ML031710811

Final - Section a Operating

ML031710811
Person / Time
Site:	Three Mile Island
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 05112/03 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: 001C030101 TIF: 3.05 KIA

REFERENCE:

System: NA KIA: 2.1.25 Rating (RO/SRO): 2.8/3.1 POSITION: SROHROH NLOO 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 1103-15B, 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CRD Groups 1-4 are fully withdrawn.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Group 8 APSR positions: 30% withdrawn.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 1103-15B, 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

!s Sequential Step STEP STANDARD SIU 1 Examinee obtains a copy of OP 1103-15B, OP 1103-158, Estimated Critical Conditions, is Estimated Critical Conditions, to calculate a Level 2 procedure.

the ECB in accordance with guidance 0 HU-AA-101-101, Procedure Use and provided in Section 3.1, using Enclosure 1. 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.

2 Examinee reviews procedure Section 2.0, 0 HU-AA-101-101, Procedure Use and Limits And Precautions. Adherence, Section 4.1.6 requires the Procedure User to observe all Precautions.

Limitations and applicable Prerequisites.

3 Examinee begins implementation of Section 3.1, Estimated Critical Boron Concentration.

4 Examinee verifies data included on Enclosure 1 is correct, in accordance with Initial Conditions.

5 Using Figure 1, the examinee determines Expected value = +6.9% AWK.

fuel excess reactivity.

6 Using Figure 6, the examinee determines Interpolation between curves for 400 and 693 reactivity worth of Control Rod Groups 5-7 EFPD is required in order to determine value for at the desired critical position. 600 EFPD.

Expected value for 600 EFPD = -15% AWK.

7 Using Figure 2, the examinee determines Interpolation between curves for 400 and 672 reactivity worth of Control Rod Group 8 at EFPD is required in order to determine value for the desired critical position. 600 EFPD.

Expected value = -0.136% AWK.

8 Using Figure 4, the examinee determines 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 />.

Xenon reactivity at the time of startup.

Expected value = -3.6% AWK.

9 Using Figure 5, the examinee determines Interpolation between curves for 400 and 693 reactivity associated with samarium and EFPD is required in order to determine value for plutonium buildup after shutdown. 600 EFPD.

ExPected value = -0.033% AWK.

10 Examinee calculates boron reactivity worth Expected value = -1.631 % AWK.

required for criticality at the desired critical rod position.

11 Using Figure 3, the examinee determines Expected value = 127.5 ppm B/% AWK.

Hot Zero Power inverse boron reactivity worth.

Page 5 of 7

A.1-I 11.2.05.122 Revision 3 05/!/ZOO3

1. STEP STANDARD SIU 12 Using the inverse boron reactivity worth, Expected value = 208 ppm.

and the required boron reactivity, the examinee calculates the corrected Critical Boron Concentration

~ ~~

• I3 Using the mixed boron depletion correction Lower Acceatance Limit = 107 Dam.

factor (provided in the Initial Conditions), Expected Value = 210 ppm.

the examinee calculates the Estimated Upper Acceptance Limit = 313 ppm.

measured Critical Boron Concentration.

Basis for acceptance range:

Reference OP 1103-158,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 (+0.8)(127.5/0.99) = 210 f103 ppm.

0 Lower Acceptance Limit = 107 ppm.

0 Upper Acceptance Limit = 313 ppm.

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 position.

END TASK Page 6 of 7

A. 1-1 11.2.05.122 Revision 3 05112/2003 JPM CHANGE HISTORY PAGE DESCRIPTION (Include AI # if Appropriate)

Modified Bank JPM 11.2.05.122.

Page 7 of 7

TMI SRO License Exam 0912/03 TMI-I OPERATOR TRAINING JOB PERFORMANCE MEASURE A.1-2 Page 1 of 7

A. 1-2 Revision 1 05/12/2003 TASK TITLE: MAINTAIN MINIMUM SHIFT STAFFING, CONTROL OVERTIME 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: SROHROO NLOO 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 0511212003 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.

0 Third CRO John Doe is NOT licensed. He is in the Auxiliary Building performing an IndependentVerification 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.

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 1OO%, 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. e reminds you that he has a license restriction that requires him to wear corrective lenses. His backup eyeglasses are missing and cannot be located.

