ML021160601
| ML021160601 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/05/2002 |
| From: | Dante Johnson FirstEnergy Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 50-440/02301, ES-301-1, NUREG-1021, Rev 8 | |
| Download: ML021160601 (103) | |
Text
FINAL AS-ADMINISTERED ADMINISTRATIVE JPMS FOR THE PERRY INITIAL EXAMINATION - MARCH 2002
ES-301 Administrative Topics Outline Form-ES-301-1 Facility: Peny Date of Examination: 3/4/2002 Examination Level: RO Operating Test Number: 2002-01 Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions A. 1 Shift Turnover 2.1.3 (3.0) - Knowledge of Shift Turnover Requirements JPM: Complete a Shift Relief/Turnover checklist as the oncoming operator Jet Pump 2.1.7 (3.7) - Ability to Evaluate Plant Performance and Make Operational Judgements Based on Operability Operating Characteristics / Reactor Behavior / Instrument Interpretation JPM: Determine Jet Pump operability A.2 Tagging 2.2.13 (3.6) - Knowledge of Tagging and Clearance Procedures JPM: Establish equipment isolation boundaries A.3 Radiation Control 2.3.1 (2.6) - Knowledge of IOCFR20 and Related Facility Radiation Control Requirements Requirements JPM: Comply with Administrative Dose Control Levels for assigned job task A.4 Personnel 2.4.39 (3.3) - Knowledge of RO's Responsibilities in Emergency Plan Implementation Accountability JPM: Perform Site Accountability actions from outside the Control Room.
NUREG-1021, Revision 8 Final-Revision 2
SAFETY SIGNIFICANCE OF RO ADMIN JPMs & QUESTIONS A.l.a 2.1.3 (3.0) Complete a Shift Relief/Tumover Checklist as the oncoming operator.
This JPM is safety significant because failure to recognize equipment out of service (RCIC) not identified on the shift relief/turnover checklist, in conjunction with HPCS already being out of service, would result in reduced ability to assure adequate core cooling.
A.l.b 2.1.7 (3.7) Determine Jet Pump operability This JPM is safety significant because failure to recognize and inform the SRO that the Acceptance Criteria for the Jet Pump Operability Surveillance was not met could result in continued operation with a failed jet pump, which directly challenges the ability of the station to assure adequate core cooling in the event of a major Loss of Coolant Accident.
A.2 2.2.13 (3.6) Establish equipment isolation boundaries This JPM is safety significant because failure to properly establish equipment isolation boundaries threatens personal safety.
A.3 2.3.1 (2.6) Comply with Administrative Dose Control Levels for assigned job task This JPM is safety significant because failure to determine that the initial Perry Administrative Dose Control Level will be exceeded could result in unnecessary additional radiation exposure for the individual and violation of the intent of the ALARA principle.
A.4 2.4.39 (3.3) Perform Site Accountability actions from outside the Control Room This JPM is safety significant because personnel accountability is an important element of Emergency Plan operations for personnel safety.
Final - Revision 2 Page 1 of I
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
Task
Title:
K/A
Reference:
Perry Complete a Reactor Operator Relief/Turnover Checklist as the On-Coming Reactor Onerator Task No:
JPM No:
299-933-03-01 2002 NRC Ala RO 2.1.3 NRC Examiner:
MethQd of testing Simulated Performance Actual Performance Classroom Simulator In Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
The plant is operating at 100% power. You are the on-coming Day Shift Reactor Operator. You have completed Section A of the Reactor Operator Relief/Tumover Checklist with the exception of the Control Room Horseshoe Panel Walkdown.
Candidate identifies RCIC is not in Stby Readiness due to both suction valves being closed (E51-F031 and E51-F010).
PAP-0 126, Attachment 3 (attached marked up copy)
Simulator IC Setup Sheet (attached)
PAP-0126, Shift Staffing and Shift Relief, Rev. 2, PIC 2 Complete the Reactor Operator Relief/Turnover Checklist by performing the Control Room Horseshoe Panel Walkdown for panels H13-P877, P601, and P680 in accordance with PAP-0126.
NO 30 minutes NUREG 1021, Revision 8, Supplement I Examinee:
Facility Evaluator:
N/A Date:
Appendix C Page 2 of 4 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
The sequence of steps is unimportant.
Performance Step:
P601 Standard:
Comment:
Performance Step:
P680 Standard:
Walkdown Control Room Horseshoe observing items such as active annunciators, status lights, train alignments, control board tags, and various parameters.
Candidate identifies RCIC is not in Stby Readiness due to E5 1-F03 1 and E5 1-F010 being closed.
Note: Annotation of the completion of the Control Room Walkdown on the RO Relief/Turnover Checklist is not a critical step.
Note: Failure to identify that RCIC is not listed as being out of service on the RO Relief/Turnover Checklist is not a critical step.
Walkdown Control Room Horseshoe observing items such as active annunciators, status lights, train alignments, control board tags, and various parameters.
Candidate identifies Pressure Regulator B is the in-service Pressure Regulator. Determines in-service Pressure Regulator was incorrectly annotated on the Reactor Operator Relief/Turnover Checklist.
Comment:
Terminating Cue:
The evaluation for this JPM is complete when the candidate completes the Control Room Horseshoe Panel walkdown for panels P877, P601, and P680.
NUREG 1021, Revision 8, Supplement 1
Appendix C Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Page 3 of4 Page 3 )of 4 VERIFICATION OF COMPLETION 2002 NRC Ala RO Form ES-C-1 N/A Result:
SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement I
Appendix C Page 4 of 4 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
The plant is operating at 100% power. You are the on-coming Day Shift Reactor Operator. You have completed Section A of the Reactor Operator Relief/Turnover Checklist with the exception of the Control Room Horseshoe Panel Walkdown.
INITIATING CUE:
Complete the Reactor Operator Relief/Turnover Checklist by performing the Control Room Horseshoe Panel Walkdown for panels H13-P877, P601, and P680 in accordance with PAP-0 126.
NUREG 1021, Revision 8, Supplement I
RO RELIEF/TURNOVER CHECKLIST PNPP No. 8290 Rev. 4/23/01 Page I of 2 PAP-0126 Section A:
Date:
03-XX-02 Mode: 1 100%
3758 MWth Shift:
M Day F-] Afternoon
-- Night Q
NI-RRA:
El NI-CC:
Perform the following (off-going RO):
El BOP:
Z Test Annunciators Z Update Annunciator tracking Log o
OUT:
Uj RW:
Discuss the following:
n FT' Equipment Out-Of-Service/Maintenance in progress:
BOLD NEW
- E22A HPCS Pump
- G36 Demin A P52 Unit 1 IA Compressor C85 1B Press Regulator P61 A feed Pump P61 A boiler fan flow switch P54 A007 Tank # 7 (MLO)
Test/Evolutions (C - Completed / I/P - In Progress I P - Planned I D - Discuss I H - Hold / A - Aborted)
This Shift Previous Shift P - I&C troubleshooting 1C85NO001 B Pressure Regulator C - SVI-E51-T2001 RCIC Pump and Valve Operability P - G36 A F/D Backwash and precoat C - Unloaded 2 Aux Boiler fuel oil trucks P - Prepare for FIN Work on N23 H Filter (Days)
C - P61-0013 clearance removal feed pump A C - Restored Perry - East Lake Line C - P52 U1 IA Compressor in Secured status to support Demister change.
Review/perform the following:
Plant Narrative Log
[
DLCO Tracking Sheets N Control Rod Positions And Core Symmetry Z ECCS Status Board Z Daily & Standing Instructions D] Control Room Walkdown (Horseshoe and Back Panels)
Z Active LCO Status Z Active Annunciators Z Tech Spec Rounds D__ __
- Monitorin RectiiersOr gacngoing D - Monitoring Rectifiers for leakage (camera is in place)
I i
i i
I I
i I
i
RO RELIEF/TURNOVER CHECKLIST PNPP No. 8290 Rev. 4/23/01 Page 2 of 2 PAP-01 26 Review/Discuss the following:
Controlling 101's:
3 / 15.
M RPV Level/Press (Within limits based on current operating conditions)
Z DW Press (_<0.5 psig)
Z CNTMT Press (_<0.5 psig)
Z SP Lvl (Within limits based on current operating conditions)
Z DW Temp (600 - 1450 F)
Z CNTMT Temp (600 - 950 F)
Z SP Temp (600 - 950 F)
Cooling Tower Status: ZNormal E] Bypass
[] Central Deicing
[
Shutdown Blowdown in Manual: Full Open General information RFBP C Motor Thrust Bearing Monitor at 180 / Shift at 1850 RFBP B Stator Temp High / Contact RSE at 2450 S/D 2500 1 P45-F068A packing leak (RHR A pump room sump)
Contact SE if any Turbine Differential Expansion Alarms M35 Plenum drains aligned to Rad waste due to tritium N23 C and H can not backwash due to valve problems 3.6.1.3 (3.6.5.3) Va~lve(s) +
Compensating Action4 Section B:
Z Control Room PER's and Tech Spec Rounds 5CC Information / 5CC Phone Numbers 2
Schedule 8-836-9867 Conversion Economics:
8-820-1450 or 1-330-252-1450 2
Generation for power changes 8-820-1471 or 1-330-252-1471 W
For VoltageNar. 1-330-336-9803 or 8-836-9868 or 1-330-336-9867 W
About Quincy Sub 8-836-9860 W Dispatcher / Oscillograph / N71 Lights-8-836-9864 (or 1-800-288-9176)
FAX: (330)336-9869 2
Switching Orders 8-836-9863 W Bulk Power: 1-216-642-7400 W North Region Dispatch (1-800-589-9111) (Pole problems)
Off-going RO:
On-coming RO:
2
ANNUNCIATOR TRACKING LOG Panel Sec Loc Description of Reason for Activation Ref Doc Activation Expected Owner Annunciator from of Annunciator Date De Panel Activation Date 1H13-
]A A-02 RWCU F/D OUT Monitor Failed WO RT 75905 2/11/02 4/30/02 FIN P680 COND HIFAILED 02-357 Status Work Complete 1H13-7A E-1I INST AIR COMP Local Panel Power WO 02-148 2/28/02 5/30/02 FIN P680 TRBL Turned Off Due to A/C in Secured Status For Demister Change 1H13-16 D-04 HPCS OUT OF Pump Breaker WO 02-419 3/04/02 3/18/02 EMM P601 A
SERVICE Maintenance 3,
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
Perra Task
Title:
K/A
Reference:
Determine Jet Pump Operability Task No:
JPM No:
202-517-02-01 2002 NRC AIb RO
2.1.7 Examinee
Facility Evaluator:
Method of testing NRC Examiner:
N/A Date:
Simulated Performance Classroom N/A Actual Performance Simulator In Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
NUREG 1021, Revision 8, Supplement I
Appendix C Job Performance Measure Form ES-C-I Worksheet Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
The plant is operating at 72% power. SVI-B33-TI 160, Jet Pump Operability Surveillance, was in progress when the Reactor Operator performing the surveillance had to leave the site unexpectedly 5 minutes ago. Sections 5.1.1 and 5.1.2 of SVI-B33-TI 160 were completed prior to his departure. ICS is not available to support performance of SVI-B33-T1 160.
Candidate identifies the Technical Specification Acceptance Criteria for SVI-B33-T1 160 has not been met (2 out of 3 Criteria are not met),
the Tech Spec / Relocated Requirements Criteria block on the Data Package Cover Sheet is annotated as 'unacceptable', and the Unit Supervisor is informed of the SVI failure.
SVI-B33-TI 160, Rev 4, PIC 2 (attached marked up copy)
PDB-A0009, Rev 13 PAP-1105, Rev 9, PIC 9 Simulator IC Setup Sheet (attached)
Calculator SVI-B33-TI 160, Rev 4, PIC 2 PDB-A0009, Rev 13 PAP-105, Rev 9, PIC 9 The Unit Supervisor directs you, as the Reactor Operator, to complete the Jet Pump Operability Surveillance by performing Section 5.1.3.1, Jet Pump Differential Pressure and Flow, evaluate the Technical Specification acceptance criteria of SVI-B33-Tl 160, and complete the Data Package Cover Sheet.
NO 30 minutes NUREG 1021, Revision 8, Supplement I
Appendix C Page 3 of 9 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Note: It is not necessary to satisfy both Section 5.1.3.1 and Section 5.1.3.2. The preferred method is contained in Section 5.1.3.1. The unnecessary section has been marked N/A.
Performance Step:
5.1.3.1.a Standard:
Jet Pump Differential Pressure.
Determine each normalized jet pump diffuser to lower plenum differential pressure for each operating recirculation loop, and indicate the method used.
Completes Attachment 3, Normalized Jet Pump dP's Data Sheet.
Comment:
The following steps are contained in SVI-B33-T1160 Attachment 3, Normalized Jet Pump dPs Data Sheet.
- Performance Step: 1 Record each Jet Pump diffuser to lower plenum dP (%).
Jet Pump diffuser to lower plenum dP's accurately recorded.
See attached marked-up copy of Attachment 3 for expected approximate values.
NUREG 1021, Revision 8, Supplement I Standard:
Comment:
Appendix C Page 4 of 9 Form ES-C-1 PERFORMANCE INFORMATION
"* Performance Step: 2 Standard:
Comment:
"* Performance Step: 3 Standard:
Comment:
Performance Step: 4 Standard:
Comment:
Performance Step: 5 Standard:
Comment:
Sum all Jet Pump dPs for each loop, and record as Loop Total dP.
Jet Pump dP's accurately summed.
See attached marked-up copy of Attachment 3 for expected approximate values.
Divide each Loop Total dP by 10 and record as Loop Average dP.
Jet Pump Loop Average dP's accurately calculated.
See attached marked-up copy of Attachment 3 for expected approximate values.
