ML031710811
| ML031710811 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/14/2003 |
| From: | Gumbert R AmerGen Energy Co |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-289/03-301 50-289/03-301 | |
| Download: ML031710811 (51) | |
Text
A
TMI SRO License Exam 0511 2/03 TMI-I OPERATOR TRAINING JOB PERFORMANCE MEASURE A.1-1 PERFORM ESTIMATED CRITICAL BORON CONCENTRATION CALCULATION Page 1 of 7
A.l-I 11.2.05.122 Revision 3 05/12/2003 TASK TITLE:
PERFORM ESTIMATED CRITICAL BORON CONCENTRATION CALCULATIONS TASK NUMBER:
001 C030101 TIF: 3.05 KIA
REFERENCE:
System:
NA KIA:
2.1.25 Rating (RO/SRO):
2.8/3.1 POSITION:
S R O H R O H N L O O EVALUATION METHOD:
PERFORM SIMULATE [7 EVALUATION LOCATION:
SIMULATOR 0 IN-PLANT c] CONTROL ROOM c] OTHER [XI TASK STANDARDS:
Examinee calculates RCS boron concentration required to achieve criticality at the desired critical rod position, within the tolerances described within this JPM.
APPROXIMATE COMPLETION TIME: 30 minutes TIME-CRITICAL TASK COMPLETION TIME:
NA minutes REQUIRED TOOLS OR MATERIALS:
Calculator.
Straight Edge.
OP 11 03-1 5B, Estimated Critical Conditions, Revision 34.
REFERENCES:
OP 1103-15B, Estimated Critical Conditions, Revision 34.
HU-AA-104-101, Procedure Use and Adherence, Revision 0.
ALTERNATE PATH JPM? NO SIMULATOR SETUP: NA INITIALIZATION: NA EVENT TRIGGERS: N/A MALFUNCTIONS: N/A REMOTE FUNCTIONS: N/A OVERRIDES: N/A MONITOR N/A Page 2 of 7
A.1-I 11.2.05.122 Revision 3 05/12/2003 READ TO STUDENT When I tell you to begin, you are to CALCULATE THE RCS BORON CONCENTRATION REQUIRED TO ACHIEVE CRITICALITY AT THE DESIRED CRITICAL ROD POSITION. Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions. Perform procedure steps as if you were actually performing the task.
INITIAL CONDITIONS:
The reactor was manually tripped from full power, equilibrium conditions, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.
Prior to the reactor trip, power was constant at 100% for the past 3 months.
Current conditions:
Reactor is at Hot Shutdown.
Preparations are in progress to go critical Reactor trip is reset.
CRD Groups 1-4 are fully withdrawn.
CRD Groups 5, 6, and 7 are fully inserted.
Group 8 APSR positions: 30% withdrawn.
RCS T-ave is 534°F.
RCS Pressure is 2155 psig.
Core Burnup is 600 EFPD.
Reactor startup (achieving criticality) is scheduled to occur 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from this time.
RCS Boron Concentration is 190 ppm.
Mixed Boron Depletion Correction Factor = 0.99.
PPC and Nuclear Engineering are unavailable to provide value for Xenon reactivity.
INITIATING CUE:
The Shift Manager directs you to calculate the RCS boron concentration required to achieve criticality at the desired control rod positions described in Enclosure 1 of OP 1103-15B, Estimated Critical Conditions (provided).
ARE THERE ANY QUESTIONS?
TIME CRITICAL: NO Page 3 of 7
JPM INSTRUCTION SHEET DIRECTIONS TO STUDENT:
When I tell you to begin, you are to CALCULATE THE RCS BORON CONCENTRATION REQUIRED TO ACHIEVE CRITICALITY AT THE DESIRED CRITICAL ROD POSITION described in enclosure 1 of OP 11 03-15B, Estimated Critical Conditions (provided). Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions. Perform procedure steps as if you were actually performing the task.
INITIAL CONDITIONS:
The reactor was manually tripped from full power, equilibrium conditions, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago.
Prior to the reactor trip, power was constant at 100% for the past 3 months.
Current conditions:
Reactor is at Hot Shutdown.
Preparations are in progress to go critical Reactor trip is reset.
0 CRD Groups 1-4 are fully withdrawn.
0 CRD Groups 5, 6, and 7 are fully inserted.
0 Group 8 APSR positions: 30% withdrawn.
RCS T-ave is 534°F.
RCS Pressure is 2155 psig.
Core Burnup is 600 EFPD.
Reactor startup (achieving criticality) is scheduled to occur 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from this time.
RCS Boron Concentration is 190 ppm.
Mixed Boron Depletion Correction Factor = 0.99.
PPC and Nuclear Engineering are unavailable to provide value for Xenon reactivity.
INITIATING CUE:
The Shift Manager directs you to calculate the RCS boron concentration required to achieve criticality at the desired control rod positions described in Enclosure 1 of OP 1103-158, Estimated Critical Conditions (provided).
TIME CRITICAL: NO Page 4 of 7
A.1-I 11.2.05.122 Revision 3 05/12/2003
- Denotes Critical Elements 1
2 3
4 5
6 7
8 9
10 11
!s Sequential Step STEP Examinee obtains a copy of OP 11 03-1 5B, Estimated Critical Conditions, to calculate the ECB in accordance with guidance provided in Section 3.1, using Enclosure 1.
Examinee reviews procedure Section 2.0, Limits And Precautions.
Examinee begins implementation of Section 3.1, Estimated Critical Boron Concentration.
Examinee verifies data included on is correct, in accordance with Initial Conditions.
Using Figure 1, the examinee determines fuel excess reactivity.
Using Figure 6, the examinee determines reactivity worth of Control Rod Groups 5-7 at the desired critical position.
Using Figure 2, the examinee determines reactivity worth of Control Rod Group 8 at the desired critical position.
Using Figure 4, the examinee determines Xenon reactivity at the time of startup.
Using Figure 5, the examinee determines reactivity associated with samarium and plutonium buildup after shutdown.
Examinee calculates boron reactivity worth required for criticality at the desired critical rod position.
Using Figure 3, the examinee determines Hot Zero Power inverse boron reactivity worth.
STANDARD 0
HU-AA-101-101, Procedure Use and OP 11 03-1 58, Estimated Critical Conditions, is a Level 2 procedure.
Adherence, Section 2.1.2 defines Level 2 as Reference Use: referring to a procedure periodically during the performance of an activity to confirm that all procedure segments of an activity have been performed, performing each step in the sequence specified, and where required, signing appropriate blocks to certify that all segments have been completed.
The procedure should be at the work location.
Adherence, Section 4.1.6 requires the Procedure User to observe all Precautions.
0 HU-AA-101-101, Procedure Use and Limitations and applicable Prerequisites.
Expected value = +6.9% AWK.
Interpolation between curves for 400 and 693 EFPD is required in order to determine value for 600 EFPD.
Expected value for 600 EFPD = -1 5% AWK.
Interpolation between curves for 400 and 672 EFPD is required in order to determine value for 600 EFPD.
Expected value = -0.136% AWK.
Correct time (hours after shutdown) is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Expected value = -3.6% AWK.
Interpolation between curves for 400 and 693 EFPD is required in order to determine value for 600 EFPD.
ExPected value = -0.033% AWK.
Expected value = -1.631 % AWK.
Expected value = 127.5 ppm B/% AWK.
SIU Page 5 of 7
A.1-I 11.2.05.122 Revision 3 12 STEP Using the inverse boron reactivity worth, and the required boron reactivity, the examinee calculates the corrected Critical Boron Concentration
- I 3
~
~~
Using the mixed boron depletion correction factor (provided in the Initial Conditions),
the examinee calculates the Estimated measured Critical Boron Concentration.
05/
STANDARD Expected value = 208 ppm.
Expected Value =
210 ppm.
Upper Acceptance Limit =
313 ppm.
