ML030840286
| ML030840286 | |
| 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: ML030840286 (208) | |
See also: IR 05000325/2003301
Text
Draft Submittal
(Pink Paper)
BRUNSWICK EXAM
50-2003-301
50-325 & 50-324
FEBRUARY 10 - 14 & 19, 2003
(A 1. Administrative Questions/JPMs
&' 2. In-plant JPMs /
t' 3. Control Room JPMs (simulator JPMs) /
eb 4 . Administrative Topics Outline ES-301-1 -'
V'5. Control Room Systems and Facility Walk-Through V
Test Outline ES-301-2
Administrative Topics Outline
Administrative Subject/Description Method of evaluation
Topic
A.1 GEN JPM
2.1.33 Complete Jet Pump Operability per OPT-1 3.1
(3.4) Note: Data will indicate a failed Jet Pump. The RO
should understandthe TS implications (and safety
implications) of the failed pump.
A.1 GEN Questions:
2.1.33/2.1.25 1. Fuel Loading has just been completed. The Night
(2.6/2.8) Orders specify completing Control Rod Operability on
your shift. The Reactor Engineer needs to use the
fuel bridge over the Reactor Cavity the whole shift to
make a final core loading verification. Can these jobs
be performed simultaneously? If not, what would
prevent it?
2. Given a copy of the Generator Loading Curve
determine the maximum MVARs with the Gross
Generation at [xxx MW].
A.2 GEN JPM
2.2.14/2.2.11 Given an approved Temporary Change (TC) make
(2.5) the necessary changes to the applicable drawings.
A.3 GEN Questions:
2.3.10 1. You have just been notified by the Refuel Floor
(2.9) SRO that a spent fuel element has just dropped into
the Fuel Pool and he is evacuating the Reactor
Building. What actions must you take to protect
yourself from any ensuing radiation?
2. If these actions are taken within 10 minutes, what is
your stay time in the control room. Cite your
references.
A.4 GEN JPM
2.1.17 Given information from the SRO regarding
Emergency Classification and PAGs, complete all
required notification(s)
Administrative Topics Outline
Administrative Subject/Description Method of evaluation
Topic
A.1 GEN JPM
2.2.32/2.2.27 Using a prepared, partial view of the newly refueled
(3.5) core and Core Loading Plan, determine if the core
loading has been done correctly.
Note: One bundle will be oriented 180 degrees out of
normal.
A.1 GEN JPM
2.1.33/2.2.12 Complete Jet Pump Operability per OPT-13.1
(4.0) Note: Data will indicate a failed Jet Pump. The SRO
should understandthe TS implications (and safety
implications)of the failed pump.
A.2 GEN JPM
2.2.14/2.2.11 Given an approved Temporary Change (TC)
(3.0) complete SRO responsibilities for installation per
OOLP-22.
A.3 GEN JPM
2.3.6 Given data provided by the on-shift Chemistry
(3.1) Technician, issue a Liquid Radwaste Discharge per
OOP-06.4
A.4 GEN JPM
2.4.40 You are in Steam Cooling OEOP-01-STCP at Step
(4.0) 018. TSC has not yet been activated. Given the
following release data [Table of stack gas and Met
data] determine the Emergency Classification and
Protective Action Guidelines to be given to the State
of North Carolina.
B.1 Control Room Systems
System/JPM Title Type Safety
Code Function
(202001) Reactor Recirculation Pump Start [With a malfunction (D)(A)(S) I
(TBD)]
(204000) Reduce RPV water level using RWCU to Radwaste (N)(S) 2
(239001) Emergency equalization around MSIVs using Hard Card (D)(S) 3
(203000) Initiate Shutdown Cooling [Min flow valve fails open] (M)(A)(S) 4
(L)
(223001) Vent the Drywell per OP-10 wiStack Rad Monitor (D)(A)(S) 5
Increases >50%
(290003) Place Control Room HVAC in Filtered Recirculation Mode (N)(S) 9
(205005) Core Performance Parameter Check- manual APRM GAF (D)(A)(S) 7
Adjustment Required
Facility Walk-Through
System/JPM Title Type Safety
Code Function
(217000) Start RCIC from remote S/D Panel (D)(R) 2
(264000) Manually start an EDG locally-local manual start using (D) 6
prelube start control
(234000) Complete Refuel Interlocks Checks on Refuel Bridge (M)(R) 8
(Partial)
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
LESSON TITLE: Evaluate Jet Pump Performance Per PT-13.1.
4(zcý,j P
REVISION NO: 0
RECOMMENDED BY: DATE
Instructor/Developer
CONCURRENCEBY: DATE
Line Superintendent/Supervisor
APPROVED BY: DATE
Superintendent/Supervisor Training
Evaluate Jet Pump Performance Per PT-1 3.1.
Special Instructions
Transfer the following data onto a current revision of PT-i 3.1:
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 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-16 - 38%
JP-6 - 33%
JP-17 - 39%
JP-7 - 31%
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%
Page 2 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-13.1.
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
to be
Attachment 2, Test Information Work Sheet 1. Attachment 2, Work Sheet 2 is not
used.
INITIATING CUE:
acceptance
You are directed to evaluate the data for Jet Pump performance, determine if
criteria is met, and inform the Unit SCO of the results.
£1 cn**- "R'E 0
.. .D..,,n ,-nO REV. 0
3A1 -1 age u
- 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 obtained and verified, if applicable.
SATIU NSAT*
Step 2 - Confirm Recirc Pump A flow is within the band of the established curves.
Figure 4.1.
Determine Recirc Pump A flow is NOT within the band of 20P-02,
- CRITICAL STEP ** SATIUNSAT*
curves.
Step 3 - Confirm Recirc Pump B flow is within the band of the established
4.2.
Determine Recirc Pump A flow is within the band of 20P-02, Figure
SAT/U NSAT*
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 ** SATIUNSAT*
Page 4 of 9 REV. 0
Evaluate Jet Pump Performance Per PT-13.1.
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.
SATIU NSAT*
Step 6 - Calculate average jet pump % psid for each loop.
Determines Loop A average is 30% and Loop B average is 40%.
SATIUNSAT*
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 established curve 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 informed jet pump 10 fails to meet acceptance criteria.
SAT/UNSAT*
Page 5 of 9 REV. 0
WA-1
Evaluate Jet Pump Performance Per PT-1 3.1.
<NTtTefolwn is~pplia1
ltpý SRO eainetrY tjK
be
Step 9 - Determine that LCO 3.4.2 is not met, condition A applies, requiring the unit to
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*
- Comments required for any step evaluated as UNSAT.
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.
Page 7 of 9 REV. 0
WA-1
Evaluate Jet Pump Performance Per PT-13.1.
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 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:
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
K BPERFORMANCE MEASURE
IN-PLANT
LOT-OJT-JP-301 -A.1.2 RO
LOT-OJT-JP-301-A .1.2 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. When requested, provide the copy of procedure OAP-001.
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 work periods. All operators began their shift
schedule at the same time each day.
REV. 0
Page 2
LOT-OJT-JP-201 -COI
LOT-OJT-JP-201-C01 Page 2 REV. 0
Evaluate Overtime Eligibility.
DAY 1 2 3 4 5 6 7 8
(Today)
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
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 I and
Day 7.
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.
LOT-OJT-JP-201-C01 Page 3 REV. 0
Evaluate Overtime Eligibility.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of OAP-001.
Current Revision of OAP-001 obtained and verified via NRCS, if applicable.
SAT/U NSAT*
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.
Determined that 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.
- 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.
Determinedthat 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.
- CRITICAL STEP **SAT/UNSAT*
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 /> strait 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period between days 7 and 8 and
would require overtime authorization.
Determined that Operator#3 would exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> strait 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period between days 7 and 8 and
would require overtime authorization.
- CRITICAL STEP ** SAT/UNSAT*
LOT-OJT-JP-201-C01 Page 4 REV. 0
Evaluate Overtime Eligibility.
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 />.
SAT/UNSAT*
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 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
Determined that Operator#5 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
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.
- CRITICAL STEP ** SAT/UNSAT*
Examiner Prompt:
IF asked, provide copy of approved Attachment 1 for operator # 5.
Step 7 - Determine that 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 between
days 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 between
days 4 and 5.
- CRITICAL STEP ** SAT/UNSAT*
TERMINATING CUE: When the examinee has evaluated overtime restriction s, this JPM i
complete.
- Comments required for any step evaluated as UNSAT.
REV. 0
Page 5
LOT-OJT-JP-201 -001
LOT-OJT-JP-201-C01 Page 5 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, Rev 9
TOOLS AND EQUIPMENT:
None.
SAFETY FUNCTION (from NUREG 1123, Rev 2.):
A.1 - Conduct Of Operations
REASON FOR REVISION:
New JPM for NRC exam.
LOT-OJT-JP-201-C01 Page 6 REV. 0
Evaluate Overtime Eligibility.
Time Required for Completion: 10 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate 4 Actual Unit:
Setting: Control Room 4 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 using NRCS?: Yes __ No
(EACH STUDENT SHOULD VERIFY ONE JPM PER EVALUATION SET USING NRCS.)
Comments:
Comments reviewed with Student
Evaluator Signature: Date:
LOT-OJT-JP-201-C01 Page 7 REV. 0
APPLICANT HANDOUT
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 work periods. All operators began their shift
schedule at the same time each day.
DAY 1 2 3 4 5 6 7 8
(Today)
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
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.
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.
LOT-OJT-JP-201-C01 Page 8 REV. 0
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-AI-2
LESSON TITLE: Evaluate Partial View Of Core For Correct Core Loading.
J
KV
Ox
REVISION NO: 0
V'
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY: UAII
Superintendent/Supervisor Training DAIE
Superintendent/Supervisor Training
Evaluate Partial View Of Core For Correct Core Loading.
SPECIAL INSTRUCTIONS
Prepare a picture of a partial core (4 cells - 16 Bundles).
Ensure I bundle is rotated 1800.
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. 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 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.
3A1ls 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 incorreclyjIaddItiNO
critical the examinee ideintifies 'the locations are swa~pppd.
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 correct location.
- 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*
WA s 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 1800).
Identify that bundle LYJ549 (Step 19 of the Core Component Sequence Sheets)
is loaded in the incorrect orientation.
- CRITICAL STEP ** SAT/UNSAT*
NOTE: All other bundles are correctly, loaded; however whoever loaded these 16 b6ndlelds
will burl y lose 'his/her SROi ice'ns eg
Step 4 - Identifies all other bundles are correctly loaded.
Identifies all other bundles are correctly loaded.
SAT/U NSAT*
Step 5 - Inform Shift Superintendent of results of partial core verification.
Shift Superintendentinformed of results of partialcore verification.
SAT/U NSAT*
I TERMINATING CUE: When evaluation;of the partial core load has been competed; tnisJI-'M
I ~ ~~~is
complete. ___ _____ ____ _____ _____ ____
a
- Comments required for any step evaluated as UNSAT.
3A1 s 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.
3Als 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 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:
3Als Page 6 of 7 REV. 0
'C1ý
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.
K-,
9113 15North
12
10
n % J %
6
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
ADMIN
BNP-03-A1-2
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 Loadinq.
SPECIAL INSTRUCTIONS
Prepare a picture of a partial core (4 cells - 16 Bundles).
Ensure 1 bundle is rotated 1800.
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.
3A1ls Page 2 of 7 REV. 0
Evaluate Partial View Of Core For Correct Core Loadina.