Divide each Jet Pump dP by its Loop Average dP, and record as Normalized Jet Pump dP.
Normalized Jet Pump dP's accurately calculated.
See attached marked-up copy of Attachment 3 for expected approximate normalized values.
All calculations independently verified.
Independent verification of all calculations is requested.
Cue: Independent verification of all calculations has been completed satisfactorily.
NUREG 1021, Revision 8, Supplement I
Appendix C Page 5 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 6 Standard:
Comment:
Confirm that each normalized jet pump diffuser to lower plenum differential pressure as determined in Step 4 of this attachment is within the corresponding Normalized dP Range of <PDB-A0009>
for the Recirculation Loop configuration indicated in Step 4.3 Determines that each normalized jet pump diffuser to lower plenum differential pressure as determined in Step 4 of this attachment is not within the corresponding Normalized dP Range.
See attached marked-up copy of Attachment 3 for expected approximate values of each normalized jet pump diffuser to lower plenum differential pressure.
The following steps are contained in SVI-B33-Tl160 Section 5.1.3, Jet Pump Differential Pressure, and in Section 5.3, Acceptance Criteria.
- Performance Step:
5.1.3.1.b Standard:
Indicate whether the relationship determined in Step 5.1.3.1.a is within the appropriate "established pattern."
Determines that relationship determined in Step 5.1.3.l.a is not within the appropriate "established pattern" by referring to step 6 of.
Comment:
NUREG 1021, Revision 8, Supplement I
Appendix C Page 6 of 9 Form ES-C-1 PERFORMANCE INFORMATION Performance Step:
Acceptance Criteria 5.3.1 The jet pumps, in each operating recirculation loop, have been demonstrated OPERABLE by one of the following two methods:
- a.
At least two of the following three criteria have been satisfied:
- 1)
Recirculation loop drive flow versus flow control valve position differs by < 10% from established patterns. (YES in Step 5.1.1.2)
- 2)
Recirculation loop drive flow versus total core flow differs by < 10% from established patterns. (YES in Step 5.1.2.2)
- 3)
Either each jet pump diffuser to lower plenum differential pressure differs by < 20% from established patterns, or each jet pump flow differs by < 10% from established patterns. (YES in either Step 5.1.3.1.b or Step 5.1.3.2.b)
Standard:
Determines that two of the three criteria of step "a" have not been satisfied.
Determines that Recirculation loop drive flow versus total core flow differs by Ž10% from established patterns.
Determines that that jet pump diffuser to lower plenum differential pressure differs by _>20% from established patterns.
Informs the Unit Supervisor that significant abnormalities exist which could indicate a Jet Pump failure.
Comment:
Cue: If requested, we are not baselining new established patterns.
NUREG 1021, Revision 8, Supplement I
Appendix C Page 7 of 9 Form ES-C-1 PERFORMANCE INFORMATION The following step is contained in the Data Package Cover Sheet for SVI-B33-T1 160.
Performance Step:
Data Package Cover Sheet Standard:
Comment:
Completes the Data Package Cover Sheet in accordance with the guidelines in PAP-1105.
Annotates the Tech Spec / Relocated Requirements Criteria as
'Unacceptable' on the Data Package Cover Sheet and informs the Unit Supervisor.
See attached marked-up copy of the Data package Cover Sheet attached to the front of SVI-B33-T1 160.
Note: The incorrect annotation of all remaining blocks on the Data package Cover Sheet is not a critical step.
Terminating Cue:
The evaluation for this JPM is complete when the candidate determines the Jet Pump Operability Surveillance acceptance criteria have not been satisfied, completes the Data Package Cover Sheet, and informs the Unit Supervisor that significant abnormalities exist which could indicate a Jet Pump failure.
NUREG 1021, Revision 8, Supplement 1
Appendix C Page 8 of 9 Form ES-C-I Question Documentation:
Question:
Response
Result:
SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement 1 Appendix C Page 8 of 9 VERIFICATION OF COMPLETION Job Performance Measure No.
2002 NRC Alb RO Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
N/A Number of Attempts:
Time to complete:
Appendix C Page 9 of 9 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
INITIATING CUE:
The plant is operating at 72% power. SVI-B33-TI 160, Jet Pump Operability Surveillance, was in progress when the Reactor Operator performing the surveillance had to leave the site unexpectedly. Sections 5.1.1 and 5.1.2 of SVI-B33-T1160 were completed prior to his departure.
ICS is not available to support performance of SVI-B33-TI 160.
The Unit Supervisor directs you, as the Reactor Operator, to complete the Jet Pump Operability Surveillance by performing Section 5.1.3. 1, Jet Pump Differential Pressure and Flow, evaluate the Technical Specification acceptance criteria of SVI-B33-Tl 160, and complete the Data Package Cover Sheet.
NUREG 1021, Revision 8, Supplement 1
AlNO 3Sfl E NINIVUI U02-DATA PACKAGE COVER SHEETJ PNPP No. 6687 Rev. 9/27/01 PAP-1105 TEST PERFORMANCE AUTHORIZATION TO START PREREQUISITES:
AUTHORIZATION TO START TEST:
S.8.,
INSTRUCTION COMPLETION
[I FULL (see l.a on reverse)
TECH. SPEC./RELOCATED 0 ACCEPTABLE REQUIREMENTS CRITERIA (see 1.b on reverse)
AS FOUND DATA (see 1.c on reverse)
[I NA OTHER DATA CRITERIA (see 1.d on reverse)
TASK COMPLETION (see 1.e on reverse) o ACCEPTABLE 0l ACCEPTABLE 0 RESCHEDULE CREDIT**
1k IA fleactor Operator PARTIAL*
0 UNACCEPTABLE 0l NA 0l OUTSIDE LAIZ El UNACCEPTABLE 0l NO RESCHEDULE CREDIT
[I OUTSIDE AV
[I NA Date A J*me Date and Time
- See comments for extent of testing When both As Left and As Found data are taken, acceptance will be based on As Left data only.
When As Found data Is outside allowable value generate a CR (see 3 on reverse)
When both As Left and As Found data are taken, acceptance will be based on As Left data only
"*Task fully completed or all failed/not completed items tracked per LCO Tracking, Work Orders, etc.
TCN's IN EFFECT:
I L W L Comments: I') EIUIS rNA,t2hlILU LEAD PERFORMER'S SIGN OFF (see 2 on reverse)
I Print Name Signature OPERATIONS UNIT SUPERVISOR SHIFT MANAGER (Required if Tech. Spec. or ODCM Acceptance criteria is not met, Otherwise Mark N/A)
Date and Time Date and Time Date and Time FOR TRAI "N.i-i,'.
USE ONLY Comments:
Responsible Section Reviewer Approval Signature Date TEST PERFORMANCE I
ýebmA Sin J t4-G,&rl I I::0 I IKi:bU LIS RENVIE;W
SVI-B33--1160 Page:
i Rev.:
4 The Cleveland Electric Illuminating Company PERRY OPERATIONS MANUAL Surveillance Instruction TITLE:
JET PUMP OPERABILITY REVISION:
PREPARED:
4 EFFECTIVE DATE:
7-14-96 Harold A.
Stiles 8-16-95
/
Date EFFECTIVE PIC's FOR TRAININL.
USE ONLY 4
PIC Type of Effective No.
Change Date 1
Non-Intent 7-17-96 Final Non-Intent 1-13-97 Final 4
4 4
4
SVI-B33-T1160 Page:
ii Rev.:
4 SCOPE OF REVISION:
Rev.
4 -
- 1.
- 2.
3.
TC's from previous revision that were evaluated for incorporation -
None.
Revised in entirety --
no revision bars needed.
Incorporated Improved Technical Specifications.
SVI-B33-ýII60 Page:
iii Rev.:
4 Change History PIC Number:
2 Affected Pages:
Summary of Change:
- 1.
Added prerequisite to verify no other maintenance or testing is in progress that would affect B33 flow indication on the ERIS computer.
PIC Number:
1 Affected Pages:
i,
- iii, 4,
5, 6,
7, 8,
11, 12, 13, 14, 15 Summary of Change:
- 1. Corrects reference Step numbers in Section 5.3.1.3.
- 2.
Corrects Section Title in 5.1.3.2.
- 3.
Place initial lines at the end of each step.
i,
- iii, 4
SVI-B33-;1160 Page:
1 Rev.:
4 Jet Pump Operability
1.0 DESCRIPTION
1.1 Scope
This instruction demonstrates the operability of each jet pump in each operating recirculation loop by confirming the existence of two of the following three conditions for each operating recirculation loop:
- 1)
Recirculation loop drive flow versus flow control valve position differs by
- 10% from established patterns,
- 2)
Recirculation loop drive flow versus total core flow differs by
- 10% from established patterns,
- 3)
Each jet pump diffuser to lower plenum differential pressure differs by
- 20% from established patterns, or each jet pump flow differs by
- 10% from established patterns.
This instruction satisfies the requirements of Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1.
1.2 Frequency
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> NOTE 1:
Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after associated recirculation loop is in operation.
NOTE 2:
Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after > 25% RTP.
1.3 Technical Specification Applicable MODES:
1 and 2 2.0 PRECAUTIONS AND LIMITATIONS
- 1.
Step numbers marked with a dollar sign ($) immediately to the left are required by Technical Specifications.
Such items, if found to exceed their Acceptance Criteria, may be NRC reportable and shall be brought to the immediate attention of the Unit Supervisor.
- 2.
Those steps of this instruction with an initial line are to be initialed as data are entered or as each step is completed.
- 3.
Sections 5.1.1, 5.1.2, and 5.1.3 may be performed in any order.
Steps within a section are to performed in the order specified unless otherwise indicated.
- 4.
Avoid performing this test at less than 10% FCV position, as position indication is not consistent there.
SVI-B33-11160 Page:
2 Rev.:
4
- 5.
Baselining new "established patterns" is conducted in accordance with <SVI-F41-T3008>, "Reactor Recirculation System Flow Data Verification" during the initial weeks of operation under circumstances such as:
- a.
Following refueling activities (fuel assembly replacement or shuffle, as well as any modifications to fuel support orifice size or core plate bypass flow) that can affect the relationship between core flow, jet pump flow and recirculation loop flow, or
- b.
Initial entry into extended single loop recirculation operation During this time, the Shift Technical Advisor, Responsible System Engineer, or a Reactor Engineer normally provides an "engineering judgment of the daily surveillance results" to detect significant abnormalities which could indicate a jet pump failure.
This engineering judgment may be based upon the nature of the refueling activities and may consider the self-consistency of the daily surveillance results, but jet pump noise is the most positive indication that the jet pump is operating.
Until new "established patterns" can be baselined, copies of the <SVI-F41-T3008> data should be retained in the Control Room for ready reference.
- 6.
In order to permit sufficient opportunity for the baselining of new established patterns, the period of time covering the "initial weeks of operation following refueling activities" normally extends to include five weeks after reaching rated power and flow.
- 7.
When using the "established patterns" in the Plant Data Book Curves, ensure the two loop curves are used during two loop operations and the single loop curves are used during single loop operations; likewise, for slow or fast speed operation.
- 8.
During single loop operations, only the jet pumps associated with the operating recirculation loop need to be demonstrated operable.
However, data may be collected from the idle loop for use in demonstrating the OPERABILITY of the operating loop.
- 9.
The following ERIS screens may be used during the performance of this surveillance instruction, as appropriate for the configuration of the recirculation system:
- a.
152, Normalized Jet Pump Flows
- b.
156, Normalized Jet Pump dPs
- c.
- 172, Dual Loop RCIRC Fast Performance
- d.
- 173, Dual Loop RCIRC Slow Performance
SVI-B33-r 1160 Page:
3 Rev.:
4 3.0 MANPOWER AND EQUIPMENT 3.1 Manpower/Location/Communication
- 1.
Control Room operator or other qualified member of the unit technical staff to record data from instruments that are located on UNIT CONTROL CONSOLE 1H13-P680 and/or JET PUMP MONITORING PANEL 1H13-P619.
- 2.
Shift Technical Advisor, Responsible System Engineer, or Reactor Engineer, if needed, to provide engineering judgment of daily surveillance results.
- 3.
The Independent Verifier may be any of the above individuals.
3.2 Required Measuring and Test Equipment (M&TE)
None 3.3 Additional Tools and Equipment
- 1.
<PDB-A0009>, Expected Jet Pump Normalized dP and Flow Ranges, if needed.
- 2.
<PDB-AO010>, Recirc Loop Drive Flow vs.
FCV Position, if needed.
- 3.
<PDB-A0012>, Recirc Drive Flow vs. Total Core Flow, if needed.
- 4.
<SVI-F41-T3008>, Reactor Recirculation System Flow Data Verification, if needed.
- 5.
ERIS (C95) computer provides data, if used.
(INTENTIONALLY BLANK)
SVI-B33-'f1160 Page:
4 Rev.:
4 / C-2 4.0 PREREQUISITES
- 1.
Mark the Unit Supervisor's "Authorization to Start Prerequisites" signature N/A on the Data Package Cover Sheet (DPCS) and initial.
- 2.
Confirm that the plant is operating in MODE 1 or 2, with THERMAL POWER > 25% RTP.
- 3.
Confirm that the recirculation flow is steady; and indicate the configuration of the recirculation loops:
Initials 4-
[
- a.
Loop A (only) in operation, with flow control in loop manual.
[
- b.
Loop B (only) in operation, with flow control in loop manual.
- c.
Both recirculation loops in fast with recirculation loop jet pump within the limits of SR 3.4.1.1.
[
- d.
Both recirculation loops in slow with recirculation loop jet pump within the limits of SR 3.4.
recirculation recirculation speed operation, flow mismatch speed operation, flow mismatch 1.1.
M IV
- 4.
When using ERIS screens, verify no other maintenance or testing is in progress which would affect recirculation flow indication.