Basis for acceptance range:
Reference OP 11 03-1 58, Estimated Critical Conditions, Enclosure 2 Section 4.3, for Critical Rod Position Tolerance Band:
Transient Xenon Startup (if Xenon is MORE negative than -0.5% AWK):
0 Critical Rod Position Tolerance Band is f 0.8% AWK from desired critical rod position.
(+0.8)(127.5/0.99)
= 210 f103 ppm.
Lower Acceptance Limit = 107 ppm.
Upper Acceptance Limit = 313 ppm.
0 0
0 Xenon Free Startup (if Xenon is LESS negative than -0.5% AWK):
Critical Rod Position Tolerance Band is k 0.5% AWK from desired critical rod Lower Acceatance Limit =
107 Dam.
position.
!/ZOO3 SIU END TASK Page 6 of 7
JPM CHANGE HISTORY PAGE A. 1-1 11.2.05.122 Revision 3 0511 2/2003 DESCRIPTION (Include AI # if Appropriate)
Modified Bank JPM 11.2.05.122.
Page 7 of 7
TMI SRO License Exam 091 2/03 TMI-I OPERATOR TRAINING JOB PERFORMANCE MEASURE A.1-2 Page 1 of 7
TASK TITLE:
MAINTAIN MINIMUM SHIFT STAFFING, CONTROL OVERTIME A. 1-2 Revision 1 05/12/2003 TASK NUMBER:
343006060303 TIF: 2.6 K/A
REFERENCE:
System:
NA WA:
2.1.4 Rating(RO/SRO):
2.313.4 Knowledge of shift staffing requirements.
POSITION:
S R O H R O O N L O O EVALUATION METHOD:
PERFORM H SIMULATE 0 EVALUATION LOCATION:
SIMULATOR 0 IN-PLANT 0 CONTROL ROOM 0 OTHER H TASK STANDARDS:
Examinee identifies required actions to restore minimum staffing, and selects personnel in accordance with requirements to control overtime.
APPROXIMATE COMPLETION TIME: 30 minutes TIME-CRITICAL TASK COMPLETION TIME:
NA minutes REQUIRED TOOLS OR MATERIALS:
OP-TM-101-111-1001, Shift Manning Requirements, Rev. 2.
Tech Spec 6.2.2 and Table 6.2-1, Amendment 219.
LS-AA-119, Overtime Controls, Rev. 1 Overtime Callout List (Prepared)
Shift Manning Log (Prepared)
Daily Attendance Form (Prepared) 308 Weekly Schedule (Prepared, OT assignments highlighted)
REFERENCES:
OP-TM-101-111-1001, Shift Manning Requirements, Rev. 2.
Tech Spec 6.2.2 and Table 6.2-1, Amendment 219.
OP-AA-101-111, Roles And Responsibilities Of On-Shift Personnel, Rev. 0.
LS-AA-119, Overtime Controls, Rev. 1 ALTERNATE PATH JPM? NO SIMULATOR SETUP: NA INITIALIZATION: NA EVENT TRIGGERS: N/A MALFUNCTIONS: N/A REMOTE FUNCTIONS: N/A OVERRIDES: N/A MONITOR: N/A Page 2 of 7
A. 1-2 Revision 1 0511 212003 READ TO STUDENT When I tell you to begin, as the Unit Supervisor, you are to PERFORM THE STEPS NECESSARY TO ENSURE THAT YOUR SHIFT IS APPROPRIATELY STAFFED. Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions. Perform procedure steps as if you were actually performing the task.
INITIAL CONDITIONS:
Reactor power is loo%, with ICs in automatic.
The time is 2355 on a SUNDAY Night.
The shift is staffed as indicated on the provided Shift Manning Log.
0 Unit reactor Operator (URO) GORSE reports that his contact lenses have just popped out and are lost. He reminds you that he has a license restriction that requires him to wear corrective lenses. His backup eyeglasses are missing and cannot be located.
Third CRO John Doe is NOT licensed. He is in the Auxiliary Building performing an Independent Verification of a valve lineup change.
0 INITIATING CUE:
When I tell you to begin, as the Unit Supervisor, you are to PERFORM THE STEPS NECESSARY TO ENSURE THAT YOUR SHIFT IS APPROPRIATELY STAFFED.
ARE THERE ANY QUESTIONS?
TIME CRITICAL: NO Page 3 of 7
JPM INSTRUCTION SHEET DIRECTIONS TO STUDENT:
When I tell you to begin, as the Unit Supervisor, you are to PERFORM THE STEPS NECESSARY TO ENSURE THAT YOUR SHIFT IS APPROPRIATELY STAFFED. Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions. Perform procedure steps as if you were actually performing the task.
INITIAL CONDITIONS:
Reactor power is 1 OO%, with ICs in automatic.
The time is 2355 on a SUNDAY Night.
The shift is staffed as indicated on the provided Shift Manning Log.
0 Unit reactor Operator (URO) GORSE reports that his contact lenses.,ave just popped out and are lost.
reminds you that he has a license restriction that requires him to wear corrective lenses. His backup eyeglasses are missing and cannot be located.
e 0
Third CRO John Doe is NOT licensed. He is in the Auxiliary Building performing an Independent Verification of a valve lineup change.
INITIATING CUE:
When I tell you to begin, as the Unit Supervisor, you are to PERFORM THE STEPS NECESSARY TO ENSURE THAT YOUR SHIFT IS APPROPRIATELY STAFFED.
TIME CRITICAL: NO Page 4 of 7
A. 1-2 Revision 1 05/12/2003 STEP STANDARD SIU 1
11 C U I f s k e d, report that there are no other licensed CROs on site.
Examinee references Shift Manning Log to determine current shift manning status.
Examinee references Shift Manning Log and determines that current staffing is acceptable.
CUE: In step 4 below, only WHEN examinee indicates need to obtain each document, THEN hand examinee JPM-prepared documents.
0 308 Weekly Schedule list 0
Daily Attendance Form 0
Overtime Callout List.
CUE: If examinee indicates need to obtain these references, provide copies:
0 OP-TM-101-111-1001, Shift Manning Requirements.
Technical Specifications pages 6-1 and 6-2.
Examinee references Technical Specifications and/or OP-TM-101-111-1001, Shift Manning Requirements, to determine minimum shift manning requirements for current conditions.
Technical Specifications:
TS 6.2.2.2.a requirement:
0 Each on-duty shift shall be composed of at least the minimum shift crew composition shown on Table 6.201.
At least one licensed Reactor Operator shall be present in the control room when fuel is in the core.
Two licensed CROs must be on shift when Tave >2OO0F.
Two licensed CROs are required to be in the Control Room during scheduled reactor shutdown.
TS 6.2.2.2.b requirement:
0 Table 6.2-1 requirement:
0 TS 6.2.2.2.c requirement:
0 OP-TM-101-111-1001, Shift Manning Requirement:
Three CROs (at least 2 RO) must be on shift when RCS Temperature > Z O O O F.
0 I
2 11 1
0 LS-AA-119. Overtime Controls.
Examinee initiates action to comply with Tech Spec requirement for two licensed ROs.
Examinee determines three CROs are required, two of which must be RO licensed. One licensed CRO is required to be in the Control Room.
Examinee initiates action to comply with Tech Spec requirement for two licensed ROs.
Page 5 of 7
A. 1-2 Revision 1 05/12/2003 4
- 5
- 6 STEP Examinee seeks a replacement for the second licensed CRO position left vacant by Gorses situation.
Examinee calls the Operations Scheduler or directly references the Overtime Callout List to identify a replacement CRO to be called.
CUE: If examinee tries to call scheduler, inform examinee Ops Scheduler is U N AVAl LAB LE, CUE: Provide Examinee with 308 Weekly Schedule Daily Attendance Form Overtime Callout List.
~
Examinee references LS-AA-I 19, Overtime Controls, to evaluate callout restrictions.