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*
!NTE it is critical that the examinee idnftifies the two bundles indorrdctlv Idaddd. It is NOT
critical the examinee ienti~fie's-the locationsaesw d
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 L YJ568 (Step 5 of the Core Component Sequence Sheets) is
not loaded in the correct location.
- 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 L YJ468 (Step 10 of the Core Component Sequence Sheets)
is not loaded in the correct location.
- CRITICAL STEP ** SAT/UNSAT*
WA s Page 3 of 7 REV. 0
Evaluate Partial View Of Core For Correct Core LoadinQ.
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 1800).
Identify that bundle L YJ549 (Step 19 of the Core Component Sequence Sheets)
is loaded in the incorrectorientation.
- CRITICAL STEP ** SAT/UNSAT*
NOM All other brtlyloaded; however whoever loaded these 16 bundles will
.,sunl lose, hislher SRO license.ýý:
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*
-I
I
ITERMINATIN9 CUE: When evaluationof the partial core load has been competed, this JPM
is compnlete
l,,
- Comments required for any step evaluated as UNSAT.
3Als Page 4 of 7 REV. 0
Evaluate Partial View Of Core For Correct Core Loadini.
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.
3A1 s 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 V. Actual Unit: 2..t
Setting: Control Room - Simulator-. ( Not applicable to In-Plant JPMs)
Time Critical: Yes - No V Time Limit _N/A__
Alternate Path: Yes - No V
EMALUATION
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: -
Page 6 of 7 REV. 0
3Als
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.
1"', fL
- Ll II
WN
( (
Core Component Sequence Sheet FORM OENP-24.12-3 (8/02)
ISSUE NO.
PAGE OF
PREPARED BY: DATE:
UNIT .* REVIEWED BY: DATE:
NMC APPROVAL: DATE:
UNIT SRO APPROVAL: DATE:
MOVEMENT SRM COUNTS
STEP # COMPONENT FROM COORDINATE FASTENER TO COORDINATE FASTENER COMPLETE A B C D COMMENTS
LOCATION LOCATION INIT/DATE
+/-Lj LN'XST I SFP P-LD SE Core 15- SE
Is L:1L413 sF? Cs fq4 N' cort k-'6 -W
16 u'N-ag41 £.EtAŽ* F.J9 1 oe 9-% ,jCF ___
1-1 _____16 SrF EL4C3 Sw coft fl-( SWw __
1$ &DS .Core WU12 ANJASET 8:16 NIAA. _
\'ý L-isSM a SF? SbMAI SE cov ))-2 & E
%O- L'1rI1It§SF %6.A2 NW Cott 0i - ro_ ŽŽX
0 %N__ _
NOTE: An * in COMMENTS indicates that proper blade guide seating must be verified at the fuel support piece by camera before OR coupling or insertion.
NOTE: "Repeatbacks" per AP-050, Site Command, Control, and Communications Manual are required.
0ENP-24.12 Rev. 23 Page 31 of 56
( ( (
Core Component Sequence Sheet FORM OENP-24.12-3 (8/02)
ISSUE NO.
PAGE OF
PREPARED BY: DATE:
UNIT a. REVIEWED BY: DATE:
NMC APPROVAL:. DATE:
UNIT SRO APPROVAL: DATE:
MOVEMENT SRM COUNTS
STEP # COMPONENT FROM COORDINATE FASTENER TO COORDINATE FASTENER COMPLETE COMMENTS
LOCATION LOCATION INIT/DATE
I Y3119-ri sr-? jAS NeCo 912,
Cl "E. _____
2, LYTS.. !S F? ESFA SN Co. W-fo Sw
L1
D%G Cort Iill
L.-y 395 SF? ESD2I sE
N?1 SF P
ct
A 30
\- 12,
WUA
S LV'SSgI rSP EIS EI WVCae 5-10 NW
G L"I5Sazti r-9 ESD.* "s,S .r 13"-I 5k ,F
2 3BG Cor kIps- AA
A32, Jrt __A
_s_
L~zsj
L--1oj -sfr- G,&E S s__1ESOr s-i2, SE
0 ILY-TH (.9 SEP %(iAq NVJ -Ate 13-1O Nw
I 14LNTH3 SF? I %AS tiGME ICrel 132S r-3 G I_______ __
Ix. Ly "o3 SF? 9-SE3 SW Cot, I ,S-6 SW I ___,_
13 'S A ISf?9
N%1oe~i~ A34M I 1fA _ _ _ _ _ _
NOTE: An * in COMMENTS indicates that proper blade guide seating must be verified at the fuel support piece by camera before CR coupling or insertion.
NOTE: "Repeatbacks" per AP-050, Site Command, Control, and Communications Manual are required.
OENP-24.12 I Rev. 23 Page 31 of 56
FIGURE 1
Page 1 of 1
Reactor Vessel Core Map
1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51
18-51 22-51 26-51 30-51 34-51
-*- North
14-47 18-47 22-47 26847 30-47 34-47 38-47 42-47
10-47
06-43 10-43 114-43 1 8-43 j22-43 0 4 32-3
-43 38-43 142-431 46-43.
10-39 14-39 18-39 22-39 26-39 30-39 34-39 38-39 42-39 46-39
06-39
02-35 06-35 10-35 14-3,9 18-35 22-35 26-35 30-35 34-351T38-35 142-35 46-35 50-35
02-31 06-31 10.31 14-31 18-31 22-31 26-31 30-31 34-31 j38-31 42-31 46-3I 50-31
02-27 06-27 10-27 14-27 18-271 22-27 26-27 30-27 34-271 38-27 42-27 46-27 50-27
02-23 06 23 10-23 14-23 18-23 22-23 26-23 30233- 2I823 42-23 40-23 50-23
02-19 06.19 10-19 14-IS 18-19 22-19 26-19 30-19 34-19 38-19 42-19 46-19 50-19
14415 18-15 22-15 26-15 30-15 34-15 a1542-15 46-15
06-IS 10-15
G6-11 10-I1 14-1l 18-lI 22-12-11 30-11 134-111 38-11 42If4-l
10-07114-07 18-07 22-07 26-07 30-07 34-07 38-07 42-07
18-03 22-03 26-03 30-03 34-03
N IRMs IRM A - 12-41 IRM E - 28-25 SRM A- 12-33
IRM 8 - 36-41 IRM F - 20-25 SRM B - 28-41
IRM C - 20-33 IRM G - 36-09 SRM C - 36-25
A SRMs
IRM 0 - 28-33 IRM H - 12-09 SRM D - 20-17
LPRM 04-21 LPRM 12-37 LPRM 20-29 LPRM 28-21 LPRM 36-13 LPRM 44-13
LPPM 04-29 LPRM 12-45 LPRM 20-37 LPRM 28-29 LPRM 36-21 LPRM 44-21
LPRM 20-45 LPRM 28-37 LPRM 36-29 LPRM 44-29
LPRM 20-13 LPRM 28-05 LPRM 28-45 LPRM 36-37 LPRM 44-37
LPRM 12-13
LPRM 20-21 LPRM 28-13 LPRM 36-05 LPRM 36-45 LPRM 44-45
LPRM 12-21
LPRM 12-29
OENP-24.12 Rev. 23 Page 20 of 56
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: L)AI
Training
Superintendent/Supervisor Training DATE
Superintendent/Supervisor
Evaluate Proposed Temporary Change.
Special Instructions
Obtain copies of prints D-02549, Sheet IB, 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 1NC 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.
Denote
On LL-09244, Sheet 15, draw jumper from terminals 2-H02/CC17 to 2-H02/BB14.
jumper installed per TC EC 03-001.
Mark up EGR-NGGC-005, Form 2 to reflect temporary changes.
Page 2 of 9 REV. 0
03-A2
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-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.
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/AA1 1 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
H02/AA 11 on LL-09243, Sheet 15.
- CRITICAL STEP ** SAT/UNSAT*
Step 3 - Determine jumper installed from terminals 2-H02/CC1 7 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.
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*
TERMINATING CUE: This box will tell the evaluator when the JPM iscomplete Obased on : I
student perfrmane)>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: 15 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 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:
03-A2 Page 8 of 9 REV. 0
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-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 Chanqe.
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 -NO05 connections 1 NC 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/AA11. Denote
jumper installed per TC EC 03-001.
On LL-09244, Sheet 15, draw jumper from terminals 2-H02/CC17 to 2-H02/B814. 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 Prooosed Temoorarv Chanae.
SAFETY CONSIDERATIONS:
None.
EVALUATOR NOTES: (Do not read to trainee)
1. The applicable procedure section WILL NOT 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. 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 t 'r change will also
defeat low level indicating lights located on local panels 2- 41-eO1 and 2-G41-P002.
The low level trip function for the Fuel Pool Cooling Pumps 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 Pronosed Temporarv Chanqe.
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/U NSAT*
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 terminals2-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.
Determines jumper should not be installed from terminals2-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.
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*
- Comments required for any step evaluated as UNSAT.
Page 6 of 9 REV. 0
- .* 03-A2
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
C C (
FORM 2
Sheet 1 of 1
Temporary Change Log
EC#T'C 03-O00 Rev# 0 Title:Ot.So .It I-G4l-LSL-NO0SoResponsibleEngineer(Ext.): výA.zow SOA (z.2.2&0)
NOTE: Accepting change indicates that affected Priority 0 drawings have been annotated and procedures have been revised.
Change Accepted by: / Approved Plant Condition
(fln~r~tinng\ Print n~rmp Sianntuire Date
TAGGING INSTALLATION RESTORATION
TAG # DESCRIPTION POSITION/CONDITION FOR PERFORMED & VERIFIED RESTORED RESTORED/TAG VERIFIED
TEMPORARY CHANGE TAG INSTALLED () POSITION/ REMOVED ()
CONDITION
BY DATE BY DATE BY DATE BY DATE
"2. a.-GHI-N3L C\oseA
2,- G341 - LS L-H -
4 TtC1% n&1 t4 C.ci11 +0
Priority 0 drawings affected: 0-0.S9' 3~ F Si24-~ Drawing annotated by/date: Drawing annotations removed by/date:
LL-OSZM~i\-S, LL-O92A4j-IS
Procedures Affected: Procedures revised by/date: Procedures revised by/date:
FORM EGR-NGGC-0005-2-16
(*) These columns are required only for those systems requiring independent verification or functional testing as required by site procedures,
('*) Transmit original Temporary Change log to Document Services upon Temporary Change removal (restoration) acceptance for storage in the EC Master File.
Temporary Change Removal Accepted by(**): /
(Operations) Print name Signature Date
EGR-NGGC-0005 I Rev. 18 Page 130 of 133I
C C C
D-02549 SHT IB, COORDINATE D3
( ( (
F- - -- -- -- -- - - - - - - - - - - - - - - - -
LSL
LEADS LIFTED PER
EC TC 03-001 U 2(,. G45LOCAL
G41 -N005
2-FP-05924, SHT 2, COORDINATE C13
( C C
r -~1
LEADS LIFTED PER
I (
EC TC 03-001
LSL
SURGE TANK LOW LEVEL
LOCAL
G41-N005
2-FP-05924, SHT 2, COORDINATE K3
Evaluate Prooosed Temoorarv Chanae.
Time Required for Completion: 7§ Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate s/ Actual Unit: 2_
Setting: Control Room Simulator. (Not applicable to In-Plant JPMs)
Time Critical: Yes No V 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
( ( ( 1
_1 ISlA*I
02-CC
25
116
JUMPER PER LS 2-G41 -N006
EC TC 03-001 "*
2H02-AA1 1
LL-09243 SHT 15
( ( (
2
SIB
[FP-05924-1]
2-H02
CC1l,
25
/
JUMPER PER /ts
EC TC 03-001 -- G41-N006
[FP-05924-1]
2-H02
BB23
2-H02
BB24
LL-09244 SHT 15
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.