5.0 SURVEILLANCE INSTRUCTION 5.1 Surveillance Test
- 1.
Notify the Supervising Operator before starting and write "S.O.
(operator's name) notified" in the "Authorization to Start Test" signature on the DPCS.
Record the time and date and initial the line.
5.1.1 Recirculation Loop Drive Flow vs. FCV Position
- 1.
Determine the relationship between each operating recirculation loop drive flow and the corresponding flow control valve position, and indicate the method used.
If using ERIS, attach a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., 172 for dual loop - fast speed, or 173 for dual loop - slow speed); otherwise, complete, Manual Recirculation Loop Drive Flow vs.
FCV Position.
f I ERIS screen
ý] Attachment 1 V
SVI-B33---1160 Page:
5 Rev.:
4 / C-I SECTION 5.1.1 Initials
- 2.
Indicate, for each operating loop, whether the relationship determined in Step 5.1.1.1 is within the appropriate "established pattern."
If using ERIS, observe cursor is within limits for the DRIVE FLOW A VS.
FCV A and/or for the DRIVE FLOW B VS.
FCV B; otherwise, refer to Step 3 on Attachment 1.
- a.
Loop A:
E YES
[ ]NO
[
N/A
- b.
Loop B:
[]YES
[ ]NO
[
N/A 5.1.2 Recirculation Loop Drive Flow vs. Total Core Flow
- 1.
Determine the relationship between recirculation loop drive flow and total core flow, and indicate the method used.
If using ERIS, attach a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g.,
172 for dual loop - fast speed, or 173 for dual loop - slow speed); otherwise, complete,
Manual Recirculation Loop Drive Flow vs. Total Core Flow.
[
ERIS screen
- 2.
Indicate whether the relationship determined in Step 5.1.2.1 is within the appropriate "established pattern."
If using ERIS, observe cursor is within limits for the DRIVE FLOW VS.
CORE FLOW; otherwise, refer to Step 3 on Attachment 2.
[IYES NO 5.1.3 Jet Pump Differential Pressure and Flow NOTE 1:
It is not necessary to satisfy both Section 5.1.3.1 and Section 5.1.3.2.
The preferred method is contained in Section 5.1.3.1.
The unnecessary section may be marked N/A.
NOTE 2:
For single loop operation, the spaces in this section may be marked N/A for the idle loop.
SVI-B33-1160 Page:
6 Rev.:
4 / C-i SECTION 5.1.3 Initials
- 1.
Jet Pump Differential Pressure
- a.
Determine each normalized jet pump diffuser to lower plenum differential pressure for each operating recirculation loop, and indicate the method used.
If using ERIS, attach a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., 156 for dual loop operation);
otherwise, complete Attachment 3, Normalized Jet Pump dP's Data Sheet.
ERIS screen
[ ] Attachment 3
- b.
Indicate whether the relationship determined in Step 5.1.3.1.a is within the appropriate "established pattern."
If using ERIS, observe NORMAL indication for the JET PUMP DPS; otherwise, refer to Step 6 on Attachment 3.
[ YES
[ ] NO
[ ] N/A
- 2.
Jet Pump Differential Flow
- a.
Determine each normalized jet pump flow for each operating recirculation loop, and indicate the method used.
If using ERIS, attach a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., 152 for dual loop operation);
otherwise, complete Attachment 4, Normalized Jet Pump Flows Data Sheet.
[ ERIS screen
[ ] Attachment 4
- b.
Indicate whether the relationship determined in Step 5.1.3.2.a is within the appropriate "established pattern."
If using ERIS, observe NORMAL indication for the JET PUMP FLOWS; otherwise, refer to Step 7 on Attachment 4.
IYES
[] NO
[ ] N/A
SVI-B33-1160 Page:
7 Rev.:
4 / C-i Initials 5.2 Plant/System Restoration None 5.3 Acceptance Criteria NOTE 1:
Satisfactory completion of this surveillance shall be based only on Technical Specification items (marked with a $ sign).
NOTE 2:
While baselining new "established patterns," copies of <SVI-F41-T3008> data should be retained in the Control Room so that the Shift Technical Advisor, the Responsible System Engineer, or a Reactor Engineer may consider the self-consistency of the data in making the "engineering judgment" on the existence of significant abnormalities which could indicate a jet pump failure.
Jet pump noise is the most positive indication that the jet pump is operating.
- 1.
The jet pumps, in each operating recirculation loop, have been demonstrated OPERABLE by one of the following two methods:
- a.
At least two of the following three criteria have been satisfied:
- 1)
Recirculation loop drive flow versus flow control valve position differs by
- 10% from established patterns.
(YES in Step 5.1.1.2)
- 2)
Recirculation loop drive flow versus total core flow differs by
- 10% from established patterns.
(YES in Step 5.1.2.2)
- 3)
Either each jet pump diffuser to lower plenum differential pressure differs by
- 20% from established patterns, or each jet pump flow differs by
- 10% from established patterns.
(YES in either Step 5.1.3.1.b or Step 5.1.3.2.b)
[ YES
[ ] NO, U.S. notified
[ ] N/A If Step 5.3.1.a is marked NO, consider the applicability of Step 5.3.1.b; otherwise mark the signature line in Step 5.3.1.b N/A.
SVI-B33-'1160 Page:
8 Rev.:
4 / C-1 Initials
- b.
While baselining the new "established patterns," the Shift Technical Advisor (STA),
or the Responsible System Engineer (RSE),
or a Reactor Engineer (RE) has reviewed the surveillance results and has determined, based upon engineering judgment, that no significant abnormality exists that could indicate a jet pump failure.
- STA, RSE, or RE Signature Date
- 2.
All other items checked in this surveillance performed satisfactorily.
[ ] YES
[
NO, applicable Supervisor notified
- 3.
Check the appropriate block on the Data Package Cover Sheet to indicate acceptable or unacceptable test results.
Comments:
Performed By:
-1a n se 3u/-
Name (Print)
Initials Date 5.4 Records The following documents are generated by this instruction:
Quality Assurance Records Data Package Cover Sheet SVI-B33-T1160, pages 4 through 8, and:, Manual Recirculation Loop Drive Flow vs.
FCV Position, if used,
Manual Recirculation Loop Drive Flow vs. Total Core Flow, if used, Normalized Jet Pump dP's Data Sheet, if used, Normalized Jet Pump Flows Data Sheet, if used ERIS screen 172 hard copy, Dual Loop RCIRC Fast Performance, if used ERIS screen 173 hard copy, Dual Loop RCIRC Slow Performance, if used ERIS screen 152 hard copy, Dual Loop Normalized Jet Pump Flows, if used ERIS screen 156 hard copy, Dual Loop Normalized Jet Pump dP's, if used
SVI-B33-'1160 Page:
9 Rev.:
4 Non Quality Records None
6.0 REFERENCES
6.1 Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1 6.2 USAR 3.2.3.2.1, Definition of Safety Class 2 3.9.5.1.2, Reactor Internals Figure 3.9-22, Jet Pump 3.9.5.3.7, Special Requirements for Jet Pump Holddown Beams 4.4.3.3.2, Regions of the Power-Flow Map 15F.2.1.1, Core Flow Measurement During Single Loop Operation 5.4.1.4, Safety Evaluation 6.2.1.1.3.3.1, Recirculation Line Break 6.3.3.7.2, Accident Description 6.3 Regulatory Documents NUREG/CR-3052, Closeout of 1E Bulletin 80-07:
BWR Jet Pump Assembly Failure 6.4 Drawings B-208-016, sh. B02,
- B03, B04 D-302-603 D-302-604 6.5 Vendor/Technical Manuals GE SIL 330 with supplements 6.6 Plant Procedures/Instructions PAP-II05, Surveillance Test Control PAP-0507, Preparation, Review and Approval of Instructions SVI-F41-T3008, Reactor Recirculation System Flow Data Verification Operations Manual 18 (OMI8),
Plant Data Book 6.7 Commitments The following commitments are either partially or fully satisfied by this instruction:
L01960
SVI-B33-ý1160 Page:
10 Rev.:
4 7.0 ATTACHMENTS 7.1 - Manual Recirculation Loop Drive Flow vs. FCV Position.
7.2 -
Manual Recirculation Loop Drive Flow vs. Total Core Flow 7.3 - Normalized Jet Pump dP's Data Sheet.
7.4 - Normalized Jet Pump Flows Data Sheet.
Sheet 1 of 1 NOTE:
Step SVI-B33-1160 Page:
11 Rev.:
4 / C-i Manual Recirculation Loop Drive Flow vs.
FCV Position For single loop operation, the spaces in this attachment may be marked N/A for the idle loop.
Initials
- 1.
Record, for each operating loop, the flow control valve position from the instrument on IH13-P680:
- a.
RCIRC LOOP A FLOW CONTROL:
- b.
RCIRC LOOP B FLOW CONTROL:
B33-K603A
(%)
B33-K603B
- 2.
Record, for each operating loop, the recirculation loop drive flow from ERIS or instruments on 1H13-P680; and indicate the source of the data and the units:
[) C51-R614-blue (%)
- a.
Flow A:
1 1
[ I B33EA028 (kGPM)
- b.
Flow B:
[.
C51-R614-red B33EA030 NOTE:
The limits on the established recirculation loop drive flows are determined from the:
- 1)
<PDB-A0010> graphs for the recirculation loop configuration of Step 4.3,
- 2)
Flow control valve positions of Step 1 of this attachment,
- 3)
Units indicated in Step 2 of this attachment.
- 3.
Confirm, for each operating loop, the recirculation loop drive flow recorded in Step 2 is between the corresponding limits determined from the appropriate "Flow + 10%"
and "Flow -
10%" curves in <PDB-AO010>.
- a.
Loop A:
- b.
Loop B:
YES YES
[ ]
[ ]
NO NO N/A N/A M%)
(kGPM) 4.
2 '
I Sheet 1 of 2 SVI-B33-1160 Page:
12 Rev.:
4 / C-I Manual Recirculation Loop Drive Flow vs. Total Core Flow Step Initials
- 1. Determine the total Recirc Drive Flow by adding the individual Recirc Drive Flows recorded in Step 2 of Attachment 1; and indicate the corresponding units:
If in single loop operation, use zero for the Recirc Drive Flow of the idle loop.
Total Recirc Drive Flow:
_0
[N]
(%)
[I (kGPM)
Independent Verifier:
- 2.
Determine the Total Core Flow from 1B33-R613 or from the combination of 1B33-R612A and IB33-R612B, all on IH13-P680; and indicate the source of the data:
If Total Core Flow is determined from 1B33-R613, mark the spaces for 1B33-R612A, IB33-R612B, and the Independent Verifier N/A.
If, during dual loop operation, 1B33-R613 is not used, add the two jet pump loop flows and record the result as Total Core Flow in Step 2.c of this attachment.
Jet Pump Loop A Flow:
Jet Pump Loop B Flow:
A 1B33-R612A (Mlb/hr) 1B33-R612B (Mlb/hr)
If, during single loop operation, 1B33-R613 is not used:
- 1)
Multiply the idle jet pump loop by 0.95 and record as corrected idle jet pump loop flow:
NA (Mlb/hr)
- 2)
Subtract the corrected idle jet pump loop flow from the operating jet pump loop flow and record the result as Total Core Flow in Step 2.c of this attachment.
Otherwise, mark the corrected idle jet pump flow space above N/A.
- c.
Total Core Flow:
fI 1B33-R612A & B 1B33-R613 (Mlb/hr)
Independent Verifier:
4 imf'
- a.
b.
4-(Cont.)
Sheet 2 of 2 SVI-B33-r1160 Page:
13 Rev.:
4 / C-I Manual Recirculation Loop Drive Flow vs. Total Core Flow (Cont.)
Initials The limits on the established recirculation loop drive flow are determined from the:
- 1)
<PDB-A0012> graph for the recirculation loop configuration of Step 4.3,
- 2)
Total Core Flow of Step 2 of this attachment,
- 3)
Units indicated in Step 1 of this attachment.
- 3.
Confirm that the flow recorded in Step 1 of this attachment is within the limits determined from the appropriate "Drive Flow +
10%"
and "Drive Flow -
10%" curves in <PDB-A0012>.
[ I YES
[*]
NO Step NOTE:
Ij Sheet 1 of 1 SVI-B33-1160 Page:
14 Rev.:
4 / C-i Normalized Jet Pump dP's Data Sheet Initials Record each Sum all Jet Divide each Jet Pump diffuser to lower plenum dP (%):
Pump dPs for each loop, and record as Loop Total dP:
Loop Total dP by 10 and record as Loop Average dP:
- 4.
Divide each Jet Pump dP by its Loop Average dP, and record as Normalized Jet Pump dP:
Loop A 1H13-P619 Jet Pump Instrument Jet Pump Normalized dP (%)
Jet Pump dP IB33-R610A IB33-R610E IB33-R610J IB33-R61ON IB33-R610T IB33-R610C IB33-R61OG 1B33-R610L 1B33-R610R 1B33-R610V "A"
Loop Total dP "A"
Loop Average dP Loop B IH13-P619 Jet Pump Instrument Jet Pump Normalized dP (%)
Jet Pump dP IB33-R610B 1B33-R610F IB33-R610K IB33-R610P IB33-R61OU IB33-R610D IB33-R610H IB33-R610M 1B33-R610S 1B33-R610W "B" Loop Total dP "B" Loop Average dP All calculations independently verified:
Independent Verifier:
Confirm that each normalized jet pump diffuser to lower plenum differential pressure as determined in Step 4 of this attachment is within the corresponding Normalized dP Range of
<PDB-A0009> for the Recirculation Loop configuration indicated in Step 4.3
[ I YES
[ I NO
- 1.
- 2.
3.
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
10.
- 11.
- 12.
- 13.
- 14.
- 15.
- 16.
- 17.
- 18.
- 19.
20.
- 5.
6.