NOTE: CRO is limited to working 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 consecutive days.
Examinee identifies next individual to be called to replace the CRO.
~~
STANDARD Examinee references OT callout and OT worked lists.
Examinee may select (CRO X) low man on overtime list for callout.
- The Examinee cancels the callout to CRO X, even though he is low man on the cumulative overtime list (due to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> worked in last 6 days)
Examinee selects CRO Y for callout due to overtime restrictions on CRO X.
s/u NOTE: **Examinee MAY use CRO X if Attachment 1 of LS-AA-119 is completed, authorizing deviation from Generic Letter GL 82-12 guidelines.
END TASK Page 6 of 7
REVISION 0
DATE P
04/12/2003
~~
05/12/2003 A. 1-2 Revision 1 0511 212003 JPM CHANGE HISTORY PAGE REFERENCE TITLE OP-TM-101-111-1001, Shift Manning Requirements.
Tech Spec Table 6.2-1.
LS-AA-119, Overtime Controls.
DESCRIPTION (Include AI # if Appropriate)
Original issue.
changed per NRC validation Page 7 of 7
Title CRO - SWITCHING AND TAGGING LOG SHIFT MANNING LOG Revision No.
33 Complete this log by indicating by name those Qualified individuals fulfilling the listed Shift Manning Duties. The CRO signature on the cover page indicates that the qualification requirements of the minimum shift manning has been verified and that personnel listed on the Fire Brigade are on the Fire Brigade Qualified Listing.
3 Control Room Operators >200°F At least 2 must have RO license if >200°F Only 2 CROs with minimum of 1 RO license required if ~200°F Designate resp. person for E-Plan notifications & Fire Brigade (3rd CRO or lac), if 3rd RO is not available, then designate and notify I&C or other qualified individual.
4 Auxiliary Operators required at all times.
(When >200 4 AOs required to satisfy AP 1029)
Emergency response assigned IAW OS-24 Attachment E.
Fire Brigade - Minimum of 5 members per AP 1029 (suggested manning) 1 Maintenance Foreman 2
2 A Auxiliary Operators 1
RadTech Maintenance (Electrical or Mechanical Discipline)
(Fire Brigade must have 2 qualified AOs as a minimum. AOs if available (must be extra) may fill Maint. slots if not also assigned as safe shutdown AO) m Supervisor - May be waived ~200°F by Director, FIRE BRIGADE/
Extra
FIRE BRIGADE LIST MEMBERS LEADERS ACON, KENNETH B.
ALTHOUSE, DAVID E.
BARONE, JOSEPH A.
BARRY, JAMES R.
BOOKS II, RICHARD C.
BUCHTER, DENNIS A.
DEMMY, MICHAEL D.
DOUGHERTY, DAN R.
ENDERS, JAMES C.
FELDENZER, RICHARD J.
FLOWERS, GREGORY S.
FUHRMAN, SCOlT M.
GINGRICH, RICHARD A.
HAHN, ROBERT E.
HOFFMAN, BRAD E.
KILSY, RONALD G.
KLEINFELTER, THOMAS K.
KNERR, DAVID C.
KOHL, HENRY M.
LEVENGOOD, JOHN P.
LUTZ, KEVIN E.
MULL, STEVEN L.
MURRAY, ROBERT J.
NOWAK, BRIAN RANDISI, JAMES W.
RIGANATI, PAUL A.
RINKER, CARL F.
WOLFORD, MICHAEL P.
321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 321 1 BAIR, DARREN K BENNETT SR, TIMOTHY J.
BRIGHTBILL, CRAIG A.
BROWN, LONNIE C.
COSAUGH, LARRY R.
CRAWFORD, ANDY M.
CRAWFORD, RICKY L.
DARRAH, WILLIAM A.
DUPES, JEFFREY K.
EPPINGER, KERRY A.
ESWORTHY, KATHY L.
FENNER, RANDY A.
FREY, BONNIE L.
GARMAN, COREY R.
GEARY, JAMES A.
HARMAN, KENNETH M.
HARPER, RICHARD R.
HENRY, RALPH H.
KILLEN, DAVID A.
MENSER, MICHAEL S.
MOORE, MICHAEL W.
ORNER, JACKIE PRICE, KEENAN D.
PUCCIO, ANTHONY Y RANK, EUGENE B.
REBER, ROY E.
REBO, RAY M.
SHEEHAN, JOSEPH F.
STAUFFER, KENNETH D.
TAFT, DAVID H TATEM, MELINDA D.
VIA, RICHARD C.
VULATIC, MICHAEL A.
WALMER, RAYMON 0 WEGRZYNIAK, JAMES WEIMER, TIMOTHY D.
WELSH, KEVIN WESTHAFER, EVELYN YOUNG, JACK R.
YOUNG, TROY D.
3222 3222 3224 3223 3224 3224 3224 3224 3222 3224 3224 3222 3222 3224 3223 3222 3224 3224 3224 3223 3224 3224 3224 3222 3224 3224 3222 3224 3223 3223 3224 3224 3224 3223 3222 3222 3222 3224 3224 3222 BAUMBACH, NED W.
BEAVER, JEFFREY A BOWMAN, GARY L.
DAVIS, BRETT A DEINER II, CARL E.
DI LELLO, STEVEN T.
DUNLAP JR, NORMAN F DURAN, RAFAEL A.
EAGLE, RICHARD E.
KLICK, MARK S.
KOLVA, JOHN J.
LEWIS, RICHARD W.
MARINKOV, MILTON MATEER, KEITH R.
MENSER, BARRIE L.
MUNZ, JOHN B.
RIDLEY, MICHAEL C.
ROETING, CHARLES J.
STEIN, JOHN G WELSH, GARY J.
WOLFE, GORDON R NO ADDITIONS UNLESS AUTHORIZED BY THE STATION FIRE MARSHAL.
THIS LIST IS EFFECTIVE AS OF 01/01/2003 AND REMAINS IN EFFECT UNTIL NEW LIST IS ISSUED.
3223 3223 3222 3222 3222 3223 3223 3223 3222 3223 3223 3223 3222 3222 3223 3223 3223 3223 3222 3223 3222
Overtime Callout List Overtime Charged This Quarter Rank Lowest Middle Name Overtime Hours Charged Phone CRO X 9
948-1 234 CRO Y 12 948-5678 I Hiahest I CRO Z I
14.5 I
948-6542 I
TMI SRO License Exam OW1 2/03 TMI-I OPERATOR TRAINING JOB PERFORMANCE MEASURE A.2 USE STATION DRAWINGS TO PREDICT IMPACT OF INSTRUMENT FAILURE Page 1 of 6
TASK TITLE:
USE STATION DRAWING TO PREDI A.2 Revision 1 05/12/2003 T IMPACT OF INSTRUMENT FAILURE TASK NUMBER:
3420070303 TIF: 2.2 KIA
REFERENCE:
System:
NA WA:
2.1.24 Rating (RO/SRO):
2.8/3.1 POSITION:
S R O N R O O N L O O EVALUATION METHOD:
PERFORM rn EVALUATION LOCATION:
SIMULATOR c]
SIMULATE 0 IN-PLANT 0 CONTROL ROOM 0 OTHER rn TASK STANDARDS:
Examinee identifies impact of isolating MU-42-FS on RC-P-1 D.
0 RC-P-1 D cannot be started from the Control Room.
APPROXIMATE COMPLETION TIME: 30 minutes TIME-CRITICAL TASK COMPLETION TIME:
NA minutes REQUIRED TOOLS OR MATERIALS:
208-1 13 Rev. 15.
SS-209-065, Rev. 9.
Marker to identify electrical contacts affected.
REFERENCES:
302-661, Rev.52.
208-1 13 Rev. 15.
SS-209-065, Rev. 9.
