ML20211G033
| ML20211G033 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/29/1997 |
| From: | Curley V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9710010391 | |
| Download: ML20211G033 (700) | |
Text
{{#Wiki_filter:( 3 S ptember 29, 1997 NOTE T0: NRC Document Control Desk Mail Stop 0-5-D-24 FROM: - ho#I o a Ie n . Lic nsing Assistant Opera';ing Licensig" Branch, R
SUBJECT:
OPERATOR LICENSING EXAMINATION ADMINISTERED ON June 9-12. 1997 , AT flaine Yankee , DOCKET #50- 309 On Junc 9-12. 1997 Operator Licensing Examinations were administered at the referenced facility. Attached, you will find the following informatial for processing through NUDOCS and distribution to the NRC staff, including the NRC PDR: Item #1 - a) Facility submitted outline and initial exam submittal, designated for distribution under RIDS Code A070. b) As given operating examination. designated for distribution under RIDS Code A070. Item #2 - Examination Report with the as given written examination attached, designated for distribution under RIDS Code IE42. \ V
)
6* a ES-301 Administrativo Topics Outline Form ES-301 1 [
.,- Facility: Maine Yankee Date of Examination: June 9-12.1997 Exam level (Circle): RO /SRO (1) /Mperating Test No.:
A.1 Conduct of Generic 2.4.28 (2.3/3.3) SEO-0303-2 Operations Code Red FEMCO notmcation. Generic 2.1.5 (2.3/3.4) SNO-0302-10 What is the minimum operations shift stamng compliment required by Maine Yankee procedures. Generic 2.2.11 (2.5/3.4) GA-0302-1 Intent Change to a procedure Generic 2.2.20 (2.6/3.5) SURV 0301-3; SNO-0303-8 Required ventilation lineup in the Fuel Building during fuel movement. A.2 Equipment Generic 2.2.13 (3.6/3.8) Control JPM New Tagging a Safety Class Component. (N)(C)(S) A.3 Radiation Generic 2.3 2.3/2.5) JPM Ne $. '--- ' [ e of* fcHret. S cW(N)(P) (X M 4NS Control v A.4 Emergency Generic 2.4.3F{2.214.0) Plan JPM-AD-0901-2 Implementing E-Plan Due to Loss of MCB Annunciators. -
, (D)(T)(P or S)
Put necessary abbreviations here: ExOmination Standards Rev. 8, PUBLIC 4
+
i v' q0
SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #1 QUESTION: What does a " Code Red' FEMCO notification from Security mean? - ANSWER: That an armed intruder is inside the protected area. SATISFACTORY: YES NO
REFERENCES:
AOP 2 51 TASK IMPORTANCE: 2.3/3.3 TASK NUMBER: KIA Generic 2.4.28 LEARNING OBJECTIVE: SEO-0303-2 TRAINEE ANSWER / COMMENTS: m
9 SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS
- QUESTION #1 4
) QUESTION: What does a ' Code Red' FEMCO notification from Security mean? 4 s 1 i
SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #2 l l QUESTION: What is the minimum operations shift staffing complement required by Maine Yankee procedures. ANSWER: One (1) PSS One (1) SOS Two (2) CRO's Two (2) NPO's or AO's One (1) Additional operator (CRO, LNPO, NPO, or AO) One (1) STA SATISFACTORY: YES NO
REFERENCES:
. OP 1-26-5, Step 3.1.1a TASK IMPORTANCE: 2.3/3.4 TASK NUMBER- K/A Generic 2.1.5 LEARNING OBJECTIVE: SNO-0302-10 TRAINEE ANSWER / COMMENTS:
4
)
SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #2 OUESTION: What is the minimum operations shift staffing complement required by Maine Yankee procedures, N
SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #3 QUESTION: What is considered an ' Intent Change' to a procedure? ANSWcR: Anything that:
- 1. Invalidates the existing 10CFR50.59
- 2. Alters the stated objective of the procedure.
- 3. Alters any acceptance criteria, or
- 4. Directs performance in a plant condition which is different from the condition when the procedure would normally be used.
a. SATISFACTORY: YES NO REFERENCF.S; 0-06-2 (Section 6.7) TASK IMPORTANCE: 2.5/3.4 TASK NUMBER: Generic 2.2.11 LEARNING OBJECTIVE: GA-0302-1 TRAINEE ANSWER / COMMENTS:
~~. . .
SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #3 4 i' QUESTION: What is considered an " Intent Change" to a procedure?' i
9 SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS J QUESTION #4 QUESTION: What is the required ventilation lineup in the Fuel Building when moving irradiated fuel that has decayed less than OO d.fe? 5 D dago H 2W$ ANSWER: The SFP ventilation system shall be operating and discharging through the HEPA and charcoal absorber filter train during fuel movement within the SFP. SATISFACTORY: YES NO t
REFERENCES:
Tech Spec 3.25.C f TASK IMPORTANCE: 2.6/3.5 TASK NUMBER: K/A Generic 2.2.30 LEARNING OBJECTIVE: SNO-0303-8 TRAINEE ANSWER / COMMENTS: = B.
SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #4 QUESTION: What is the required ventilation lineup in the Fuel Building when moving irradiated fuel that has decayed less than 60 days?
- 9 f
5 JOB PERFORMANCE MEA @URE - - $f20 80 m p//^' JPM NUMBER: NEW-3X N3 M TASK NUMBER: 1190100301 TITLE: Use of Survey Meters START TIME: STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are 1101 authorized by this document to actually perform any action in the plant.
- 2. High radiation areas will not be entered. Location and operation of equipment inside high radiation areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to
} - the evaluator, who will " role-play" these personn,el. EVALUATION LOCATION: O PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 10 minutes IMPORTANCE RATING: 3.0 REQUIRED TOOLS AND EQUIPMENT:
- 1. RO-M h0 PREPARED / REVISED BY: DATE:
APPROVED BY: DATE: REVISION #: 0 DATE: 5/23/97 LORC JPM NEW-3X (AD-0103-13) PAGE 1 OF 6
- SAFETY CONSIDERATIONSi
, - None EVOLUTIONS CONDITIONS:
The plant has experienced a large break LOCA with failed fuel. The core is being cooled in the recirculation mode.. The hot leg injection valves will not operate from the EFW Pump Room. You have volunteered to enter the HPSI Valve Room to see why the valves will not open. The anticipated dose - rate is 20-30 R/hr. INITIATING CUES:
$0 Report to the HP Checkpoint and obtain a RO-3R radiation dose rate meter. Inform the HP Technician
( that y.oM will verify that the meter is ready for use. EVOLUTION STANDARDS: Trainee performs all four (4) checks to verify that the meter is ready for use.
