ML030840277
ML030840277 | |
Person / Time | |
---|---|
Site: | Brunswick |
Issue date: | 09/09/2002 |
From: | Ernstes M Operator Licensing and Human Performance Branch |
To: | Keenan J Carolina Power & Light Co |
References | |
-RFPFR, 50-324/03-301, 50-325/03-301 | |
Download: ML030840277 (204) | |
See also: IR 05000325/2003301
Text
Final Submittal
BRUNSWICK EXAM
50-2003-301
50-325 & 50-324
FEBRUARY 10 - 14 & 19, 2003
1. Administrative Questions/JPMs
2. In-plant JPMs
3. Control Room JPMs (simulator JPMs)
Administrative Topics Outline Form ES-301-1 (R8, S1)
Facility: Brunswick _______Date
of Examination: _February 2003
Examination Level (circle one): RO / SRO Operating Test Number:
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
I.'3 ToI-n Administrntive Questions
I I*{*rl[lll()l I
A.1 GEN JPM Complete Jet Pump Operability per OPT-13.1 Note: Data
failed Jet Pump.
A.1.1 2.1.33/2.2.12 will indicate a
(4.0)
A.1.2 GEN JPM
2.2.32/2.2.27 Using a prepared, partial view of the newly refueled core and
(3.5) Core Loading Plan, determine if the core loading has been done
correctly.
A.2 GEN JPM
2.2.14/2.2.11 Given an approved Temporary Change (TC) complete SRO
(3.0) responsibilities for installation per OOLP-22.
A.3 GEN JPM
2.3.6 Given data provided by the on-shift Chemistry Technician, issue
(3.1) a Liquid Radwaste Discharge per OOP-06.4
A.4 I GEN JPM
2.4.40 Determine Off-Site Release Per PEP-03.4.7 and Recommend
(4.0) Protective Actions.
2003 ES-301-1
O:\Brunswick Examinations\lnitial Exam 2003-301\QA forms\Brunswick
Administrative Topics Outline SRO (final).wpd
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-AI-1
LESSON TITLE: Evaluate Jet Pump Performance Per PT-1 3.1.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Evaluate Jet Pump Performance Per PT-1 3.1.
Special Instructions
Transfer the following da ta onto a current revision of PT-1 3.1:
Reactor power level 96.6%
Recirc Pump A speed 8 8%
Recirc Pump B speed 8 8%
Recirc Pump A Flow 5 2 gpm X 1000
Recirc Pump B Flow 4 3 gpm X 1000
Jet Pump Loop A 3 0 mlbm/hr
Jet Pump Loop B 39 mlbm/hr
E
Attachment 2, Work She et 1
Loop A Loop B
JP 1 -30% JP-11 -40%
JP-2 - 32% JP-12 -42%
JP-3 - 31% JP-13 - 39%
JP-4 - 33% JP-14 - 43%
JP-5 - 32% JP-15 -40%
JP-6 - 33% JP-16 - 38%
JP-7 -31% JP-17 - 39%
JP-8 - 32% JP-18 - 38%
JP-9 - 25% JP-19 - 39%
JP-10 -21% JP-20 - 42%
NOTE: Average of Loop A is 30.0%, Loop B is 40%
3A1I-1 Page 2 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
SAFETY CONSIDERATIONS
None
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
1. Unit Two (2) is operating at power.
2. OPT-13.1, Reactor Recirculation Jet Pump Operability is being performed.
3. Another operator has recorded data required for the PT in Section 7.3, and on
Attachment 2, Test Information Work Sheet 1. Attachment 2, Work Sheet 2 is not to be
used.
INITIATING CUE:
You are directed to evaluate the data for Jet Pump performance, determine if acceptance
criteria is met, and inform the Unit SCO of the results.
3A1-1 Page 3 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-13.1.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step I - Obtain a current revision of OPT-13.1 and 20P-02.
Current Revision of OPT-13.1 and 20P-02 obtainedand verified, if applicable.
SATIUNSAT*
NOTE: The following steps requires evaluation of curves located in 20P-02, Figures 4.1, 4.2,
5.1, 5.2 and 6.1 through 6.10.
Step 2 - Confirm Recirc Pump A flow is within the band of the established curves.
Determine Recirc Pump A flow is NOT within the band of 20P-02, Figure 4.1.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Confirm Recirc Pump B flow is within the band of the established curves.
Determine Recirc Pump A flow is within the band of 20P-02, Figure 4.2.
SAT/UNSAT*
Step 4 - Confirm Jet Pump loop A flow is within the band of the established curves.
Determine Jet Pump Loop A flow is NOT within the band of 20P-02, Figure 5.1.
- CRITICAL STEP ** SAT/UNSAT*
3A1-1 Page 4 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
Step 5 - Confirm Jet Pump loop B flow is within the band of the established curves.
Determine Jet Pump Loop A flow is within the band of 20P-02, Figure 5.2.
SAT/UNSAT*
Step 6 - Calculate average jet pump % psid for each loop.
Determines Loop A average is 30% and Loop B average is 40%.
SAT/UNSAT*
Step 7 - Compare the % psid for each jet pump and calculated average jet pump % psid for
each loop with the established curves (20P-02, Figures 6.1 through 6.10).
Determinejet pump 10 falls outside the establishedcurve in 20P-02, Figure 6.5
(all otherjetpumps within limits)
- CRITICAL STEP ** SAT/UNSAT*
Step 8 - Inform Unit SCO that jet pump 10 fails to meet acceptance criteria.
Unit SCO informedjet pump 10 fails to meet acceptance criteria.
SAT/UNSAT*
WA-1 Page 5 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
PROMPT: For SRO examinees only, direct the examinee to determine any action required by
ITech Specs i1
.6
II NOTE: The following step is applicable to sRO examinees only i'
Step 9 - Determine that LCO 3.4.2 is not met, condition A applies, requiring the unit to be
placed in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Determines that LCO 3.4.2 is not met, condition A applies, requiringthe unit to
be placed in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: If desired, the examiner may ask the examinee the safety implications of a failed jet
pump. Invalidates LOCA analysis (due to loss of core reflooding to 2/3 core height
and/or increased blowdown area).
TERMINATING CUE: When examinee has evaluated jet pump operability per PT-1 3.1 (and
determined Tech Spec actions if applicable) this JPM is complete. I
- Comments required for any step evaluated as UNSAT.
3A1-1 Page 6 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
RELATED TASKS:
202001B201, Perform Reactor Recirculation Jet Pump Operability Test Per PT-1 3.1
K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.1.33 3.4/4.0
GEN 2.2.12 3.0/3.4
REFERENCES:
OPT-13.1
TOOLS AND EQUIPMENT:
Calculator.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
Admin Al - Conduct Of Operations
REASON FOR REVISION:
New JPM.
3A1-1 Page 7 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual A- Unit: 2
Setting: Control Room Simulator (Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes No z
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
'V
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
WA-11 Page 8 of 9 REV. 0
TASK CONDITIONS:
1. Unit Two (2) is operating at power.
2. OPT-13.1, Reactor Recirculation Jet Pump Operability is being performed.
3. Another operator has recorded data required for the PT in Section 7.3, and on
Attachment 2, Test Information Work Sheet 1. Attachment 2, Work Sheet 2 is not to be
used.
INITIATING CUE:
You are directed to evaluate the data for Jet Pump performance, determine if acceptance
criteria is met, and inform the Unit SCO of the results.
\3/4 ..
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-AI-2
LESSON TITLE: Evaluate Partial View Of Core For Correct Core Loading.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Evaluate Partial View Of Core For Correct Core Loading.
SPECIAL INSTRUCTIONS
Prepare a picture of a partial core (4 cells - 16 Bundles).
Ensure 1 bundle is rotated 180o.
Ensure each bundle has a different serial number on the bail handle.
Prepare a core loading sequence sheet for the 16 bundles.
Ensure 2 of the bundles are in the incorrect location (but properly oriented).
SAFETY CONSIDERATIONS:
None
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. Provide examinee with copy of prepared partial core view, prepared core load sequence
sheets, and reactor vessel core map (ENP-24.12, Figure 1).
Read the following to trainee.
TASK CONDITIONS:
1. Unit 2 is in Mode 5. Core reload has just been completed.
2. You have a partial view of the reloaded core, along with the Core Component
Sequence Sheets for those bundles, and Figure 1 from ENP-24.12, Reactor Vessel
Core Map.
INITIATING CUE:
You are directed by the Shift Superintendent to evaluate the partial core loading for core
verification and inform the Shift Superintendent of the results.
3Als Page 2 of 7 REV. 0
Evaluate Partial View Of Core For Correct Core Loading.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Evaluate partial Core View, Core Component Sequence Sheets for those bundles,
and Figure 1 from ENP-24.12, Reactor Vessel Core Map.
PartialCore View, Core Component Sequence Sheets for those bundles, and
Figure 1 from ENP-24.12, Reactor Vessel Core Map evaluated.
SAT/UNSAT*
NOTE: It is critical that the examinee identifies the two bundles incorrectly loaded. It is NOT I
critical the examinee identifies the locations are swapped.
Step 2 - Identify that bundle LYJ568 (Step 5 of the Core Component Sequence Sheets) is
specified for location 9-10 but bundle LYJ468 is loaded in that location.
Identify that bundle LYJ568 (Step 5 of the Core Component Sequence Sheets) is
not loaded in the correctlocation.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Identify that bundle LYJ468 (Step 10 of the Core Component Sequence Sheets) is
specified for location 13-10 but bundle LYJ568 is loaded in that location.
Identify that bundle LYJ468 (Step 10 of the Core Component Sequence Sheets)
is not loaded in the correct location.
- CRITICAL STEP ** SAT/UNSAT*
WAs Page 3 of 7 REV. 0
Evaluate Partial View Of Core For Correct Core Loading.
Step 3 - Identify that bundle LYJ549 (Step 19 of the Core Component Sequence Sheets) is
loaded in the incorrect orientation and that the Fastener location should be
Southeast (as specified on the Core Component Sequence Sheets and not
Northwest as shown in the partial core view (or that the bundle is rotated 180o).
Identify that bundle LYJ549 (Step 19 of the Core Component Sequence Sheets)
is loaded in the incorrectorientation.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: All other bundles are correctly loaded; however whoever loaded these 16 bundles
will surly lose his/her SRO license.
Step 4 - Identifies all other bundles are correctly loaded.
Identifies all other bundles are correctly loaded.
SAT/UNSAT*
Step 5 - Inform Shift Superintendent of results of partial core verification.
Shift Superintendentinformed of results of partialcore verification.
SAT/UNSAT*
TERMINATING CUE: When evaluation of the partial core load has been competed, this JPM
is complete.I
- Comments required for any step evaluated as UNSAT.
3Al1s Page 4 of 7 REV. 0
Evaluate Partial View Of Core For Correct Core Loading.
RELATED TASKS:
None
K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.2.32 3.5
REFERENCES:
ENP-24.12
ENP-24.13
FH-11
TOOLS AND EQUIPMENT:
None
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
Admin Section Al
REASON FOR REVISION:
New JPM.
3A1ls Page 5 of 7 REV. 0
Evaluate Partial View Of Core For Correct Core Loading.
Time Required for Completion: 20 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate -4 Actual Unit: 2
Setting: Control Room Simulator (Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes No ,*
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3A1ls Page 6 of 7 REV. 0
TASK CONDITIONS:
1. Unit 2 is in Mode 5. Core reload has just been completed.
2. You have a partial view of the reloaded core, along with the Core Component
Sequence Sheets for those bundles, and Figure 1 from ENP-24.12, Reactor Vessel
Core Map.
INITIATING CUE:
You are directed by the Shift Superintendent to evaluate the partial core loading for core
verification and inform the Shift Superintendent of the results.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-A2
LESSON TITLE: Evaluate Proposed Temporary Change.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Evaluate Proposed Temporary Change.
Special Instructions
Obtain copies of prints D-02549, Sheet 1B, 2-FP-05924, Sheet 2, LL-09243, Sheet 15 and
LL09244, Sheet 15
On D-02549, change V35 and V36 to show closed, and denote valves closed per EC TC
On 2-FP-9524, Sheet 2, draw cloud around G41-N005 connections INC and 1C, denote
leads lifted per EC TC 03-001.
On 2-FP-9524, Sheet 2, draw cloud around G41-NO05 connections 2NC and 2C, denote
leads lifted per EC TC 03-001.
On LL-09243, Sheet 15, draw jumper from terminals 2-H02/CC5 to 2-H02/AA1 1. Denote
jumper installed per TC EC 03-001.
On LL-09244, Sheet 15, draw jumper from terminals 2-H02/CC17 to 2-H02/BB14. Denote
jumper installed per TC EC 03-001.
Mark up EGR-NGGC-005, Form 2 to reflect temporary changes.
03-A2 Page 2 of 9 REV. 0
Evaluate Proposed Temporary Change.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL NOT be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. This JPM may be administered in any setting.
Read the following to trainee.
TASK CONDITIONS:
1. Unit Two (2) Fuel Pool Cooling Skimmer Surge Tank low level alarm switch 2-G41-LSL
N005 has failed. The shelf condition of this level switch is closed. This failed level
switch has resulted in Annunciator A-4 6-7 (Fuel Pool Cooling Alarm) being sealed in on
Panel P603.
2. The failed level switch is obsolete. A temporary change has been developed in
accordance with EGR-NGGC-0005 to abandon this level switch in place until a suitable
replacement can be located and installed.
3. This temporary change is to valve out the failed level switch and lift leads and/or jumper
the level switch contacts. This temporary change will defeat the level switch input to
Annunciator A-4 6-7 (a multiple input Annunciator). This temporary change will also
defeat low level indicating lights located on local panels 2-G41P001 and 2-G41-P002.
The low level trip function for the Fuel Pool Cooling Pumps will not be affected.
4. A Temporary Change Log form (EGR-NGGC-0005, Form 2) has been prepared
indicating a description of this temporary change and the Priority 0 drawings affected.
The Priority 0 drawings referenced have been marked up to reflect the temporary
change.
03-A2 Page 3 of 9 REV. 0
Evaluate Proposed Temporary Change.
INITIATING CUE:
You are directed by the WCC SRO to review the marked up Priority 0 drawings identified
on the Temporary Change Log Form 2 and ensure the changes reflected on the identified
Priority 0 drawings meet the intent of the temporary change, and inform the WCC SRO of
the results of your evaluation.
03-A2 Page 4 of 9 REV. 0
Evaluate Proposed Temporary Change.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Review Temporary Change Log, Form 2 and evaluate drawings listed as Priority 0 on
the Log.
Reviews Temporary Change Log, Form 2 and evaluate drawingslisted as
Priority0 on the Log.
SAT/UNSAT*
Step 2 - Determine jumper installed from terminals 2-H02/CC5 to 2-H02/AA1 1 on drawing LL
09243, Sheet is for level switch N006, not N005 and should not be installed.
Determinesjumper should not be installedfrom terminals 2-H02/CC5 to 2
H02/AA 11 on LL-09243, Sheet 15.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Determine jumper installed from terminals 2-H02/CC17 to 2-H02/BB23 on drawing
LL-09244, Sheet is for level switch N006, not N005 and should not be installed.
Determinesjumper should not be installed from terminals 2-H02/CCI7 to 2
H02/BB23 on LL-09244, Sheet 15.
- CRITICAL STEP ** SAT/UNSAT*
03-A2 Page 5 of 9 REV. 0
Evaluate Proposed Temporary Change.
Step 4 - Determine other drawing changes meet the intent of the TC.
Determines other drawing changes meet the intent of the TC.
- CRITICAL STEP ** SAT/UNSAT*
Step 5 - Inform WCC SRO of results.
SAT/UNSAT*
3/4>
TERMINATING CUE: This box will tell the evaluator when the JPM is complete based on
student performance. I
- Comments required for any step evaluated as UNSAT.
03-A2 Page 6 of 9 REV. 0
Evaluate Proposed Temporary Change.
RELATED TASKS:
200 665 B5 04, Perform AO Actions For A Loss Of Division I DC Panels Per AOP-39.0
K/A REFERENCE AND IMPORTANCE RATING:
295004 AA1.01 3.3/3.4
Ability to operate D.C. electrical distribution systems as it applies to Partial Loss of D.C.
power.
REFERENCES:
AOP-39.0, Revision 11
Loss of DC Power
TOOLS AND EQUIPMENT:
Plant Page.
Keys.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
6 - Electrical (DC Electrical Distribution)
REASON FOR REVISION:
Renamed from AOR to ACT, changed format to WORD from WP 5.1, updated for
procedure revision, changed to support either unit, removed record of revision page.
03-A2 Page 7 of 9 REV. 0
Evaluate Proposed Temporary Change.
Time Required for Completion: 30 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate , Actual Unit: 2
Setting: Control Room Simulator (Not applicable to In-Plant JPMs)
Time Critical: Yes Noo 4 Time Limit N/A
Alternate Path: Yes No j
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
03-A2 Page 8 of 9 REV. 0
K->
TASK CONDITIONS:
1. Unit Two (2) Fuel Pool Cooling Skimmer Surge Tank low level alarm switch 2-G41-LSL
N005 has failed. The shelf condition of this level switch is closed. This failed level
switch has resulted in annunciator A-4 6-7 (Fuel Pool Cooling Alarm) being sealed in on
Panel P603.
2. The failed level switch is obsolete. A temporary change has been developed in
accordance with EGR-NGGC-0005 to abandon this level switch in place until a suitable
replacement can be located and installed.
3. This temporary change is to valve out the failed level switch and lift leads and/or jumper
the level switch contacts. This temporary change will defeat the level switch input to
annunciator A-4 6-7 (a multiple input annunciator). This temporary change will also
defeat low level indicating lights located on local panels 2-G41 P001 and 2-G41-P002.
The low level trip function for the Fuel Pool Cooling Pumps will not be affected.
4. A Temporary Change Log form (EGR-NGGC-0005, Form 2) has been prepared
indicating a description of this temporary change and the Priority 0 drawings affected.
The Priority 0 drawings referenced have been marked up to reflect the temporary
change.
INITIATING CUE:
You are directed by the WCC SRO to review the marked up Priority 0 drawings identified
on the Temporary Change Log Form 2 and ensure the changes reflected on the identified
Priority 0 drawings meet the intent of the temporary change, and inform the WCC SRO of
the results of your evaluation.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-A3-SRO
LESSON TITLE: Evaluate Liquid Discharge Release Permit.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Evaluate Liquid Discharge Release Permit.