ALTERNATE PATH JPM? NO SIMULATOR SETUP: NA INITIALIZATION: NA EVENT TRIGGERS: N/A MALFUNCTIONS: N/A REMOTE FUNCTIONS: N/A OVERRIDES: N/A MONITOR: N/A Page 2 of 6
A.2 Revision 1 05/12/2003 READ TO STUDENT When I tell you to begin, you are to USE ELECTRICAL PRINTS TO PREDICT THE IMPACT THE CLEARANCE REQUEST (TO MECHANICALLY ISOLATE MU-42-FS, Total Seal Injection Flow Switch) ON OPERATION OF RC-P-1 D.
INITIAL CONDITIONS:
RCS heatup is in progress.
RC-P-1A and RC-P-1 B are operating.
RC-P-1 C and RC-P-1 D are not operating.
Intermediate Closed Cooling Pump IC-P-1 A is operating.
Operators are prepared to start RC-P-1 D.
A piping leak has identified at MU-42-FS.
Maintenance has submitted a Clearance Request that MECHANICALLY isolates MU-42-FS in order to terminate and repair the leak.
INITIATING CUE:
When I tell you to begin, you are to use electrical prints (208-1 13, Rev. 15, and 209-065, Rev. 9) to predict the impact of the clearance request on operation of RC-P-1 D. The clearance mechanically isolates MU-42-FS, Total Seal Injection Flow Switch. Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions.
ARE THERE ANY QUESTIONS?
TIME CRITICAL: NO Page 3 of 6
JPM INSTRUCTION SHEET Directions to Student:
When I tell you to begin, you are to USE ELECTRICAL PRINTS TO PREDICT THE IMPACT THE CLEARANCE REQUEST (TO MECHANICALLY ISOLATE MU42-FS, Total Seal Injection Flow Switch) ON OPERATION OF RC-P-1 D.
INITIAL CONDITIONS:
RCS heatup is in progress.
RC-P-1A and RC-P-1B are operating.
RC-P-1 C and RC-P-1 D are not operating.
Intermediate Closed Cooling Pump IC-P-1A is operating.
Operators are prepared to start RC-P-1 D.
A piping leak has identified at MU-42-FS.
Maintenance has submitted a Clearance Request that MECHANICALLY isolates MU-42-FS in order to terminate and repair the leak.
INITIATING CUE:
When I tell you to begin, you are to use electrical prints (208-1 13, Rev. 15, and 209-065, Rev. 9) to predict the impact of the clearance request on operation of RC-P-1 D. The clearance mechanically isolates MU42-FS, Total Seal Injection Flow Switch. Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions.
TIME CRITICAL: NO Page 4 of 6
A.2 Revision 1 05/12/2003
- Denotes Critical Elements
- Denotes Sequential Step STEP STANDARD SIU NOTE: Steps may be performed in any sequence.
CUE: Provide Examinee with the following tools:
0 Print 208-113 Rev. 15.
0 Print 209-065, Rev. 9.
0 Marker 4
5
- 6 Examinee obtains a copy of print 209-065 Auxiliary Relays of MU42-FS (LOW RC PP. TOTAL SEAL INJECTION FLOW).
Examinee circles affected flow switch and auxiliary relay contacts on print 209-065, in accordance with the initiating cue.
Examinee determines impact of low flow condition following isolation of the flow switch.
Examinee obtains a copy of print 208-1 10, RC Pump ID.
Examinee circles contacts affected by low flow condition following isolation of MU24-FS, in accordance with the initiating cue.
Examinee determines impact of low flow condition following mechanical isolation of the flow switch on RC-P-1 D operation.
Examinee obtains a copy of 209-065 Auxiliary Relays of MU42-FS (LOW RC PP. TOTAL SEAL INJECTION FLOW).
Examinee circles the following three contacts (associated with impact on RC-P-1 D) on print 209-065 affected by low flow condition at MU24-FS following isolation by Maintenance:
Examinee circles one contact operated directly from MU42-FS (labeled 8611 FS, low setpoint) in the center of the print.
Examinee circles two contacts operated by auxiliary relay 80WMU42-FS2 associated with RC-P-1 D (at bottom of the print).
NOTE: Examinee may circle additional contacts 0
0 associated with the other three RCPs.
Examinee may verbalize the following description of impact on print 209-065:
1.) MU42-FS low flow condition energizes auxiliary relays 80NMU42-FSI and 80XIMU42-FS2.
2.) When auxiliary relay 80WMU42-FS2 energizes:
RC-P-1 D start circuit contact (C31 to C3) opens.
RC-P-1 D trip circuit contact (PT to TI) closes.
0 Examinee obtains a copy of print 208-1 13 RC Pump ID.
Examinee circles the following two contacts on print 208-1 13:
0 0
Examinee circles one MU42-FS contact in RC-P-1 D start circuit.
Examinee may circle one additional MU42-FS contact in RC-P-1 D trip circuit.
Examinee describes impact of low flow condition following mechanical isolation of the flow switch on RC-P-1 D operation:
RC-P-1 D can not be started from the control room, due to failure of the low seal injection flow starting interlock.
0 END TASK Page 5 of 6
REVISION 0
1 DATE 04/12/2003 05/12/03 A.2 Revision 1 0511 212003 JPM CHANGE HISTORY PAGE REFERENCE TITLE 302-661, Rev.52.
208-1 13 Rev. 15.
SS-209-065, Rev. 9.
DESCRIPTION (Include AI # if Appropriate)
P Original issue.
incorporated NRC validation comments Page 6 of 6
A. 3 Revision 0 05/12/2003 TMI-I OPERATOR TRAINING JOB PERFORMANCE MEASURE A.3 LIQUID RELEASE PERMIT APPROVAL Page 1 of 6
A. 3 Revision 0 05/12/2003 TASK TITLE:
LIQUID RELEASE PERMIT APPROVAL TASK NUMBER:
068C010101 Initiate, make and complete a liquid waste release.
TIF: 2.5 KIA
REFERENCE:
System:
Generic WA:
2.3.6 Rating
2.1/3.1 POSITION:
SRO [XIRO 0 NLO 0 EVALUATION METHOD: PERFORM IXI SIMULATE 0 EVALUATION LOCATION: SIMULATOR IN-PLANT 0 CONTROL ROOM 0 OTHER IXI TASK STANDARDS: Examinee does NOT approve the liquid release, due to exceeding ODCM Calendar Quarter cumulative organ (Liver) dose limit of 1.5 Mrem.
APPROXIMATE COMPLETION TIME: 30 minutes TIME-CRITICAL TASK COMPLETION TIME: NA REQUIRED TOOLS OR MATERIALS:
Releasing Radioactive Liquid Waste, 661 0-ADM-4250.01, Rev. 16.
Offsite Dose Calculation Manual, 6610-PLN-4200.01, Rev 23.
REFERENCES:
Releasing Radioactive Liquid Waste, 661 0-ADM-4250.01, Rev. 16.
Offsite Dose Calculation Manual, 6610-PLN-4200.01, Rev 23.
ALTERNATE PATH JPM? NO SIMULATOR SETUP:
INITIALIZATION: NA EVENT TRIGGERS: NA MALFUNCTIONS: NA REMOTE FUNCTIONS: NA OVERRIDES: NA MONITOR: NA Page 2 of 6
A. 3 Revision 0 05/12/2003 When I tell you to begin, you are to (AS SHIFT MANAGER) REVIEW AND APPROVE A LIQUID RELEASE PERMIT IN ACCORDANCE WITH 6610-ADM4250.01, RELEASING RADIOACTIVE LIQUID WASTE. Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions. Perform procedure steps and make notifications as if you were actually performing the task.
INITIAL CONDITIONS:
The plant is stable at 100% power.
WDL-T-1 IA, Waste Evaporator Condensate Storage Tank, is isolated and "DO NOT OPERATE' tagged.
A Liquid Release Permit has been initiated for WDL-TI 1A.