[ I N/A
Attac-mnet 4 Sheet 1 of 1 SVI-B33-T1160 Page:
15 LAST Rev.:
4 / C-I Normalized Jet Pump Flows Data Sheet Initials MA
-MA MR U Pr-
- 1.
Record each Jet Pump diffuser to lower plenum dP (%):
- 2.
Take the square root of each Jet Pump dP, and record as Jet Pump SQRT(dP):
- 3.
Sum all Jet Pump SQRT(dP)s for each loop, and record as Loop Total SQRT(dP):
- 4.
Divide each Loop Total SQRT(dP) by 10 and record as Loop Average SQRT(dP):
- 5.
Divide each Jet Pump SQRT(dP) by its Loop Average SQRT(dP),
and record as Normalized Jet Pump Flow:
Loop A 1H13-P619 Jet Pump Instrument Jet Pump Jet Pump dP (%)
SQRT(dP)
Normalized Jet Pump Flow IB33-R610A 1B33-R610E 1B33-R610J 1B33-R610N 1B33-R610T 1B33-R610C 1B33-R610G 1B33-R610L 1B33-R610R 1B33-R610V "A"
Loop Total SQRT(dP)
"A" Loop Average SQRTdP)
Loop B 1H13-P619 Jet Pump Instrument Jet Pump Jet Pump dP (%)
SQRT(dP)
Normalized Jet Pump Flow 1B33-R610B IB33-R61OF 1B33-R610K 1B33-R610P 1B33-R610U 1B33-R610D IB33-R610H 1B33-R610M 1B33-R610S 1B33-R610W "B" Loop Total SQRT(dP)
"B" Loop Average SQRT(dP)
All calculations independently verified:
Independent Verifier:
Confirm that each normalized jet pump flow as determined in Step 5 of this attachment is within the corresponding Normalized Flow Range of <PDB-A0009> for the Recirculation Loop configuration indicated in Step 4.3
[ I YES
[ I NO
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
10.
- 11.
- 12.
- 13.
- 14.
- 15.
- 16.
- 17.
- 18.
- 19.
20.
- 6.
7.
[ I N/A Mpt Ns A NA Nk -
Appendix C Job Performance Measure Form ES-C-I Worksheet PerrM Determine Isolation Boundaries for Equipment Tagging Task No:
JPM No:
299-925-03-01 2002 NRC RO A2 NRC Examiner:
N/A Date:
Actual Performance Simulator Class / Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
It is 0400 on Saturday morning. Reactor Feed Booster Pump B (1N27-COOIB) experienced high vibration followed by pump seal failure. The pump has been shutdown in accordance with SOI-N27, Section 6.8. In addition, 1P12-F606B is closed and tagged, under OPS Admin Control, to isolate seal water to the RFBP.
Candidate determines the following mechanical and electrical isolation boundaries are required for RFBP B: N27-F050B, F015B, and F503B handwheels; N27-F050B and FO 1 5B breaker disconnects; RFBP B breaker.
P&ID 302-0081-0000-LL Electrical Drawing B-208-149 sheets 04, 08, and 44 PAP-1401, Tagging/Clearances Rev 10, PIC I P&ID 302-0081-0000-LL Electrical Drawing B-208-149 sheets 04, 08, and 44 The Unit Supervisor directs you, as the Reactor Operator, to identify all of the components, including their required positions, for a Clearance that will isolate Reactor Feed Booster Pump B (N27-C0001B).
Clearance paperwork is not required to be generated.
NO 20 minutes NUREG 1021, Revision 8, Supplement I Facility:
Task
Title:
K/A
Reference:
2.2.13 Examinee:
Facility Evaluator:
Method of testing Simulated Performance Classroom
Appendix C Page 2 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Evaluator Note: 1.
The candidate may determine isolation boundaries in any order.
- 2.
The candidate is not required to identify P44 motor cooling water isolation valves 1P44-F624B and 1P44-F625B.
- 3.
The candidate is not required to identify 1N27-F670B, 1N27-F714B, or 1N27-F592B since they are vent or drain valves located within the isolation boundaries.
" Performance Step:
Standard:
Comment:
"* Performance Step:
Standard:
Comment:
- Performance Step:
Standard:
Comment:
Close and tag 1N27-F050B, RFBP B Discharge Valve handwheel.
Identify 1N27-FO50B valve handwheel to be closed and tagged.
Feedwater P&ID 302-0081-0000-LL.
Close and tag 1N27-FO 15B, RFBP B Suction Isolation Valve handwheel.
Identify 1N27-FO15B valve handwheel to be closed and tagged.
Feedwater P&ID 302-0081-0000-LL.
Close and tag 1N27-F503B, RFBP B Casing Warmup Isolation Valve handwheel.
Identify 1N27-F503B valve handwheel to be closed and tagged.
Feedwater P&ID 302-0081 -0000-LL NUREG 1021, Revision 8, Supplement 1
Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION
" Performance Step:
Standard:
Comment:
" Performance Step:
Standard:
Comment:
Performance Step:
Standard:
Comment:
Tag control switch and open and tag breaker disconnect for 1N27-F050B, RFBP B Discharge Valve.
Identify breaker disconnect (FIB06 Comp W) to be opened and tagged.
Note: The tagging of the control switch (S66) is optional per PAP-1401 and is not a critical step.
Electrical Drawing B-208-149 sh. 08 Tag control switch and open and tag breaker disconnect for 1N27-FO 153B, RFBP B Suction Isolation Valve.
Identify breaker disconnect (FIB06 Comp U) to be opened and tagged.
Note: The tagging of the control switch (S72) is optional per PAP-1401 and is not a critical step.
Electrical Drawing B-208-149 sh 44 Tag RFBP B control switch and rack out and tag RFBP B breaker H1208.
Identify breaker H1208 to be racked out and tagged.
Note: The tagging of the control switch (S3) is optional per PAP-1401 and is not a critical step.
Electrical Drawing B-208-149 sh 04 Terminating Cue:
The evaluation for this JPM is complete when the candidate has identified the required isolation boundaries NUREG 1021, Revision 8, Supplement I
Appendix C Page 4 of 5 Form ES-C-1 Question Documentation:
Question:
Response
Result:
SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement I Appendix C Page 4 of 5 VERIFICATION OF COMPLETION Job Performance Measure No.
2002 NRC RO A2 Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
N/A Number of Attempts:
Time to complete:
Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
It is 0400 on Saturday morning. Reactor Feed Booster Pump B (IN27-COOIB) experienced high vibration followed by pump seal failure.
The pump has been shutdown in accordance with SOI-N27, Section 6.8. In addition, 1P12-F606B is closed and tagged, under OPS Admin Control, to isolate seal water to the RFBP.
INITIATING CUE:
The Unit Supervisor directs you, as the Reactor Operator, to identify all of the components, including their required positions, for a Clearance that will isolate Reactor Feed Booster Pump B (N27-COOO1B).
Clearance paperwork is not required to be generated.
NUREG 1021, Revision 8, Supplement 1
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
Task
Title:
K/A
Reference:
Perry Comply with Administrative Dose Controls Levels for Assigned Job Task Task No:
JPM No:
299-848-01-01 2002 NRC A3 RO
2.3.1 Examinee
Facility Evaluator:
NRC Examiner:
N/A Date:
Method of testin2 Simulated Performance Classroom In-Plant Actual Performance Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
NUREG 1021, Revision 8, Supplement I
Appendix C Job Performance Measure Form ES-C-1 Worksheet Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
The plant is operating at 100% power. HPCS Alternate Keepfill Startup using P21 is in progress per SOI-E22A, Section 7.8.2. Steps I through 5 are completed.
You have been assigned to open HPCS Pump Discharge Line Flush Connection Valve, 1E22-F031 in accordance with Step 6.
Your calculated stay time is 30 minutes. Your current year-to-date exposure is 965 mrem (TEDE).
Candidate determines he would exceed his Perry Administrative Dose Control Level of 1000 mrem/year (TEDE) for the assigned job task and recommends that he not be given the in-plant job assignment.
Survey Map (marked up copy)
SOI-E22A, High Pressure Core Spray System Rev 5, PIC 10 HPI-B0003, Processing of Personnel Dosimetry Rev 8, PIC 4 SOI-E22A, High Pressure Core Spray System Rev 5, PIC 10 PNPP Radiation Worker Training Information Manual HPI-B0003, Processing of Personnel Dosimetry Rev 8, PIC 4 Determine if you can perform the in-plant job assignment in accordance with Perry Administrative Dose Control Levels.
NO 10 minutes NUREG 1021, Revision 8, Supplement 1
Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Note: This JPM should be performed prior to performing In-plant JPM P1 (Commence Alternate Boron Injection).
Note: This JPM can be administered in the plant, the simulator, or the classroom.
Performance Step: 1 Determine the location of HPCS Pump Discharge Line Flush Connection valve, 1E22-F03 1.
Standard:
Determines valve 1E22-F031 is located at Aux Building 620' D/02.
Comment:
Performance Step: 2 Standard:
Comment:
"Performance Step: 3 Standard:
Comment:
Note: Candidate is allowed to reference SOI-E22A, VLI-E22A, or any other plant reference that would state the location of the valve.
Locate the correct Survey Map in order to determine the dose rate for the assigned job task.
Locates Survey Map that includes valve 1E22-F03 1. (Aux Building, 620', HPCS Valve Room).
Cue: Provide candidate with marked up Survey Map after he either shows or states that the Survey Maps are keep at the RCA entrance.
Determine the hypothetical dose for the assigned job task.
Using Survey Map, determines the dose rate in the vicinity of valve 1E22-F031 is 100 mrem/hour.
Determines his hypothetical dose is 50 mrem.
100 mrem/hour x 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> = 50 mrem NUREG 1021, Revision 8, Supplement 1
Appendix C Page 4 of 6 Form ES-C-I PERFORMANCE INFORMATION Performance Step: 4 Standard:
Comment:
Determine the hypothetical yearly dose total (TEDE) if the assigned job task is performed.
Determines his hypothetical yearly dose total (TEDE) will be 1015 mrem.
Reports that he should not perform the in-plant job assignment because he will exceed his current Perry Administrative Dose Control Level of 1000 mrem/year.
965 mrem (current) + 50 mrem (job task) = 1015 mrem.
Terminating Cue:
The evaluation for this JPM is complete when the candidate determines he would exceed his Perry Administrative Dose Control Level of 1000 mrem/year if he was to perform the assigned job task.
NUREG 1021, Revision 8, Supplement 1
Appendix C Page 5 of 6 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Job Performance Measure No.
2002 NRC A3 RO Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
N/A Number of Attempts:
Time to complete:
Form ES-C-1 Question Documentation:
Question:
Response
Result:
SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement 1
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Appendix C Page 6 of 6 Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS:
INITIATING CUE:
The plant is operating at 100% power. HPCS Alternate Keepfill Startup using P21 is in progress per SOI-E22A, Section 7.8.2. Steps I through 5 are completed.
You have been assigned to open HPCS Pump Discharge Line Flush Connection Valve, 1E22-F031 in accordance with Step 6.
Your calculated stay time is 30 minutes. Your current year-to-date exposure is 965 mrem (TEDE).
Determine if you can perform the in-plant job assignment in accordance with Perry Administrative Dose Control Levels.
NUREG 1021, Revision 8, Supplement I
Appendix C Job Performance Measure Form ES-C-1 Worksheet Percy Perform Site Accountability Actions from Outside Control Room Task No:
JPM No:
N/A 2002 NRC A4 RO K/A
Reference:
Examinee:
Facility Evaluator:
2.4.39 NRC Examiner:
N/A Date:
Method of testin2 Simulated Performance Classroom Plant Actual Performance Simulator N/A Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
NUREG 1021, Revision 8, Supplement I Facility:
Task
Title:
Appendix C Job Performance Measure Form ES-C-I Worksheet Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
You are the Operations Foreman currently in the plant when a Site Area Emergency occurs.
The following messages are being broadcast over the Plant PA System:
"Attention all site personnel. Accountability is now in effect.
Personnel performing a plant operating or emergency function, report your location to the Control Room or appropriate emergency facility.
All other personnel exit the site using normal exiting procedures."
"Attention all site personnel. The OSC and TSC are being activated."
Candidate locates the OSC (CC 599'). Candidate then locates the Emergency Personnel Accountability card reader located in the TSC hallway (SB 605') and simulates inserting his keycard into the card reader.
None EPI-B5, Rev 6, PIC 6 The Shift Manager directs you to report directly to the Operations Support Center and await the arrival of the shift Plant Operators.
No 5 minutes NUREG 1021, Revision 8, Supplement 1
Appendix C Page 3 of 5 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Performance Step: 1 Standard:
Comment:
Performance Step: 2 Standard:
Comment:
Performance Step: 3 Standard:
Comment:
Locate the Operations Support Center (CC 599') as directed.
Locates the Operations Support Center (OSC) at CC 599'.
Cue: Direct the candidate to demonstrate the actions that he would be required to perform in order to complete Site Accountability before he is logged into the OSC.
Locate the Emergency Personnel Accountability card reader in the TSC hallway (Service Building 605').
Candidate locates the Emergency Personnel Accountability card reader in the TSC hallway (Service Building 605').
Note: the candidate was directed to report immediately to the OSC, therefore he would not be expected to use the Unit 1 or Unit 2 Control Room Emergency Personnel card reader just inside the Control Room door.
Insert and then withdraw keycard into the designated accountability card reader.
Inserts (simulates) and then withdraws keycard into the designated accountability card reader.
Cue: The red light has blinked on the accountability card reader.
Terminating Cue:
The evaluation for this JPM is complete when the candidate locates the OSC and completes his actions to demonstrate Site Accountability.
NUREG 1021, Revision 8, Supplement 1
Form ES-C-I Question Documentation:
Question:
Response
Result:
SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement 1 Appendix C Page 4 of 5 VERIFICATION OF COMPLETION Job Performance Measure No.
