ML090780277
| ML090780277 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/21/2008 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| Download: ML090780277 (182) | |
Text
FLORIDA POWER & LIGHT DRAFT NRC Admin. Exam ST LUCIE NRC LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM A1 ADM Determine Fuel Preconditioning Guidelines and Classification of Reactivity Event CANDIDATE EXAMINER ST LUCIE JPM A 1 Page 10f4
FLORIDA POWER & LIGHT NRC Admin. Exam Determine Fuel Preconditioning Guidelines and Classification of Reactivity Event Examinee:
SAFETY FUNCTION ADMIN. TOPIC TESTING KIA #
ENVIRONMENT NONE Conduct of Classroom / Simulator 2.1.37 (4.6)
Operations POSITION FAULTED VALIDATED TIME TIME CRITICAL (YIN)
(YIN)
SRO N
10 N
STANDARD:
Determine Fuel Pre-conditioning guidelines exceeded and event considered a Noteworthy Reactivity event.
REFERENCES:
1-GOP-101 Reactor Operating Guidelines during Steady State and Scheduled Load Changes NAP-402 Conduct of Operations Attachment E INITIATING CUE:
Unit 1 has been at 45% power for 3 days after a refueling outage. The up power was taken off hold and direction was given to increase power to 100%. The RO programmed the DEH for a 2.4 MW/e up power and depressed the GO button. Determine if this up power rate meets the fuel preconditioning guidelines and reactivity management controls.
START TIME END TIME DURATION (minutes)
OPERATOR PERFORMANCE AS EVALUATED TO STANDARD (circle one)
SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________
DATE:
EXAMINER (print):
FLORIDA POWER & LIGHT NRC Admin. Exam
- indicates a "critical" step STEP STANDARD Stu
- 1.
Refer to 1-GOP-1 01 Reactor Operating Determines correct category 0.42 Guidelines during Steady State and MW/MIN Scheduled Load Changes. Appendix B may Current load rate of 2.4 MW/MIN be used to determine guideline.
exceeds preconditioning guidelines.
- 2.
Refers to NAP-402 Conduct of Operations Determines event classified as Attachment E.
'Noteworthy Reactivity Event' END TIME:
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE:
Unit 1 has been at 45% power for 3 days after a refueling outage. The up power was taken off hold and direction was given to increase to 100% power. The RO programmed the DEH for a 2.4 MW/e up power and depressed the GO button.
Determine if this up power rate meets the fuel preconditioning guidelines and reactivity management controls.
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Title:
ST. LUCIE UNIT 1 GENERAL OPERATING PROCEDURE SAFETY RELATED REFERENCE USE Procedure No.
1-GOP-101 Current Revision No.
4 Effective Date 03/22/06 REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES Responsible Department: OPERATIONS REVISION
SUMMARY
Revision 4 - Incorporated PCR 06-0761 to remove references to Appendix C, as it applied to Cycle 16 core only, remove references to Tavg program, and provide direction for maintaining 100% power to insure license power level is not exceeded. (David Beakes, 03/01/06)
AND Incorporated PCR 05-3006 for CR 2005-18614 to add Level of Use to procedure cover page.
(Helga Baranowsky, 10/07/05)
Revision 3 - Incorporated PCR 05-0114 to changed power level and escalation rate based on self assessment against vendor documents. (Ray M. Klein, 01/31/05)
Revision 2 - Incorporated PCR 04-1499 to change reactivity note. (Jeff Folden, 05/03/04)
Revision 1A - Incorporated PCR 03-2864 for PCM 03068 to revise DDPS references to address the DCS. (John Rush, 12/17/03)
Revision 1 - Incorporated PCR 04-0122 to add precaution about potential reactivity effects in procedure. (J, McKenzie, 01/29/04)
Revision 0 - Changed NOP-1-0030123 into this procedure. (E. F. Cone, 08/20/02)
Revision FRG Review Date Approved By Approval Date S_1_0PS 0
08/14/02 D. Rose 08/20102 DATE Plant General Manager DOCT Revision FRG Review Date Approved By Approval Date DOCN 4
N/A SYS Plant General Manager COM David K. Albritton 03/01/06 ITM Authorized Approver N/A Authorized Approver Minor Co
REVISION NO.:
4 PROCEDURE NO.:
1-GOP-101 SECTION PROCEDURE TITLE:
REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 TABLE OF CONTENTS PAGE:
2 of 16 PAGE 1.0 PURPOSE............................................................................................................. 3
2.0 REFERENCES
...................................................................................................... 3 3.0 PREREQUISITES................................................................................................. 4 4.0 PRECAUTIONS / LIMITATIONS...........................................................................4 5.0 RECORDS REQUIRED........................................................................................ 5 6.0 INSTRUCTIONS................................................................................................... 6 6.1 Power Level Escalations............................................................................ 6 6.2 Power Level Reductions............................................................................. 9 6.3 Maintaining Steady State Power Level..................................................... 1 0 7.0 INFREQUENT OPERATIONS............................................................................ 12 APPENDIXES APPENDIX A PRESSURIZER RECIRCULATION GUIDELINES................................ 13 APPENDIX B FUEL PRECONDITIONING GUIDELINES WORKSHEET.................... 15
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 PROCEDURE NO.:
1-GOP-101 1.0 PURPOSE REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 3 of 16 1.1 To maintain power escalation rates below the limits specified in the fuel vendors preconditioning guidelines in order to maximize fuel rod integrity.
1.2 To provide guidance for plant load changes and steady state operations.
1.3 To provide instructions for placing the Pressurizer on recirculation to equalize boron concentration with the RCS.
2.0 REFERENCES
NOTE One or more of the following symbols may be used in this procedure:
§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without the required Focus review and appropriate approval.
,-r Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.
'P Indicates a step that requires a sign off on an attachment.
2.1
§1 St. Lucie Unit 1 Technical Specifications 2.2
§2 St. Lucie Unit 1 FUSAR Section 7.7.1.1.2 2.3
,-r1 Preconditioning and Maneuvering Criteria for Exxon Nuclear Fuel (PREMACX), XN-NF-1068(P) 2.4 NOP-100.02, Axial Shape Index Control 2.5 1-GOP-201, Reactor Plant Startup - Mode 2 to Mode 1 2.6 1-GOP-123, Turbine Shutdown - Full to Zero Load 2.7 1-NOP-02.24, Boron Concentration Control 2.8 1-NOP-01.11, RCS Cleanup 2.9 JPN Evaluation, Power Ramp Rates following Refueling Outages for PSL 1/2, JPN-PSL-SEFJ-94-024 2.10
§3 FPL Letter L-96-93, Reply to Notice of Violation EA 96-040 2.11 Self Assessment Nuclear Fuels, Evaluation of Power Ramp Rate NFSA-061 Rev. 0
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 PROCEDURE NO.:
1-GOP-101 REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 3.0 PREREQUISITES 4 of 16 3.1 Plant is at Power Operation (Mode 1), except for performance of Appendix A, Pressurizer Recirculation Guidelines, which may be performed in any Mode if there is a bubble established in the Pressurizer.
4.0 PRECAUTIONS I LIMITATIONS 4.1 At or above 50% power, boration/dilution should be the primary means to compensate for changes in power level and transient xenon. This subjects the majority of the fuel rods to uniform and smooth power transients.
4.2 During steady state base load operations, the CEA Mode Selector switch should be maintained in OFF.
4.3 Continuous (in excess of 10 inches) regulating group withdrawals or insertions are undesirable. CEA motion should be in small increments, primarily in response to deviations of ASI from ESI.
4.4 ASI control bands about the ESI: (ASI values are in RPS units)
- 1.
Steady State Band:
ESI plus or minus 0.5 during steady state base load operation
- 2.
Transient Band:
A.
ESI plus or minus 0.2 during load transients.
B.
ASI control to plus or minus 0.1 is recommended whenever practical.
- 3.
Refer to NOP-100.02, Axial Shape Index Control, for specific guidance.
4.5 Pressurizer boron concentration should be maintained within 25 ppm of RCS boron concentration.
4.6
§1 RCS T-cold shall be maintained less than or equal to 549°F, refer to Technical Specification 3.2.5.
4.7 With the Reactor critical, the RCS T-avg should be maintained greater than 525°F.
- 1.
lfT-avg decreases below 525°F, Then at least once per 30 minutes verify RCS T-avg greater than or equal to 515°F.
- 2.
§1 If T-avg decreases below 515°F, Then restore T-avg to greater than or equal to 515°F within 15 minutes or be in Hot Standby within the next 15 minutes. Refer to Technical Specification 3.1.1.5.
REVISION NO.:
4 PROCEDURE NO.:
1-GOP-101 PROCEDURE TITLE:
REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 PAGE:
5 of 16 4.8 When placing the main turbine into service following a refueling outage and the magnitude of the moderator temperature coefficient of reactivity is small (in the range of +1 to -1 pcmrF), additional rod motion may be required to maintain RCS temperature immediately following closing of the generator output breaker.
4.9 Performance of this procedure WILL affect core reactivity. ENSURE all evolutions are properly briefed regarding Reactivity Management, including discussions on expected parameter changes and operational contingencies to minimize reactivity management challenges.
5.0 RECORDS REQUIRED 5.1 Normal log entries.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 6 of 16 PROCEDURE NO.:
1-GOP-101 REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 6.0 INSTRUCTIONS 6.1 Power Level Escalations NOTE CEAs should be above the Long-term Steady State Insertion Limit (102 inches withdrawn on Group 7) before reaching 20% core power and at a position to begin controlling ASI as the ESI between 20% and 50% power.
Refer to NOP-1 00.01, Axial Shape Index Control, for further guidance.
- 1.
As Main Generator loading commences, MAINTAIN T-avg at T-ref by:
A.
CEA withdrawal in Manual Sequential.
AND/OR B.
Boron concentration changes in accordance with 1-NOP-02.24, Boron Concentration Control.
- 2.
At or above 50% power:
A.
All planned reactivity additions should be made by boration or dilution in accordance with 1-NOP-02.24, Boron Concentration Control.
B.
Use CEAs for ASI control, consider the reactivity effect of CEAs when adjusting ASI.
C.
Refer to NOP-100.02, Axial Shape Index Control, for specific instructions regarding ASI control during power escalations.
D.
111 When raising reactor power, all power escalation rates should be within the following fuel preconditioning guidelines:
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 REACTOR OPERATING GUIDELINES DURING 7 of 16 PROCEDURE NO.:
STEADY STATE AND SCHEDULED LOAD CHANGES 1-GOP-101 ST. LUCIE UNIT 1 6.1 Power Level Escalations (continued)
- 2.
(continued)
NOTE When placing the main turbine on-line following a refueling outage or an extended shutdown and the fuel preconditioning guidelines place the unit in a Category 1 status, power escalation requirements are not applicable until the generator output breaker has been closed and the unit synchronized to the grid. As soon as load has been picked up and the generator is stable at or above 15% power, the ramp rate requirements of the table are to be applied.
Category Max Core Power Escalation Rate Max Equivalent Turbine Generator Load Rate 1
3% I HR at or above 15% Power
.42 MW/MIN 2
3% I HR above 53% Power
.42 MW/MIN 3
8% I HR above 53% Power 1.12 MW/MIN 4
30% I HR above 53% Power 4.2 MW/MIN NOTE To determine the correct category for a power escalation, Appendix 8, Fuel Preconditioning Guidelines Worksheet, may be used. Reactor Engineering can be contacted if further assistance is required.
- 3.
Category Definitions A.
Category 1:
Increase in power to a level which has not been previously sustained in this core cycle for at least 72 continuous hours.
B.
Category 2:
- 1.
Increase in power following 30 continuous days or more at a power level less than 70% of rated thermal power. The above turbine load rate should be applied to start at current power level.
- 2.
Increase in power to a level which has not been maintained for a total of 3 continuous days or more during the past 30 days.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 REACTOR OPERATING GUIDELINES DURING 8 of 16 PROCEDURE NO.:
STEADY STATE AND SCHEDULED LOAD CHANGES 1-GOP-101 ST. LUCIE UNIT 1 6.1 Power Level Escalations (continued)
- 3.
(continued)
C.
Category 3:
Increase in power to a level which has been maintained for a total of 3 continuous days or more during the past 30 days.
D.
Category 4:
Increase in power to a level which has been maintained for 3 continuous days or more during the previous 6 days.
- 4.
1f available, Then ENSURE two Charging Pumps are operating. If necessary, start an additional Charging Pump in accordance with 1-NOP-02.02, Charging and Letdown.
- 5.
PLACE the Pressurizer on recirculation in accordance with Appendix A, Pressurizer Recirculation Guidelines.
- 6.
CONTINUE to load the Main Generator in accordance with 1-GOP-201, Reactor Plant Startup - Mode 2 to Mode 1.
END OF SECTION 6.1
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 REACTOR OPERATING GUIDELINES DURING 9 of 16 PROCEDURE NO.:
STEADY STATE AND SCHEDULED LOAD CHANGES 1-GOP-101 ST. LUCIE UNIT 1 6.2 Power Level Reductions
- 1.
At or above 50% power:
A.
All planned reactivity additions should be made by boration or dilution in accordance with 1-NOP-02.24, Boron Concentration Control.
B.
Use CEAs for ASI control, consider the reactivity effect of CEAs when adjusting boron concentration.
C.
Refer to NOP-1 00.02, Axial Shape Index Control, for specific instructions regarding ASI control during planned or unplanned load reductions.
- 2.
1f available, Then ENSURE two Charging Pumps are operating. If necessary, start an additional Charging Pump in accordance with 1-NOP-02.02, Charging and Letdown.
- 3.
PLACE the Pressurizer on recirculation in accordance with Appendix A, Pressurizer Recirculation Guidelines.
- 4.
UNLOAD the Main Generator in accordance with 1-GOP-123, Turbine Shutdown - Full to Zero Load.
END OF SECTION 6.2
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 10 of 16 PROCEDURE NO.:
1-GOP-101 REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 6.3 Maintaining Steady State Power Level
- 1.
ASI Control A.
MAINTAIN ASI during steady state in accordance with NOP-100.02, Axial Shape Index Control.
CAUTION RCS T-cold shall be maintained less than or equal to 549°F.
- 2.
MAINTAIN the unit at steady state power as follows:
A.
MAINTAIN RCS temperature on program:
NOTE During end of Cycle Coastdown, Tcold is expected to deviate from program Tcold, and Tavg may deviate from Tref by as many as several degrees F.
During the performance of OP-011 0058, Coastdown Methods for Use at End of Cycle, Annunciator K-19, Reactor T-avglT-ref Temp Low, may be in alarm.
Consult Reactor Engineering for expected RCS temperature values.
- 1.
§3 100% power Tc should be maintained between 548.4 to
- 2.
548.6°F. At 548.8°F take corrective action to maintain Tc less than 549.0°F.
When less than 100% power maintain T-cold on program:
(% power x 16.5°F) + 532°F = program T-cold.
B.
Compensatory reactivity additions (for example, xenon transients or fuel depletion) should be made by boration or dilution in accordance with 1-NOP-02.24, Boron Concentration Control.
C.
1f necessary, Then ADJUST Main Generator load to maintain steady state conditions in accordance with 1-GOP-201, Reactor Plant Startup - Mode 2 to Mode 1, or 1-GOP-123, Turbine Shutdown - Full to Zero Load.
D.
Maintain steady state power between 99.92% and 99.97%.
Refer to Ops Policy 503, Technical Specification Guidance.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 PROCEDURE NO.:
1-GOP-101 REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 6.3 Maintaining Steady State Power Level (continued) 11 of 16
- 3.
if Chemistry analysis shows a significant (greater than or equal to 25 ppm) difference between RCS and Pressurizer boron concentration, Then PLACE the Pressurizer on recirculation in accordance with Appendix A, Pressurizer Recirculation Guidelines.
- 4.
When Chemistry results show that Pressurizer and RCS boron concentration are sufficiently equalized (within 25 ppm), Then the pressurizer may be taken off recirculation in accordance with Appendix A, Pressurizer Recirculation Guidelines.
NOTE 1-NOP-01.11, RCS Cleanup, contains actions which may be initiated /
performed as early as 7 days prior to unit shutdown.
- 5.
if the unit is to be shutdown and additional RCS cleanup is desired, Then IMPLEMENT 1-NOP-01.11, RCS Cleanup.
END OF SECTION 6.3
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 REACTOR OPERATING GUIDELINES DURING 12 of 16 PROCEDURE NO.:
STEADY STATE AND SCHEDULED LOAD CHANGES 1-GOP-101 ST. LUCIE UNIT 1 7.0 INFREQUENT OPERATIONS None END OF SECTION 7.0
REVISION NO.:
4 PROCEDURE NO.:
1-GOP-101 PROCEDURE TITLE:
REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 APPENDIX A PRESSURIZER RECIRCULATION GUIDELINES (Page 1 of 2)
NOTE PAGE:
13 of 16 The purpose of placing the Pressurizer on recirculation is to keep the Pressurizer and RCS boron concentration within 25 ppm when changing RCS boron concentration.
From measured data, the estimated time in minutes to correct a greater than or equal to 25 ppm boron mismatch by operating 6 Backup Heater Banks may be determined as follows:
Time (in min.) to correct mismatch = [(pzr ppm - RCS ppm) - 25 ppm] x 3
- 1.
To place the Pressurizer on recirculation:
A.
PLACE all available Backup Heater Bank (B-1 through B-6) control switches to ON.
B.
Slowly REDUCE the AUTO setpoint on PIC-1100X or PIC-1100Y, the selected "Pressurizer Pressure Control Channel," to maintain normal operating pressure.
C.
OBSERVE HIC-1100, Pzr Pressure Spray Cntl Vlv, output and PCV - 11 OOE/11 OOF, Pressurizer spray Valve 1 B2/1 B1, position indication to verify Main Spray flow.
REVISION NO.:
4 PROCEDURE NO.:
1-GOP-101 PROCEDURE TITLE:
REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 APPENDIX A PRESSURIZER RECIRCULATION GUIDELINES (Page 2 of 2)
NOTE Normally, the required number of Backup Heater Banks in service is dependent upon:
PAGE:
14 of 16
- 1. The magnitude of thermal losses from the system, including leakage to the Quench Tank.
- 2. The number of heater elements out of service.
The normal configuration is to have enough Backup Heater Banks in service to keep the Proportional Heater Banks at approximately 50%
output.
- 2.
To take the Pressurizer off recirculation:
A.
REMOVE the additional Backup Heater Banks from service one at a time by returning the control switch to AUTO.
B.
ADJUST the AUTO setpoint on PIC-1100X or PIC-1100Y, the selected "Pressurizer Pressure Control Channel," to maintain normal operating pressure.
C.
OBSERVE HIC-1100, Pzr Pressure Spray Cntl Vlv, output and PCV-1100E/1100F, Pressurizer Spray Valve 1 B2/1 B1, position indication to ensure:
- 1.
Main Spray flow has stopped.
AND
- 2.
Proportional Heater banks are at approximately 50% output.
END OF APPENDIX A
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 PROCEDURE NO.:
1-GOP-101 REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1 APPENDIX B FUEL PRECONDITIONING GUIDELINES WORKSHEET (Page 1 of 2)
NOTE This worksheet is intended to assist the operating crew in defining the power escalation rate limits for fuel preconditioning guidelines. Contact Reactor Engineering for assistance, if required.
- 1.
Power history determination.
A.
DETERMINE the maximum power level sustained for 3 15 of 16 INITIAL continuous days or more during the last 6 days and enter here:
(1 ) __ _
B.
DETERMINE the maximum power level sustained for 3 continuous days or more within the last 30 days and enter here:
(2) __ _
C.
Has the plant been at less than 70% power for 30 continuous days or more?
D.
E.
- 1.
If YES, enter the power level here: __ _
- 2.
If NO, enter 100% here: __ _
- 3.
Enter the power level from C.1 or C.2 here: __ _
ENTER the lesser value of (2) or C.3 here:
DETERMINE the maximum power level sustained for 72 continuous hours or more by this core since BOC and enter here:
(3) __
(4) __
REVISION NO.:
PROCEDURE TITLE:
PAGE:
4 16 of 16 PROCEDURE NO.:
REACTOR OPERATING GUIDELINES DURING STEADY STATE AND SCHEDULED LOAD CHANGES ST. LUCIE UNIT 1
- 2.
1-GOP-101 APPENDIX B FUEL PRECONDITIONING GUIDELINES WORKSHEET (Page 2 of 2)
NOTE INITIAL The result of this worksheet will yield the limiting category and the associated power it is in effect. Always use the most limiting category when two or more categories apply.
Limiting power Escalation rate determination.
A.
Fuel is Category 1 when greater than: [enter (4) or 15%
whichever is greater]
B.
Fuel is Category 2 when greater than: [enter (3) or 53%
whichever is greater]
C.
Fuel is Category 3 when greater than: [enter (1) or 53%
whichever is greater]
D.
Fuel is Category 4:
- 1.
From 53% to 100% power, if 2.A, Band C are ill! 100%
- 2.
From 53% power to the lesser of 2.A, B or C.
END OF APPENDIX B
"ROCEDURE NO.:
PROCEDURE TITLE:
PAGE:
NAP-402 59 of 135 CONDUCT OF OPERATIONS
~EVISION NO.:
r-____
5 ____ ~
____________________________ ~
_______ 11 ATTACHMENT E REACTIVITY MANAGEMENT CONTROLS (Page 1 of 29) 1.0 PURPOSE 1.1 This procedure defines the philosophy, responsibilities, and requirements necessary to implement reactivity management consistent with nuclear safety goals. This procedure establishes a conservative philosophy of operations such that reactivity of nuclear fuel is always controlled. It ensures safe, conservative operation so that the health and safety of the general public is protected.
1.2 Reactivity management is vital to nuclear safety since it is a key factor in ensuring safe maintenance of barriers to fission product release. Reactivity management provides that all plant evolutions affecting reactivity will be controlled and, in the case of core reactivity manipulations, adequate shutdown margin will be maintained.
1.3 This procedure is applicable to all personnel involved with the operation, maintenance, testing and modification of plant systems and components that control, monitor, or otherwise affect the reactivity of the nuclear fuel in the core or in storage. This includes those personnel having direct responsibility for equipment or systems, procedures, programs or processes, or training programs that have a potential to affect reactivity or the control of reactivity.
2.0 TERM AND DEFINITIONS 2.1 Reactivity A measure of the fractional change in neutron population per generation.
A measure of how quickly the number of neutrons in the core or spent fuel pool is changing.
This directly impacts the amount of power being generated by the reactor or heat by the spent fuel pool.
2.2 Reactivity Management Plant procedures for Operations require that reactivity is changed only in a deliberate, carefully controlled manner while nuclear instrumentation and redundant indications of reactor power and neutron flux are constantly monitored.
Because of the significant potential adverse consequences of an unantiCipated reactivity event, activities not associated with the reactivity change are intentionally limited and controlled to minimize distractions to the individuals involved in the reactivity change.
ROCEDURE NO.:
PROCEDURE TITLE:
PAGE:
63 of 135 NAP-402 CONDUCT OF OPERATIONS REVISION NO.:
~
5 ____ ~
____________________________ ~
_______ 11 ATTACHMENT E REACTIVITY MANAGEMENT CONTROLS (Page 5 of 29)
B. Noteworthy Reactivity Event A noteworthy reactivity event is an unexpected or unplanned event not in accordance with procedures, plans, or work documents which degrade the ability to control or monitor reactivity, or any unexpected change in reactivity I reactor power as described below. A noteworthy reactivity event should include those reactivity control related events that involve moderate challenges to reactivity management. Examples include:
Inaccuracy in procedures or instructions which causes improper control of reactivity Inadequate verification of data or information used to control reactivity that causes improper control of reactivity Errors in calculations which invalidate reactivity related surveillance tests Improper bypass of reactivity control systems which result in improper control of reactivity Mislocated fuel assemblies in the core corrected prior to reactor operations Transmittal of erroneous core physics predictions by engineering groups which is implemented or invalidates a test or calculation Non-conservative calibration of safety system instrumentation not corrected within tech spec requirements Errors in engineering analysis which result in operation with non-conservative operating limits Actual failure to meet acceptance criteria of any reactivity related physics test Criticality outside ecc bounds by > 0.5%delta k/k (500pcm)
Reactor critical below the rod insertion limits or not critical at the all rods out point during a reactor startup Primary or secondary system effects causing unplanned power changes in excess of.5% rtp or a tavg change of> 3 degrees.
Violation of rod sequencing pattern Any ni or safety system instrumentation monitoring or control instrumentation malfunction not resulting in a reactor trip Any reactivity calculation errors detected after the calculation is reviewed and approved resulting in > 0.05% delta k/k (50 pcm)
Tech Spec limits corrected within Tech Spec time requirements for TAVG,
"ROCEDURE NO.:
PROCEDURE TITLE:
PAGE:
NAP-402 64 of 135 CONDUCT OF OPERATIONS REVISION NO.:
r-____
5 ___________________________________________ 1 ATTACHMENT E REACTIVITY MANAGEMENT CONTROLS (Page 6 of 29)
Operation in excess of 101% RTP but less than 102% RTP Improper movement of a fuel insert during fuel handing Misplaced fuel assembly in the spent fuel pool not found until spent fuel pool verification Unexplainable reactivity changes Improperly performed or inadequate maintenance which causes a change in reactor power of 0.5% of rated power or more o
Exceeding site guidelines for preconditioning fuel Unanticipated operations within 1 % of raoc limits.
C. Reactivity Event A reactivity event may result in an impact on reactivity. A reactivity event should include those reactivity control related events, which by themselves represent minor challenges to reactivity management.
Examples include:
mispositioned control rods restored within procedural requirements Operations in excess of 100.5% RTP but less than 101% RTP.
Critical prediction or target rod pattern that differs from the measured state point by a predetermined acceptance criteria Inaccuracy in approved maneuvering instructions or procedures relative to the control of reactivity Improper calibration or bypass of safety system instrumentation or other reactivity control systems corrected in accordance with Tech Specs Primary or secondary system effects causing unplanned power changes in excess of 0.25% RTP or a T AVG change of> 1 degree.
Transmittal of erroneous rod pattern or core physics data by engineering groups which is not used, but could invalidate a test or calculation Heat balance discrepancy Unisolable steam leak Loss of control rod indication while reactor is critical Demineralizer placed in service when not in equilibrium
FLORIDA POWER & LIGHT NRC Admin. Exam ST LUCIE NRC LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPM A2ADM Determine QSPDS Values With Plasma Display Out of Service CANDIDATE EXAMINER ST LUCIE JPM A2 Page 1 of4
FLORIDA POWER & LIGHT NRC Admin. Exam Determine QSPDS Values With Plasma Display Out of Service Examinee:
SAFETY FUNCTION ADMIN. TOPIC TESTING KIA #
ENVIRONMENT NONE Conduct of Classroom 1 Simulator 2.1.25 (3.9/4.2)
Operations POSITION FAULTED VALIDATED TIME TIME CRITICAL (YIN)
(YIN)
RO/SRO N
10 N
STANDARD:
REFERENCES:
2-1150020 Qualified Safety Parameter Display System Operation 2-0SP-1 00.17 Accident Monitoring Instrumentation Monthly Channel Check INITIATING CUE:
Unit 2 QSPDS Plasma Display Channel A is out of service. The shift is completing 2-0SP-100.17 Accident Monitoring Instrumentation Monthly Channel Check with Channel A QSPS Plasma Display out of service.