WDL-TI 1A level is 5.8 feet.
The current time is 2000.
INITIATING CUE:
Review and approve the Liquid Release Permit for WDL-TI 1A in accordance with 6610-ADM-4250.01, Releasing Radioactive Liquid Waste.
ARE THERE ANY QUESTIONS?
TIME CRITICAL: NO Page 3 of 6
JPM INSTRUCTION SHEET DIRECTIONS TO STUDENT:
When I tell you to begin, you are to (AS SHIFT MANAGER) REVIEW AND APPROVE A LIQUID RELEASE PERMIT IN ACCORDANCE WITH 6610-ADM-4250.01, RELEASING RADIOACTIVE LIQUID WASTE. Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions. Perform procedure steps and make notifications as if you were actually performing the task.
INITIAL CONDITIONS:
The plant is stable at 100% power.
WDL-T-1 IA, Waste Evaporator Condensate Storage Tank, is isolated and "DO NOT OPERATE" tagged.
A Liquid Release Permit has been initiated for WDL-TI IA.
WDL-TI 1A level is 5.8 feet.
The current time is 2000.
INITIATING CUE:
As Shift Manager, review and approve the Liquid Release Permit for WDL-TI IA, in accordance with 6610-ADM-4250.01, releasing Radioactive Liquid Waste.
TIME CRITICAL: NO Page 4 of 6
A. 3 Revision 0 05/12/2003
- Denotes Critical Elements STEP STANDARD SIU INITIATING CUE: (AS SHIFT MANAGER) REVIEW AND APPROVE THIS LIQUID RELEASE PERMIT IN ACCORDANCE WITH 6610-ADM4250.01, RELEASING RADIOACTIVE LIQUID WASTE.
Accompanying documents are:
0 0
0 0
Dose Summary Report - Year-to-Date.
Dose Summary Report - Calendar Quarter to-Date.
Dose Summary Report - Month-to-Date.
Dose Summary Report for this release.
1 2
- 3
- 4 Examinee ascertains Shift Manager signature responsibilities and dose limits for liquid releases by referencing 661 0-ADM-4250.01, Releasing Radioactive Liquid Waste.
NOTE: Ofkite Dose Calculation Manual, 661 0-PLN-4200.01, may be referenced to ascertain dose limits for releasing radioactive liquid waste.
Examinee reviews Cumulative Dose Summary for the current year to verify projected doses for this release will not cause the station to exceed individual dose limits from radioactive materials in liquid effluents released to the site boundary.
Examinee reviews Cumulative Dose Summary for the current quarter to verify projected doses for this release will not cause the station to exceed individual dose limits from radioactive materials in liquid effluents released to the site boundary.
Examinee signs Form 1621-3 (line 30) to approve the release IAW 661 O-ADM-4250.01 step 4.1 0.4.
661 0-ADM-4250.01, Releasing Radioactive Liquid Waste, section 4.10.4, describes Shift Manager responsibilities.
6610-ADM4250.01, Releasing Radioactive Liquid Waste, section 3.2, describes quarterly and yearly dose limits for releasing radioactive liquid.
6610-PLN-4200.01, Offsite Dose Calculation Manual, section 2.2.1.1, describes quarterly and yearly dose limits for releasing radioactive liquid.
~~~
In accordance with 661 0-ADM4250.01, Releasing Radioactive Waste, section 3.2.b, during any calendar year, dose will be:
0 13 mrem to the whole body.
0 Dose will be 110 mrem to any organ.
Examinee determines that the calendar year dose limits will not be exceeded.
In accordance with 661 0-ADM4250.01, Releasing Radioactive Waste, section 3.2.a, during any Calendar Quarter, dose will be:
0 11.5 mrem to the whole body.
0 Dose will be 15 mrem to any organ.
Examinee determines that the projected whole body dose (1.67 mrem) WILL EXCEED the quarterly whole body dose limit (1.5 mrem).
The examinee DOES NOT SIGN Form 1621-3 to approve this release, due to exceeding total Offsite Dose Calculation Manual (ODCM) allowable dose for the calendar quarter.
END TASK Page 5 of 6
A. 3 Revision 0 05/12/2003 JPM CHANGE HISTORY PAGE DATE 511 212003 REFERENCE TITLE NA DESCRIPTION (Include AI # if Appropriate)
Initial issue.
Page 6 of 6
DOSE
SUMMARY
REPORT 10CFR50 DOSE REPORT FOR ADULT (MREM)
Release # 200XXX035 GENERATED: Today I
I I
I I
I I
CUMULATIVE DOSE
SUMMARY
Month (This Month) to Date Gamma Air GENERATED Today Beta Air Dose Due to Noble Gas Releases (MRAD)
Cum. Dose (Bound.)
Cum. Dose (Cr. Rec.)
Inhalation Meat Gr. Plane CowlMMl Vegetation Tot. Dose 4.91E-01 1.19E-01 O.OOE+OO 1.58E-03 2.68E-03 5.37E-03 9.24E-04 2.23E-04 00.00E+00 1 ME-03 2.77E-03 5.56E-03 Dose Due to Liquid Releases (MREM)
I Tot.Body I Liver I
Bone I
Thyroid I
Kidney I
Lung I
GI - LLI I Cum. Dose I
5.1E-01 I 1.36E+00 I 1.39E+00' I 5.38E-01 I
I.lIE+OO I 7.59E-01 I
6.05E-01 Includes Batch Releases 029 thru 035 8 Cont. Releases 540-542 Dose Due Part./lodine/Tritium Releases (MREM)
CUMULATIVE DOSE
SUMMARY
This Quarter - 2003 Gamma Air GENERATED Today Cum. Dose (Bound.)
Cum. Dose (Cr. Rec.)
Dose Due to Noble Gas Releases (MRAD)
Inhalation Meat Gr. Plane CowlMWl Vegetation Tot. Dose 8.91E-04 2.16E-04 O.OOE+OO 1.58E-03 2.68E-03 5.37E-03 9.24E-04 2.23E-04 O.OOE+OO 1.64E-03 2.77E-03 5.56E-03 Dose Due to Liquid Releases (MREM)
I Tot.Body I Liver I
Bone I
Thyroid I
Kidney I
Lung 1
GI - LLI I Cum.Dose I 1.67E+00 I 1.63E+00 I 1.39E+00 I 5.38E-01 I
1.11E+00 I 7.59E-01 I 6.05E-01 Includes Batch Releases 029 thru 035 (L Cont. Releases 540 thru 542
CUMULATIVE DOSE
SUMMARY
2003 Cum. Dose 5.03E-04 GENERATED Today 3.23E-04 Dose Due to Noble Gas Releases (MRAD)
Dose Due to Liquid Releases (MREM)
I Tot.Body I Liver I
Bone I
Thyroid I
Kidney I
Lung I
GI - LLI I Cum.Dose I 2.91E+00 I 2.79E+00 I 2.65E+OO I
I. ~ ~ E + O O I 1.24E+00 I 2.95E+00 I 2.15E+00 Includes Batch Releases 001 thru 035 & Cont. Releases 501 thru 624 Dose Due Part.llodine/Tritium Releases (MREM)
I Inhalation I Meat I
Gr. Plane I CowlMWl I Vegetation I Tot. Dose Cum. Dose (Bound.)
I 1.88E+00 I
4.77E-01 I 4.43E-08 I
3.51E+00 I 5.94E+00 I 1.91 E+OO
~~
~~~~
~
Cum. Dose (Cr. Rec.)
I 1.89E+00 I 4.82E-01 I 2.83E-08 I
3.54E+00 I 5.99E+00 I 1.91E+00 I
Includes Batch Releases 001 thru 014 & Cont. Releases 501 thru 614
TMI - Unit 1 Radiological Controls Procedure Title Number 661 0-ADM4250.01 Revision No.