Special Instructions
Prepare a Liquid Release Permit, OP-06.4, Attachment 4. Complete Part I, Part IIand Part
III up to the Unit SCO approval line.
Ensure required recirc time and sample taken time is filled in prior to the actual time
required by OP-06.4.
The remainder of the data should be correct.
Fill out OE&RC-2009, Attachment 2, Part I. Ensure sample time matches time specified in
the OP-06.4, Attachment 4.
Obtain a copy of an E&RC Pre-Release Permit.
An actual release may be obtained from the E&RC counting room to aid in filling out the
required data.
3A3s Page 2 of 8 REV. 0
Evaluate Liquid Discharge Release Permit.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee.
2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. Provide examinee with prepared copy of OOP-06.4, Attachment 4, OE&RC-2009,
Attachment 2, and the E&RC Pre-Release Permit.
Read the following to trainee.
TASK CONDITIONS:
1. The Unit 1 Salt Water Release Tank is nearing capacity, and is scheduled to be
released.
2. A Radioactive Liquid Release Permit has been prepared in accordance with OOP-06.4.
3. A Pre-Release Permit has been prepared by E&RC in accordance with E&RC-2009.
INITIATING CUE:
You are directed by the Shift Superintendent to review the Radioactive Liquid Release
Permit, and the Pre-Release Permit, and determine if the Unit 1 Salt Water Release Tank
can be released per the supporting documentation, and inform the Shift Superintendent of
the results of your review.
3A3s Page 3 of 8 REV. 0
Evaluate Liquid Discharge Release Permit.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
NOTE: The examiner should have a copy of OOP-06.4, Section 5.7 to provide to the
examinee if requested, or allow examinee access to the entire procedure.
I
Step 1 - Obtain a current revision of OOP-06.4.
Current Revision of OOP-06.4 obtained and verified, if applicable.
SAT/UNSAT*
Step 2 - Determine Volume of U/1 SWRT at level of 79% is correct as specified on the
Radioactive Liquid Release Permit.
Determinedthat volume of U/1 SWRT of 28637.5 gallons is correct as specified
on the Radioactive Liquid Release Permit.
SAT/UNSAT*
Step 3 - Determine required Recirculation time for a U/1 SWRT at a tank level of 79% is
correct as specified on the Radioactive Liquid Release Permit.
Determined that requiredRecirculationtime for the U/1 SWRT at a tank level of
79% of 316 minutes is correctas specified on the Radioactive Liquid Release
Permit.
SAT/UNSAT*
3A3s Page 4 of 8 REV. 0
Evaluate Liquid Discharge Release Permit.
Step 4 - Determine with a Start Recirculation time of 0040, the required Recirc completion
time should be 0556 (not 0546) and that the sample taken time must be after 0556
(not 0553) as specified on the Radioactive Liquid Release Permit.
Determines requirementsfor Recirculationtime and/or sample time per OOP
06.4 have not been satisfied, and that the release should not be approved.
- CRITICAL STEP ** SAT/UNSAT*
Step 5 - Informs Shift Superintendent that the Release Permit may not be approved.
Shift Superintendentinformed that the Release Permit may not be approved.
SATIUNSAT*
TERMINATING CUE: When the Radioactive Liquid Release Permit has been evaluated as
11 unsatisfactory, this JPM is complete.
- Comments required for any step evaluated as UNSAT.
3A3s Page 5 of 8 REV. 0
Evaluate Liquid Discharge Release Permit.
RELATED TASKS:
341012B302, Review Radioactive Waste Discharge/Release Permits Per E&RC-2009 prior
To Approval.
K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.3.6 3.1
REFERENCES:
OOP-06.4
OE&RC-2009
BSEP Radioactive Liquid Release Permit 02-0044
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
Admin A3
REASON FOR REVISION:
New JPM.
3A3s Page 6 of 8 REV. 0
Evaluate Liquid Discharge Release Permit.
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate -4- Actual Unit: __
Setting: Control Room Simulator (Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes No 4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
Did Trainee Verify Procedure as Authorized Copy?: Yes - No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3A3s Page 7 of 8 REV. 0
V
TASK CONDITIONS:
1. The Unit 1 Salt Water Release Tank is nearing capacity, and is scheduled to be
released.
2. A Radioactive Liquid Release Permit has been prepared in accordance with OOP-06.4.
3. A Pre-Release Permit has been prepared by E&RC in accordance with E&RC-2009.
INITIATING CUE:
You are directed by the Shift Superintendent to review the Radioactive Liquid Release
Permit, and the Pre-Release Permit, and determine if the Unit 1 Salt Water Release Tank
can be released per the supporting documentation, and inform the Shift Superintendent of
the results of your review.
<2 CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-A4-SRO
LESSON TITLE: Determine Off-Site Release Per PEP-03.4.7 And Recommend
Protective Actions.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. This JPM may be performed in any location with a computer loaded with the CPL
Dose program.
4. Transfer data from attachment 2 of this JPM handwritten onto an actual attachment
from PEP-03.4.7.
5. The release at the site boundary should be approximately 6.38 E+01 mrem TEDE
and 1.99 E+02 mrem CDE. Slight variances may be expected due to time data is
entered in relation to Reactor shutdown. (Dose requires declaration of Site Area
Emergency, however General Emergency EALs have been exceeded)
3A4s Page 2 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
Read the following to trainee.
TASK CONDITIONS:
1. A General Emergency has been declared due to a steam line break in the Turbine
Building on Unit 1. One set of MSIVs has failed to close and there are indications of
fuel failure.
2. The operating crew is currently executing the Radioactivity Release Control EOP, and
Steam Cooling Procedure due to loss of all RPV injection sources. RPV level has been
below TAF for 15 minutes and below LL4 for 5 minutes.
3. Drywell High Range Radiation Monitors are reading 10,000 R/Hr at the 50' elevation,
and 2000 R/Hr at the 20' elevation.
4. The Unit 1 reactor initially failed to scram, but was successfully scrammed 15 minutes
ago.
5. Attachment 2 of PEP-3.4.7 has been filled out for data entry.
INITIATING CUE:
You are directed by the Shift Superintendent (SEC) to:
1. Perform an initial dose calculation per PEP 03.4.7, Automation of Off-Site Dose
Projection procedure. You are to determine the EAL classification for the RADIATION
RELEASE for execution of the Radiation Release Control EOP.
2. Determine required Protective Action Recommendations per OPEP-02.6.28 for the
emergency in progress.
You are to inform the Shift Superintendent (SEC) of the results of your assessments.
3A4s Page 3 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
ATTACHMENT 2
Data Sheet for Dose Projection Inouts
CHARACTERISTIC TIME
Main Stack Release Rate (klCi/Sec) 2.4e6
Flow Rate (CFM) 40000
Turbine Building #1 Release Rate (pCi/Sec) 5.2E6
- 1 Flow Rate (CFM) 15000
- 2 Release Rate (iCi/Sec) 5.2E6
- 2 Flow Rate (CFM) 15000
Reactor Building Release Rate (CPM) 315E2
Flow Rate (CFM) 0
Torus Vent Release Rate (RCi/Sec) 0
Core Uncovered Time (1) lost/ (2) Returned
Effective Filtration Yes / No Yes
Reloeas Ganf(rond Yesl
Elevated Yes
Release Duration Anticipated Length of Time 1 Hours
Shutdown Date
Time
Met Data Wind Speed Upper 5 MPH
Lower 4 MPH
Met Data Direction Upper 77 DEG
Lower 75 DEG
Stability Class B
Seabreeze Yes / No No
3A4s Page 4 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of PEP-03.4.7.
CurrentRevision ofPEP-03.4.7 obtained.
SAT/UNSAT*
Step 2 - Access the Dose Projection program.
Dose ProjectionProgram accessed.
SAT/UNSAT*
NOTE: The attached sheets show the three screens for CPL DOSE program (answer key)
and the expected inputs (with 'exception of time)
Slight variances may be expected due to time data is entered in relation to Reactor
shutdown
Step 3 - Enter data from PEP-03.4.7 attachment into the dose projection program.
Data correctly entered into the dose projection program.
SAT/UNSAT*
3A4s Page 5 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
Step 4 - Determine highest off-site dose is approximately 6.38E+01 TEDE and 1.99E+2 CDE
both at the site boundary.
Determined that projected dose at site boundary is . 6.38 mrem TEDE and
1.99+02 mrem CDE.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: The EAL for the release (Site Area Emergency) is on bottom right of last display
(results display) of Dose program and on last page of printout. The examinee may
releaseper OPEP-02.1, Attachment 1, Section 4, or the EAL flowchart. (EAL
04.03.01).
Step 5 - Determine projected dose at the site boundary meets the EAL for a Site Area
Emergency.
Determine projected dose at the site boundary meets the EAL for a Site Area
Emergency.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: The EAL forth? release is a Site Area Emergency. However, since a General
Emergency has been declared, Protective Action Recommendations (PAR) are
required per OPEP-02.6.28. Since release does not exceed GE EAL, the Guidance
inAttachment 2 does not need to be modified.
I
Step 6 - Refer to OPEP-02.6.28 Determine with current met data that OPEP-02.6.28 requires
a PAR to evacuate zones A,B,C,D,E and shelter zones F,G,HK.
Determines with current met data that OPEP-02.6.28requires a PAR to evacuate
zones A, B, C, D,E and shelterzones F,G,H,K.
- CRITICAL STEP ** SAT/UNSAT*
3A4s Page 6 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
PROMPT: When the PAR has been determined, hand examinee extra attached final
printout from a dose projection. Inform examinee that it is now one hour later,
and another operator has performed a dose projection, and direct the examinee
to determine the EAL classification for the RADIATION RELEASE for execution
of the Radiation Release Control EOP.
NOTE The last sheet shows a projected dose of 1.79E+03 TEDE and 6.75E+03 CDE
which exceeds the EAL for a General Emergency. The EAL block of this form
has been deliberately deleted to force the examinee to evaluate EALs. EALs
may be evaluated using OPEP-02.1, or the EAL flow chart
Step 7 - Determine second dose projection requires declaration of a General Emergency for
the Radiation Release using PEP-02.1 or the EAL flow chart.
Determines the release is at the General Emergency Classification.
- CRITICAL STEP ** SAT/UNSAT*
Step 8 - Notifies Shift Superintendent of results.
Shift Superintendentnotified of off-site dose projection, PAR and EAL results.
SAT/UNSAT*
TERMINATING CUE: When the off§ite dose projection has been performed and lines 12 & 13 I
of the Emergency Notification form are filled in, this JPM is complete. I
- Comments required for any step evaluated as UNSAT.
3A4s Page 7 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
RELATED TASKS:
344 058 B3 02
K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.4.40 4.0
REFERENCES:
OPEP-03.4.7
OPEP-02.1
OPEP-02.6.28
TOOLS AND EQUIPMENT:
Computer loaded with CPL Dose.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
Administrative - Emergency Plan
REASON FOR REVISION:
New JPM.
3A4s Page 8 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual 4 Unit: 2
Setting: Control Room Simulator ( Not applicable to In-Plant JPMs)
Time Critical: Yes No Time Limit N/A
Alternate Path: Yes No 4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
Did Trainee Verify Procedure?: Yes __ No
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3A4s Page 9 REV. 0
TASK CONDITIONS:
1. A General Emergency has been declared due to a steam line break in the Turbine
Building on Unit 1. One set of MSIVs has failed to close and there are indications of
fuel failure.
2. The operating crew is currently executing the Radioactivity Release Control EOP, and
Steam Cooling Procedure due to loss of all RPV injection sources. RPV level has been
below TAF for 15 minutes and below LL4 for 5 minutes.
3. Drywell High Range Radiation Monitors are reading 10,000 R/Hr at the 50' elevation,
and 2000 R/Hr at the 20' elevation.
4. The Unit 1 reactor initially failed to scram, but was successfully scrammed 15 minutes
ago.
5. Attachment 2 of PEP-3.4.7 has been filled out for data entry.
INITIATING CUE:
You are directed by the Shift Superintendent (SEC) to:
1. Perform an initial dose calculation per PEP 03.4.7, Automation of Off-Site Dose
Projection procedure. You are to determine the EAL classification for the RADIATION
RELEASE for execution of the Radiation Release Control EOP.
2. Determine required Protective Action Recommendations per OPEP-02.6.28 for the
emergency in progress.
You are to inform the Shift Superintendent (SEC) of the results of your assessments.
Administrative Topics Outline Form ES-301-1 (R8, S1)
Facility: -Brunswick Date of Examination: _February 2003
RO / SRO Operating Test Number:
Examination Level (circle one):
Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR
Description 2. TWO Administrative Questions
A.1 GEN JPM Complete Jet Pump Operability per OPT-13.1 Note: Data
2.1.33/2.2.12 will indicate a failed Jet Pump.
A.1.1
(4.0)
GEN JPM Evaluate Overtime Eligibility
A.1.2 2.1.5 (2.3/3.4)
A.2 GEN
2.2.14/2.2.11 Given an approved Temporary Change (TC) make the
(2.5) necessary changes to the applicable drawings.
A.3 GEN 1.. You have been notified by the Refuel Floor SRO that a
2.3.10 spent fuel element has just dropped into the fuel pool
(2.9/3.0) and he is evacuating the reactor building.
A. What action must you take to protect yourself
2.3.1 from any ensuing radiation? (.5)
(2.6/3.0) B. How long do you have to accomplish this? (.3)
And
C. What is the allowable stay time in the Control
Room. (.2) Cite References.
2. Determine which operator of obtains a lower dose for 2
operators using different paths.
JPM Estimate Release from Unit 1 Reactor Building and
Turbine Building Per PEP-03.6.1.
I I
1/2-'
2003 ES-301-1
O:\Brunswick Examinations\lnitial Exam 2003-301\QA forms\Brunswick
Administrative Topics Outline RO (final).wpd
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
LESSON TITLE: Evaluate Jet Pump Performance Per PT-1 3.1.
REVISION NO: 0
RECOMMENDED BY
Instructor/Developer DATE
CONCURRENCE BY:
I inn Riiunrintendent/Suiiervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Evaluate Jet Pump Performance Per PT-1 3.1.
Special Instructions
Transfer the following data onto a current revision of PT-13.1:
Reactor power level 96.6%
Recirc Pump A speed 88%
Recirc Pump B speed 88%
Recirc Pump A Flow 52 gpm X 1000
Recirc Pump B Flow 43 gpm X 1000
Jet Pump Loop A 30 mlbm/hr
Jet Pump Loop B 39 mlbm/hr
Attachment 2, Work Sheet I
Loop A Loop B
JP 1 -30% JP-11 -40%
JP-2 - 32% JP-12 - 42%
JP-3-31% JP-13- 39%
JP-4 - 33% JP-14 - 43%
JP-5 - 32% JP-15 - 40%
JP-6 - 33% JP-16 - 38%
JP-7 - 31% JP-17-39%
JP-8 - 32% JP-18 - 38%
JP-9 - 25% JP-19 - 39%
JP-10 - 21% JP-20 - 42%
NOTE: Average of Loop A is 30.0%, Loop B is 40%
3A1I-1 Page 2 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
SAFETY CONSIDERATIONS
None
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
1. Unit Two (2) is operating at power.
2. OPT-13.1, Reactor Recirculation Jet Pump Operability is being performed.
3. Another operator has recorded data required for the PT in Section 7.3, and on
Attachment 2, Test Information Work Sheet 1. Attachment 2, Work Sheet 2 is not to be
used.
INITIATING CUE:
You are directed to evaluate the data for Jet Pump performance, determine if acceptance
criteria is met, and inform the Unit SCO of the results.
3A1-1 Page 3 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-13.1.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of OPT-13.1 and 20P-02.
Current Revision of OPT-13.1 and 20P-02 obtainedand verified, if applicable.
SAT/UNSAT*
NOTE: The following steps requires evaluation of curves located in 20P-02, Figures 4.1, 4.2,
5.1 52and 6.1 through 6.10.
Step 2 - Confirm Recirc Pump A flow is within the band of the established curves.
Determine Recirc Pump A flow is NOT within the band of 20P-02, Figure 4.1.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Confirm Recirc Pump B flow is within the band of the established curves.
Determine Recirc Pump A flow is within the band of 20P-02, Figure 4.2.
SAT/UNSAT*
Step 4 - Confirm Jet Pump loop A flow is within the band of the established curves.
Determine Jet Pump Loop A flow is NOT within the band of 20P-02, Figure 5.1.
- CRITICAL STEP ** SAT/UNSAT*
WA-1 Page 4 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
Step 5 - Confirm Jet Pump loop B flow is within the band of the established curves.
Determine Jet Pump Loop A flow is within the band of 20P-02, Figure 5.2.
SAT/UNSAT*
Step 6 - Calculate average jet pump % psid for each loop.
Determines Loop A average is 30% and Loop B average is 40%.
SAT/UNSAT*
Step 7 - Compare the % psid for each jet pump and calculated average jet pump % psid for
each loop with the established curves (20P-02, Figures 6.1 through 6.10).
Determinejet pump 10 falls outside the establishedcurve in 20P-02, Figure 6.5
(all otherjet pumps within limits)
- CRITICAL STEP ** SAT/UNSAT*
Step 8 - Inform Unit SCO that jet pump 10 fails to meet acceptance criteria.
Unit SCO informedjet pump 10 fails to meet acceptance criteria.
SAT/UNSAT*
WA-1 Page 5 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
I
PROMPT: For SRO examinees only, direct thb:examinee to determine any action required by
Tech Specs -I
i
S.. . .. .
.5
I m
I NOTE: The following step is applicable to SRO examinees only II
Step 9 - Determine that LCO 3.4.2 is not met, condition A applies, requiring the unit to be
placed in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
Determines that LCO 3.4.2 is not met, condition A applies, requiring the unit to
be placed in Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: If desired, the examiner may ask the examinee the safety implications of a failed jet
pump. Invalidates LOCA analysis (due to loss of core reflooding to 2/3 core height
and/or increased blowdown area).
TERMINATING CUE: When examinee has evaluated jet pump operability per PT-1 3.1 (and
II determined Tech Spec actions if applicable) this JPM is complete.
- Comments required for any step evaluated as UNSAT.
3A1-1 Page 6 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-1 3.1.
RELATED TASKS:
202001 B201, Perform Reactor Recirculation Jet Pump Operability Test Per PT-1 3.1
K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.1.33 3.4/4.0
GEN 2.2.12 3.0/3.4
REFERENCES:
OPT-1 3.1
TOOLS AND EQUIPMENT:
Calculator.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
Admin Al - Conduct Of Operations
REASON FOR REVISION:
New JPM.