<2
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 0OP-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.
- r
3. A Pre-Release""Permit has been prepared by' E&RC in accordance with E&RC-2009.
CUE:
INITIATING
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.
4/
PERFORMANCE CHECKLIST
V
NOTE: Sequence is assumed unless denoted in the Comments.
I The examiner should have a copv of OOP-06.4, Section 5.70to provide to the
I -,examinee if re*uested, or allow examinee access to the entire procedure.
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.
Determinedthat requiredRecirculation time for the U/1 SWRT at a tank level of
79% of 316 minutes is correct as specified on the Radioactive Liquid Release
Permit.
SAT/U NSAT*
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 requirements for Recirculationtime and/or sample time per COP
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.
SAT/UNSAT*
- * :ll
I1: I CUE: When the Radioactive iquid Release Permit has been ev'aluated as
- unsatisfactor this JPM is*complete. j
- 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 Liauid Discharae Release Permit.
K-?
Time Required for Completion: 15 Minutes (approximate).
APPLICABLE METHOD OF TESTING
Performance: Simulate VC Actual - Unit:
Setting: Control Room - Simulator-_ ( Not applicable to In-Plant JPMs)
Time Critical: Yes - No V Time Limit N/A
Alternate Path: Yes - No
EVALUATIOlN
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
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: ($' E ..
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.
ATTACHMENT 4
Page 1 of 6
BSEP Radioactive Liquid Release Permit
Release# 03-000l
D ate - o ay
BSEP RADIOACTIVE LIQUID RELEASE PERMIT
PART I. TANK DATA
A. Tank to be released U It SW -RT
B. Tank to be released will be recirculated and sampled as in accordance with
section S',-] of OOP-06.4.
6. Level "-7 1 % Volume A*2 (o37". gallons.
1. *Batch Release Tank Volumes
NOTE: Attachment 3 of OE&RC-2009, Radioactive Effluent Releases and
Reports, lists abnormal release volumes for miscellaneous tanks.
WSTs = 208.4 gallons/% level
FDSTs = 209.4 gallons/% level
DDTs = 10.9 gallons/% level
U/1 SWRT = 362.5 gallons/percent
D. Required Recirculation Time 4 min / % Level X -1 cl % Level =
3a1 _ Min
E. Start Recirculation Date/Time Tocka 00 4cj
Required recirc time completed Date/Time "rTooy' O-SLA
Sample Taken Date/Time "TS)-Ay.L OS-S
(After required recirc time)
F. Source of water U1 o,,ck U., Cirt *.JcAer ?%+5
G. Treatment prior to release k". n
H. *Has the tank to be released been subjected to PH adjustments due to NAOH
or H2S04? Yes No X
- Reference procedure E&RC-2009.
OOP-06.4 I Rev. 35 Page 84 of 1011
ATTACHMENT 4
Page 2 of 6
BSEP Radioactive Liquid Release Permit
1. Tank to be released will be discharged in accordance with Section ,. of
OOP-06.4.
J. Part I completed Date/Time "T'oJ,,&
Radv ste Operator (signature)
PART II. RADIATION MONITOR STATUS
A. Monitor is being used for discharge (General Electric D1 2-RM-K604)
Yes X No
(If monitor is NOT being used, list special instructions in Part Iil. See
ODCMS 7.3.1 for additional sampling requirements.)
B. Monitor Hi-Hi setpoint is at \.oo
- E-0cps.
_
(If monitor is NOT being used, set monitor Hi-Hi setpoint to maximum to prevent
spurious trip during release.)
C. Monitor Hi-Hi setpoint set between background and maximum monitor setpoint
(E&RC-2009). Yes ffi No
D. Monitor indication prior to release (chart) 2 00 cps.
(Circle one used) Unit 1/E
E. CONFIRM Radwaste effluent isolation valves are closed.
1-D12-V27A Position .ose cL 2-D12-V27B Position C- %o-s e 4,
Unit 1 Unit 2
OOP-06.4 I Rev. 35 Page 85 of 101I
ATTACHMENT 4
Page 3 of 6
BSEP Radioactive Liquid Release Permit
Pad I1l. APPROVAL FOR USE
A. Both unit Reactor Operators have been informed of release and are aware of
Circulating Water/Service Water Pump requirements.
Unit I RO
Signat&r
Unit 2 RO
Signatlue
B. 1. Liquid Radwaste effluent flow measurement device operable (if inoperable,
ODCMS 7.3.1 Required Compensatory Measure C1, requires the flow rate
be estimated at least once/4 hours during actual releases.)
Yes X/_ No
2. Liquid Radwaste radioactivity effluent monitor operable (if inoperable,
reference ODCMS 7.3.1)
Yes __ No
C. Special instructions for release: N)0 A9-
D. Approval to release:
Unit SCO Date/Time
Key(s) _ Received by
Radwaste Operator (signature)
IOOP-06.4 I Rev. 35 Page 86 of 101
ATTACHMENT 4
Page 4 of 6
BSEP Radioactive Liquid Release Permit
Part IV. RELEASE DATE
A. Maximum permissible release rate gpm
B. Special instructions in Part III understood
Radwaste Operator (signature)
C. Release times:
Start (Date/Time) Stop (Date/Time) Time Interval
minutes
minutes
minutes
Total release time: minutes
NOTE: Post-Trip and DDT Flushes go to the Floor Drains or the Oily Drain
Collector Tank. Flush water flows through the radiation monitor and flow
totalizer, while the 1-D12-V27A and 2-D12-V27B are closed. If a Post-Trip or
DDT flush is performed, then the number of gallons of flush water should be
logged below as this water is not released. If a post trip or DDT flush is not
performed, N/A this reading.
D. Flow rate instrument verification in accordance with ODCMS TR 7.3.1.2
Flow Totalizer
2-G16-FIQ-3497
(Discharge via
2-G16-F187)
Release Zero Set
Flush to ODCT or Floor Drains gallons.
Release Final Reading
OOP-06.4 Rev. 35 Page 87 of 1011
ATTACHMENT 4
Page 5 of 6
BSEP Radioactive Liquid Release Permit
E. Flow rate instrument verification (in accordance with TR 7.3.1.2).
Flow rates (recorder) 2-G16-FR-R039
Start GPM Stop GPM
NOTE: Reference
operable. of Part F7.3.1
CompletionODCMS is NOTRequired Compensatory
required Measure C1.
if the 2-G 16-FIT-NO57 is
F. Flow estimate using tank level indicator.
Formula: (Start % - Stop % = Difference % X Gallons/% =
Gallons from tank decrease total release time = GPM)
Start % - Stop % = Difference %
Difference %X *Gallons/% =
(From line above) (Gal. from tank decrease)
Gallons from tank decrease _-- Total release time = GPM
(From line above) (In minutes)
G. Monitor Flush:
Flow Totalizer
(Discharge via
2-G16-F187)
Flush Start
Flush Total
Difference
- Gallons/% obtained from E&RC-2009.
IOOP-06.4 Rev. 35 Page 88 of 101l
ATTACHMENT 4
Page 6 of 6
BSEP Radioactive Liquid Release Permit
Post-flush readings (chart) CPS Unit I / Unit 2
(Circle one used)
Comments:
H. Release completed Date Time
Radwaste Operator (signature)
Part V. Review
A. Key(s) returned to Main Control Room
Initials
B. Radiation monitor channel check in accordance with ODCMS 7.3.1, and
TR 7.3.1.1.
NOTE: Use same monitor as used in Part II. D.
Highest reading during release (chart) CPS
Average reading during release (chart) CPS
C. Monitor Hi and Hi-Hi setpoints set above background reading.
Initials
Unit SCO (signature) Date
OOP-06.4 Rev. 35 Page 89 of 101
c
Continuous
ATTACHMENT 2
Page 1 of 1
Routine Release Sample Data Sheet
Circle one: FDSTA FDSTB WSTA WSTB
DDT A DDT BERT
I. TO BE COMPLETED BY E&C
Liquid radwaste monitor in service: Yes No*
SDCP Release in Progress Yes**- No X*_
Sample location: I-Svfl.-JV1Date: ToAc&'s Time: 0S53
Sample by: 0 1A,
drý-O-Psý E&C or OPS*
Release Permit Number (03-0001 -pH 9. 0
O3OOO1-3001 Detector '- RW Bkg 2- 0 0
File #
Unit 1 Unit_2 TotalI# Pumps
- Circ Pumps #Circ Pumps Ciro (o
- Serv Pumps #Serv Pumps Serv H
Release Rate .,
Calculation: E& ýTechnician E&C Technician*
II. REFER TO PART III OF THE ATTACHED BSEP RADIOACTIVE LIQUID
RELEASE PERMIT FOR SPECIAL INSTRUCTIONS.
Reviewed Prior to Release
Shift Superintendent / Date
Ill. POSTRELEASE REVIEW
Reviewed by:
E&C Technician Date
- Two independent samples, and verification thereof, are required when radwaste
effluent monitor is declared inoperative and two technically qualified E&C personnel are
required to verify and sign the release rate calculations.
- If SDCP Release is in Progress, subtract two Service Pumps from total service pumps
used in the release.