2002 NRC A4 RO Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
N/A Number of Attempts:
Time to complete:
Appendix C Page 5 of 5 Form ES-C-I JPM CUE SHEET INITIAL CONDITIONS:
INITIATING CUE:
You are the Operations Foreman currently in the plant when a Site Area Emergency occurs.
The following messages are being broadcast over the Plant PA System:
"Attention all site personnel. Accountability is now in effect. Personnel performing a plant operating or emergency function, report your location to the Control Room or appropriate emergency facility. All other personnel exit the site using normal exiting procedures."
"Attention all site personnel. The OSC and TSC are being activated."
The Shift Manager directs you to report directly to the Operations Support Center and await the arrival of the shift Plant Operators.
NUREG 1021, Revision 8, Supplement I
OSC STAFF ACCOUNTABILITY ACTIONS ACCOUNTABIUTY INITIATED Yes USE CARD READER AT TSC ACCESS OR REPORT LOCATION TO OSC CONFERENCE ROOM (59V CCB) USING AVAILABLE COMMUNICATIONS NF974 w
(-n (D
ct (D
- I f-t cD C)
II
EPI-A7 Page:
6 Rev.:
9 / C-4
- 5.
Periodically update the Operations Foreman on plant status and emergency activities presently underway or required, and obtain a status of on-going and completed OSC activities.
5.2 OSC Coordinator 5.2.1 Activation
- 1.
Use the OSC Activation Checklist (PNPP No.
7992, Attachment 1) to track and document completion of the activation actions outlined below.
NOTE:
Goal for OSC activation is 45 minutes:
30 minutes response time when notified, plus 15 minutes to reach operational status.
- a.
If directed to use the Unit 2 Control Room an alternate OSC location, perform the following:
- 1)
Obtain the OSC Equipment kit stored in the Unit 1 Control Room E-Plan Locker which contains forms, procedures, etc., to aid in the initial activation of the OSC.
- 2)
Identify OSC personnel assembly areas to address space limitations and/or occupancy restrictions.
- 3)
Relocate the Plant Emergency Instruction (PEI) tool cabinet to the alternate OSC, based on ability to access the 599' CCB.
- 2.
Determine available OSC staff present in or responding to the OSC.
- a.
Direct available personnel to initiate callouts for required PMS supervisors and craft based on the event, using the PMS Callout List (maintained by PMS in the OSC).
Ensure the fitness for duty status of all call-ins as determined per <NOP-LP-1002>.
- b.
Verify that the on-shift Radiation Protection Supervisor or Technician-In-Charge has initiated callouts per
<RPI-0124> to ensure minimum staffing levels are met.
NOTE 1:
A minimum of four RP technicians, in support of in-plant activities, are required at an Alert.
NOTE 2:
A minimum of seven RP technicians, in support of in-plant activities, are required at a Site Area Emergency.
- c.
Direct the on-shift Chemistry Technician to callout a second Chemistry Technician or Supervisor per
<NOP-LP-1002>,
if not presently on-site, for events classified as a Site Area Emergency.
EPI-A7 Page:
7 Rev.:
9 / C-4
- 3.
Identify I&C technicians qualified as Control Room/TSC Communicators and, if requested, dispatch to the TSC to assist in facility activation.
- 4.
Identify qualified RMT Leaders and Helpers present in the OSC, and when requested, dispatch to EOF Decontamination Room as RMTs are mobilized.
NOTE:
Ensure minimum RP complement (4 at Alert/7 at Site Area Emergency) is maintained as OSC in-plant support.
Callouts for additional RMT personnel, if required, will be initiated by TSC per <EPI-B3>.
- 5.
Direct personnel reporting to the OSC Conference Room, to utilize the "accountability" card reader located in the TSC hallway.
- a.
If the TSC "accountability" card reader is inoperable, obtain a listing of personnel reporting to the OSC using the Personnel Accountability Checklist form (PNPP No.
7957).
- b.
When a Site Area Emergency is declared concurrent with OSC activation, direct available RP personnel to issue dosimetry to OSC staff per <HPI-B0003>.
NOTE:
OSC personnel located outside the Protected Area will report to the TEC Auditorium, Ext. 7817, once accountability is declared.
- 6.
Utilize the OSC status boards and OSC Team Briefing/Debriefing Sheets (PNPP No.
7993, Attachment 2) to maintain accountability of OSC personnel leaving or dispatching from the OSC.
- 7.
Contact the Shift Supervisor to obtain a briefing on plant conditions and emergency actions requiring OSC support.
- 8.
If a potential radiological hazard exists, Radiation Protection to initiate periodic monitoring of area and airborne radiation levels in the OSC and adjacent areas.
<P00092>
- 9.
Synchronize OSC Conference Room wall clock with ICS by contacting TSC.
ES-301 Administrative Topics Outline Form-ES-301-1 Facility: Perry Date of Examination: 3/4/2002 Examination Level: SRO Operating Test Number: 2002-01 Administrative Describe method of evaluation:
Topic/Subject
- 2. TWO Administrative Questions A. 1 Shift Turnover 2.1.3 (3.4) - Knowledge of Shift Turnover Requirements JPM: Complete a Shift Relief/Turnover Checklist as the oncoming operator Feedwater 2.1.7 (4.4) - Ability to Evaluate Plant Performance and Make Operational Judgements Based on Temperature Operating Characteristics / Reactor Behavior / Instrument Interpretation Reduction Ops JPM: Prepare for Feedwater Temperature Reduction Operations A.2 Risk Assessment 2.2.17 (3.5) - Knowledge of the Process for Managing Maintenance Activities During Power Operations JPM: Perform an On-Line Risk Determination A.3 Radiation Control 2.3.1 (3.0) - Knowledge of 10CFR20 and Related Facility Radiation Control Requirements requirements JPM: Comply with Administrative Dose Control Levels for assigned job task A.4 Emergency Plan 2.4.29 (4.0) - Knowledge of the Emergency Plan JPM: Classify an Emergency event, make Protective Action Recommendations, and complete paperwork for notification of Off-Site authorities NUREG-1021, Revision 8 Final - Revision 2
SAFETY SIGNIFICANCE OF SRO ADMIN JPMs & QUESTIONS A.L.a 2.1.3 (3.4)
Complete a Shift Relief/Turnover Checklist as the oncoming operator.
This JPM is safety significant because failure to recognize equipment out of service (RCIC) not identified on the shift relief/turnover checklist, in conjunction with HPCS already being out of service, would result in reduced ability to assure adequate core cooling. Also, failure to identify the SB&PR regulator error on the shift relief/turnover checklist could result in an unplanned reactor shutdown.
A.l.b 2.1.7 (4.4)
Prepare for Feedwater Temperature Reduction Operations This JPM is safety significant because failure to recognize that Final Feedwater Temperature is below the applicable feedwater temperature curve would result in reactor operation outside the assumptions of the safety analysis with respect to the Minimum Critical Power Ratio thermal limit.
A.2 2.2.17 (3.5)
Perform an On-Line Risk Determination This JPM is safety significant because failure to properly perform the On-Line Risk Determination could result in the station entering an equipment configuration that directly increases the probability of occurrence of an accident or directly increases the consequence of an accident.
A.3 2.3.1(3.0)
Comply with Administrative Dose Control Levels for assigned job task This JPM is safety significant because failure to determine that the initial Perry Administrative Dose Control Level will be exceeded for an individual could result in unnecessary additional radiation exposure and violation of the intent of the ALARA principle.
A.4 2.4.29 (4.0)
Classify an Emergency Event, make Protective Action Recommendations, and complete paperwork for notification of Off-Site authorities This JPM is safety significant because failure to properly classify an event, failure to make the appropriate Protective Action Recommendations for an event, or failure to make the appropriate notifications would directly threaten the health and safety of the public.
Final - Revision 2 Page I of I
Appendix C Job Performance Measure Form ES-C-1 Worksheet Perry Complete a Unit Supervisor Relief/Turnover Checklist as the On-Coming Unit Supervisor Task No:
JPM No:
299-933-03-01 2002 NRC A l a SRO NRC Examiner:
N/A Date:
Simulated Performance Actual Performance Classroom Simulator In Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
The plant is operating at 100% power. You are the on-coming Day Shift Unit Supervisor. You have completed Section A of the Unit Supervisor Relief/Turnover Checklist with the exception of the Control Room Horseshoe Panel Walkdown.
Candidate identifies RCIC is not in Stby Readiness due to both suction valves being closed (E51--F031 and E511-F010) and determines the plant must be in MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> (due to HPCS and RCIC being inoperable) unless either HPCS or RCIC is restored to OPERABLE.
PAP-0126, Attachment 3 (attached marked up copy)
Technical Specifications Simulator IC Setup Sheet (attached)
PAP-0126, Shift Staffing and Shift Relief, Rev. 2, PIC 2 Complete the Unit Supervisor Relief/Turnover Checklist by performing the Control Room Horseshoe Panel Walkdown for panels H13-P877, P601, and P680 in accordance with PAP-0 126.
NO 30 minutes NUREG 1021, Revision 8, Supplement I Facility:
Task
Title:
K/A
Reference:
2.1.3 Examinee
Facility Evaluator:
Method of testing
Appendix C Page 2 of 5 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Performance Step:
P601 Standard:
Comment:
Performance Step:
P680 Walkdown Control Room Horseshoe observing items such as active annunciators, status lights, train alignments, control board tags, and various parameters.
Candidate identifies RCIC is not in Stby Readiness due to E5 1 -F03 I and E5 I -FO 10 being closed.
Note: Annotation of the completion of the Control Room Panel Walkdown on the US Relief/Turnover Checklist is not a critical step.
Note: Failure to identify that RCIC is not listed as being out of service on the US Relief/Turnover Checklist is not a critical step.
Walkdown Control Room Horseshoe observing items such as active annunciators, status lights, train alignments, control board tags, and various parameters.
Standard:
Candidate identifies Pressure Regulator B is the in-service Pressure Regulator. Determines in-service Pressure Regulator was incorrectly annotated on the Unit Supervisor Relief/Turnover Checklist.
Comment:
Note: At the completion of the Control Room Horseshoe panel walkdown, direct the candidate to determine the operational implication of RCIC not being in Stby Readiness in conjunction with any other equipment currently out of service.
Performance Step:
Determine the operational implication of RCIC not being in Stby Readiness in conjunction with any other equipment currently out of service (i.e., HPCS).
Candidate identifies that RCIC is inoperable due to not being in Stby Readiness (LCO 3.5.3). In conjunction with HPCS being inoperable, the plant will be required to be in MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> (LCO 3.5.3, Conditions A and B).
Note: Per LCO 3.5.3, 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> is based on a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time for Required Action A.1 and a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time for Required Action B.1.
NUREG 1021, Revision 8, Supplement I Standard:
Comment:
Appendix C Page 3 of 5 Form ES-C-i PERFORMANCE INFORMATION Terminating Cue:
The evaluation for this JPM is complete when the candidate completes the Control Room Horseshoe Panel walkdown for panels P877, P601, and P680 and determines the operational implication of HPCS and RCIC being inoperable.
NUREG 1021, Revision 8, Supplement I
Appendix C Page 4 of 5 Result:
Form ES-C-1 SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement I ApXFpendix C Page 4 of 5 VERIFICATION OF COMPLETION Job Performance Measure No.
2002 NRC Ala SRO Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
N/A Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Appendix C Page 5 of 5 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
INITIATING CUE:
The plant is operating at 100% power. You are the on-coming Day Shift Unit Supervisor. You have completed Section A of the Unit Supervisor Relief/Turnover Checklist with the exception of the Control Room Horseshoe Panel Walkdown.
Complete the Unit Supervisor Relief/Turnover Checklist by performing the Control Room Horseshoe Panel Walkdown for panels H 13-P877, P60 1, and P680 in accordance with PAP-0126.
NUREG 1021, Revision 8, Supplement 1
US RELIEFITURNOVER CHECKLIST Paae 1 of 2 PNPP No. 8293 Rev. 4/23/01 Section A:
Date: 03-XX-02 Shift: [: NIGHT Z DAY
-1AFT Mode:
1 Thermal Power: 100% (3758 Mwth limit)
Level Band: 192 to 200" by SPDS Discuss the following:
Equipment Out-Of-Service/Maintenance in progress (include open manholes):
ALCO's G36 Demin A C51 - ALL OPRM'S P52 Unit 1 IA Compressor E22A HPCS Pump C85 1B Press Regulator P61 A feed Pump P61 A boiler fan flow switch P54 A007 Tank # 7 (MLO)
ODCM POD Activities Upper Air Lock LLRT ONI's PTI-GENP0024 Test/Evolutions (completedlin progresstplanned):
C - SVI-E51-T2001 RCIC Pump and Valve Operability C - Unloaded 2 Aux Boiler fuel oil trucks C - P61-0013 clearance removal feed pump A C - Restored Perry - East Lake Line C - P52 U1 IA Compressor in Secured status to support Demister change.
P - I&C troubleshooting 1C85N0001B Pressure Regulator P - G36 A F/D Backwash and precoat P - Prepare for FIN Work on N23 H Filter (Days)
PAP-01 26 I
i I
i
US RELIEF/TURNOVER CHECKLIST Paae 2 of 2 PNPP No. 8293 Rev. 4/23/01 Equipment Under Administrative Controls:
LH-1-A and LH-1 -B ABT's, keep aligned to breaker 8C-2 OAT on 8C-1.