The Shift Manager has directed you to determine the below parameters using the QSPDS Conversion Data Sheet #1 for Top Chassis Channel A.
2A Hot Leg Counts 3197 2B Hot Leg Counts 3189 2A2 Cold Leg Counts 2918 2B1 Cold Leg Counts 2919 Pzr. Press.
Counts 3077 RCS Subcooling START TIME END TIME DURATION (minutes)
OPERATOR PERFORMANCE AS EVALUATED TO STANDARD (circle one)
SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________
DATE:
EXAMINER (print):
FLORIDA POWER & LIGHT NRC Admin. Exam
- indicates a "critical" step STEP STANDARD S/U
- 1.
2A Hot Leg 596°F (+/- O.5OF)
- 2.
2B Hot Leg 594.7oF (+/- O.5OF)
- 3.
2A2 Cold Leg 548.50F (+/- O.50F)
- 4.
2B1 Cold Leg 548.50F (+/- O.5OF)
- 5.
PZR. Press.
2252 psi a (+/- 2psia)
- 6.
RCS Subcooling 56.8°F (+/- 2°F)
END TIME:
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE:
Unit 2 aSPDS Plasma Display Channel A is out of service. The shift is completing 2-0SP-100.17 Accident Monitoring Instrumentation Monthly Channel Check with Channel A asps Plasma Display out of service.
The Shift Manager has directed you to determine the below parameters using the aSPDS Conversion Data Sheet #1 for Top Chassis Channel A.
2A Hot Leg Counts 3197 28 Hot Leg Counts 3189 2A2 Cold Leg Counts 2918 281 Cold Leg Counts 2919 Pzr. Press.
Counts 3077 2A Hot Leg 28 Hot Leg 2A2 Cold Leg 281 Cold Leg PZR. Press RCS Subcooling ST LUCIE JPM A2 Page 4 of4
Title:
ST. LUCIE UNIT 2 OPERATING PROCEDURE SAFETY RELATED INFORMATION USE QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION Responsible Department: OPERATIONS REVISION
SUMMARY
Revision 13C - Incorporated MC 07-2105 to enhance procedural steps to make both units match in Appendix B. (Clyde Price, 06/11/07)
Revision 138 - Incorporated MC 07-0694 to correct typo's and to enhance and move Note to proper location in Appendix B. (Clyde Price, 02/26/07)
Revision 13A - Incorporated PCR 06-4287 to delete reference to Data Sheet 1 of 2-0SP-100.17 and add reference to 2-0SP-100.17 in reference section.
(David Beakes, 12/01/06)
Revision 13 - Incorporated PCR 06-2248 to change the conversion method to make it readily apparent as how to use it. (Spencer Patterson, 08/29/06)
Revision 12C - Incorporated PCR 06-2168 to update procedure numbers based on procedure upgrade project. (Joe Hessling, 06/27/06)
Revision 128 - Incorporated PCR 06-1490 to make editorial changes and add a line on Data Sheet 10. (Joe Hessling, 05/02/06)
Revision 12A - Incorporated PCR 04-2534 to correct test number and add a line to record data. (Joe Hessling, 08/05/04)
Revision FRG Review Date Approved By Approval Date SLOPS 0
08/06/84 D. A. Sager 08/06/84 DATE Plant General DOCT Revision FRG Review Date Approved By Approval Date DOCN 13C N/A SYS Plant General Manager COM R. Weller 08/29/06 ITM Authorized Approver Mike Bladek 06/11/07
NO.:
13C PROCEDURE NO.:
2-1150020 SECTION PROCEDURE TITLE:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2 TABLE OF CONTENTS 1.0 TITLE...................................................................................................................... 3 REVIEW AND APPROVAL..................................................................................... 3 PURPOSE............................................................................................................... 3 PRECAUTIONS AND LIMITS................................................................................. 3 RELATED SYSTEM STATUS................................................................................. 3 REFERENCES........................................................................................................ 4 RECORDS REQUIRED.......................................................................................... 4 INSTRUCTIONS..................................................................................................... 5 APPENDIXES PENDIX A DIRECTORY......................................................................................... 12 PENDIX B
.............................................................................................................. 13
13C IPR()CEIDURE NO.:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2
.0 TITLE QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION
.0 REVIEW AND APPROVAL See cover page.
. 0 PURPOSE
.1 This procedure provides instructions for operating the QSPDS Function Keyboard of the Qualified Safety Parameter Display System (QSPDS). Provides alternate method of determining operability of QSPDS.
PRECAUTIONS AND LIMITS One of the QSPDS Displays shall display saturation margin (page 211) continuously as the preferred, normal operating condition of the system.
Heartbeat: rectangle in upper left corner of Plasma Display Unit should be redrawn alternately solid and clear. This indicates QSPDS is updating.
Unit 2 Technical Specifications RELATED SYSTEM STATUS Class 1 E 125V DC system in operation.
120V AC instrument inverters 2C/2D lined up for normal operation or the alternate sources MCC 2A5/2B5 are aligned to supply power to 120V AC instrument buses 2MC-1/2MD-1.
REVISION NO.:
PROCEDURE TITLE:
13C PROCEDURE NO.:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2
6.0 REFERENCES
NOTE One or more of the following symbols may be used in this procedure:
§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without the required Focus review and appropriate approval.
1[ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.
6.1 Technical Specifications Section 3.3.3.6, Table 3.3-10, Items 11 and 17 6.2 CE NPROD - ICE-3202 6.3 CE Spec. No. 13172 - ICE-3220 6.4 CE Des. No. 13172 - ICE-3218 6.5 NUREG - 0737 II.F.2 6.6 1[1 99-0378 6.7 1[2 CR 00-1604 6.8 2-0SP-100.17, Accident Monitoring Instrumentation Monthly Channel Check.
7.0 RECORDS REQUIRED 7.1 Normal log entries.
7.2 Appendix B Saturation Margin, RTD, HJTC and UHJTC and CET Temperatures
13C PROCEDURE NO.:
2-1150020 8.0 INSTRUCTIONS QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2 8.1 The QSPDS is organized into a hierarchy of 3 levels: (See Appendix A)
- 1.
Level One:
Consists of the Display Directory page (100), Core Summary page (101) and the Diagnostic Page (102).
- 2.
Level Two:
Consists of the Saturation Margin page (211), Reactor Vessel Level page (212) and the Core Exit Thermocouple page (213).
These pages provide expanded detail of the Inadequate Core Cooling (I.C.C.) variables of the Core Summary page (101).
- 3.
Level Three: Consists of the Subcooled Margin page (311). Heated Junction Thermocouple page (321) and the Core Map page (331). These pages provide expanded detail of the Reactor Vessel Level, the Core Exit Thermocouples and a larger display of Subcooled Margin.
END OF SECTION 8.1
ION NO.:
13C RENO.:
2-1150020 PROCEDURE TITLE:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2
.2 The Operator Selects Display Pages and Acknowledges Alarm Conditi Using the QSPDS Function Keyboard
- 1.
To call up any display page; (See Appendix A for Directory)
A.
Depress:
B.
Depress:
C.
Depress:
PAGE XXX (Page Number)
EXEC
- 2.
To acknowledge Q.S.P.D.S. alarm conditions A.
Depress: ACK (acknowledges only plasma display alarms)
B.
At the bottom of the current display page, the page that is in alarm will be shown in inverse mode. (black letters on orange background)
C.
To determine the problem, select the alarming page on the keyboard.
- 1.
Alarm Setpoint - The parameter value will be shown in inverse mode. (Black letters on orange background)
13C PROCEDURE NO.:
2-1150020 QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2 8.2 The Operator Selects Display Pages and Acknowledges Alarm Using the QSPDS Function Keyboard (continued)
- 2.
- c.
(continued) fu NOTE The representative core exit temperature is calculated based on a statistical analysis with practice checks from the input. The out-of-range GET temperature inputs are discarded, the mean GET temperature is calculated from the remaining inputs, the GET temperature inputs are checked within a statistical band around the mean GET temperature. Those inputs falling outside the bands are flagged as suspicious inputs and discarded from the calculation. The mean, GET temperature is then recalculated using the remaining inputs.
The process continues until there are no more flagged or discarded inputs. At this point, the GET inputs are considered stable and valid, and the representative GET temperature is calculated. The mean GET temperature is constrained to be plus or minus 30 degrees F of the maximum Hot Leg temperature. Those GET(s) with outputs that are more than plus or minus 30 degrees F from the mean GET temperature are flagged "suspicious" (with ?) and not used until their values return to less than plus or minus 30 degrees F from the mean GET temperature. Both the out-of-range and suspect inputs are considered invalid, with the out-of-range inputs displayed as all question marks and the suspect inputs displayed as a question mark in front of the displayed value.
When saturation margin alarms occurs, either RGS or upper head, the process of identifying suspicious GET temperatures stops. At this point all GET input are considered valid except those previously flagged and those out-of-range. Any remaining suspect GET input will be reconsidered in the calculation if it falls within a specific band around the mean GET temperature.
If the number of valid GET inputs is less than nine, the representative GET temperature and the other GET calculated variables will be displayed as all question marks. If the number of GETs operable becomes less than 2 in anyone quadrant, a "GET Below Tech Spec Minimum Requirement" alarm message is displayed.
The aforementioned description only holds true for the Gore Exit Thermocouple (QSPDS Display Page 213). The above description does not apply to the Subcooled Margin (QSPDS Display Pages 211 and 311). The Subcooled Margin display annotates the GET temperature with a question mark when the GET input data is outside a calculated statistical acceptance I rejection band. This particular statistical acceptance I rejection band is derived by calculating the average value of all valid GETs in the specified range between 40°F and 2295°F, calculating the standard deviation by taking the square root of the sum of the squares. The standard deviation is multiplied by a given ration of 2.33, if the value inputs is greater than 30°F, the GET temperature on the Subcooled Margin is marked as suspect by display a question mark.
The increase is suspect GET inputs can be attributed to the core loading. The new fuel assemblies are loaded into the center of the core and the partially burned fuel assemblies are relocated to the outer core perimeter. The center of the core has a higher temperature than the outer perimeter. Per discussion with Reactor Engineering, the expected range of assembly outlet temperature is approximately from 615°F to 562°F. Therefore, the QSPDS will mark GETs as suspect due to the wide delta temperature experienced as a result of the core loading.
I&G Department or Engineering will have to determine if GET is inoperable if a determination is re uired and can not be determined b 2-0SP-100.17.
- 2.
Bad Data Alarm - Parameter values are replaced with question marks.
REVISION NO.:
13C PROCEDURE NO.:
2-1150020 PROCEDURE TITLE:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2 8.2 The Operator Selects Display Pages and Acknowledges Alarm Conditi Using the QSPDS Function Keyboard (continued)
- 2.
C.
(continued)
- 3.
Hardware / Software Error - The message System Error is shown blinking in the lower right hand corner of the display.
Diagnostic Page gives details.
- 4.
Keyboard input Error - Messages is shown at the lower left corner of the display.
END OF SECTION 8.2
REVISION NO.:
13C PROCEDURE NO.:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 8.3 Normal Display - Saturation Margin
- 1.
- 2.
- 3.
Depress Depress Depress PAGE 211 EXEC
- 4.
Verify Saturation Margin is displayed.
NOTE As a guideline, Saturation Margin should be greater than 20°F but less than 200°F.
A.
Saturation Margin will be displayed as both temperature and pressure margins. (Pressure is sensed by PT 1107 Ch A and PT 1108 Ch B).
B.
Upper head margin is based on the highest of the upper three Unheated Junction Thermocouples.
C.
RCS margin is based on the highest RTD either hot leg or cold leg.
D.
GET margin is based on the GET representative value which will be calculated as follows:
- 1.
Non-valid GETs will be detected by out-of-scale checks, tolerance checks and statistical analysis.
- 2.
The representative GET temperature will be based on a statistical analysis of all the remaining valid GETs.
END OF SECTION 8.3
NO.:
13C PROC TITLE:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2 Additional Keyboard Function
- 1.
BACK or FWD - Selects an adjacent page at the same level of hierarchy.
- 2.
SECT - Selects higher (SECT 0) or lower (SECT 1) level of hierarchy relevant to that page.
END OF SECTION 8.4
SION NO.:
PROCEDURE TITLE:
13C PROCEDURE NO.:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 8.5 Alarm condition for RTG8 203 Alarms (Ch 8 alarm in parenthesis 0.)
ANNUNCIATOR J-41, (J-45) ICC CH A (8) Subcooled Margin Low J-42, (J-46) ICC Ch A (8) Rx Vessel Low J-43, (J-47) ICC Ch A (8) Rx Core Exit Temp High J-44, (J-48) ICC Ch A (8) Trouble INDICATED CONDITION RCS SMM or Upper HEAD SMM less than or equal to 10° subcooled or CETs greater than or equal to 10° superheat Vessel level less than 100%
Representative CET greater than 670°F Power failure to QSPDS computer or internal computer problem END OF SECTION 8.5
REVISION NO.:
13C PROCEDURE NO.:
2-1150020 LEVEL 1 PROCEDURE TITLE:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION S1. LUCIE UNIT 2 APPENDIX A DIRECTORY (Page 1 of 1)
Page 100 Display Directory Page 101 Core Summary Page 102 Diagnostics LEVEL 2 Page 211 Saturation Margin Page 212 Reactor Vessel Level Page 213 Core Exit Thermocouples LEVEL 3 Page 311 Subcooled Margin Page 321 Heated Junction Thermocouples Page 331 Core-Map END OF APPENDIX A
REVISION NO.:
PROCEDURE TITLE:
13C PROCEDURE NO.:
2-1150020 QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2 APPENDIX B (Page 1 of 15)
NOTE Appendix B is used when the QSPDS Plasma Display Unit is out of service (blank). Completion of this appendix and 2-0SP-1 00.17 satisfies Technical Specification requirements.
- 1.
If the Control Room Plasma Display Unit for a train of QSPDS is out of service, the following information can be obtained inside the QSPDS cabinet:
Top Chassis Depressing the TEMP / PRESS pushbutton will display RCS subcooling in degrees Fahrenheit and psia.
Bottom Chassis Depressing the LEVEL I TCETC pushbutton will display the Reactor Vessel Level (from RVLMS) and the representative CET temperature.
2.
Purpose:
This appendix provides instructions for operating the pushbuttons on the top and bottom chassis inside the QSPDS cabinets to obtain counts, convert the counts into volts for the top chassis and millivolts for the bottom chassis and convert that value into actual temperature and / or pressurizer pressure using the conversion charts.
NOTE The top chassis calculates hot and cold leg temperatures and pressurizer pressure. The bottom chassis calculates HJTC, UHJTC and CET temperatures.
- 3.
Place the top or bottom chassis into TEST by depressing the TEST pushbutton.
(The ten's digit number 0 will be flashing).
13C PROCEDURE NO.:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B (Page 2 of 15)
- 4.
Select the ten's digit of the desired test number (from conversion chart) by depressing the TEMP / PRESS pushbutton one time for each incremental increase if using the TOP CHASSIS, OR LEVEL / TCETC pushbutton one time for each incremental increase if using the BOTTOM CHASSIS, until the desired ten scale of the test number appears.
Select the unit scale by depressing the ACK pushbutton. (The unit's digit number o will be flashing).
Select the unit's digit of the desired test number (from conversion chart) by depressing the TEMP / PRESS pushbutton one time for each incremental increase if using the TOP CHASSIS, OR LEVEL / TCETC pushbutton one time for each incremental increase if using the BOTTOM CHASSIS, until the desired unit scale of the test number appears.
Depress the ACK pushbutton on the affected chassis. The counts value for the test number selected will appear. Record the number displayed on the conversion data sheet.
Depress the ACK pushbutton on the affected chassis again.
Repeat Steps 4 through 8 as necessary, until all desired data is taken.
- 10.
Depress the TEST pushbutton to restore the chassis to its normal display.
- 11.
Complete the data conversions on the conversion data sheets.
- 12.
Transpose all data to 2-0SP-1 00.17 and attach this appendix and conversion charts to 2-0SP-100.17.
REVISION NO.:
I t'~uGEDURE TITLE:
PAGI 13C QUALIFIED SAFETY PARAMETER DISPLAY 5 of IRE NO.:
SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B (Page 3 of 15)
CONVERSION DATA SHEET #1 This appendix is only to be used when the QSPDS Plasma Display is out of service (blank) and in addition to 2-0SP-1 00.17.
Top Chassis Channel A Point ID Test Counts Conversion VDC Conversion Factor Results No.
Factor 2A Hot Leg 19 0.00244 (VDC X 70) + (50) of 2B Hot Leg 20 0.00244 (VDC X 70) + (50) of 2A2 Cold Leg 21 0.00244 (VDC X 70) + (50) of 2B1 Cold Leg 22 0.00244 (VDC X 70) + (50) of PZR. Press.
23 0.00244 VDC x 300 PSIA Top Chassis ChannelB Point ID Test Counts Conversion VDC Conversion Factor Results No.
Factor 2A Hot Leg 19 0.00244 (VDC X 70) + (50) of 2B Hot Leg 20 0.00244 (VDC X 70) + (50) of 2A1 Cold Leg 21 0.00244 (VDC X 70) + (50 of 2B2 Cold Leg 22 0.00244 (VDC X 70) + (50) of PZR. Press.
23 0.00244 VDC x 300 PSIA
- 0 w
REVISION NO.:
PROCEDURE TITLE:
PAGI 13C QUALIFIED SAFETY PARAMETER DISPLAY 6 of PROCEDURE NO.:
SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B (Page 4 of 15)
CONVERSION DATA SHEET #2 This appendix is only to be used when the QSPDS Plasma Display is out of service (blank) and in addition to 2-0SP-100.17.
Bottom Chassis Channel A Reactor Vessel Level Test Conversion MVDC: Compare MVDC to Results Point ID No.
Counts Factor Thermocouple Conversion Temperature Chart HJTC 1 19 0.02439 UHJTC 1 20 0.02439 HJTC2 21 0.02439 UHJTC 2 22 0.02439 HJTC 3 23 0.02439 UHJTC 3 24 0.02439 HJTC4 25 0.02439 UHJTC 4 26 0.02439 HJTC5 27 0.02439 UHJTC 5 28 0.02439 HJTC 6 29 0.02439 UHJTC 6 30 0.02439 HJTC 7 31 0.02439 UHJTC 7 32 0.02439 HJTC 8 33 0.02439 UHJTC 8 34 0.02439
REVISION NO.:
PROCEDURE TITLE:
I PAG~;}~l~. I.
13C QUALIFIED SAFETY PARAMETER DISPLAY il[~J:r~fi2.
SYSTEM OPERATION PROCEDURE NO.:
i~\\,V*li:'i;yi, 2-1150020 ST. LUCIE UNIT 2 APPENDIX B
>~ii'~!~\\<':;(..
(Page 5 of 15)
CONVERSION DATA SHEET #3 This appendix is only to be used when the QSPDS Plasma Display is out of service (blank) and in addition to 2-0SP-1 00.17.
Bottom Chassis ChannelB Reactor Vessel Level Test Conversion MVDC: Compare MVDC to Results Point ID No.
Counts Factor Thermocouple Conversion Temperature Chart HJTC 1 19 0.02439 UHJTC 1 20 0.02439 HJTC2 21 0.02439 UHJTC 2 22 0.02439 HJTC 3 23 0.02439 UHJTC 3 24 0.02439 HJTC4 25 0.02439 UHJTC 4 26 0.02439 HJTC 5 27 0.02439 UHJTC 5 28 0.02439 HJTC6 29 0.02439 UHJTC 6 30 0.02439 HJTC 7 31 0.02439 UHJTC 7 32 0.02439 HJTC 8 33 0.02439 UHJTC 8 34 0.02439
REVISION NO.:
I PROC~~URE. TITLE:
IPAGI 13C QUALIFIED SAFETY PARAMETER DISPLAY 8 of PROCEDURE NO.:
SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B (Page 6 of 15)
CONVERSION DATA SHEET #4 This appendix is only to be used when the QSPDS Plasma Display is out of service (blank) and in addition to 2-0SP-1 00.17.
Bottom Chassis Channel A CET CET Test Counts Conversion MVDC: Compare MVDC to Results No.
Factor Conversion Chart Temperature R18 35 0.02439 R16 36 0.02439 L20 37 0.02439 L18 38 0.02439 E18 39 0.02439 R20 60 0.02439 T20 61 0.02439 E16 40 0.02439 E13 41 0.02439 C18 42 0.02439 C13 43 0.02439 C6 45 0.02439 E2 44 0.02439 G4 46 0.02439 G6 47 0.02439 L4 48 0.02439 R2 49 0.02439
IREVISION NO.:
r IRI= TITLE:
13C QUALIFIED SAFETY PARAMETER DISPLAY 9 of PROCEDURE NO.:
SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B (Page 7 of 15)
CONVERSION DATA SHEET #5 This appendix is only to be used when the QSPDS Plasma Display is out of service (blank) and in addition to 2-0SP-100.17.
Bottom Chassis Channel A CET CET Test Counts Conversion MVDC: Compare MVDC to Results No.
Factor Conversion Chart Temperature L6 50 0.02439 T4 51 0.02439 R9 52 0.02439 R13 53 0.02439 T6 54 0.02439 T9 55 0.02439 W4 56 0.02439 W9 57 0.02439 W13 58 0.02439 Y8 59 0.02439 Y14 62 0.02439
REVISION NO.:
PROCEDURE TITLE:
IPAif;~~
13C QUALIFIED SAFETY PARAMETER DISPLAY PROCEDURE NO.:
SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B
- .**. Vi* *.*
(Page 8 of 15)
CONVERSION DATA SHEET #6 This appendix is only to be used when the QSPDS Plasma Display is out of service (blank) and in addition to 2-0SP-1 00.17.
Bottom Chassis ChannelB CET CET Test Counts Conversion MVDC: Compare MVDC to Results No.
Factor Conversion Chart Temperature T18 45 0.02439 G20 46 0.02439 L16 47 0.02439 L13 48 0.02439 G18 49 0.02439 G16 50 0.02439 E20 51 0.02439 G13 52 0.02439 G9 53 0.02439 C16 54 0.02439 E9 55 0.02439 E6 56 0.02439 C9 57 0.02439 A14 58 0.02439 C4 61 0.02439 A8 62 0.02439
REVISION NO.:
PROCEDURE TITLE:
IPA;i,~~kr 13C QUALIFIED SAFETY PARAMETER DISPLAY
- ~~/:
PROCEDURE NO.:
SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2
/
APPENDIX B (Page 9 of 15)
CONVERSION DATA SHEET #7 This appendix is only to be used when the QSPDS Plasma Display is out of service (blank) and in addition to 2-0SP-100.17.
Bottom Chassis ChannelB CET CET Test Counts Conversion MVDC: Compare MVDC to Results No.
Factor Conversion Chart Temperature L2 35 0.02439 T2 36 0.02439 R6 37 0.02439 R4 38 0.02439 L9 39 0.02439 G2 59 0.02439 E4 60 0.02439 W6 40 0.02439 T16 41 0.02439 T13 42 0.02439 W18 43 0.02439 W16 44 0.02439
2-1150020 PZR Pressure:
UHJTC number 1:
UHJTC number 2:
UHJTC number 3:
Bottom Chassis:
PROCEDURE TITLE:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2 APPENDIX 8 (Page 10 of 15)
CONVERSION DATA SHEET #8 Saturation Margin Channel A of Subcooled
_____ PSIA of TSAT for PZR Press:
_____ °F---+
Highest:
°F~
_____ PSIA TSATfor of........
PZR Press:
_____ of ---+
Highest:
_____ PSIA TSATfor PZR Press:
°F-----..
______ OF Subcooled
______ OF Subcooled OF Subcooled
REVISION NO.:
PROCEDURE TITLE:
13C PROCEDURE NO.:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B (Page 11 of 15)
CONVERSION DATA SHEET #9 Upper Head Subcooling:
Saturation Margin Channel A PSI Subcooled PZR Press:
Derived PSAT for highest upper head UHJTC:
RCS Subcooling:
PZR Press:
Derived PSAT for highest hot leg temperature:
CET Subcooling:
PZR Press:
Derived PSAT for TCETC from bottom chassis:
_____ PSI Subcooled
_____ PSI Subcooled
_____ PSI Subcooled
REVISION NO.:
PROCEDURE TITLE:
13C PROCEDURE NO.:
2-1150020 Upper Head Subcooling:
PZR Pressure:
UHJTC number 1:
UHJTC number 2:
UHJTC number 3:
RCS Subcooling:
PZR Pressure:
2A Hot Leg:
2B Hot Leg:
CET Subcooling:
PZR Pressure:
TCETC From Bottom Chassis:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION ST. LUCIE UNIT 2 APPENDIX B (Page 12 of 15)
CONVERSION DATA SHEET #10 Saturation Margin Channel B OF Subcooled PSIA TSAT for OF "'--..
PZR Press:
°F--.
Highest:
OF.../'"
PSIA TSAT for
° F "'--..
PZR Press:
°F--.
Highest:
PSIA TSAT for PZR Press:
OF OF Subcooled OF Subcooled OF Subcooled
REVISION NO.:
PROCEDURE TITLE:
13C PROCEDURE NO.:
QUALIFIED SAFETY PARAMETER DISPLAY SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B (Page 13 of 15)
CONVERSION DATA SHEET #11 Upper Head Subcooling:
Saturation Margin Channel B PSI Subcooled PZR Press:
Derived PSAT for highest upper head UHJTC:
RCS Subcooling:
PZR Press:
Derived PSAT for highest hot leg temperature:
CET Subcooling:
PZR Press:
Derived PSAT for TCETC from bottom chassis:
_____ PSI Subcooled
_____ PSI Subcooled
_____ PSI Subcooled
REVISION NO.:
PROCEDURE TITLE:
PA~E26 of 27ffi.