OE&RC-2009 Rev. 20 Page 39 of 50
CAROLINA POWER AND LIGHT COMPANY PAGE I
BRUNSWICK STEAM ELECTRIC PLANT
LIQUID RADIOACTIVE WASTE RELEASE PERMIT NUMBER: 03-0001
PRE-RELEASE PERMIT DATE: TODAY 08:00:00
PART I: PRE-RELEASE DATA:
RELEASE POINT: SALT WATER TANK U I WASTE SAMPLE PERMIT: 03-0001
PERMIT REQUESTED BY: KAB
PERMIT TIME: TODAY/0800 SAMPLE PH 8.0
RAD MONITOR NUMBER: D12-RM-K604 RAD MONITOR BACKGRD: 3.000E+02 CPS
- CIRC WATER PUMPS: 6.0 RAD MONITOR EFF: 1.251E+07
- SERVICE WATER PUMPS: 4.0 DILUTION FACTOR: 1.547E-01
PART II: PRE-RELEASE CALCULATIONS
TOTAL ACTIVITY: 1.677E-06 CI TOTAL GAMMA ACTIVITY: 1,547E-8 UCIIML
TOTAL CONC/EC: 5.000E-02 RELEASE VOLUME: 2.864E+04 GAL
MAX MONITOR SETPOINT: 1.348E+04 CPS MAX RELEASE RATE: 2.27 IE+06 GPM
PART HI: SPECIAL INSTRUCTIONS
PRE-RELEASE COMPLIANCE CHECK PASSES
PRE-RELEASE ADMIN LIMIT PASSES
CAROLINA POWER AND LIGHT COMPANY PAGE 2
BRUNSWICK STEAM ELECTRIC PLANT
LIQUID RADIOACTIVE WASTE RELEASE PERMIT NUMBER: 03-0001
PRE-RELEASE PERMIT DATE: TODAY 08:00:00
PRE-DILUTION DATA
NUCLIDES (UCI/ML) EC (UCIIML)
1-131 1.547E-08 1.000E-06
CAROLINA POWER AND LIGHT COMPANY PAGE 3
BRUNSWICK STEAM ELECTRIC PLANT
LIQUID RADIOACTIVE WASTE RELEASE PERMIT NUMBER: 03-0001
PRE-RELEASE PERMIT DATE: TODAY 08:00:00
CUMULATIVE DOSE REPORT FROM THE PRE-RELEASE CALCULATIONS
CRITICAL AGE: ADULT
CONTROLLING LOCATION FOR LIQUID RELEASES: SW SECTOR AT 0.1 MILES
DOSE CALCULATIONS (MREM)
BONE LIVER TOT-BODY THYROID KIDNEY LUNG GI-LLI
FROM
THIS
RELEASE 2.29E-09 3-28E-09 1.88E-09 1.07E-06 5.62E-09 0.OOE+00 8.65E-10
WEEK
PRIOR TO
RELEASE 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
I----------------------------------------------------------------------------------------------------
WEEK
AFTER
RELEASE 2.29E-09 3.28E-09 1.88E-09 1.07E-06 5.62E-09 0.OQE+00 8.65E-10
ADMIN
WEEKLY
LIMIT 3.85E-01 3.85E-01 1.15E-01 3.85E-01 3.85E-01 3.85E-01 3.85E-01
----------------------------------------------------------
PERCENT
WEEKLY
LIMIT 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%
MONTH
PRIOR TO
RELEASE 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00
MONTH
AFTER
RELEASE 2.29E-09 3.28E-09 1.88E-09 1.07E-06 5.62E-09 0.OOE+00 8.65E-10
ADMIN
MONTHLY
LIMIT 1.67E+00 1.67E+00 5.00E-01 1.67E+00 1.67E+00 1.67E+00 1.67E+00
PERCENT
MONTHLY
LIMIT 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%
------------------------------------------------------
CAROLINA POWER AND LIGHT COMPANY PAGE 4
BRUNSWICK STEAM ELECTRIC PLANT
LIQUID RADIOACTIVE WASTE RELEASE PERMIT NUMBER: 03-0001
PRE-RELEASE PERMIT DATE: TODAY 08:00:00
CUMULATIVE DOSE REPORT FROM THE PRE-RELEASE CALCULATIONS
CRITICAL AGE: ADULT
CONTROLLING LOCATION FOR LIQUID RELEASES: SW SECTOR AT 0.1 MILES
DOSE CALCULATIONS (MREM)
BONE LIVER TOT-BODY THYROID KIDNEY LUNG GI-LLI
QUARTER
PRIOR TO
RELEASE 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00
QUARTER
AFTER
RELEASE 2.29E-09 3.28E-09 1.88E-09 1.07E-06 5.62E-09 0.00E+00 8.65E-10
ODCMS
QUARTER
LIMIT 1.00E+01 1.00E+01 3.00E+00 1.00E+01 1.00E+01 1.00E+01 1.00E+01
PERCENT
QUARTER
LIMIT 0.000% 0.000% 0.000% 0.000% 0.000% 0.000% 0.000%
YEAR
PRIOR TO
RELEASE 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+OO
YEAR
AFTER
RELEASE 2.29E-09 3.28E-09 1.88E-09 1.07E-06 5.62E-09 0.00E+00 8.65E-10
ODCMS
ANNUAL
LIMIT 2.OOE+01 2.00E+01 6.OOE+00 2.OOE01 2.OOE+01 2.OOE+01 2.00E+01
PERCENT
ANNUAL
LIMIT 0.000% 0.000% 0.000% 0.000% 0000% 0.000% 0.000%
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.
1)
\leJ
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
<-V
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. \
TACOt frnK~rk1r~nkIC.
Read the following to trainee. y
RLng
V/
I I'&*
".J.J1 l II
flIJflI 'J*. A-. !
1. A General Emergency has been declared due to a steam line break ex4ets-in the
Turbine Building on Unit/. 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 ?"reactor initially failed to scram, but was successfully scrammed 15 minutes
ago. 4-
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 Protection Inputs
CHARACTERISTIC TIME
Main Stack Release Rate (pCi/Sec) 2.4e6
Flow Rate (CFM) 40000
Turbine Building #1 Release Rate (pCi/Sec) 5.2E6
- 1 Flow Rate (CFM) 15000
- 2 Release Rate (pCi/See) 5.2E6
- 2 Flow Rate (CFM) 15000
Reactor Building Release Rate (CPM) 3.5E2
Flow Rate (CFM) 0
Torus Vent Release Rate (liCUSec) 0
1
Core Uncovered Time (1) lost (2) Returned
Effective Filtration Yes / No Yes
Release Height Ground Yes
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.
LA)'
Step 1 - Obtain a current revision of PEP-03.4.7.
Current Revision ofPEP-03.4.7 obtained.
SAT/UNSAT*
Step 2 - Access the Dose Projection program.
Dose ProjectionProgram accessed.
SAT/UNSAT*
Step 3 - Enter data from PEP-03.4.7 attachment into the dose projection program.
Data correctly entered into the dose projectionprogram.
4svfelAf 4immttS5 SAT/UNSAT*
Step 4 - Determine highest off-site dose is approximately 6.38E+01 TEDE and 1.99E+2 CDE
both at the site boundary.
,,Deteraud that projected dose at site boundary is364mrem TEDE and
C 29+02 mrem CDE
- CRITICAL STEP ** SATIUNSAT*
3A4s Page 5 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
NOT'E: The EAL for the release (Site Area Emergency) is on bottom right of last display
(results display, of Dose 'prograim and on last age of printout. The examinee' ma
use this to determlne the EAL f*r the release, for the'
or may determine the EAL(EAL
rees per.OPEP-02.1,:Attachment1, Secion.
04.01MOi
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*
.01 .... .. .............
...
NOTE.!i;ýý: :3The EAL for the release isia Site Area Emergency. However, since a General,
.......
.. ..
c has been decl*e*n.d, Protebtive Action Recommendat1ons (PAR) are6....
quired e PEP02628 Sncerelease does not exceed E EAL, the Guidance
in Attahrent 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,H,K.
Determines with current met data that OPEP-02.6.28requires a PAR to evacuate
zones A,BC,D,E and shelterzones FG,HK.
- CRITICAL STEP ** SAT/UNSAT*
Step 7 - Notifies Shift Superintendent of results.
Shift Superintendent notified of off-site dose projection results.
SAT/UNSAT*
3A4s Page 6 REV. 0
Determine Off-Site Release Per PEP-03.4.7 And Recommend Protective Actions.
TCUE: When the offsite dose projection has been performedand lines6 2&113/
of.the Emr gency.NotificI.atio.n fdrrn are filled Iin this.JPM s, c...o mplete. 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 4 j29"
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?: 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 exists in the
Turbine Building on Unit 2. 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 2 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.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
IN-PLANT
LESSON TITLE: Start RCIC From The Remote Shutdown Panel.
REVISION NO: 0
RECOMMENDED BY
Instructor/Developer DATE
CONCURRENCE BY'
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendent/Supervisor Training DATE
Start RCIC From The Remote Shutdown Panel.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain a current revision of AOP-32.0.
Current Revision of AOP-32.0 obtained.
SAT/UNSAT*
Controller, E51-FIC-3325, is out.
Step 2 - Station 1, Verify yellow ALM light on RCIC Flow verified out
Yellow ALM light on RCIC Flow Controller, E51-FIC-3325,
SAT/UNSAT*
i a~umd t b. t~ tbrr~l tanby foti8
algnment91111 JFAt$ýjstfit4+ P
NOT:~
Page 3 of 12 REV. 0
3B2a
Start RCIC From The Remote Shutdown Panel.
Step 3 - Station 2, verify open or open RCIC CST Suction Valve E51-FOIO, at MCC 1(2)XBD,
Compt B38, Row C2.
E51-FOIO is verified open.
SAT/UNSAT*
Step 4 - Station 2, verify closed or close RCIC Supp Pool Suction Valve E51-F031, at MCC
I(2)XBD, Compt B45, Row GI.
E51-F031 is verified closed.
SAT/U NSAT*
Step 5 - Station 2, verify closed or close RCIC Supp Pool Suction Valve E51-F029, at MCC
1(2)XBD, Compt B46, Row G2.
E51-F029 is verified closed.
SAT/UNSAT*
3132a Page 4 of 12 REV. 0
Start ROIC From The Remote Shutdown Panel.
Fm I
/u1' 01N
r
i~~nea~epabsb~~~t't .pen ihitrefgt n1# 9 fl i& U
I
Step 6 - Station 2, verify open or open RCIC Cooling Water Valve E51-F046, at MCC
1(2)XBD, Compt B39, Row D1.
E51-F046 is opened at the MCC.
- CRITICAL STEP ** SAT/UNSAT*
Step 7 - Station 2, verify open or open RCIC Pump Discharge Valve E51-F012, at MCC
I(2)XBD, Compt B40, Row D2.
E51-F046 is verified open.
SAT/UNSAT*
Page 5 of 12 REV. 0
3132a
Start RCIC From The Remote Shutdown Panel.
r,. I
t E5týH e. RMr
PRQMPT:* W17h;6fl
..
Nkeefnfr
.. .. . ... .
exacesinealtsiafc t F01n r8lighte is#d ofgrde lidI~th*&?4
Whn ekrnnepac. ioi:viM
I
Step 8 - Station 2, verify open or open RCIC Injection Valve E51-F013, at MCC 1(2)XBD,
Compt B41, Row El.
E51-FO13 is opened at the MCC.
- CRITICAL STEP ** SAT/UNSAT*
~~~~~~~I1i" RCIbroerccneeracmprptp
Step 9 - Station 2, Start the RCIC barometric condenser vacuum pump, at MCC 1(2)XBD,
Compt B35, Row BI.
RCIC barometric condenser vacuum pump is running.
- CRITICAL STEP ** SAT/UNSAT*
3132a Page 6 of 12 REV. 0
Start RCIC From The Remote Shutdown Panel.
Step 10 -Station 2, verify open or open RCIC Turbine Trip and Throttle Valve E51-V8, at MCC
I(2)XBD, Compt B37, Row C1.
E51-V8 is verified open.
SAT/UNSAT*
Step 11 -Station 2, verify open or open RCIC Steam Supply Outboard Isolation Valve E51-
F008, at MCC I(2)XBD, Compt B43, Row Fl.
E51-F008 is verified open.
SAT/UNSAT*
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
3B2a Page 7 of 12 REV. 0
Start RCIC From The Remote Shutdown Panel.
Step 13 -Station 2, verify open or open RCIC Turbine Steam Supply Valve E51-F045, at MCC
I(2)XBD, Compt B44, Row F2.
E51-F045 is opened at the MCC.
- CRITICAL STEP ** SATIUNSAT*
KP ra 'R -- lo~ ~sindictedoh E5{FJC-ý3325,iindic~d
u6~~d;If inicateRCIO
!ROMPT atei9"'Ogt
0..1 P
Step 14 -Station 1, Verify RCIC flow corresponds to ROIC Flow Controller, E51-FIC-3325,
setting.
RCIC flow corresponds to RCIC Flow Controller,E51-FIC-3325,setting.
SAT/UNSAT
3132a Page 8 of 12 REV. 0
Start RCIC From The Remote Shutdown Panel.
- PROMPT When askd
Zt<Ua &n* on~ide ranieinforrn exami'n~ee athtem~te
levei instrumenf reactor level indicates
- shdtdown panq! +(0u- O!thes;*B1§tak
186!ipcdsand
S I> K R 04.............. t K2 ....... ,i
Step 15 -Station 1, Adjust RCIC Flow Controller, E51 -FIC-3325, to maintain reactor vessel
level between 170" and 200".
RCIC setpoint tape maintainedat 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.
SATIU NSAT*
iiCTERMINATING~
... . . CUr*nR!@1a
. .. ý ....@
~ t.~*p!*
. . ....... *l
- Comments required for any step evaluated as UNSAT.