WA-1 Page 7 of 9 REV. 0
Evaluate Jet Pump Performance Per PT- 3.1.
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual A- Unit: 2
Setting: Control Room Simulator ( Not applicable to In-Plant JPMs)
Time Critical: Yes No _ Time Limit N/A
Alternate Path: Yes No -4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3A1-1 Page 8 of 9 REV. 0
TASK CONDITIONS:
1. Unit Two (2) is operating at power.
2. OPT-13.1, Reactor Recirculation Jet Pump Operability is being performed.
3. Another operator has recorded data required for the PT in Section 7.3, and on
Attachment 2, Test Information Work Sheet 1. Attachment 2, Work Sheet 2 is not to be
used.
INITIATING CUE:
You are directed to evaluate the data for Jet Pump performance, determine if acceptance
criteria is met, and inform the Unit SCO of the results.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-AI-2-RO
LESSON TITLE: Evaluate Overtime Eligibility.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Evaluate Overtime Eligibility.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL NOT be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
1. A startup of Unit 1 is planned for the following shift. One Reactor Operator must be
held over three hours for startup.
2. The following is the work history (excluding shift turnover time) of the available Reactor
Operators on shift (hours reflect those worked PRIOR to the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> holdover). A break
of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> occurred between all working periods. All operators began their shift
schedule at the same time each day.
3A1-2.r Page 2 of 9 REV. 0
Evaluate Overtime Eligibility.
DAY 1 2 3 4 5 6 7 8
Operator
- 1 0 4 12 10 10 14 10 11
Operator
- 2 0 12 10 12 3 12 8 13
Operator
- 3 0 0 12 12 12 8 8 14
Operator
- 4 0 8 12 10 10 8 10 11
Operator
- 5 0 0 12 14 12 10 13 10
NOTE: A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> has occurred between all work periods
INITIATING CUE:
Evaluate the work history for all 5 operators. Determine which operator(s), if any, can be
held over for three hours without prior overtime approval, and determine which operators
CANNOT be held over for three hours without prior overtime approval.
Also identify any deviations to OAP-001 that may have already occurred between Day 1
and Day 7 (assume no authorization to exceed OAP-001 limits)
3A1-2.r Page 3 of 9 REV. 0
Evaluate Overtime Eligibility.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step I - Obtain a current revision of OAP-001.
Current Revision of OAP-O01 obtained.
SAT/U NSAT*
NOTE: It is Critical that the examinee correctly determines which operators can be held over
for three hours, and which operators cannot without overtime authorization per OAP
001.
It is not critical that the examinee identify the specific limit that would be exceeded for
the operators who cannot be held over.
Step 2 - Determine Operator #1 would exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period and would require
overtime authorization.
Determines Operator#1 would require overtime authorization.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Determine Operator #2 would exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period and would require
overtime authorization.
Determines Operator#2 would require overtime authorization.
- CRITICAL STEP ** SATIUNSAT*
3A1-2.r Page 4 of 9 REV. 0
Evaluate Overtime Eligibility.
Step 4 - Determine Operator #3 would exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight and 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
period (today) and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period (days 7 and 8) and would require
overtime authorization.
Determines Operator#3 would require overtime authorization.
- CRITICAL STEP ** SATIUNSAT*
Step 5 - Determine Operator #4 would not exceed any overtime restrictions and could be held
over for the 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Determinedthat Operator#4 would not exceed any overtime restrictionsand could
be held over for the 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
SATlUNSAT*
Step 6 - Determine Operator #5 would exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period and would exceed
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7 day period and would require overtime authorization.
Determines Operator#5 would require overtime authorization.
- CRITICAL STEP ** SATIUNSAT*
3A1-2.r Page 5 of 9 REV. 0
Evaluate Overtime Eligibility.
PROMP: If sked, inform examineeithat no approved copy of OAP-OO1, Attachment 1,
exits for, Operator #5I
Step 7 - Determine Operator #5 has exceeded 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period (day 3 and 4, and
day 4 and 5).
Determinedthat Operator#5 exceeded 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period (day 3 and 4,
and day 4 and 5).
- CRITICAL STEP ** SAT/UNSAT*
TERM INATING CUE: When the examinee has evaluated overtime restrictions, this JPM is
complete..
- Comments required for any step evaluated as UNSAT.
3A1-2.r Page 6 of 9 REV. 0
Evaluate Overtime Eligibility.
RELATED TASKS:
Conduct shift turnover and relief
K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.1.5.
REFERENCES:
OAP-001
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
A.1 - Conduct Of Operations
REASON FOR REVISION:
New JPM for NRC exam.
3A1-2.r Page 7 of 9 REV. 0
Evaluate Overtime Eligibility.
Time Required for Completion: 10 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate ,4 Actual Unit:
Setting: Control Room Simulator (Not applicable to In-Plant JPMs)
Time Critical: Yes No --4-N- Time Limit N/A
Alternate Path: Yes No _4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes __ No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3A1-2.r Page 8 of 9 REV. 0
Applicant Sheet
TASK CONDITIONS:
1. A startup of Unit 1 is planned for the following shift. One Reactor Operator must be
held over three hours for startup.
2. The following is the work history (excluding shift turnover time) of the available Reactor
Operators on shift (hours reflect those worked PRIOR to the 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> holdover). A break
of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> occurred between all working periods. All operators began their shift
schedule at the same time each day.
DAY 1 2 3 4 5 6 7 8
Operator
- 1 0 4 12 10 10 14 10 11
Operator
- 2 0 12 10 12 3 12 8 13
Operator
- 3 0 0 12 12 12 8 8 14
Operator
- 4 0 8 12 10 10 8 10 11
Operator
- 5 0 0 12 14 12 10 13 10
NOTE: A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> has occurred between all work periods
INITIATING CUE:
Evaluate the work history for all 5 operators. Determine which operator(s), if any, can be
held over for three hours without prior overtime approval, and determine which operators
CANNOT be held over for three hours without prior overtime approval.
Also identify any deviations to OAP-001 that may have already occurred between Day 1
and Day 7 (assume no authorization to exceed OAP-001 limits)
3A1-2.r Page 9 of 9 REV. 0
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
LESSON TITLE: Evaluate Proposed Temporary Change.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Evaluate Proposed Temporary Change.
Special Instructions
Obtain copies of prints D-02549, Sheet 1B, 2-FP-05924, Sheet 2, LL-09243, Sheet 15 and
LL09244, Sheet 15
On D-02549, change V35 and V36 to show closed, and denote valves closed per EC TC
On 2-FP-9524, Sheet 2, draw cloud around G41-N005 connections INC and 1C, denote
leads lifted per EC TC 03-001.
On 2-FP-9524, Sheet 2, draw cloud around G41-N005 connections 2NC and 2C, denote
leads lifted per EC TC 03-001.
On LL-09243, Sheet 15, draw jumper from terminals 2-H02/CC5 to 2-H02/AA11. Denote
jumper installed per TC EC 03-001.
On LL-09244, Sheet 15, draw jumper from terminals 2-H02/CC17 to 2-H02/BB14. Denote
jumper installed per TC EC 03-001.
Mark up EGR-NGGC-005, Form 2 to reflect temporary changes.
03-A2 Page 2 of 9 REV. 0
Evaluate Proposed Temporary Change.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL NOT be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. This JPM may be administered in any setting.
Read the following to trainee.
TASK CONDITIONS:
1. Unit Two (2) Fuel Pool Cooling Skimmer Surge Tank low level alarm switch 2-G41 -LSL
N005 has failed. The shelf condition of this level switch is closed. This failed level
switch has resulted in Annunciator A-4 6-7 (Fuel Pool Cooling Alarm) being sealed in on
Panel P603.
2. The failed level switch is obsolete. A temporary change has been developed in
accordance with EGR-NGGC-0005 to abandon this level switch in place until a suitable
replacement can be located and installed.
3. This temporary change is to valve out the failed level switch and lift leads and/or jumper
the level switch contacts. This temporary change will defeat the level switch input to
Annunciator A-4 6-7 (a multiple input Annunciator). This temporary change will also
defeat low level indicating lights located on local panels 2-G41P001 and 2-G41-P002.
The low level trip function for the Fuel Pool Cooling Pumps will not be affected.
4. A Temporary Change Log form (EGR-NGGC-0005, Form 2) has been prepared
indicating a description of this temporary change and the Priority 0 drawings affected.
The Priority 0 drawings referenced have been marked up to reflect the temporary
change.
03-A2 Page 3 of 9 REV. 0
Evaluate Proposed Temporary Change.
INITIATING CUE:
You are directed by the WCC SRO to review the marked up Priority 0 drawings identified
on the Temporary Change Log Form 2 and ensure the changes reflected on the identified
Priority 0 drawings meet the intent of the temporary change, and inform the WCC SRO of
the results of your evaluation.
03-A2 Page 4 of 9 REV. 0
Evaluate Proposed Temporary Change.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Review Temporary Change Log, Form 2 and evaluate drawings listed as Priority 0 on
the Log.
Reviews Temporary Change Log, Form 2 and evaluate drawings listed as
Priority0 on the Log.
SAT/UNSAT*
Step 2 - Determine jumper installed from terminals 2-H02/CC5 to 2-H02/AA1I1 on drawing LL
09243, Sheet is for level switch N006, not N005 and should not be installed.
Determinesjumper should not be installed from terminals 2-H02/CC5 to 2
HO21AAI I on LL-09243, Sheet 15.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Determine jumper installed from terminals 2-H02/CC17 to 2-H02/BB23 on drawing
LL-09244, Sheet is for level switch N006, not N005 and should not be installed.
Determinesjumper should not be installed from terminals 2-H02/CC17 to 2
H02/BB23 on LL-09244, Sheet 15.
- CRITICAL STEP ** SAT/UNSAT*
03-A2 Page 5 of 9 REV. 0
Evaluate Proposed Temporary Change.
K
Step 4 - Determine other drawing changes meet the intent of the TC.
Determines other drawing changes meet the intent of the TC.
- CRITICAL STEP ** SATIUNSAT*
Step 5 - Inform WCC SRO of results.
SAT/U NSAT*
6
_____________________________ I
TERMINATING CUE: This box will tell the evaluator when the JPM is complete based on
Istudent
liý
performance. -ii I
- Comments required for any step evaluated as UNSAT.
03-A2 Page 6 of 9 REV. 0
Evaluate Proposed Temporary Change.
RELATED TASKS:
200 665 B5 04, Perform AO Actions For A Loss Of Division I DC Panels Per AOP-39.0
K/A REFERENCE AND IMPORTANCE RATING:
295004 AA1.01 3.3/3.4
Ability to operate D.C. electrical distribution systems as it applies to Partial Loss of D.C.
power.
REFERENCES:
AOP-39.0, Revision 11
Loss of DC Power
TOOLS AND EQUIPMENT:
Plant Page.
Keys.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
6 - Electrical (DC Electrical Distribution)
REASON FOR REVISION:
Renamed from AOR to AOT, changed format to WORD from WP 5.1, updated for
procedure revision, changed to support either unit, removed record of revision page.
03-A2 Page 7 of 9 REV. 0
Evaluate Proposed Temporary Change.
Time Required for Completion: 30 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate , Actual Unit: 2
Setting: Control Room Simulator (Not applicable to In-Plant JPMs)
Time Critical: Yes No --4-- Time Limit N/A
Alternate Path: Yes No
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
03-A2 Page 8 of 9 REV. 0
I,--/
TASK CONDITIONS:
1. Unit Two (2) Fuel Pool Cooling Skimmer Surge Tank low level alarm switch 2-G41 -LSL
N005 has failed. The shelf condition of this level switch is closed. This failed level
switch has resulted in annunciator A-4 6-7 (Fuel Pool Cooling Alarm) being sealed in on
Panel P603.
2. The failed level switch is obsolete. A temporary change has been developed in
accordance with EGR-NGGC-0005 to abandon this level switch in place until a suitable
replacement can be located and installed.
3. This temporary change is to valve out the failed level switch and lift leads and/or jumper
the level switch contacts. This temporary change will defeat the level switch input to
annunciator A-4 6-7 (a multiple input annunciator). This temporary change will also
defeat low level indicating lights located on local panels 2-G41P001 and 2-G41-P002.
The low level trip function for the Fuel Pool Cooling Pumps will not be affected.
4. A Temporary Change Log form (EGR-NGGC-0005, Form 2) has been prepared
indicating a description of this temporary change and the Priority 0 drawings affected.
The Priority 0 drawings referenced have been marked up to reflect the temporary
change.
INITIATING CUE:
You are directed by the WCC SRO to review the marked up Priority 0 drawings identified
on the Temporary Change Log Form 2 and ensure the changes reflected on the identified
Priority 0 drawings meet the intent of the temporary change, and inform the WCC SRO of
the results of your evaluation.
BNP 03 A3 RO QUESTION 1
REFERENCES ARE NOT PERMITTED FOR PART A
Part A
Unit One is in a refueling outage. You are an operator in the Control Room.
A fuel handing accident has just occurred on Unit One requiring evacuation of
the Refuel Floor and the Reactor Building due to high radiation conditions.
What action must you perform to protect Control Room personnel from
excessive dose?
REFERENCES ARE PERMITTED FOR PARTS B and C
Part B
What is the maximum time to complete the above action?
Part C
Completion of the above required action in the required time ensures the
Control Room will remain habitable for a minimum of without
exceeding dose limits specified in 10CFR50. (Fill in the blank)
BNP 03 A3 RO QUESTION 2
K-> Two operators are directed to perform a task in the Unit Two Reactor Building.
They take separate paths to the job location as described in the following table:
Operator I Operator 2
Dose Rate Path Dose Rate Path
9 mr/hr Transient time in 8 mr/hr Transient time in
the Unit One the Unit One
Reactor Building 6 Turbine Building 3
minutes minutes
9 mr/hr Transient time in 8 mr/rh Transient time in
the Unit Two the Unit Two
Reactor Building 3 Turbine Building 3
minutes minutes
1 mr/hr Changes into PCs 9 mr/hr Transient time in
to go into the Unit Two
contaminated area Reactor Building 6
in Unit Two minutes
Reactor Building
(Takes 6 minutes)
1 mr/hr Transient time Arrives at job site
through
contaminated area
is 3 minutes
1 mr/hr Changes out of
PCs to exit
contaminated area
in Unit Two
Reactor Building
(Takes 6 minutes)
I Arrives at job site
Which operator received the lower dose?
BNP 03 A3 RO QUESTION 1 ANSWER KEY
REFERENCES ARE NOT PERMITTED FOR PART A
Part A
Unit One is in a refueling outage. You are an operator in the Control Room.
A fuel handing accident has just occurred on Unit One requiring evacuation of
the Refuel Floor and the Reactor Building due to high radiation conditions.
What action must you perform to protect Control Room personnel from
excessive dose?
Start Control Building Emergency Air Filtration(or CREV). (0.5 pts)
Reference AOP-05.0, immediate action
REFERENCES ARE PERMITTED FOR PARTS B and C
Part B
What is the maximum time to complete the above action?
20 minutes (0.25 pts)
Part C
Completion of the above required action in the required time ensures the
Control Room will remain habitable for a minimum of without
exceeding dose limits specified in 10CFR50. (Fill in the blank)
30 days (0.25 pts)
Minimum acceptable for Question 1 is 0.75 pts.
Reference AOP-05.0, Immediate Actions and General Discussion
Reference Tech Spec Bases B 3.7.3, Background
Reference SD-37, Section 1.2 (Design Bases)
K/A: 2.3.10 2.9/3.0
BNP 03 A3 RO QUESTION 2 ANSWER KEY
<2 Two operators are directed to perform a task in the Unit Two Reactor Building.
They take separate paths to the job location as described in the following table:
ODerator 1 Ooerator 2
Dose Rate Path Dose Rate Path
9 mr/hr Transient time in 8 mr/hr Transient time in
the Unit One the Unit One
Reactor Building 6 Turbine Building 3
minutes minutes
9 mr/hr Transient time in 8 mr/rh Transient time in
the Unit Two the Unit Two
Reactor Building 3 Turbine Building 3
minutes minutes
1 mr/hr Changes into PCs 9 mr/hr Transient time in
to go into the Unit Two
contaminated area Reactor Building 6
in Unit Two minutes
Reactor Building
(Takes 6 minutes)
1 mr/hr Transient time Arrives at job site
through
contaminated area
is 3 minutes
1 mr/hr Changes out of
PCs to exit
contaminated area
in Unit Two
Reactor Building
(Takes 6 minutes)
Arrives at job site
Which operator received the lower dose?
Operator 1
(9 mr/hr X 0.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) + (9 mr/hr X 0.05 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) + (1 mr/hr X 0.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) + (1 mr/hr X
0.05 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) + (1 mr/hrX 0.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) = 1.6 mr
Operator 2
(8 mr/hr X 0.05 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) + (8 mr/hr X 0.05 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) + (9 mr/hr X 0.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) = 1.7 mr
Operator #1 received the total lower dose
K/A 2.31 2.6/3.0
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-A4-RO
LESSON TITLE: Estimate Release From Unit One Reactor Building and Turbine Building
Per PEP-03.6.1.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Estimate Release From Unit One Reactor Building and Turbine Building Per PEP-03.6.1.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure WILL be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
1. An accident is in progress on Unit One.
2. Unit One Reactor Building HVAC has been started per OEOP-01-SEP-04 with three
supply fans and three exhaust fans running.
3. Unit One Reactor Building Vent Flow instrument 1-VA-FR-3356 is failed downscale
4. Unit One Reactor Building Roof Vent monitor (1-CAC-AQR-1 264-3) is reading 2.3
E+03 CPM. The posted efficiency factor is 1.525 E-05.
5. Unit One Turbine Building Vent Flow Instrument (1-VA-FT-3358) is inoperable.
6. Unit One Turbine Building Vent monitor (1-D12-RR-4548) is reading 5.3 E-04
1LCi/cc.
7. The Emergency Operations Facility has requested the Release Rate from the Unit
One Turbine Building and the Unit One Reactor Building be estimated for
determination of off-site release dose projections.
INITIATING CUE:
You are directed by the Shift Superintendent to estimate the release rates from the Unit
One Reactor Building and the Unit One Turbine Building per OPEP-03.6.1. Determine if
these release rates can be added together, or must be reported separately. Inform the
Shift Superintendent of the results.
3.A.4-RO Page 2 of 9 REV. 0
Estimate Release From Unit One Reactor Building and Turbine Building Per PEP-03.6.1.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of OPEP-03.6.1.
CurrentRevision of OPEP-03.6.1 obtained.