13C QUALIFIED SAFETY PARAMETER DISPLAY PROCEDURE NO.:
SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 i
APPENDIX B (Page 14 of 15)
CONVERSION CHART (Page 1 of 2)
Temperature in OF Thermoelectric Voltage in Absolute Millivolts Deg F 0
1 2
3 4
5 6
7 8
9 Deg F 150 2.666 2.689 2.712 2.735 2.758 2.781 2.804 2.827 2.850 2.873 150 160 2.896 2.920 2.943 2.966 2.989 3.012 3.035 3.058 3.081 3.104 160 170 3.127 3.150 3.173 3.196 3.220 3.243 3.266 3.289 3.312 3.335 170 180 3.358 3.381 3.404 3.427 3.450 3.473 3.496 3.519 3.543 3.566 180 190 3.589 3.612 3.635 3.658 3.681 3.704 3.727 3.750 3.773 3.796 190 200 3.819 3.842 3.865 3.888 3.911 3.934 3.957 3.980 4.003 4.026 200 210 4.049 4.072 4.095 4.118 4.141 4.164 4.187 4.210 4.233 4.256 210 220 4.279 4.302 4.325 4.348 4.371 4.394 4.417 4.439 4.462 4.485 220 230 4.508 4.531 4.554 4.577 4.600 4.622 4.645 4.668 4.691 4.714 230 240 4.737 4.759 4.782 4.805 4.828 4.851 4.873 4.896 4.919 4.942 240 250 4.964 4.987 5.010 5.033 5.055 5.078 5.101 5.124 5.146 5.169 250 260 5.192 5.214 5.237 5.260 5.282 5.305 5.327 5.350 5.373 5.395 260 270 5.418 5.440 5.463 5.486 5.508 5.531 5.553 5.576 5.598 5.621 270 280 5.643 5.666 5.688 5.711 5.733 5.756 5.778 5.801 5.823 5.846 280 290 5.868 5.891 5.913 5.936 5.958 5.980 6.003 6.025 6.048 6.070 290 300 6.092 6.115 6.137 6.160 6.182 6.204 6.227 6.249 6.271 6.294 300 310 6.316 6.338 6.361 6.383 6.405 6.428 6.450 6.472 6.494 6.517 310 320 6.539 6.561 6.583 6.606 6.628 6.650 6.672 6.695 6.717 6.739 320 330 6.761 6.784 6.806 6.828 6.850 6.873 6.895 6.917 6.939 6.961 330 340 6.984 7.006 7.028 7.050 7.072 7.094 7.117 7.139 7.161 7.183 340 350 7.205 7.228 7.250 7.272 7.294 7.316 7.338 7.361 7.383 7.405 350 360 7.427 7.449 7.471 7.494 7.516 7.538 7.560 7.582 7.604 7.627 360 370 7.649 7.671 7.693 7.715 7.737 7.760 7.782 7.804 7.826 7.848 370 380 7.870 7.893 7.915 7.937 7.959 7.981 8.003 8.026 8.048 8.070 380 390 8.092 8.114 8.137 8.159 8.181 8.203 8.225 8.248 8.270 8.292 390 400 8.314 8.336 8.359 8.381 8.403 8.425 8.448 8.470 8.492 8.514 400 410 8.537 8.559 8.581 8.603 8.626 8.648 8.670 8.692 8.715 8.737 410 420 8.759 8.782 8.804 8.826 8.849 8.871 8.893 8.916 8.938 8.960 420 430 8.983 9.005 9.027 9.050 9.072 9.094 9.117 9.139 9.161 9.184 430 440 9.206 9.229 9.251 9.273 9.296 9.318 9.431 9.363 9.385 9.408 440 450 9.430 9.453 9.475 9.498 9.520 9.563 9.565 9.588 9.610 9.633 450 460 9.655 9.678 9.700 9.723 9.745 9.763 9.790 9.813 9.835 9.858 460 470 9.880 9.903 9.926 9.948 9.971 9.993 10.016 10.038 10.061 10.084 470 480 10.106 10.129 10.151 10.174 10.197 10.219 10.242 10.265 10.287 10.310 480 490 10.333 10.355 10.378 10.401 10.423 10.446 10.469 10.491 10.514 10.537 490 Deg F 0
1 2
3 4
5 6
7 8
9 Deg F
REVISION NO.:
PROCEDURE TITLE:
13C QUALIFIED SAFETY PARAMETER DISPLAY of PROCEDURE NO.:
SYSTEM OPERATION 2-1150020 ST. LUCIE UNIT 2 APPENDIX B (Page 15 of 15)
CONVERSION CHART (Page 2 of 2)
Temperature in of Thermoelectric Voltage in Absolute Millivolts Deg F 0
1 2
3 4
5 6
7 8
9 Deg F 500 10.560 10.582 10.605 10.628 10.650 10.673 10.696 10.719 10.741 10.764 500 510 10.787 10.810 10.833 10.855 10.878 10.901 10.924 10.947 10.969 10.992 510 520 11.015 11.038 11.061 11.083 11.106 11.129 11.152 11.175 11.198 11.221 520 530 11.243 11.266 11.289 11.312 11.335 11.358 11.381 11.404 11.426 11.449 530 540 11.472 11.495 11.518 11.541 11.564 11.587 11.610 11.633 11.656 11.679 540 550 11.702 11.725 11.748 11.770 11.793 11.816 11.839 11.862 11.885 11.908 550 560 11.931 11.954 11.977 12.000 12.023 12.046 12.069 12.092 12.115 12.138 560 570 12.161 12.184 12.207 12.230 12.254 12.277 12.300 12.323 12.346 12.369 570 580 12.392 12.415 12.438 12.461 12.484 12.507 12.530 12.553 12.576 12.599 580 590 12.623 12.646 12.669 12.692 12.715 12.738 12.761 12.784 12.807 12.831 590 600 12.854 12.877 12.900 12.923 12.946 12.969 12.992 13.016 13.039 13.062 600 610 13.085 13.108 13.131 13.154 13.178 13.201 13.224 13.247 13.270 13.293 610 620 13.317 13.340 13.363 13.386 13.409 13.433 13.456 13.479 13.502 13.525 620 630*
13.549 13.572 13.595 13.618 13.641 13.665 13.688 13.711 13.734 13.757 630 640 13.781 13.804 13.827 13.850 13.874 13.897 13.920 13.943 13.967 13.990 640 650 14.013 14.036 14.060 14.083 14.106 14.129 14.153 14.176 14.199 14.222 650 660 14.246 14.269 14.292 14.316 14.339 14.362 14.385 14.409 14.432 14.455 660 670 14.479 14.502 14.525 14.548 14.572 14.595 14.618 14.642 14.665 14.688 670 680 14.712 14.735 14.758 14.782 14.805 14.828 14.852 14.875 14.898 14.922 680 690 14.945 14.968 14.992 15.015 15.038 15.062 15.085 15.108 15.132 15.155 690 700 15.178 15.202 15.225 15.248 15.272 15.295 15.318 15.342 15.365 15.389 700 710 15.412 15.435 15.459 15.482 15.505 15.529 15.552 15.576 15.599 15.622 710 720 15.646 15.669 15.693 15.716 15.739 15.763 15.786 15.810 15.833 15.856 720 730 15.880 15.903 15.927 15.950 15.974 15.997 16.020 16.044 16.067 16.091 730 740 16.114 16.138 16.161 16.184 16.208 16.231 16.255 16.278 16.302 16.325 740 750 16.349 16.372 16.395 16.419 16.442 16.466 16.489 16.513 16.536 16.560 750 760 16.583 16.607 16.630 16.654 16.677 16.700 16.724 16.747 16.771 16.794 760 770 16.818 16.841 16.865 16.888 16.912 16.935 16.959 16.982 17.006 17.029 770 780 17.053 17.076 17.100 17.123 17.147 17.170 17.194 17.217 17.241 17.264 780 790 17.288 17.311 17.335 17.358 17.382 17.406 17.429 17.453 17.476 17.500 790 Deg F 0
1 2
3 4
5 6
7 8
9 Deg F END OF APPENDIX B
Title:
ST. LUCIE UNIT 2 OPERATIONS SURVEILLANCE PROCEDURE SAFETY RELATED CONTINUOUS USE 06/14/07 ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK Responsible Department: OPERATIONS REVISION
SUMMARY
Revision 1 - Incorporated PCR 07-1821 for CR 2006-17966 to change acceptance band range. (Donald MacArthur, 06/13/07)
REVISION 0 - Incorporated PCR 06-1992 to create new procedure for Accident Monitoring Instrumentation Surveillance. (Joe Hessling, 06/28/06)
Revision FRG Review Date Approved By Approval Date SLOPS 0
06/27/06 Chris R. Costanzo 06/28/06 DATE Plant General Manager DOCT Revision FRG Review Date Approved By Approval Date DOCN N/A SYS Plant General Manager COM Joe Hessling 06/13/07 ITM Authorized Approver N/A Authorized Approver (Minor Correction
NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 TABLE OF CONTENTS SECTION 1.0 PURPOSE............................................................................................................... 3
2.0 REFERENCES
........................................................................................................ 3 3.0 PREREQUiSiTES................................................................................................... 4 4.0 PRECAUTIONS I LIMITATIONS............................................................................. 4 5.0 RECORDS REQUIRED.......................................................................................... 5 6.0 ACCEPTANCE CRITERIA...................................................................................... 5 7.0 INSTRUCTIONS..................................................................................................... 6 TABLES TABLE 1 HJTCs AND CETs EOOS........................................................................... 13
REVISION NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION PROCEDURE NO.:
MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 1.0 PURPOSE 1.1 The purpose of this Surveillance is to perform the Accident Monitoring Instrumentation check as required by Technical Specification Section 3.3.3.6.
2.0 REFERENCES
NOTE One or more of the following symbols may be used in this procedure:
§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without the required Focus review and appropriate approval.
1l Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.
'I' Indicates a step that requires a sign off on an attachment.
2.1 Technical Specifications Section 3.3.3.6, Accident Monitoring Instrumentation 2.2 Miscellaneous Documents 111 CRN 02083-10571, Revise Calibration of Containment Sump Level Channel L-07-6
§1 L-2001-255, Missed Surveillance on LI-1103 (PMAI 02-05-060) 112 CR04-0027, Expected Bands 113 PSL-ENG-SEIS-00-029, Accident Monitoring Instrumentation 114 PSL-ENG-SEIS-06-006, Operation with increased Steam Generator Tube Plugging (42%) During Cycle 16 (update based on 25% DGTP)
1 PROCEDURE NO.:
ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 3.0 PREREQUISITES 3.1 None o
PRECAUTIONS / LIMITATIONS 1
A Channel Check shall be the qualitative assessment of channel behavior during operation by observation. This observation shall include, where possible, comparison of the channel indications and/or status derived from independent instrumentation channels measuring the same parameter. The above definition has several points to consider:
- 1.
Note that it is not a quantitative assessment but a qualitative assessment.
This means that absolute values of indication between various instruments need not be within a specified range. It does mean that the various indications must be compared with each other and a conclusion reached that all indicators and channels are operable.
- 2.
It is necessary to compare with other type of instruments such as alarms, recorders, etc.
- 3.
Single channel instruments which cannot be compared with other instruments should be assessed based on system operation; e.g., is that the expected range of values for the specific load, speed, time of day, etc. A conclusion regarding operability must be reached.
- 4.
Establishing absolute values to compare one channel indication to another channel may provide an apparent easy method to determine operability; however, it would not address the case where 2 of 4 channels indicated 40% and the other 2 indicated 45%. Which two channels are correct? It would also not solve the case of having only one channel or instruments with different ranges.
- 5.
The following guidelines should be used when conducting channel checks:
A.
Ensure as many different channels are compared as possible.
B.
Although the absolute value differences are not specified, use those differences to help provide assurances of operability.
C.
Since most channel checks are conducted during actual logging of parameters on log sheets, etc., be especially alert that system parameters are consistent with plant condition.
REVISION NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION PROCEDURE NO.:
MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2
.1 (continued)
- 5.
(continued)
D.
If during the reading taking or channel checking an instrument cannot be established as operable using available information, declare it inoperable and take required action; e.g., action statement, NPWO, alternate monitoring, etc.
- 6.
In conclusion, the instruments must be determined to be operable, the parameters within limits and the values consistent with plant conditions.
. 2 Alternative indications are provided as listed with an "OR" statement. Only one of the alternative indications is required to be checked to meet the surveillance requirement for that indication and channel.
4.3
§1 The "Expected Parameter Band" is provided as a historical reference band of previous readings and is NOT acceptance criteria. The "Expected Parameter Band" provided assumes 100% Steady State Full Power Operation. Some values may differ if this surveillance is performed at plant conditions other than 100% Steady State Full Power Operation. Should a parameter fall outside the "Expected Band" it should be evaluated and either declared out-of-service or the justification as to why it remains operable should be provided.
5.0 RECORDS REQUIRED 5.1 RCO Chronological Log entries 5.2 The completed copy of section 7 with applicable steps initialed shall be maintained in the plant files in accordance with QI-17 -PSL-1, Quality Assurance Records.
6.0 ACCEPTANCE CRITERIA 6.1 The Accident Monitoring Instrumentation meets the applicable acceptance criteria as specified for each indication.
SION NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION PROCEDURE NO.:
MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 7.0 INSTRUCTIONS
.1 Record the following data:
Date
/
/
- 1.
- Containment Pressure (Expected Band: -2 to +2 psig)
A.
B.
PI-07-4A1 ___
psig OR PR-07-4A1 ____ psig PI-07-4B1 psig
- 2.
- Containment Sump Water Level (Narrow Range. Expected Band:
-5.8 to -5.2 feet)
A.
LI-07-14A, ____ ft. OR LR-07-14A ____ ft.
NOTE 1[1 The end of the transmitter bubbler tube is located 6 inches above the bottom of the sump (plant elevation minus 7 feet). and therefore this instrument channel can NOT measure sum level below 6 inches.
- 3.
- 4.
B.
1[1 (if LI-07-14A is inoperable. use LlS-07-6 on RTGB 205. Expected Band: 14.4 inches to 24.2 inches)
LlS-07 -6 inches
- Containment Sump Water Level (Wide Range. Expected Band:
-1.25' to -0.75')
A.
B.
LI-07-13A. ____ ft. OR LR-07-13A ___ ft.
LI-07-13B ft.
- Refueling Water Storage Tank Level (Expected Band: all within 0.5 ft.)
LlS-07 -2A. ____ ft.
LlS-07-2B ft.
LlS-07-2C ft.
A.
B.
C.
D.
LlS-07-2D ft. OR LR-07-2D ft.
S_2_ OPS DATE DOCT Procedure DOCN 2-0SP-100.17 SYS OPS COMP ITM 0
- 0
ON NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 (continued)
- 5.
114
- 2A Steam Generator Pressure (expected Band: 810 to 825 A.
B.
C.
D.
psia)
PI-8013A. ____,psia PI-8013B psia PI-8013C ____ psia PI-8013D ____ psia OR PR-8013D ____ psia
- 6.
114
- 2B Steam Generator Pressure (expected Band: 810 to 825 psia)
A.
PI-8023A. ____,psia B.
PI-8023B ____ psia
- c.
PI-8023C ____,psia D.
PI-8023D ____,psia OR PR-8023D ____ psia
- 7.
- Reactor Coolant Outlet Temperature - T Hot (Wide Range)
Expected Band: 590 to 610°F)
A.
TR-1112HA'--___ OF OR Hot Leg 2A Temp of (Alternate Indication on Page 211 of A QSPDS)
TR-1122HB ___ --oF OR Hot Leg 2B Temp of (Alternate Indication on Page 211 of B B.
- 8.
- Reactor Coolant Inlet Temperature - T Cold (Wide Range)
Expected Band: 540 to 560°F)
A.
TR-1112CA'--___ OF OR Cold Leg 2A2 Temp of (Alternate Indication on Page 211 of A QSPDS)
B.
TR-1122CB ____ oF OR Cold Leg 2B2 Temp of (Alternate Indication on Page 211 of B QSPDS)
REVISION NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION PROCEDURE NO.:
MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 7.1 (continued)
- 9.
,-r2
- Reactor Coolant Pressure - Wide Range (Expected Band:
2230 to 2270 psia)
A.
PI-1107-1 psi a OR Pressurizer Pressure
____ psia (Pressurizer Pressure Alternate indication on Page 211 of B QSPDS)
B.
PI-1108-1 psia OR PR-11 08 psi a OR PZR Pressure psia (Pressurizer Pressure Alternate indication on Page 211 of A QSPDS)
- 10.
- Pressurizer Water Level (Expected Band: 61%-65%):
A.
U-1110X ____ % OR LR-111 OX (if selected)
B.
U-1110Y
- 11.
- Steam Generator Level - Wide Range (Expected band:
57%-60%)
A.
L9012 (DCS FPD) ___ % OR U-9014 (PACB #2)
B.
L9022 (DCS FPD) ___ % OR U-9024 (PACB #2)
- 12.
- Auxiliary Feedwater Flow Rate (Expected Value: 0 gpm):
A.
Header A Flow FI-09-2A gpm OR FR 2A gpm B.
Header B Flow FI-09-2B gpm OR FR 2B gpm
- c.
Header C Flow FI-09-2C gpm OR FR 2C gpm
REVISION NO.:
R~ TITLE:
IPAGI 1
ACCIDENT MONITORING INSTRUMENTATION of PROCEDURE NO.:
MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 7.1 (continued)
- 13.
- Reactor Coolant System Subcooling Margin Monitor (Page 211):
Degrees F (E
~d Band)
PSI (Ext.;t::cted Band)
QS]'DS A Upper Head
(~O°F)
(500-700 psia)
QS]'DS ARCS (40-60°F)
(600-800 psia)
QS]'DS A CET (20-40°F)
(300-500 psia)
QSPDS B Upp~r J-I~Cld
(~Q-50°F)
(500-~psia)
QSPDS B RC~
(40-60°F)
(600-800 psia)
(300-§QQ2sia)
- 14.
- Incore Thermocouples (Page 331, Expected Band 560-630°F)
QSPDSA QSPDSA QSPDSA QSPDSA Quadrant 1 Quadrant 2 Quadrant 4 Quadrant 3 CET TEMP CET TEMP CET TEMP CET TEMP T20 C18 Y14 L6 R20 E16 W13 G6 L20 E13 R13 T4 R18 C13 W9 L4 L18 C6 T9 G4 E18 R9 R2 R16 Y8 E2 T6 W4 QSPDS B QSPDS B QSPDS B QSPDS B Quadrant 1 Quadrant 2 Quadrant 4 Quadrant 3 CET TEMP CET TEMP CET TEMP CET TEMP G20 C16 W18 L9 E20 A14 W16 R6 T18 G13 T16 R4 G18 G9 T13 E4 L16 E9 W6 T2 G16 C9 L2 L13 A8 G2 E6 C4
REVISION NO.:
PROCEDURE TITLE:
PA~l o~1~j'\\1 1
ACCIDENT MONITORING INSTRUMENTATION PROCEDURE NO.:
MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 i.'>*******
7.1 (continued)
- INITIAL
- 15.
- Reactor Vessel Level Monitoring System (Page 321):
NOTE HJTC Differential Temperature SHALL be greater than or equal to 80°F for a Channel A level sensor to be considered OPERABLE.
A QSPDS UNHEATED A QSPDS HEATED A QSPDS (Expected Band: 560-630°)
(Expected Band: 680-800°F)
DIFFERENTIAL
- 1.
- 1.
- 2.
- 2.
- 3.
- 3.
- 4.
- 4.
- 5.
- 5.
- 6.
- 6.
- 7.
- 7.
- 8.
- 8.
HEATER CONTROL SIGNAL 1
% FULL POWER (Expected Value 100%)
HEATER CONTROL SIGNAL 2
% FULL POWER (Expected Value 100%)
NOTE HJTC Differential Temperature SHALL be greater than or equal to 51°F for a Channel B level sensor to be considered OPERABLE.
B QSPDS UNHEATED B QSPDS HEATED B QSPDS (Expected Band: 560-630°)
(Expected Band: 680-800°F)
DIFFERENTIAL
- 1.
- 1.
- 2.
- 2.
- 3.
- 3.
- 4.
- 4.
- 5.
- 5.
- 6.
- 6.
- 7.
- 7.
- 8.
- 8.
HEATER CONTROL SIGNAL 1
% FULL POWER (Expected Value 100%)
HEATER CONTROL SIGNAL 2
% FULL POWER (Expected Value 100%)
1 NO.:
ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2
.1 (continued)
- 16.
- Verify PORV block valve position indicators are illuminated and indicate desired position (not required if the PORV block valves are closed and power is removed).
A.
V1476 B.
V1477
- 17.
- Verify PORV Valve Position Indicators are illuminated and indicate desired position.
A.
V1474 B.
V1475
- 18.
- Verify the following on the PORV and Safety Valve acoustic flow monitor (FI-01-1, FI-01-2, FI-01-3, FI-01-4 & FI-01-5):
A.
No flow indication Red LEOs is illuminated.
B.
Power available Red LEOs are illuminated.
. 2 1f it has been evaluated that an accident monitoring instrument has failed the channel check, Then ensure that a plant work order is initiated and the instrument is entered in the equipment out-of-service program.
Additionally, ensure those instruments determined to be satisfactory are removed from the equipment out-of-service program. Equipment out-of-service entries for CETs and HJTCs are documented on a form similar to Table 1 of this data sheet. A single generic EOOS entry is utilized.
Table 1 will be maintained in the EOOS notebook along with the green PWO tags associated with the individual plant work orders. A single yellow dot will be affixed to the QSPDS monitor to identify that the system has pending work orders.
. 3 Ensure that Table 1 is placed in the review file at the beginning of each fuel cycle and a new Table 1 is initiated (transferring all existing EOOS entries to the new Table 1).
7.4
~3
- The Accident Monitoring Instrumentation checked by this Data Sheet has been verified against and meets the requirements of Tech Spec 3.3.3.6, Table 3.3-10.
REVISION NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION PROCEDURE NO.:
MONTHLY CHANNEL CHECK 2-0SP-100.17 ST. LUCIE UNIT 2 7.5 Recorded by:
- Satisfactory performance of the above asterisked steps assures conformance with applicable Technical Specifications.
I have reviewed the requirements of this procedure including other surveillances performed during this procedure, if any (i.e., data sheet(s), PMT sheet(s}, etc.}. Any deviations, abnormal results, equipment problems, failures, or human performance issues must be documented via a Condition Report for each individual item.
C.R.# _____ _
Reviewed by: ____________ _
SM/US END OF SECTION 7.0
REVISION NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK PROCEDURE NO.:
2-0SP-100.17 ST. LUCIE UNIT 2 TABLE 1 HJTCs AND CETs EOOS (Page 1 of 5)
QSPDSA HJTC HJTC#
Date & Time OOS Reason WO#
US I SM Removed from Date & Time SIS SM I US Returned to Service Service QSPDS S HJTC HJTC# I Date & Time OOS I Reason I
WO#
I US I SM Re':10ved from I Date & Time SIS I SM I US R~turned to Service Service
REVISION NO.:
PROCEDURE TITLE:
PAGE:d:j:':;~{
1 ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK
.~i~~~5;f!~:..
PROCEDURE NO.:
2-0SP-100.17 ST. LUCIE UNIT 2 TABLE 1 HJTCs AND CETs EOOS (Page 2 of 5)
Date & Time OOS Reason WO#
US / SM Removed Date & Time SIS SM / US Returned to from Service Service QSPDS S GET Quadrant 2 GET#
Date & Time OOS Reason WO#
US / SM Removed Date & Time SIS SM / US Returned to from Service Service
r,'.J REVISION NO.:
PROCEDURE TITLE:
PAOEI~~
1 ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK PROCEDURE NO.:
2-0SP-100.17 ST. LUCIE UNIT 2
,,' <,il:at;i~
TABLE 1 HJTCs AND CETs EOOS (Page 3 of 5)
Date & Time OOS Reason WO#
US / SM Removed Date & Time SIS SM / US Returned to from Service Service QSPDS S GET Quadrant 4 GET#
Date & Time OOS Reason WO#
US / SM Removed from I Date & Time SIS SM / US Returned to Service Service
REVISION NO.:
PROCEDURE TITLE:
1 ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK PROCEDURE NO.:
2-0SP-100.17 ST. LUCIE UNIT 2 TABLE 1 HJTCs AND CETs EOOS (Page 4 of 5)
Date & Time OOS Reason WO#
US / SM Removed from Date & Time SIS SM / US Returned to Service Service QSPDS A CET Quadrant 4 CET#
Date & Time OOS Reason WO#
US / SM Removed from Date & Time SIS SM / US Returned to Service Service
REVISION NO.:
PROCEDURE TITLE:
PAGE:
1 ACCIDENT MONITORING INSTRUMENTATION MONTHLY CHANNEL CHECK PROCEDURE NO.:
2-0SP-100.17 ST. LUCIE UNIT 2 TABLE 1 HJTCs AND CETs EOOS (Page 5 of 5)
Date & Time OOS Reason WO#
US I SM Removed from Date & Time SIS SM I US Returned to Service Service QSPDS A GET Quadrant 2 GET#
Date & Time OOS Reason WO#
US I SM Removed from Date & Time SIS SM I US Returned to Service Service END OF TABLE 1
FLORIDA POWER & LIGHT R FT NRC Admin. Exam CANDIDATE EXAMINER ST LUCIE NRC LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPMA3ADM Determine Shutdown Margin Criteria (SRO)
FLORIDA POWER & LIGHT NRC Admin. Exam Perform Shutdown Margin Verification Surveillance Examinee:
SAFETY FUNCTION ADMIN. TOPIC TESTING ENVIRONMENT NONE Equipment Classroom / Simulator Control POSITION FAULTED VALIDATED TIME (YIN)
SRO N
20 STANDARD:
Direction to borate due to not meeting SDM requirements
REFERENCES:
Unit 2 Plant Physics Curves KIA #
2.2.39 (4.5)
TIME CRITICAL (YIN)
N 2-NOP-100.04, "Surveillance Requirements for Shutdown Margin; Modes 2,3,4, and 5 (Subcritical)"
INITIATING CUE:
Unit 2 was at 1 00% power for 1 00 days, 1021 EFPH. An automatic reactor I turbine trip just occurred. CEA 56 did not drop and is at 132" withdrawn. Current RCS temperature is 532°F, RCS Cb is 1085 ppm, and current time is 1500. You are directed to verify shutdown margin for the current plant conditions using the same RCS temperature.
EXAMINERS NOTE: This SDM calculation was conducted using 1000 EFPH, cycle 17. Plant curves, Figure B.3 dated 3/4/08, Fig. BA, B.5, B.6, B.8 dated 2/26/08, B.7 1/10108. Ensure the same revisions given to the applicants for performance of this JPM.
START TIME END TIME DURATION (minutes)
OPERATOR PERFORMANCE AS EVALUATED TO STANDARD (circle one)
SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________
DATE:
EXAMINER (print):
FLORIDA POWER & LIGHT NRC Admin. Exam
- indicates a "critical" step STEP STANDARD S/U Step 5A Xenon worth
-2563 PCM Step 5B Reactivity Deviation
+1148 Step 50, Total Reactivity
-1263 6A Step 6B Boron worth
+8.14 Step 6C Equivalent Boron worth in PPM
-155 Step 60 Shutdown Boron Concentration
+1251
- Step 6E Required Boron Concentration
+1096 (+/-5 ppm)
Step 7A Current Boron Concentration
+1085 NOT Meeting shutdown margin
- Determines SDM not met for current Direct Emergency Boration >40 plant conditions gpm of >1720 ppm. (T.S. 3.1.1.1)
END TIME:
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE:
Unit 2 was at 100% power for 100 days, 1000 EFPH. An automatic reactor I turbine trip occurred. CEA 56 did not drop and is at 132" withdrawn. Current RCS temperature is 532°F, RCS Cbis 1085 ppm, and current time is 1500. You are directed to verify shutdown margin for the current plant conditions using the same RCS temperature.
Title:
ST. LUCIE UNIT 2 NORMAL OPERATING PROCEDURE SAFETY RELATED CONTINUOUS USE Effective Date 04/20/07 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN MARGIN; MODES 2, 3, 4 AND 5 (SUBCRITICAL)
Responsible Department: REACTOR ENGINEERING REVISION
SUMMARY
Revision 1 - THIS PROCEDURE HAS BEEN COMPLETELY REWRITTEN. Incorporated PCR 07-0869 for CR 2006-8825 to provide operators with the option of estimating future shutdown margin needs such as when conditions are changing following a reactor trip. Also clarifies the Data Sheet to make data entry easier and reduce the chance for error when target conditions are estimated. (Walter Mead, 03/13/07)
Revision OE - Incorporated MC 03-3006 for CR 2005-18614 to add level of use to cover page.