N64-F0064B- (Dryer B loop Seal)
N64C0001A-Glyc. CW pump abn. noise P61-F0823 G42-F0175-F/D drain leaking
-1 I-Tech Spec 3.6.1.3 / 3.6.5.3 inop valves Penetration Controls Reviewiperform the following:
Z Plant Narrative Log Z ECCS Status Board
[
Control Room Panel Walkdown Z Active LCO Status Z Daily & Standing Instructions
[
Active Annunciators Section B:
Review the following:
E RO Checklist Z
DLCO Tracking Sheets Z
Potential LCO Status Z
Surv. Tracking Schedule Z Condition Change Checklist Z
Ops Admin Tag Logbook Status Z Review Control Room NOMS Additional Turnover Items/Remarks:
Monitoring Rectifiers for leakage (camera is in place)
Minimum ESW flow allowed to RHR-B Hx - 6700 gpm ( DI) w Stem leakoff alarm/bypass pts 24, 25
-1 I-PAP-0126 On-coming US: List the names of any US or RO who are working overtime this shift (excluding turnover time.)
Off-going US:
On-coming US:
Appendix C Job Performance Measure Form ES-C-i Worksheet Facility:
Perry Task
Title:
K/A
Reference:
Prepare for Feedwater Temperature Reduction Operations Task No:
JPM No:
344-506-04-02 2002 NRC AIb SRO 2.1.7 NRC Examiner:
Facility Evaluator:
Method of testing Simulated Performance Classroom N/A Date:
N/A Actual Performance Simulator In Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
The plant is operating at 80% power. ONI-N36, Loss of Feedwater Heating, has been entered due to the loss of Feedwater Heaters 5A and 6A. All immediate actions of ONI-N36 have been completed. It will take 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to affect repairs and return the feedwater heaters to service.
Candidate identifies the new Pressure Setpoint and Allowable Values are < 190 and 196 psig respectively and initiates the process for preparing an Provisional Setpoint Change Request.
FTI-B 10, Rev 5, PIC 1 PDB-A0011, Rev 2 Simulator IC Setup Sheet (attached)
FTI-B 10, Rev 5, PIC 1 PDB-AOO 11, Rev 2 The Shift Manager directs you, as the Unit Supervisor, to perform FTI-B 10, Preparation for Final Feedwater Temperature Reduction Operation.
NO 10 minutes NUREG 1021, Revision 8, Supplement 1 Examinee:
Appendix C Page 2 of 5 Form ES-C-I PERFORMANCE IMFORMATION (Denote Critical Steps with an asterisk)
Performance Step:
5.1.1 Standard
Comment:
Performance Step:
5.1.2 Standard
Determine Feedwater temperature relative to full power operation.
- a. For an unplanned event, obtain the operating feedwater temperature. For less than full power conditions, extrapolate to the equivalent full power feedwater temperature using <PDB-AOO11 >.
Obtains the operating feedwater temperature and determines the extrapolated equivalent full power feedwater temperature to be approximately 390 'F using PDB-AOOI11.
Note: Average FDW temperature (per NSSS Heat Balance Screen) is approximately 370 'F.
Determine the Pressure Setpoint and Allowable Value corresponding to the feedwater temperature using Attachment 1.
Determines the new Pressure Setpoint is < 190 and new Allowable Value is < 196 psig increasing based on a Feedwater temperature range of 425.5 to 375.5 'F per Attachment 1.
Comment:
Performance Step:
5.1.3 Standard
Comment:
Process Provisional Setpoint Change Requests per <PAP-1403> to change the pressure setpoints for trip units 1C71-N0652A, B, C, and D to the values determined in step 5.1.2.
Recognizes requirement to initiate Provisional Setpoint Change Requests.
Cue: The Shift Manager will direct the responsible Engineer to process the Provisional Setpoint Change Requests.
Note: FTI-B 010 describes a Provisional Setpoint Change Request.
However, it is actually called an Exempt Instruction Setpoint Change Request per PAP-1403.
Note: Step 5.1.4 is not required to be completed until Step 5.1.3 is completed.
NUREG 1021, Revision 8, Supplement 1
Appendix C Page 3 of 5 Form ES-C-i PERFORMANCE IMFORMATION Terminating Cue:
The evaluation for this JPM is complete when the candidate determines the new Pressure Setpoint and Allowable Values and recognizes the requirement to initiate Provisional Setpoint Change Requests.
NUREG 1021, Revision 8, Supplement I
Appendix C Page 4 of 5 Form ES-C-1 VERIFICATION OF COMPLETION Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Result:
2002 NRC AIb SRO N/A SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement I
Appendix C Page 5 of 5 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
INITIATING CUE:
The plant is operating at 80% power. ONI-N36, Loss of Feedwater Heating, has been entered due to loss of Feedwater Heaters 5A and 6A. All immediate actions of ONI-N36 have been completed. It will take 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to affect repairs and return the feedwater heaters to service.
The Shift Manager directs you, as the Unit Supervisor, to perform FTI-B 10, Preparation for Final Feedwater Temperature Reduction Operation.
NUREG 1021, Revision 8, Supplement 1
Appendix C Job Performance Measure Form ES-C-1 Worksheet Perry Perform On-Line Risk Assessment Task No:
JPM No:
342-650-03-02 2002 NRC A2 SRO NRC Examiner:
N/A Date:
Actual Performance Simulator Class / Simulator Plant READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
NUREG 1021, Revision 8, Supplement I Facility:
Task
Title:
K/A
Reference:
2.2.17 Examinee:
Facility Evaluator:
Method of testing Simulated Performance Classroom
Appendix C Job Performance Measure Form ES-C-I Worksheet Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
The plant is in MODE 1. The HPCS System is to be placed in secured status for preventative maintenance during the next hour. ESW Pump A just tripped on motor overcurrent while operating to support a liquid radwaste discharge. All other plant equipment is operable. The PSA Engineer is not available. A Plant Narrative Log entry has not been made for ESW Pump A.
Candidate identifies the new Risk Category as '2' (color is orange and the CDF is 3.42E-04) for the hypothetical situation of the HPCS and ESW A Systems being inoperable at the same time and recommends that HPCS should not be removed from service for preventative maintenance.
Safety Monitor Desk Guide A Computer station loaded with the Safety Monitor Program PAP 1924, Rev. 2, PIC 2 Safety Monitor Desk Guide Using the Safety Monitor in the 'Hypothetical Mode', determine the Risk Category for the case of the HPCS System and ESW Pump A being inoperable at the same time, includino your recommendation for removing the HPCS System from service.
The Safety Monitor Program is currently in the 'Real Mode' with a simulated plant configuration.
NO 15 minutes NUREG 1021, Revision 8, Supplement I
Appendix C Page 3 of 6 Form ES-C-I PERFORMANCE INFORMATION IMPORTANT INFORMATION ***
Admin JPM Setup Instructions
- 1. Open the Safety Monitor 3.Oa Program.
- 2. Select 'Real Mode'.
- 3. On the 'Real Time Operation' screen, verify the following parameters are set:
- a. Click on the 'View / Change Plant Configuration' tab.
- 1) Click on the 'Environ / Testing' tab.
a)
Verify the 'Environment / Test factor' indicates 'SWITCHYARD'.
- 2) Click on the 'Operating Mode' tab.
a)
Verify the 'Mode' indicates '1'.
- 3) Click on the 'Alignment' tab.
a)
Using 'All Systems', verify that that the equipment lineup reflects a 100% normal full power lineup.
- 4. On the 'Real Time Operation' screen, confirm the CDF value is 3.55E-6 and the color is green.
The Safety Monitor initial setup is now complete.
Admin JPM Completion Instructions After the completion of the JPM by a license candidate, the following steps must be performed to clear the previous CDF calculation and then setup the Safety Monitor for the next license candidate.
- 1. Select'Real Mode'.
- 2. Select 'Hypothetical Mode'.
- 3. Select 'Real Mode Configuration'.
- 4. Select 'Real Mode'.
- 5.
Confirm the CDF value is 3.55E-6 and the color is green.
The Safety Monitor setup is now completed for the next license candidate.
NUREG 1021, Revision 8, Supplement I
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Performance Step: 1 Place the Safety Monitor in the Hypothetical Mode and determine the Risk Category for the hypothetical case of the HPCS System and ESW Pump A being inoperable at the same time.
Standard:
Determines the plant would be in Risk Category '2' (color is orange and the CDF value is 3.42E-04) in accordance with the definition of Risk Category and recommends that the HPCS System not be removed from service for preventative maintenance due the increased risk.
This is the general sequence of steps for the Safety Monitor Program:
- 1. Select 'Hypothetical Mode'.
- 2.
Select either 'Real mode configuration' or 'Current hypothetical configuration'.
Note: Either configuration contains the same identical conditions.
- 3. Select 'View / Change Plant Configuration'.
- 4. Select 'Component Status'.
- 5. Select 'E22 High Pressure Core Spray System'.
- 6.
Select '1E22C0001 Pump, High Pressure Core Spray'.
Note: Inoperability Information-the type of inoperability is not critical.
- 7.
Select 'P45 Emergency Service Water System'.
- 8. Select 'IP45CO001A Emergency Service Water Pump A'.
- 9.
Select 'Calculate'.
Comment:
Note: The Instructor must follow the 'Admin JPM Completion Instructions' on the previous page in order to setup the Safety Monitor for another performance of this JPM.
Terminating Cue:
When the candidate determines the new Risk Category using the Safety Monitor and makes his recommendation regarding the removal of HPCS from service for preventative maintenance, the evaluation for this JPM is complete.
NUREG 1021, Revision 8, Supplement I
Appendix C Page 5 of 6 Question Documentation:
Question:
Response
Result:
Examiner's Signature and Date:
Form ES-C-I SAT OR UNSAT NUREG 1021, Revision 8, Supplement 1 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Job Performance Measure No.
2002 NRC A2 SRO Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
N/A Number of Attempts:
Time to complete:
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
INITIATING CUE:
The plant is in MODE I. The HPCS System is to be placed in secured status for preventative maintenance during the next hour. ESW Pump A just tripped on motor overcurrent while operating to support a liquid radwaste discharge. All other plant equipment is operable. The PSA Engineer is not available. A Plant Narrative Log entry has not been made for ESW Pump A.
Using the Safety Monitor in the 'Hypothetical Mode', determine the Risk Category for the case of the HPCS System and ESW Pump A being inoperable at the same time, including your recommendation for removing the HPCS System from service.
The Safety Monitor Program is currently in the 'Real Mode' with a simulated plant configuration.
NUREG 1021, Revision 8, Supplement 1
Safety Monitor Desk Guide Item 6-1 November 12, 2001 Prepared By:
_signature on file________________
M. S. Rupp PSA Element Approved By:
-signature on file__________________
Nuclear Unit Supr.
Brian Stetson
Safety Monitor Desk Guide Item 6-1 Page 1 of 7 November 12, 2001 Scope This desk guide covers those functions associated with the Real Mode and the Hypothetical Mode of Safety Monitor 3.Oa and the Manual and Auto modes of ROMAL 2.04. These modes support online risk assessment of plant operations. Other modes will be added, as required, at a later date.
General The Program Administrator will control the software in accordance with NOP-SS-1001, "FENOC Administrative Program for Computer Related Activities". User access levels will be set up to limit access to various program modes. The Administrator will have read/write access to all modes.
The Real Mode will be read/write accessible from the dedicated Safety Monitor PC in the Control Room, using the logon ID. The Control Room PC will contain the official version of the Safety Monitor plant history. All other Logon IDs will have read only access to Real Mode. STAs will have read/write access to Hypothetical Mode, while Work Management will have read/write access to the Schedule Mode (later).
Real Mode and Hypothetical Mode functions will be described below.
Functions
- 1) Booting/Re-Booting Safety Monitor and ROMAL in Control Room using Logon ID a) When the boot process has completed, de-activate automatic virus checking by clicking on the icon in the lower right comer of the screen, and click on the disable button.
b) Double click on the icon found on the Desktop to start Safety Monitor 3.0a. (The executable is located in C:\\SM30a\\SM30.EXE) Click OK to continue. Enter USER ID and PASSWORD (upper case) then click "OK". When the self-check is finished, then main screen will appear.
c) Click on View on top in the window bar, and then select Real Mode. Next click on Zoom and select 1 day or 7 day.
d) Next click on Options, select Import Formats, and make sure the following are set:
Comma delimited 1 header line YYYYMMDD HHMM date format
Safety Monitor Desk Guide Item 6-1 Page 2 of 7 November 12, 2001 Selected fields are in the following order:
Activity Component Event Type Functionally unavailable Begin date End date Comment Click OK to continue. Next, click on Options, select Auto Data Import then select Set Import Data File. Verify S:\\V DRIVE\\SMDATA\\REALDATA.TXT is the file named. Click NO if the file name is correct, or YES if it is not and change it to be correct.
e) Next click on Options and then Auto Data Import. Then, select Enable Auto Import.
f) Double click on the icon found on the Desktop to start ROMAL 2.04. The executable file is located in C:\\SM30\\ROMAL204.MDB. Click on MANUAL UPDATE. (You may be prompted for a password for NOMSREAD.) This function transfers Narrative Log information since the Safety Monitor "last configuration" date. This may take several minutes.
g) When MANUAL UPDATE is complete, click on AUTO. ROMAL is now in auto mode.
h) Minimize ROMAL and maximize Safety Monitor. Safety Monitor is now in REAL mode with an automatic link to the Narrative Log.
Potential problems with SM
"* If you see a message box about not being able to open the Import Log File, click on OK. This may occur a number of times in a row, so just keep clicking OK until it is cleared.
"* If you see a message box about not being able to open a table or query, this is a symptom of network trouble. Shut down the PC from the START button. Re-boot in accordance with 1) above.
"* If the program locks up, try to shut down without turning off the power. Otherwise shut off the power. Re-boot in accordance with 1) above.
Potential problems with ROMAL If the Last Calculation Date in ROMAL doesn't agree with Safety Monitor Last Configuration Date, or the Wait Begins time is not within 45 seconds of PC time (lower right comer), then close ROMAL and restart by clicking on the desktop icon. Follow steps f) and g) of 1) above.