SATIUNSAT*
NOTE: Sequence of steps for determining Reactor Building and Turbine Building estimated
releases are not important.
Step 2 - Estimate Unit One Reactor Building Release as follows:
a. Record Meter Reading (CPM) on Attachment 2
2.3 E+03 CPM recordedon Attachment 2.
SAT/UNSAT*
b. Record Flow on Attachment 2
Multiplies 43,200 times 3 and records 129600 (CFM) on Attachment 2.
SAT/UNSAT*
3.A.4-RO Page 3 of 9 REV. 0
Estimate Release From Unit One Reactor Building and Turbine Building Per PEP-03.6.1.
c. Record Efficiency Factor on Attachment 2
1.525 E-05 recordedon Attachment 2.
SAT/UNSAT*
d. Determines Release Rate from Unit One Reactor Building to be 4545.72 .Ci/sec
and records Release Rate on Attachment 2
Multiplies 2.3E+03 times 129600 times 1.525E-05, determines Release Rate
is 4.5E+03 to 4.6E+03.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Estimate Unit One Turbine Building Release as follows:
a. Record Meter Reading (CPM) on Attachment 3
5.3 E-04 ,Ci/cc recorded on Attachment 3.
SAT/UNSAT*
b. Record Flow on Attachment 3
Records 15,500 (CFM) on Attachment 3.
SATIUNSAT*
3.A.4-RO Page 4 of 9 REV. 0
Estimate Release From Unit One Reactor Building and Turbine Building Per PEP-03.6.1.
c. Record Conversion Factor on Attachment 3
472 recordedon Attachment 3.
SATIUNSAT*
d. Determines Release Rate from Unit One Turbine Building to be 3877.48 ,Ci/sec
and records Release Rate on Attachment 2
Multiplies 5.3E-04 times 15500 times 472, determines Release Rate is
3.8E+03 to 3. 9E+03.
- CRITICAL STEP ** SAT/UNSAT*
Step 4 - Determines that since multiple building vent rad monitors are not monitoring the
same point, the individual source terms may be added to obtain the total source term
(BOTH are considered ground level vs. elevated release per PEP-03.6.1, Step 9.3).
Determines that the individual source terms may be added to obtain the total
source term.
- CRITICAL STEP ** SAT/UNSAT*
3.A.4-RO Page 5 of 9 REV. 0
Estimate Release From Unit One Reactor Building and Turbine Building Per PEP-03.6.1.
Step 5 - Adds Reactor Building and Turbine Building Release (4545.72 i 1Ci/sec + 3877.48
, Ci/sec) to obtain total release of 8423.2 gCi/sec
Total release rate calculated to be 8.3E+03 to 8.5E+03 MCi/sec
- CRITICAL STEP ** SAT/UNSAT*
Step 6 - Report results of Release Rate Estimates to the Shift Superintendent.
Shift Superintendent informed of results.
SAT/UNSAT*
TERMINATING CUE: When the release rate from the Unit One Turbine Building and Unit
I One ReactorBuilding has been estimated, this JPM is complete. I
- Comments required for any step evaluated as UNSAT.
3.A.4-RO Page 6 of 9 REV. 0
Estimate Release From Unit One Reactor Building and Turbine Building Per PEP-03.6.1.
RELATED TASKS:
299201B201, Perform Daily Surveillance Report Per 01-3.1 Or 01-3.2
K/A REFERENCE AND IMPORTANCE RATING:
GEN 2.4.39 3.3/3.1
REFERENCES:
OPEP-03.6.1
TOOLS AND EQUIPMENT:
Calculator.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
A.4 - Admin - Emergency Plan
REASON FOR REVISION:
New JPM.
3.A.4-RO Page 7 of 9 REV. 0
Estimate Release From Unit One Reactor Building and Turbine Building Per PEP-03.6.1.
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual -A Unit: 1
Setting: Control Room Simulator (Not applicable to In-Plant JPMs)
Time Critical: Yes No , Time Limit N/A
Alternate Path: Yes No _
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
Did Trainee Verify Procedure as Authorized Copy?: Yes - No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3.A.4-RO Page 8 of 9 REV. 0
TASK CONDITIONS:
1. An accident is in progress on Unit One.
2. Unit One Reactor Building HVAC has been started per OEOP-01-SEP-04 with three
supply fans and three exhaust fans running.
3. Unit One Reactor Building Vent Flow instrument 1-VA-FR-3356 is failed downscale
4. Unit One Reactor Building Roof Vent monitor (1-CAC-AQR-1264-3) is reading 2.3
E+03 CPM. The posted efficiency factor is 1.525 E-05.
5. Unit One Turbine Building Vent Flow Instrument (1-VA-FT-3358) is inoperable.
6. Unit One Turbine Building Vent monitor (1-D12-RR-4548) is reading 5.3 E-04
ýCi/cc.
7. The Emergency Operations Facility has requested the Release Rate from the Unit
One Turbine Building and the Unit One Reactor Building be estimated for
determination of off-site release dose projections.
INITIATING CUE:
You are directed by the Shift Superintendent to estimate the release rates from the Unit
One Reactor Building and the Unit One Turbine Building per OPEP-03.6.1. Determine if
these release rates can be added together, or must be reported separately. Inform the
Shift Superintendent of the results.
3.A.4-RO Page 9 of 9 REV. 0
ES-301 Control Room Systems Form ES-301-2 (R8, $1)
and Facility Walk-Throuqh Test Outline
Facility: Brunswick Date of Examination: _February 2003
Exam Level (circle one): RO / SRO(]) / SRO(U) Operating Test No.:
B.1 Control Room Systems
System / JPM Title Type Safety
Code* Function
a. Reactor Recirculation Pump Start - Recirculation Pump (D)(A)(S) 1
Speed Control Failure (BNP-03-Bla)
b. Reduce RPV water level using RWCU to Radwaste (BNP- (N)(S) 2
c. Emergency equalization around MSIVs using Hard Card (D)(S) 3
(BNP-03-Alc)
d. Shutdown Cooling Restoration With RHR Pump overload. (D)(A)(S) 4
(BNP-03-Bld) (L)
e. Vent the Drywell per OP-1 0 w/ Stack Rad Monitor (D)(A)(S) 5
Increase >50% (U) (BNP-03-Bl e)
f. Manual Startup of Control Building Emergency Ventilation - (N)(A)(S) 9
Trip of One Fan (U), (BNP-03-Blf)
g. Core Performance Parameter Check- manual APRM GAF (D)(S) 7
Adjustment Required (U4)(BNP-03-Blg)
B.2 Facility Walk-Through
a. Start RCIC from remote S/D Panel (i) (BNP-03-B2a) (D)(R) 2
b. Local Manual Start Of "A" DG using Prelube Start Control (D) 6
(BNP-03-B2b)
c. Fire Water Injection Using The Motor Driven Fire Pump (Q) (M)(R) 8
(BNP-03-B2c)
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol
room, (S)imulator, (L)ow-Power, (R)CA
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
SIMULATOR
LESSON TITLE: Recirculation Pump Start - Recirculation Pump Speed Control Failure.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
SIMULATOR SETUP (Recommended)
IC-11 BOC
Rx Pwr 100%
Core Age BOC
Triggers
El - Auto initiated, Recirc B Runback Reset Push Button = TRUE
Malfunctions
None
Overrides
El - Recirc B Flow Control 1.0 over 60 seconds
Remote
None
Special Instructions
Reduce core flow to ENP-24 limit, drive 11 3 sets of rods on ENP-24.
Secure Recirc Pump B, place seal staging valve (V17) to Manual/Open, and reduce
controller output to approx. 16%.
Ensure core flow >30.8 and <45 mlbm/hr, and Recirc A pump flow >23,500 gpm. Ensure
scram avoidance region will not be entered when Recirc A pump flow is reduced to 23.500
gpm.
Page 2 of 15 REV. 0
33B1a
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee. Evaluator should
provide copy of OP-02, Sections 5.2 and 8.2 completed up to the steps specified in the
task conditions.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. Steps in 20P-02 to place APRMs to setup are not applicable in the simulator due to
simulator configuration with Unit One PRNM.
Read the following to trainee.
TASK CONDITIONS:
1. Recirculation Pump 2B has tripped. The cause of the trip has been corrected.
2. Recirculation Pump 2A is in operation.
3. RWCU is in normal operation per 20P-14.
4. An off-going operator has completed steps in 20P-02, Section 8.2, up to step 8.2.2.4,
and Section 5.2, up to step 5.2.2.22.
5. Another operator is available to make log entries as required.
INITIATING CUE:
You are directed to continue the startup of Recirculation Pump 2B and inform the Unit SCO
when 20P-02 Sections 5.2 and 8.2 are complete.
Page 3 of 15 REV. 0
33Bla
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of 20P-02, Sections 5.2 and 8.2.
Current Revision of 20P-02, Sections 5.2 and 8.2 obtained and verified, if
applicable.
SAT/UNSAT*
Step 2 - Ensure temperature differential between the reactor coolant within the dome and
bottom head drain is less than 145oF as follows:
a. Determine reactor pressure, convert to psia by adding 14.7 and use steam tables
to convert reactor pressure to temperature.
Reactor temperaturein the dome determined by converting psig to psia and
using steam tables.
SATIUNSAT*
PROMPT:if examinee requests another individual to read C12-TR-R018, Channel 153 (Local I
- ndication), direct examinee to use available indication on panel P603.
NOTE: since bottom head drain temperature indication is available, B32-TR-R650 (H12
P0 or process computer points, B105-B08 should not be used.
33Bla Page 4 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
b. Determine bottom head drain temperature using G31-TI-R607 Point 5 (Panel
H12-P603), or C12-TR-R018 Channel 153 (Local).
Bottom head drain temperatureusing G31-TI-R607 Point 5 is determined.
SAT/UNSAT*
c. Determine temperature difference and record time.
Temperature differential determined and time recordedin OP-02.
SATIUNSAT*
PROMPT: If examinee requests another individual to record differential temperature and time
in the CO logbook, report log entry is complete.
PROMPT: Ifexaminee asks, inform examinee APRM setup is not desired.
NOTE: Steps 23 and 24 of 20P-02, Section 52.2 are not applicable.
Step 3 - Slowly reduce speed of the operating Reactor Recirculation Pump using Recirc
Pump 2A Speed Control potentiometer until loop flow is less than or equal to 50%
(23,000 gpm) of rated loop flow.
Recirc loop 2A flow is <23,500 gpm on B32-FR-R614 or B32-R613.
- CRITICAL STEP ** SAT/UNSAT*
33B1a Page 5 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
Step 4 - Within 30 minutes prior to startup of the second pump, ensure temperature
differential between operating loop and idle loop is less than or equal to 50oF and
that operating loop flow is less than or equal to 23,500 gpm as follows:
a. Operating loop temperature (B32-TR-R650) or process computer (B055-B058)
Loop 2A temperature recordedin 20P-02 using B32-TR-R650 or B055-B056.
SAT/UNSAT*
b. Idle loop temperature (B32-TR-R650) or process computer (B055-B058)
Loop 2B temperature recordedin 20P-02 using B32-TR-R650 or B057-B058.
SATIUNSAT*
c. Determine differential temperature, record results and time in 20P-02
Differentialtemperature determined and recorded, along with time in 20P-02.
SAT/UNSAT*
IPROMPT: if examinee requests inother indivdual to record differential temperature and time
inthe CO logbook, reportlo entry is complete. I
NOTE: B32-FR-R614 (flow recorder) is available and should be used for the following step.
Page 6 of 15 REV. 0
33Bla
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
d. Operating loop flow rate on B32-FR-R614, if available, or flow indicator B32
R613 is less than or equal to 23,500 gpm (50% of rated loop flow) and time
recorded in 20P-02
Loop 2A flow rate from B32-FR-R614 and time recoded in 20P-02.
SATIUNSAT*
PROMPT: Ifexaminee requests another individual to record Loop 2A flow rate and time in the i
CO logbook, report log entry is complete.
NOTE: step 27 of 20P-02, Section 5.2.2 is not applicable.
A recirc runback signal will be received when the discharge valve is closed. 1
Step 5 - Ensure Pump 2B discharge valve B32-FO31B is closed.
Pump 2B discharge valve B32-FO31B is full closed.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: Step 29 of 20P-02, Section 5.2.2 is not applicable.
Step 6 - Ensure 30 minutes has not elapsed since temperature differentials and flow rate were
determined.
30 minutes has not elapsed since temperature differentials and flow rate were
determined
SAT/UNSAT*
331la Page 7 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
Step 7 - Start MG Set 2B drive motor and ensure the following:
MG Set 2B drive motor is started
- CRITICAL STEP ** SAT/UNSAT*
a. MG Set B drive motor breaker closes.
Ensures MG Set 2B drive motor closes.
SAT/UNSAT*
b. MG Set B accelerates to speed.
Ensures MG 2B acceleratesto speed.
SAT/UNSAT*
c. Approximately 6 seconds after the drive motor breaker closes, the generator field
breaker closes and starts the Reactor Recirculation Pump.
Ensures MG 2B field breaker closes and Recirculation Pump 2B starts.
SAT/UNSAT*
LNOTE:
0
B32-R613 Will indicate very little flow since the discharge valve is closed. Flow is
thouh the dis5charge bypass valve only. j1
I.
311 Page 8 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
d. Recirc Pump 2B discharge flow B32-R613 indicates flow.
Ensures Recirc Pump 2B discharge flow B32-R613 indicates flow.
SAT/UNSAT*
I
PROMPT: Ifexamin6ee requests another individual to record time the MG Set 2B drive motor
breaker was closed in the CO logbook, report log entry is complete. II
Step 8 - If in Modes 1 or 2 and the reactor is critical, perform the following:
a. Using 2 second jogs and 10 second rest times for the first minute, jog open
Pump 2B discharge valve B32-F031 B.
B32-FO31B is opened using 2 second jogs and 10 second rest times for the
first minute (5 total jogs).
- CRITICAL STEP ** SATIUNSAT*
b. Fully open Pump 2B discharge valve B32-FO31B.
B32-FO31B is fully opened.
- CRITICAL STEP ** SAT/UNSAT*
S.. . . . . .h
IIFThstens.34and 35 of 20P-02. Section 5.2.2 are not applicable.
--
II
33Bla Page 9 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
Step 9 - Place the control switch for Seal Staging Valve B32-V17 to AUTO and ensure the
valve remains open.
B32-VI 7 open with the control switch in AUTO.
SAT/UNSAT*
Step 10 - Reset Recirculation runback in accordance with Section 8.3.
Recognizes runback must be reset and obtains copy of 20P-02, Section 8.3.
SAT/UNSAT*
Step 11 - Adjust the potentiometer on Recirc Pump 2B Speed Control lowering the speed
demand signal until speed signal shows a slight decrease in pump speed.
Recirc B Speed Control is lowered to achieve a slight decrease in pump speed.
SAT/UNSAT*
NOTE: When the Runback Reset push button for Recirc Pump 2B is depressed, the speed
demand will begin to increase. Speed demand signal will ramp to 100% over a 60
second period. Pump speed (and reactor power) will increase until the scoop tube is
locked. Locking the scoop tube is an immediate operator action of AOP-03.0.
Maximum pump speed mismatch is 20% below 58 mlbm/hr total core flow and 10%
above 58 mlbm/hr total core flow.
3Bla Page 10 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
PROMPT: If examinee requests I&C assistance in resetting the runback, as I&C report signals /
matched and, runback can be reset.
Step 12 - Reset the Recirculation runback for Reactor Recirculation Pump 2B as follows:
a Depress the Recirc Runback Reset push button for Recirculation Pump 2B.
Recirc Runback Reset pushbutton for Pump 2B is depressed.
- CRITICAL STEP ** SAT/UNSAT*
b Ensure reactor power and flow are stabilized.
Recognize increasingspeed on Recirc Pump 2B and lock the scoop tube prior
to exceeding maximum pump speed mismatch.
- CRITICAL STEP ** SAT/UNSAT*
- NOTE: Ifdesired, record Pump Speeds and Core flow When the scoop tube islocked.
Pump A Speed - Pump B Speed __ Total Core Flow
and
forms SCO of the faiolmpe theJ PM is
inc eannot be competed
aomplete s nce the task
aocmple e e
fosi tkannoer
the ompthe
Since hhe fakbJP:Mte
t ofcrnnt
examinee that the JPM is complete.
is
I
will
PROMPT: When informed as SCO of the failure, inform examinee that another operator
- enter and announce AOP-03.
Page 11 of 15 REV. 0
33B1a
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
Step 13 - Inform SCO of speed control failure.
SCO informed of speed control failure.
SAT/UNSAT*
TERMINATING
_..... C.
.... CUE: tube is locked for Recirc MG Set 2B, this JPM is
When the scoopPicomplete.
- Comments required for any step evaluated as UNSAT.
33Bla Page 12 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
RELATED TASKS:
202004B101, Startup A Reactor Recirculation Pump Per OP-02
2020155B401, Respond To A Recirc Flow Control Failure Increasing Per AOP-03.0
K/A REFERENCE AND IMPORTANCE RATING:
202001 A4.01 3.7/3.7
Ability to manually operate and/or monitor in the control room: Recirculation pumps
REFERENCES:
TOOLS AND EQUIPMENT:
Steam Tables
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
1 - Reactivity Control (Recirculation System)
REASON FOR REVISION:
Bank JPM LOR-SIM-JP-002-A07. Renamed from LOR to LOT, changed format to WORD
from WP 5.1, updated for procedure revision.
33B1a Page 13 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
Time Required for Completion: 20 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual --4- Unit: 2
Setting: Control Room Simulator-- (Not applicable to In-Plant JPMs)
Time Critical: Yes No , Time Limit N/A
Alternate Path: Yes --4-- No
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes - No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3Bla Page 14 of 15 REV. 0
TASK CONDITIONS:
1. Recirculation Pump 2B has tripped. The cause of the trip has been corrected.
2. Recirculation Pump 2A is in operation.
3. RWCU is in normal operation per 20P-14.
4. An off-going operator has completed steps in 20P-02, Section 8.2, up to step 8.2.2.4,
and Section 5.2, up to step 5.2.2.22.
5. Another operator is available to make log entries as required.
INITIATING CUE:
You are directed to continue the startup of Recirculation Pump 2B and inform the Unit SCO
when 20P-02 Sections 5.2 and 8.2 are complete.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
SIMULATOR
BNP-03-Bl b
- j
LESSON TITLE: Reduce RPV Water Level Using RWCU To Radwaste.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Reduce RPV Water Level Using RWCU To Radwaste.