(Helga Baranowsky, 10/07/05)
Revision OD -Incorporated PCR 05-2752 to change NPS/ANPS to SM/US on Page 10 And Page 12. (Bob Tremayne, 09/06/05)
Revision OC - Incorporated PCR 03-0872 to update reference to the Reactor Plant Startup procedure. (C.F. Diaz, 04/09/03)
AND Incorporated PCR 03-0814 for PC/M 02-042 to change OOPS to DCS. (J. Folden, 04/09/03)
Revision OB - Added a line in Step 3C to record numbers on. (Glenn Mulcahy, 12/27/01)
Revision FRG Review Date Approved By Approval Date SLOPS 0
10/28/99 R.G. West 10/28/99 DATE Plant General DOCT Revision FRG Review Date Approved By Approval Date DOCN N/A SYS Plant General Manager COM R. Weller 03/13/07 ITM Authorized Approver N/A Authorized Approver
1 IPRC)CEDIURE NO.:
2-NOP-100.04 SECTION SURVEILLANCE REQUIREMENTS FOR SHUTDOWN MARGIN; MODES 2, 3, 4 AND 5 (SUBCRITICAL)
ST. LUCIE UNIT 2 TABLE OF CONTENTS PAGE 1.0 PURPOSE............................................................................................................... 3 o
REFERENCES........................................................................................................ 3 o
PREREQUISITES................................................................................................... 5 o
PRECAUTIONS / LIMITATIONS............................................................................. 5 o
RECORDS REQUIRED.......................................................................................... 6 o
INSTRUCTIONS..................................................................................................... 7 6.1 Determine Shutdown Margin........................................................................ 7 DATA SHEETS DATA SHEET 1 SHUTDOWN MARGIN VERIFICATION FOR MODE 2 (SUBCRITICAL)............................................................................... 10 DATA SHEET 2 SHUTDOWN MARGIN VERIFICATION FOR MODES 3, 4, 5 (SUBCRITICAL)............................................................................... 11
NO.:
1 RENO.:
2-NOP-100.04 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN MARGIN; MODES 2,3,4 AND 5 (SUBCRITICAL)
ST. LUCIE UNIT 2
.0 PURPOSE 1.1 To provide detailed steps for determining the boron concentration required to meet the Shutdown Margin Requirements of Modes 2, 3, 4 and 5 with the reactor subcritical.
1.2 To provide the steps required to meet the surveillance requirements on Shutdown Margin for Mode 2 prior to achieving criticality.
2.0 REFERENCES
NOTE One or more of the following symbols may be used in this procedure:
§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Amendment, etc. and shall NOT be revised without the required Focus review and appropriate approval.
~ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.
. 1 Technical Specifications
§1 Section 3.1.1.1
§1 Section 3.1.1.2
§1 Section 3.1.3.6
.2 Updated Final Safety Analysis Report (UFSAR)
Chapters 4 and 15 2.3 Management Directives and Regulatory Commitments NONE
REVISION NO.:
PROCEDURE TITLE:
1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:
MARGIN; MODES 2,3,4 AND 5 (SUBCRITICAL) 2-NOP-100.04 ST. LUCIE UNIT 2 2.4 Procedures 111 2-0NP-02.02, Emergency Boration.
OSP-64.01, Reactor Engineering Periodic Test, Checks and Calibrations.
OP 2-0010125, Schedule of Periodic Tests, Checks and Calibrations.
2-0SP-100.14, Surveillance Requirements for Shutdown Margin; Mode 1 and Mode 2 (Critical).
2-GOP-302, Reactor Plant Startup - Mode 3 to Mode 2.
2.5 Miscellaneous Documents Unit 2 Plant Physics Curve Book.
r,vv,-,uvRE TITLE:
1 NO.:
2-NOP-100.04 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN MARGIN; MODES 2, 3, 4 AND 5 (SUBCRITICAL)
ST. LUCIE UNIT 2 3.0 PREREQUISITES 3.1 The reactor is subcritical in Modes 2, 3, 4 or 5.
4.0 PRECAUTIONS I LIMITATIONS NOTE Shutdown Margin is defined as the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all CEAs are fully inserted except for the single CEA of hi hest reactivit worth which is assumed to be full withdrawn.
4.1
§1 With the measured RCS boron concentration lower than the required boron concentration for current plant conditions, immediately initiate and continue emergency boration per 2-0NP-02.02 until the required boron concentration is achieved.
4.2 11 the measured RCS boron concentration is lower than the required boron concentration for the target conditions, Then commence boron addition to the RCS per 2-NOP-02.24.
4.3 The boron concentration required for Shutdown Margin shall be determined while in Modes 3, 4 or 5:
- 1.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or as often as required when xenon and temperature conditions are changing.
- 2.
Within one hour after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the CEA(s) is / are inoperable. If the inoperable CEA is immovable or untrippable, the required boron concentration (line 6E on Data Sheet 2) shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA(s).
When in Mode 2 with K eff less than 1.0, the Shutdown Margin shall be determined within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical CEA position is within the limits of St. Lucie Unit 2 Technical Specification 3.1.3.6.
5 The Shutdown Boron Concentration versus Moderator Temperature Plant Physics Curves takes no credit for peak Samarium poisoning.
S Proper compliance with Shutdown Margin requirements does not assure compliance with requirements for K eff. Therefore, prior to taking any action that will change reactivity (such as withdrawing CEAs), the effect on K effmust be considered independently of the effect on Shutdown Margin.
REVISION NO.:
PROCEDURE TITLE:
1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:
MARGIN; MODES 2,3,4 AND 5 (SUBCRITICAL) 2-NOP-100.04 ST. LUCIE UNIT 2 4.7 The required Shutdown Margin changes during the Mode 5 to Mode 4 ttt~§SitiOQ.
Ensure the RCS is borated to the higher SDM requirement as indicated in the COLR.
4.8 While in Mode 1 or 2 with the reactor critical, utilize 2-0SP-100.14 in determining Shutdown Margin.
4.9 if in Mode 3 awaiting a Reactor startup, with CEAs NOT fully inserted and Xenon decaying, Then DETERMINE the shutdown margin boron concentration requirement sufficiently in advance of Reactor startup and ensure the boron concentration for the estimated critical condition remains greater than the required shutdown boron requirement.
5.0 RECORDS REQUIRED 5.1 The completed data sheet along with any collected data shall be maintained in the plant files in accordance with QI-17 -PSL-1, Quality Assurance Records.
REVISION NO.:
PROCEDURE TITLE:
1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:
MARGIN; MODES 2, 3, 4 AND 5 (SUBCRITICAL) 2-NOP-100.04 ST. LUCIE UNIT 2 6.0 INSTRUCTIONS 6.1 Determine Shutdown Margin
- 1.
- 2.
- 3.
- 4.
A.
ENSURE Section 3.0, Prerequisites, completed.
REVIEW Section 4.0, Precautions I Limitations.
If the Plant is subcritical and in Mode 2, Then COMPLETE Data Sheet 1 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving criticality.
If the Plant is in Mode 3, 4, or 5, Then DETERMINE Shutdown Margin Verification by completion of Data Sheet 2 in accordance with the following steps:
Current Plant Conditions:
- 1.
ENTER the reference information as specified in Section 3 of Data Sheet 2.
B.
Target Plant Conditions
- 1.
ENTER the surveillance time interval (hours for which the surveillance is valid), typically 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or less on line 4A of Data Sheet 2.
- 2.
ENTER the lowest RCS temperature anticipated during surveillance target time on line 4B of Data Sheet 2.
C.
Reactivity Components:
- 1.
DETERMINE from Plant Physics Curves (Figure A.4) or the RCS screen on DCS, the lowest Xenon Worth (in PCM) expected during the surveillance time interval.
- a.
ENTER it on line 5A.
- b.
This value is always negative.
- 2.
DETERMINE the most recent Reactivity Deviation from the Reactivity Deviation Log (Plant Physics Curves, Figure B.3, col. 2).
- a.
ENTER it on line 58.
- b.
INCLUDE the proper sign.
NO.:
RE TITLE:
1 PROCEDURE NO.:
2-NOP-100.04 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN MARGIN; MODES 2, 3, 4 AND 5 (SUBCRITICAL)
ST. LUCIE UNIT 2 6.1 Determine Shutdown Margin (continued)
- 4.
(continued)
NOTE The required shutdown boron concentration in Figures B.5, B.6 and B.7 assume a hypothetical stuck CEA. If there is an actual stuck CEA, the reactivity difference of the worst CEA and the second worst CEA given in Figure B.4 should be used (i.e., added to the required shutdown boron concentration).
- 5.
D.
Actions for Stuck CEAs:
- 1.
If there is no actual stuck CEA, Then ENTER zero pcm for line 5C of Data Sheet 2.
- 2.
If there is an actual stuck CEA, Then CONSULT the Reactor Engineering Supervisor and the Plant Physics Curve Book (Figure B.4) to determine the worth.
- a.
ENTER that value on line 5C.
- 3.
§ 11J 1 If there is more than one actual stuck CEA, Then INITIATE and continue boration at 40 gpm of 1720 ppm boron or equivalent until the RCS boron concentration is ~1720 ppm unless otherwise specified by Reactor Engineering.
E.
ADD lines SA, 5B and 5C and enter the sum on line 50.
- 1.
OBSERVE the proper signs.
Reactivity Balance:
A.
ENTER the total Reactivity Component from line 50 on line 6A.
- 1.
OBSERVE the proper sign.
B.
DETERMINE from Plant Physics Curves (Figure B.5), the All Rods In (ARI) Boron Worth which corresponds to the Limiting RCS temperature of Section 3 or 4.
- 1.
ENTER this value on line 6B.
REVISION NO.:
PROCEDURE TITLE:
1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:
MARGIN; MODES 2,3,4 AND 5 (SUBCRITICAL) 2-NOP-100.04 ST. LUCIE UNIT 2 6.1 Determine Shutdown Margin (continued)
- 5.
(continued)
C.
DETERMINE the Total Reactivity Component Worth in terms of boron by dividing line 6A by line 6B.
- 1.
ENTER this value on line 6C.
- 2.
OBSERVE the sign.
NOTE Figure B.7 may only be used when calculating the shutdown boron requirements for Modes 2 and 3 with Reactor Coolant System temperature greater than or equal to 515°F.
- 6.
D.
DETERMINE from Plant Physics Curves (Figures B.6, B.7 or B.8),
the boron concentration which corresponds to the Limiting RCS temperature, core burnup and to the present mode of Section 3 or 4.
- 1.
Linear interpolation may be necessary.
- 2.
RECORD any interpolation calculations at the bottom of Data Sheet 2.
- 3.
If interpolation is NOT used, Then USE the conservative boron value which corresponds to a smaller core burnup.
- 4.
ENTER this value on line 60.
E.
DETERMINE the Required Boron Concentration by adding lines 6C and 60.
- 1.
ENTER the result on line 6E.
- 2.
ENTER zero if the sum is negative.
Shutdown Margin Verification:
A.
ENTER the present RCS boron concentration on line 7 A.
- 1.
This value should be the result of a chemistry analysis.
B.
Line 7 A greater than or equal to line 6A assures conformance with applicable Technical Specifications.
END OF SECTION 6.1
REVISION NO.:
PROCEDURE TITLE:
1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:
MARGIN; MODES 2,3,4 AND 5 (SUBCRITICAL)
- 1.
2-NOP-100.04 ST. LUCIE UNIT 2 DATA SHEET 1
/:"c;:i:.c:;\\
SHUTDOWN MARGIN VERIFICATION FOR MODE 2 (SUBCRITICAl)
(Page 1 of 1)
NOTE The purpose of the Data Sheet is to ensure the Shutdown Margin for subcritical Mode 2 operation is determined in compliance with Surveillance Re uirement 4.1.1.1.1.c.
Time ___ Date ___ of present Mode 2 condition.
NOTE This time must be within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving criticality.
- 2.
Predicted Critical CEA Position from applicable ECC of 2-GOP-302.
Group A = _____ Group 3 = ____ _
Group B = _____ Group 4 = ____ _
Group 1 = _____ Group 5 = ____ _
Group 2 = ____ _
NOTE The Power Dependent Insertion Limit for operation at zero percent power for St. Lucie Unit 2 requires CEAs be withdrawn to at least the following configuration: Groups A, B, 1, 2 full out, Group 3 at 55 inches withdrawn and Groups 4 and 5 fully inserted.
- 3.
The predicted critical CEA position of Step 2 is within the limits of St. Lucie Unit 2 Technical Specification 3.1.3.6 and was verified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving critical ity.
Verified By (RCO)
Performance of the above asterisked (*) steps assures compliance with the applicable Technical Specification.
I have reviewed the requirements of this procedure including other surveillances performed during this procedure, if any (i.e., datasheet(s), PMT sheet(s), etc.). Any deviation(s) found during the performance of this procedure has (have) been listed and appropriate actions and notifications made.
Verified By ____________ _
SM / US END OF DATA SHEET 1
REVISION NO.:
PROCEDURE TITLE:
1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:
MARGIN; MODES 2, 3, 4 AND 5 (SUBCRITICAL) 2-NOP-100.04 ST. LUCIE UNIT 2 DATA SHEET 2 t
SHUTDOWN MARGIN VERIFICATION FOR MODES 3 4 5 SUBCRITI (Page 1 of 3)
- 1.
Prerequisites, Section 3 completed.
RCa
- 2.
Precautions/Limitations Section 4.0 reviewed.
RCa
- 3.
Current Plant Conditions:
Date
/
/
Time Mode Temperature _____ oF Core Burnup ______ EFPH (DCS)
- 4.
Target Plant Conditions A.
B.
Surveillance time interval (Enter "0" if calculating for current conditions)
Minimum expected RCS Temperature during the surveillance interval
- 5.
Reactivity Components:
A.
Xenon Worth corresponding to Current Plant Conditions or the Target Plant Conditions surveillance time interval (Plant Physics Curves, Figure A.4 or the RCS screen a
Hours on DCS).
(-)2 3> PCM B.
Reactivity Deviation
( ),I ;{ '4'-' PCM (Plant Physics Curves, Figure B.3, Col. 2, observe sign)
C.
Stuck CEA D.
- 1.
If there are no actual stuck CEAs, Then ENTER O.
- 2.
If there is an actual stuck CEA, Then ENTER the stuck CEA difference between worst and second worst stuck CEA worth (Figure BA)
(+) i i q PCM Total (Lines 5A + 5B + 5C, observe sign)
REVISION NO.:
PROCEDURE TITLE:
1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:
MARGIN; MODES 2,3,4 AND 5 (SUBCRITICAL) 2-NOP-100.04 ST. LUCIE UNIT 2 DATA SHEET 2(."(,<
SHUTDOWN MARGIN VERIFICATION FOR MODES 3, 4, 5 (SUBCRITICAL)
(Page 2 of 3)
- 6.
Reactivity Balance:
A.
Reactivity Component Total ( From line 50, observe sign) f) I L~l PCM B.
Boron Worth corresponding to Current Plant Conditions or the Target Plant Conditions expected RCS minimum temperature, (ARI-1) (Plant Physics Curves, Figure B.5) (+) g. I r PCM/PPM C.
Reactivity Component Total: Equivalent Boron Worth in PPM (Line 6A.;.. 6B, observe sign)
H I ~ ~ PPM O.
E.
Shutdown Boron Concentration (Plant Physics Curves, Figure B.6, B.7** or B.8)
Required Boron Concentration (Line 6C+60, observe sign)
(+)/2';'1 PPM (of) I ~ q k PPM
- Figure B.7 may only be used when calculating the shutdown boron requirements for Modes 2 to 3 with Tavg greater than or equal to 515°F.
REVISION NO.:
PROCEDURE TITLE:
1 SURVEILLANCE REQUIREMENTS FOR SHUTDOWN PROCEDURE NO.:
MARGIN; MODES 2, 3, 4 AND 5 (SUBCRITICAL) 2-NOP-100.04 ST. LUCIE UNIT 2 DATA SHEET 2 SHUTDOWN MARGIN VERIFICATION FOR MODES 3. 4. 5 (SUBCRI (Page 3 of 3)
CAUTION
§1 if the measured RCS boron concentration is lower than the required boron concentration for current plant conditions, Then immediate boration is required per Technical Specifications.
- 7.
Shutdown Margin Verification A.
Present RCS Boron Concentration (Chemical Analysis) Sample Time __ : __ Date __ I __ I __
- B.
Present Boron Concentration is greater than or equal to the required Boron Concentration (Line 7 A greater than or equal to Line 6E).
Verified by RCO __________ _
Performance of the above asterisked (*) steps assures compliance with the applicable Technical Specification.
I have reviewed the requirements of this procedure including other surveillances performed during this procedure, if any [i.e., datasheet(s), PMT sheet(s), etc.]. Any deviation(s),
abnormal results, equipment problems, failures, or human performance issues must be documented via a Condition Report.
C.R. # ________ _
Verified by SM I US _________ _
END OF DATA SHEET 2
FLORIDA POWER & LIGHT FT NRC Admin. Exam ST LUCIE NRC LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPMA4ADM Use a Survey Map To Determine Radiological Hazards CANDIDATE EXAMINER ST LUCIE JPM A4 Page 10f4
FLORIDA POWER & LIGHT NRC Admin. Exam Use a Survey map to determine radiological hazards Examinee:
SAFETY FUNCTION ADMIN. TOPIC TESTING KIA #
ENVIRONMENT NONE Radiation Classroom 1 Simulator KIA 2.3.14 (3.4/3.8)
Control POSITION FAULTED VALIDATED TIME TIME CRITICAL (YIN)
(YIN)
ROISRO N
10 N
STANDARD:
Correctly determines radiological hazards in each Charging Pump room.
REFERENCES:
Completed HPS-207 Charging Pumps Survey Map HPP-20 Area Radiation and Contamination Surveys INITIATING CUE:
Using the Survey map determine the radiological hazards in each Charging pump room.
START TIME END TIME DURATION (minutes)
OPERATOR PERFORMANCE AS EVALUATED TO STANDARD (circle one)
SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________
DATE:
EXAMINER (print):
FLORIDA POWER & LIGHT NRC Admin. Exam
~Indicates a "critical,j step
.;;(,;
.{,
STEP STANDARD S/U
- 1.
2A Charging Pump Room
- Contaminated area
- Radiation Area
- 2.
2B Charging Pump Room Hot Spot Radiation Area
- 3.
2C Charging Pump Room High Radiation Area Contaminated Area END TIME:
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE: Using the Survey map, determine the radiological postings in each Charging pump room.
FLORIDA POWER & LIGHT - PSL HPS-207 LOCATION:
CHARGING PUMPS - EL. -.5 FT DATE:
(G) GRAVE DANGER - VERY HIGH RAD AREA
I(L)
LOCKED HIGH RADAREA (C) CONTAMINATEDAREA (P) HOT PARTICLE AREA TIME:
l(H)HIGHRADAREA RPT (PRINT)
(R) RADIATION AREA
1 (M) RADIOACTIVE MATERIAL (S) SPECIFIC RWP REQUIRED (B) H.P. COVERAGE REQUIRED RPT SIGNATURE:
(A) AIRBORNE RADIOACTIVITY AREA f3 MDA=
dpm RWP #:
(D)HIGHLYCONTAMINATEDAREA la MDA=
dpm INSTRUMENT TYPE / #
INSTRUMENT TYPE / #
INSTRUMENT TYPE / #
INSTRUMENT TYPE / #
~
/,
SMEARS IN DPM / 100 eM 2 1 2 I'::' I tI a 6 '" 1 1(..1,.)(1111 "I 16 I
21 2 < I ~/
7" I 12 V 17 V 22 34 JICI 8
"x 13 l'.......
18 A
23 4 <t I< I
\\ II 9 1'\\
14 I
'\\.. 19 I
24 5~//4 10 I
\\
15 1\\0 I
\\.25 LEGEND:
=
General Area Dose Rates
=
Contact Dose Rate o = Smear Location t:"
=
Neutron Dose Rate (mremlHr DOE) o
=
Beta Radiation in mRadlHr
=
Radiation / Contaminated Boundry Print Name
~-<..1 __ 2 I
V 27 ~/
J'...... 28 X-I
~ /\\
I 30\\
I
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Reviewed By:
Signature ALI
- A (JmG." IN MRlHR UNLESS OTHERWISE N TED
==
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Hot Part.
No 1 probe area y / N A 4)l<..
IV B I.........
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G
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c:>=J ~ c::l ~ I*
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0 0
1lIil" 2 A CHSRGING PUMP
==-
S 2 OPS DATE ____
Exposure Received Completing Survey: __ 2 __ mrem.
DOCT HPS REMARKS:
DOCN _H_P-,,-S-,--2...:...07~_
SYS HP COMP ____
ITM
r:: o
+=ic 19Q) r:: E Q) ::J E u
- J 0
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Z"Co..J QQ)x <<
Z g'~ f=
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0:::.Q 8 Q.~ til U. Q)..r::
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Title:
ST. LUCIE PLANT HEALTH PHYSICS PROCEDURE NON-SAFETY RELATED REFERENCE USE 05/16/08 AREA RADIATION AND CONTAMINATION SURVEYS Responsible Department: HEALTH PHYSICS REVISION
SUMMARY
Revision 27 - Incorporated PCR 08-2234 to change Hot Spot posting criteria. (Jeffrey Brown, 05/16/08)
Revision 26 - Incorporated PCR 07-3462 for CR 07-17108,07-32549, CR 05-25359, CR 07-7637 to establish when to document dose gradient surveys, implement Tennelec scaler counting, and correct inconsistent posting standards for large areas I buildings.
(Dewayne Taylor, 10/11/07)
Revision 25A -Incorporated MC 07-3034 to change Form HPP-20.1 SOPS stamp to DOCT:
Checklist. (Karen Shepard, 09/17/07)
Revision 25 - Incorporated PCR 06-4329 for CR 2005-23159 to add appendix for the installation, monitoring and removal of catch containments and plastic tubing. (Jeffrey Brown, 12/15/06)
Revision 248 - Incorporated PCR 06-2002 to clarify expectation to indicate postings on survey form and clarify guidance to obtain smear if Masslinn is >50K DPM I probe area. (John Neu, II, 06/13/06)
Revision 24A - Incorporated PCR 06-0278 to clarify the expectation to utilize a comprehensive survey prior to initiating a posting change. Page 18 and 27 include the change. (John Neu II, 02/02/06)
Revision FRG Review Date Approved By Approval Date S_ OPS 0
12/16/93 C. L. Burton 12/16/93 DATE Plant General DOCT Revision FRG Review Date Approved By Approval Date DOCN 27 N/A SYS Plant General Manager COM Mark Moore 05/16/08 ITM Authorized Approver N/A Authorized Approver r Correction)
,ncC''LII'II NO.:
27 IPR()cEIDURE NO.:
HPP-20 SECTION AREA RADIATION AND CONTAMINATION SURVEYS ST. LUCIE PLANT TABLE OF CONTENTS 1.0 PURPOSE............................................................................................................... 3
.0 REFERENCES........................................................................................................ 4
.0 PREREQUISITES................................................................................................... 5
.0 PRECAUTIONS I LIMITATIONS............................................................................. 5
.0 RECORDS REQUIRED.......................................................................................... 7
.0 INSTRUCTIONS..................................................................................................... 8 6.1 GeneraL........................................................................................................ 8 6.2 Beta I Gamma Loose Surface Contamination Surveys.............................. 11 6.3 Alpha Loose Surface Contamination Surveys............................................ 13 6.4 Beta Radiation Surveys.............................................................................. 14 6.5 Recording of Survey Information................................................................ 15 6.6 Requirements Based on Survey Results.................................................... 16 6.7 Guidelines for Posting of Very High Radiation Areas, High Radiation Areas, Radiation Areas and Contaminated Areas...................................... 18 6.8 Multiple Postings........................................................................................ 21 6.9 Yard Sump Surveys.................................................................................... 22 6.10 Survey of Hot Tool Room........................................................................... 23 6.11 Maintenance hot shops located within the RCA shall be surveyed in accordance with the requirements of Section 6.1 0.1.A thru 6.10.1. E......... 24 6.12 Post Reactor Trip Surveys.......................................................................... 25 FORMS HPP-20.1 HIGH RADIATION AREA POSTINGS CHANGE CHECKLIST.................. 26 APPENDIXES DIX A INSTALLATION, MONITORING, AND REMOVAL OF CATCH CONTAINMENTS AND PLASTIC TUBING.......................................... 27
SION NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 1.0 PURPOSE 1.1 This procedure provides guidelines for the performance of Radiation and Contamination Surveys.
1.2 Discussion
- 1.
Contamination Surveys A.
Contamination surveys are taken by qualified Health Physics personnel to determine the location and magnitude of known or potential contaminated areas, to ascertain trends in radiological conditions, to determine the need for respiratory protection and to determine radiological controls including dress requirements for working in an area.
Routine surveys of areas and locations within the protected area are performed to ensure that contamination does not exist in normally uncontrolled locations. Surveys are performed within the radiation controlled area so that the status of each location is known with reasonable accuracy.
- 2.
Radiation Surveys A.
Radiation Surveys are taken by qualified Health Physics personnel to determine the location and intensity of known or potential radiation areas, to ascertain the dose rate trends in radiological conditions, to allow for maintaining ALARA personnel dose and to determine radiological controls required for an area.
B.
Many of the plant's portable survey instruments display the radiation levels in units of mr/hr or R/hr. For the purposes of this procedure a reading of 1 mr/hr = 1 mrem/hr and a reading of 1 R/hr = 1 Rem/hr.
- 3.
§3,4 Routine Periodic Radiation and Contamination Surveys are performed on a schedule as specified in Procedure HPP-4, Scheduling of Health Physics Activities.
REVISION NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 1.2 Discussion (continued)
- 4.
Special Radiation and/or Contamination Surveys are taken:
A.
In areas and/or on equipment when Health Physics requires the information (e.g. potentially contaminated equipment).
B.
Upon the request of a Supervisor who may be contemplating work in an area.
C.
When an RWP is issued and the potential exists for levels which exceed values posted for the area.
D.
In any area where a spill involving radioactive material has occurred.
E.
When ARMs (Area Radiation Monitors) indicate a change in radiological conditions.
F.
When conditions in an area may change due to; the movement of radioactive liquids or gases through a system.
G.
112 When scaffold is built or a ladder installed to an area previously not accessible to personnel.
H.
As necessary for job activities with higher radiological significance (e.g., shielding activities, system draining, system breaches, hot spot flushes, transferring resin, etc.).
2.0 REFERENCES
NOTE One or more of the following symbols may be used in this procedure:
§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without the required Focus review and appropriate approval.
11 Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.
'¥ Indicates a step that requires a si n off on an attachment.
2.1
§1 10 CFR 20 2.2
§2 St. Lucie Technical Specifications Manual
2.10 2.11 2.12 2.13 2.14 2.15 2.16 2.17 2.18 2.19 2.20 27 ENO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT
§3 HP-2, FPL Health Physics Manual
§4 HPP-4, Scheduling of Health Physics Activities
§s HPP-22, Air Sampling HP-13A, Operation of Portable Survey Instruments NUREG 5569, Health Physics Position Data Base, HPPOS-036 and HPPOS Pages 52-54 St. Lucie Unit 2 UFSAR Sections 12.1.3, 12.3.2, 12.3.4, 12.5.3
§6 Condition Report Number 97-1793 1[1 America Nuclear Insurer's Audit Report Item LR 98-01 1[2 PMAI # PM 99-03-101 1[3 PMAI # PM 99-03-102 1[4 PMAI # PM 99-08-083 HP-71, Decontamination of Tools, Equipment and Areas 1[s PMAI # PM 99-04-157 1[6 PMAI # PM 99-11-120 1[7 Condition Report number 00-1376 1[8 Condition Report number 01-1365 Condition Report number 02-0244
§7 Condition Report number 02-2715 3.0 PREREQUISITES None 4.0 PRECAUTIONS I LIMITATIONS 1
Smears should be separated to prevent cross contamination.