0 Third CRO John Doe is NOT licensed. He is in the Auxiliary Building performing an IndependentVerification 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

1. STEP STANDARD SIU 1 Examinee references Shift Manning Log to Examinee references Shift Manning Log and determine current shift manning status. determines that current staffing is acceptable.

1 C U I f s k e d , report that there are no other licensed CROs on site.

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 Technical Specifications pages 6-1 and 6-2.

OP-TM-101-111-1001, Shift Manning Requirements.

1 0 LS-AA-119. Overtime Controls.

Examinee determines three CROs are required, 2 Examinee references Technical Specifications and/or OP-TM-101-111- two of which must be RO licensed. One licensed 1001, Shift Manning Requirements, to CRO is required to be in the Control Room.

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.

TS 6.2.2.2.b requirement:

0 At least one licensed Reactor Operator shall be present in the control room when fuel is in the core.

Table 6.2-1 requirement:

0 Two licensed CROs must be on shift when Tave >2OO0F.

TS 6.2.2.2.c requirement:

0 Two licensed CROs are required to be in the Control Room during scheduled reactor shutdown.

OP-TM-101-111-1001, Shift Manning Requirement:

1 0 Three CROs (at least 2 RO) must be on shift when RCS Temperature > Z O O O F .

I Examinee initiates action to comply with Examinee initiates action to comply with Tech Spec Tech Spec requirement for two licensed requirement for two licensed ROs.

ROs.

Page 5 of 7

A. 1-2 Revision 1 05/12/2003

1. STEP

~~

STANDARD

-s/u 4 Examinee seeks a replacement for the Examinee references OT callout and OT worked second licensed CRO position left vacant lists.

by Gorses situation.

Examinee may select (CRO X) low man on Examinee calls the Operations Scheduler overtime list for callout.

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 UNAVAl LABLE, CUE: Provide Examinee with 308 Weekly Schedule Daily Attendance Form Overtime Callout List.

~

• 5 Examinee references LS-AA-I 19, **The Examinee cancels the callout to CRO X, Overtime Controls, to evaluate callout even though he is low man on the cumulative restrictions. 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)

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.

• 6 Examinee identifies next individual to be Examinee selects CRO Y for callout due to called to replace the CRO. overtime restrictions on CRO X.

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

A. 1-2 Revision 1 0511212003 JPM CHANGE HISTORY PAGE REVISION DATE REFERENCE DESCRIPTION TITLE (Include AI # if Appropriate)

P 0 04/12/2003 OP-TM-101-111-1001, Shift Original issue.

Manning Requirements.

Tech Spec 6.2.2.2.

Tech Spec Table 6.2-1.

~~

LS-AA-119, Overtime Controls.

05/12/2003 changed per NRC validation Page 7 of 7

Title Revision No.

CRO - SWITCHING AND TAGGING LOG 33 SHIFT MANNING LOG 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.

m Supervisor May be waived ~200°Fby Director, 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 FIRE BRIGADE/

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 >2004 AOs required to satisfy AP 1029)

• Extra

• Emergency response assigned IAW OS-24 Attachment E.

Fire Brigade - Minimum of 5 members per AP 1029 (suggested manning) 1 Maintenance Foreman 2 Maintenance (Electrical or Mechanical Discipline) 2 A Auxiliary Operators 1 RadTech (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)