REFERENCES:
- 1. GET-20,"Use of Survey Meters *
- 2. 9-311-3, CONTROL OF INSTRUMENTS
.7;lMULATOR:
N/A 8 LORC JPM NEW-3X (AD-0103-13) PAGE 2 OF 6
PERFORMANCE CHECKLIST '
, STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
1, Standard: Verife current calibration label on the meter. i O SATISFACTORY O UNSATISFACTORY COMMENTS: l 2.
, Standard: Verify proper physical properties (i.e., mrter is not damaged, beta shield is closed).
i O SATISFACTORY . O UNSATISFACTORY COMMENTS: LORC JPM NEW-3X (AD-0103-13) PAGE 3 OF 6 j
PERFORMANCE CHECKLIST
-- STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
3. Standard: Perform a battery check of the instrument. O SATISFACTORY O UNSATISFACTORY COMMENTS: 3 4. I I Standard: Verify a source check of the instrument has been performed that day. Cue: You are now ready to enter the PAB. O SATISFACTORY O UNSATISFACTORY COMMENTS: LORC JPM NEW-3X (AD-0103-13) PAGE 4 OF 6
PERFORMANCE CHECKLIST
- STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
7 5. Standard: Ensure instrument is set for the anticipated radiation area (20-30 R/hr). l
-O SATISFACTORY O UNSATISFACTORY COMMENTS:
l LORC JPM NEW-3X (AD-0103-13) PAGE 5 OF 6
EVOLUTIONS CONDITIONS: The pli.nt has experienced a large break LOCA with failed fuel. The core is being cooled in the recirculation mode. The hot leg injection valves will not operate from the EFW Pump Room. You have volunteered to enter the HPSI Valve Room to see why the valves will not open, The anticipated dose rate is 20-30 R/hr. INITIATING CUES: Report to the HP Checkpoint and obtain a RO-:8 radiation dose rate meter. Inform the HP lechnician that yp.y will verify that ibe meter is ready for use. i I 9 1 LORC JPM NEW-3X (AD-0103-13) PAGE 6 OF 6
,s JOB PERFORMANCE MEASURE- SRO ADMIN k JPM NUMBER: New-33 TASK NUMBER: K/A 2 213 TITLE: TAGGING A SAFETY CLASS COMPONENT TIME CRITlCAL: ,
O YES 5 NO START TIME: ALTERNATE PATH: 0 YES h NO STOP TIME: PERFORMANCE TRAINEE: ' PERFORMANCE RESULTS: O PASS O Fall 5 l QUESTION RESULTS: Out of Corree EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are MQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome cc.ntamination areas will not be entered.
Location and operation of equipment inside these areas r.hould be described.
- 3. All controlled references normally available may be ust;d. Control Room procedures and emergecy station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR N CONTROL ROOM APPROXIMATE COMPLETION TIME: 30 Minutes IMPORTANCE RATING: 3.6/3.8 REQUIRED TOOLS AND EQUIPMENT: -
- 1. Procedure 0-14-1, Attachment A, B, C, and M
- 2. White Tags PREPAREDIREVISED BY: DATE: h 97 APPROVED BY: [ DATE: 4//3/f7 REVISION #: 0 DATE: 3/19/97 JPM New-33 PAGE 1 OF 6
SAFETY CONEIDtiRATIONS: I None EVOLUTION CONDITIONS: The plant is operating at 90% powc INITIATING CUES: Maintenance has turned in a tagging request to clean E-58, SCC Service Water Heat Exchanger. You are required to fill out all necessary paperwork and have all nercasary checks performed to tag this Service Water Heat Exchanger for cleaning. The White Tags are not to be hung at this time. EVOLUTION STANDARDS: The trainee will demonstrate the ability to Danger Tag / White Tag a cafety class component.
REFERENCES:
QA Procedure 0-14-1 SIMULATOR: N/A NOTE: The evaluator should pw.*le an Attachment C of procedure 0-141, White Tag Order Master Index, filled out to the poir.t that the trainee will be able to determine the next sequential tagglng order number. The E" .luator shall also provide a Tagging Order Request (Attachment M of 0-14-1) for E-bi:s. The minimum tagout required per procedure 0-14-1 is attached to this JPM. t t
, ~-
JPM New-33 PAGE 2 OF 6 _____a
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 1. ,_
Trainee understands intended work scope of tagging order. Standard: Trainee asks questions of worker (Evaluator) as necessary to fully unJerstand work scope.
/
NOTE:
~
Trainee may ask Evaluator as many questions as necessary to understand scope of work. Trainee should be told that the endbells of the heat exchanger will be removed and ends of the heat exchanger will be cleaned out. O SATISFACTORY O UNSATISFACTORY COMMENTS: O l 2. I
- Trainee enters information on Attachment C for next sequential White Tagging Order number.
Standard- Trainee fills out W/T for, W/T By, Dat'e, and Equipment while referring to Attachment M of 0-14-1, 4 O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-33 PAGE 3 OF 6
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: l 3.
- Fills out Attachment A of 0-141.
Standard: Completes Attachment A referring to FMs and Attachment M of 0-14-1. NOTE: Completed Attacnment A of 014-1 for the minimum tagging boundary required is attn:hed to the back of this JPM. 7 O SATISFACTORY O UNSATISFACTORY r COMMENTS: l l 1 l . 4.
- Realizes that the Service Water Heat Exchanger is Safety Class and an Independent Verification is required. >
Standard: Vocalizes or indicates to the Evaluator that this Tagout requires an independent verification. O SATISFACTORY O UNSATISFACTORY COMMENTS: w JPM New-33 PAGE 4 OF 6 9 -
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
'5.
L t ._ Fills out necessary information on White Tags. Standard: Fills out Order No., Tag No., Valve No., and Position on Tag. l C SATISFACTORY O- UNSATISFACTORY COMMENTS: 6.'
- Obtains PSS permission to release equipment.