NO.:
27 PROCEDURE NO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 2
Protective clothing shall be worn during performance of surveys as applicable Radiation Work Permit or based on contamination levels cvr'C"Tcn areas to be surveyed.
3 Under certain circumstances, to assist the Health Physics technician, it is acceptable for personnel other than a Health Physics technician to take smears for the evaluation of contamination levels. This process will take place only under the direction and observation of a qualified Health Physics technician, and approved by the H.P.S.S.
§6 Prior to use, survey instruments shall:
- 1.
Bear a valid calibration sticker
- 2.
Pass a battery check
- 3.
Pass a daily response source check as described in Ref 2.6
.5
§3 Copies of Radiation and Contamination Surveys are available for all plant personnel and should be located at the Unit 1 and Unit 2 access control point area. Other areas may be established by the HPSS for special projects, outages, etc., as necessary.
4.6 Locked high radiation areas where general area radiation levels exist at levels in excess of 1 Rem/hr at 12 inches (30 cm) from the radiation source should only be surveyed when approved by the Health Physics Supervisor or designee.
4.7 If unexpected high radiation levels are encountered, notify Health Physics Supervision and restrict access to the area.
4.8 For the purpose of undress, a step-off pad should be considered clean. Any step-off pad found to be contaminated should be replaced with a clean one or deconned.
4.9
,-r6 When setting up an undress area step-off pad, check the immediate area for hazards that could possibly injure an individual and to ensure adequate space for the proper removal of protective clothing. It may be necessary to move a few feet to a safer area with more space for the undress step-off pad.
4.10 Smears (or packs of smears) should be screened with a frisker prior to counting on Count Room instrumentation.
11 Smears (or packs of smears) reading >50,000 cpm should not be counted on Count Room instrumentation.
12 Used step-off pads are potentially contaminated and could become a source of transferable contamination.
ION NO.:
27 HPP-20 PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS ST. LUCIE PLANT Restricted areas established within controlled areas shall be surveyed in accordance with this procedure.
§6 All radiation and contamination levels shall be documented.
111 Routine radiation surveys performed outside the Radiation Controlled Area (RCA) should be performed using a Micro-R Meter.
- 1.
111 The Radiation Protection Manager should be informed of dose rates in areas outside the RCA that are equal to or greater than 50 microR/hr.
16 115,8 Additional Hot Spot postings (stickers) shall not be affixed directly on stainless components. The adhesive in some of these stickers contains halogens (i.e., chlorides) that may result in degradation on the component.
RECORDS REQUIRED Completed survey forms are QA records and shall be maintained in the plant files in accordance with QI-17 -PSL-1, Quality Assurance Records.
5.2 117 HPP-20.1, High Radiation Area Postings Checklist shall be used and completed when areas are re-posted due to changing dose rates.
27 PROCEDURE NO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT INSTRUCTIONS NOTE This section provides general guidance and fundamentals for performing surveys. Though individual techniques vary, surveys shall be sufficiently detailed to determine the relative radiological conditions of the area while maintaining dose ALARA HPSS signature review on the survey form verifies the ade uac of the surve.
1 General
- 1.
Health Physics personnel should plan the survey by reviewing previous surveys, obtaining required materials, maps, instruments, etc. and dress out in the required protective clothing.
NOTE During the first seven (7) days of each month a comprehensive survey will be performed for each location designated as a "weekly" survey.
Depending on dose rates in these areas the Radiation Protection Manager may declare an area an "ALARA Trending Area". For the remainder of the month the weekly survey will be abbreviated. Waist level dose rates will be taken at predetermined locations and compared to the comprehensive survey taken during the first week. Stickers on the floor identify survey locations.
A.
The purpose of a DAILY survey is to determine general trends and detect any significant changes in frequently occupied area. Enough survey points should be included to satisfy this purpose.
B.
In general, WEEKLY surveys are normally required in areas that are not occupied as frequently as those that are surveyed daily. Enough survey points should be included to verify the area posting.
C.
When performing surveys for RWPs the radiological conditions of the specific area that will be worked (e.g. pump, valve, motor, etc.) must be determined. Enough survey points should be included to determine if additional dosimetry, relocation of dosimetry or other controls are needed.
NO.:
27 NO.:
PROCEDURE AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 1
General (continued)
- 2.
When performing surveys RP personnel should consider the following:
A.
ENTER survey areas with the instrument set on a scale appropriate for the expected radiation levels. If levels are unknown, then consider placing the instrument on the highest anticipated scale and adjust as necessary.
B.
HOLD the instrument extended in front of the body and ENTER the area with the instrument first.
C.
EVALUATE the area for known and potential sources (pipes, elbows, valves, penetrations, spills, low points, hot spots, etc.).
D.
DETERMINE general area (>30 cm from surfaces) dose rates between the head and the knee.
NOTE If the Deep Dose Equivalent (DDE) dose rates in the general area exceed 100 mRem/hr AND the anticipated work area DDE make it likely that some portion of the whole body shall exceed the chest dose by more than 50%,
relocation of the dosimet shall be evaluated.
E.
DETERMINE dose gradients between the head, waist and knee when conditions meet dosimetry relocation criteria, for initial surveys to establish a Radiation Work Permit, or when general area radiation fields (>100 mrem/hr) are originating from the overhead or floor I grating. For a specific job evaluation, DETERMINE the anticipated body position to verify personnel dosimetry location is adequate.
F.
DETERMINE the dose rate (contact and 30 cm) from the largest contributing accessible radiation source(s). The highest radiation levels should be located for posting purposes and HOT SPOT identification, when applicable.
G.
~3 When performing comprehensive surveys, ENSURE all areas in a room accessible to personnel are surveyed; scaffolds, platforms or ladders.
SION NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 1
General (continued)
- 3.
Record information on survey maps and forms as soon as practical. Survey nomenclature on maps and forms should be as follows:
A.
Numbers representing mrem/hr general area dose rate are underlined for gamma, boxed for beta, within a triangle for neutron.
B.
Numbers representing mrem/hr contact dose rate are indicated by an asterisk or star next to numbers underlined, boxed or within a triangle, as appropriate.
C.
Levels of removable contamination in dpm/100cm2 should be indicated by circled numbers for smear locations.
D.
Units of Rem/hr or additional pertinent nomenclature shall be clearly indicated on maps or forms.
- 4.
Postings and updating should be noted on the survey maps and forms before the maps are approved. Outdoor postings should be checked for proper colors and fading due to sun.
- 5.
Personnel performing surveys are responsible for:
A.
Initiating radiological controls as indicated by the survey results.
B.
Completing and signing the survey forms prior to the end of the shift, if time permits.
C.
Routing the original survey to the Health PhYSics Shift Supervisor for review and approval.
D.
Placing the completed survey in the completed surveys box during non-outage operation.
E.
Notifying the Health Physics Shift Supervisor when changes to postings were made.
- 6.
A Health Physics Shift Supervisor is responsible for reviewing and approving the adequacy of completed survey forms.
A.
Copies of approved surveys shall be available for plant personnel to review prior to entering the RCA.
END OF SECTION 6.1
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27 PROCEDURE NO.:
TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 6.2 Beta I Gamma Loose Surface Contamination Surveys
- 1.
Perform a smear survey. Each smear survey should cover approximately 100cm2 (4 inches x 4 inches) or an 18" swipe(s).
- 2.
Mark each smear for identification so that the survey location can be documented on the survey map.
- 3.
Suitable precautions (i.e. lay down masslinn, tape, etc.) should be taken when counting smears from a contaminated area with counting room instrumentation.
- 4.
§6 When counting smears on portable survey equipment from areas or equipment that is potentially contaminated or suspected of having low levels of contamination (1 K-2K dpm/1 00 cm2), COUNT the smears for approximately 15 seconds.
- 5.
§6 When counting gross masslinn smears from areas or equipment that is potentially contaminated or suspected of having low levels of contamination (1 K-2K dpm/1 00 cm2), COUNT the gross masslinn smears in the following manner:
A.
Survey the masslinn with the probe at a distance of one-half inch or less from the surface of the masslinn.
AND B.
Move the probe across the surface of the masslinn at a rate of less than 2 inches per second.
AND C.
1f an increase in the count rate is noted, Then allow the meter reading to stabilize for approximately 15 seconds.
D.
1f masslinn is ~ 50K dpm I probe area resurvey with smears.
27 PROCEDURE NO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCI E PLANT 6.2 Beta / Gamma Loose Surface Contamination Surveys (continued)
- 6.
Gross Masslinn smears are to be used on the Daily Surveillance routine.
A.
Each smear shall cover the entire clean area as defined on map of the Daily Surveillance form.
B.
If masslinn <1000 dpm/probe area it shall be considered clean.
C.
If masslinn is 21000 dpm/probe area, the area shall be re-surveyed with conventional smears.
D.
Smears should be counted with Tennelec, L-2000 or suitable scaler.
If any beta / gamma contamination level is found to be >200 dpm /
100 cm2, the specific area should be deconned or cleaned.
- 7.
Gross masslinn smears may be used to perform post-decontamination surveys, or routine surveys in clean areas. In order to be considered clean, the masslinn must be less than 100 corrected counts per minute per probe area (or <1000 dpm / probe area).
- 8.
Special survey consideration should be given to overhead components and systems, which are accessible to personnel without climbing.
- 9.
For routine surveys, approximately 20% of smears or masslinns should be taken other than on the floor (for example - hand rails, pipes, supports, phones, etc.). Vertical and horizontal surfaces and equipment should be considered.
- 10.
When performing contamination surveys, special consideration should be given to the clean side of contamination area boundaries. Including step off pads.
- 11.
During comprehensive contamination surveys, any catch containments setup to collect leakage from radioactive systems in the area should be surveyed to ensure contamination is contained. Containments with internal contamination levels> 100,000 dpm should be replaced.
- 12.
If directed by RP Supervision when Electron Capture contamination (e.g.,
Zn-65, Mn-54, Co-58, Cr-51) is suspected to be the major isotopic contributor, PERFORM a gamma spectroscopy analysis on at least 10% of the smears. FORWARD a copy of the contamination survey and isotopic results to the RP Technical Supervisor for evaluation.
END OF SECTION 6.2
NO.:
27 NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 6.3 Alpha Loose Surface Contamination Surveys
- 1.
If a smear survey indicated beta/gamma activity greater than or equal to 50,000 dpm/100 cm2, analyze one of the highest activity smears, (greater than or equal to 50,000 dpm/1 00 cm2 ) for alpha activity.
A.
Log the alpha results in the alpha log book located in the counting room.
- 2.
Record the results of the alpha activity analysis on the survey form along with the identification of the instrument that counted the smear.
- 3.
Analyze smears using a zinc sulfide detector system if available. A counting time of 1 minute is an acceptable counting time.
NOTE A gas flow proportional counter may be used if care is exercised to prevent contamination of the countin chamber.
- 4.
§5 If alpha activity in excess of 100 dpm/100 cm2 is found in an area where work is in progress, notify the HPSS and take an alpha air sample in accordance with Health Physics Procedure, HPP-22, Air Sampling.
END OF SECTION 6.3
27 PROCEDURE NO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 6.4 Beta Radiation SUNeys
- 1.
Beta Radiation sUNeys should be performed when:
A.
Initially breaching a primary system, OR B.
Areas of work where beta I gamma contamination levels could be present in excess of 500,000 dpm/100 cm2
- 2.
Obtain a suitable beta sUNey instrument. An ion chamber with a beta window (RO-20 or equivalent) are normally used for beta sUNeys.
- 3.
Take an open WINDOW and closed WINDOW reading as close to the SOURCE as practical. Do not contaminate the instrument by touching it to the SOURCE.
- 4.
Calculate beta dose rate using the following equation:
beta dose rate = mrad/hr or Rad/hr =
(open window reading - closed window reading) x (CF)
- where, CF = the beta correction factor of the sUNey instrument END OF SECTION 6.4
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT Recording of Survey Information NOTE Scalers shall have an MDA <200 dpm (beta I gamma) or <20 dpm (alpha) to be suitable for use for clean area smears. MDA for friskers is N/A.
- 1.
If using the Tennelec, L-2000 or other suitable scaler for contamination, RECORD the MDA. ENSURE the MDA value meets the required limits.
MDA for friskers is N/A.
- 2.
Removable surface contamination results for disc smears should be recorded in dpm I 100 cm2.
A.
If using a scaler and the value is less than the calculated MDA, activity levels may be recorded as <MDA.
B.
If using a frisker for beta I gamma levels and the value is less than 1000 dpm, levels may be recorded as <1000 dpm I probe area.
C.
Other acceptable units include CCPM or NCPM for activity, and Probe Area for measured area.
- 3.
Removable surface contamination results for Large Area Smears (Wipes) should be recorded in dpm I probe area.
A.
If the value is less than 1000 dpm, levels may be recorded as
<1000 dpm I probe area.
B.
Other acceptable units include CCPM or NCPM per probe area.
- 4.
Fixed surface contamination measured by frisker should be recorded as CCPM or NCPM.
- 5.
Beta I gamma activity levels that approach or exceed the capability of a frisker may be recorded in mrad/hr or Rad/hr if using an ion chamber (RO-20 or equivalent).
END OF SECTION 6.5
27 PROCEDURE NO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT Requirements Based on Survey Results
- 1.
Radiation Areas A.
§1,3 Any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 5 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 12 inches (30 cm) from the radiation source or from any surface that the radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, RADIATION AREA.
B.
§1,2,3 Any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 100 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 12 inches (30 cm) from the radiation source or from any surface that the radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, HIGH RADIATION AREA, SPECIFIC RWP REQUIRED. Additionally, the area shall have access control requirements established in accordance with the applicable Technical Specifications.
C.
§2,3 Any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 1,000 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 12 inches (30 cm) from the radiation source or from any surface that the radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, CAUTION, LOCKED HIGH RADIATION AREA, SPECIFIC RWP REQUIRED, HP COVERAGE REQUIRED, Additionally, the area shall have access control requirements established in accordance with the applicable Technical Specifications.
D.
§1,2,3 Any area, accessible to individuals, in which radiation levels could result in an individual receiving an absorbed dose in excess for 500 rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 1 meter from the radiation source or from any surface that the radiation penetrates shall be posted with a conspicuous sign bearing the radiation symbol and the words, GRAVE DANGER, VERY HIGH RADIATION AREA, SPECIFIC RWP REQUIRED, HP COVERAGE REQUIRED. Additionally, the area shall have access control requirements established in accordance with 10 CFR 20.
- 2.
Surveys, postings and placards are not required in overhead areas, unless made accessible by ladders or scaffolding.
ION NO.:
27 RENO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT
.6 Requirements Based on Survey Results (continued)
NOTE
,-r5,8 Hot Spot stickers shall not be "stuck" directly on stainless steel components. Some adhesives contain halogens (i.e., chlorides) that may degrade the component. Alternate means of Hot Spot postings are to be utilized to identify Hot Spots. The recommended method is to affix the Hot Spot sticker to a yellow plastic CAUTION sign attached to the component with Rad rope or ribbon.
- Hot Spots need not be identified for areas not routinely accessed or for areas accessed only during outages, unless otherwise directed by RP Su ervision.
- 3.
§3 A component or item having a contact reading greater than 100 mrem/hr and more than 5 times the general area radiation levels (i.e. 30 cm from contact) should be posted as a HOT SPOT. The Hot Spot Log should be updated monthly upon completion of the comprehensive surveys.
- 4.
§1 The boundary of the Radiation Controlled Area shall be maintained at less than 2 mrem/hr. If the radiation levels outside the RCA are found to be greater than 2 mrem/hr, barricade and post the area and take action to reduce the radiation levels to less than 2 mrem/hr.
- 5.
Contamination Areas A.
Any area containing removable surface contamination in excess of 1000 dpm/1 00cm2 beta/gamma or 20 dpm/1 00cm2 alpha shall be posted as a Contaminated Area.
B.
Any area containing removable surface contamination in excess of 100,000 dpm/100cm2 beta / gamma should be posted as a Highly Contaminated Area.
C.
Exits from contaminated areas require as a minimum, a single step-off pad placed on the CLEAN side of the access point for the area.
D.
Areas in which contamination exists over a major portion of the area in excess of 100,000 dpm/100cm2 may require a double step-off pad.
E.
Replace step-off pads between areas of higher and lower contamination levels at a frequency determined by contamination surveys.
F.
Restricted areas established in the controlled area shall be surveyed and posted in accordance with the requirements of 6.6.1 above.
END OF SECTION 6.6
NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 7
Guidelines for Posting of Very High Radiation Areas, High Radiation Radiation Areas and Contaminated Areas NOTE
§7 Prior to changing the level of postings on High Radiation, Locked High Radiation or Very High Radiation Areas, (unless excepted in Step 6.7.6), an HPP-20.1 High Radiation Area Postings Change Checklist shall be completed for each posting change.
When performing independent verification of posting changes, the survey used to perform the posting change is to be used in verifying the change is correct. The survey shall be comprehensive and specifically erformed to su ort the ostin chan e.
§7 The posting of areas in this paragraph are intended as an aid to technicians performing surveys and supervisory personnel in reviewing the posting of areas based on survey results. Independent verification of posting changes is a very important tool to ensure regulatory requirements are met for posting and control of high radiation areas. It is essential that the PSL Health Physics Department confirms any changes to High Radiation Areas, Locked High Radiation Areas, and Very High Radiation Areas. Verification of proper posting and control of these areas fulfill requirements in PSL Tech Specs and 10CFR20. In addition, establishing regulation and Tech Spec required postings is considered an irreversible act which once completed inaccurately could cause unplanned personnel exposures and violations of regulations.
- 1.
Very High Radiation Areas ALL areas qualifying as Very High Radiation Areas shall be posted as, Grave Danger, Very High Radiation Area, Specific RWP Required, HP Coverage Required, at the entrance to the area or on the barrier erected to prevent access to the very high radiation area. An example is the Reactor Containment Building during power operation.
- 2.
Locked High Radiation Areas All areas qualifying as locked high radiation areas shall be posted as Locked High Radiation Area, HP Coverage Required and Specific RWP Required.
The focus of this posting is to post at the entry point of the room or area where positive access control can be provided.
27 NO.:
r.v"C:;""'Jr.", TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT
.7 Guidelines for Posting of Very High Radiation Areas, High Radiation Radiation Areas and Contaminated Areas (continued)
NOTE
§7 Prior to changing the level of postings on High Radiation, Locked High Radiation or Very High Radiation Areas, (unless excepted in Step 6.7.6),
an HPP-20.1 High Radiation Area Postings Change Checklist shall be com leted for each ostin chan e.
- 3.
High Radiation Areas Where possible, discrete high radiation areas in rooms should be barricaded to define the boundaries of the high radiation area and these boundaries should be posted as a High Radiation Area and Specific RWP Required.
Examples of this type of area posting are the reactor head lay down area, bottom of the Safety Injection Tanks on the 43' elevation of Unit 1, reactor drain tank pump strainers and local areas within the pipe penetration rooms and pipe tunnels.
In certain instances the radiation levels within an area may make posting of discrete high radiation areas confusing to workers or impractical to control.
It is acceptable to post an entire area as a High Radiation Area, Specific RWP Required.
- 4.
Radiation Areas Radiation Areas shall be posted in such a manner that anyone entering the area will need to pass within sight of a Radiation Area posting. The posting of discrete areas within the RCA is more effective in alerting workers of the radiological conditions in the area, and should be employed whenever possible.
As in the case of high radiation areas, instances arise in which posting of discrete radiation areas becomes confusing to workers or impractical to control. It is acceptable to post the entrance to the area.
NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 7
Guidelines for Posting of Very High Radiation Areas, High Radiation Radiation Areas and Contaminated Areas (continued)
- 5.
Contaminated Areas Contaminated Area barriers and postings should be used to provide workers information and to restrict inadvertent entries. It is desirable to optimize the size of the Contaminated Area footprint to allow sufficient space for work crews to complete maintenance or repairs. Posting an entire room, in lieu of the specific area involved is discouraged.
Minimizing Contaminated Area footprint minimizes the need for protective clothing, the generation of radioactive waste and helps to maintain the plant exposures ALARA. Repetitive tasks that require Contaminated Area boundaries (e.g., charging pump valve and plunger work, check valve overhauls and other primary system breaches) should be evaluated prior to posting to verify that engineering and process controls are used to prevent the area from becoming contaminated.
Some areas will require postings at entries and exits. Both Reactor Containment Buildings, the Unit 1 Decon Room and the two Cask Wash buildings are examples of completely posted areas. They are not generally conducive to limited postings due to the scope of work and difficulty of maintaining areas as clean. Some rooms, such as the ECCS equipment rooms, Pipe Tunnels and Pipe Penetrations, are usually posted as Contaminated Areas only during outages, when major work activities are taking place.
S.
Reactor Containment Building (during outages)
NOTE Dose rates in the RCB are less than 500 Rads/hr when the reactor is shut down (i.e., < 5E-4 % power). Neutron flux and high energy gamma radiation from N-16 are assumed to be negligible.
Reactor Containment Buildings may be down posted from Very High Radiation Areas to Locked High Radiation Areas immediately upon reactor shut down. Reactor shut down shall be verified by contacting the affected unit's control room. This down post of containment will not require completion of an HPP-20.1.
- 7.
Steam Generators Steam generator openings, (manways and hand holes) do not require the completion of an HPP-20.1, when down posting after reinstallation of strong backs.
END OF SECTION S.7
SION NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT Multiple Postings NOTE NRC required postings are Caution or Grave Danger with the magenta, purple, or black three bladed radiation symbol on a yellow background, together with following applicable designations:
Radiation Area High Radiation Area Very High Radiation Area Airborne Radioactivity Area Radioactive Materials Informational postings include HOT SPOT, SPECIFIC RWP REQUIRED, HEALTH PHYSICS COVERAGE REQUIRED FOR ENTRY, and other similar inserts used to alert the worker to specific area requirements.
Informational Postings will normally be posted at the personnel access oint Doors, Ste off Pads, etc..
- 1.
When multiple postings are needed, Then place the NRC required postings first, followed by any PSL specific informational postings. The general order of multiple postings inserts should be:
A.
Radiation Area, High Radiation Area, Locked High Radiation Area, or Very High Radiation Area B.
Airborne Radioactivity Area C.
Radioactive Material(s)
D.
Contaminated Area E.
Any additional informational inserts END OF SECTION 6.8
REVISION NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT 6.9 Yard Sump Surveys
- 1.
~4 Contamination surveys of the U-1 and U-2 ECCS Yard Sumps are required; frequency is defined in HPP-4. This allows Operations to pump these sumps as required to ensure the ECCS piping supports are not standing in water.
A.
In the event contamination is found during this survey, post the area accordingly.
B.
Notify the applicable Control Room not to pump the sump to the storm drains.
C.
Notify HP Supervision as soon as possible.
D.
Decontamination of the area will proceed as soon as possible in accordance with procedure HP-71, Decontamination of Tools, Equipment and Areas.
END OF SECTION 6.9
NO.:
27 ENO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT
.10 Survey of Hot Tool Room
- 1.
The Hot Tool Room is divided into four sectors. A detailed survey should be performed on one sector. The sectors surveyed should rotate to allow the entire tool room to be surveyed monthly.
A.
Open drawers and tool boxes in the selected sector.
B.
Scan tools with frisker.
C.
If there are layers of tools in drawers or box, remove the top ones to ensure tools are checked, replace tools after surveying.
D.
Smear the tools with the highest readings discovered during the frisk.
E.
Frisk the inside of the drawers and toolboxes along with the storage shelves.
F.
Tools or components with smearable contamination shall be contained (i.e., bagged) and tagged and taken to a designated decon facility.
G.
Tools or components with fixed contamination levels exceeding 20K DPM on a direct frisk should be segregated from the tools for re-issue.
H.
When tools or components surveyed in the Hot Tool Room exceed the above limits notify the HPSS.
- 2.
A general area survey of the entire Hot Tool Room should be performed on a weekly basis.
END OF SECTION 6.10
REVISION NO.:
27 PROCEDURE NO.:
HPP-20 PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS ST. LUCIE PLANT 6.11 Maintenance hot shops located within the RCA shall be surveyed in with the requirements of Section 6.10.1.A thru 6.10.1.E.
END OF SECTION 6.11
27 PROCEDURE NO.:
HPP-20 AREA RADIATION AND CONTAMINATION SURVEYS ST. LUCIE PLANT 12 Post Reactor Trip Surveys
- 1.
After a Reactor Trip. Perform and Document ALARA Trending Surveys in the following areas. Surveys should be started within one half hour of reactor trip.
A.
VCT B.
Pipe Penetration C.
Pipe Tunnel.
D.
LPSI Pumps E.
HPSI Pumps F.
Containment Spray Pumps G.
Shut Down Host Exchangers
- 2.
Upon completion of Surveys, Advise the HPSS I Duty Call Supervisor of any posting changes or abnormal radiological conditions.
END OF SECTION 6.12
'CV'.:"l'U NO.:
PROCEDURE TITLE:
27 IPROCIEDlJRE NO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT HPP-20.1 HIGH RADIATION AREA POSTINGS CHANGE CHECKLIST (Page 1 of 1)
Area LocationlDescription: _________________________ _
Area Posted From I
Area Posted To Radiation Area Radiation Area High Radiation Area High Radiation Area Locked High Radiation Area Locked High Radiation Area Very High Radiation Area Very High Radiation Area o Survey map(s) attached is comprehensive and specifically performed to support the posting change.
Survey and Posting Performed by:
Independent Posting Verification Performed by:
HP Supervision:
Print & Sign Print & Sign Print & Sign FOR INFORMATION ONLY This document is not controlled. Before use, verify information with a controlled document.
DATE VERIFIED __ 1 __ 1 __
INITIAL END OF HPP-20.1 Date & Time Date & Time Date & Time S_OPS DATE ____
DOCT CHECKLIST DOCN HPP-20.1 SYS HP COMP ____ _
ITM. _____
I
REVISION NO.:
27 PROCEDURE NO.:
HPP-20 PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS ST. LUCIE PLANT APPENDIX A INSTALLATION, MONITORING, AND REMOVAL OF CATCH CONTAINMENTS AND PLASTIC TUBING (Page 1 of 8)
NOTE
- To ensure and prevent the unintended release of contamination to the floor or to groundwater catch containments are utilize at PSL.
- The catch containments are intended to be in place for periods greater than fourteen days. Catches containment that are installed for control of liquids during a repair process need not be tracked under this Appendix.
- Attachment A is to be used as a guide to for installation, monitoring, and removal of catch containers.
1.0 RESPONSIBILITIES
- 1.
The Radioactive Material Control Supervisor is responsible for the overall maintenance of the catch containment program.
- 2.
The Radiation Protection Utility Worker Crewleader is responsible for maintaining the catch containment log book and the monitoring and surveying of selected catch containments.
- 3.