FIRE BRIGADE LIST MEMBERS LEADERS ACON, KENNETH B. 321 1 BAIR, DARREN K 3222 BAUMBACH, NED W. 3223 ALTHOUSE, DAVID E. 321 1 BENNETT SR, TIMOTHY J. 3222 BEAVER, JEFFREY A 3223 BARONE, JOSEPH A. 321 1 BRIGHTBILL, CRAIG A. 3224 BOWMAN, GARY L. 3222 BARRY, JAMES R. 321 1 BROWN, LONNIE C. 3223 DAVIS, BRETT A 3222 BOOKS II, RICHARD C. 321 1 COSAUGH, LARRY R. 3224 DEINER II, CARL E. 3222 BUCHTER, DENNIS A. 321 1 CRAWFORD, ANDY M. 3224 DI LELLO, STEVEN T. 3223 DEMMY, MICHAEL D. 321 1 CRAWFORD, RICKY L. 3224 DUNLAP JR, NORMAN F 3223 DOUGHERTY, DAN R. 321 1 DARRAH, WILLIAM A. 3224 DURAN, RAFAEL A. 3223 ENDERS, JAMES C. 321 1 DUPES, JEFFREY K. 3222 EAGLE, RICHARD E. 3222 FELDENZER, RICHARD J. 321 1 EPPINGER, KERRY A. 3224 KLICK, MARK S. 3223 FLOWERS, GREGORY S. 321 1 ESWORTHY, KATHY L. 3224 KOLVA, JOHN J. 3223 FUHRMAN, SCOlT M. 321 1 FENNER, RANDY A. 3222 LEWIS, RICHARD W. 3223 GINGRICH, RICHARDA. 321 1 FREY, BONNIE L. 3222 MARINKOV, MILTON 3222 HAHN, ROBERT E. 321 1 GARMAN, COREY R. 3224 MATEER, KEITH R. 3222 HOFFMAN, BRAD E. 321 1 GEARY, JAMES A. 3223 MENSER, BARRIE L. 3223 KILSY, RONALD G. 321 1 HARMAN, KENNETH M. 3222 MUNZ, JOHN B. 3223 KLEINFELTER,THOMAS K. 321 1 HARPER, RICHARD R. 3224 RIDLEY, MICHAEL C. 3223 KNERR, DAVID C. 321 1 HENRY, RALPH H. 3224 ROETING, CHARLES J. 3223 KOHL, HENRY M. 321 1 KILLEN, DAVID A. 3224 STEIN, JOHN G 3222 LEVENGOOD, JOHN P. 321 1 MENSER, MICHAEL S. 3223 WELSH, GARY J. 3223 LUTZ, KEVIN E. 321 1 MOORE, MICHAEL W. 3224 WOLFE, GORDON R 3222 MULL, STEVEN L. 321 1 ORNER, JACKIE 3224 MURRAY, ROBERT J. 321 1 PRICE, KEENAN D. 3224 NOWAK, BRIAN 321 1 PUCCIO, ANTHONY Y 3222 RANDISI, JAMES W. 321 1 RANK, EUGENE B. 3224 RIGANATI, PAUL A. 321 1 REBER, ROY E. 3224 RINKER, CARL F. 321 1 REBO, RAY M. 3222 WOLFORD, MICHAEL P. 321 1 SHEEHAN, JOSEPH F. 3224 STAUFFER, KENNETH D. 3223 TAFT, DAVID H 3223 TATEM, MELINDA D. 3224 VIA, RICHARD C. 3224 VULATIC, MICHAEL A. 3224 WALMER, RAYMON 0 3223 WEGRZYNIAK, JAMES 3222 WEIMER, TIMOTHY D. 3222 WELSH, KEVIN 3222 WESTHAFER, EVELYN 3224 YOUNG, JACK R. 3224 YOUNG, TROY D. 3222 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.

Overtime Callout List Overtime Charged This Quarter Rank Name Overtime Hours Charged Phone Lowest CRO X 9 948-1234 Middle 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

A.2 Revision 1 05/12/2003 TASK TITLE: USE STATION DRAWING TO PREDI 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: SRONROO NLOO EVALUATION METHOD: PERFORM rn SIMULATE 0 EVALUATION LOCATION: SIMULATOR c] IN-PLANT 0 CONTROL ROOM 0 OTHER rn TASK STANDARDS:

Examinee identifies impact of isolating MU-42-FS on RC-P-1D.

0 RC-P-1D cannot be started from the Control Room.

APPROXIMATE COMPLETION TIME: 30 minutes TIME-CRITICAL TASK COMPLETION TIME: NA minutes REQUIRED TOOLS OR MATERIALS:

208-113 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-1D.

INITIAL CONDITIONS:

RCS heatup is in progress.

RC-P-1A and RC-P-1B are operating.

RC-P-1C and RC-P-1D are not operating.

Intermediate Closed Cooling Pump IC-P-1A is operating.

Operators are prepared to start RC-P-1D.

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 (208-113, Rev. 15, and 209-065, Rev. 9) to predict the impact of the clearance request on operation of RC-P-1D. 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-1D.

INITIAL CONDITIONS:

RCS heatup is in progress.

RC-P-1A and RC-P-1B are operating.

RC-P-1C and RC-P-1D are not operating.

Intermediate Closed Cooling Pump IC-P-1A is operating.

Operators are prepared to start RC-P-1D.