3B2a Page 9 of 12 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 AAI.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 10 of 12 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:
3132a Page 11 of 12 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) requred 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 Generator Fis
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 obtained and verified, if applicable.
SAT/UNSAT*
Step 2 - Confirm the diesel Generator auxiliary systems are operable by observing the
following conditions locally.
PROMPT: Ifretjtested, ipdicate each re~dinlg/indication fqr tF~e following :St6ess:! "as-seerg' f
a. Starting air pressure is between 240-260 psig as indicated by DG-PI
6514-1 (2, 3, 4)
Startingairpressure is observed to be between 240-260 psig as
indicated by DG-PI-6514-1 (2, 3, 4).
SAT/U NSAT*
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 pressuresare observed to be between
325-350 psig as indicatedby DG-PI-1690 and 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 airpressure is observed to be between 90-125 psig as
indicatedby DG-PI-1686 (1680, 1660, 1252).
SAT/UNSAT*
d. Jacket Water Expansion Tank level is between A and % full in sight glass.
Jacket Water Expansion Tank level is observed to be between $ and
3/4 full in sight glass.
SAT/UNSAT*
e. Jacket Water Heater Pump is in operation.
Jacket Water Heater Pump observed to be in operation.
SAT/UNSAT*
f. Jacket Water Heater temperature out is between 1500 to 1600 as
indicated by MUD-TI-2117 (4144, 2171, 2198).
Jacket Water Heatertemperatureout is observed to be between 1500
to 160 0 as indicatedby MUD-TI-2117 (4144, 2171, 2198).
SAT/UNSAT*
3132b 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/UNSAT*
h. Lube oil bypass filter temperature is between 1300 to 1600 as indicated by
MUD-TI-2117 (4144, 2171, 2198).
Lube oil bypass filter temperature is observed to be between 1300 to
1600as indicated by MUD-TI-2117 (4144, 2171, 2198).
SAT/U NSAT*
Governor oil level is at or above the high level mark.
Governor oil level is observed to be at or above the high level mark.
SAT/UNSAT*
iNOT: ... h c* .epae nLCL IULmd fr oto om pnlX- ny
3132b 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.
SAT/U NSAT*
PROM
NOTE:Whenthe
~ d~pre~sing
PROMPTl"
restrt Nis derse! hi6axlais~~
examWhe
4
stat sor&bd)ittedlydb
Y&/U,
jaclbt aterpurp~$&hi~6~
blwr auosttAAl1nin3(
th Prestart are lhted in OP-A9,~ecItio .. ;Ses4atruht
i~~~rse~~trPB-'ifrquested, ater'0--dd
eod.,At~~~~
n
20secondidct
j
I
fndcaiond 1Tddh~ "tg b ~ indica ion; o dylbt6p
in di MO rMiki $KII7A " .0
Step 4 Der,"essa
- PRETAR puhbttnlctedon loal Engt66;f6ýineCotrol Panel" o
PRE TARTipused~hatbutobsq depressed., ings
CRITICAL STEPl
laSAINST
- o
NOTEi;*, i;****;** **ii*ii!*vnl a*!!*
The following i( ii i*i~l
alarm **!~lmsl!!oae
located oh~iconfrol
- iin i!*** room*ii!ia~l;!
o~~i iro! !! ¸*!*U2i!!
- i * * *ii!*
Aea.RMT -p,rgo xi ,mat9l'y 10 ýs~eco nds, f'rom n thetmtheniesasnfrexpne
s~~~~~t~~
tthe DG.nin.t i .....ha bee receive in.. th cotol.om.
PRO~~~~~U~ %ýl1 [eustdidida~t>erSvice' Wter rsuqo WP-5d~~
l riaell pprox 04W at-l01445 risig A
3B2b Page 6 of 10 REV. 0
Local Manual Start Of A DG Using Prelube Start Control.
Step 5 - Ensure Service Water Pressure SW-PI-153-1 (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*
Ipor~
PROMP.
PROMPT~ or66tidri,with that'.;6bot~erP~ tr
~ xaiminee or,, monitor-diesel !generator 6p rati6r:Jnp"t'.
Intdrdertrwill
I
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*
elrica~ýop erati1Rn4h'id
for
It~~~~I 1 ~ I ~~ I It MR-crplt m
- 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-1 2.2A-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 Generato'ris
ready for electrical operation per OP-50.1.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
IN-PLANT
LESSON TITLE: Fire Water Injection Using The Motor Driven Fire Pump.
REVISION NO: 0
RECOMMENDED BY:
Instructor/Developer UDAI
CONCURRENCE BY:
Line Superintendent/Siu ervisor 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. 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 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.
S3132c 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: Jý,Ste ipL~O to' strtte ir umI(8
wtuto durihgd~~9P
excto9tee,-1)aei
edure.D ste;ps mare NOT, requed to Pe,
aetei,
OT!rmedi be) ,erm0e- dJ,~
li*ý ,i ý, 0,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/U NSAT*
Step 2 - Shift the Motor Driven Fire Pump to the alternate supply as follows:
a. Disengage position pin from position plate.
Positionpin 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-SWcabinet 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.
SATIUNSAT*
I
I
PRMT fearnif1e4-can~taQctscontro ppmnrf~tstarthp' Motor-,Driven, ir~ Pup.nfr
ea~ithe upwlht titfo the cotro room an0stoclysatd I
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*
i . .... .... . . . . . .. ... ... ... . ... . ... . .. .. . .. . .. .
Step 4 - Unlock and open Fire Protection (Well Water) to Service Water Flush Supply Shutoff
Valve 2-FP-PIV20.
- CRITICAL STEP ** SAT/UNSAT*
NOTE4disdipnct
El {O7 witcli~ n te 23 elvation of:the" abe fspre"'ae
3132c Page 5 of 9 REV. 0
Fire Water Injection Using The Motor Driven Fire Pump.
Step 5 - Place the El1-F073 disconnect switch to On at Node L1G in the cable spread area.
Ell-F073 disconnect switch is in On at Node LIG in the cable spread area.
- CRITICAL STEP ** SAT/UNSAr*
PRMP:When ::Xaminqeeinforscoto ro.1i t~thpffe El1F7 d"sA (ýs"0;-.ý
inforrningeqasý tat,Eli haT1F73dic nnewthi n
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.
TTERMINATINGC
I K
s boxit
dtuden~ pedtorM8n~
the v o when...heP..m.eado
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-0O
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.
3132c 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:
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:
3132c 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, Section 6, and inform the CO when
your actions are complete.
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
TRUE
El - Auto initiated, Recirc B Runback Reset Push Button =
Malfunctions
None
Overrides
El - Recirc B Flow Control 1.0 over 60 seconds
Remote
None
Special Instructions
rods on ENP-24.
Reduce core flow to ENP-24 limit, drive 1st 3 sets of
and reduce
Secure Recirc Pump B, place seal staging valve (V17) to Manual/Open,
controller output to approx. 16%.
flow >23,500 gpm. Ensure
Ensure core flow >30.8 and <45 mlbm/hr, and Recirc A pump
Recirc A pump flow is reduced to 23.500
scram avoidance region will not be entered when
gpm.
Page 2 of 15 REV. 0
3B13a
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. 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. 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:
3/4
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.
- ._ 313B1a Page 3 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in Uie Comments.
Step I - 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 145°F as follows:
a. Determine reactor pressure, convert to psia by adding 14.7 and use steam tables
to convert reactor pressure to temperature.
Reactor temperature in the dome determined by converting psig to psia and
using steam tables.
K SAT/UNSAT*
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 12-TR-R018 Channel 153.
Bottom head rain Lemperature using G31-TI-R607 Point 5 is determined.
//
L 7`cMýSATIU NSAT*
c. Determine temperature difference and record time.
Temperature differential determined and time recorded in OP-02.
SAT/UNSAT*
PROM P lowexamiy. reduce*s noftheopaer*in R*dal tour ecirddifntl temperaingk Rcirr
NOT:* Sterps23....
....... and 24 of* 20P-02 Section 5.2.2 aret not= aplil'=cab .......
e* >49K;.
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 50°F 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 recorded in 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 recorded in 20P-02 using B32-TR-R650 or B057-B058.
SAT/U NSAT*
c. Determine differential temperature, record results and time in 20P-02
Differential temperature determined and recorded,along with time in 20P-02.
SAT/UNSA'*
I PROMPT:
If ex~rninee r~quetsnth
lobo.r~r
inihe~~~~~M4
idiiutorcrdifetalem
CO aetyIs~onlt
rtrendie
I
[I . ... ...
6h~s6', bpi.,I - Ort
NOTE: * , savaiab and should be Msqo
4flowrec*tery ,Bj21RR6l
- 5MENNEN f
-o!e n
33B1a Page 6 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
e . 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.
SAT/UNSAT*
. me I
I~-ýpAA*
I~ ~~ ~~~~~~~ s;!;* *i i i~
.......* ***l; * i+ ; ; ..,'.*; ..
.... ... i *? w ; i ! *** 'ItiF*!
- i! 1.*;*
. 1**1*~*
i!*
j . i 11i
i z*~ i *
~ ~~~~~~~~. .........................
l;~
- f~2
~~ ~ NOE
~ f2PO~Scin522i
A~~~~~~~~~~~~
Step 5 - Ensure Pump 2B discharge valve B32-F031B is closed,
~ ~ 1 ntaplicable'
rei6inakia!6ilerpevdwe~edica~evle
sc~~&
I
Pump 2B discharge valve B32-FO31B is full closed.
- CRITICAL STEP ** SAT/UNSAT*
NOTE Ste 29o§0-2 ection S22"is no :a pplcbe
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
SATIUNSAT*
33B1a 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/U NSAT*
b. MG Set B accelerates to speed.
Ensures MG 2B acceleratesto speed.
SAT/U NSAT*
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 RecirculationPump 2B starts.
SAT/U NSAT*
I NOTE: B32lowthe discharge byass
Sthrough ve
sincehe discharge valv is closed
.lW
. ........
33Bla 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/U NSAT*
reqe t anthe idvdua !torecorld timiiýfetheMG ýSet 2B ýdr~iv'e mtr
I .....PRMPT:ilf:ý,6¶rnipJ & db o Ieit*h, rdpo.. l e.... i*... .... .I
Step 8 - If in Modes 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-FO31B.
B32-FO31B is opened using 2 secondjogs and 10 second rest times for the
first minute (5 totaejogs).
- CRITICAL STEP ** SAT/UNSAT*
b. Fully open Pump 2B discharge valve B32-F031B.
B32-FO31B is fully opened.
- CRITICAL STEP ** SAT/UNSAT*
NOTE:n35 6;20P-2, Sectio5.2.2 are r;ot applaIe
331 a 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-V17 open with the control switch in AUTO.
SATIUNSAT*
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.
tI *7 SAT/UNSAT*
f°
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.
I/o,*t- C4. SAT/UNSAT*
- NOTEj:AWhe6n',IheýýRuflback Re~set :O'hýbuitton":forReio typ2 icersed thsed
de WIn ead~ga jIrrp3i0
ýilbegin :to irncrqgase, pe reactor', `4m ~a6
sec&~~~d~eri6Q~
PupspM(-dpoes
th.co uei nimdae pao cino O-3O
Locking...
!