SIMULATOR SETUP
IC-03 BOC
Rx Pwr 0%
Core Age BOC
Triggers
None
Malfunctions
None
Overrides
None
Remote
None
Special Instructions
Secure RWCU reject flow by closing G31-F033 and G31-F034.
Raise RPV level to approximately 195". Ensure alarm A7 2-2 is sealed in.
Ensure both RWCU Filter Demins are in service.
331lb Page 2 of 9 REV. 0
Reduce RPV Water Level Using RWCU To Radwaste.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL NOT be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. There is no direct procedural guidance for this JPM. It is considered within the operator's
capability to control RPV water level using CRD and RWCU as directed by General
Operating Procedures.
Read the following to trainee.
TASK CONDITIONS:
1. Unit Two is in Mode 2, performing a reactor startup per GP-02.
2. RPV level band is 182" to 192" as indicated on C32-LI-NO04A/B/C.
3. CRD is operating for control rod withdrawal.
4. RWCU is in operation. RWCU was aligned for reject to the main condenser, but that
flow path has been secured for maintenance to repair a small leak in the header
downstream of G31-F034, Reject To Condenser. G31-F034 has been placed under
clearance in the closed position.
5. Reactor Level Hi/Lo has alarmed since securing the RWCU reject flow path.
INITIATING CUE:
You are directed by the Unit SCO establish a RWCU reject to Radwaste in accordance
with GP-02, Step 5.3.4, and lower RPV water level to <192" as indicated on narrow range
instruments C32-LI-NO04A/B/C. You are to inform the Unit SCO when the Reactor Hi/Lo
Level alarm is clear.
33B1b Page 3 of 9 REV. 0
Reduce RPV Water Level Using RWCU To Radwaste.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
NOTE: The following actions are directed by GP-02. There are no specific instructions in
OP-14 (Reactor Water Cleanup Operating Procedure) that apply for current plant I
conditions. The operator is expected to be able to control RPV level using CRD and I
RWCU reject during execution of General Operating Procedures.I
-- -qIIm
PROMPT: When notified of reject operation to Radwaste, as Radwaste CO, inform examinee
that you have aligned the reject flow path to the Waste Collector Tank. Report
Waste Collector Tank level is 20% and sufficient capacity exists for approximately
I
20,000 gallons of reject flow. II
Step 1 - Obtain current revision of GP-02.
Currentrevision of GP-02 is obtained.
SATIUNSAT*
Step 2 - Notify Radwaste of intention to reject to Radwaste, and coordinate to ensure
Radwaste can accept the reject flow.
Radwaste notified of reject to Radwaste.
SATIUNSAT*
Step 3 - Open Reject To Radwaste Vlv, G31-F035.
Reject To Radwaste Vlv, G31-F035 is open.
- CRITICAL STEP ** SAT/UNSAT*
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Reduce RPV Water Level Using RWCU To Radwaste.
Step 4 - Throttle open RWCU Reject Flow Control Vlv, G31-F033 to achieve a lowering RPV
water level.
G31-F033 is opened to achieve a lowering reactorwatertrend.
- CRITICAL STEP ** SAT/UNSAT*
PROMPT: I.f asked, as RadWaste CO, report Water Collector Tank level rising.
NOTE: The operator may (but is not required to) reduce CRD flow rate to the RPV to aid in
reducing RPV level to the desired band. If the operator reduces CRD flow rate, CRD
parameters should be maintained per OP-08, Section 6.0 (CRD Dive Water Pressure
restored 260-275 psig by throttling closed Dive Pressure Control Valve).
NOTE: The operator should monitor Regen HX Outlet, Point 2, and/or Filter Inlet, Point 3, on
G31-TI-R607, to ensure Non-Regen heat exchangers outlet temperature remains
below 130oF, but with RPV temperature <212oF, this limitation will not be exceeded.
Step 5 - Monitor Regen HX Outlet, Point 2, and/or Filter Inlet, Point 3, on G31-TI-R607, to
ensure Non-Regen heat exchangers outlet temperature remains below 130oF.
Operatormonitors Regen HX Outlet, Point 2, and/or FilterInlet, Point 3, on G31
TI-R607, to ensure Non-Regen heat exchangers outlet temperatureremains
below 130 cF.
SAT/UNSAT*
33B1b Page 5 of 9 REV. 0
Reduce RPV Water Level Using RWCU To Radwaste.
Step 6 - Lower RPV water level at or below 192" as indicated by C32-LI-NO04AIB/C.
RPV water level indicates at or below 192" as indicatedby C32-LI-NOO4A/B/C
and Reactor Level Hi/Lo alarm is clear.
- CRITICAL STEP ** SAT/UNSAT*
Step 7 - Inform Unit SCO that RPV water level is in the required band.
Unit SCO informed RPV water level is in the requiredband.
SAT/UNSAT*
TERMINATING CUE: When RPV water level indicates <192" on narrow range indicators
II N004A/B/C, this JPM is complete. ii11
- Comments required for any step evaluated as UNSAT.
33B1b Page 6 of 9 REV. 0
Reduce RPV Water Level Using RWCU To Radwaste.
RELATED TASKS:
2040026101, Place The RWCU System In Service With The Reactor Not In Cold
Shutdown Per OP-14.
K/A REFERENCE AND IMPORTANCE RATING:
204000, A4.08 3.4/3.4
REFERENCES:
GP-02
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
2 - Inventory Control (Reactor Water Cleanup)
<'> REASON FOR REVISION:
New JPM.
33Blb Page 7 of 9 REV. 0
Reduce RPV Water Level Using RWCU To Radwaste.
V
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual ,_ Unit: 2
Setting: Control Room Simulator_4_ ( Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes No _
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3B3lb Page 8 of 9 REV. 0
TASK CONDITIONS:
1. Unit Two is in Mode 2, performing a reactor startup per GP-02.
2. RPV level band is 182" to 192" as indicated on C32-LI-NO04A/B/C.
3. CRD is operating for control rod withdrawal.
4. RWCU is in operation. RWCU was aligned for reject to the main condenser, but that
flow path has been secured for maintenance to repair a leak in the header downstream
of G31-F034, Reject To Condenser. G31-F034 has been placed under clearance in the
closed position.
5. Reactor Level Hi/Lo has alarmed since securing the RWCU reject flow path.
INITIATING CUE:
You are directed by the Unit SCO establish a RWCU reject to Radwaste in accordance
with GP-02, Step 5.3.4, and lower RPV water level to <192" as indicated on narrow range
instruments C32-LI-NO04A/B/C. You are to inform the Unit SCO when the Reactor Hi/Lo
Level alarm is clear.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
CONTROL ROOM
BNP-03-Blc
LESSON TITLE: Emergency Equalization Around MSIV's - Using the Hard Card
REVISION NO: 1
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Emergency Equalization Around MSIV's - Using the Hard Card
SIMULATOR SETUP:
A. Initial Conditions:
1. Recommended Initial Conditions
IC 11
Rx. Pwr. 100%
Core Age BOL
2. Required Plant Conditions
MSIVs closed with control switches in open, condenser vacuum < 10", no other
group 1 conditions present.
B. Malfunctions
A small steam leak in the drywell or secondary containment
C. Overrides
None
D. Special Instructions
Perform a MANUAL Scram carry out initial operator actions. Close the MSIVs. Ensure
condenser vacuum drops to <10". After this is done place the MSIV control switches to
OPEN.
3Alc Page 2 REV. 1
Emergency Equalization Around MSIV's - Using the Hard Card
SAFETY CONSIDERATIONS:
1. NONE.
EVALUATOR NOTES: (Do not read to examinee)
1. The applicable procedure section WILL NOT be provided to the examinee (Hard Card
from P601).
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the examinee.
Read the following to trainee.
TASK CONDITIONS:
1. A scram and Group 1 Isolation have occurred.
2. No fuel failure or steam line breaks have occurred.
3. The Main Condenser is available as a heat sink.
4. The SRO has anticipated that Emergency Depressurization may become required.
INITIATING CUE:
You are directed to perform the control operator actions associated with Emergency
Equalization around the MSIV's, and open MSIVs when pressure is <200 psid, using the
Hard Card. You are to inform the Unit SCO when the Hard Card actions are complete.
3A1lc Page 3 REV. 1
Emergency Equalization Around MSIV's - Using the Hard Card
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain "Hard Card" for MSIV equalization
"HardCard"obtained for MSIV equalization.
SAT/UNSAT*
NOTE: When requested, place the low condenser vacuum bypass switches to Bypass using
Remote Function MSIAGP1 BYP
PROMPT: (From Simulator Operator) Inform examinee low condenser vacuum bypass
switches are in Bypass
Step 2 - Request the condenser vacuum bypass switches in bypass position.
Vacuum bypass switches placed in bypass
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Place all MSIV switches in the CLOSE position.
All MSIV switches in CLOSE position (B21-FO22A, B, C &D, B21-FO28A, B, C &
D).
- CRITICAL STEP ** SAT/UNSAT*
REV. 1
Page 4
3A1c
3A1lc Page 4 REV. 1
Emergency Equalization Around MSIV's - Using the Hard Card
Step 4 - Reset Group 1 Isolation.
Resets Group I Isolation reset switches, A 72-S32 and S33, on P601, are
depressed and White lights are ON.
- CRITICAL STEP** SAT/UNSAT*
Step 5 - Open Outboard MSIV's.
Outboard MSIV switches: B21-FO28A, B21-FO28B, B21-F028C, B21-FO28D
placed in OPEN and MSIVs are OPEN.
- CRITICAL STEP ** SAT/UNSAT*
Step 6 - Open MS-F020.
MSL Drain Isolation Valve MS-F020 open.
SATIUNSAT*
Step 7- Open B21-F019.
MSL Outboarddrain Isolation Valve B21-F019 open.
- CRITICAL STEP ** SATIUNSAT*
REV. 1
Page 5
3AlIc
3A1C Page 5 REV. 1
Emergency Equalization Around MSIV's - Using the Hard Card
Step 8 - Close MS-V28
Steam supply to MSR's, SJAE's, RFP's, MS-V28 indicates full closed.
SATIUNSAT*
Step 9 - Close MVD-F021.
Common drain line orifice Bypass Valve to condenser,MVD-F021 closed.
SATIUNSAT*
Step 10- Open B21-F016.
MSL Inboard drain Isolation Valve, B21-F016 open.
- CRITICAL STEP ** SATIUNSAT*
NOTE: The expectation is to open all four valves in the following step. It is critical that at leastl
one valve be opened for equalization. I
Step 11 - Open MS-F038 A, B, C, D.
At least one MSL orifices bypass valve: MS-F038A, B, C, or D open to increase
steam line pressure.
- CRITICAL STEP ** SAT/UNSAT*
3A1lc Page 6 REV. I
Emergency Equalization Around MSIV's - Using the Hard Card
Step 12 - Ensure steam line pressure is increasing downstream of Outboard MSIVs.
Steam line pressure rising as indicatedon Main Steam PressureA/B indications
on XU-1.
SAT/UNSAT*
Step 13- Close MS-V46, V47, V48, V49 and V35.
MSL drain valves MS-V46, MS-V47, MS-V48, & MS-V49 and V35 are all closed.
SAT/UNSAT*
Step 14 - When less than 200 psid across the valve, open Inboard MSIVs.
Inboard MSIVs B21-FO22A, B, C & D are open.
- CRITICAL STEP ** SAT/UNSAT*
Step 15- Open MVD-F021.
MVD-F021 indicates open.
3A1lc Page 7 REV. 1
Emergency Equalization Around MSIV's - Using the Hard Card
SAT/UNSAT*
NOTE: When requested, open MVD-V5005 using Remote Function MS-VMS5005D.
PROMPT: (From Simulator Operator) Inform examinee MVD-V5005 is open.
Step 16- Request AO open MVD-V5005.
MVD-V5005 is open
SATIUNSAT*
Step 17 - Open MS-V46, V47, V48, V49 and V35.
MS-V46, V47, V, 8, V49 and V35 are opened.
SAT/UNSAT*
Step 18 - Ensure open MS-V43, MS-V44, MS-V45, MS-V37/39, MS-V41/V42, MS-V36.
MS-V43, MS-V44, MS-V45, MS-V37/39, MS-V41/V42, MS-V36 are open.
SATIUNSAT*
3Al c Page 8 REV. 1
Emergency Equalization Around MSiV's - Using the Hard Card
NOTE: Closing MS-V28 is not critical to equalize pressure around MSIVs. If closed, re
opening, MS-V28 is critical to re-establish condenser vacuum to allow operation of
turbine bypass, valves (turbine steam seals and SJAEs).
I
Step 19 - Open MS-V28.
MS-V28 is open.
- CRITICAL STEP ** SAT/UNSAT*
Step 20 - Notify Unit SCO that MSIVs are open and to continue with pressure control as
directed by the EOPs.
Supervisornotified MSIVs have been opened per the Hard Card.
SAT/UNSAT*
TERMINATING CUE: When the actionsto equalize around and open MSIVs have been
performed per the hard card, thisJPM is complete.,
- Comments required for any step evaluated as UNSAT.
3A1lc Page 9 REV. 1
Emergency Equalization Around MSIV's - Using the Hard Card
LIST OF REFERENCES
RELATED TASKS:
239 201 B4 01
Equalize Around And Open Main Steam Isolation Valves Per Hot Startup OP-25.
K/A REFERENCE AND IMPORTANCE RATING:
239001 A4.01 4.2/4.0
Ability to manually operate and or monitor in the Control Room: MSIVs
REFERENCES:
EOP-01-RVCP, Reactor Vessel Control Procedure
Hard Card for MSIV equalization and reopening (S/1 032)
AND EQUIPMENT: S>TOOLS
None
SAFETY FUNCTION
3 - Reactor Pressure Control (Main and Reheat Steam System)
REASON FOR REVISION:
Bank JPM LOT-SIM-JP-025-A01. Updated to current revision of procedure (addition of
MVD-V5005).
3Alc Page 10 REV. 1
Emergency Equalization Around MSIV's - Using the Hard Card
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual j> Unit: 2
Setting: Control Room Simulator__4_(Not applicable to In-Plant JPMs)
Time Critical: Yes No _ Time Limit N/A
Alternate Path: Yes No -4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes __ No
Did Trainee Verify Procedure?: Yes __ No
( Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3Alc Page I11 REV. 1
TASK CONDITIONS:
1. A scram and Group 1 Isolation have occurred.
2. No fuel failure or steam line breaks have occurred.
3. The Main Condenser is available as a heat sink.
4. The SRO has anticipated that Emergency Depressurization may become required.
INITIATING CUE:
You are directed to perform the control operator actions associated with Emergency
Equalization around the MSIV's, and open MSIVs when pressure is <200 psid, using the
Hard Card. You are to inform the Unit SCO when the Hard Card actions are complete.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
SIMULATOR
LESSON TITLE: Shutdown Cooling Restoration With RHR Pump Overload.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
SIMULATOR SETUP
IC-01
Malfunctions
Overrides
El, ZA347 (RHR Pump B Overload alarm)
El, ZUA1861 (4KV Bus E4 Motor Overload alarm)
E2, ZA367 (RHR Pump D Overload alarm)
E2, ZUA1661 (4KV Bus E2 Motor Overload alarm)
Special Instructions
1. Throttle Ell-FO03B and E1l-F048B to achieve system flow of 6000 gpm with both
valves indicating dual position.
2. Insert malfunction RP004F (or transfer RPS Bus B to alternate).
3. Perform actions to restore systems lost as desired. The 1/4 scram may be reset, but
DO NOT reset PCIS logic.
4. Loss of RPS MG Set B results in closure of the RHR Outboard Valve (E lI-F008)
and the injection valve (El 1-FO15B) with resultant RHR Pump trip.
Shutdown Cooling Restoration With RHR Pump Overload.
SAFETY CONSIDERATIONS:
None
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL NOT be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
1. RHR Loop B was operating in Shutdown Cooling when a trip of RPS MG Set B resulte-d"'
in a Group 8 isolation and a loss of Shutdown Cooling.
2 RPS Bus B has been transferred to Alternate Power.
3. RHR Loop B flow was 6000 gpm prior to the RPS MG Set B trip.
4. The shift superintendent has directed a reactor water level band of +200" to +220".
INITIATING CUE:
You are directed to restart RHR Shutdown Cooling using RHR Loop B per AOP-1 5.0
step 3.2.8, and inform the Unit SCO when Shutdown cooling has been restored.
3Bld Page 3 REV. 0
Shutdown Cooling Restoration With RHR Pump Overload.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of AOP-1 5.0.
Current Revision of AOP-15.0 obtained.
SAT/U NSAT*
Step 2 - Restore and maintain reactor water level 200-220".
Reactorwater level is 200-220" as indicated on B21-LI-NO27A or B.
SAT/UNSAT*
Step 3 - Reduce reactor pressure below 125 psig per GP-05
Reactorpressure is below 125 psig.
SAT/U NSAT*
Step 4 - Ensure RPS is energized.
RPS Buses A and B are energized.
SAT/UNSAT*
33B1d Page 4 REV. 0
Shutdown Cooling Restoration With RHR Pump Overload.
Step 5 - Reset the group 8 isolation.
Isolation Reset Groups 1,2,3,6,8 pushbutton, A71-S33 is depressed.
- CRITICAL STEP ** SAT/UNSAT*
If requested,
11.PROMPT: areNOT as Unit sco, inform examinee that piping cooldown or drain down.,
a concern
Step 6- Close Loop B Outboard Injection Valve, ElI-FO17B.
El1-FO17B indicates full closed.
SAT/UNSAT*
Step 7 -Open Loop B Inboard Injection Valve Eli-F015B.
El 1-FO15B indicates full open.
- CRITICAL STEP ** SAT/UNSAT*
Step 8 - Open RHR Shutdown Cooling Outboard Isolation Valve El 1-F008.
E 11-FOO8 indicates full open.
- CRITICAL STEP ** SAT/UNSAT*
3Bld Page 5 REV. 0
Shutdown Cooling Restoration With RHR Pump Overload.
Step 9 - Open RHR Shutdown Cooling Inboard Isolation Valve El1-F009.
El1-F009 indicates full open.
SAT/U NSAT*
Step 10 - Start an RHR Pump in the loop being used for shutdown cooling.
RHR Pump 2B or 2D is running.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: When E11-FO17B has been throttled to establish approximately 6000 gpm loop
flow, if RHR Pump B has been started, initiate Trigger El, or if RHR Pump D has
been started, initiate Trigger E2 (do NOT initiate both).
When the Pump (B or D) with the overload alarm is stopped, clear the Alarm
Sum mary.