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 (208-113, Rev. 15, and 209-065, Rev. 9) to predict the impact of the clearance request on operation of RC-P-1D. 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

1. Denotes Sequential Step

1. 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 Examinee obtains a copy of print 209-065 Examinee obtains a copy of 209-065 Auxiliary Auxiliary Relays of MU42-FS (LOW RC Relays of MU42-FS (LOW RC PP. TOTAL SEAL PP. TOTAL SEAL INJECTION FLOW). INJECTION FLOW).

Examinee circles affected flow switch and Examinee circles the following three contacts auxiliary relay contacts on print 209-065, in (associated with impact on RC-P-1D) on print accordance with the initiating cue. 209-065 affected by low flow condition at MU24-FS following isolation by Maintenance:

0 Examinee circles one contact operated directly from MU42-FS (labeled 8611FS, low setpoint) in the center of the print.

0 Examinee circles two contacts operated by auxiliary relay 80WMU42-FS2 associated with RC-P-1D (at bottom of the print).

NOTE: Examinee may circle additional contacts associated with the other three RCPs.

Examinee determines impact of low flow Examinee may verbalize the following description condition following isolation of the flow of impact on print 209-065:

switch. 1.) MU42-FS low flow condition energizes auxiliary relays 80NMU42-FSI and 80XIMU42-FS2.

2.) When auxiliary relay 80WMU42-FS2 energizes:

RC-P-1D start circuit contact (C31 to C3) opens.

0 RC-P-1D trip circuit contact (PT to T I )

closes.

4 Examinee obtains a copy of print 208-1 10, Examinee obtains a copy of print 208-113 RC RC Pump ID. Pump ID.

5 Examinee circles contacts affected by low Examinee circles the following two contacts on flow condition following isolation of print 208-113:

MU24-FS, in accordance with the initiating 0 Examinee circles one MU42-FS contact in cue. RC-P-1D start circuit.

0 Examinee may circle one additional MU42-FS contact in RC-P-1D trip circuit.

• 6 Examinee determines impact of low flow Examinee describes impact of low flow condition condition following mechanical isolation of following mechanical isolation of the flow switch on the flow switch on RC-P-1D operation. RC-P-1D operation:

0 RC-P-1D can not be started from the control room, due to failure of the low seal injection flow starting interlock.

END TASK Page 5 of 6

A.2 Revision 1 0511212003 JPM CHANGE HISTORY PAGE REVISION DATE REFERENCE DESCRIPTION TITLE (Include AI # if Appropriate)

P 0 04/12/2003 302-661,Rev.52. Original issue.

208-113 Rev. 15.

SS-209-065,Rev. 9.

05/12/03 incorporated NRC validation comments 1

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, 6610-ADM-4250.01, Rev. 16.

Offsite Dose Calculation Manual, 6610-PLN-4200.01, Rev 23.

REFERENCES:

Releasing Radioactive Liquid Waste, 6610-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-1IA, 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 INSTRUCTIONSHEET 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

1. 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 -

Dose Summary Report Year-to-Date.

0 -

Dose Summary Report Calendar Quarter to-Date.

0 -

Dose Summary Report Month-to-Date.

0 Dose Summary Report for this release.

1 Examinee ascertains Shift Manager 6610-ADM-4250.01, Releasing Radioactive Liquid signature responsibilities and dose limits Waste, section 4.10.4, describes Shift Manager for liquid releases by referencing 6610- responsibilities.

ADM-4250.01, Releasing Radioactive Liquid Waste. 6610-ADM4250.01, Releasing Radioactive Liquid Waste, section 3.2, describes quarterly and yearly NOTE: Ofkite Dose Calculation Manual, dose limits for releasing radioactive liquid.

