemistry hold following a startup, MOL. eauilibrium xenon onditions. Boron Concentration is 1125 PPM. Unit 2 is at 100% power.
hrnover: G-01 EDG is out of service for annual maintenance, It was taken out of service 3 days ago and is expected o be returned to service in 3 days. (3-02 is aligned to 4.16 kV buses 1A-05 and 2A-05 IAW OI-35A.
TE-404, Loop B Hot Leg TemDerature Element has failed high and has been removed from service IAW I-SOP-IC-I01 Yellow.
KC-515, Block valve for I RC-431C is closed due to POKV leakaee. Tech Spec 3.4.1 1, Reauired Action A.l has
)een completed.
RPI is selected to alternate power (lYO2) due to planned breaker replacement on lYO6 (Bkr 21).
~e on-site. ERO Maintenance msonnel are working on GO1 .
The obiective of the shift is to maintain stable d a n t conditions.
Event I XOI Lockout I Turbine Trip I I 1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUKEG-1021, Revision 9
During the week of October 17, 2005, I reviewed the licensees outline submittal for the Point Beach Initial License Exam - 2005.
I did not have any comments regarding the IFensees initial outline submittal.
Raykond Keiih Walton, Chief Examiner