The Radiation Protection Shift Supervisor is responsible for determining the frequency of surveying of the catch containments.
- 4.
The Radiation Protection Technicians are responsible for inspecting, repairing, replacing, and surveying of catch containments while conducting routine surveys.
- 5.
The Radiation Protection Utility Workers are responsible for assisting in the repair and replacement of catch containments under the directions of the Radiation Protection Utility Worker Crewleader.
- 6.
Individuals that install catches are responsible to generate a work request (W/R) for repairs to mitigate or stop the leak and to notify the Radioactive Material Control Supervisor of the catch containment.
27 PROCEDURE NO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT APPENDIX A INSTALLATION. MONITORING. AND REMOVAL OF CATCH CONTAINMEN 2.0 PRECAUTIONS PLASTIC TUBING (Page 2 of 8)
- 1.
Ensure that the installation, use and removal of the catch containments are performed in accordance with an appropriate Radiation Work Permit.
- 2.
Be aware of leaks that may be thermally hot. Active fluid leaks with a temperature greater than 165 0 Fahrenheit shall not have a catch containment attached.
- 3.
Ensure that the installation of catch containments does not interfere with plant equipment operation or present a safety hazard.
- 4.
When removing catch containments, be aware that they may be highly contaminated and care should be exercised. Contact Radiation Protection prior to removing a catch containment.
- 5.
Ensure that catch containment hoses are routed and secured to a proper receptacle or a functional drain.
3.0 INSTRUCTIONS FOR INSTALLATION
- 1.
Determine which device and size will best control the fluid leak. Options are:
A.
Catch containment.
B.
Catch containment with Plastic tubing.
NOTE On rare occasions, a small whirl pack, plastiC bag, or plastic tubing directly run from leaking pipe to drain may be used for leak control. These alternative means are when the installment of a catch containment is not possible. These will also be tracked and inspected in accordance with this Ap endix.
- 2.
Obtain the appropriate device and a Catch Containment Inventory Tag from the storage location.
A.
Ensure that the catch containment is intact and free of rips and tears.
B.
Complete the Catch Containment Inventory Tag, similar to Figure 1, for each catch containment installation and record the information on a form similar to HPP-20 Form-1, the Catch Containment log.
NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT APPENDIX A AND REMOVAL OF CATCH CONTAINM PLASTIC TUBING (Page 3 of 8)
.0 INSTRUCTIONS FOR INSTALLATION (continued)
- 3.
Contact the appropriate control room to notify Operations of the identified leak and to inform them that a catch is being placed to control the leak.
- 4.
Install the catch containment device in a manner that will contain the fluid leak.
- 5.
Tie wraps are the preferred method for securing catch containments. Duct tape should not be used to support the weight of the containment.
CAUTION Ensure Chemist is notified prior to directin fluid to the floor drains.
- 6.
Check the condition of the floor drain for blockage.
- 7.
If plastic tubing is used, the following criteria must be adhered to:
A.
Ensure it is sloped towards the floor drain (or an approved container) to allow the fluid to drain properly. The plastic tubing should not have any kinks, constrictions, or sharp turns that would result in low points that could accumulate fluid.
B.
Plastic tubing can be no larger than 1 1/4 inch (inside diameter).
C.
Ensure that the plastic tubing is firmly fastened into the catch containment nipple. A hose clamp or Tie wrap should be use for added security.
D.
If the plastic tubing is run on the floor, then tubing must be secured to a structural component with a tie-wrap within 3 feet of the drain with noticeable slack in tubing between valve and tie-wrap.
E.
If the plastic tubing is not run on the floor, then tubing must be secured to structural components at regular intervals not to exceed a maximum spacing of 5 feet.
F.
If the plastic tubing is run along the floor, then it must be taped to the floor at regular intervals not to exceed 8 feet
27 PROCEDURE NO.:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT INSTALLATI MONITORI APPENDIX A AND PLASTIC TUBING (Page 4 of 8) 3.0 INSTRUCTIONS FOR INSTALLATION (continued)
- 7.
(continued)
G.
Plastic tubing can not be run over or next to electrical components, conduit, or junction boxes that would be adversely affected by water or any sensitive instrumentation or equipment that could cause a reactor or turbine trip.
H.
Plastic tubing can not be secured to snubbers, tubing for any system, or piping and conduit less than 1 ~ inches in normal diameter.
- 8.
Ensure that the plastic tubing does not create a tripping hazard.
NOTE Having more than two hoses actively draining at one time could cause an overload of the capacity of the floor drain.
- 9.
Ensure the end of the plastic hose is properly secured at the floor drain to prevent the unintended spillage of the fluid.
NOTE Poly drums may be use for leak containment collection when drainage to a functional floor drain is not feasible. Provisions must be made to empty the drum on a regular basis as directed by the Radiation Protection Shift Supervisor.
- 10.
Ensure that a work request (W/R) is generated for each leak and a work request (green PWO) tag is attached to the leaking component.
- 11.
Ensure the work request number is written on the Catch Containment I nventory Tag.
- 12.
Attach the Catch Containment Inventory Tag to the containment device.
REVISION NO.:
27 PROCEDURE NO.:
PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS HPP-20 ST. LUCIE PLANT APPENDIX A INSTALLATION, MONITORING, AND REMOVAL OF CATCH CONTAINME PLASTIC TUBING (Page 5 of 8) 4.0 INSTRUCTIONS FOR MONITORING CATCH CONTAINMENTS
- 1.
The Radiation Protection Technician shall monitor and survey catch containments when performing routine surveys in accordance with HPP-4.
A.
If a catch containment has failed, the following actions shall occur:
- 1.
The immediate area shall be surveyed and documented for loose surface contamination.
- 2.
The catch containment shall be repaired or replaced.
- 3.
The Radioactive Material Control Supervisor and the Radiation Protection Crewleader should be notified.
- 2.
Catch Containments that have internal contamination >100,000 dpm /
100 cm2 should be replaced.
- 3.
Catch Containments that do not fall in a frequently surveyed area (i.e.> 30 days) or could contain contaminated fluids that have the potential to leak to groundwater shall be monitored and surveyed by the Radiation Protection Crewleader. The on-shift Radiation Protection Technicians shall monitor and survey on back shifts and weekends, as required.
A.
The frequency of the survey and inspection will be determined by the Radiation Protection Shift Supervisor. This frequency shall be recorded in the Radiation Protection electronic and/or written log book and discussed at turnovers.
B.
The results of the surveys shall be recorded on the appropriate HPP-64 or HP-264 survey form with a copy forwarded to the Radioactive Material Control Supervisor.
REVISION NO.:
27 PROCEDURE NO.:
HPP-20 PROCEDURE TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS ST. LUCIE PLANT PLASTIC TUBING (Page 6 of 8) 5.0 INSTRUCTIONS FOR REMOVAL
- 1.
When the containment device is no longer needed (e.g., the leak has been repaired or the condition no longer exists), it shall be removed.
- 2.
The lead person for the repair team, or the person who determines that the catch containment is no longer needed, shall coordinate the removal.
Contact the Radiation Protection department for assistance.
- 3.
The Containment Inventory Tag shall be removed from the device and forwarded to the Radiation Protection Crew Leader, indicating that the catch containment has been removed from service.
CAUTION Used catch containments and Plastic hoses could be highly contaminated.
Exercise caution to ensure no contamination is spread during disassembly.
- 4.
The used catch containments and associated hoses should be drained of all liquids prior to discarding.
- 5.
Catch containments that were used for contaminated systems should be discarded as radioactive waste.
27 PROCEDURE NO.:
HPP-20 TITLE:
AREA RADIATION AND CONTAMINATION SURVEYS ST. LUCIE PLANT APPENDIX A INSTALLATION, MONITORING, AND REMOVAL OF CATCH CONTAINMEN PLASTIC TUBING (Page 7 of 8)
Figure 1 Front CONTAMINATION CONTROL CATCH DEVICE TAG COMPONENT DESCRIPTION (e.g. valve no., etc.)
PWONO:
DATE PLACED PLACED BY:
PROBLEM:
TAG NO.:
o Back DO NOT REMOVE TAG OR DEVICE UNLESS WASTE AND DECON FOREMAN IS NOTIFIED
REVISION NO.:
PROCEDURE TITLE:
27 AREA RADIATION AND CONTAMINATION SURVEYS PROCEDURE NO.:
HPP-20 ST. LUCIE PLANT APPENDIX A INSTALLATION, MONITORING, AND REMOVAL OF CATCH CONTAINMENTS AND PLASTIC TUBING (Page 8 of 8)
HPP-20, APPENDIX FORM-1 CATCH CONTAINMENT LOG DATE INSTALLED BY ROOM I EQUIPMENT W/R#
CATCHMENT #
INSTALLED DESCRIPTION END OF APPENDIX A DATE REMOVED
FLORIDA POWER & LIGHT FT NRC Admin. Exam ST LUCIE NRC LICENSE EXAMINATION JOB PERFORMANCE MEASURE JPMA5ADM Evaluate E-Plan Based on Loss of Annunciators CANDIDATE EXAMINER ST LUCIE JPM A5 Page 10f4
FLORIDA POWER & LIGHT NRC Admin. Exam Evaluate E-plan based on Loss of Annunciators Examinee:
SAFETY FUNCTION ADMIN. TOPIC TESTING KIA #
ENVIRONMENT NONE Emergency Classroom / Simulator 2.4.29 (4.4)
Plan POSITION FAULTED VALIDATED TIME TIME CRITICAL (YIN)
(YIN)
SRO N
15 N
STANDARD:
Determines classification of Unusual Event.
REFERENCES:
1-0NP-100.03 Partial or Complete Loss of Annunciators EPIP-01 Classification of Emergencies INITIATING CUE:
At 12:15 A.M. on Unit 1 the 1AB DC bus CKT 3 has tripped and cannot be reset. It has also been determined that Fuses F-4 and F-12 RTGB 101 KKK has blown and will not be replaced until the cause has been determined. Current time is 12:32 A.M.
As the Shift Manager, Implement 1-0NP-100.03 Partial or Complete Loss of Annunciators.
START TIME END TIME DURATION (minutes)
OPERATOR PERFORMANCE AS EVALUATED TO STANDARD (circle one)
SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________
DATE:
EXAMINER (print):
FLORIDA POWER & LIGHT NRC Admin. Exam
- indicates a "critical" step STEP STANDARD S/U
- 1.
Determine the affected annunciator panels Determines Panels A,B,C,D and M,N,P,Q,R,S affected (84.6%)
annunciators lost. (>50%)
- 2 Evaluate and implement the E-Plan as Determines> 75% of safety system required in EPIP-01 Classification of annunciators lost.
emergencies.
- 3.
Determines E-Plan classification required.
Classifies as Unusual Event based on LOSS OF ALARMS I COMMUNICATION I MONITORING. Unplanned loss of most (>75%) or all Safety System annunciators for greater than 15 minutes.
END TIME:
FLORIDA POWER & LIGHT NRC Admin. Exam INITIATING CUE:
At 12:15 A.M. on Unit 1 the 1AB DC bus CKT 3 has tripped and cannot be reset. It has also been determined that Fuses F-4 and F-12 RTGB 101 KKK has blown and will not be replaced until the cause has been determined. Current time is 12:32 A.M.
As the Shift Manager, Implement 1-0NP-100.03 Partial or Complete Loss of Annunciators.
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Title:
ST. LUCIE UNIT 1 OFF-NORMAL OPERATING PROCEDURE QUALITY RELATED CONTINUOUS USE Procedure No.
1-0NP-100.03 Current Revision No.
1C Effective Date 07/11106 PARTIAL OR COMPLETE LOSS OF ANNUNCIATORS Responsible Department: OPERATIONS REVISION
SUMMARY
Revision 1C - Incorporated PCR 05-3006 for CR 2005-18614 to add Level of Use to procedure cover page. (Helga Baranowsky, 10/07/05)
Revision 1 B - Incorporated PCR 04-2375 to redesignate procedure as "Quality Related". (J.
S. Napier, 07/23/04)
Revision 1A - Incorporated PCR 04-2068 to remove "greater than 15 minutes" from procedure step. (J. S. Napier, 07/02/04)
Revision 1 - Eliminated conflict with E-plan classification in note. (S. Oehrle, 03/07/02)
REVISION 0 - This procedure was previously issued as ONOP 1-0030137. This procedure provides guidance for resolving conditions resulting from the loss of Control Room annunciators. The actions listed are intended to be a guide in responding to the loss of annunciators and are NOT intended to be a substitute for good judgement based on plant conditions. There were no technical changes. (Steve Willett, 4/15/99)
Revision FRG Review Date Approved By Approval Date S_1_0PS 0
04/15/99 R.G. West 04/15/99 DATE Plant General Manager DOCT Revision FRG Review Date Approved By Approval Date DOCN 1C 03/07/02 R. G. West 03/07/02 SYS Plant General Manager COM N/A ITM Authorized Approver Bill Parks 10107/05 Authorized Approver inor correctio
REVISION NO.:
1C PROCEDURE NO.:
1-0NP-100.03 SECTION PROCEDURE TITLE:
PARTIAL OR COMPLETE LOSS OF ANNUNCIATORS ST. LUCIE UNIT 1 TABLE OF CONTENTS PAGE:
2of6 PAGE 1.0 PURPOSE...................................................................................................... 3
2.0 REFERENCES
............................................................................................... 3 3.0 RECORDS REQUIRED.................................................................................. 3 4.0 ENTRY CONDITIONS.................................................................................... 3 5.0 EXIT CONDITIONS........................................................................................ 3 6.0 OPERATOR ACTIONS................................................................................... 4 APPENDICES APPENDIX A SAFETY SYSTEM ANNUNCIATORS....................................... 5 APPENDIX B POWER SUPPLIES.................................................................. 6
REVISION NO.:
1C PROCEDURE NO.:
1-0NP-100.03 1.0 PURPOSE PROCEDURE TITLE:
PARTIAL OR COMPLETE LOSS OF ANNUNCIATORS ST. LUCIE UNIT 1 PAGE:
30f6 1.1 This procedure provides guidance for resolving conditions resulting from the loss of Control Room annunciators. The actions listed are intended to be a guide in responding to the loss of annunciators and are NOT intended to be a substitute for good judgement based on plant conditions.
2.0 REFERENCES
NOTE One or more of the following symbols may be used in this procedure:
§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without the required Focus review and appropriate approval.
,-r Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.
'¥ Indicates a step that requires a sign off on an attachment.
2.1 UFSAR Section 7.5.1.6.3 2.2
§1 EPIP-01, Classification of Emergencies.
2.3 CWD 8770-B-327.
2.4 Annunciator Response Procedures 3.0 RECORDS REQUIRED 3.1 RCO Chronological log.
4.0 ENTRY CONDITIONS 4.1 Plant parameters exceed alarm setpoints without annunciation.
4.2 Annunciator check indicates a complete or partial loss of annunciation.
5.0 EXIT CONDITIONS 5.1 All annunciators have been returned to operation and are functioning properly.
REVISION NO.:
1C PROCEDURE NO.:
1-0NP-100.03 PROCEDURE TITLE:
PARTIAL OR COMPLETE LOSS OF ANNUNCIATORS ST. LUCIE UNIT 1 6.0 OPERATOR ACTIONS PAGE:
4of6 INSTRUCTIONS CONTINGENCY ACTIONS
- 1. RECORD the time that annunciators were lost.
- 2.
TEST all Control Room alarm panels to determine the extent of any malfunction.
- 3.
§1 IMPLEMENT Appendix A.
- 4.
PERFORM the following:
- INCREASE the frequency of monitoring RTGB and local indications for plant equipment affected.
- Periodically EXAMINE available reflash panels on the affected annunciator panels.
- 5.
CHECK the annunciator power supplies in accordance with Appendix B.
- 6.
CONTACT I&C for trouble-shooting and repair.
END OF SECTION 6.0
REVISION NO.:
1C PROCEDURE NO.:
1-0NP-100.03 PROCEDURE TITLE:
PARTIAL OR COMPLETE LOSS OF ANNUNCIATORS ST. LUCIE UNIT 1 APPENDIX A SAFETY SYSTEM ANNUNCIATORS (Page 1 of 1)
NOTE PAGE:
The total below assumes a complete loss of an annunciator panel(s) resulting in the loss of all the safety system annunciators associated with that anel.
- 1. DETERMINE the affected annunciator panels (A, B, C, LR, etc.).
50f6
- 2. From the table below, DETERMINE the percentage of Safety System Annunciators that are lost by adding the percent of total for each affected panel.
- 3. If the percentage of safety system annunciators exceeds 50%, Then EVALUATE and IMPLEMENT the E-Plan as required in EPIP-01, Classification of Emergencies.
PERCENTAGE OF SAFETY SYSTEM ANNUNICATORS PER PANEL PANEL
% OF TOTAL A
8.6%
B 8.6%
C 0.8%
D 0.0%
E 2.3%
F 2.7%
G 3.4%
H 5.5%
J 1.3%
K 4.8%
L 6.3%
END OF APPENDIX A
- 0
REVISION NO.:
PROCEDURE TITLE:
PAGE:
1C PARTIAL OR COMPLETE LOSS 6of6 PROCEDURE NO.:
OF ANNUNCIATORS 1-0NP-100.03 ST. LUCIE UNIT 1 APPENDIX B POWER SUPPLIES (Page 1 of 1)
NOTE The neon light on the back of RTGB alarm panels indicates the DC converter is operating. After power is removed from the panel, it may be necessary to remove and replace the fuse to restart the converter.
- 1. VERIFY the following power supplies to the affected Control Room annunciators and reset as required.
RTGB ANN. PAN.
POWER SUPPLY GROUND DET.
101 A, B,C,D RTGB 101 KKK F-4, F-12 1AB DC CKT 6 GD-1 102 E, F, G RTGB 101 KKK F-3, F-111AB DC CKT 6 GD-2 103 H, J RTGB 101 KKK F-5, F-13 1AB DC CKT 3 GD-3 104 K, L RTGB 101 KKK F-6, F-14 1AB DC CKT 3 GD-4 105 M, N RTGB 101 KKK F-8, F-16 1AB DC CKT 3 GD-5 106 P,Q,R,S RTGB 101 KKK F-7, F-15 1AB DC CKT 3 GD-6 NOTE Power supply RTGB 101 KKK F-7, F-15 1AB DC Ckt. 3 also supplies seismic monitoring.
CRAC Panel Y Fuses 11 F5, 11 F7 1B DC CKT 25 CRAC Panel Z Fuses 11 F10, 11 F12 1B DC CKT 25 Rad. Monitor F-10 in Rad. Mon. Cabinet DC PP 119 CKT 1
- 2. TEST all the Control Room annunciator panels from the Control Room test panels.
- 3. TEST all the reflash modules feeding annunciators on the affected panels.
NOTE I&C Department assistance may be required.
- 4. SELECT an annunciator on each affected panel and functionally CHECK by generating the annunciator from the field.
- 5. CONTACT I&C Department to investigate and troubleshoot the problem.
END OF APPENDIX B
REVISION NO.:
15 PROCEDURE NO.:
EPIP-01 EVENT/CLASS
- 17. LOSS OF ALARMS /
COMMUNICATION /
MONITORING
- 17.
LOSS OF ALARMS /
COMMUNICATION /
MONITORING PROCEDURE TITLE:
CLASSIFICATION OF EMERGENCIES ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 18 of 21)
UNUSUAL EVENT A. §2 Significant loss of effluent monitoring capability.
communications. indication and alarm panels. etc..
which impairs ability to perform accident or emergency assessment.
Loss of effluent or radiological monitoring capability requiring plant shutdown.
OR Loss of all primary and backup communication capability with offsite locations.
OR Unplanned loss of most (greater than 75%) or all Safety System annunciators for greater than 15 minutes.
ALERT B. §2 Loss of alarms Unplanned loss of most (greater than 75%) or all safety system annunciators.
AND Plant transient in progress.
SITE AREA EMERGENCY C. Loss of alarms/monitoring Inability to monitor* a significant transient in progress.
'Monitoring means loss of ERDADS, QSPDS and/or the inability to determine anyone of the following:
reactivity control, core cooling, RCS status or containment integrity.
CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR GENERAL EMERGENCY
2600 2400 2200 2000 1800 1600 E
(,)
.e: 1400
~
.s;:
.~ 1200 co
~ 1000 800 600 400 200 o
o 1000 2000 3000 Figure A.1 Rev. 1 St. Lucie Unit 2 Cycle 17 100°;' Power
~
..... ~~
~
~
..----~
75% Power
~.
~
~~
~
---~
~
~
50% Power
~
I--
~
~
I---""
25% Power 4000 5000 6000 7000 8000 9000 10000 11000 12000 Burnup (EFPH)
[Intermediate power level data can be linearly interpolated.]
Date Of Update
_/_/~tflr
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment PSL-ENG-SEFJ-07-011 Rev. 0; Attachment 1 Page 2
Figure A.1 Rev. 1-Page 1 -of 4 St. Lucie Unit 2 Cycle 17 Power Defect (pcm) vs Burnup (EFPH)
EFPH 100%
75%
50%
25%
200 1255 945 538 321
__ 300 1"261 949 641 328 400 1267 954 644 330 500 1273' 958 647 331 600 1279 963 650 333 700 1285 967 652 334 800 1290 971 655 335 900 1295 975 657 336 1000 1300 978 659 337-1100 1304 981 661 338 1200 1308 984 663 339 1300 1312 986 664 339 1400 1315 988 665 340 1500 1319 990 666 340 1600 13'22 992 667 340 1700 1325 994 668 341 1800 1327 995 669 341 1900 1330 997 669 341 2000 1333 998 670 341 2100 1336 1000 670 341 2200 1338 1001 671 342 2300 1341 1003 672 342 2400 1345 1004 673 342 2500 1348 1006 674 342 2600 1351 1009 675 343 2700 1355 1011 676 343 2800 1359 1014 678 344 2900 1364 1017 679 345 3000 1369 1020 681 346 3100 1375 1024 684 347 3200 1380 1028 686 348 3300 1387 1033 689 350
{Intermediate power level data can be linearly interpolated.]
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment 1 Page 3 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 3
I EFPH 3400 3500 3600 3700 3800*
3900 4000 4100 4200 4300 4400 4500 4600 4700 4800 4900 5000 5100 5200 5300 5400 5500 5600 5700 5800 5900 6000*
6100 6200 6300 6400 6500 6600 Figure A.1 Rev.1 Page2 of 4 St. Lucie Unit 2 Cycle 17 Power Defect (pcm) vs Bumup (EFPH)
I 100% I 75% I 50% I 25%
I t394
-1037 692 351 1401 1042 690 353 1408 1048 699 355 1415 1053 703 357 1423 1059 707 359 1431 1065 711 361 1440 1071 715 363 1448 1078 719 365 1457 1084 724 367 1465 1090 728 370 1474 1097 732 372 1482 1103 737 374 1491 1110 741 376 1500 1116 745 379 1508 1123 750 381 1517 1129 754 383 1525 1135 758 385 1533 1141 762 387 1541 1147 766 389 1549 1153 770 391 1556 1158 773 393 1564 1164 777 394 1572 1169 781 396 1579 1175 784 398 1587 1180 788 400 1594 1186 791 401 1602 1192 795 403 1610 1197 799 405 1618 1203 803 407 1626 1209 806 409 1634 1215 810 411 1642 1221 815 413 1650 1227 819 416
__ L.
~--
[Intermediate power level data can be linearly interpolated.]
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment 1 Page 4 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 4
I EFPH 6700 6800 6900 7000 7100 7200 7300 7400 7500 7600 7700 7800 7900 8000 8100 8200 8300 8400 8500 8600 8700 8800 8900 9000 9100 9200 9300 9400 9500 9600 9700
, 9800 9900 Figure A.1 Rev. 1 Paae 3 of 4 Sf Lucie Unit 2 Cycle 17 Power Defect (pcm) vs Burnup (EFPH)
I 100% I 75%
I 50% I 25%
I 1659 I 1234 823 418 1668 I 1240 828 421 1677 1247 833 424 1687 1255 838 426 1697 1262 843 429 1707 1270 849 433 1717 1278 855 436 1728 1286 861 440 1739 1295 867 443 1750 1303 873 447 1762 1312 880 451 1773 1321 886 455 1785 1330 893 459 1797 1340 900 463 1809 1349 907 467 1821 1359 914 471 1834 1368 921 475 1846 1378 928 479 1859 1388 935 484 1871 1397 942 488 1884 1407 949 492 1896 1417 956 496 1909 1426 963 500 1922 1436 970 504 1934 1446 977 508 1947 1455 984 512 1959 1465 991 516 1971 1474 997 520 1984 1484 1004 524 1996 1493 1011 527 2008 1502 1017 531 2021 1511 1024 535 2033 1521 1030 538 I
[Intermediate power level data can be linearly interpolated.]
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment 1 Page 5 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 5
Date Of Update
~.L£...J.:;r EFPH 10000 10100 10200 10300 10400 10500 10600 10700 10800 10900 11000 11100 11200 11300 11400 11500 11600 11694 Figure A.1 Rev. 1 Paae4 of 4 st. Lucie Unit 2 Cycle 17 Power Defect (pcm) vs Burnup (EFPH) 100%
75%
-50%
25%
2045 1530 1036 542 2057 1539 1043 521:5
-2069 1548 1049 549 2082 1557 1055 552 2094 1566 1062 555 2106 1575 1068 559 2118 1585 1074 562 2130 1594 1080 565 2142 1603 1087 569 2154 1612 1093 572 2167 1621 1099 575 2179 1630 1105 579 2191 1639 1112 582 2203 1648 1118 585 2215 1657 1124 589 2227*
1666 1130 592 2240 1675 1137 595 2251 1684 1143 598
[Intermediate power level data can be linearly interpolated.]
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment 1 Page 6 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 6
Figure A.2 1000 EFPH Rev. 2 st. Lucie UnIt 2 Cycle 17 Xenon Buildup to Equilibrium 2800 1-~ --j---l------.. *.1----r--,-T--.-T----r----.r---l---I-T 1 0% Po sr 2600f--**~*+--*.. ~T"****-**t.. -** ----+---***--l.. *
...... -r-_*-*-*.......... _...... -........ **--*-t*-*~-\\--+
~ 1
~-
I I'
.~)
- ;-T-=~=l-=-~--
.. ------:=- ~ --
1--l75%_p+'lw-,-,-!!r--t-_-+---l I
I
,I 2000.' ----... ---1----L--.
-"-.-.---.-. -*.. *-**-1.. **.. -.. *--..L**--***-.. --*-+.. ---.-+1-_+_
I I
~ 1 BOO.* __.
..~.
1_.-
I---... -j----t-----+.-=t-
__ !j.---l-. I
\\50% Pt:twer S
I!
1600 '--- --
-.--.-~--+.. -.-... +
.... -----~.-+- -4-+--1 1----1 o*
I I
I
[
i 1400
+--+--t-:1=1=+ I I =E:-:I-"~~l::~
- 0. 1200..
-.. --r.. =-l---~---~---J-
- ---. -~
c: o 5i 10001-*
.....;-,...<:-..j-.* ---.... ---
~--*-.. I------.. II---+--!-
I I --I-'--!---I---f---I I
i 800 f--
... -- ---'------.--l...----f.-...... -.~.-+-.-+--.+I --1--+----+---1--+---+--1----1 I
I I
I I
iI.' L.