Safety Monitor Desk Guide Item 6-1 Page 3 of 7 November 12, 2001
- 2) Real Mode Core Damage Frequency (CDF) Monitoring Note: The Real Mode CDF is based on the unavailability of systems, trains or components that are modeled by the PSA program. Using Safety Monitor in the Real Time mode is dependent on the proper control room log (NOMS) entries. The entries must be made in a specific format for Safety Monitor to recognize them. Additionally, Safety Monitor is set-up to calculate the CDF on a 3-minute cycle. Program ROMAL transfers the narrative log information to Safety Monitor about 45 seconds after a Safety Monitor calculation. The Manual Transfer mode of ROMAL will transfer NOMS data occurring after the Safety Monitor "last configuration" date. The Auto mode of ROMAL will transfer NOMS data occurring after the date of the last ROMAL transfer to Safety Monitor. This is to ensure that the same NOMS data is not re-transferred each time there is no Safety Monitor calculation and therefore no change in the "last configuration" date.
If there is no new data for ROMAL to transfer, a dummy record is transferred to keep Safety Monitor happy.
a) NOMS narrative log entries must contain the following key words to work with Safety Monitor:
Entry Types:
- 1) Asset # Unavailable Enter the reason, choose from:
Routine Maintenance, Component Failure, or Functional Test
- 2) Asset # Available b) Applications
- 1) Asset # Format: NANNANNNN(A)
The (A) alpha at the end as applicable.
Example:
1G33F0004
- 2)
For electrical unavailability below the bus level, please identify the affected component and log in NOMS.
Example: If EF-1-B was unavailable, ECC Pump A (1P42CO001A) would be unavailable. The pump Asset # would have to be logged on NOMS for the Safety Monitor to access the CDF impact.
- 3) Notify the PSA Engineer for the unavailability of:
Containment venting functions Service air or instrument air system unavailability R22 or C22 system components
Safety N1mionlr lDesk (,ui~ld M,
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Ilw hl irt hin t' do is set the S;iletv Nlornita iII lypoihlitical M ode.('l'c on' Vic, a*Nid tha eljc t 11) lyp(tlhctical Mode.,elcIct No initial Icotnfigutlr'ation aIId cl ich )
OK li, teop O y aur ou crcen should have a blue bar which indicates tire sontware \\vCr.islm, c:l.'ulitlamihal mode and user, in this case:
"Safety Monitor 3.0a (ttypothetical (peration) P]lmit P12 R: U1nit 1 : User XXX" You may also start with thie current real mode configuration. To do this, switch back to Real Mode, then Hypothetical Mode to re-answer the question of initial configuration.
(Click View/Change Plant Configuration, then select Component Status. The following screen should appear:
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il rilIt ms im i iirl(l, icit.INv iII the I INI) box i krno\\wii, m! 5,lcct it i1ki)1 trhe diikp kkm\\ii list. t tili l tiii' i(
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'lick oil M %". I ic scIl.cctcd conlponclrt will bc listcd iII the Proposcd cmil,)licnt status clrangcs Hf it is P"SA Ilclitcd then it Will be in Rli I), otherwise it will bc in (iRtIZI' N. This entr)y can be deleted by highlighting and clicking on Delete transaction and clicking on OK.
Multiple components ca-n bec selected for removal. Also, components that have been previously removed from service, as seen in the previous configuration list, can be returned to service by highlighting and clicking on Return to service.
When you are finished modifying component status, click on Close. You will see a summary of changes thus far completed. You may also change plant alignments or put into effect environ/test factors.
To change plant alignment click on Alignment and the following screen appears:
I Ils shows the master list of coumpIlcnts and their current status. (Click onl ti1e Status Irop (10,w11 list M
t C1it mpr lrhlc rtiiilt to t(it','lC the staltus value. Or, to reduce thc size of, ti1 Wit~oiertlitsclcc t
rrirririi syest(-i1i flii(
rw Nm arc firetisired clmihrttr'rr
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lign tmIs*(,I.dd all alig*rnment's ;1'!d K
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'y,'oifiw. hak alid 1 hlilti Ia Proposed alignmtllenit Chlai(nge and cI bliick in!, o) I)elet((e tiisacti sn e I,. lic-
! ()Oil one of thc Add aliirIuiicll ! titoun To put into CA Ccf
-t nvir\\i ictet clik Oil F nviro !i/test and the folloving scrlcci appears:
In a similar fashion as removing components from service, you select an Environ/test factor by highlighting and clicking on Set in effect. Or, highlight previous factors and click (on Set not in effect. ()r the
'Ilcctcd tiansactions can bc removed h% hielthlightini, and pw, An, l)DlOte transaction ( Wk i- ('lose to hi*ish.
Nom, click on ('alculate ti detear)ine the recsulting hypothetical C)F. If'yOU click on (lose beforc ('alcuItte you ILSE1 AI.
changes. Message boxes will pop up indicating fault tree updales, loading data and fault tr-e solutions The home screen will pop up with the ('1)1 i'.iapl and tlcrnotnctcr.
l)ouhlc click the left mouse hutton on the thermometer for current detailed status infortini I)Doublc click the right inomic button on any position on the graph for hi-tolri(.al detailed status inforInmation.
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'1)'llRANJd dte I a, ( o)iffivuriaiion tiii " suih Ii tlmi \\wh('11 P,( )MAi., i iCi5 N( )\\tS iil-% ti oh ciilct i.'
aftcJ I t his d;(IC will he includt-ded
- 5) t Jti-ci;,Change Rcle.al NModc P1aint I fistory Whic'nvcr it hhas been determinei ned tl*at the Safety Monitor historictal p1lant (*tit' Is incomplete, an option exists to update it. 111om the main screen click in Vei*/IChange Operating History and select the time range and click on OK. The following screen will appear:
I li.l g'lit <Ii II t ari d t li( i A o 1 lD c t'I'( to, I'i ll()\\(-: it or do iut I I
li' o,
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- IT I the time. (Click ori Newv to add a (ilpoiltiliK'Iit a1 tiiulialirglntet for I
( lii oil Refresh to sct the ctrricnt statuis ofthe" )luestecd changes.
(lick
()I ( 'alculatc to updatc the history '*1a d recalculate (1)I", and ýis bet>
, it oil click n (los tist yo
\\Uill I.()051 AIJ, chtluim'es I)ceIcting tiltit.'e-s ý the end oftice list will effectively changc the Last Cl ofliu riation ihdate Ihis is use'ul \\w heii it is desired to it:- establlish histo rical]
tLita i1 N( )\\1<"
. thce Nlrijum;l I l*p zitc Ill()(t]( of' R( ),\\IAI.
Appendix C Job Performance Measure Form ES-C-1 Worksheet Facility:
Task
Title:
K/A
Reference:
Perry Comply with Administrative Dose Controls Levels for Assigned Job Task Task No:
JPM No:
299-848-01-01 2002 NRC A3 SRO 2.3.1 NRC Examiner:
N/A Date:
In-Plant Actual Performance Simulator READ TO THE EXAMINEE I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
NUREG 1021, Revision 8, Supplement I Examinee:
Facility Evaluator:
Method of testing Simulated Performance Classroom Plant
Appendix C Job Performance Measure Form ES-C-I Worksheet Initial Conditions:
Task Standard:
Required Materials:
General
References:
Initiating Cue:
Time Critical Task:
Validation Time:
The plant is operating at 100% power. HPCS Alternate Keepfill Startup using P21 is in progress per SOI-E22A, Section 7.8.2. Steps 1 through 5 are completed.
A Perry Plant Operator is required to open HPCS Pump Discharge Line Flush Connection Valve, 1E22-F031 in accordance with Step 6.
The calculated stay time is 30 minutes.
The following Perry Plant Operators, with their current year-to-date exposure history (TEDE), are available:
Bob 930 mrem (TEDE)
Dan 965 mrem (TEDE)
Candidate assigns Perry Plant Operator 'Bob' since he will not exceed his Perry Administrative Dose Control Level of 1000 mrem/year (TEDE) for the job task.
Candidate determines Perry Plant Operator 'Dan' will exceed his Perry Administrative Dose Control Level of 1000 mrem/year (TEDE) for the job task and therefore does not assign him to the job task.
Survey Map (marked up copy)
SOI-E22A, High Pressure Core Spray System Rev 5, PIC 10 HPI-B0003, Processing of Personnel Dosimetry Rev 8, PIC 4 SOI-E22A, High Pressure Core Spray System Rev 5, PIC 10 PNPP Radiation Worker Training Information Manual HPI-B0003, Processing of Personnel Dosimetry Rev 8, PIC 4 Determine which Perry Plant Operator is to be assigned to perform the job task in accordance with Perry Administrative Dose Control Levels.
NO 10 minutes NUREG 1021, Revision 8, Supplement 1
Appendix C Page 3 of 6 Form ES-C-1 PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Note: This JPM should be performed prior to performing In-plant JPM P1 (Commence Alternate Boron Injection).
Note: This JPM can be administered in the plant, the simulator, or the classroom.
Performance Step: 1 Standard:
Comment:
Performance Step: 2 Standard:
Comment:
Performance Step: 3 Standard:
Comment:
Determine the location of HPCS Pump Discharge Line Flush Connection valve, I E22-F03 1.
Determines valve 1 E22-F031 is located at Aux Building 620' D/02.
Note: Candidate is allowed to reference SOI-E22A, VLI-E22A, or any other plant reference that would state the location of the valve.
Locate the correct Survey Map in order to determine the dose rate for the job task.
Locates Survey Map that includes valve IE22-F03 1. (Aux Building, 620', HPCS Valve Room).
Cue: Provide candidate with marked up Survey Map after he either shows or states that the Survey Maps are keep at the RCA entrance.
Determine the hypothetical dose for the job task.
Using Survey Map, determines the dose rate in the vicinity of valve 1E22-F031 is 100 mrem/hour.
Determines the hypothetical dose is 50 mrem.
100 mrem/hour x 0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> = 50 mrem NUREG 1021, Revision 8, Supplement I
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 4 Standard:
Comment:
Determine the hypothetical yearly dose total (TEDE) for each Perry Plant Operator if the job task is performed.
Determines the hypothetical yearly dose total (TEDE) for Perry Plant Operator 'Bob' will be 980 mrem.
'Bob' will not exceed his current Perry Administrative Dose Control Level of 1000 mrem/year.
Determines the hypothetical yearly dose total (TEDE) for Perry Plant Operator 'Dan' will be 1015 mrem.
'Dan' will exceed his current Perry Administrative Dose Control Level of 1000 mrem/year.
Determines "Bob" will be assigned the job task.
'Bob' - 930 mrem (current) + 50 mrem (job) = 980 mrem total.
'Dan' - 965 mrem (current) + 50 mrem (job) = 1015 mrem total.
Terminating Cue:
The evaluation for this JPM is complete when the candidate determines he would assign the job task to Perry Plant Operator 'Bob' because he will not exceed his Perry Administrative Dose Control Level of 1000 mrem/year (TEDE).
NUREG 1021, Revision 8, Supplement 1
Appendix C Page 5 of 6 Form ES-C-1 Question Documentation:
Question:
Response
Result:
SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement 1 Appendix C Page 5 of 6 VERIFICATION OF COMPLETION Job Performance Measure No.
2002 NRC A3 SRO Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
N/A Number of Attempts:
Time to complete:
AlNO 3Sfl O)NINIVUL 80-1 R~P ADIPOLOGICAL SURVEY REPORT I SURVEY No WJ$TRUMENT k0__
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C0(TAMdW1ON REU.1 N.SMEAR BETA ALPHA 4 fac r
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ih 21 22 23 24 27 20 23 Dose Roeeived: ISmRem Dumtln 0 Min
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Appendix C Page 6 of 6 Form ES-C-i JPM CUE SHEET INITIAL CONDITIONS:
INITIATING CUE:
The plant is operating at 100% power. HPCS Alternate Keepfill Startup using P21 is in progress per SOI-E22A, Section 7.8.2. Steps I through 5 are completed.
A Perry Plant Operator is required to open HPCS Pump Discharge Line Flush Connection Valve, 1E22-F031 in accordance with Step 6.
The calculated stay time is 30 minutes.
The following Perry Plant Operators, with their current year-to-date exposure history (TEDE), are available:
Bob 930 mrem (TEDE)
Dan 965 mrem (TEDE)
Determine which Perry Plant Operator is to be assigned to perform the job task in accordance with Perry Administrative Dose Control Levels.
NUREG 1021, Revision 8, Supplement 1
Appendix C Job Performance Measure Form ES-C-I Worksheet Facility:
Task
Title:
K/A
Reference:
Perry Perform Event Classification and Protective Action Recommendations Task No:
JPM No:
344-531-05-02 2002 NRC A4 SRO 2.4.29 NRC Examiner:
N/A Simulated Performance Classroom READ TO THE EXAMINEE Date:
Actual Performance Simulator Plant I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues.
When you complete the task successfully, the objective for this Job Performance Measure will be satisfied.
NUREG 1021, Revision 8, Supplement I Examinee:
Facility Evaluator:
Method of testing Simulator
ANSWER KEY INITIAL NOTIFICATION PNPP No. 7794 Rev. 9/17/01 Page 1 of 2 EPI-B1
- 1. This is the Perry Nuclear Power Plant:
Z Control Room E] Technical Support Center (TSC)
E] Emergency Operations Facility (EOF)
Fi Backup EOF (Communicator. State your NAME and ERO POSITION TITLE.)
- 2. This is a(n):
[] Actual Emergency Z Drill For step 3 below: Use only step 'a' when classifying or reclassifying an event. Use both steps 'a' & 'b' when simultaneously classifying and terminating from an Unusual Event or Alert. Use step 'c' when classifying after a transitory event. Use step 'd' when revising a protective action recommendation.