.PROMPT: If requested, as AO report 51,device shows target on phase B at breaker for RHR
Pump B (E4) or RUR Pump D (E2) as applicable.
If informed as Unit SCO of overload alarm, acknowledge the report, and inform
examinee that you will contact l&C, and have another operator dispatch an AO to
the pump motor breaker to check relay status.
Step 11 - Slowly throttle open Loop B Outboard Injection Valve El1-FO17B to re-establish
RHR loop conditions prior to the event.
E1I-F017B throttled open to establish RHR Loop flow of >4150 gpm.
- CRITICAL STEP ** SAT/UNSAT*
REV. 0
Page 6 REV. 0
3B1d
3Bld Page 6
Shutdown Cooling Restoration With RHR Pump Overload.
NOTE: The APP (A-03 4-7 for RHR Pump B/A-03 6-7 for RHR Pump D)) provides three
courses of action for a pump overload:,
If in accident conditions, continue running pump (does NOT apply).
If testing the pump, trip the pump (does NOT apply).
If pump is operating for some other mode, start a redundant pump and stop the
pump with the overload.
Step 12 - Refer to APP for RHR Pump (B or D) overload
Refers to APP for RHR Pump (B or D) overload
SAT/UNSAT*
Step 13- Start redundant RHR Pump (B or D)
RHR Loop B Pump (B or D) without overload is running.
- CRITICAL STEP ** SAT/UNSAT*
Step 14 - Stop RHR Pump (B or D) with overload alarm.
RHR Pump with overload alarm (B or D) is off.
- CRITICAL STEP ** SAT/UNSAT*
Page 7 REV. 0
33B1d
Shutdown Cooling Restoration With RHR Pump Overload.
Step 15 - Fully open Loop B Outboard Injection Valve El1-FO17B.
El 1-F01 7B indicates full open.
SAT/U NSAT*
Step 16- Ensure Reactor Head Vent Valves, B21-F003 and B21-F004 are Open.
Reactor Head Vent Valves, B21-FO03 and B21-F004 are Open.
SAT/U NSAT*
Step 17 - Inform Unit SCO RHR shutdown cooling has been re-established per AOP-15.0.
Unit SCO informed RHR shutdown cooling has been re-establishedper AOP
15.0.
SAT/U NSAT-*r
TERMINATING CUE: When RHR shutdown cooling has been re-established ppr AOP-1 5.0,
this JPM is complete.
- Comments required for any step evaluated as UNSAT.
REV. 0
Page 8
3B1d
33B1d Page 8 REV. 0
Shutdown Cooling Restoration With RHR Pump Overload.
RELATED TASKS:
205016B401, Respond To A Loss Of Shutdown Cooling Per AOP-15
K/A REFERENCE AND IMPORTANCE RATING:
295021 AA1.02 3.5/3.5
Ability to operate and/or monitor RHR/shutdown cooling as it applies to loss of shutdown
cooling.
REFERENCES:
APP A-03, UA-16, UA-18
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
4 - Heat Removal From Reactor Core (Shutdown Cooling System)
REASON FOR REVISION:
New JPM.
33Bld Page 9 REV. 0
Shutdown Cooling Restoration With RHR Pump Overload.
Time Required for Completion: 10 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate 4 Actual Unit: 2
Setting: Control Room - Simulator ( Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes 4 No
EVALUATION
Trainee: SSN:
JPM: Pass Fail __
Remedial Training Required: Yes - No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3Bld Page 10 REV. 0
TASK CONDITIONS:
1. RHR Loop B was operating in Shutdown Cooling when a trip of RPS MG
Set B resulted in a Group 8 isolation and a loss of Shutdown Cooling.
2 RPS Bus B has been transferred to Alternate Power.
3. RHR Loop B flow was 6000 gpm prior to the RPS MG Set B trip.
4. The shift superintendent has directed a reactor water level band of +200" to
+220".
INITIATING CUE:
You are directed to restart RHR Shutdown Cooling using RHR Loop B per
AOP-15.0 step 3.2.8, and inform the Unit SCO when Shutdown cooling has
been restored.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
CONTROL ROOM
BNP-03-Ble
TITLE: Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
REVISION NO: 3
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Vent the Drywell per OP-10 w/Stack Rad Monitor Increase >50%
SIMULATOR SETUP:
A. Initial Conditions:
1. Recommended Initial Conditions
IC 11
Rx. Pwr. 100%
Core Age BOC
2. Required Plant Conditions
Drywell Pressure above 0.5 psig SLOWLY rising or stable, AND below 1.8 psig.
B. Malfunctions
None required
C. Overrides
Meters
Trigger 1 Q6225LGT CAC-V23 Green Lamp = False
D. Special Instructions
Secure Drywell Coolers 2C and 2D Fans 1 and 2 and allow drywell pressure to rise to
_Ž0.6 psig as indicated on CAC-PI-2685-1 on XU-51, then restart Drywell Coolers 2D Fan
2 and allow Drywell pressure to stabilize. Override Drywell Cooler 2C Fans 1 and 2 and
Drywell Cooler 2D Fan 1 control switches OFF.
33Ble Page 2 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
SAFETY CONSIDERATIONS:
NONE
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee, once it is
demonstrated he/she knows the correct procedure.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained in
NUREG 1021, Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
1. Drywell pressure is above normal due to a partial loss of Drywell Cooling.
2. AOP-14.0 has been entered.
3. Standby Gas Treatment System is in the Standby Alignment.
4. The plant stack radiation monitor is in service and CAC-CS-5519, CAC Purge Vent
Isolation Override is in OFF.
INITIATING CUE:
The Unit SCO directs you to vent the Drywell via Standby Gas Treatment, and to inform him
when drywell pressure has been reduced below 0.5 psig.
33Ble Page 3 of 12 REV. 3
Vent the Drywell per OP-1i0 w/ Stack Rad Monitor Increase >50%
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain current revision of OP-1 0, Section 8.2 and verify if applicable.
Current revision of OP-IO, Section 8.2 is obtained and verified as required.
SAT/U NSAT*
Step 2 - Record D12-RR-R600B, STACK RAD MONITOR, digital point display.
Value for D12-RR-R600B recorded in OP-IO.
SAT/UNSAT*
Step 3 - Add 0.17 to the value to obtain the logarithmic equivalent of a 50% increase in stack
radiation monitor reading and record result. 7;
Value recorded in OP-10 of initial reading + 0. 17 (1.23).
SAT/U NSAT*
NOTE:, Step 3 of Section 8.2.2 is not applicable.
Step 4 - Monitor Stack Rad Monitor, D12-RM-R600B, for increase in activity during venting.
D1 2-RM-R600B periodicallymonitored.
SAT/UNSAT*
3Ble Page 4 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
Step 5 - CLOSE REACTOR BUILDING SBGT TRAIN 2A INLET VALVE, VA-2D-BFV-RB.
VA-2D-BFV-RB indicates fully closed.
- CRITICAL STEP ** SAT/UNSAT*
Step 6 - CLOSE REACTOR BUILDING SBGT 2B INLET VALVE, VA-2H-BFV-RB.
VA-2H-BF V-RB indicates fully closed.
- CRITICAL STEP ** SAT/U NSAT*
Step 7 - OPEN SBGT DW SUCT DAMPER, VA-2F-BFV-RB.
VA-2F-BFV-RB, indicates open.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: Steps 10 and 11 of Section 8.2.2 are not applicable.
Step 8 - OPEN DW PURGE EXH VALVE, CAC-V9.
CAC-V9 indicates full open.
- CRITICAL STEP ** SAT/U NSAT*
33Ble Page 5 of 12 REV. 3
Vent the Drywell per OP-1 0 w/ Stack Rad Monitor Increase >50%
Step 9 - OPEN DW PURGE EXH VALVE, CAC-V23.
CAC-V23 indicates full open.
- CRITICAL STEP ** SAT/UNSAT*
It is normal indication in the plant for the stack rad monitor reading to rise when
NOTE: It is normal indication in the plant for the stack rad monitor reading to rise when
venting is initiated.
NOTE: When CAC-V23 is opened, stack rad monitor reading will begin to rise.
NOTE: It is not normal practice in the plant to open CAC-V49 and CAC-V50. If
examinee does not open these valves, steps 10 and 11 of this JPM are not
applicable.
PROMPT: If requested, inform examinee as Unit sc0 that it is not desired to vent from the
drywell head.
Step 10- OPEN DW HEAD PURGE EXH VLV, CAC-V49.
CAC-V49 indicates full open.
SAT/U NSAT*
Step 11 - OPEN DW HEAD PURGE EXH VLV, CAC-V50.
CAC-V50 indicates full open.
SAT/UNSAT*
33Ble Page 6 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
Step 12 - Monitor Main Stack Rad Monitor and determine reading has risen by >50%.
Determines Main Stack Rad Monitor reading has risen by >. 17 (50%).
SAT/U NSAT*
NOTE: It is critical for at least one valve to be closed in each vent path that is open,
i.e., CAC-V23 or CAC-V9, AND, CAC-V49 or, CAC-V50 (if opened), or that the
primary containment suction valve VA-2F-BFV-RB is closed to isolate the
release path.
CUE: When the vent path has been isolated, delete the meter override on the Main
Stack Rad Monitor.
PROMPT: If the examinee informs the Unit SCO that the Main Stack has risen by >50%,
direct examinee as Unit SCO to perform required actions for the, increase.
Step 13 - CLOSE DW PURGE EXH VLV, CAC-V23.
CAC-V23 indicates full closed.
- CRITICAL STEP ** SAT/UNSAT*
Step 14 - CLOSE DRYWELL PURGE EXH VALVE, CAC-V9.
CAC-V9 indicates full closed.
- CRITICAL STEP ** SAT/UNSAT*
33Ble Page 7 of 12 REV. 3
Vent the Drywell per OP-1 0 w/ Stack Rad Monitor Increase >50%
NOTE: Either Step 15 OR Step 16 of this JPM is critical ONLY if opened.
Step 15- ENSURE DW HEAD PURGE EXH VLV, CAC-V49, IS CLOSED.
CAC-V49 indicates full closed.
- CRITICAL STEP ** SAT/UNSAT*
Step 16 - ENSURE DW HEAD PURGE EXH VLV, CAC-V50, IS CLOSED.
CAC-V50 indicates full closed.
- CRITICAL STEP ** SAT/UNSAT*
Step 17 - CLOSE SBGT DW SUCT DAMPER, VA-2F-BFV-RB.
VA-2F-BFV-RB indicates full closed.
- CRITICAL STEP** SATIUNSAT*
NOTE: The following valves would auto open on SBGT Initiation therefore Steps 18 and
19 are NOT critical.
Step 18 - OPEN SBGT TRAIN 2B REACTOR BUILDING SUCTION VALVE, VA-2H-BFV-RB.
VA-2H-BFV-RB indicates full open.
SAT/UNSAT*.
33Ble Page 8 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
Step 19 - OPEN SBGT TRAIN 2A REACTOR BUILDING SUCTION VALVE, VA-2D-BFV-RB.
VA-2D-BFV-RB indicates full open.
SAT/U NSAT*
Step 20 - CONFIRM ALL SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKERS
are closed.
All Suppression Chamberto Drywell vacuum breakers verified closed.
SAT/UNSAT*
PROMPT: If asked, inform examinee as Unit SCO that E&RC has been notified to sample
containment and perform E&RC 2020, Noble Gas Instantaneous Release Rate-
Determination.
PROMPT: If asked, inform examinee as Unit SCO that another operator is standing by to
perform OPT-02.3.1, Suppression Chamber to DW Vacuum Breaker Test.
Step 21 - Inform Unit SCO venting is secured due to increase of 50% in Main Stack Rad
Monitor reading.
Unit SCO is informed venting is secured due to increase of 50% in Main Stack
Rad Monitorreading.
SAT/UNSAT*
TERMINATING CUE: Primary containment Venting has been secured.
- Comments required for any step evaluated as UNSAT.
3Ble Page 9 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
LIST OF REFERENCES
RELATED TASKS:
261 008 B1 01, Perform Normal Primary Containment Venting.
K/A REFERENCE AND IMPORTANCE RATING:
261000 A4.04 3.3/3.4
Ability to manually operate and monitor Primary Containment Pressure.
REFERENCES:
20P-10, Sect. 8.2 Rev 59
TOOLS AND EQUIPMENT:
None
SAFETY FUNCTION (from NUREG 1123, Rev 2):
Safety Function 9, Radioactivity Release
REASON FOR REVISION:
Bank JPM. Minor changes.
33Ble Page 10 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
Time Required for Completion: 10 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual v" Unit: 2
Setting: Control Room V(Not applicable to In-Plant JPMs)
Simulatori
Time Critical: Yes No v/ Time Limit N/A
Alternate Path: Yes V/ No
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
33Ble Page 11 of 12 REV. 3
TASK CONDITIONS:
1. Drywell pressure is above normal due to a partial loss of Drywell Cooling.
2. AOP-14.0 has been entered.
3. Standby Gas Treatment System is in the Standby Alignment.
4. The plant stack radiation monitor is in service and CAC-CS-5519, CAC Purge Vent
Isolation Override is in OFF.
INITIATING CUE:
The Unit SCO directs you to vent the Drywell via Standby Gas Treatment, and to inform him
when drywell pressure has been reduced below 0.5 psig.
-I
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
CONTROL ROOM
TITLE: Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
Simulator Setup:
IC-11
Triggers
El - Trips CREV Train A
E2 - Trips CREV Train B
E3 - Overrides Emerg Air Fan Fail To Run alarm
Malfunctions
None
Overrides
El - CREV Train A Switch in STBY
E2 - CREV Train B Switch in STBY
E3 - Alarm UA-14 2-2 ON
3Blf Page 2 of 9 Rev. 0
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
SAFETY CONSIDERATIONS:
None
EVALUATOR NOTES: (Do not read to examinee)
1. The applicable procedure section WILL be provided to the examinee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained in NUREG 1021,
Appendix E, or similar to the examinee.
Read the following to examinee.
TASK CONDITIONS:
1. You are the Unit Two Control Operator.
2. Unit Two is operating at power. Unit One is in MODE 5.
3. The Control Building Emergency Recirculation System is in standby.
4. A fuel handling accident has occurred on Unit One.
5. The Unit One SCO has entered AOP-05.0 and EOP-04-RRCP.
6. This JPM is time critical.
INITIATING CUE:
You are directed to perform the actions for manual startup of the Control Building
Emergency Recirculation System Per the Hard Card and inform the Unit SCO when the
actions are complete.
33Blf Page 3 of 9 Rev. 0
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 -Obtain hard card S/1067.
Hard card S/1067 obtained.
SAT/UNSAT*
Step 2 - PLACE CB Emergency Recirculation Fan, 2A(B)-ERF-CB in ON.
2A(B)-ERF-CB control switch placed to ON.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - ENSURE Control Room Normal Makeup Damper, 2L-D-CB, Closes.
2L-D-CB, Control Room Normal Makeup Damper verified closed.
SAT/UNSAT*
Step 4 - ENSURE Control Building Emergency Recirculation Damper, VA-2J-D-CB, Opens.
VA-2J-D-CB, Control Building Emergency Recirculation Damper verified OPEN.
SATIUNSAT*
33Blf Page 4 of 9 Rev. 0
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
NOTE: Monitor CREV on panel mimics. f CREV Fan A has, been started, initiate Triggers 1
and 3. If CREV Fan B has been started, initiate Triggers 2 and . Do NOT initiate
both Triggers I andd 2.
Dropping 'out the, 42 device, on eit her CREV Fan, 10 seconds after an auto start in
PREF, or a manual start will bring in alarm UA-14 2-2.
'The examinee may start the CREV Fan that was not previously running per guidance
of the Hard Card or APP UA-1 4 2-2.
If the Fan that was tripped is placed in Stby or Pre0 delete alarm override ZUA1422.
Step 5 - Recognize loss of running CREV Fan and START the CREV not previously started.
One CREV Train (A ore B) is in operation)
- CRITICAL STEP **SAT/UNSAT*
Step 6 - STOP Control Building Washroom Exhaust Fan, 2D-EF-CB, and ENSURE
associated damper closes.
2D-EF-CB, ControlBuilding Washroom Exhaust Fan, stopped and associated
damper verified closed.
- CRITICAL STEP ** SAT/UNSAT*
Step 7 - STOP Control Building Mechanical Equipment Room Vent Fans, 2F-SF-CB and
2E-EF-CB, and ENSURE associated Supply and Exhaust Dampers CLOSE.
2F-SF-CB and 2E-EF-CB, Control Building MechanicalEquipment Room Vent
Fans stopped and associated Supply and Exhaust Dampers verified closed.
- CRITICAL STEP ** SAT/UNSAT*
33Blf Page 5 of 9 Rev. 0
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
Step 8 - STOP Cable Spread Room 2 Vent Fans, 2A-SF-CB and 2A-EF-CB, and ENSURE
associated Supply and Exhaust Dampers CLOSE.
2A-SF-CB and 2A-EF-CB, Cable Spread Room 2 Vent Fans stopped and
associatedSupply and Exhaust Dampers verified closed.
- CRITICAL STEP ** SAT/UNSAT*
PROMPT: When requested to STOP (Unit One) Cable Spread Room 1 Vent Fans initiate
I batch file unit one cable spread fan shutdown j
Step 9 - Request Unit 1 STOP Cable Spread Room 1 Vent Fans, 1A-SF-CB and 1A-EF-CB,
and ENSURE associated Supply and Exhaust Dampers CLOSE.
1A-SF-CB and IA-EF-CB, Cable Spread Room I Vent Fans stopped and
associatedSupply and Exhaust Dampers verified closed.
- CRITICAL STEP ** SAT/UNSAT*
Step 10 - Inform Unit SCO that actions for manual startup of the Control Building Emergency
Recirculation System are complete.
Unit SCO notified.
SAT/UNSAT*
TERMINATING Cue: When the Control Building Emergency Recirculation System has been
started and isolated per the hard card, this JPM is complete.
. Comments required for any step evaluated as UNSAT.
33Blf Page 6 of 9 Rev. 0
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
RELATED TASKS:
288202B1301, Start the Control Building ventilation System per OP-37
K/A REFERENCE AND IMPORTANCE RATING:
290003 A4.01 3.2/3.2
Ability to use procedures to manually initiate Control Building HVAC.
REFERENCES:
Hard Card S/1067
TOOLS AND EQUIPMENT:
None
SAFETY FUNCTION (from NUREG 1123, Rev. 2)
9, Radioactivity Release
REASON FOR REVISION:
New JPM.