1- ---I _**I-l--l--t---i + I I-.......}--\\
Tt
--*.... T
.... -*-tl. *
.. ***---**r*****.. *-*!-*-******.. j.. ***-**_*.. *I-*****l-*.. -r-.....
200.* ~...1fI.#-,"-.. -
- .... _*r.*--.... *--*.. -*.. ***---r----t.. '.. -* *t*.. **.. **-r---*-*r**-*--~~-+-
I
,.-i----f-'--!
- ,lIV i
1 I
I I
L
'i i o.. ~--.. --.
-.-.-'--- ___ L... _.--,-.. _._._~_. __.. __ L_
.......L __......L_..
I. *.J-,-........ I. I.
!..,..I....--...J o
5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 Time Following Startup (hours)
Date Of Update
~21J~
References:
PSL.. 2FJF-b7-154 Rev. 0, Attachment 1 Page 5 PSL*ENG-SEFJ*07 *011 Rev. 0, Attachme~~
11
-HOURS 0
t 2
- l 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 Figure A..2 Rev. 2 Paqe 1 of 3 St. lucie Unit 2 Cycle 17 Xenon Buildup to Equilibrium (1000 EFPH) 100%
75%
50%
25%
0 0
0 a
107 84 60 32 21-6 171 121 66 331 263 188 104 453 363 262 145 585 474 345 193 728 596 438 248 872 721 536 306 1009 842 632 365 1138 956 724 423 1258 1064 813 480 1371 1167 898 535 1475 1263 979 589 1571 1353 1056 641 1660 1437 1129 691 1741 1514 1197 738 1815 1585 1260 783 1882 1649 1319 825 1943 1708 1373 865 1998 1762 1423 902 2049 1812 1469 937 2096 1858 1512 970 2138 1900 1551 1000 2177 1938 1588 1029 2213 1973 1621 1055 2245 2005 1652 1080 2274 2034 1680 1103 2300 2061 1706 1124 2324 2084 1729 1143 2344 2105 1749 1161 2363 2124 1768 1178 2379 2141 1785 1193 2393 2156 1800 1207 2406 2168 1814 1219
References:
PSL-2FJF-07-154 Rev. 0, Attachment 1 Page 6 PSL-ENG-SEFJ-07 -011 Rev. 0, Attachment 1 Page 12
HOURS 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 Figure A.2 Rev. 2 PaQe 2 of 3 St. lucie Unit 2 Cycle 17 Xenon Buildup to Equilibrtum (1000 EFPH) 100%
75%
50%
25%
2417 2180 1826 1231 2426-2190 1836 1242 2434 2199 1846 125.1 2441 2206 1854 1260 2447 22-13 1862 1268 2453 2219 1869 1275 2458 2225 1875 1282 2463 2230 1881 1288 2467 2235 1886 1294 2471 2240 1891 1299 2475 2244 1896 1304 2479 2248 1900 1309 2482 2252 1904 1313 2486 2255 1908 1317 2489 2258 1911 1320 2491 2261 1914 1324 2494 2264 1917 1326 2496 2266 1920 1329 2498 2268 1922 1331 2500 2270 1924 1333 2502 2272 1926 1335 2504 2274 1928 1337 2505 2275 1929 1338 2507 2277 1931 1340 2508 2278 1932 1341 2509 2279 1933 1342 2510 2280 1934 1343 2511 2281 1935 1344 2512 2282 1936 1345 2512 2282 1936 1346 2513 2283 1937 1346 2514 2284 1938 1347 2514 2284 1938 1348 2514 2284 1939 1348
References:
PSL-2FJF-07-154 Rev. D, Attachment 1 Page 7 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 13
~
r
~
IJJ -
VI
~
-]
-I
~
Date Of Update 21..?{) I O'b HOURS 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 Figure A.2 Rev. 2 Paoe3 of 3 St. lucie Unit 2 Cycle 17 Xenon Buildup to Equilibrium (1000 EFPH) 100%
75%
50%
2515 2285 1939 2515 2285 1-939 2515 2285 1940 2516 2285 1940 2516 2286 1940 2516 2286 1940 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1941 2516 2286 1942 2516 2286 1942 2516 2286 1942 2517 2287 1942 2517 2287 1942 2517 2287 1942 2517 2287 1942 2517 2287 1942 2517 2287 1942 2517 2287 1942 2517 2287 1942
~
25%
1349 1349 1350 1350 1350 1351 1351 1351 1351 1351 1352 1352 1352 1352 1352 1352 1353 1353 1353 1353 1353 1353 1353 1353 1353 1353 1354 1354 1354 1354 1354 1354 1354
References:
PSL-2FJF-07-154 Rev. 0, Attachment 1 Page 8 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 14
Figme A.3 1000 EFPH Rev. 2 St. Lucie Unit 2 Cycle 17 Xenon Worth vs. Reactor Power (SO and EQ)
- *.. -. _._- -~ff =t= +:~"l~Fl+t~ ~-.
- ---t-~-- =t-t:~:~~*~F~~=r=+.-Sh Id-~W-~ ~-eno-~ll---+--t-~,...e::::..-+-
3400*
---. ----------t "-'-'-T" ---+----- "-j-"
.. -----+... - ---
I.
'j I
I I
I 3200"*-- --- -.- --*+.... --i-*'--*-*l*-----!*..... -r... t*----.. t--- "------
-*-..J..".1E~I_
E 2800 -.---.---- ---r*--i=L-. ----+*---t-.... -.~... ).... +-.... --+"..... _'- ---+-- I --
~ 2600.
"'-}' ----
-.... - *--*1--**--t*_-_*-+*.. *.... +
.. -*-*.. - ----I..
._- -r I _.-1--
2400.*
-_. "+-+--t-.- --1--- ---'r"
~ 2200.*
---.. --L..
--+. -~-----... ~-.-
._...... 1_.---..... -"
._+ __ 1 __
-1 ___ _
c
.: J' i
+.
~
I 1-.
Equili rlum x npn
.~ 2000 :. _. 1--+,-"-'\\ --r-r--
I
.. - -- ~ -.. -.
i i
r--i.
l II I
~ 1800 :
.l._....... __ 1--
I
,---1-'---** f
---I--!
g 1600:;
__ J___..
"----,"-',,-+--..... --L.. -.. --~_........ __ _ _
..,.-1 ___ 1---1---1 QI
\\
I I
.0 X 1400.-. --'-'
--i--.. **+... ---+--.. *-r'*----*l-
---r--
1200 *.'
---... -_. __. -_...... ".-.. *****.... *t***........ _** -"""--r-
......:.. --- -- f-----!--I----+--+--+-.-.
I I
I
.~ ~
1000 :.
-__ ~_
.. ~.-..
800.
--... _.... __ +
___.+ __.. ___.
i
.1 400 [zfj------t'---E* -r----t-----,*---j--.. --.. "-l* -.. +
.. --l-....... -t----*
+-
200
.,--.. ~-.. _*-t' -j--+-' (-,.. _
... t*.. *-_.. i
... ****.... r.. *-*1*--*--.. "-.. \\
o
-~ _-L_ -
-_.J.. __. __, __.. __.1_,... __._L_._. _____ ~
o 5
10 15 20 25 30 35 40 45 50 55 60 65 70 75 \\
80
-85 90*
95 100 "105 Date Of Update
_=_j~_LCr Percent Rated Thermal Power
~--~~~o~~----~----~~~~*~~~G~
Refere~ges: PSL-2FJF~07-154 Rev, 0, AttaCJI. m
'\\PSL-ENG-SEFJ-07-011 Rev. 0, Attac~m
Figure A.31000 EFPH Rev. 2 St Lucie Unit 2 Cycle 17 Xenon Worth VS. Reactor Power (SDand EQ)
- -. ------R---- t-~~rfft--f1=_-....I. ---f!'. -t-'1~
3600
_.. _-_.:". -+/----I---"'---
._,,_. '--"--r'".. *-*j***.. *--***,*-*----l*--t-.
- k';~ ~~~
--~~+-.. --
3400
-\\-----. --.-- "-'-'-'l.. ---1' ' -'-1-'.. -"---1-"'-~--
.~I I ---1-1--
I.
Ii" I
3200 -'-- -- -*--t----l-.. *
.. --i-*--t'***-*~ -----t.. *... !".. *.. *1**--.. *1--- ----- -
3000 ****--.L--*-*!-*-i.. **----*~---.. t-.-.----~. -**-l-*...... *t"*.... 'r--'" *-r'-.. _*-!*.. *.. *---I"*--*... * --
- -j*_-t 1"'---t--+---+-*_-,
E 2BOO -*-*-1*--**- I -l-*-_L. -----+---1"....... r ---+-. *t-*-* ---i---*-------
-*-r---i---*...*-
--~--
~ 2600 '.
..-~---~--. --l--.. --t---_.. --r****-***!*.. -*-*.. -* ---1_.
- -+ -
... _+---+--+---
of 2400. --
-.- ---+-+--+--i-'- --1--*.. -*-i---
~ 2200
.--.. - ------+_... --\\--.+.. -+... --~-.- -... _
.. -*..... *1-**........ -..
.~ 2000 _.J_+_.-t---\\_.... _+-+_.'
-I--"~"--'
'i:
-+---. +---+---+---1---'--
~ 1800 -~~-.... *.. --I--r*--
*---1-'---
I f --1---'-:--
~ 1600 -E+/-'-l---. -
""'--:"'".,.. t-*.... --t*---"'i-:-'+/-'--- -----I-.-.-- --.J--+.-~-I-.~
>< 1400 -_
---.\\--
__. ___ J __. ___.+_.... ______.L_ --or
+--+-
I I '-l 1200
--_. --.~.--
*-*-+--.... --\\-**.. -+.. *
.. *----.... ---t-
~f'--_t j
I -t--t--t-._-
1000r-----r-t-~ I i tl--- --+-'+-'--1 BOO J---.t.---h/k
_.. ---.... --+.. -... -~
400[33.
--*.. **-r-E-i---t-_.. t.. *_-*_...... _*.. *
.. *,.... *.. +
.. *_-j-_.... - -_._-..
. 1=--
200.** -
- "--r-" *-t--"*i--+*"-*-*.. *
.... **_.. t...... *_**.. t.. _*.... *.. T-***_*t--*--* --
--- \\ -
'7.
o..
~ __ LJ -
--L... __.J.". ____ L_.... --"l.......... '---L-.-.J-.--
~. --.'
\\
o 5
10 15 20 25 30 35 40 45 50 55 60 65 70 75 80
'8S 90*
95 100 1\\05 Date Of Update
-~--l~-~-J C6" Percent Rated Thermal Power
"'~'~.'::;-
~
Referen2es: PSL-2FJF-07-154 Rev. 0, Attac~rh
.C
- .p:SL-ENG-SEFJ-07-011 Rev. 0, Attac'm
Figure A.3 Rev. 2 Pa e 1 of 2 St. Lucie Unit 2 Cycle 17 (1000 EFPHt Xenon Worth vs. Reactor Power (Shutdown and Equilibrium)
_RXPower S/DXe U
-0 1
65 2
-129 3
t93 4
258 5
322 6
385 7
449 8
512 9
575 10 637 11 698 12 759 13 820 14 879 15 938 16 997 17 1054 18 1110 19 1166 20 1220 21 1273 22 1326 23 1377 24 1427 25 1475 26 1522 27 1568 28 1613 29 1657 Equil-Xe _
RXPower SIOXe Equil Xe -
0 62 123-185 246 307 368 428 488 547 605 663 720 776 831 885 938 990 1041 1090 1138 1184 1229 1273 1314 1354 1392 1428 1463 1496 30 1699 1528 31 1741 1558 32 1-781 1586 33 1820 1613 34 1859 1639 35 1897 1664 36 1934 1688 37 1970 1711 38 2005 1732 39 2040 1753 40 2074 1773 41 2108 1792 42 2142 1811 43 2174 1829 44 2207 1846 45 2239 1863 46 2271 1879 47 2303 1895 48 2335 1911 49 2366 1927 50 2398 1942 51 2429 1957 52 2461 1973 53 2492 1988 54 2524 2003 55 2555 2018 56 2587 2033 57 2618 2048 58 2650 2063 59 2681 2077
References:
PSL-2FJF-D7-154 Rev. 0, Attachment 1 Page 33 PSL-ENG-SEFJ-07-D11 Rev. 0, Attachment 1 Page 39
Figure A.3 Rev. 2 Pace 2 of 2 st. Lucie Unit 2 Cycle 17 (1000 EFPH)
Xenon Worth vs. Reactor Power (Shutdown and Equilibrium)
RXPower SlDXe Equll Xe SIDXe Equil Xe 60 2712 2092 90 3580 2434
£1 2743
- 2100
]
62
_2775 2120 91 3607
- 2443 92 3633 2451 63 2806 21"34 93 3660 2460 64 2836 2148 94 3686 2468 65 2867 2162 95 3712 2476 66 2898 2175 96 3738 2484 67 2928 2188 97 3765 2493 68 2959 2201 98 3791 2501 69 2989 2214 99 3817 2509 70 3019 2227 100 3843 2517 71 3049 2240 72 3078 2252 73 3108 2264 74 3131 2276 75 3166 228'7 76 3195 2298 77 3224 2309 78 3252 2320 79 3280 2331 80 3308 2341 81 3336 2351 82 33~
2361 83 3391 2371 84 3419 2380 85 3446 2389 86 3473 2399 87 3500 2408 88 3527 2417 89 3554 2425 Date Of Update
References:
PSL-2FJF-07-154 Rev. 0, Attachment 1 Page 34 2J.AI...H.
PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 40
4200 4000 3800 3600 3400 3200 3000
_2800 E
&. 2600
...... 2400 o s: 2200 C
~ 2000
'0 D. 1800 c g 1600 (1)
>< 1400 1200 1000 BOO 600 400 200 o
Figure A.41000 EFPH Rev. 2 St. Lucie Unit 2 Cycle 17 Xenon Worth Following Shutdown
-. *"r--!---**l---'*---'-=L~~I. __.. ~.... _. ___ ~_,,_.. _. ___. _. ___.
~_._+ ___
.-r--'-~ 1 I
~
-. - -'"700 ~~
I +! f -
"--r I
r J
~,. __.* _~._
_+_. ___
-\\
---'-+--'-=-,-
--.... *.. --1-_*-
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\\
~
I
--- __ 1_'.. "
- 7
\\.\\
+_._--.... -
1 __ * -,,-- -_.... ---r-'
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"\\
rr;, '"rn - 1-+.--r----- ->-- -
.-\\-
\\
______._....l_.. __ +._.. _.
~ " \\ \\.-- --+-+---T"-
"C!W&r --- f----
.P
-*1----1-1-*
'. "'P~ K I\\~, ~+.
I \\ \\:\\ ~-+->-l-I
- ~- 1--- -
. _._,. I:
I
'-+-_~'-+' __ +
- .. --: --I-.
I I
I
\\ 1\\
}-.... ---.-._-.-I--
'\\. \\ I i I
~", --- '-- -,
~ '\\. i\\;
I 1--_
,:25%P wer14 5pcm '"
"\\I'---'T-----
"". --f---
~
~
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,~
,I:-
, t-...
~
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1=
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.~ -r=- -- -
.t..... ~r--:::~~
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I j
l-.
,,__........ _..,....... J,...
- _____ L...,.._
_..... _,_-;..!-__ I..-__
o 5
10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 105 Time Following Shutdown (hours)
Date Of Update
~
.?-...£i.JZfL.
References:
PSL-2FJF-07-1S4 Rev. 0, Attachment 1 Pag PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Pag
HOURS 0
1 2
3 I
4 5
I 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 Figure A.4 Rev. 2 Page 1 of 3 St. Lucie Unit 2 Cycle 17 Xenon Worth Following Shutdown I I (1000 EFPH) 100% I 75%
50%
25%
2563 I 2333 1987 1386 2865 2539 2098
-1416 3150 2734 2201 1444 3404 2905 2290 1464 3610
-3041 2357 1475 3753 3130
- 2394 1473 3823 3166 2398 1456 3843 3165 2378 1429 3835 3144 2346 1397 3806 3106 2305 1361 3755 3053 2255 1321 3686 2988 2196 1279 3601 2911 2131 1234 3504 2825 2062 1187 3396 2733 1988 1139 3282 2636 1912 1091 3163 2536 1835 1043 3042 2435 1758 996 2920 2333 1681 949 2797 2232 1605 903 2676 2132 1530 859 2557 2034 1457 816 2441 1939 1387 775 2327 1847 1319 735 2217 1757 1252 696 2109 1669
'188 659 2003 1584 1126 623 1901 1502 1066 589 1802 1422 1008 556 1705 1344 952 524 1612 1270 899 493 1522
'198 847 464 1435 1128 797 436 1351 1062 750 410
References:
PSL-2FJF-07-154 Rev. 0, Attachment 1 Page 55 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 61 len "
J 'I
(
'{
]
~
HOURS 34 35 36 37 38 39 40 41 42 43 44 45 46 47 4B 49 50 51 52 53 54 55 56 57 5B 59 60 61 62 63 64 65 66 67 Figure A.4 Rev. 2 Page2 of 3 Sl Lucie Unit 2 Cycle 17 Xenon Worth Following Shutdown (1000 EFPH) 100%
75%
50%
25%
1270 998 704 384 11'93 937 660 360 1119 878 619 337 1048 822 579 315 981 770 5:42 295 917 719 506 275 857 672 473 257 BOO 627 442 240 747 586 412 224 697 546 384 208 651 510 358 194 607 475 334 1B1 566 443 311 168 528 414 290 157 493 386 271 146 460 360 252 136 429 336 235 127 -
401 313 220 118 374 293 205 110 350 274 192 103 327 256 179 96 306 239 167 90 286 224 157 84 268 210 146 78 251 196 137 73 235 184 128 68 220 172 120 64 206 161 112 60 192 150 105 56 180 140 98 52 168 131 91 48 156 122 85 45 146 114 79 42 136 106 74 39
References:
PSL-2FJF-07-154 Rev. 0. Attachment 1 Page 56 PSL-ENG-SEFJ-07-011 Rev.O. Attachment 1 Page 62
,. ~
r
~
U)
'I 1
I HOURS Date Of Update
-2:J~A 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 B4 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 Figure A.4 Rev. 2 Page 3 of 3 St. Lucie Unit 2 Cycle 17 Xenon Worth Following Shutdown I
(1000 EFPH) 100% I 75% I 50% I 25% !
1.26 98 69 36 117 91 64 34 109 85 59 31 101 79 55 29 94 73 51 27 88 68 47 25 81 63 44 23 75 58 41 22 70 54 38 20 65 50 35 19 60 47 33 17 56 43 30 16 52 40 28 15 48 37 26 14 45 34 24 13 42 32 22 12 39 29 21 11 36 27 19 10 33 25 18 10 31 24 16 9
29 22 15 8
27 20 14 8
25 19 13 7
23 18 12 7
22 16 11 6
20 15 11 6
19 14 10 5
18 13 9
5 16 12 B
4 15 11 8
4 14 11 7
4 13 10 7
3 12 9
6 3
References:
PSL-2FJF-07-154 Rev. 0, Attachment 1 Page 57 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 63 r
ILf j V
,jI l
I
Figure A.S 1000 EFPH Rev. 2 St. Lucie Unit 2 Cycle 17 Shutdown SmfNplTranslent Fission Product Worth 900 *,**"****"r...... T' **"-r*.. *.. *T**.. j".. **"-r".. * "T"'T --"1".." r*..... T'." ""1""..* r.... "-T---r*.. *-r"-T-..,--*"--,-*-T"*-~---"*--,,
i:,
-~:l l
~I
~
j I
T I
.I.
i 860 ~
i l'
~~
1 J
~~
I 840 V
V E
I.......
i
(,)
/V
~
I I
-I.
I
~
, f'1 vV "
I
---l a:
+
800 i
.I I
J V
J J
780-f-~
I 1 i "f'j 1
I 760 T
~
T 1
740 LI-H-.... ~~ +H H-c+H-++<-++' 0->++\\-<+, ~-,-._.+,.,"-,-- +H+r"-H-F-" -+H-~ *
~+r ~-f->++-+++I-;_k-J o
20 40 60 80 100 120 140 160 1110 200 220 240 260 280 300 320 340 360 360 400 420 440 460 480 500 Date of Update _3:::../.>tj OS'"
Time Fol!owlng Shutdown (hours)
References:
PSL-2FJF-07-154 Rev. 0, Attac PSL-ENG-SEFJ-07-011 Rev, 0, Attacha1e
Figure A.5 Rev. 2 Page 1 of 1 St. Lucie Unit 2 Cycle 17 SmlNplTransient Fission PJ"oduct Worth Contribution Following Shutdown IHOURSSJol WORTH I (PCM) 0 758 5
762 10 767 15 n1 20 n5 25 n9 30 783 35 787 40 791 45 795 50 798 55 801 60 804 65 807 70 810 75 812 80 815 85 817 90 819 95 821 100 823 105 825 110 827 115 828 120 830 125 832 130 833 135 835 140 836 145 838 150 839 155 840 160 842 165 843 170 844 Date of Update: 2! :J6/~
(1000 EFPH)
HOURSS/D WORTH HOURSS/D WORTH CPCM)
(PCM) 175 B45 350 867 180 846 355 867 185 847 360 868 190 848 365 868 195 849 370 868 200 850 375 868 205 851 380 869 210 852 385 869 215 853 390
, 869 220 853 395 870 225 854 400 870 230 855 405 870 235 856 410 871 240 856 415 871 245 857 420 871 250 858 425 872 255 858 430 872 260 859 435 872 265 859 440 872 270 860 445 873 275 861 450 873 280 861 455 873 285 862 460 874 290 862 465 874 295 863 470 874 300 863 475 875 305 863 480 875 310 864 485 875 315 864 490 875 320 865 495 876 325 865 500 876 330 865 335 866 340 866 345 867
References:
PSL-2FJF-07-154 Rev. 0, Attachment 1 Page 81 PSL-ENG-SEFJ-07-011 Rev: 0, Attachment 1 Page 87 t' ~
~ 'I I
I
.:,]
8400 8200 8000 7800
_ 7600 E
[ 7400
~
.- 7200
~ 700
(\\)
IX 680 660 640 620 V
/ ""
lL V
V
'-\\-- t::::c
.7."
~ ~'
Figure A.S Rev. 2 St. Lucie Unit 2 Cycle 17 HZP Sequential Integral CEA Worth, 1000 EFPH I
I I
I I II i
(
ARO = 8172 pem_
V-I---
p'l I--' ~
~
,.. ".".1""
,/
~
V
/" ~
~
V V
/ l' I
~.,
r'60TJ/
0 20 40 60 80 100 120 '137
'0 20 40 60 80 100 120 137 Bank3 Date of Update: ~/.J GjIJ 8' Bank 5 o
20 40 60 80 100 120 137 Bank 4
References:
PSL-2FJF-07*162 Rev. 0, Attachmemt 1, PSL-ENG-SEFJ-07-0'11 Rev. 0, Attachmel1t I. P
Position (Inches Group Withdrawn)
Group A
0 A
17 A
37 A
57 A
77 A
97 A
117 A
137 B
B B
B 8
B B
1 0
B 1
17 1
37 1
57 1
77 1
96 2
1 113 2
1 133 2
1 137 2
2 Date of Update: ~~/~
Figure A.S Rev. 2 St. lucie Unit 2 Cycle 17 HZP Sequential integral CEA Worth, 1000 EFPH Position Integral (Inches Worth Withdrawn)
(pcm) 0 406 1360 1786 2011 2165 2332 0
2491 17 2744 37 3543 57 3942 77 4161 97 4317 117 4494 137 4656 4669 4734 4854 4982 0
5095 17 5290 37 5666 57 5958 77 6149 Position Position Integral (Inches (Inches Worth Group Withdrawn)
Group Withdrawn)
(pcm) 3 0
2 96 6291 3
17 2
113 6478 3
37 2
133 6710 3
57 2
137 6857 3
77 6994 3
96 4
° 7112 3
113 4
17 7236 3
133 4
31 7357 3
137 4
57 7402 4
77 7461 5
0 4
96 7527 5
17 4
113 7611 5
37 4
, 133 7715 5
57 4
137 7804 5
77 7906 5
97 8011 5
117 8121 5
137 8172 I
I
References:
PSL-2FJF-OT-162,1 Rev. Q, Attachment 1 Page 5 PSL-ENG-SEFJ-07 -011, Rev. 0, Attacnment 1 Page 100
8250 8200 8150 8100 E 80S0
- 8. -
~ 8000
- g m 7950 a:
7900 7850
- 7800 77S0 L V i"'"'
Figure A.7 Rev. 2 St. Lucie Unit 2 Cycle 17 HZP Integral Worth of CEA (Lead Group 55 In. to ARO), 1000 EFPJ-f I
I I
I ARO = 8172 pcm
~
~
V L
V V
~
V
/' V
/ V
/' V 55 60 65 70 75 80 85 90 9S 100 10S 110 *11S 120 125 130 135 140 Date of Update: ~?::fJ-'!'x f~!<'"'~;~"'{o" I
- ,t "1
f', ~",,,",,,,,,,,,,i
.~
Inches Withdrawn
~~I
References:
PSL-2FJF-07-162 Rev. ° Attachmenmage 22 PSL-ENG-SEFJ-07 -011 Rev. 0, Attachment 1, Page 115
Figure A.7 Rev. 2 St. lucie Unit 2 Cycle-17 HZP Integral Worth of CEA (lead Group 55 in. to ARO), 1000 EFPH CEA CEA CEA CEA Position Position Position Position (Inches Integral (Inches Integral (Inches Integral (h,ches Integral Withdrawn) Worth (pcm)
Withdrawn) Worth (pcm)
Withdrawn) Worth (pcm)
Withdrawn) Worth (pcm) 55 7794 76 7901 97 8011 1-------
,118 8125 56 7799 77 7906 98 8017 119 8128 57 7804 78 7911 99 8022 I
120 8132 58 7809 79 7916 100 8028 141, "
8135 59 7814 80 7921 101 8034 122 8139 60 7820 81 7926 102 8040
- 123, 8142 61 7825 82 7931 103 8046 124 8145 62 7830 83 7936 104 8052 125,
8147 63 7835 84 7941 I
105 8058 1"2(3 8150 64 7840 85 7946 106 8064 12'(
8152 65 7845 86 7952 107 8070 128 8155 66 7850 87 7957 108 8075 129 8157 67 7855 88 7962 109 8081
, 130 8159 -
68 7861 89 7967 110 8086 131 8161 69 7866 90 7972 111 8092 132 8163 70 7871 71 7876 91 7978 92 7983 112 8097 113 8102 133 8165 1--
134 8167 72 7881 93 7988 114 8107 135 8169 73 7886 74 7891 94 7994 95 7999 115 8112 116 8116 136 8170 1--: '137 8172 75 7896 96 8005 117 8121 Date of Update: ~~/J2%
~"
10.5 10.0
~
Q.
~
- !E U
e:. 9.5
- E o
~
c: e o
III 9.0 (ij
~
l!!
~
c B.5 8.0 o
,)'"
Date Of Update,
_/_/~/()r Figure A.a Rev. 1 st. Lucie Unit 2 Cycle 17 HZP Differential Boron Worth vs Burnup V
I l/
.,/
V
- /
t~
'~-.-... -"."-',/
~
V".