- 3. a. A (n) Li UNUSUAL EVENT E] ALERT [] SITE AREA EMERGENCY Z GENERAL EMERGENCY has been declared at XX:XX hours on 03 / XX / 02 based on EAL(s): AG1 - Loss of Barriers.
- b. The emergency situation has been terminated at hours on
/
/
(Time)
(Date)
- c. A transitory event has occurred which would have required the declaration of a(n):
E] ALERT F1 SITE AREA EMERGENCY Ri GENERAL EMERGENCY but was mitigated prior to classification. Current event status is at a(n):
L] UNUSUAL EVENT Li ALERT Li SITE AREA EMERGENCY declared at hours on
/
/
based on EAL(s):
(Time)
(Date)
- d. General Emergency protective actions are being changed at hours on
/ I (Time)
(Date)
- 4. Brief non-technical description of event: A Loss of Coolant Accident (LOCA) has occurred. A Loss of Coolant Accident (LOCA) has occurred. RPV water level cannot be maintained above the Top of Active Fuel (TAF).
- 5. Li
- a. NO unplanned radioactive release has occurred.
0
- b. An unplanned radioactive release is in progress.
- 6. Utility recommended protective actions:
Li a. None.
Z
- b. Evacuation of people in Subareas: 1 2
3 4
5 6
7 Lake Erie (circle)
- 7. I repeat, this is a(n):
Li Actual Emergency Z Drill COMMENTS:
Notification is due at:
XX:XX hours on 03/XX/2002; (Time)
(Date)
EMERGENCY COORDINATOR APPROVAL (signature)
ANSWER KEY INITIAL NOTIFICATION PNPP No. 7794 Rev. 9/17/01 Page 2 of 2 EPI-B1 COMMUNICATOR INSTRUCTIONS:
A. Ensure Items 1-7 (page 1) are completed, and Emergency Coordinator has approved release of information.
B. Pickup the "5-Way" Ringdown. As parties answer, perform a roll call to verify that the State and county agencies listed below are on-line; record time contacted below.
If party does NOT answer, initiate a separate call per EPI-BI.
TIME CONTACTED ASHTABULA COUNTY 5-WAY USED?
YES NO EL E]
TIME CONTACTED LAKE COUNTY 5-WAY USED?
YES NO EL 0 GEAUGA COUNTY EL EL STATE OF OHIO 0_ El Read the following: "Please obtain an Initial Notification form to copy this transmission. Communication on the "5-Way" Circuit is being recorded." (Pause 5-10 seconds to allow agencies to obtain form before continuing.) Read the following: "The current date and time is: date I
I time."
C. Transmit data on page 1. When completed, record the name of contact below; request a call back if the 5 Way was NOT used.
NOTE: The following step can be done in parallel with step C. above if additional communicators are available.
D. Once State and county agencies have been contacted, initiate call on NRC ENS Circuit. Read the following:
"The following is a communication from the Perry Nuclear Power Plant. Communication on the ENS Circuit is being recorded."
E. Transmit data on page 1. When completed, record the name of contact below; request a call back if the ENS was NOT used.
TIME NRC CONTACTED:
If the "5-Way" Ringdown or ENS Circuit was NOT used, a verification call back is required.
TIME OF CALLBACK ORGANIZATION PERSON CONTACTED JOB TITLE (If Applicable)
Ashtabula County
[] N/A Geauga County E] N/A Lake County E] N/A State of Ohio N/A Nuclear Regulatory DN/A Commission COMMON OFFSITE ACRONYMS:
SD Sheriff s Department EOC Emergency Operations Center HP Highway Patrol EMA Emergency Management Agency OSHP Ohio State Highway Patrol OEMA Ohio Emergency Management Agency Communicator(s) Name: (1)
(2)
[TSC & EOF ONLY]
Forward a copy of completed form to the Information Liaison and Regulatory Affairs Coordinator.
Appendix C Job Performance Measure Form ES-C-I Worksheet Initial Conditions:
Task Standard:
Required Materials:
You are the on-duty Shift Manager. An event has occurred requiring Emergency Classification.
The following conditions exist:
"* The reactor is shutdown following a LOCA in the Drywell.
"* RPV Emergency Depressurization was performed in accordance with PEI-B 13 when RPV water level decreased to -42.5 inches without injection available.
"* The Severe Accident Guidelines have been entered and Primary Containment Flooding has been initiated due to RPV level remaining lower than -25 inches.
Various Plant Radiation Monitors are alarming and the following readings have been noted:
"* TB/JB Vent Gas Monitor, 1D17-K856, indicates 1.2E+4 cpm and slowly rising.
"* Plant Vent Gas Monitor, 1D19-N300, indicates 3.5E0 ptCi/cc and stable.
Estimated time to complete Emergency Dose calculations is 20 minutes.
Field Survey results are expected in approximately 30 minutes.
The current wind speed is 1.1 MPH coming from 292 degrees.
Within 15 minutes, candidate classifies the event as a General Emergency in accordance with EPI-Al, Emergency Action Levels.
Within the next 15 minutes, PNPP 7794, Initial Notification Form, is correctly prepared in accordance with EPI-B 1, Emergency Notification System, including the correct PAR based on wind direction.
EPI-Al, Rev 6, PIC 6 EPI-B1, Rev 10, PIC 5 EPI-A2, Rev 7, PIC 4 EPI-B8, Rev 8, PIC 4 Initial Notification Form (PNP 7794)
General
References:
EPI-A I, Rev 6, PIC 6 EPI-A2, Rev 7, PIC 4 EPI-BI, Rev 10, PIC 5 EPI-B8, Rev 8, PIC 4 Initiating Cue:
Time Critical Task:
Validation Time:
As the Shift Manager, classify the event in accordance with EPI-AI, Emergency Action Levels, and complete the PNPP Form No. 7794, Initial Notification, in accordance with EPI-B 1, Emergency Notification System.
YES 30 minutes 12 minutes NUREG 1021, Revision 8, Supplement I
Appendix C Page 3 of 6 Form ES-C-I PERFORMANCE INFORMATION (Denote Critical Steps with an asterisk)
Performance Step: 1 Consults EPI-A1 in order to classify the event.
Standard:
Classify as General Emergency within 15 minutes. EAL Category is AG1.
Comment:
NOTE: This step is time critical and must be completed within 15 minutes.
Event classification is expected to be completed within 15 minutes in accordance with EPI-Al such that initial notifications can be completed within the next 15 minutes.
NUREG 1021, Revision 8, Supplement I
Appendix C Page 4 of 6 Form ES-C-1 PERFORMANCE INFORMATION Performance Step: 2 Standard:
Comment:
Obtains Form PNPP No. 7794, Initial Notification, and consults EPI-B 1 in order to fill out the Initial Notification Form.
PNPP No. 7794, Initial Notification, is properly filled out within 15 minutes of classifying the event.
For a General Emergency, ensure that at a minimum the default PAR, as outlined in section 5.1.1.2 of EPI-A2, is included.
Based on wind direction, recommendation should be made to evacuate sub-areas 1, 2, 3.
Note:
This step is time critical and must be completed within 15 minutes from the completion of step 1.
"* See attached copy of completed Form PNPP No. 7794, Initial Notification, in order to verify proper completion of the Initial Notification Form.
"* The candidate must properly complete blocks 1 - 8 of PNPP Form No. 7794.
Note: The candidate should identify where he can obtain PNPP Form No. 7794. When candidate identifies the need for PNPP Form No. 7794, hand the candidate a blank form Note: The candidate is not required to complete any other E-Plan forms such as PNPP Form No. 9100, Pager Messages.
Note: The Evaluator will role-play as the Control Room Communicator by accepting the completed PNPP Form No. 7794 when the candidate is ready for the Control Room Communicator to make the initial notifications to the counties, state, and NRC.
Terminating Cue:
The evaluation for this JPM is complete when the event is classified as a General Emergency in accordance with AGI and PNPP Form No. 7794, Initial Notification is properly filled out (including a Protective Action Recommendation).
NUREG 1021, Revision 8, Supplement I
Appendix C Job Performance Measure No.
Examinee's Name:
Examiner's Name:
Date Performed:
Facility Evaluator:
Number of Attempts:
Time to complete:
Question Documentation:
Question:
Response
Page 5 of 6 Page 5 of 6 VERIFICATION OF COMPLETION 2002 NRC A4 SRO Form ES-C-1 N/A Result:
SAT OR UNSAT Examiner's Signature and Date:
NUREG 1021, Revision 8, Supplement I
Appendix C Page 6 of 6 Form ES-C-1 JPM CUE SHEET INITIAL CONDITIONS:
INITIATING CUE:
You are the on-duty Shift Manager. An event has occurred requiring Emergency Classification.
The following conditions exist:
"* The reactor is shutdown following a LOCA in the Drywell.
"* RPV Emergency Depressurization was performed in accordance with PEI-B 13 when RPV water level decreased to -42.5 inches without injection available.
"* The Severe Accident Guidelines have been entered, and Primary Containment Flooding has been initiated due to RPV level remaining lower than -25 inches.
Various Plant Radiation Monitors are alarming and the following readings have been noted:
"* TB/HB Vent Gas Monitor, 1D17-K856, indicate 1.2E+4 cpm and slowly rising.
"* Plant Vent Gas Monitor, 1D19-N300, indicates 3.5E0 ttCi/cc and stable.
Estimated time to complete Emergency Dose calculations is 20 minutes.
Field Survey results are expected in approximately 30 minutes.
The current wind speed is 1.1 MPH coming from 292 degrees.
As the Shift Manager, classify the event in accordance with EPI-Al, Emergency Action Levels, and complete the PNPP Form No. 7794, Initial Notification, in accordance with EPI-B 1, Emergency Notification System.
NUREG 1021, Revision 8, Supplement 1
INITIAL NOTIFICATION PNPP No. 7794 Rev. 9/17/01 Page 1 of 2 EPI-B1
- 1. This is the Perry Nuclear Power Plant:
D] Control Room E] Technical Support Center (TSC)
Ej Emergency Operations Facility (EOF)
F-1 Backup EOF (Communicator. State your NAME and ERO POSITION TITLE.)
- 2. This is a(n):
[] Actual Emergency R Drill For step 3 below: Use only step 'a' when classifying or reclassifying an event. Use both steps 'a' & 'b' when simultaneously classifying and terminating from an Unusual Event or Alert. Use step 'c' when classifying after a transitory event. Use step 'd' when revising a protective action recommendation.
- 3. a. A (n) R] UNUSUAL EVENT E] ALERT [] SITE AREA EMERGENCY R] GENERAL EMERGENCY has been declared at hours on I I based on EAL(s):
- b. The emergency situation has been terminated at hours on I
/
(Time)
(Date)
- c. A transitory event has occurred which would have required the declaration of a(n):
F] ALERT R] SITE AREA EMERGENCY F1 GENERAL EMERGENCY but was mitigated prior to classification. Current event status is at a(n):
Ri UNUSUAL EVENT Ri ALERT F] SITE AREA EMERGENCY declared at hours on
/
/
based on EAL(s):
(Time)
(Date)
- d. General Emergency protective actions are being changed at hours on I I (Time)
(Date)
- 4. Brief non-technical description of event:
- 5. fi a. NO unplanned radioactive release has occurred.
fi b. An unplanned radioactive release is in progress.
- 6. Utility recommended protective actions:
- a. None.
[] b. Evacuation of people in Subareas: 1 2
3 4
5 6
7 Lake Erie (circle)
- 7. I repeat, this is a(n):
fi Actual Emergency fi Drill COMMENTS:
Notification is due at:
hours on I
/
(Time)
(Date)
EMERGENCY COORDINATOR APPROVAL (signature)
INITIAL NOTIFICATION PNPP No. 7794 Rev. 9/17/01 Page 2 of 2 EPI-B1 COMMUNICATOR INSTRUCTIONS:
A. Ensure Items 1-7 (page 1) are completed, and Emergency Coordinator has approved release of information.
B. Pickup the "5-Way" Ringdown. As parties answer, perform a roll call to verify that the State and county agencies listed below are on-line; record time contacted below. If party does NOT answer, initiate a separate call per EPI-B1.
5-WAY USED?
TIME CONTACTED YES NO ASHTABULA COUNTY E_
El GEAUGA COUNTY EK K]
5-WAY USED?
TIME CONTACTED YES NO LAKE COUNTY K]
STATE OF OHIO El El Read the following: "Please obtain an Initial Notification form to copy this transmission. Communication on the "5-Way" Circuit is being recorded." (Pause 5-10 seconds to allow agencies to obtain form before continuing.) Read the following: "The current date and time is: date I
I time."
C. Transmit data on page 1. When completed, record the name of contact below; request a call back if the 5 Way was NOT used.
NOTE: The following step can be done in parallel with step C. above if additional communicators are available.
D. Once State and county agencies have been contacted, initiate call on NRC ENS Circuit. Read the following:
"The following is a communication from the Perry Nuclear Power Plant. Communication on the ENS Circuit is being recorded."
E. Transmit data on page 1. When completed, record the name of contact below; request a call back if the ENS was NOT used.
TIME NRC CONTACTED:
If the "5-Way" Ringdown or ENS Circuit was NOT used, a verification call back is required.
TIME OF CALLBACK ORGANIZATION PERSON CONTACTED JOB TITLE (If Applicable)
Ashtabula County DN/A Geauga County DN/A Lake County Ej N/A State of Ohio
[] N/A Nuclear Regulatory FI N/A Commission COMMON OFFSITE ACRONYMS:
SD Sheriff's Department EOC Emergency Operations Center HP Highway Patrol EMA Emergency Management Agency OSHP Ohio State Highway Patrol OEMA Ohio Emergency Management Agency Communicator(s) Name: (1)
(2)
[TSC & EOF ONLY]
Forward a copy of completed form to the Information Liaison and Regulatory Affairs Coordinator.