Standard: Voc.alizes or indicates to the Evaluator that this Tagout requires PSS permission to release the equipment. C SATISFACTORY O UNSATISFACTORY i COMMENTS: J JPM New-33 PAGE 5 OF 6
EVOLUTION CONDITIONS: The phnt is operating at 90% power, INITIATING CUES: Maintenance has tumed in a tagging request to clean E 5B, SCC Service Water Exchanger. You are i me,uired to fill out all necessary paperwork and have all necesaary checks performed to tag this SeWICS Water Heat Exchanger for cleaning. The White Tags are not to be hung at this time, l JPM New-33 PAGE 6 OF 6 d
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MAINEYANKEEkGGINGORDER MAINE YANKEE TAGGING ORDER ~ Tags Checked and Equipment Prepared By: Date / / Vertfled De-energized / Step 6.3.3: l Issued By: ' Date / / Tagging Order Cleared: Tagged for PSS/ SOS Vertfy All Holds and Grounds WO/ PROC / ADMIN CONTROL Removed: Tag Out Adequacy Validated By:
- COMPONENT TAGrIn A E REASON- l Ll:ensed Operator Second Knowledgeable Authorized Person (N/A)
Safety Class (1. 2. 3 or IE) Yes No if Yes. Independent verification is required and complete following: ' > DlITY PSS SIGNATURE NOTES: g
- 1. Permission to release equipment -
- 2. Equipment returned to service or y functional test pendino-G' ATTADifNTS YES
[ Hold Sheet Panalares Disabled: Ground Tags ** Change forms o INDIV. IMIV. U VERIF. POSITION VERIF. INSTALLED INSTALLED IEIV. IEIV. FOR TAG RDOVED REMOVED TAG VALVE. BREAKER POSITION BY BY DATE TAG TAG REMlWAL BY BY DATE No. SWITCil SLIDE (PSS/505) mum OPER 1 OPER 2 INSTAtLED DECK CLEAPiD (PSS/505) OPER 1 OPER 2 REMOVED ggg
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Proc. No. 0-14 1 Rev. No. 18 Page 68 of 74 ATTACNEMT M (Sheet 1 of 1)
. TAGOUT REQUEST FORM To: Plant Shift Superintendent / Shift Operating Supervisor:
It 's requested that the following equipment be tagged out, de-enersized drp'ned and depressurized as necessary to perform the maintenance discr16ed be ow. EQUIPMEE: DATE & TIME WORK WILL BEGIN: SAFETY CLASS:
)W:
WORK TO BE PERFM.O: l l l l SPECIAL TAGGING INSTRUCTIONS OR 3YSTEM LINEUPS: t TAG TO: RESP. SECTION: SIGNATURE: REVIEWED BY:.. Person Requesting Tags Operations 4 DATE: w* d
FOR TRA;NING USE ON'_.Y g* go ;;txt Page 68 of 74 e- ATTADNENT M (Sheet 1 of 1)
. TAGOUT RE0 VEST FOPJi To: P' ant Shift Superintendent / Shift Operating Supervisor:
It is requested that the following equi nt be ta ed out, de-energized, drpined and depressurized as necessary Eperform he maintenance discribed be oW. t
- EQUIPMENT: DATE & TIME WORK WILL BEGIN:
. E~58 .
WOf: 97,,,gg7 SAFETY CLASS: $ g.3 WORX TO BE PERFORMED: j 0/6d krd .*Z~dfDCf P 58 l Sernevid7 Seevick idafee Aen/ Gehartfee eda %eUs f SPECIAL T/6GING INSTRUCTIONS OR SYSTEM LINEUPS:
'O JAlde $ld-/68 40!ll A?e R&?tbu'ecl tDlieM e.JdbollN wwd-l
( Y11423l14ll ka,J}eaAda.e f SIGNATURE: 1o n aI/ REVIEWED BY: Perlon Regtjesting Tags Operations DATE: W... FO R TRALif NG USE ONLY
N . b .o ,. JOB PERFORMANCE MEASURE---SRO ADMIN -( JPM NUMBER: AD-0901-2-1 TASK NUMBER: K/A 2 4 38 TITLE: IMPLEMENTING E PLAN DUE TO LOSS OF MCB ANNUNCIATORS SRO ONLY TIME CRITICAL: NYES O NO START TIME: ALTERNATE PATH: O YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE O Fall l RESULTS: O PASS QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE:
' ~~ ' ' ~ ~~ ~
DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
/ location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play
- these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 15 Minutes IMPORTANCE RATING: 2.2/4.0 REQUIRED TOOLS AND EQUIPMENT: 2 50-0 2501 PREPARED / REVISED BY: - DATE: 7 APPROVED BY: y;[ DATE: 8/[3/77 i ' L. REVISION #: f 2 DATE: 3/27/97 JPM AD-0901-2-1 PAGE 1 OF 8
SAFETY CONSIDERATIONS: 4 Non* 4 EVOLUTION CONDITIONS: Plant is at 100% power. You are the Plant Shift Superintendent. y INITIATING CUES: ge'* l You are the PSS with the plant O 100% power, The plant has just sustained a lightning strike,' causing a loss of Main Control Board annunciators, You are to assess and implement the E Plan, if required. lt EVOLUTION STANDARDS: i Within 15 minutes, the trainee should declare an unusual event and make appropriate notifications.
REFERENCES:
2 50-0, EMERGENCY CLASSIFICATION 2 501 UNUSUAL EVENT PRR 95 081 PRR 96-162
. 3IMULATOR:
t 1. Roset Simulator to 100% IC.
- 2. Insert malfunction AN02B and C to remove MCB annunciators.
- 3. Freeze simulator.
4 e 4 4 s. JPM A40901-2-1 PAGE 2 OF 8
. .. . __ i
a PERFORMANCE CHECKLIST STT2PS/ STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. Trainee may ask for more information regarding the lightning strike. Standard: As above. Cue: HPO reports several strikes on site. CRO reports several panalarms were received prior to the loss of annunciators. NOTE: It may be necessary at this point to explain to the trainee that the primary focus of this JPM is E Plan implementation. It is not the intent of the JPM that he tries to troubleshoot and solve the problem. Record start Time O SATISFACTORY O UNSATISFACTORY COMMENTS: 2. Reference E Plan classification Procedure 2 50-0. , Standard: Trainee references Procedure 2 50-0 Attachment A, Emergency Condition Classification Matrix. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM AD-09012-1 PAGE 3 OF 8
PERFORMANCE CHECKLIST ( l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 4 3. l
- Classify the event as an ' Unusual Event" based on 2 50-0, Attachment A, Subcategory 2.1.
Standard: As above, f Cue: If asked, plant computeris available and capable of displaying data requested. 1 O SATISFACTORY O UNSATISFACTORY COMMENTS: e i i 1 } 1 4 4. 1 i Obtain copy of Procedure 2-50-1, UNUSUAL EVENT. j Standard: As above.