~
~
L L-----~
L... _______
___.. ___ 1 __
I.-
1000 2000 3000 4000 5000 1 ______ -
6000 Burnup (EFPH) 7000 1 __ -
1 _______ L _____
L.-_~-'------'-__
BOOO 9000 10000 11000 12000
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment PSL-ENG-SEFJ-Ot-011 Rev. 0, Attachment 1 Page 126
(pcmfppro) 200 30G 400 500 600 700 800 900 1000 1100 1200 130:0 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2500 2600 2700 2800 2900 3000 3100 3200 3300 Date Of Update
_/_f Ie, p Y 8.27 8.27 8.28 8.28 8.29 8.29 8.30 8.30 8.31 8.32 8.32 8.-33
~It-8.34 8.35 8.36 8.37 8.37 8.38 8.39 8.40 8.41 8.42 8.43 8.44 8.46 8.47 8.48 8.49 8.50 8.51 8.52 8.54 Figure A.a Rev. 1 j,ilr;c;;Wiiii;lti Page 1 of 1 St. Lucie Unit 2 Cycle 17
~
HZP Differential Boron Worth vs Burnup Burnup Boron Burnup Boron Burnup Boron Viorth Worth Worth (EFPH)
(pcmlppm)
(EFPH)
(pcm/ppro)
-(EF'PH)
(pem/ppm) 3400 8.55 6600 9.01 9800 9.61 3500 8.56 6700 9.03 I~I.
9900 9.63 3600 8.57 6800 9.04 10000 9.65 3700 8.59 6900 9.06 10100 9.67 3800 8.60 7000 9.08 10200 9.69 3900 8.61 7100 9.09 10300 9.72 4000 8.62 7200 9.11 10400 9.74 4100 8.64 7300 9.13 10500 9.76 4200 8.65 7400 9.15 10600 9.78 4300 8.66 7500 9.16 10700 9.80 4400 8.68 7600 9.18 10800 9.82 4500 8.69 7700 9.20 10900 9.85 4600 8.70 7800 9.22 11000 9.87 4700 8.72 7900 9.24 11100 9.89 4800 8.73 8000 9.26 11200 9.91 4900 8.75 8100 9.27 11300 9.93 5000 8.76 8200 9.29 11400 9.96 5100 8.78 8300 9.31 11500 9.98 5200 8.79 8400 9.33 11600 10.00 5300 8.80 8500 9.35 11694 10.02 5400 8.82 8600 9.37 5500 8.83 8700 9.39 5600 8.85 8800 9.41 5700 8.87 8900 9.43 5800 8.88 9000 9.45 5900 8.90 9100 9.47 6000 8.91 9200 9.49 6100 8.93 9300 9.51 6200 8.94 9400 9.53 6300 8.96 9500 9.55 6400 8.98 9600 9.57 6500 8.99 9700 9.59
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment 1 Page 8 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 127
,I
- 8::1"." "".V Page-j-of2 St. Lucie Unit 2 Cycle 17 Inverse Count Rate Ratio Data Sheet 1000 EFPH, Rev. 2 Date: _,_,_
Time of Completion: ___ _
Initial Power (%) or Count Rate (CPS):
Count ICountTime(sec) I Channel Channel 1
120
~t 2
120 1
T 3"
120 Total Counts-->
r;::}
LJ)J rL, EFPH ___
Avg Counts (fota//3)-> I
--I(Base Counts)
Estimated Critical CEA Position:
Actual Critical CEA Position:
(Filled in at time of use)
SUGGESTED CEA HEIGHT Group Inches Gp 1 0
Gp1 101 Gp2 36 Gp2 78 Gp3 32 Gp3 102 Gp4 84 Gp5 60 Gp5 ARO 1
Group at Inches WID Group at' Inches WID ACTUAL HEIGHT Group Inches 1
o
% POWER or COUNT RATE CH CH Base Count I Base Count
-~
_COMPLETED BY:
REVIEWED BY: __________ _
Date of Update:
- 1 I ~G I (J £""
Date 10124/07 1-t./--of
/(~;;r~
3/If/b~
ST. LUCiE UNIT 2, CYCLE 17 EFPH 0
"5l-(5 tl4:l. b FIGURE B.3 Reactivity Deviation Log (Column 2)
(Column 3)
- Reactivity Boron-10 Deviation (pcm)
Depletion (ppm)
~1000 0
f,:z.,R II//IJ-
-4.51 NIt+-
-f-lS(.<19 IV (A Verified by:
/t/IJ1v" h....
.h.-...v
- Boron-10 depletion for information only. Not to be used unless as directed by Reactor Engineering.
Figure B.4 St.;. Lucie Unit 2 Cycle 17 en Total Worth (lOOO EFPH, Rev. 2)
CEA TOT-AL WORTH HZP A1l Rods In to All Rods Out
=
STOCK CEA INFORMATION Single Worst Stuck CEA Worth
[Location: N2*]
>(,..,
Combined First and Second Worst Stuck eEA Worth
[Locations: N2 and J2*]
Difference Between Worst and Second Worst Stuck CEA Worth
=
=
=
HFP DROPPED CEA INFORMATION Highest Single Dropped CEA Worth =
[Location: '1'5"]
- Symmetric locations are also applicable.
8172 pan 915 pcm 2063 pcm 1148 pcm 93 pan Date of Update ~/.)" I~I
References:
PSL-2FJF-07-178 Rev. 0 Page 3 PSL-ENG-SEFJ-07-011 Rev. 0 Page 145
11.0 r 10.8 10.6 - -~
10.4
- e 10.2
- 0. i 10.0
()
Q. 9.8
.l:
1:: 9.6 0
- 94 c
2 o 9.2 IX!
iii 9.0
- l c e 8.8
~
8.6 C
8.4 8.2 B.O 7.8 50 Date of Update 2.};tl.J..a.8-100 Figure 8.5 Rev. 2 St. Lucie Unit 2 Cycle 17 Differential Boron Worth vs RCS Temp.
(1000 EFPH, No Xenon, ARI Minus Worst Stuck CEA)
~
~
...... ~
I
~
~
....... ~
~.
~,
'" I'".....
I I
I
_ I 1 ___
t
__.I.. ____.I_-L 150 200 250 300 350 Moderator Temperature (Deg F) 400 450 500 550
Reference:
PSL-2FJF-07-164 Rev. 0 AttadlP.'lf""Page 3 PSL-ENG-SEFJ-Q1-011 Rev. 0 Attach. 1 Page 153
r' '"
1U1
{/
Figure 8.5 Rev. 2
(
Page 1 of1 Sl Lucie Unit 2 Cycle 17 (1000 EFPH)
Differential Boron Worth vs Moderator Temperature ReS Boron Temp.
Worth
\\F)
(pcmJppm) 68 72 '
76 80 84 88 92 96 100 104 108 112 116 120 124 128 132 136 140 144 148 152 156 160 164 168 172 176 180 184 Date Of Update 2.JW 08" 10.85 10.83 10.82 10.81 10.80 10.79 10.78 10.76 10.75 10.74 10.73 10.71 10.70 10.68 10.67 10.65 10.64 10.62 10.61 10.59 10.57 10.55 10.53 10.51 10.49 10.47 10.45 10.43 10.41 10.39 (No Xenon, ARt Minus Worst Stuck CEA)
Worth Temp.
(oF)
(pcmlppm)
(oF) 188 10.37 308 192 10.35 312 196 10.32 316 200 10.30 320 204 10.28 324 208 10.26 328 212 10.24 332 216 10.21 336 220 10.19 340 224 10.17 344 228 10.15 348 232 10.13 352 236 10.11 356 240 10.08 360 244 10.06 364 248 10.04 368 252 10.02 372 256 9.99 376 260 9.97 380 264 9.95 384 268 9.93 388 272 9.90 392 276 9.88 396 280 9.86 400 284 9.84 404 288 9.81 408 292 9.79 412 296 9.77 416 300 9.74 420 304 9.72 424 Boron RCS
-Boron
- Worth Temp.
Worth (pcm/ppm)
(oF}
(pcm/ppm) 9.70 428 8.92 9.67 432 8.89 9.65 436 8.86 9.62 440 8.84 9.60 444 8.81 9.57 448 8.78 9.55 452 8.75 9.53 456 8.72 9.50 460 8.69 9.47 464 8.66 9.45 468 8.64 9.42 472 8.61 9.40 476 8.58 9.37 480 8.55 9.35 484 8.52 9.32 488 8.49 9.29 492 8.46 9.27 496 8.43 9.24 500 8.39 9.22 504 8.36 9.19 508 8.33 9.16 512 8.30 9.14 516 8.27 9.11 520 8.23 9.08 524 8.20 9.06 528 8.17 '
9.03 532 8.14 9.00 8.97 8.95
References:
PSL-2FJF-07-164 Rev. 0 Attach. 1 Page 4 PSL-ENG-SEFJ-07-011 Rev. 0 Attach. 1 Page 154
1550 1500 1"-................ ~
I Figure B.G Rev. 2 St. lucie Unit 2 Cycle 17 Shutdown Boron COIlcentratlon vs RCS Temp.
(Modes 1-4, 1000 EFPH, No X9, ARI Minus Worst Stuck CEA)
ARI-1 3600 pCrll SID Margin
~
.... r-.-
!i 1450 Co e:.
c
~
C 1400 8
C 8 c e o 1350 OJ
~
E
- I c75 1300 1250 1200 200 220 240 Date of Update ----=:.; ~ G I Olt' 260 280 300
r--.
""'-............ ~ " ""
t
~
~
320 340 360 380 400 420 440 460 480 500 Moderator temperature (Oeg F)
Reference:
- PSL-2FJF-07-164 Rev. 0 A PSL:*ENG-SEFJ.07.o11 Rev. 0 Atta
~
520 540
ReS Temp.
(OF) 201 204 208 212 216 220 224 228 232 236 240 244 248 252 256 260 264 268 272 276 280 284 288 292 296 300 304 308 Date Of Update
-2J2W1JK.
r Figure B.6 Rev. 2 J)
Paae 1 of 1
'I Sl Lucie Unit 2 Cycle 17 (1000 EFPH)
!~
J Shutdown Boron Concentration (Modes 1-4. No Xenon. ARI Minus Worst stuck CEA)
-RCS-Boron--'
Temp_
Temp.
(ppm)
(OF)
(ppm)
(OF)
(ppm).
1513 312 1451 424 1375 1511 316 1450 428 1369 1508 320 1448 432 1364 1506 324 1446 436 1358 1504 328 1445 440 1352 1501 332 1443 444 1346 1499 336 1442 448 1340 1496 340 1440 452 1333 1494 344 1439 456 1327 1492 348 1437 460 1321 1489 352 1435 464 1315 1487 356 1434 468-
--1-3-09 1485 360 1432 472 1303 1482 364 1430 476 1297 1480 368 1428 480 1292 1478 372 1426 484 1286 1476 376 1423 488 1281 1473 380 1421 492 1275 1471 384 1418 496 1271 1469 388 1415 500 1266 1467 392 1411 504 1261 1465 396 1408 508 - '1257 1463 400 1404 512 1254 1461 404 1400 516 1250 1459 408 1395 520 1247 1457 412 1391 524 1244 1455 416 1386 528 1242 1453 420 1380 532 1239
References:
PSL-2FJF-07-164 Rev. o Attach. 1 Page 18 PSL-ENG-SEFJ-07-011 Rev. o Attach. 1 Page 168
1400 1350 1300 1250 1200 1150 1100 1050
~ 1000
.a: 950 c
0 =
I!!
900 C
850 Q) 0 800 c
0 t) 750 c e 700 0 m 650 600 550 500 450
. 400 350 300 o
Date of Update
_I_'.. !!....I£.L Figure B.7 Rev. 0 St. Lucie Unit 2 Cycle 11 Modes 1-3 Shutdown Boron Concentration vs Burnup HZP,515°F
~
-.............. ~
"- 1'0..
'"---~L-----.l_~. ____ '-. ___
1 ____... 1 ______,.1
.* ___. ___.1 ____ 1 ____
2000 4000 6000 8urnup (EFPH) 8000 10pOO 12000
Reference:
PSL.. 2FJI::-07-164 Rev. 0 Attach. 1 Page 29 PSL.. ENG.. SEFJ-07-011 Rev. 0 Attach. 1 Page 179
-Burnupl (EFPH) 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2500 2600 2700 2800 2900 3000 3100 Date Of Update
-Ll /t> IdY BO_fon
_(ppm) 1339 1328 1317 1306 1295 1284 1273 1262 1251 1240 1230 1219 1209 1199 1188 1178 1168 1158 1149 1139 1129 1119 1110 1100 1091 1082 1072 1063 1054 1045 Figure B.7 Rev. 0 Pae1of1 St. Lucie Unit 2 Cycle 17 Modes 1-3 Shutdown Boron Concentration vs Burnup HZP, 515 OF I
Burnup -Boron Burnup Boron (EFPM)*
(ppm)
(EFPH)
(ppm) 3200 1036 6200 814 3300 1027 6300 808 3400 1018 6400 801 3500 1009 6500 795 3600 1000 6600 788 3700 992 6700 781 3800 983 6800 774 3900 975 6900 767 4000 966 7000 759 4100 958 7100 751 4200 geO 1200 743 4300 942 7300 735 4400 934 7400 726 4500 926 7500 717 4600 919 7600 708 4700 911 7700 699 4800 904 7800 689 4900 897 7900 680 5000 890 8000 670 5100 883 8100 660 5200 877 8200 650 5300 870 8300 640 5400 864 8400 629 5500 858 8500 619 5600 851 8600 608 5700 845 8700 597 5800 839 8800 586 5900 833 8900 575 6000 827 9000 564 6100 821 9100 553 Burnup Boron (EFPH)
(ppm) 9200 542 9300 530 9400.
519 9500 507 9600 496 9700 484 9800 473 9900 461 10000 449 10100 438 10200 426 10300 414 10400 402 10500 390 10600 379 10700 367 10800 355 10900 343 11000 331
References:
PSL-2FJF-07-164 Rev. 0 Attach. 1 Page 30 PSL-ENG-SEFJ-07-011 Rev. o Attach. 1 Page 180
1570 1565 1560 i'1555 0-e:.
c o
~ 1550 c g o 1545 (J
2 o
!Il 1540
~
- s
~ 1535 en 1530 1525 1520 60
.... ~
~
70 60 Date of Update ~~....Qk.
Figure B.8 Rev. 2
. St. lucie Unit 2 Cycle 17 Shutdown Boron Concentration vs ReS Temperature (Mode 5, 1000 EFPH, No Xe, ARI Minus Worst Stuck CEA)
ARI-1 3000 pcm SID Marcin
"" ~<
~
r-.....
~
~
-:---+
90 100 110 120 130 140 150 160 170 160 190 200 Moderator Temperature (Deg F)
Reference:
PSL-2FJF-07-164 Rev.
PSL-ENG-SEFJ-07-011 Rev. 0
r tSt
~
Figure B.8 Rev. 2
--1,1/
Page 1 of 1
~------------------S-t-L-U-C-ie~u~n~it;2~C~Y-C-le--17------------------~,~=~- ~~~
Date Of Update
~21LJ~
(1000 EFPH)
Shutdown Boron Concentration (Mode 5, No Xenon, ARt Minus Worst Stuck CEA)
Res Temp.
(oF) 68 72 76 80 84 88 92 96 100 104 108 112 116 120 124 128 132 136 140 144 148 152 156 160 164 16£ 172 176 180 184 188 192 196 200 Boron (ppm) 1568 1567 1566 1565 1564 1563 1561 1560 1559 1558 1557 1556 1554 1553 1552 1550 1549 1548 1546 1545 1543 1541 1540 1538 1536 1535 1533 1531 1530 1528 1526 1525 1523 1521
References:
PSl-2FJF-07-164 Rev. 0 Attach. 1 Page 34 PSL-ENG-SEFJ-07-011 Rev. o Attach. 1 Page 184
10.0 9.S
~
- 0.
- 0.
~
U
~ 9.0
.c 1::
0 3:
t: e 0
IX!
C6 8.5 t:
e.!
Q)
~
Cl B.O -
7.5 o
Date Of Update I:LIJ.JLJ JCl L,.----
1000 2000 Figure C.1 Rev. 0 St. Lucie Unit 2 Cycle 17 HFP Differential Boron Worth vs Burnup
./
V
/'
//
~
/
I I
~
I
~
~
~
~
3000 4000 5000 6000 7000 Burnup (EFPH)
____ I __... ______.. ~-
__. __ ~L BODO 9000 10000 11000 12000
Reference:
PSL-2FJf-07-182 Rev. 0, Attachment 1 Pa'Qe 9 PSL-ENG-SEFJ-07-0n Rev. 0, Attachment 1 Page 195
Boron II-Bumup Worth
-II (EFPH)
(pcm/ppml 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2500 2600 2700 2800 2900 3000 3100 3200 3300 Date Of Update
.J2./-LU1 ~-;
7.86 7.87 7.87 7.88 7.88 7.89 7.89 7.90 7.91 7.91 7.92 7.93 7.93 7.94 7.95 7.96 7.96 7.97 7.9B 7.99 8.00 8.01 8.02 8.03 8.04 8.05 8.06 8.07 8.08 8.09 8.11 8.12
- 2 Figure C.1 Rev. 0 Page 1 of 1 St. Lucie Unit 2 Cycle 17 HFP Differential Boron Worth vs Bumup Bumup Boron Burnup Boron Burnup Boron Worth Worth Worth (EFPH)-
(pcm!ppm)
(EFPH)
(pcmlppm)
(EFPH)
(pcm/ppm)
I 34QO 8.13 6600 I
8.57 9800 9.15 3500 8.14 6700 I 8.59 9900 9.17 3600 8.15 6800 8.60 10000 9.19 3700 8.16 6900 8.62 10100 9.21 3800 8.17 7000 8.63 10200 9.24 3900 8.19 7100 8.65 10300 9.26 4000 8.20 7200 8.67
.. 10400 9.28 4100 8.21 7300 8.68 10500 9.30 4200 8.22 7400 8.70 10600 9.32 4300 8.24 7500 8.72 10700 9.34 4400 8.25 7600 8.74 10800 9.36 4500 8.26 7700 8.75 I
10900 9.38 4600 8.28 7800 8.77 11000 9.41 4700 8.29 7900 8.79 11100 9.43 4800 8.30 8000 8.81 11200 9.45 4900 8.32 8100 8.82 11300 9.47 5000 8.33 8200 8.B4 11400 9.49 5100 8.34 8300 B.86 11500 9.51 5200 8.36 8400 B.88 11600 9.53 5300 8.37 8500 8.90 11694 9.55 5400 8.39 8600 8.92 5500 8.40 8700 8.93 5600 8.42 8800 8.95 5700 8.43 8900 8.97 5800 8.45 9000 8.99 5900 8.46 9100 9.01 6000 8.48 9200 9.03 6100 8.49 9300 9.05 6200 8.51 9400 9.07 6300 8.52 9500 9.09 6400 8.54 9600 9.11 6500 8.55 9700 9.13
Reference:
PSl-2FJF-07-182 Rev. 0: Attachment 1 Page 10 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 196
1200 1100
~,
1000 e-900
- 0.
.e:
c::
800
. 2
~ 700 c::
G.I U c:
600 0
U c
0 500 0
tIl
~ 400 u :g U
300 200 100 o
o Date Of Update
~/-.!.a..J~
1000 2000 Figure C.2 Rev. 0 St. Luch~ Unit 2 Cycle 17 HFP Critical Boron Concentration vs Bur~up (Un-normalized)
'" ~
............ ~
3000 4000
....... ~
.... ~
i"o.. '" "'" ~
5000 6000 7000 8000 9000
'10000 11000 12000 Burnup (EFPH)
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment 1 Page 1 PSL-ENG-SEFJ-0'7-0'11 Rev. 0. Attachment 1 Page 197
2 Figure C.2 Rev. 0 Page 1 of 1 St. Lucie Unit 2 Cycle 17 HFP Critical Boron Concentration vs Bumup (Un-normalized)
Critical
. Burnup (J:FPH) 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200 2300 2400 2500 2600 2700 2800 2900 3000 3100 3200 3300 Date Of Update
.J2LW-L!
Boron (ppm) 1134 1117 1103 1089 1077 1065 1055 1045 1035 1025 1016 1007 998 988 979 970 961 951 942 933 923 913 904 894 884 875 865 855 846 837 828 819 I
Bumup Critical Bumup Critical Burnup Critical Boron Boron Boron (EFPH)
(ppm)
(EFPH)
(ppm)
(EFPH)
(ppm) 3400 810 6600 565 9800 231 !
3500 801 6700 558 9900 218 I~
3600 792 6800 550 10000 206 3700 783 6900 543 10100 194 3800 775 7000 535 10200 181 3900 766 7100 527 10300 169 4000 758 7200 519 10400 157 4100 750 7300 510 10500 144 4200 741 7400 501 10600 132 4300 733 7500 492 10700 120 4400 725 7600 483 10800 107 4500 717 7700 473 10900 95 4600 709 7800 464 11000 83 4700 701 7900 453 11100 71 4800 693 8000 443 11200 59 4900 686 8100 432 11300 47 5000 678 8200 421 11400 35 5100 670 8300 410 11500 23 5200 663 8400 399 11600 11 5300 656 8500 387 11694 0
5400 648 8600 376 5500 641 8700 364 5600 634 8800 352 5700 627 8900 340 5800 620 9000 328 5900 613 9100 316 6000 606 9200 304 6100 599 9300 292 6200 592 9400 280 6300 586 9500 267 6400 579 9600 255 6500 572 9700 243
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment 1 Page 12 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 198
Frt Radial Date EFPH Peaking Tq Core Tilt 1/5/08 1.4 1.640 0.00800 1/5/08 7.1 1.623 0.00604 1/6/08 25.6 1.596 0.00462 1/8/08 57.2 1.590 0.00519 1/15/08 224.7 1.581 0.00517 1/22/08 392.6 1.577 0.00514 1/29/08 556.4 1.581 0.00511 2/8/08 559.4 1.640 0.01021 2/12/08 638.7 1.577 0.00505 2/19/08 806.5 1.576 0.00516 2/26/08 974.2 1.576 0.00517 3/4/08 1142.2 1.576 0.00519 Prepared By: ~W;~
Date 3-1 !iI-'l<6 Unit 2 Cycle 17 Operator Information Figul-e C.3 LHRm(z)
Max mum Power level permissable for operation with
[FqC(z)/l<<z)]
1 near heat rate being monitored by the Exdore (kw/ft)
Detector MonitorinQ System i....
2.878 24.2% upon loss of i~cores 4.653 43.4% upon loss of incores 9.184 95.1% upon loss of incores I
9.607 99.9% upon loss of incores 9.514 100% upon loss of incores 9.484 100% upon loss of incores 8.739 I
90.9% upon loss of incores 3.226 27.4% upon loss of incores 9.466 100% upon loss of incores 9.445 100% upon loss of incores ---
9.425 100% upon loss of incores 9.399 100% upon loss of incore~
Equibr'ium Shape Index. Current value posted on R,PS NA Pwr Aso 9/17/2807
-0.25 1/11/2998
-0.36 1/25/2008
-0.26 Veri fi ed By: Ai ~
f Date J 1£.Jif
- 8
- 10.~
- 12
- 14
- 16 G:"
~ *18
()
E;
~ *20
- l:
-22
-24
.26
-28
-30 a
Date Of Update
.!.LJ.ilL}...QJ
~
1000 2000 Figure C.4 I~ev. 0 St. lucie Unit 2 Cycle 17 HFP Moderator Temperature Coefficient vs Burnup
"" ~
3000
~
i
~
~
'" ~
'" " ~ ".'" "
~
4000 5000 6000 7000 BOOO 9000 10000 11000 12000 :ii' I
Burnup (EFPH)
- ]51
Reference:
PSLi~fZJF-07-182 Re~. 0, Attachment 1 Page' PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 199
Bumup MTC (EFPH) (pcmfF) 200
-8.8 300
-8.9 400
-9.1 500
-9.2 600
-9.4 700
-9.5 800
-9.7 900
-9.8 1000
-10.0 1100
-10.1 1200
-10.2 1300
-10.4 1400
-10.5 1500
-10.6 1600
-10.8 1700
-10.9 1800
-11.1 1900
-11.2 2000
-11.3 2100
-11.5 2200
-11.6 2300
-11.7 2400
-11.9 2500
-12.0 2600
-12.2 2700
-12.3 2800
-12.4 2900
-12.6 3000
-12.7 3100
-12.9 3200
-13.0 3300
-13.2 Date Of Update
.J.2.J.1.!lJ '-""
2 Figure C.4 Rev. 0 Page 1 of 1
': St. Lucie Unit 2 Cycle 17 HFP Moderator Temperature Coefficient vs Burnup Burnup MTC Burnup-MTC
-Bufnup M"'fC I (EFPH) (pcmfF);,
(EFPH)- (pcmf'F)-
(EFPH) (pcmrF)
I 3400
-13.3 6600
-18.1 9800
-24.3 3500-
-13.5 6700
-t82 J 9900
-24.6 3600
-13.7 6800
-18.4 10000-
-24.8 3700
-13.8 6900
-18.5 10100
-25.0 3800
-14.0 7000
-18.7 10200
-25.2 3900
-14.1 7100
-18.9 10300
-25.5 4000
-14.3 7200
-19.0 10400
-25.7 4100
-14.4 7300
-19.2 10500
-25.9 4200
-14.6 7400
-19.4 10600
-26.2 4300
-14.7 7500
-19.5 10700
-26.4 4400
-14.9 7600
-19.7 10800
-26.6 4500
-15.0 7700
-19.9 j090n I
-26.9 4600
-15.2 7800
-20.1 11QOO
--27.1 4700
-15.3 7900
-20.3 11100
-27.3 4800
-15.5 8000
-20.5 11200
-27.6 4900
-15.6 8100
-20.7 11300
-27.8 5000
-15.8 8200
-20.9 11400
-28.0 5100
-15.9 8300
-21.1 11500
-28.3 5200
-16.1 8400
-21.3 11600
-28.5 5300
-16.2 8500
-21.5 11694
-28.7 5400
-16.4 8600
-21.7 5500
-16.5 8700
-21.9 5600
-16.6 8800
-22.1 5700
-16.8 8900
-22.3 5800
-16.9 9000
-22.5 5900
-17.1 9100
-22.8 6000
-17.2 9200
-23.0 6100
-17.3 9300
-23.2 6200
-17.5 9400
-23.4 6300
-17.6 9500
-23.6 6400
-17.8 9600
-23.9 6500
-17.9 9700
-24.1
Reference:
PSL-2FJF-07-182 Rev. 0, Attachment 1 Page 14 PSL-ENG-SEFJ-07-011 Rev. 0, Attachment 1 Page 200
100 90 80.~.
70
-C 60 III
~
0 50 Q....
0..
U
/II III 40 a::
30 20 10 0
o 20 40 Bank 3 Date Of Update: ~/_1JLJ 0-:]
60 o
80 20 100 40 Figure C.S Rev. 0 St. lucie Unit 2 Cycle 17 Two Stuck CEA POlL 120 60 137 0
80 100 Bank4 20 120 40 t
Op ratic (SO,O)
I 1/
60 137
/',.
I (137,40)
/
/
i n Pr hibit ~d V
I V
80 V
/
100
/
120 Bank 5
Reference:
PSL-2FJF-07-173 Rev. 0 Page 1 PSL-ENG-SEFJ-07-011 Rev. 0 Page 201