EXHIBIT 4 (Example)
Form 1621-1 Releasing Radioactive Liquid Waste Page 1 of 5 16 OPERATIONS INPUT TO LIQUID RELEASE PERMIT (4) Release Number LZOOXXX035 (11 Datemime: 2 Days ~ ~ 0 1 1 1 0 0 Requester (Signature):
Shift Manager I
(signed)
(Shift Mgr.)
~
~~
~~
~
((3) Tank Put on Recirculation (min. of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)
Time: 1000 Date:s Davs no Tank Isolated and "Do Not Operate" Tagged:
Time: I100 Date:n Days ASO Tank Volume Ft. 5.8 gallons 4044 Recirc Time >40 Hours -;1:
Signed/Date Shift Manager/(Siclned)/ Dated Yesterday (32) (Record all start and stop date times)
Tank Level at Start of Release ft.
ga1.r Time Release Stopped Tank Level at End of Release ft.
ga1.L Time Date Tank Volume Released (Actual) gal.
Time Release Started MDCT Effluent Totalizer at Stop gal.
Time Date MDCT Effluent Totalizer at Start gal.
Total Time of Release Total Dilution Flow gal.
Minutes (33)
Actual Release Rate = Actual Gallons Released =
minutes gpm
((34)
Cancelled or Partial Release State reason this release was cancelled or only partially released:
135) Release data completed and chemistry notified of actual gallons released:
Signature Daterrime Shift Manager Datemime Shift Manager Datemime All data required on this form has been completed.
Completed Release Permit has been forwarded to Rad Eng.
'1 Tank level is read on WDL-u-132 for WDL-1-11A or WDL-u-I 33 for WDL-1-14 B. WDL-L&-126 may be used if primarv instruments are not available.
Releasing Radioactive Liquid Waste PH CONDUCTIVITY Form 1621-2 (Exam de) 5.39 4.5 - 9.5 (NOTE I) 2.22
< I O uMHO (NOTE 2)
Chemistry Data Sheet for Releasing Radioactive Liquid Waste Number 661 0-ADM4250.01 Revision No.
16 Page 2 of 5 (4) RELEASE NUMBER I
~ 2 0 0 ~ ~ x 0 3 5 I NOTE AFTER COMPLETION FORWARD THIS DATA SHEET ALONG WITH COPIES OF THE GAMMA AND TRITIUM ANALYSIS TO RADIOLOGICAL CONTROLS FOR INCLUSION IN THE RELEASE PERMIT.
SIGNATURE (PRINTEIGN)
(51 TANK RECIRCULATED 2 8 HRS.
BY: RM Pugliese I (signed) DATWIME Today I 0005 (61 RELEASE SAMPLE(S) COLLECTED BY: RM Pugliese I (signed) DATEKIME Today I 0010 (7)
RELEASE GAMMA SCAN BY: RM Pugliese I (signed) DATEKIME Today I0018 RELEASE TRITIUM ANALYSIS BY: RM Pugliese I (signed) DATElTlME Today I0050 WEEKLY COMPOSITE SAMPLES BY: RM Pugliese I (signed) DATElTlME Today I 0100 I I - - - - - -
I RESULT I
LIMIT II II BORON I
26 I
PPM II NOTE
- 1.
- 2.
The limit of 4.5 - 9.5 will ensure that the NPDES limit of 6 - 9 is not exceeded at the main station discharge to the Susquehanna River.
Must be 4 0 uMHO to consider water with pH less than 6 or greater than 9. If conductivity is > I O uMHO and pH is less than 6.0 or greater than 9.0, release must be approved by Chemistry Supervisor or his designee with a written evaluation attached to release form.
Number I
Radiological Controls Procedure Title I
TMI - Unit 1 I
661 0-ADM-4250.01 Revision No.
Releasing Radioactive Liquid Waste 16 Time for Release (30)
Release Information Completed By S. Edelman I (siqned)
Rad. Controls Tech. A (Sign)
Release Recommended By D. Viola I (siqned)
Group Rad. Controls Supervisor (Sign) 150 Release Approved By Shift Manager (Final Approval)
Instrument Readings:
Expected Reading 1231FR-84 2.7E+01 gpm (31 1 Release Data:
Reading at Reading After Reading After Reading After Reading After Start 1/4 Complete 1/2 Complete 3/4 Complete Release Comp.
(19)
(22)
WDL-V-257/RM-L6 Hi Radiation Interlock Test Sat.
FR-146 Alarm Setpoint at 7.2E+03 gpm FR-146 (Low MDCT Flow) Test Sat.
FR-84 Alarm Setpoint at 3.00E+01 gpm FR-84 (Hi Liq. Release Flow) Test Sat.
initials initials initials initials initials RM-L6 Operable per SP 1301 -1 (Check Source) initials
[25)RM-L6 1.06E+03cpm t19)FR-146 7.2E+03gpm I
[26)RM-L7 I
.OE+02 cpm
Form 16214 Release Number L200XXX035 t8)
Radiological Analyses Review by:
(91 Nuclides 1
(GRCS)
D. Viola I (sinned)
Datemime Today I AM (1 01 (111 (121 (1 41 (1 51 Specific (101 x (141 Controlling Activity Sensitivity of Monitor Specific Activity Effluent Conc.
Controlling RM-L6 to each
Response
pCi/ml pCi/ml Conc.
Nuclide (CPW Ce-141 Ce-I 44 CO-58 CO-60 cs-134 I
H-3 I
3.12E-01 I
2E-3.
I 1.56E+02 I I
3E-5.
5.8E7 3E-6.
1.I E7 2E-5.
1.2E8 3E-6.
1.9E8 9E-7.
2.5E8 Fe-59 1-1 31 Mn-54 Mo-99 Zn-65 I
cs-I 37 I
5.70E-07 I
1E-6.
I 5.70E-01 I 1.05E8 I
5.99E+01 1 E-5.
1.1E8 1 E-6.
1.1E8 3E-5.
1.I E8 2E-5.
1.5E7 5E-6.
5.4E7 I
I I
(131 Required D.F.
I CO-57 I
I 6E-5.
I I
9.5E7 I
(161 Monitored Response of RM-L6 Above Bkgd.
(17)
Dilution Factor Required Based on Boron =
26 PPM =
3.71 E+OI Record Results in Step t201 0.7 PPM
Number TMI - Unit 1 Radiological Controls Procedure Title Releasing Radioactive Liquid Waste 661 0-ADM4250.01 Revision No.
16 (18)
Contact Control Room Operator for following data Gorse D.
Name of CRO contacted
- a.
MDCT Flow 8.00E+03 gpm (must be >5000 gpm)
(19)
MINIMUM MDCT FLOW (0.9 x usable MDCT Flow from (181 a) =
Form 1621-3, (must be > 5000 GPM).
7.20E+03. Record on Step (191 on (20)
Radionuclide D.F. From (131 1.57E+02 Boron D.F. From (171 3.71E+01 MAXIMUM = 1.57E+02 DF (21)
RR max = Min MDCT from (191 7.20E+03
= 3.00E+01 R. R. MAX (5.55 to 30 gpm)
Required D.F. from (20) 1.57E+02 (22)
FR-84 ALARM SETPOINT = RR Max. Record this value at (221 on Form 1621-3.
(23)
RR Actual = 0.9 x RR max (3.OE+Ol) = 2.7E+Ol gpm Record this value at (5 to 27 gpm) (23) on Form 1621-3.
(24)
Estimated time of release = Est. Vol. to be released 4044 gal = 150 MIN RR Actual (from (23))2.70E+01 gpm Record this value at (24) on Form 1621-3.
(25)
Estimated Reading of RM-L6:
5.99E+Ol cpm (From (16)) + 1.00E+03 cpm (RM-L6 Background) = 1.06E+03 cpm Record this value on Step (251 on Form 1621-3.