Z7 44'%6" AZfl"ccjitJ "40Ae1--/O-O
REV. 0
Page 10 of 15 REV. 0
11 3Bla
3B3la Page 10 of 15
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
PROMPT,: I examinet ICas6sistance in resetting the runa*c ,
Step 12 - Reset the Recirculation runback for Reactor Recirculation Pump 2B as follows:
a Depress the Reciro 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 ** SATIUNSAT*
II
ei cndtaineq se AO.When examin k
I
PROMPT" when informed as SC ofthe failure infor examinee thatanothe e'ratorWi
eter aan nnounbe AOPnO3 L >1
33B1a Page 11 of 15 REV. 0
Recirculation Pump Start - Recirculation Pump Speed Control Failure.
Step 13 - Inform SCO of speed control failure.
SCO informed of speed control failure.
SAT/UNSAT
6
IS.
TEMNTN
.. .t
CU:hen the scoop tube is locked for Reciro MG
-
.;
.'
..
.
... et 2B, this JPMis
- m
I
- 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:
202004B1301, 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.
3Bla 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: Co ntrol Room Simulator 4 ( Not applicable to In-Plant JPMs)
Time Critical: Yes No 4 Time Limit N/A K
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:
33B1a 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 start'up 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
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 Usina 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.
5. Reactor Level Hi/Lo has alarmed since securing the RWCU reject flow path.
6.ý tl-vfl-V Lt £t Wof
INITIATING CUE: /o
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.
331lb Page 3 of 9 REV. 0
Reduce RPV Water Level Usincg RWCU To Radwaste
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
I'T The folowing actions are directed by GP-02. There are no specific instructions in
OP-14 (Reactor Water Cleanup Operatinq Procedure) that applV for current plant I
conditions. The operator is expected to be able to control RPV level usinq CRD and I
RWOU reject during execution of General Operating Procedures. I
PROMPT, When notified of reject operation to Radwaste, as Radwvaste CO, inform examinee
that Vou have aliqned the reject flow path to the Waste Collictor Tank. Report
Waste CollectorTank level is 20% and sufficient capacitv exiSts or approximately
20,000 gallons of reject flow.
Step 1 - Obtain current revision of GP-02.
Currentrevision of GP-02 is obtained.
SAT/UNSAT*
1/2->
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.
SAT/UNSAT*
Step 3 - Open Reject To Radwaste Viv, G31 -F035.
Reject To Radwaste VIv, G31-F035 is open.
- CRITICAL STEP ** SAT/UNSAT*
331lb Page 4 of 9 REV. 0
Reduce RPV Water Level Usinq RWCU To Radwaste.
Step 4 - Throttle open RWCU Reject Flow Control VIv, G31 -F033 to achieve a lowering RPV
water level.
G31-F033 is opened to achieve a lowering reactorwater trend.
- CRITICAL STEP ** SAT/UNSAT*
EBpodMEI If asked, as Radwaste CO, Irep6rtWater C ollector Tank level, rising.
NO I e operator may (but is not r.euired to) reduce CR0 flcw rate to the RPV to aid in I
reducinq RPV level to the desired band. Ifthe operat6r rdduces CRD flow rate, ORD I
parameters should be maintainedlper 0 Section 6.0. ko-I
NOIE The operator should monitor Reqen HX Outlet, Point 2, and/or Filter Inlet Point 3, on
G31-TI-R607, to ensure Non-Reqen heat exchanqers outlet temperature remains I
below 1300F, but with RPV temperature,<2120F, 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 1300F.
Operatormonitors Regen HX Outlet, Point2, and/or Filter Inlet, Point 3, on G31
TI-R607, to ensure Non-Regen heat exchangers outlet temperature remains
below 1300F.
SAT/UNSAT*
33Blb 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-NO04A/B/C.
RPV water level indicatesat or below 192" as indicatedby C32-LI-NOO4A/B/C
and ReactorLevel 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*
I
fTRMINATING CUE: When RPVwatrf 6ýev ,idicates! 192" on narrow range indicators
II ' NOO4A/B/C, this JPM s complete. _ 1
- Comments required for any step evaluated as UNSAT.
33Blb Page 6 of 9 REV. 0
Reduce RPV Water Level Usina RWCU To Radwaste.
RELATED TASKS:
204002B1301, 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.
3B3lb Page 7 of 9 REV. 0
Reduce RPV Water Level Using RWCU To Radwaste.
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 Vt Time Limit N/A
Alternate Path: Yes - No ,
EVALUATIOlN
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:
33Blb 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.
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.
'C
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
CONTROL ROOM
F
BNP- 03-A'Ic
I
LESSON TITLE: Emergency Equalization Around MSIV's - Using the Hard Card
REVISION NO: I
RECOMMENDED BY:
Instructor/Developer DATE
CONCURRENCE BY:
Line Superintendent/Supervisor DATE
APPROVED BY:
Superintendentlsupervlsor I raining UAIL
DATE
Superintendent/Supervisor Training
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. If this 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. I
Emergency Equalization Around MSIV's - Using the Hard Card
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step I - Obtain "Hard Card" for MSIV equalization
"HardCard"obtained for MSIV equalization.
SAT/UNSAT*
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*
- x-c* oer
Y
(-x-e,
K
"
A-4Z4/
"//I
/, 4fTIL
- 1Ic Page 4 REV. 1
6 6t :- .
Emerqency Equalization Around MSIV's - Using the Hard Card
Step 4 - Reset Group 1 Isolation.
Resets Group l 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-F028B, 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.
SAT/UNSAT*
Step 7 - Open B21-F019.
MSL Outboarddrain Isolation Valve B217F019 open.
- CRITICAL STEP ** SAT/UNSAT*
3A1lc 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.
SAT/UNSAT*
Step 9 - Close MVD-F021.
Common drain line orifice Bypass Valve to condenser, MVD-F021 closed.
SATIUNSAT*
Step 10 - Open B21-F016.
MSL Inboarddrain Isolation Valve, B21-F016 open.
- CRITICAL STEP** SAT/UNSAT*
Step 11- Open MS-F038 A, B, C, D-ae- dr t
9---e-, ,
At least one MSL orifices bypass valve: MS-F038A, B, C, or D open to increase
steam line pressure.
- CRITICAL STEP ** SAT/UNSAT*
Zf 4-ow ~" 4 Arcc#
3Alc Page 6 REV. I
Emergency Equalization Around MSIV's - Using the Hard Card
K-
Step 12 - Ensure steam line pressure is increasing downstream of Outboard MSIVs.
Steam line pressure rising as indicated on 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 closed.
SAT/UNSAT*
1/2>
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/U NSAT*
Step 15- Open MVD-F021.
MVD-F021 indicatesopen.
SAT/U NSAT*
3A1lc Page 7 REV. 1
Emergency Equalization Around MSIV's - Using the Hard Card
MNOTE:iWhe re5Jstd6 oeMV-9uing Remt Funcýtion !MS" VMSO5.
45kOM.4 inflhl RIN4
1> Kv
gntinet1VA56bi.
~
Step 16 - Request AO open MVD-V5005.
MVD-V5005 is open
SAT/UNSAT*
Step 17 - Open MS-V46, V47, V48, V49 and V35.
MS-V46, V47, V48, V49 and V35 are opened.
SAT/UNSAT*
Step 18 - Ensure open MS-V43, MS-V44, MS-V45, MS-V37/39, MS-V411NV42, MS-V36.
MS-V43, MS-V44, MS-V45, MS-V37/39, MS-V41NV4Z MS- V36 are open.
SAT/UNSAT*
3Al c Page 8 REV. I
Emergency Equalization Around MSIV's - Using the Hard Card
oeigM.V....
0?,i~~,J crt6I.0f4~bih6ndenserivacuumidrw
(trie6W~sasadSAE$ t,rt&&f< Y 1/2
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.
Supervisor notified MSIVs have been opened per the Hard Card.
SAT/UNSAT*
WW
- 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/1032)
TOOLS AND EQUIPMENT:
None
SAFETY FUNCTION
3 - Reactor Pressure Control (Main and Reheat Steam System)
REASON FOR REVISION:
Bank JPM LOT-SIM-JP-025-AO1. 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 4 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 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:
I 3Alc Page 11 REV. I
K.
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
mmmm--%
BNP-03-Bld
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, ZA447 (RHR Pump B Overload alarm)
El, ZUA1861 (4KV Bus E4 Motor Overload alarm)
E2, ZA467 (RHR Pump D Overload alarm)
E2, ZUA1661 (4KV Bus E2 Motor Overload alarm)
Special Instructions
1. Throttle El1 -FO03B and El1 -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 1/2 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 (El 1-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 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.
3. 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.
33Bld 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-15.0.
Current Revision of AOP-15.0 obtained.
SAT/UNSAT*
Step 2 - Restore and maintain reactor water level 200-220".
Reactorwater level is 200-220" as indicatedon B21-LI-NO27A or B.
SAT/U NSAT*
Step 3 - Reduce reactor pressure below 125 psig per GP-05
Reactorpressure is below 125 psig.
SAT/UNSAT*
Step 4 - Ensure RPS is energized.
RPS Buses A and B are energized.
SAT/U NSAT*
33Bld 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.
,t* ** CRITICAL STEP ** SAT/UNSAT*
lo"If -f 4ýw, Cý
.PROMPT:; Irequeteds Unit SCOQinfor examneethat p coldo dindown ,
aeNOTaIPnoHPiTii
Step 6 - Close Loop B Outboard Injection Valve, El1-FO17B. (/
E 11-FO1 7B indicates full cloi
- , _ I
-,t,499 T-9EP " SAT/UNSAT*
/7
ý-tt- A
/C~,6 rr44 -,l
4 -Cr-
Step 7 - Open Loop B Inboard Injection Valve El1-FO15B.
EII-FO15B indicatesfull open.
- CRITICAL STEP ** SAT/UNSAT*
Step 8 - Open RHR Shutdown Cooling Outboard Isolation Valve El 1-F008.
El 1-F008 indicates full open.
- CRITICAL STEP ** SATIUNSAT*
REV. 0
Page 5 REV. 0
3B1d
33B1d Page 5
Shutdown Cooling Restoration With RHR Pump Overload.
Step 9 - Open RHR Shutdown Cooling Inboard Isolation Valve E 1l-F009.
El 1-F009 indicates full open.
SATIUNSAT*
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 hf Et-rFO-1B11 hs beerhr16"e to6e'stablish ppprboximately, 6090 'gploo
B iid~45 siarted,,,
it RHR~~Puh~ip itate Trigge' l)~l ~xup~a
nh:Pm 0) tad i tdpd at
++ ... .... .* ~~~~~~~~r
..... . .. , [s i++... :;!i 'J '
I.
.POMPT Tfljm
4&I
ý:i Ifireqesed AO bepitl devc showstarget: on phase
BE4)~j~:or RHRepm P(2asapibl.
g tbeaeo
Jyt4 <Vt* RHR~ý
.....
...
PQE:4(4<0,W
<<4tsi
ifig4~~~Ui ~oo~la
t
>examin66 il lC
lam cnweg hr~~dh~r
cotc7ndhvyou s atu.ngth________
hat~~~~~
~~~~~ nohrprt&dth nPOt
beakrt~beckrd~~
pumpmotr
I
Step 11 - Slowly throttle open Loop B Outboard Injection Valve Ell -F01 7B to re-establish
RHR loop conditions prior to the event.
ElI-FO17B throttled open to establish RHR Loop flow of >4150 gpm.
- CRITICAL STEP ** SAT/UNSAT*
£7 /4t&A1A. /Z A- 4 / e-
REV. 0
Page 6 REV. 0
3B1d
3B3ld Page 6
Shutdown Cooling Restoration With RHR Pump Overload.