- O O SATISFACTORY UNSATISFACTORY COMMENTS
4 i l 1 4 4 JPM AD-0901-2-1 PAGE 4 OF 8
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: l i 5. 1 Announce to Control Room that an Unusual Event has been declared. Standard: As above, C SATISFACTORY O UNSATISFACTORY COMMENTS: i . 6. ll Direct STA to perform emergency notifications per 2 50 5, EMERGENCY NOTIFICATION, 4 I
- Standard
- As above, 4 Cue: STA commences 2 50-5, i
j O SATISFACTORY O UNSATISFACTORY l COMMENTS: l l i l JPM AD-09012-1 PAGE 5 OF 8
. - - , _ _ . . . . - _ . -. , _=_.- .-. - _ . - . - - - . - . - . -
1 PERFORMANCE CHECKLIST i STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: . l I . _
- Sound evacuation alarm and make Unusual Event announcement over FEMCO. I Standard: As above.
! O SATISFACTORY O UNSATISFACTORY t
' COMMENTS:
i 8. Fill out appropriate information on 2 501, Attachment A, Maine Yankee Emergency Notification form. j Standard: Maine Yankee has declared: Unusual Event, Wind: direction and speed, Problem: Loss of Annunciators, Radiological Release: Has not occurred. i PAR: None. NOTE: Current wind speed and direction is provided using SPDS on MET tower i hh. 1 4 O SATISFACTORY O UNSATISFACTORY ) COMMENTS: 1 i i JPM AD-09012-1 PAGE 6 OF 8
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 9.
'Make emergency notification to State Police within 15 minutes.
Standard: State Police are informed of minimum infom1ation stated in Step 8 Standard , I within 15 minutes of the emergency declaration time as recorded in 2 50-1,
, Step 6.1.1 or on Att. A.
NOTE: Record notification time: O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM AD-09012-1 PAGE 7 OF 8
EVOLUTION CONDITIONS: Plant is at 100% power. You are the Plan'. Shift Superintendent. INITIATING CUES: You are the PSS with the plant O 100% pc wer. The plant has just sustained a lightning strike, causing a loss of Main Centrol Board annunciators. You art, to assess and implement the E Plan, if required, i JPM AD-09012-1 PAGE 8 OF 8
.o
I__-___ It r / JOB PERFORMANCE MEASURE-SRO p& JPM NUMBER: N1-0901-1-1 TASK NUMBER: K/A 015 A3 03 TITLE: ESTABLISHING ALTERNATE SYMMETRIC OFFSET LIMITS TIME CRITICAL: O YES 5 No START TIME: ALTERNATE PATH: O YES 5 NO STOP TIME: PERFORMANCE TRAINEE: ' PERFORMANCE RESULTS: O' PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: 1 DIRECTIONS TO TRAINEE: I l 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by l this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations. 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation. 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will ' role play" these personnel. EVALUATION LOCATION:, O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 5 minutes IMPORTANCE RATING: 3.9/3.9 REQUIRED TOOLS AND EQUlPMENT:
- 1. Technical Data Book
- 2. OP 1-4-1 PREPARED / REVISED BY: DATE:
t APPROVED BY: [ DATE: t/[3/f7 REVISION #: g 3 DATE: 3/20/97 JPM N1-0901-1-1 PAGE 1 OF 9
SAFETY CONSIDERATIONS: - None, t EVOLUTION CONDITIONS: The plant is steady state at power. The plant computer (OSS) is out of service. INITIATING CUES: You are the Primary RO. RPS must be placed in attemate symmetric offset for Technical Specification concerns. You are to place RPS channels in ALTERNATE LAW OP 141. EVOLUTION STANDARDS: After receiving the initiating cue, the trainee will ensure the plant is within alternate symmetric offset limits of TDB Figure 3.1.2.2 and then place the RPS channels in ALTERNATE.
REFERENCES:
Technical Data Book PRR 92120 PRR 96162
- 9IMULATOR:
- 1. Reset to an IC of 45% power or less.
- 2. Ensure power and symmetric offset are within alternate symmetric offset limits.
- 3. Sign off OP 1-41 to step 5.5.2. Check the box for power reduction to within SO pretrip band.
- 4. Bring in the trainee and conduct a turnover.
JPM Nl.0901-1-1 PAGE 2 OF 9
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. 1 Obtain a copy of OP 1-41. j Standard: Trainee is provided a copy of OP 1-41 with the appropriate steps, including calculation of 'P 5.g ct[f, O SATISFACTORY O UNSATISFACTORY COMMENTS: 1. Reference Technical Data Book Figure 3.1.2.2 for symmetric offset limits. Standard: Verify plant symmetric offset is within pre trip limits of TDB Figure 3.1.2.2. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NI.0901-1-1 PAGE 3 OF 9
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: l l 3.
- Select one RPS channel to ALTERNATE and verify symmetric offset is within limits.
I Standard: 1) Normal /Altemate switch taken to ALTERNATE (on RPS SOTC drawer).
- 2) Trips and pre trips verified clear by absence of white and red status lights on SOTC trip bin (can also check absence of alarm R 1 12).
O SATISFACTORY O UNSATISFACTORY COMMENTS: f 4.
' Select ALTERNATE position on the three remaining chamels.