(261 Estimated Reading of RM-L7:
5.99E+01 cpm (From (161) 1.57E+02
+
1.00E+02 cpm (RM-L7 Background) = 1.00E+02 cpm Dilution Factor (From (201)
Record this value on Step (261 on Form 1621-3.
TMI SRO License Exam 511 2/2003 TMI-1 OPERATOR TRAINING JOB PERFORMANCE MEASURE A.4 DAY I Page 1 of 6
A.4 Revision 1 0511 212003 TASK TITLE: EMERGENCY ACTION LEVEL IDENTIFICATION AND EVENT DECLARATION.
TASK NUMBER:
5001 045001 TIF: 3.35 KIA
REFERENCE:
System:
Generic WA:
2.4.41 Rating:
2.314.1 POSITION:
SROH ROO NLOO EVALUATION METHOD: PERFORM SIMULATE 0 EVALUATION LOCATION: SIMULATOR IN-PLANT CONTROL ROOM 0 OTHER H TASK STANDARDS: Examinee classifies the event as an ALERT under HA4, due to Non-Bomb Explosion inside the Vital Area, within 15 minutes of direction to classify the event, and then completes EP-MA-114-100 MAROG Notifications Attachment 1 (PNMD Notification Form) to support initial off-site notifications.
APPROXIMATE COMPLETION TIME: 20 minutes.
TIME-CRITICAL TASK COMPLETION TIME:
Classification: 15 minutes.
REQUIRED TOOLS OR MATERIALS:
EP-AA-I I 1 Emergency Classification and Protective Action Recommendations, Rev. 5.
Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station.
Table TMI 3-1, Emergency Action Level (EAL) Matrix.
EP-MA-114-100 MAROG Notifications Attachment 1 (PNMD Notification Form)
REFERENCES:
0 0
0 EP-AA-Ill Emergency Classification and Protective Action Recommendations, Rev. 5.
Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station.
Table TMI 3-1, Emergency Action Level (EAL) Matrix.
EP-MA-114-100 MAROG Notifications Attachment 1 (PNMD Notification Form)
ALTERNATE PATH JPM? NO SIMULATOR SETUP:
INITIALIZATION: NA EVENT TRIGGERS: NA MALFUNCTIONS: NA REMOTE FUNCTIONS: NA OVERRIDES: NA MONITOR: NA Page 2 of 6
A.4 Revision 1 0511 2/2003 READ TO STUDENT When I tell you to begin, you are to CLASSIFY THE EVENT, AND COMPLETE THE MAROG NOTIFICATIONS Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions.
Perform procedure steps to identify the EAL,classify the event, and complete the initial notifications form as if you were actually performing the task.
FORM, ATTACHMENT 1 (PNMD NOTIFICATION FORM) TO SUPPORT INITIAL OFF-SITE NOTIFICATIONS.
INITIAL CONDITIONS:
The plant was stable at 100% power with only one operating Feedwater Pump. ICs was in manual mode.
SEQUENCE OF EVENTS:
I. Selected RCS T-Hot instrument failed high, affecting ICs T-Ave indication and control.
- 2. A hydrogen gas leak reduced Main Generator gas pressure, requiring a forced load reduction to protect the generator. Because of an Integrated Control System malfunction the load reduction had to be performed manually.
- 3. Following the load reduction, protective relay operation transferred loads off the I A Auxiliary Transformer to 1 B Auxiliary Transformer and Emergency Generator EG-Y-1 B.
- 4. A major steam line rupture inside the Containment Building caused the reactor to trip.
- 6. Following isolation of feedwater sources to the affected OTSG, crew members were required take actions to prevent RCS reheat and re-pressurization.
- 8. All Emergency Feedwater Pumps started.
- 9. Control and termination of HPI flow was complicated by a stuck open High Pressure Injection valve.
Current Conditions:
Reactor is shutdown.
RCS is 45°F subcooled.
RB pressure peaked at 36 psig and is now at 6 psig.
OTSG 1A is isolated and depressurized.
HPI flow has been terminated.
Steam line RMS indications remain at background levels.
RCS pressure and temperature have been stabilized.
All Emergency feedwater Pumps are operating (on recirculation).
The current time is 1605.
Wind Speed 8 mph.
Wind direction is from 270 degrees.
The EOF is NOT activated.
INITIATING CUE:
Based on these conditions, classify this event and complete EP-MA-114-100 MAROG Notifications Attachment 1 (PNMD Notification Form) to support initial off-site notifications.
ARE THERE ANY QUESTIONS?
TIME CRITICAL: YES Page 3 of 6
JPM INSTRUCTION SHEET DIRECTIONS TO STUDENT:
When I tell you to begin, you are to CLASSIFY THE EVENT, AND COMPLETE THE MAROG NOTIFICATIONS Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions.
Perform procedure steps to identify the EAL,classify the event, and complete the initial notifications form as if you were actually performing the task.
INITIAL CONDITIONS:
The plant was stable at 100% power with only one operating Feedwater Pump. ICs was in manual mode.
SEQUENCE OF EVENTS:
FORM, ATTACHMENT 1 (PAIMD NOTIFICATION FORM) TO SUPPORT INITIAL OFF-SITE NOTIFICATIONS.
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
Selected RCS T-Hot instrument failed high, affecting ICs T-Ave indication and control.
A hydrogen gas leak reduced Main Generator gas pressure, requiring a forced load reduction to protect the generator. Because of an Integrated Control System malfunction the load reduction had to be performed manually.
Following the load reduction, protective relay operation transferred loads off the 1 A Auxiliary Transformer to 1 B Auxiliary Transformer and Emergency Generator EG-Y-I 6.
A major steam line rupture inside the Containment Building caused the reactor to trip.
Excessive OTSG heat transfer results in a core overcooling event, and ESAS actuation.
Following isolation of feedwater sources to the affected OTSG, crew members were required take actions to prevent RCS reheat and re-pressurization.
A and B OTSG steam line RMS indications and surveys were at background levels.
All Emergency Feedwater Pumps started.
Control and termination of HPI flow was complicated by a stuck open High Pressure Injection valve.
Current Conditions:
Reactor is shutdown.
RCS is 45°F subcooled.
RB pressure peaked at 36 psig and is now at 6 psig.
OTSG 1A is isolated and depressurized.
Steam line RMS indications remain at background levels.
HPI flow has been terminated.
RCS pressure and temperature have been stabilized.
All Emergency feedwater Pumps are operating (on recirculation).
The current time is 1605.
Wind Speed 8 mph.
Wind direction is from 270 degrees.
The EOF is NOT activated.
INITIATING CUE:
Based on these conditions, classify this event and complete EP-MA-114-100 MAROG Notifications Attachment I (PNMD Notification Form) to support initial off-site notifications.
ARE THERE ANY QUESTIONS?
TIME CRITICAL: YES Page 4 of 6
A.4 Revision 1 05/12/2003 STEP STANDARD SIU
- 2 3
Examinee obtains a copy of Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station and/or Table TMI 3-1, Emergency Action Level (EAL) Matrix, to identify the specific EAL(s) applicable to current conditions, and to classify the event.
The examinee declares the event and identifies himself as the ED. (Examinee may indicate to the examiner that they would make the announcement.)
Examinee completes MAROG Notifications form, Attachment 1 (PAIMD Notification Form) to support initial off-site notifications.
exists, specifically:
0 ALERT HA4, due to Non-Bomb Explosion inside the Vital Area.
The examinee declares the event and identifies himself as the ED. (Examinee may indicate to the examiner that they would make the announcement.)
NOTE: This declaration is required to be completed within 15 minutes from the time the examiner provides direction to classify the event.
Time of Declaration:
~
Examinee completes MAROG Notifications form, (PNMD Notification Form) to support initial off-site notifications.
Fields to be completed:
2 - Classification, Affected Unit, Initial Declaration 3 - Brief Non-Technical Description 4 - Non-Routine Radiological Release Status:
NO non-routine radiological release in progress (RMS normal) 0 5 - PAR, not applicable 6 - Meteorology:
Wind from 270 degrees at 8 miles per hour.