33Blf Page 7 of 9 Rev. 0
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
LIST OF REFERENCES
Time Required for Completion: 10 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual V Unit: 0
Setting: Control Room Simulator "/(Not applicable to In-Plant JPMs)
Time Critical: Yes / No Time Limit 20 min
Alternate Path: Yes * No
EVALUATION
Examinee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes No
Did Examinee Verify Procedure? Yes __ No
(Each Student should verify one JPM per evaluation set)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
33Blf Page 8 of 9 Rev. 0
TASK CONDITIONS:
1. You are the Unit Two Control Operator.
2. Unit Two is operating at power. Unit One is in MODE 5.
3. The Control Building Emergency Recirculation System is in standby.
4. A fuel handling accident has occurred on Unit One.
5. The Unit One SCO has entered AOP-05.0 and EOP-04-RRCP.
6. This JPM is time critical.
INITIATING CUE:
You are directed to perform the actions for manual startup of the Control Building
Emergency Recirculation System Per the Hard Card and inform the Unit SCO when the
actions are complete.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
CONTROL ROOM
BNP-03-Blg
LESSON TITLE: Core Performance Parameter Check - Manual APRM GAF
Adjustment Required
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
SIMULATOR SETUP:
A. Initial Conditions:
1. Recommended Initial Conditions
IC 11 (UNIT1)
B. Malfunctions
None
C. Overrides
None
D. Special Instructions
1. Ensure Process Computer is operating properly.
2. At the NUMAC adjust the gain for APRM 1 so APRM 1 GAF (PPC 820) is 1.02.
3. Obtain an updated Core Performance Log to provide to the examinee.
33Blg Page 2 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
SAFETY CONSIDERATIONS:
1. NONE.
EVALUATOR NOTES: (Do not read to examinee)
1. The applicable procedure sections WILL be provided to the examinee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained in
NUREG 1021, Appendix E, or similar to the examinee.
3. This JPM will be administered on the Simulator.
4. Performance means Frequency A (every 24 hrs when >25% RTP) is required.
Read the following to examinee.
TASK CONDITIONS:
1. The CODSR (Control Operator Daily Surveillance Report) requires performance of
1PT-01.11 Core Performance Parameter Check on Unit 1.
2. All applicable prerequisites of IPT-01.11 are met.
3. Ifindependent verification is required, assume the verification is complete as
applicable.
INITIATING CUE:
The Unit SCO directs you to perform 1PT-01.11 and inform the SCO of the results upon
completion.
Page 3 of 16 REV. 0
3Blg
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain current revision of 1PT-01.11 and verify if applicable.
Currentrevision of IPT-01. 11 obtainedand verified as required.
References Section 7.1
SAT/U NSAT*
PROMPT:':ý Once examinee demonstratesý that he/she can' demand a,Core Performanc'e Lo~g,
prvide, theCr Perfdrrntnce: Log obtained before administebring this ,JP for;,".
use throughout the'remaindrothsJM
NOTE:ý An edit of the process computer core performan ce program is obtained by calling
upcmue i~a 2,depesn the blue soft:10 kIe9I ,;then:depressing,the
blue soft 2 key,
There are many methods 'to call up computer display 820. The quickest way is to
simply depress' the green, Heat Balance soft key.
Step 2 - Obtain an edit of the process computer core performance (Heat Balance/Core Mon)
program.
Core Performance Log (HeatBalance/Core Mon) obtainedfrom process
computer.
SAT/UNSAT*
33B1g Page 4 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
NOTE::'J Failed sensor inputs would, be identified, by a magenta value: displ'ayed in the'
..upperight quadrant ofcomuter display 820, which ststhsensor nputs to the
i heat balance.
Step 3 - Verify, using the Failed Sensor List, failed inputs have correct substitute values.
Determines no failed sensors exist and that this step is marked as N/A.
SAT/UNSAT*
Step 4 - Locate WTFLAG on the Core Performance Log and proceed with step 7.1.5.
WTFLAG determined to equal 2, proceeds to Step 7.1.5 of 1PT-01. 11.
SAT/UNSAT*
Step 5 - Determine if criteria listed in Section 6.1 of 1PT-1.11 are met.
Checks core performance log and verifies value for CMFLCPR *1.00.
SAT/UNSAT*
Checks core performance log and verifies value for CMAPRA T_*I.00.
SAT/UNSAT*
PROMPT: If informed that APRM I GAF is,> 1.00, direct the examinee to adjust APRM 1 to
ithin Imits using manual GAP adjustment.
331lg Page 5 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
PROMPT,: Inf6rm examinee that the Unit SC0 approves adjustment of,APRM GAF byý
performing a manual gain adjustment with th Ap
NoTE If ~equ ed. the examiner many act as the independen veiierI
Step 6 - Determine ifthe acceptance criteria listed in Section 6.2 of 1 PT-01.11 are satisfied.
DeterminesAPRMS 2, 3, and 4 are within limits and APRM I is above the limit.
"**CRITICAL STEP ** SAT/UNSAT*
Step 7 - Obtain current revision of 1OP-09 and verify if applicable.
Current revision of I OP-09 obtained and verified as required. References
Section 8.1.2.
SAT/UNSAT*
I
PROMPT: As the Unit SC0, direct the examinee to adjust the GAF on APRM I by /
performiaig a manual gain adjustmentwith the* PRM bypassed. ":11",
NOTE: if requested, the examiner may act as the independentverfer
Step 8 - OBTAIN Unit SCO permission to adjust the APRM GAFs.
Obtains SCO permission.
SAT/UNSAT*
" 3Blg Page 6 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step 9 - OBTAIN Display 820 at the PPC.
PPC Screen 820 is displayed.
SAT/UNSAT*
Step 10 - Review heat balance substituted values and failed sensors for impact on APRM 1
gain adjustment.
Determines no substitute values and no failed sensors.
SAT/UNSAT*
Step 11 - Ensure APRM 1 keylock is in OPER.
Checks APRM keylock in OPER.
SAT/UNSAT*-
Step 12 - Ensure APRM 1 heading indicates OPERATE.
Checks APRM I headershows OPERA TE.
SAT/U NSAT*
NOTE: Since the simulator models Unit 2i but has Unit TAPRM, Process Computer
PointUC5IR1e06 is rit avai ab'* on teruar(t 2 )roces Computer.
PROMT: irect: examinee to use Process Computer oint U2C51R1066,for GAFn
adjustment.'
- J 313Blg Page 7 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step 13 - OBTAIN value of U1 C51 RI 066.
Obtains U1C51R1066 from PPC Screen 820 or Core Performance Log.
SAT/UNSAT*
Step 14 - PLACE the APRM to be adjusted in BYPASS.
Places APRM I in bypass at P603.
SAT/U NSAT*
Step 15 - CONFIRM BYP is indicated for the selected APRM channel at Panel P608.
Observe BYP (BYPASS) heading in inverse video for APRM 1.
SAT/UNSAT*
Step 16 - PRESS ETC soft key to obtain ENTER SET MODE soft key.
Obtains the ENTER SET MODE soft key.
- CRITICAL STEP ** SAT/UNSAT*
Step 17 - PRESS ENTER SET MODE soft key.
PressesENTER SET MODE soft key.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: If ten (10)seconds expires before the password is accepted (ENT is pred°o
the numeric keypad) the screen, will revert to the Main APRM Bar Graph display.
-The examinee must repeat steps 16,A718 to access the correct screen.
PROMPT-:'If requested, direct the tArafinee to take ainy'actions needed to dontinue.:,
3Blg Page 8 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step 18 - ENTER password "1 2 3 4" AND PRESS ENT.
Using the data keypad enters 1234 and presses ENT before 10 seconds expire.
- CRITICAL STEP ** SAT/UNSAT*
Step 19 - SELECT APRM GAIN using cursor keys.
Using the cursorkeypad selects APRM GAIN.
SAT/UNSAT*
Step 20 - PRESS SET PARAMETERS soft key.
Presses SET PARAMETERS soft key.
"**CRITICAL STEP ** SAT/UNSAT*
Step 21 - CONFIRM APRM indicates SET PARAMETERS: APRM GAIN display.
Observes SET PARAMETERS: APRM GAIN displayed.
SAT/U NSAT*
NOTE: The LEFT and RIGHTcursor keys are used to select the DESIRED GAIN digitt
be modified-, andthe UP and DOWN cursor keys will change the selectedd
The PROJECTED FLUX (%) apn'd -the PROJECTED, AGAF are recalculated each
tiea DESIRED, APRMGAIN: digit: is,changed. I
3Blg Page 9 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step 22 - ADJUST the DESIRED APRM GAIN so that the PROJECTED FLUX (%) is Ž> Heat
Balance value previously obtained.
Using the cursorkeypad selects and changes the DESIRED APRM GAIN until
PROJECTED FLUX (%o) is Ž Heat Balance value obtainedin Step 13.
"**CRITICAL STEP ** SAT/UNSAT*
Step 23 - PRESS ACCEPT soft key.
Presses ACCEPT soft key.
"**CRITICAL STEP ** SAT/UNSAT*
Step 24 - CONFIRM the "PRESENT" APRM GAIN changes to equal the "DESIRED" APRM
GAIN AND the PROJECTED AGAF equals 1.000.
Confirms "PRESENT"and "DESIRED"APRMGAIN equal and PROJECTED
AGAF is *<1.000.
SAT/UNSAT*
Step 25- PRESS EXIT soft key.
Presses EXIT soft key.
SAT/UNSAT*
Step 26 - PRESS EXIT SET MODE soft key.
Presses EXIT SETMODE soft key.
SAT/UNSAT*
3Blg Page 10 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step 27 - PRESS YES soft key.
Presses Yes soft key.
SAT/UNSAT*
Step 28 - CONFIRM APRM display header shows OPERATE.
Confirms APRM display headerindicates OPERA TE.
SAT/UNSAT*
Step 29 - Verify APRM GAF * 1.00 on Attachment 3 of 1OP-09.
Confirms APRM I AGAF *<1.00 using PPC 820 screen or by obtaining a new
Core PerformanceLog.
SAT/UNSAT*
Step 30 - REMOVE APRM from BYPASS.
Removes APRM I from bypass at P603.
SAT/UNSAT*
Step 31 - If Process Computer is available AND additional APRM GAF adjustments are NOT
required, Then perform the following:
a. Press XFER COMMAND soft key from PPC Screen 877, PRNM TO PPC DATA
TRANSFER MENU
XFER COMMAND soft key from PPC Screen 877, PRNM TO PPC DATA
TRANSFER MENU is depressed
SAT/UNSAT*
3Blg Page 11 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
b. Press A/L GAINS soft key from PPC Screen 877, to initiate transfer of LPRM
and APRM Gains from PRNM to PPC
AIL soft key from PPC Screen 877, is depressed
SAT/U NSAT*
c. Confirm completed transfer status on PPC Screen 887
Completed transferstatus on PPC Screen 887 is confirmed
SAT/UNSAT*
PROMPT Inform examinee that andther operator will complete Attachment 3.
Step 32 - Determine if CMFLPD is *<1.00.
Checks core performance log and verifies value for CMFLPDis *1.00.
SAT/U NSAT*
NOTE: The Following Step is like aread performed and is NOT required to be
completed again,:i:I
Step 33 - Verify acceptance criteria listed in Section 6.0 met satisfactorily.
Acceptance criteria determined to be satisfactory.
SAT/UNSAT*
3Blg Page 12 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
<-
Step 34 - Notify Unit SCO that 1PT-01.11 is completed SAT.
Supervisor notified.
SAT/UNSAT*
.6 m
TERMINATINGCCU.'E
11PT-O1 .11 acceptance Icriteria verified and th IeUnit SCO informed the results are Isatisfactory.
i-Il I
0
- Comments required for any step evaluated as UNSAT.
3Blg Page 13 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
LIST OF REFERENCES
RELATED TASKS:
215209B401: Operate the PRNMS per OP-9.
K/A REFERENCE AND IMPORTANCE RATING:
215005 A1.07 (3.0/3.4)
REFERENCES:
1PT-01.11
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2):
7 - Instrumentation (APRM System)
REASON FOR REVISION:
Bank JPM. Modified to provide enhanced examiner notes. Changed from alternate
path to not alternate path.
3Blg Page 14 of 16 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate Actual 4 Unit: I
Setting: Control Room Simulator 4 (Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes No 4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3Blg Page 15 of 16 REV. 0
TASK CONDITIONS:
1. The CODSR (Control Operator Daily Surveillance Report) requires performance of
1PT-01.11 Core Performance Parameter Check on Unit 1.
2. All applicable prerequisites of 1PT-01.11 are met.
3. Ifindependent verification is required, assume the verification is complete as
applicable.
INITIATING CUE:
The Unit SCO directs you to perform 1PT-01.11 and inform him of the results upon
completion.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
IN-PLANT
BNP-03-B2a
LESSON TITLE: Start RCIC From The Remote Shutdown Panel.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer UATEI
CONCURRENCE BY:
LilA 11=
Line SuperintendentlSupervisor DATE I
APPROVED BY:
Superintendent/Supervisor Training DATE
Start RCIC From The Remote Shutdown Panel.
SAFETY CONSIDERATIONS:
Use caution in vicinity of energized electrical equipment.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL NOT be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. This JPM is written based on RCIC being in the standby alignment.
4. This JPM may be performed on either Unit.
Read the following to trainee.
TASK CONDITIONS:
1. The Shift Superintendent has directed entry into AOP-32.0 and evacuation of the
Control Room.
2. All immediate actions of AOP-32.0 are complete.
3. Remote shutdown equipment has been distributed and communications between
remote shutdown stations is established.
4. All Normal/Local switches listed in AOP-32.0 have been placed in Local.
5. This task will be performed on Unit . (Specified by the examiner)
INITIATING CUE:
You are directed by the Unit SCO to perform ALL operator actions, including Remote
Shutdown Panel actions (Stations 1, 2, & 3) required to start RCIC for reactor vessel
injection to maintain reactor vessel injection +170-200". You are to inform the Unit SCO
when reactor vessel level is >170", or reactor vessel level is rising toward 170".
3132a Page 2 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
NTE:1 The hae cpy of0
examin e1e, woul haere AO-3 already.I desrd the' eaiet may
a the` e'xmnee
ask w er thee,,remote shutdowný procedure and equi;:mnt is normallyI
nee.... II
Step 1 - Obtain a current revision of AOP-32.0.
Current Revision of AOP-32.0 obtained.
SAT/U NSAT*
NOTE; The yellowALM light on ROIC Flow Controler, E51-FIC-3325 will:be lit for actual
plant con~ditions' since the, Normal/Local switch is4i Local and poweris isolated .1
l
hn asked, inform examine ,that yellow ALM light on: ROIC Flo1w :Controller, Eý51-
PRMP:
FC-3325 isOU ou __ 5_ I
Step 2 - Station 1, Verify yellow ALM light on RCIC Flow Controller, E51-FIC-3325, is out.
Yellow ALM light on RCIC Flow Controller, E51-FIC-3325, verified out
SAT/U NSAT*
NOTE R!s .
assumed to be in a normal..standby. alignmoent for this J.P
PROMPT:!When asked inform examinee that E51-FOIO red light is On gren light: off
indicated at MCC 1(2)XBD.
3132a Page 3 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
Step 3 - Station 2, verify open or open RCIC CST Suction Valve E51-F010, at MCC 1(2)XBD,
Compt B38, Row C2.
E51-FOIO is verified open.
SAT/UNSAT*
PROMT Whenask6ed, inform 2examinee Xl that E51-F031 red light is off, green Ight ona-zs
indicatd'
. t MOO( )XB..
Step 4 - Station 2, verify closed or close RCIC Supp Pool Suction Valve E51-F031, at MCC
I(2)XBD, Compt B45, Row G1.
E5I-F031 is verified closed.
SAT/UNSAT*
PROMPT: When asked, inform examinee that E51-FQ29 red light is off, green light n
indicated atMCC 1(2)XBD.::,,',,
Step 5 - Station 2, verify closed or close RCIC Supp Pool Suction Valve E51-F029, at MCC
I(2)XBD, Compt B46, Row G2.
E51-F029 is verified closed.
SAT/UNSAT*
3132a Page 4 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
PROMPT When- gsked, inform examirneethat E51-F046 red light is off, green lightion as
indicated at C 2XD
sea :!i , ý ,-iý
When'examinee, places localsichtOpn indic'ate reiht onhen gre lihtý
S:
Step 6 - Station 2, verify open or open RCIC Cooling Water Valve E51-F046, at MCC
I(2)XBD, Compt B39, Row D1.
E51-F046 is opened at the MCC.
- CRITICAL STEP ** SAT/UNSAT*
PROPT:Whn asked, inform exa~minee that, E51 -F01 2 red light is on' green light ofa
iniatedaL MOOI 2)BD
"Step7 - Station 2, verify open or open RCIC Pump Discharge Valve E51-F012, at MCC
1(2)XBD, Compt B40, Row D2.
E51-F046 is verified open.
SAT/U NSAT*
3132a Page 5 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
PROMPT: When asked, inform examninee that E51-F013 red light is off green lght on as
indicated at MCC I (2)XBD.
place , switch to O,
oal indicate, red light on, tengreken light
"When examine!~se pacs p-en 9..........
- off (Valve is seal-in)
Step 8 - Station 2, verify open or open RCIC Injection Valve E51-F013, at MCC 1(2)XBD,
Compt B41, Row El.
E51-F013 is opened at the MCC.
- CRITICAL STEP ** SAT/UNSAT*
Whn ased, at~r xamiee paces RCIC barometric condenser vacuum pump't
PROMP:
start at the MCC, inform examinee that'ROIC b~ometric condenser vacuum. pumv-pd
red ig ht is 6 n: gree6n ig htoff' as i nd icated, at M CC 1,(2)X BD.
Step 9 - Station 2, Start the RCIC barometric condenser vacuum pump, at MCC 1 (2)XBD,
Compt B35, Row B1.
RCIC barometric condenservacuum pump is running.
- CRITICAL STEP ** SAT/UNSAT*
"*.-*' 3B2a Page 6 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
PROMPT: When asked inform exaninee th6at E51-V8 red ight is on green ight offas K
irndiated at MOC 1(2)XBOD
Step 10 -Station 2, verify open or open RCIC Turbine Trip and Throttle Valve E51-V8, at MCC
1(2)XBD, Compt B37, Row C1.
E51-V8 is verified open.