6610-PLN-4200.01, may be referenced to ascertain dose limits for releasing 6610-PLN-4200.01, Offsite Dose Calculation radioactive liquid waste. Manual, section 2.2.1.1, describes quarterly and yearly dose limits for releasing radioactive liquid.

~~~

2 Examinee reviews Cumulative Dose In accordance with 6610-ADM4250.01, Releasing Summary for the current year to verify Radioactive Waste, section 3.2.b, during any projected doses for this release will not calendar year, dose will be:

cause the station to exceed individual 0 13 mrem to the whole body.

dose limits from radioactive materials in 0 Dose will be 110 mrem to any organ.

liquid effluents released to the site boundary. Examinee determines that the calendar year dose limits will not be exceeded.

• 3 Examinee reviews Cumulative Dose In accordance with 6610-ADM4250.01, Releasing Summary for the current quarter to verify Radioactive Waste, section 3.2.a, during any projected doses for this release will not Calendar Quarter, dose will be:

cause the station to exceed individual 0 11.5 mrem to the whole body.

dose limits from radioactive materials in 0 Dose will be 15 mrem to any organ.

liquid effluents released to the site boundary. Examinee determines that the projected whole body dose (1.67 mrem) WILL EXCEED the quarterly whole body dose limit (1.5 mrem).

• 4 Examinee signs Form 1621-3 (line 30) to The examinee DOES NOT SIGN Form 1621-3 to approve the release IAW 661O-ADM- approve this release, due to exceeding total Offsite 4250.01 step 4.10.4. 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 REFERENCE DESCRIPTION TITLE (Include AI # if Appropriate) 511212003 NA 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 GENERATED

SUMMARY

Today Month (This Month) to Date Dose Due to Noble Gas Releases (MRAD)

Gamma Air Beta Air 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)

Inhalation Meat Gr. Plane CowlMMl Vegetation Tot. Dose Cum. Dose (Bound.) 4.91E-01 1.19E-01 O.OOE+OO 1.58E-03 2.68E-03 5.37E-03 Cum. Dose (Cr. Rec.) 9.24E-04 2.23E-04 00.00E+00 1ME-03 2.77E-03 5.56E-03

CUMULATIVE DOSE

SUMMARY

GENERATED This Quarter 2003- Today Dose Due to Noble Gas Releases (MRAD)

Gamma Air 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 Inhalation Meat Gr. Plane CowlMWl Vegetation Tot. Dose Cum. Dose (Bound.) 8.91E-04 2.16E-04 O.OOE+OO 1.58E-03 2.68E-03 5.37E-03 Cum. Dose (Cr. Rec.) 9.24E-04 2.23E-04 O.OOE+OO 1.64E-03 2.77E-03 5.56E-03

CUMULATIVE DOSE

SUMMARY

GENERATED 2003 Today Dose Due to Noble Gas Releases (MRAD)

Cum. Dose 5.03E-04 3.23E-04 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 OI 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/TritiumReleases (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 1.91E+OO I 1.89E+00 I 4.82E-01 I 2.83E-08 I 3.54E+00 I 5.99E+00 I I

~~ ~~~~ ~

Cum. Dose (Cr. Rec.) 1.91E+00 Includes Batch Releases 001 thru 014 & Cont. Releases 501 thru 614

Number TMI - Unit 1 Radiological Controls Procedure 6610-ADM4250.01 Title Revision No.

Releasing Radioactive Liquid Waste 16 EXHIBIT 4 Page 1 of 5 Form 1621-1 (Example)

OPERATIONS INPUT TO LIQUID RELEASE PERMIT (4) Release Number LZOOXXX035 (11 Datemime: 2 Days ~ ~ 0 1 1 1 0Requester 0 (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 >40Hours -;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 All data required on this form has been completed.

Shift Manager Datemime Completed Release Permit has been forwarded to Rad Eng.

Shift Manager Datemime

'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.

Number 6610-ADM4250.01 Revision No.

Releasing Radioactive Liquid Waste 16 Form 1621-2 Page 2 of 5 (Examde)

Chemistry Data Sheet for Releasing Radioactive Liquid Waste (4) RELEASE NUMBER I ~200~~x035 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 I0005 (61 RELEASE SAMPLE(S) COLLECTED BY: RM Pugliese I(signed) DATEKIME Today I0010 (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 I0100 II------ I RESULT I LIMIT I PH 5.39 4.5 - 9.5 (NOTE I)

CONDUCTIVITY 2.22 < I O uMHO (NOTE 2)

I BORON I 26 I PPM I NOTE

1. 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.

2. 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.

I TMI - Unit 1 II Number Radiological Controls Procedure 6610-ADM-4250.01 Title Revision No.

Releasing Radioactive Liquid Waste 16 Time for Release 150 (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)

Release Approved By Shift Manager (Final Approval)