END TASK Page 5 of 6
A.4 Revision 1 0511 212003 REVISION 0
1 JPM CHANGE HISTORY PAGE 511 212003 DESCRIPTION (Include AI # if Appropriate)
Initial issue.
per NRC validation added RMS indications to support NO non-routine release call.
Page 6 of 6
TMI SRO License Exam 5/12/2003 TMI-I OPERATOR TRAINING JOB PERFORMANCE MEASURE A.4 Day 2 Page 1 of 6
A.4 Revision 1 0511 2/2003 TASK TITLE: EMERGENCY ACTION LEVEL IDENTIFICATION AND EVENT DECLARATION.
TASK NUMBER:
5001045001 TIF: 3.35 KIA
REFERENCE:
System:
Generic WA:
2.4.41 Rating:
2.3/4.1 POSITION:
S R O B R O O N L O O EVALUATION METHOD:
PERFORM SIMULATE 0 EVALUATION LOCATION: SIMULATOR IN-PLANT CONTROL ROOM OTHER TASK STANDARDS: Examinee classifies the event as an ALERT under FA1 within 15 minutes of direction to classify the event, and then completes EP-MA-114-100 MAROG Notifications Attachment 1 (PNMD Notification Form) to support initial off-site notifications.
APPROXIMATE COMPLETION TIME: 20 minutes.
TIME-CRITICAL TASK COMPLETION TIME:
Classification: 15 minutes.
REQUIRED TOOLS OR MATERIALS:
0 0
0 0
EP-AA-Ill Emergency Classification and Protective Action Recommendations, Rev. 5.
Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station.
Table TMI 3-1, Emergency Action Level (EAL) Matrix.
EP-MA-114-100 MAROG Notifications Attachment I (PNMD Notification Form)
REFERENCES:
0 0
0 0
EP-AA-111 Emergency Classification and Protective Action Recommendations, Rev. 5.
Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station.
Table TMI 3-1, Emergency Action Level (EAL) Matrix.
EP-MA-114-100 MAROG Notifications Attachment 1 (PNMD Notification Form)
ALTERNATE PATH JPM? NO SIMULATOR SETUP:
INITIALIZATION: NA EVENT TRIGGERS: NA MALFUNCTIONS: NA REMOTE FUNCTIONS: NA OVERRIDES: NA MONITOR: NA Page 2 of 6
A.4 Revision 1 05/12/2003 READ TO STUDENT When I tell you to begin, you are to CLASSIFY THE EVENT, AND COMPLETE THE MAROG NOTIFICATIONS FORM, ATTACHMENT 1 (PNMD NOTIFICATION FORM) TO SUPPORT INITIAL OFFSITE NOTIFICATIONS.
Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions.
Perform procedure steps to identify the EAL,classify the event, and complete the initial notifications form as if you were actually performing the task.
INITIAL CONDITIONS:
The plant was stable at 30% power with only one operating Feedwater Pump. EF-P-2A was 00s for bearing replacement. ICs was in AUTO mode.
SEQUENCE OF EVENTS:
- 1. Pressurizer level instrument failed low, requiring alternate input selection to return to auto makeup control.
- 2. The crew shifted operating MU pumps IAW procedures.
- 3. Seal injection valve MU-V-32 failed in auto, requiring manual mode to control seal injection flow.
- 5. CRD Diamond station fails to respond in auto, requiring ICs to be placed in manual for power reduction.
- 7. One train of ESAS fails to actuate, requiring component level manual actuation.
- 9. Crew minimizes SCM to between 30 and 70 degrees F, and commences plant cooldown.
- 10. All steam line RMS indications and surveys are elevated >2 times background levels, but below any alarm.
Current Conditions:
Reactor is shutdown.
RCS is 45°F subcooled.
The current time is 1710.
Wind Speed I 1 mph.
Wind direction is from 285.
The EOF is NOT activated.
INITIATING CUE:
Based on these conditions, classify this event and complete EP-MA-114-100 MAROG Notifications Attachment 1 (PNMD Notification Form) to support initial off-site notifications.
ARE THERE ANY QUESTIONS?
TIME CRITICAL: YES Page 3 of 6
JPM INSTRUCTION SHEET DIRECTIONS TO STUDENT:
When I tell you to begin, you are to CLASSIFY THE EVENT, AND COMPLETE THE MAROG NOTIFICATIONS Before you start, I will describe the general plant conditions, state the initiating cues, and answer any questions.
Perform procedure steps to identify the EAL,classify the event, and complete the initial notifications form as if you were actually performing the task.
FORM, ATTACHMENT 1 (PAIMD NOTIFICATION FORM) TO SUPPORT INITIAL OFF-SITE NOTIFICATIONS.
INITIAL CONDITIONS:
The plant was stable at 30% power with only one operating Feedwater Pump. EF-P-2A was 00s for bearing replacement. ICs was in AUTO mode.
SEQUENCE OF EVENTS:
- 1. Pressurizer level instrument failed low, requiring alternate input selection to return to auto makeup control.
- 2. The crew shifted operating MU pumps IAW procedures.
- 3. Seal injection valve MU-V-32 failed in auto, requiring manual mode to control seal injection flow.
- 5. CRD Diamond station fails to respond in auto, requiring ICs to be placed in manual for power reduction.
- 7. One train of ESAS fails to actuate, requiring component level manual actuation.
- 9. Crew minimizes SCM to between 30 and 70 degrees F, and commences plant cooldown.
- 10. All steam line RMS indications and surveys are elevated >2 times background levels, but below any alarm.
Current Conditions:
Reactor is shutdown.
RCS is 45°F subcooled.
The current time is 171 0.
Wind Speed 11 mph.
Wind direction is from 285.
The EOF is NOT activated.
INITIATING CUE:
Based on these conditions, classify this event and complete EP-MA-114-100 MAROG Notifications Attachment 1 (PAIMD Notification Form) to support initial off-site notifications.
TIME CRITICAL: YES Page 4 of 6
A.4 Revision 1 05/12/2003 STEP STANDARD Examinee obtains a copy of Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station and/or Table TMI 3-1, Emergency Action Level (EAL) Matrix, to identify the specific EAL(s) applicable to current conditions, and to classify the event.
SIU The examinee declares the event and identifies himself as the ED. (Examinee may indicate to the examiner that they would make the announcement.)
Examinee completes MAROG Notifications form, Attachment I (PAIMD Notification Form) to support initial off-site notifications.
The examinee determines that an ALERT condition exists, specifically:
0 ALERT FA1 Event, due to High Make Up Flow alarm (0-3-1) or leakrate
>I60 gpm ALERT FA1 Event, due to High Make Up Flow alarm (D-3-1) or leakrate
>I60 gpm AND Loss of inventory into OTSG OR 0
The examinee declares the event and identifies himself as the ED. (Examinee may indicate to the examiner that they would make the announcement.)
NOTE: This declaration is required to be completed within 15 minutes from the time the examiner provides direction to classify the event.
Time of Declaration:
Examinee completes MAROG Notifications form, (PNMD Notification Form) to support initial off-site notifications.
Fields to be completed:
2 - Classification, Affected Unit, Initial Declaration 3 - Brief Non-Technical Description 4 - Non-Routine Radiological Release Status:,
0 Airborne non-routine radiological release IS in progress.
5 - PAR, not applicable 6 - Meteorology:
Wind from 285 degrees at 11 miles per hour.
END TASK Page 5 of 6
REV1 SI ON 0
1 A.4 Revision 1 05/12/2003 JPM CHANGE HISTORY PAGE DATE I REFERENCE TITLE 5/12/2003 DESCRIPTION (Include AI # if Appropriate)
Initial issue.
per NRC validation added RMS indications to support non-routine release call.
Page 6 of 6