Step 12 - Refer to APP for RHR Pump (B or D) overload
Refers to APP for RHR Pump (B or D) overload
A -o03- SAT/U NSAT*
q7
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*
Step 15 - Fully open Loop B Outboard Injection Valve El 1-F017B.
E1I-FOI7B indicates full open.
SAT/UNSAT*
33Bld Page 7 REV. 0
Shutdown Cooling Restoration With RHR Pump Overload.
K->
Step 16 - Ensure Reactor Head Vent Valves, B21-F003 and B21-F004 are Open.
Reactor Head Vent Valves, B21-F003 and B21-F004 are Open.
SAT/UNSAT*
Step 17 - Inform Unit SCO RHR shutdown cooling has been re-established per AOP-1 5.0.
Unit SCO informed RHR shutdown cooling has been re-establishedper AOP
15.0.
SATIUNSAT*
TERMINATING C.UE::. WhenHRsh*ui!sfi td'6n
ioo ing has been re-establiseprA-5O
- Comments required for any step evaluated as UNSAT.
33Bld Page 8 REV. 0
Shutdown Cooling Restoration With RHR Pump Overload.
RELATED TASKS:
2050166B401, Respond To A Loss Of Shutdown Cooling Per AOP-1 5
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:
AOP-1 5.0
APP A-4, 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.
REV. 0
Page 9
33Bldd
3B1 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:
33B1d 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.
3. 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.
CAROLINA POWER & LIGHT COMPANY
BRUNSWICK TRAINING SECTION
CONTROL ROOM
mmlmm--ý%
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-lO 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
Event Panel Tag Title Value Activate Deactivate
(ramp rate) Time (sec) Time (sec)
I
El XU-3 GSB02G15 Main Stack Radiation 13/5 min 0 SEC N/A
Trigger I 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.
33B1e 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. . ,-rj-- '.
t4D
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.
33B1e Page 3 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
PERFORMANCE CHECKLIST
NOTE: Sequence is assumed unless denoted in the Comments.
Step 1 - Obtain current revision of OP-10, Section 8.2 and verify if applicable.
Currentrevision of OP-10, Section 8.2 is obtainedand verified as required.
SAT/UNSAT*
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.
I -I
Value recorded in OP-10 of initial reading + 0. 17 (1.23).
SAT/UNSAT*
I.
>/
NOTEK> *I ep of Section 8.2.2S i*no applicble* ;**>***; :? *i
Step 4 - Monitor Stack Rad Monitor, D12-RM-R600B, for increase in activity during venting.
D 12-RM-R600B periodically monitored.
SAT/UNSAT*
331le 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/UNSAr*
Step 6 - CLOSE REACTOR BUILDING SBGT 2B INLET VALVE, VA-2H-BFV-RB.
VA-2H-BFV-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*
NT Steps 10 nd'f6§ý
11hofoSeto 827a: not apIiab1e
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-10 w/ Stack Rad Monitor Increase >50%
Step 9 - OPEN DW PURGE EXH VALVE, CAC-V23.
CAC-V23 indicates full open.
- CRITICAL STEP ** SAT/UNSAT*
Step 10- OPEN DW HEAD PURGE
CA C-V49 indicates full open.
SAT/U NSAT*
Step 11 - OPEN DW HEAD PURGE EXH VLV, CAC-V50.
CAC-V50 indicates full open.
SAT/UNSAT*
c-Ur~a~CA-
Step 12 - Monitor Main Stack Rad Monitor and determine reading has risen by >50%.
Determines Main Stack Rad Monitorreading has risen by >. 17 (50%).
SAT/UNSAT*
3B3le Page 6 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
Step 13- CLOSE DW PURGE EXH VLV, CAC-V23.
CAC-V23 indicates full closed.
/11
- CRITICAL STEP ** SAT/UNSAT*
CO,cn-,
ct%4s- 6{tt
flAitr, o 4 Ct*
Step 14 - CLOSE DRYWELL PURGE EXH VALVE, CAC-V9.
CAC-V9 indicates full closed.
- CRITICAL STEP ** SATIU NSAT*
NT: EtrStp1ORSe:i6o hsJMi rtclOL ifopnd
Step 15 - ENSURE DW HEAD PURGE EXH VLV, CAC-V49, IS CLOSED.
CAC-V49 indicates full closed.
- CRITICAL STEP ** SATIUNSAr
3Ble Page 7 of 12 REV. 3
Vent the Drywell per OP-10 w/ Stack Rad Monitor Increase >50%
Step 16 - ENSURE DW HEAD PURGE EXH VLV, CAC-V50, IS CLOSED.
CAC-V50 indicates full closed.
- CRITICAL STEP ** SAT/U NSAT*
Step 17 - CLOSE SBGT DW SUCT DAMPER, VA-2F-BFV-RB.
VA-2F-BFV-RB indicates full closed.
- CRITICAL STEP ** SAT/U NSAT*
I..r w6r ae / FlC4-.-,
01*00
0~l ............
~.
K 2<
T'9 ar T'cii~
ON
Step 18 - OPEN SBGT TRAIN 2B REACTOR BUILDING SUCTION VALVE, VA-2H-BFV-RB.
VA-2H-BFV-RB indicates full open.
SAT/U NSAT*
Step 19 - OPEN SBGT TRAIN 2A REACTOR BUILDING SUCTION VALVE, VA-2D-BFV-RB.
VA-2D-BFV-RB indicates full open.
SAT/UNSAT*
33B1e Page 8 of 12 REV. 3
Vent the Drywell per OP-10 w/Stack Rad Monitor Increase >50%
Step 20 - CONFIRM ALL SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKERS
are closed.
All Suppression Chamberto Drywell vacuum breakers verified closed.
SAT/U NSAT*
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*
tary ýconaqinme
PriiM'ý her'g0 u1
- Comments required for any step evaluated as UNSAT.
33B1e 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.
KIA 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 Simulator-" (Not applicable to In-Plant JPMs)
Time Critical: Yes No I/ 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:
33B1e 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.
CAROLINA POWER & LIGHT COMPANY
v\
BRUNSWICK TRAINING SECTION
CONTROL ROOM
BNP-03-Blf
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-ll
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:
jat- 0>U.*& £&W4YSL
1. Unit Two is operating at power. Unit One is in MODE 5.
2. The Control Building Emergency Recirculation System is in standby.
3. A fuel handling accident has occurred on Unit One.
/
4. The Unit SCO has entered AOP-05.0 and EOP-04-RRCP.
5. This JPM is time critical. d,
,.P,,L.,=c
INITIATING CUE: ,ZK4s 72t* .t
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.
33B1f 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, ControlBuilding Emergency Recirculation Damper verified OPEN.
SAT/UNSAT*
3Blf Page 4 of 9 Rev. 0
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
Step 5 - Recognize loss of running CREV Fan an start e CREV not previously started.
One CREV Train (A ore B) is in opera
- CRITICAL S 'EP ** 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 Mechanical Equipment Room Vent
Fans stopped and associatedSupply and Exhaust Dampers verified closed.
- CRITICAL STEP ** SAT/UNSAT*
33B1f 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) CabledSpead Ro6om j6nt Fans isitiate
bat'chfi'Ie)u'nit'one'cable spread fanshudw
Step 9 - Request Unit 1 STOP Cable Spread Room I Vent Fans, 1A-SF-CB and 1A-EF-CB,
and ENSURE associated Supply and Exhaust Dampers CLOSE.
IA-SF-CB and IA-EF-CB, Cable Spread Room I Vent Fans stopped and
associatedSupply and Exhaust Dampers verified closed.
1/1//-icC 5777-05 14 SAT/UNSAT*
&2i Fotz J7D 0?'O
Step 10 - Inform Unit SCO that actions for manual startup of the Control Building Emergency
Recirculation System are complete.
Unit SCO notified.
SAT/UNSAT*
TERMINATINGCue: Wen the;ontrol Buiding Emegency ecirculation System has been
sared a'nd isolated perthe har'd this JPM is comrn ete.- iN
. Comments required for any step evaluated as UNSAT.
3Blf Page 6 of 9 Rev. 0
Manual Startup of Control Building Emergency Ventilation - Trip Of One Fan
RELATED TASKS:
288202B101, 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 " Unit: 0
Setting: Control Room Simulator " (Not applicable to In-Plant JPMs)
Time Critical: Yes " No Time Limit 20 min
Alternate Path: Yes V 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:
C4 2 S
tc 4,le
1. Unit Two is operating at power. Unit One is in MODE 5.
2. The Control Building Emergency Recirculation System is in standby.
3. A fuel handling accident has occurred on Unit One.
4. The Unit SCO has entered AOP-05.0 and EOP-04-RRCP.
5. 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
CoePromnePrmtr hc aulAR A
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 15 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 examine9e.
C-0ý TADCl \orX y
TASK CONDITIONS:
( 44ý)
The CODSR requires performance of 1PT-01.11 Core Performance Parameter
Check on Unit 1.
2. All applicable prerequisites of I PT-01.11 are met.
3. Ifindependent verification is required, assume the verification is complete as
applicE ble.
INITIATIN4G CUE
@
The Uni tSCO directs you to perform 1PT-01.11 and inform the SCO of the results upon
complet ion.
>0 koua'ýCA-a 1-14ýCA1o. ý-;
3Blg Page 3 of 15 REV. 0
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.
Current revision of IPT-01. 11 obtainedand verified as required.
References Section 7.1
SATIU NSAT*
PROMPT ncce examineeOdemonstratesjthat he/she can demandizaCorelPerormanceLog*
usiethro u butth
II nrovdehedore rem*idd& obtane boam Deoa
teeormanceo sprinthJP
a
.f..
. I
li
NOE An eit of processh:compupeyc~ye pre-ranmngj
~~~~~omue;display: d~~i~t~bu ot1 d~tip 4 rsigte
id~i
a,re:Many mnethd tocl uio<dtalJ
"-r
I
A
"plydepressth r~ Ba lbhc sbtky 9KM~ MRt U st
Step 2 - Obtain an edit of the process computer core performance program.
Core PerformanceLog obtained from process computer.
,0 t7~leozthý/&-0. /0c SAT/UNSAT*
&Yr r4e 1? Az 2A.-
33Blg Page 4 of 15 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step 3 - Verify, using the Failed Sensor List, failed inputs have correct substitute values.
_De*rjte *es-ne-faieds sensors-exist-a at this step is marked as N/A.
0 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 IPT-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.
SATIU NSAT*
Checks core performance log and verifies value for CMAPRA T *51.00.
SAT/UNSAT*
14
33Blg Page 5 of 15 REV. 0
Core Performance Parameter Check- Manual APRM GAF Adjustment Required
Step 6 - Determine if the acceptance criteria listed in Section 6.2 of 1PT-01.11 are satisfied.
Determines APRMS 2, 3, and 4 are within limits and APRM I is above the limit.
"**CRITICAL STEP ** SAT/UNSAT*
Step 7 - Obtain current revision of I OP-09 and verify if applicable.
Currentrevision of IOP-09 obtainedand verified as required. References
Section 8.1.2.
SAT/UNSAT*
Step 8 - OBTAIN Unit SCO permission to adjust the APRM GAFs.
ObtainsSCO permission.
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Core Performance Parameter Check - Manual APRM GAF Adjustment Required
-Step 9 - OBTAIN Display 820 at the PPC.*
PPCScreen 820 is displayed.
SATIUNSAT*
Step 10 - Review heat balance substituted values and failed sensors for impact on APRM I
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*
3/4
Step 12 - Ensure APRM 1 heading indicates OPERATE.
Checks APRM 1 headershows OPERATE.
SAT/UNSAT*
Step 13 - OBTAIN value oU1.C51R1066.