(31 1 Release Data:

WDL-V-257/RM-L6 Hi Radiation Interlock Test Sat. initials (19) FR-146 Alarm Setpoint at 7.2E+03 gpm initials FR-146 (Low MDCT Flow) Test Sat. initials (22) FR-84 Alarm Setpoint at 3.00E+01 gpm initials FR-84 (Hi Liq. Release Flow) Test Sat. initials RM-L6 Operable per SP 1301-1 (Check Source) initials Instrument Readings: Reading at Reading After Reading After Reading After Reading After Expected Reading Start 1/4 Complete 1/2 Complete 3/4 Complete Release Comp.

1231FR-84 2.7E+01gpm I

[25)RM-L6 1.06E+03cpm t19)FR-146 7.2E+03gpm

[26)RM-L7 I.OE+02 cpm

Form 16214 Release Number L200XXX035 t8) Radiological Analyses Review by:

(91 (101 (111 (GRCS)

Datemime (121 D. Viola I(sinned)

Today IAM (141 (151 1

Specific (101 x (141 Controlling Activity Sensitivity of Monitor Specific Activity Effluent Conc. Controlling RM-L6 to each Response Nuclides pCi/ml pCi/ml Conc. Nuclide (CPW I H-3 I 3.12E-01 I 2E-3. I 1.56E+02 I I Ce-141 3E-5. 5.8E7 Ce-I 44 3E-6. 1.IE7 CO-58 2E-5. 1.2E8 CO-60 3E-6. 1.9E8 cs-134 9E-7. 2.5E8 I cs-I 37 I 5.70E-07 I 1E-6. I 5.70E-01 I 1.05E8 I 5.99E+01 Fe-59 1E-5. 1.1E8 1-131 1E-6. 1.1E8 Mn-54 3E-5. 1.I E8 Mo-99 2E-5. 1.5E7 Zn-65 5E-6. 5.4E7 I CO-57 I I 6E-5. I I 9.5E7 I I I I (131 (161 Required Monitored Response of D.F. 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 6610-ADM4250.01 Title Revision No.

Releasing Radioactive Liquid Waste 16 (18) Contact Control Room Operator for following data Gorse D. Name of CRO contacted

a. MDCT Flow 8.00E+03 gpm (must be >5000gpm)

(19) MINIMUM MDCT FLOW (0.9 x usable MDCT Flow from (181 a) = 7.20E+03 . Record on Step (191 on Form 1621-3, (must be > 5000 GPM).

(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 5112/2003 TMI-1 OPERATOR TRAINING JOB PERFORMANCE MEASURE A.4 DAY I Page 1 of 6

A.4 Revision 1 0511212003 TASK TITLE: EMERGENCY ACTION LEVEL IDENTIFICATION AND EVENT DECLARATION.

TASK NUMBER: 5001045001 TIF:3.35 KIA

REFERENCE:

System: Generic WA: 2.4.41 Rating: 2.314.1 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 EP-AA-Ill Emergency Classification and Protective Action Recommendations, Rev. 5.

0 Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station.

Table TMI 3-1, Emergency Action Level (EAL) Matrix.

0 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 05112/2003 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 OFF-SITE 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:

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 IA Auxiliary Transformer to 1B Auxiliary Transformer and Emergency Generator EG-Y-1B.

4. A major steam line rupture inside the Containment Building caused the reactor to trip.

5. Excessive OTSG heat transfer results in a core overcooling event, and ESAS actuation.

6. Following isolation of feedwater sources to the affected OTSG, crew members were required take actions to prevent RCS reheat and re-pressurization.

7. A and B OTSG steam line RMS indications and surveys were at background levels.

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 NotificationsAttachment 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 FORM, ATTACHMENT 1 (PAIMD NOTIFICATION FORM) TO SUPPORT INITIAL OFF-SITE 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:

1. 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 1A Auxiliary Transformer to 1B Auxiliary Transformer and Emergency Generator EG-Y-I 6.

4. A major steam line rupture inside the Containment Building caused the reactor to trip.

5 . Excessive OTSG heat transfer results in a core overcooling event, and ESAS actuation.

6. Following isolation of feedwater sources to the affected OTSG, crew members were required take actions to prevent RCS reheat and re-pressurization.

7 . Aand B OTSG steam line RMS indications and surveys were at background levels.

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.

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

1. STEP STANDARD SIU Examinee obtains a copy of Exelon Nuclear Radiological Emergency Plan exists, specifically:

Annex for Three Mile Island (TMI) Station 0 ALERT HA4, due to Non-Bomb Explosion and/or Table TMI 3-1, Emergency Action inside the Vital Area.

Level (EAL) Matrix, to identify the specific EAL(s) applicable to current conditions, and to classify the event.