SAT/UNSAT*
PROMPT: When ask'ed, inform examinee thatE51-_F008,red light, is,on,: green light, off a6si
indicated at MOOC 1(2ý)XbD. I
Step 11 -Station 2, verify open or open RCIC Steam Supply Outboard Isolation Valve E51
F008, at MCC 1(2)XBD, Compt B43, Row Fl.
E51-FO08 is verified open.
SAT/UNSAT*
PROMPT: When asked, inform examine that E51-F007 red light is on, green light *ff as
indcated at MOO (2)ýXC.
Step 12 -Station 3, verify open or open RCIC Steam Supply Inboard Isolation Valve E51
F007, at MCC 1(2)XC, Compt DS4, Row D3.
E51-FO07 is verified open.
SAT/UNSAT*
3132a Page 7 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
PROMPT-: When asked, inform::exam iIneIeh that, E51-F045 red light is off, green, light on a's
1(2)XBD, Compt B44, Row F2.
E51-F045 is opened at the MCC.
- CRITICAL STEP ** SAT/UNSAT*
PROMPT: If *requstedindicate' RCICfl'o as indicated ,n E51 -F C-3325 indicates 400 gp
(sa4-Sas controller setting)C
Stp d that
flo controlft r output indicates 80%.
Step 14 -Station 1, Verify ROIC flow corresponds to ROIC Flow Controller, E51 -FIC-3325,
setting.
RCIC flow corresponds to RCIC Flow Controller,E51-FIC-3325,setting.
SAT/U NSAT*
- 3132a Page 8 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
PROPT:Whe asked~inform 'eamin~ee that E51-F01,9 red lightIis off,' gree lihtona
indicated at MCC 1,(2)XDB
Step 15- Verify closed, or close RCIC Minimum Flow Bypass Valve to
Suppression Pool, E51-F019, at MCC l(2)XDB Compt B47,
Row H1.
E51-F019 is verified closed.
SAT/UNSAT*
PROMPT.: When asked, inform examinee that reactor level indicates +150 inches and steady:ý
on wide range level instrumnent at remote shutdown p anel, (0-210 inchies, B1-I
R6O4BX).
Step 15 -Station 1, Adjust RCIC Flow Controller, E51 -FIC-3325, to maintain reactor vessel -..
level between 170" and 200".
RCIC setpoint tape maintained at 400 gpm, or adjusted to _<500 gpm.
SAT/U NSAT*
Step 16 -Inform Unit SCO that RCIC is injectiong to the reactor vessel and level is being
maintained 170: to 200".
Unit SCO informed.
SAT/U NSAT*
TERMINATING CUE: When RC C *has been started per AOP-32.0, thisJPM Is 6cmplete.
3132a Page 9 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
- coniments- required for any step evaluated as UNSAT.
3132a Page 10 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
RELATED TASKS:
200204B401, Perform The Station 1 Actions For Shutdown Outside The Control Room Per
K/A REFERENCE AND IMPORTANCE RATING:
295016 AA1.06 4.0/4.1
REFERENCES:
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
2 - Inventory Control (Reactor Core Isolation Cooling)
REASON FOR REVISION:
Bank JPM. Converted to WORD and updated for latest procedure revision.
3132a Page 11 of 13 REV. 0
Start RCIC From The Remote Shutdown Panel.
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate 4 Actual Unit: 0
Setting: Control Room Simulator ( Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes No 4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3B2a Page 12 of 13 REV. 0
TASK CONDITIONS:
1. The Shift Superintendent has directed entry into AOP-32.0 and evacuation of the
Control Room.
2. All immediate actions of AOP-32.0 are complete.
3. Remote shutdown equipment has been distributed and communications between
remote shutdown stations is established.
4. All Normal/Local switches listed in AOP-32.0 have been placed in Local.
5. This task will be performed on Unit . (Specified by the examiner)
INITIATING CUE:
You are directed by the Unit SCO to perform ALL operator actions, including Remote
Shutdown Panel actions (Stations 1, 2, & 3) required to start RCIC for reactor vessel
injection to maintain reactor vessel injection +170-200". You are to inform the Unit SCO
when reactor vessel level is >170", or reactor vessel level is rising toward 170".
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
IN-PLANT
BNP-03-B2b
LESSON TITLE: Local Manual Start Of A DG Using Prelube Start Control.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Local Manual Start Of A DG Using Prelube Start Control.
SAFETY CONSIDERATIONS:
Use caution in the vicinity of operating equipment.
Use caution in vicinity of energized electrical equipment.
Hearing Protection required in the Diesel Building.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee.
2. Ifthis is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
3. This JPM may be performed on any of four Diesel Generators (ensure DG is in standby
alignment, not running or under clearance).
Read the following to trainee.
TASK CONDITIONS:
1. All applicable prerequisites as listed in OP-39, Section 4.0 are met.
2. Diesel Generators are in the standby mode in accordance with OP-39, Section 5.1.
3. Diesel Generator# is to be started.
4.
5. The Diesel Generator will be tied and loaded from the Control Room per OP-50.1.
INITIATING CUE:
You are directed by the Unit SCO to perform a local manual start of Diesel Generator
per OP-39, Section 5.4. You are to inform the Control Room when the Diesel Generato-ris
ready for electrical operation per OP-50.1.
3132b Page 2 of 10 REV. 0
Local Manual Start Of A DG Using Prelube Start Control.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of OOP-39, Section 5.4.
Current Revision of OOP-39, Section 5.4 obtainedand verified, if applicable.
SAT/UNSAT*
Step 2 - Confirm the diesel Generator auxiliary systems are operable by observing the
following conditions locally.
PROMPT: If requested, indicate each rqading/indication for the following steps is "as-seeni!'.
a. Starting air pressure is between 240-260 psig as indicated by DG-PI
6514-1 (2, 3, 4)
Starting airpressure is observed to be between 240-260 psig as
indicated by DG-PI-6514-1 (2, 3, 4).
SAT/UNSAT*
b. Starting air Receivers A & B pressures are between 325-350 psig as
indicated by DG-PI-1690 and 1692 (1674 and 1677, 1663 and 1666, 787
and 788)
Starting air Receivers A & B pressures are observed to be between
325-350 psig as indicated by DG-PI-1690and 1692 (1674 and 1677,
1663 and 1666, 787 and 788).
SAT/UNSAT*
3132b Page 3 of 10 REV. 0
Local Manual Start Of A DG Using Prelube Start Control.
c. Engine control air pressure is between 90-125 psig as indicated by DG-PI
1686 (1680,1660,1252).
Engine control air pressureis observed to be between 90-125 psig as
indicated by DG-PI-1686 (1680, 1660, 1252).
SATIUNSAT*
d. Jacket Water Expansion Tank level is between 1/2 and 3/4 full in sight glass.
Jacket Water Expansion Tank level is observed to be between Y2 and
Y4 full in sight glass.
SAT/UNSAT*
e. Jacket Water Heater Pump is in operation.
Jacket Water HeaterPump observed to be in operation.
SATIUNSAT*
Jacket Water Heater temperature out is between 1500 to 1600 as
indicated by MUD-TI-2117 (4144, 2171, 2198).
Jacket Water Heatertemperature out is observed to be between 1500
to 160 0 as indicated by MUD-TI-2117 (4144, 2171, 2198).
SAT/UNSAT*
3B2b Page 4 of 10 REV. 0
Local Manual Start Of A DG Using Prelube Start Control.
g. Lube Oil Filter Pump is in operation.
Lube Oil FilterPump observed to be in operation.
SAT/U NSAT*
h. Lube oil bypass filter temperature is between 1300 to 1600 as indicated by
LO-TI-2062 (2040, 2063, 2086).
Lube oil bypass filter temperature is observed to be between 130 0 to
1600 as indicated by LO-TI-2062 (2040, 2063, 2086).
SAT/UNSAT*
Governor oil level is at or above the high level mark.
Governoroil level is observed to be at or above the high level mark.
SAT/UNSAT*
NOTE: The DG can be placed in LOCAL MANUAL mode form control room pane XU2only
16
PROMPT: When control room is reýuestd t'o tra*nsfer the Diesel Generator to the Local
Manual mode, informjexamihiee he Diesel"Generator is in the Loca Manual imode.,
. If requested, indicate the o 6! liht on the Engine Contro ane is li and
A Start light is:out.. .. .. .. ....
g
I 1
gm
3B2b Page 5 of 10 REV. 0
Local Manual Start Of A DG Using Prelube Start Control.
Step 3 - Request control room place the DG in the Local Manual mode.
DG is in the Local Manual Mode.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: When the PrestartFPB is depressed, engine auxiliaries (i.e., motor driyen lube oil
jacket water pumps, cirahkcase vacuumn blower) auto start. Actual engine crakn
eng of air start solenoids ) is time delayed by 20 seconds., Auto sI on
S~ actions
depressing: the Pre'start are listedinýr OP-39, Section 5'.4.2, Steps'4a thkrough .4f.'":ý
PROMPT,: When exminee depresses Prestart PB, if requested, after 20 seconds indicate
engine has started as indicated by noise, RPM indication, or any other, reasonabe
indication a large.engine is unning .
II DT* infnrm examinee that observation of automatic actions for troubleshootin: is not I
iuired andcan be mark -II
Step 4 - Depress PRESTART push button located on local Engine Control Panel
PRESTART push button is depressed.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: The following alarm is locatedý contro roo panel XU-2.I
I
PROMPT: After approximately, 10 seconds from the time the engine starts, inform examinee
Xthat theDG Runn6lr is been received in the control room.
,PROMPT:,When: requested, indicate, Service Water Pressure on, SWP-153-1 (2, 3, 4)
I
indicatesý approximately: 4,5 1'psig. I
111ý
3132b Page 6 of 10 REV. 0
Local Manual Start Of A DG Using Prelube Start Control.
Step 5 - Ensure Service Water Pressure SW-PI-1 53-1 (2, 3, 4) on Engine Control Panel is 40
50 psig, by adjusting Jacket Water Cooler Service Water Outlet Valve 2-SW-V206
(V207, V208, V209), to maintain pressure.
Service Water Pressure SW-PI-153-1 (2, 3, 4) on Engine Control Panelis
observed to be 40-50 psig.
SAT/UNSAT*
=,
I....
6; -
PROMPT: lporm examine ..that an oth erbope rator, will mopn itor diesel gQe nerato r! ope ration in
accordance with section 6.0.
-
Ii
Step 6 - Inform the control room that the diesel generator is ready for electrical operation per
Control room informed that the diesel generatoris ready for electricaloperation
per OP-50.1.
SAT/U NSAT*
TERMINATING CUE: When the DG is running and readyfor electrical operation, this JPM is
'complete.ý:
- Comments required for any step evaluated as UNSAT.
3132b Page 7 of 10 REV. 0
Local Manual Start Of A DG Using Prelube Start Control.
RELATED TASKS:
264004B204, Perform DG Monthly Load Test Per PT-12.2A-D
K/A REFERENCE AND IMPORTANCE RATING:
264000 A1.03 2.9/2.9.
REFERENCES:
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
6 - Electrical (Emergency Generators)
REASON FOR REVISION:
Bank JPM. Revised from WP to WORD.
3132b Page 8 of 10 REV. 0
Local Manual Start Of A DG Using Prelube Start Control.
Time Required for Completion: 10 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate 4 Actual Unit:
Setting: Control Room Simulator ( Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes No 4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3132b Page 9 of 10 REV. 0
TASK CONDITIONS:
1. All applicable prerequisites as listed in OP-39, Section 4.0 are met.
2. Diesel Generators are in the standby mode in accordance with OP-39, Section 5.1.
3. Diesel Generator # is to be started.
4. The Diesel Generator will be tied and loaded from the Control Room per OP-50.1.
INITIATING CUE:
You are directed by the Unit SCO to perform a local manual start of Diesel Generator __
per OP-39, Section 5.4. You are to inform the Control Room when the Diesel Generator is
ready for electrical operation per OP-50.1.
N.
0
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
IN-PLANT
BNP-03-B2c
LESSON TITLE: Fire Water Injection Using The Motor Driven Fire Pump.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Fire Water Injection Using The Motor Driven Fire Pump.
SAFETY CONSIDERATIONS:
Use caution in the vicinity of operating equipment.
Use caution in vicinity of energized electrical equipment.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL be provided to the trainee.
2. If this is the first JPM of the JPM set, read the JPM briefing contained NUREG 1021,
Appendix E, or similar to the trainee.
Read the following to trainee.
TASK CONDITIONS:
1. Unit One is in accident conditions, and is executing EOP-01 -RVCP due to low reactor
water level. Reactor water level is below Top of Active Fuel. EOP-01-RVCP directs
aligning all available alternate coolant injection per EOP-01-LEP-01. Reactor pressure,
is 10 psig.
2. Off-Site Power is unavailable to either unit. DG2 is tripped, and Bus E2 is de
energized, and cannot be energized by cross-tie. Buses El, E3, and E4 are energized
by their respective DGs. Buses E5 and E6 have been cross-tied.
3. The Diesel Driven Fire Pump is unavailable.
4. The Motor Driven Fire Pump is aligned to its normal power supply. The Motor Driven
Fire Pump cannot be started from the control room.
5. Fire protection tank level is normal. A radwaste operator is available to control and
monitor fire protection tank level.
6. RHR Loop B injection flow path is available.
3132c Page 2 of 9 REV. 0
Fire Water Injection Using The Motor Driven Fire Pump.
INITIATING CUE:
You are directed by the Unit CO to transfer the Motor Driven Fire Pump to its alternate
power supply, start the Motor Driven Fire Pump locally, and perform the AO actions for
aligning Fire Protection Injection per EOP-01-LEP-01, Section 6, and inform the CO when
your actions are complete.
3132c Page 3 of 9 REV. 0
Fire Water Injection Using The Motor Driven Fire Pump.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
NOTE: Steps in LEP-01 to start the Fire Pump (OP-41) are in parenthesis. Per 01-28,
Swithoutduring EOP execution, these steps may be (but are NOT required to be) performed
procedure. ý
I
I
Step 1 - Obtain a current revision of EOP-01-LEP-01 and OP-41.
Current Revision of EOP-O1-LEP-01 and OP--41.
SAT/UNSAT*
Step 2 - Shift the Motor Driven Fire Pump to the alternate supply as follows:
a. Disengage position pin from position plate.
Position pin is disengaged.
- CRITICAL STEP ** SAT/UNSAT*
b. Place Transfer switch located on front of 2-FP-P2-XFER-SW cabinet to position
A.
Transferswitch located on front of 2-FP-P2-XFER-SW cabinet placed to
position A.
- CRITICAL STEP ** SAT/UNSAT*
\ 3132c Page 4 of 9 REV. 0
Fire Water Injection Using The Motor Driven Fire Pump.
c. Ensure position pin engages position plate.
Position pin engaged.
SAT/UNSAT*
PROMPT: Ifexaminee contacts control room to start the Motor Driven Fire Pump. Inform
examinee, the pump will not start from the control room and must be locally started.
Step 3 - Momentarily depress the local start push button for the Motor Driven Fire Pump.
Motor Driven Fire Pump is running.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: PIV-20 is located north of the Unit 1 Reactor Building near MWT.
Step 4 - Unlock and open Fire Protection (Well Water) to Service Water Flush Supply Shutoff
Valve 2-FP-PIV20.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: E1i-F073 disconnect switch is on the 23' elevation of the cable spread area.
3B2c Page 5 of 9 REV. 0
Fire Water Injection Using The Motor Driven Fire Pump.
Step 5- Place the El l-F073 disconnect switch to On at Node LiG in the cable spread area.
E1l-F073 disconnect switch is in On at Node LIG in the cable spreadarea.
- CRITICAL STEP ** SAT/UNSAT*
SPROMPT: When examinee informs control room that the El1-F073 disconnect switch is on,
nform examinee as that El l-F073 and F075 are open.
Step 6 - Open RHR Service Water Header Flush Valve, SW-V140 (located 50' elevation
behind B & D RHRSW booster pumps)
SW-V140 is manually opened.
- CRITICAL STEP ** SAT/UNSAT*
Step 7 - Open Well Water Flush To Service Water Shutoff Valve, WW-V203 (located 50'
elevation behind B & D RHRSW booster pumps)
WW-V203 is manually opened.
- CRITICAL STEP ** SAT/UNSAT*
Step 8 - Inform CO local actions are complete to inject fire water to the reactor.
CO informed actions for fire water injection are complete.
STERMINATING CUE: This box will tell the evaluator when the JPM is complete based on
student performance. I
- Comments required for any step evaluated as UNSAT.
3132c Page 6 of 9 REV. 0
Fire Water Injection Using The Motor Driven Fire Pump.
RELATED TASKS:
200075B504, Perform Alternate Coolant Injection With Fire Water Per LEP-01
K/A REFERENCE AND IMPORTANCE RATING:
286000 A1.05 3.2/3.2
REFERENCES:
EOP-01-LEP-01
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
8 - Fire Protection
REASON FOR REVISION:
New JPM.
3B2c Page 7 of 9 REV. 0
Fire Water Injection Using The Motor Driven Fire Pump.
Time Required for Completion: 20 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate 4 Actual Unit: 1
Setting: Control Room Simulator ( Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A
Alternate Path: Yes No 4
EVALUATION
Trainee: SSN:
JPM: Pass Fail
Remedial Training Required: Yes No
Did Trainee Verify Procedure as Authorized Copy?: Yes No
(Each Student should verify one JPM per evaluation set.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
3B2c Page 8 of 9 REV. 0
TASK CONDITIONS:
1. Unit One is in accident conditions, and is executing EOP-01 -RVCP due to low reactor
water level. Reactor water level is below Top of Active Fuel. EOP-01-RVCP directs
aligning all available alternate coolant injection per EOP-01-LEP-01. Reactor pressure
is 10 psig.
2. Off-Site Power is unavailable to either unit. DG2 is tripped, and Bus E2 is de
energized, and cannot be energized by cross-tie. Buses El, E3, and E4 are energized
by their respective DGs. Buses E5 and E6 have been cross-tied.
3. The Diesel Driven Fire Pump is unavailable.
4. The Motor Driven Fire Pump is aligned to its normal power supply. The Motor Driven
Fire Pump cannot be started from the control room.
5. Fire protection tank level is normal. A radwaste operator is available to control and
monitor fire protection tank level.
6. RHR Loop B injection flow path is available.
INITIATING CUE:
You are directed by the Unit CO to transfer the Motor Driven Fire Pump to its alternate
power supply, start the Motor Driven Fire Pump locally, and perform the AO actions for
aligning Fire Protection Injection per EOP-01-LEP-01, Sectiut 6, and inform the CO when
your actions are complete.