Standard: Each remaining channel placed in ALTERNATE on RPS SOTC drawers and trips and pre-trips verified clear, by absence of white and red status lights on SOTC trip bins (can also check for alarm R 1 12 clear). O SATISFACTORY O UNSATISFACTORY COMMENTS: (; JPM NI 0901-1-1 PAGE 4 OF 9 j
EVOLUTION CONDITIONS: The plant is steady state at power. The plant computer (OSS) is out of service. INITIATING CUES: You are the Primary RO. RPS must be placed in altemate symratric offset for Technical Specification concoms. You are to place RPS channels in ALTERNATE LAW OP 1-4-1. i
~
( I JPM NI-0901-1 1 PAGE 5 OF 9 i _ .. __ __ _j
JPM QUESTION #1 Ni 0901 11 ) ! QUESTION: What immediate action is required for four (4) or more coincident, valid incore instrument t alarms? How is validity of alarm determined in the Control Room? ANSWER: Immediateh reduce power to clear alarms per T.S. 3.10.C.3. Alarm validity is determined by an INCA pdntout LAW OP 18-1, POWER DISTRIBUTION AND MTC CONTROL
.9 y'\c\s
, y.Y s
i l SATISFACTORY: YES NO
REFERENCES:
Tech Spec 3.10.C.3, RO-L-4.3 (page 20), SRO-L-10.8 (page 40), OP 18-1 TASK IMPORTANCE: 3.9/3.9 TASK NUMBER: KIA 015-A3.03 LEARNING OBJECTIVE: INCA 01013, SNO-0303-9, SNO 0303-10 TRAINEE ANSWER / COMMENTS:
$/
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6/ j JPMEl-0901-1 1 PAGE 6 OF 9
JPM QUESUON #2 Nl0901 11 QUESTION: (This question does not relate to the JPM.) The waste gas decay tank release is in progress when the RMS Channel (RM-3g01) fails low (the flow control valve still functions). What remedial actions are required in this condition per the ODCM in order to continue the release? ANSWER: With less than the minimum number of channels operable per Table 2.2 (page 16) of ODCM, you l must have at les',t two (2) Independent samples of the drum's contents analyzed and have at least two (2) quellfled individuals independently veify release rate calculations and discharge valve lineup. SATISFACTORY: YES 'NO
REFERENCES:
ODCM Table 2.2 (page 17) TASK IMPORTANCE: 2.7/3.5 TASK NUMBER: K/A 071 K4.06 LEARNING OBJECTIVE: SNO-03041 TRAINEE AtlSWER/ COMMENTS: 4 JPM NI-0901-1-1 PAGE 7 OF 9
JPM QUESTlON #1 I^ NI 0901 1-1 QUESTION: What immediate action is required for four (4) or more coincident, valid incore instrument alarms? How is validity of alarm determined in the Control Room? l N44 e
# 4 4
JPM NI-0901-1 1 PAGE 8 OF 9
JPM QUESTION #^ i NI 0901 1.1 QUESTION: (This question does not relate to the JPM.) The waste gas decay tank release is in progress when the RMS Channel (RM 3901) fails low (the flow control valve still functions). What , temedial actions are required in this condition per the ODCM in order to continue the release? i O I i 1 + i i d l I 4 1 J 4 JPM Nf-0901-1-1_ PAGE 9 OF 9
N $" JOB PERFORMANCE MEASURE-SRO [~aS , NPM NUMBER: New 25 TASK NUMBER: _ K/A 011 EA111 l T!TLE: PERFORMING RHR SYSTEM FAST STARTU? DURING POST-LOCA COOLDOYM ' TIMG CruTICAL: C YES N NO START TIME: AVTERtMTE PATH: O yes W NO STOP TIME: PERFORMANCE TRAINED:
- - _ _ =
PERFORMANCE RESULTS: O PAPG O Fall QUESTION RESULTS: _ _ _ Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. A
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who w;11" role-play
- these personriel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 Minutes IMPORTANCE RATING: 4.2/4.2 REQUIRED TOOLS AND EQUIPMENT: AOP 2 56 PREPARED / REVISED BY: / DATE: 7 A" PROVED BY: [ DATE: t/[3h7 REVISION #: f 0 DATE: 3/20/97 JPM NEW-25 PAGE 1 OF 18
4
- SAFETY CONSIDERATIONS:
l None lpdVOLUTION CONDITIONS: . I ES 1,2, POST-LOCA COOLDOWN AND DEPRESSURIZATION, is in progress. The plant has just reached RHR entry conditions. Containment and and Spray Building Lower Level are inaccessible due
- to high radiatien levels. TSC has recommended fast startup of the RHR System.
1 INITIATING CUES: ) You are the primary RO. You have been directed to place Train 'A' RHR in service IAW OP 2 56, I j RESIDUAL HEAT REMOVAL SYSTEM FAST STARTUP. EVOLUTION STANDARDS: The trainee will place Train 'A' RHR in sertce IAW OP 2 56. ]
REFERENCES:
1 , 1. ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION. j 2. AOP 2 56, RESIDUAL HEAT REMOVAL SYSTEM FAST STARTUP. l ( "SIMULATOR:
- 1. Initialize in cooldown IC#18 ready to place RHR inservice.
- 2. Align plant equipment to match actions in E-0, E-1, ES-1.2 flowpath. (RCP #1 running, CIS i Reset, normal charging restored, letdown isolated, SlAS blocked, SITS isolated, etc.).
- 3. Initiate fuel clad failure. (Malfunction CRO1,100%).
- 4. Initiate 50 gpm RCS leak (Malfunction RC04A,25%).
- 5. Ensure Spray Building Radiation Monitor (RM-6110)is in alarm high (malfunction RM01K1).
- 6. Ensure RCS less than 317 psig and 340*F for proper RHR cut in prerequisites (Containment condi!!ons will be normal for this scenario. Will need to use pressurizer PORV to reduce j pressure to less than 317 psig and will need to use steam dump to cool down to less than 4 340*F, it is desirable to have pressurizer level on scan but not required for this JPM.)
- 7. Freeze simulator and tum over to trainee.
1
! I
- f. v JPM NEW 25 PAGE 2 OF 18
..-_~-- .-
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: , 1. Verify RCS borated to cold shutdown. Standard: As above. Cue: Adequate boron has been injected into the RCS for cold shutdown. O SATISFACTORY O UNSATISFACTORY l COMMENTS: l l l 2. Verify RCS temperature less than 340'F and stable or decreasing. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEW 25 PAGE 3 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: e. 3. Verify RCS pressure less than 317 psig (210 psig for harsh cimt) and stable or decreasing. Standard: As above. If not, then trainee establishes these conditions using aux spray or l PORV and steam dumps, as necessary. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4. Verify SlAS, RAS, and CSAS have been reset. Standard: Check 86 devices back of MCB reset. heck ECCS lightbox for SIAS, RAS, and CSAS white lights out. Can also check associated annunciators off l (RH-3-1, RH 3-7, RH-3-4). OR j
., s O SATISFACTORY O UNSATISFACTORY COMMENTS:
f
%s JPM_ NEW-25 PAGE 4 OF 18
PERFORMANCE CHECKLIST e, STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5. Verify ECCS routine testing OP 3-12.1, SAFEGUARDS LOCKED VALVE LIST and OP 312.2, PRE POWER VALVE CHECKLIST are in place. S'tandard: As above. Cue: These procedures are in place. O SATISFACTORY O UNSATISFACTORY COMMENTS:
? '
s_ s Clear white tags and shut breakers and disconnects for RH-M-1 and RH-M 2. Standard: Dispatch an AO to perfom1 the above actions. Cue: - After performing remote function RH120, report local actions completed. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEW-25 PAGE 5 OF 18
PERPORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 7' h. Place P-12A in PTL Standard: As above, ? O SATISFACTORY O UNSATISFACTORY COMMENTS: T- g,
- Align HPSI P 14A suction to RWST or place in PTL Standard: Open P-14A suction valve to RWST, HSI M 50 or place P-14A in PTL NOTE: Since RWST level will be full in this scenario, opening HSI-M 80 is preferable to placing pump in PTL but either choice satisfies procedure step.