• 2 The examinee declares the event and The examinee declares the event and identifies identifies himself as the ED. (Examinee himself as the ED. (Examinee may indicate to the may indicate to the examiner that they examiner that they would make the would make the announcement.) announcement.)

NOTE: This declaration is requiredto be completed within 15 minutes from the time the examiner provides direction to classify the event.

Time of Declaration:

~

3 Examinee completes MAROG Examinee completes MAROG Notifications form, Notifications form, Attachment 1 (PAIMD Attachment 1 (PNMD Notification Form) to support Notification Form) to support initial off-site initial off-site notifications.

notifications. Fields to be completed:

2 - Classification, Affected Unit, Initial Declaration 3 - Brief Non-Technical Description 4 - Non-Routine Radiological Release Status:

0 NO non-routine radiological release in progress (RMS normal) 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 JPM CHANGE HISTORY PAGE REVISION DESCRIPTION (Include AI # if Appropriate) 0 Initial issue.

1 511212003 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 05112/2003 TASK TITLE: EMERGENCY ACTION LEVEL IDENTIFICATIONAND EVENT DECLARATION.

TASK NUMBER: 5001045001 TIF: 3.35 KIA

REFERENCE:

System: Generic WA: 2.4.41 Rating: 2.3/4.1 POSITION: SROB ROO NLOO 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 EP-AA-Ill Emergency Classification and Protective Action Recommendations, Rev. 5.

0 Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station.

0 Table TMI 3-1, Emergency Action Level (EAL) Matrix.

0 EP-MA-114-100 MAROG Notifications Attachment I(PNMD Notification Form)

REFERENCES:

0 EP-AA-111 Emergency Classification and Protective Action Recommendations, Rev. 5.

0 Exelon Nuclear Radiological Emergency Plan Annex for Three Mile Island (TMI) Station.

0 Table TMI 3-1, Emergency Action Level (EAL) Matrix.

0 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.

4. Greater than 1 GPM OTSG tube leak occurs, and crew commences plant shutdown IAW EOP-005.

5. CRD Diamond station fails to respond in auto, requiring ICs to be placed in manual for power reduction.

6. Large break OTSG tube rupture occurs, requiring HPI and Rx trip.

7. One train of ESAS fails to actuate, requiring component level manual actuation.

8. Crew performs post trip response IAW the EOPs.

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 NotificationsAttachment 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 FORM, ATTACHMENT 1 (PAIMD NOTIFICATION FORM) TO SUPPORT INITIAL OFF-SITE 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.

4. Greater than IGPM OTSG tube leak occurs, and crew commences plant shutdown IAW EOP-005.

5 . CRD Diamond station fails to respond in auto, requiring ICs to be placed in manual for power reduction.

6. Large break OTSG tube rupture occurs, requiring HPI and Rx trip.

7. One train of ESAS fails to actuate, requiring component level manual actuation.

8. Crew performs post trip response IAW the EOPs.

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 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

1. STEP STANDARD SIU Examinee obtains a copy of Exelon The examinee determines that an ALERT condition Nuclear Radiological Emergency Plan exists, specifically:

Annex for Three Mile Island (TMI) Station 0 ALERT FA1 Event, due to High Make and/or Table TMI 3-1, Emergency Action Up Flow alarm (0-3-1) or leakrate Level (EAL) Matrix, to identify the specific >I60 gpm EAL(s) applicable to current conditions, OR and to classify the event. 0 ALERT FA1 Event, due to High Make Up Flow alarm (D-3-1) or leakrate

>I60 gpm AND Loss of inventory into OTSG The examinee declares the event and The examinee declares the event and identifies identifies himself as the ED. (Examinee himself as the ED. (Examinee may indicate to the may indicate to the examiner that they examiner that they would make the would make the announcement.) 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 Examinee completes MAROG Notifications form, Notificationsform, Attachment I(PAIMD Attachment 1 (PNMD Notification Form) to support Notification Form) to support initial off-site initial off-site notifications.

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

A.4 Revision 1 05/12/2003 JPM CHANGE HISTORY PAGE REV1SION DATE I REFERENCE TITLE DESCRIPTION (Include AI # if Appropriate) 0 Initial issue.

1 5/12/2003 per NRC validation added RMS indications to support non-routine release call.

Page 6 of 6