Obtains UIC51R1066 from PPC Screen 820 or Core PerformanceLog.
SAT/U NSAT*
3Blg Page 7 of 15 REV. 0
Core Performance Parameter Check- Manual APRM GAF Adjustment Required
Step 14- PLACE the APRM-to be adjusted in BYPASS.
PlacesAPRM I in bypass at P603.
SAT/UNSAT*
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.
Presses ENTER SET MODE soft key.
- CRITICAL STEP ** SAT/UNSAT*
fl seond exir~befrethe pasodicete &(ENT"sý'~edi
PRoMPT.* i r,eueste, d irect tbe traihee tq take any actions needed tq eor~tih~~ft
I II
33Blg Page 8 of 15 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
P '
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.
SATIUNSAT*
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/UNSAT*
NOT;* i' ; ;LeEE1!
ST ea*:a6d!RIGN
ar~ cuso
a e*esaeueolselec
..,,$,curso gjVlp crso*ý 11th
- e; ESIREQ GAIN
cnan1, 1n.. t&:l *
dgit
u u~*:
u -es
a p......... g<,p i
33B1g Page 9 of 15 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step22 : ADJUST the DESIRED APRM GAIN so that the PROJECTED FLUX (%) is Ž
U1 C51 RI 066 value previously obtained.
Using the cursorkeypad selects and changes the DESIRED APRM GAIN until
PROJECTED FLUX (%) is Ž UIC51R1066 value obtained in Step 9.
- CRITICAL STEP ** SATIUNSAT*
Step 23 - PRESS ACCEPT soft key.
PressesACCEPT soft key.
"**CRITICAL STEP ** SAT/UNSAT*
Step 24 - CONFIRM the "PRESENT" APRM GAIN changes to equal the "DESIRED" APRM
GAIN AND the PROJECTED AGAF equals 1.000.
Confirms "PRESENT"and "DESIRED"APRMGAIN equal and PROJECTED
AGAF is *<1.000.
SAT/UNSAT*
Step 25- PRESS EXIT soft key.
Presses EXIT soft key.
SATIU NSAT*
Step 26 - PRESS EXIT SET MODE soft key.
Presses EXIT SETMODE soft key.
SAT/UNSAT*
33Blg Page 10 of 15 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step 27 - PRESS YES soft key.
Presses Yes soft key.
SAT/UNSAT*
Ii POMP: Ifor exmndthat"ante 'operator: wi corn pete Attac hmpn, 4H$ 9M M'ii
I.
Step 28 - CONFIRM APRM display header shows OPERATE.
Confirms APRM display headerindicates OPERATE.
SAT/UNSAT*
Step 29 - Verify APRM GAF * 1.00 on Attachment 3 of IOP-09.
Confirms APRM 1 AGAF *<1.00 using PPC 820 screen or by obtaininga new
Core Performance Log.
SAT/U NSAT*
Step 30 - REMOVE APRM from BYPASS.
Removes APRM I from bypass at P603.
SAT/UNSAT*
PROMPT: roter operatoqiltaseh gi
Infrmthb6 ex'amine6: athatb a~rTtXK
Ih
tcninue with, OPT-OIAI2
PPiadJA U
6.
33B1g Page 11 of 15 REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
Step 31 - Determine if CMFLPD is *<1.00.
Checks core performance log and verifies value for CMFLPD is *<1.00.
SAT/UNSAT*
~f~The Follw~ing Steprýisiely~alreadyipprorrne~adi
NOTE: Oyqietb Mld IITi -j,
t i
' R........
comD~~eu aiaiIM
Step 32 - Verify acceptance criteria listed in Section 6.0 met satisfactorily.
Acceptance criteria determined to be satisfactory.
SAT/U NSAr*
- Q
PROMP*::*
~~h'
cn*eq ~ ta~ :~ *1sop
J. mSte*etez az
-anditsfat_0 110mii* 1N511ii]
Step 33 - Notify Unit SCO that I PT-01.11 is completed SAT.
Supervisor notified.
SAT/U NSAT*
6
c
aIetac
~~~a p p q
c. teI
- q j e 51v
n
.,E1*011i Wi"S I hee
Ino* 1.~
rGm!!
...........
e dthes,'ue
!e..... ....
s ;apiispis acpto, y
.....
W ............ .
i1
- Comments required for any step evaluated as UNSAT.
Ox94X-
t
/400
1016ýA lc),ý ",f
3Blg Page 12 of 15 f REV. 0
Core Performance Parameter Check - Manual APRM GAF Adjustment Required
LIST OF REFERENCES
RELATED TASKS:
2152098401: Operate the PRNMS per OP-9.
KIA 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.
33Blg Page 13 of 15 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:
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:
33B1g Page,14 of 15 REV. 0
\- /
TASK CONDITIONS:
1. The CODSR requires performance of 1PT-01.11 Core Performance Parameter Check
on Unit 1.
2. All applicable prerequisites of I PT-01.11 are met.
3. If independent 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.
/ BRUNSWICK-1 TWK-0305 03JAN28-1( 3_25 19977 MWD/MTU TRIGR=PPXSU REV=JUN01 C
CORE PERFORMANCE LOG --- LONG EDIT (PAGE 2)
- CONTROL ROD POSITIONS AND CALIBRATED LPRM READINGS *****
02 06 10 14 18 22 26 30 34 38 42 46 50
51 51
47 -- 21 .. -. 33 .. -. 37 -. .-- 28 -.. .- 16 47
46 59 57 56 34
68 79 69 80 51
43 -- 48 -- 36 46 -- 16 48 -- 36 48 -.. .- 39 43
39 18 -.. .. 37 . . -- 46 .. -- 51 -.- 41 -- 28 39
37 67 65 75 65 57
56 87 65 60 75 82
35 -- 40 -- 36 48 -- 08 38 -- 24 36 -- 08 43 36 48 35
31 -- 23 -- 46 -- 52 -- 50 -.. .. 50 -. .-- 37 -.. .. 31
"* OTHER FA]
41 65 74 67 75 56 "* SENSOR DT
57 66 54 52 60 70
27 -- 47 16 41 24 34 08 34 -- 24 37 -- 16 50 -.. .. 27
SENSOR S9
23 -- 21 -. .-- 41 .. -- 48 .. .-- 51 -. .-- 45 .. -- 33 -- 23 1PPXDUI1 E
39 66 66 73 65 58 1PPXDUM2 E
57 78 57 54 65 79
19 -- 45 -- 36 43 -- 08 36 -- 24 35 -- 08 40 -- 36 49 19
15 -. .-- 30 .. -. 41 -- 46 .. -- 37 -.- 21 15
60 67 65 66 45
85 78 66 87 68
11 -.. .- 60 -- 36 43 16 41 -- 36 50 --. .- 51 11
07 D - .. ..- 21 -.. .. 24 -.. .. 1i8 07
C 39 41 37
B 58 57 56
03 A -- 45 -. . .--48 -.. .--42 03
02 06 10 14 18 22 26 30 34 38 42 46 50
CONTROL ROD SYMMETRY : EIGHT-FOLD CONTROL ROD SEQUENCE : A-2 CONTROL ROD DENSITY : 0.0791
BRUNSWIC( - WK-0305 03JAN28-10.53.25 19977 MWD/MTU TRIG( ŽPXSU REV=JUN01 (
CORE PERFORMANCE LOG --- LONG EDIT
B1CT4 BOC TO EOFPC-2026MWD/MT ODYNB POW DEP MCPR
CALCULATION TYPE : NORMAL CONVERGENCE : TIGHT SYMMETRY : FULL
CTP CALCULATION : HEAT BALANCE CYCLE : 14
STATE CONDITIONS FLOW RATES CORE PARAMETERS NUCLEAR LIMITS LOCATION
GMWE 919.61 WT 78.1 CMEQ 0.2466 P-PCS 1.94 41-20-09
CMWT 2738.4 (93.7%) WTSUB 76.58 CAEQ 0.1543 FCBB 2.443
PR 1044.9 PSIA WTFLAG 2 CAQA 0.1432 CMPF 2.835 39-14-06
DHS 20.60 WFW 11.83 CAVF 0.4846 CMFLCPR 0.934 29-24
WT 78.10(101.4%) WD 33.69 CAPD 55.2607 P=1.468 F=1.260
CRD 0.0791 RWL 187.1008 CMAPRAT 0.928 41-18-08
CYCEXP 0 MWD/MTU ERATIO 0.96 CDLP 19.0616 P=1.000 F=1.000
MEASURED/CALCULATED LPRM READINGS DPCC 24.7085 CMFLPD 0.867 39-14-06
AVG: 0.00% MAX: 0.00% KEFF 1.0016 CMFLEX 0.777 11-48-06
LOCATION 1 2 3 4 5 6 7 8 9 10 11 12
AXIAL REL POWER 0.54 1.22 1.37 1.43 1.40 1.32 1.19 0.98 0.89 0.75 0.60 0.31
REGION REL POWER 0.92 1.02 0.93 1.02 1.16 1.03 0.92 1.02 0.92
RING REL POWER 0.83 1.23 1.15 1.13 1.12 1.09 0.70
APRM GAFS 1.03 1.00 1.00 1.00
- THE 10 MOST LIMITING BUNDLES ******
FLCPR LOC CPR LIMIT APRAT LOC APLHGR LIMITI FLPD LOC LPD LIMIT
10.41 11.22
0.934 29-24 1.573 1.468 0.928 41-18-08 10.41 11.24 0.867 39-14-06 11.62 13.40
0.934 39-14 1.573 1.468 0.926 35-12-08 0.864 41-42-05 11.58 13.40
0.928 31-22 1.582 1,468 0.917 43-18-08 10.09 11.00 0.860 41-16-08 11.53 13.40
0.922 31-28 1.593 1.468 0.914 35-10-08 10.05 10.99 0.859 37-12-08 11.51 13.40
0.921 37-24 1.594 1.468 0.911 43-20-08 10.29 11.29 0.846 35-14-08 11.33 13.40
0.921 33-24 1.594 1.468 0.907 33-10-08 10.15 11.19 0.845 39-18-08 11.32 13.40
0.921 27-22 1.595 1.468 0.869 39-14-07 8.05 9.27 0.831 43-16-07 11.14 13.40
0.920 29-20 1.596 1.468 0.866 41-16-08 8.03 9.27 0.831 37-10-07 11.13 13.40
0.919 29-16 1.598 1.468 0.865 37-12-08 8.02 9.27 0.830 39-44-05 11.12 13.40
0.916 39-18 1.602 1.468 00.857 41-42-05 8.16 9.52 0.829 43-40-05 11.12 13.40
- ASSYS W LIMITS > 1 I FLCPR 0 1 APRAT 0 1 FLPD 0
- NUCLEAR LIMITS BY REGION *********
7 8 9
0.919 13-40 0.909 23-38 0.922 39-40
0.862 13-40-05 0.824 29-46-05 0.864 41-42-05
0.912 17-42-08 0.899 33-44-08 0.917 35-42-08
.------------------------------ +----------------------------
4 5 6
0.911 15-30 0.934 29-24 0.921 37-24 * MFLCPR *
0.817 07-30-05 0.739 31-22-11 0.825 45-24-05 * MFLPD *
0.903 09-20-08 0.813 33-26-14 0.911 43-20-08 * MAPRAT *
*----------------------------
1 2 3
0.927 13-14 0.919 29-16 0.934 39-14
0.862 13-14-06 0.817 29-08-05 0.867 39-14-06
0.921 17-12-08 0.907 33-10-08 0.928 41-18-08