6 O SATISFACTORY O UNSATISFACTORY COMMENTS: wa JPM NEW-25 PAGE 6 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 9. Place Train 'A' Containment Spray Pump P-61 A in PTL. Standard: As above. O SATISF.'CTORY O UNSATISFACTORY COMMENTS: 1 l 10.
' Align the following valves:
e Shut LSI-M-41, CS-M-91, and CS-M-1.
- Throttle open PCC M-43.
e Shut LSI 55. o Open RH-6, RH 9, and RH-11. e Shut LSI-47, CS-13, and CS-31. Standard: As above. Direct an AO to perform the last three bullet items. Cue: After performing remote functione RH104 (close LSI-47), RH108 (close LSI 55), RH106 (open RH-6), RH101 (open RHg), RH115 (open RH-11), and CS111 (close CS-13), then AO repcrts that LSI 55, LSI-47, CS-13, and CS 31 are shut and that RH-6, RH-9, and RH-11 are open. O SATISFACTORY O UNSATISFACTORY COMMENTS: us JPM NEW-25 PAGE 7 OF 18
PERFORMANCE CHECe(LIST STEPS / STANDARDS FOR SUCCESSFUL PERFC>RMANCE:
- 11.
Secure operating LPSI pump and place in PTL Standard: As above. If P-12B is running, then stop it and place it in PTL O SATISFACTORY O UNSATISFACTORY COMMENTS: 12. Shut CS-A-55 and CS-A 56. Standard: As above. Cue: If asked, LPSI pump vent valves LSI-67 and 68 are open. (inaccessible in this scenario.) , C SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEW-25 PAGE e OF 18
PERFORMANCE CHECKLIST . STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 13. Verify LSI-F 59 controller is fully open. Standard: As above. NOTE: , LSI-F 59 valve is blocked full open in the Spray Building and is inaccessible. For this scenario, this valve will remain fully open at all times. O SATISFACTORY O UNSATISFACTORY COMMENTS: 14. Open RH-T-12 to 20% on the controller. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEW-25 PAGE 9 OF 18
PERFORMANCE CHECKLIST _ STEPS /STANDARDG FOR SUCCESSFUL PERFORMANCE: 10. I Shut LSI-M-11,21, and 31. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 16. Throttle open LSI-M-31 just off its seat. Standard: LSI-M-31 is jogged open until intermediate position indication is observed. ' O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEW-25 PAGE 10 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 17.
*Open RH-M-1 and RH-M-2.
Standard: As above9 O SATISFACTORY O UNSATISFACTORY COMMENTS: I m k8 9 9
%e ./
JPM NEW-25 PAGE 11 OF 18 1
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
,m
' 18.
' Commence RHR System heatup as follows:
- 1. Start RHR Pump P-12A.
- 2. Slowly open LSI-M-11 and LSI M-31.
- 3. Slowly cycle RH T-12 full stroke.
Standard: As above. RHR System warmup rate should not exceed 21*F/ minute P12A beering temperature should not exceed 250*F. At least 500 gpm should be maintained through the RHR pump. NOTE: Per notes preceding this step, trainee should monitor (1) RHR pump bearing temperatures (plant computer group B-01), (2) RHR System heatup on TR-351X/Y or TI-352/353X/Y, (3) RHR flow to Loops 1 and 3 on F1-312/F1-332, and (4) PCC flow through RHR hx using F1-1708/F1-3408 or pump amp changes, Since these actions are in a note vs an action step, they are not considered critical for the purposes of this JPM. Once it is observed that the trainee can control the 21'F/ hour RHR System warmup rate, then to save time, trainee may be prompted to assume RHR System is fully warmed up and to proceed accordingly.
- O SATISFACTORY O UNSATISFACTORY COMMENTS
Ne JPM NEW-25 PAGE 12 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 19.
' Control RCS temperature as follows:
- 1. Throttle open RH-T-12 to allow flow through the RHR hx.
- 2. Throttle PCC-M-43 and balance the flow with RH-T-12.
Standard: As above. To decrease cooldown rate, close RH-T-12, and/or PCC-M-43. To increase cooldown rate, open RH-T-12 and/or PCC-M-43. , Cue: Direct trainee to establish an observable cooldown rate using RHR . Once l established, then direct trainee to stop the cooldown. Once evaluator is l confident that trainee cr.n control cooldown rate using RHR, then cue that JPM is l ' complete. NOTE: To see the full effect of the trainee's actions to control the RCS cooldown rate, make sure that the SGs are not cooling down the RCS due to steaming and feeding before asking him to start and stop a cooldown on RHR. O SATISFACTORY O UNSATISFACTORY COMMENTS: r JPM NEW-25_ PAGE 13 OF 18
EVOLUTION CONDITIONS: ES 1.2, POST-LOCA COOLDOWN AND DEPRESSURIZATION, is in progress. The plant has just reached RHR entry conditions. Containment and Spray Building Lower Level are inaccessible due to high radiation levels. TSC has recommended fast startup of the RHR System. INITIATING CUES: You are the primary RO. You have been directed to place Train "A" RHR in service IAW OP 2-56, RESIDUAL HEAT REMOVAL SYSTEM FAST STARTUP. t i I
#!=
h. 4 JPM NEW-25 PAGE 14 OF 18 I
. . - - - .- =- - - -
JPM QUESTION #1 NEW 25 QUESTION: How is the RHR piping protopted from overpressure tpnsients during cold shutdown conditions / W.Tk T Th( RCS $cl e f$d ell M M ? ANSWER: The RHR spring reliefs (RH-S-24 and 25) and auto closure of RH-M-1 & 2 on high pressure (585 psig), 6
/ .
h
. 1 d'h 3 4 9
i d' eMv0s { ... SATISFACTORY: YES NO
REFERENCES:
RO-L-2.7 (page 5) TASK IMPORTANCE: 3.5/3.7 - TASK NUMBER: K/A 005-A2.02 LEARNING OBJECTIVE: RHR-0101-5, RHR-0101-8 TRAINEE ANSWER / COMMENTS: s JPM NEW-25 PAGE 15 OF 18
JPM QUESTION #2 NEW - 25
.m i JUESTION: During normal procedure conditions (OP 1-7), the RHR Systern auto isolates with PZR level greater than 80%. What actions are required? (RCS is not vented).
ANSWER: Wdhin six hours perform one of the following:
- 1. Restore the required condition.
- 2. Station a dedicated operator to prevent RCS overpressurization and within 72 hours place the plant in a condition where LTOP is not required.
f
.p*
p
\\
V,>$ o
- SATISFACTORY: YES NO
REFERENCES:
Tech Spec 3.4.D.3 TASK IMPORTANCE: 3.4/4.0 TASK NUMBER: K/A Generic 2.1.33 LEARNING OBJECTIVE: ISR-0301-3, SNO-0303-13, SNO-0303-9 TRAINEE ANSWERiCOMMENTS: h JPM NEW-25 PAGE 16 OF 18
unl q ulllnni miu u44 JPM QUESTION #1 NEW-25 QUESTION: How is the RHR piping protected from overpressure transients during cold shutdown conditions without the RCS adequately vented? G k i._ JPM NEW-25 PAGE 17 OF 18 a
JPM QUESTION #2 NEW a 25 (^)UESTION: During normal procedure conditions (OP 1-7), the RHR System auto isolates with PZR level greater than 80%. What actions are required? (RCS is not vented). , I 9 e-9 JPM NEW-25 PAGE 18 OF 18
4
\ p!F JOB PERFORMANCE MEASURE SRO k' JPM NUMBER: ES F-0901-1-1 TASK NUMBER: K/A OO6-A4.08 TITLE: PERFORMING ESF PANEL OPERATIONS TO RECOVER FROM INADVERTENT SIAS TIME CRITICAL: O YES N NO START TIME:
ALTERNATE PATH: O YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. ('
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who wiil " role-play" these personnel.
. EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 6 minutes IMPORTANCE RATING: 4.2/4.3 REQUIRED TOOLS AND EQUIPMENT:
ES-1.1 PREPARED / REVISED BY: DATE: 7 APPROVED BY: [ DATE: 3[97 U REVISION #: / 6 DATE: 3/19/97 JPM ESF-0901-1-1 PAGE 1 OF 9
SAFETY CONSIDERATIONS: None EVOLUTION CONDITIONS: An inadvertent initiation of SlAS has occurred. SIAS has been reset IAW ES-1.1, Si TERMINATION. 'I INITIATING CUES: You are the Primary RO. You aro to reset and retum to normal the following valves:
- 1. Containment sump pump discharge valves, PD A-122,124,
- 2. CO2 fire protection to Containment, C-A-14,15.
- 3. Containment APD lines to Containment, IA-A-98,107.
EVOLUTION STANDARDS: I The trainee will reset the designated system valves at the ESF panels to demonstrate his knowledge of
, ESF Panel operations.
REFERENCES:
/
ES-1.1, SI TERMINATION PRR 92-120 PRR 92-120 PRR 96-162 S!MULATOR:
- 1. Reset to a power IC.
g 2. Manually fire trains A & B of Safety injection and retum to AUTO.
- 3. Perform operator actions of E-0 & ES-1.1 up to and including SIAS RESET.
- 4. Bring in the trainee and conduct a tumover.
!(.s JPM ESF-0901-1-1 PAGE 2 OF 9
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1.
, Obtain a copy of ES-1.1, Sl TERMINATION.
Standard: Trainee is provided with a copy of ES-1.1 when referenced. NOTE: The valves do not have to be reset in a specWic order. For purposes of this JPM, only the valves listed below need be done. Intent is MQI to do all valves on Attachment B. Cue: ES-1.1 has been completed up to step for aligning secondary plant equipment per Attachment B. O SATISFACTORY O UNSATISFACTORY COMMENTS: 2.
- Reset containment sump discharge valves.
Standard: 1) ESF A control switch for PD-A-122 taken to reset.
- 2) ESF B control switch for PD-A-124 taken to reset.
- 3) Status lights verified to go out.
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM ESF-0901-1-1 PAGE 3 OF 9
. . - -. ._ . = .-_ .. . . _ ._- - .. - . - - _ . . _ . .
l
, PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
3.
- Reset CO, fire protection valves.
Standard: 1) C-A-14 reset on ESF A.
- 2) C-A-15 reset on ESF B.
I 3) Valve status lights verified to go out. , 1 0 SATISFACTORY O UNSATISFACTORY 4 COMMENTS: 1 2 i i ,
'j
- 4,
' Reset containrnent APD valves.
I Standard: 1) lA-A-98 reset on ESF B.
- 2) lA-A-107 reset on ESF B.
- 3) Valve status lights verified to go out.
O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 4 JPM ESF-0901-1-1 PAGE 4 OF 9
EVOLUTION CONDITIONS: An inadvertent initiation of SIAS has occurred. SIAS has been reset IAW ES-1.1, Si TERMINATION. INITIATING CUES: You are the Primary RO, You are to reset and retum to normal the following valves:
- 1. Containment sump pump discharge valves, PD-A-122,124,
- 2. CO2 fire protection to Containment, C-A-14,15,
- 3. Containment APD lines to Containment, IA-A-98,107.
i r ; 4 JPM ESF-0901-1-1 PAGE 5 OF 9
JPM QUESTION #1
; ESF-0901-1-1 QUESTION: What are the required actions and conditions necessary to block RAS?
ANSWER: When 3/4 PZR pressure channels are <1720 psig, place the RAS select switch to
- BLOCK".
SATISFACTORY: YES NO
REFERENCES:
NOP 1-7, RO-L-4.7 (page 13) TASK IMPORTANCE: 3.7/3.9 TASK NUMBER: K/A 013-K4.12 LEARNING OBJECTIVE: SNO-0303-13, ESF-101-4, ESF-01015 TRAINEE ANSWER / COMMENTS: JPM ESF-0901-1-1 PAGE 6 OF 9
JPM QUESTION #2 ESF4901-1-1 i QUESTION: How is the operator alerted to a loss of control power for an SIAS related 86 device? ANSWER: Annunciator RH-3-3 "SIAS 86 Device Trip Path Fault' monitors control power to various SIAS 86 devices. l i t SATISFACTORY: YES NO
REFERENCES:
RO-L-2.6 (page 54), RO-S-2.8 TASK IMPORTANCE: 3.7/4.2 TASK NUMBER: K/A 013-A2.05 LEARNING OBJECT!VE: ECCS-01013 TRAINEE ANSWER / COMMENTS: i JPM ESF-0901-1-1 PAGE 7 OF 9
-_]
JPM QUESTION #1 ESF-0901-1-1 QUESTION: What are the required actions and conditions necessary to block RAS? a x 9 JPM ESF-0901-1-1 PAGE 8 OF 9 __ u
JPM QUESBON #2 i ESF-0901-1-1 QUESTION: How is the operator sletted to a loss of contrcl power for an SlAS related 86 device? s
#- ,i v-JPM ESF-0901-1-1 PAGE 9 OF 9
JPM NUMBER: New-15 TASK NUMBER: K/A 055-EA1.08 I TITLE: STARTING DG-1B LOCALLY DURING SBO TIME CRITICAL: 0 YES N NO START TIME: ALTERNATE PATH: NYES O NO STOP TIME: PERFORMANCE TRAINEE: ' QUESTION RESULTS: Out of Correct PERFORMANCE RESULTS: O PASS O Fall DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATE" The trainee and examiner are tiQI authorized by l this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. l 3. All controlled references normally available may be used. Control Room procedures and l emergency station procedures should not be removed from their storage locations. l 4. The application of all safety rules, general work practices, and STAR (self-checking) will be
- examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will ' role-play" these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: IMPORTANCE RATING: 4.1/4.5 REQUIRED TOOLS AND EQUIPMENT: AOP 2-48 PREPARED / REVISED BY: DATE: // ! 7 APPROVED BY: [ DATE: 4/[3/97 k-. REVISION #: r 0 DATE: 3/21/97 JPM New-15 PAGE 1 OF 13
SAFETY CONSIDERATIONS: None EVOLUTION CONDITIONS: A loss of all AC power has occurred with DG-2 available, AOP 2-48 is in progress. DG-1B auto started but then tripped. T INITIATING CUES: You are the Spare AO. You have been directed to attempt a bcal start of DG-1B IAW AOP 2-48 Attachment F. EVOLUTION STANDARDS: Trainee will perform AOP 2-48 Attachment F. As part of the evolution, he will discover that the diesel tripped on overspeed and will reset it to allow restart. He will also adjust diesel speed on two occasions.
REFERENCES:
AOP 2-48, Loss of All AC DG-2 Available/ Station Blackout (SBO) ~ 4 SIMULATOR: N/A - I
~f 1
JPM Ngg PAGE 2 OF 13 o _
PERFORMANCE CHECKLIST STEPS! STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 1. _
g Obtain copy of AOP 2-48 Attachment F, EDG 1B Manual Start and Loading. Standard: Trainee is provided a copy of AOP 2 48 Attachment F when requested. OLLt.' STarr Seguence rdays Oud breaker Trlp s, are. reset O SATISFACTORY O UNSATISFACTORY , COMMENTS: i I 9 2.
- Check DG panel alarms.
Standard: Trainee should investigate panel alarms, discover that the diesel tripped on overspeed, and reset it by moving overspeed trip lever clockwise to approximately the "g o' clock" position and verifying that it latches in tiie set. position. Cue: OVERSPEED TRIP (DG 2-6) local alarm is lit. If asked, cue as required that the DG is tripped, the overspeed trip lever is in the tripped position, and the govemor oillevel is normal. If trainee contacts Control about the overspeed trip, Control Room directs trainee i to reset it and continue with the local start attempt.
= if asked about alarm after resetting overspeed trip, alarm is clear.
l O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 1 (. JPM New-15 PAGE 3 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3. 1 Ensure CB START I and CB START ll circuit breakers in ON position. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: r, l 4. Ensure AC and DC control breakers in ON position. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: i . JPM New-15 PAGE 4 OF 13 _____________i
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 5. Place SELECTOR SWITCH in LOCAL START position. Standard: As above. O SATISFACTORY O UNSATISFACTORY
~
COMMENTS: 6. Lower speed setting on the diesel to minimum. Standard: Hold GOVERNOR CONTROL in LOWER until govemor setting is at O. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-15 PAGE 5 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 7.
- Ensure overspeed trip is reset.
Standard: OVERSPEED TRIP alarrr. (DG 2-6) clear, Can also check the overspeed trip lever rotated clockwise f a about "9 o' clock" position and latchec in set position. f O SATISFACTORY O UNSATISFACTORY COMMENTS: i 8.
- Press ENGINE START button to start the diesel.
Standard: As above. Cue: DG starts and accelerates to 930 rpm. O SATISFACTORY , O UNSATISFACTORY COMMENTS: JPM New-15 PAGE 6 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 9.
- Raise DG speed to 950 rpm.
Standard: Hold GOVERNOR CONTROL in RAISE till 950 rpm is reached. Cue: After GOVERNOR CONTROL placed in RAISE, DG rpm is 950 rpm. O SATISFACTORY O UNSATISFACTORY COMMENTS: l ! i 10. Place SELECTOR SWITCH in AUTO position. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-15 PAGE 7 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 11. Inform the Control Room that dieselis ready for Aashing. Standard: As above. Cue: After receiving this report, the Control Room flashes the diesel and requests trainee to verify diesel speed is 900 rpm. O SATISFACTORY O UNSATISFACTORY COMMENTS: 12.
- Verify DG speed at 900 rpm after flashing, gg th/, M mMi2IQh PaatI Standard: Trainee takes GOVERNOR CONTRO RAISE and informs Control Room.
Cue: Before trainee adjustment, diesel speed is 890 rpm. After adjustment, if trainee takes GOVERNOR CONTROL to RAISE, then diesel speed increases to 900 rpm. O SATISFACTORY O' UNSATISFACTORY COMMENTS: JPM New-15 PAGE 8 OF 13
EVOLUTION CONDITIONS:
^
A loss of all AC power has occurred with DG-2 available. AOP 2-48 is in progress. DG-1B auto started but then tripped. INITIATING CUES: You are the Spara AO. You have been directed to attempt a local start of DG-1B IAW AOP 2-48 Attachment F. i l l l-l j i JPM New-15 PAGE 9 OF 13
JPM QUESTION #1 NEW-15 QUESTION: Attachment Q of ECA-0.0 lists several emergency procedure actions that require notificati7n due to 10CFR50.54X requirements. What is the purpose behind a one hour notification involving a 10CFR54X issue? ANSWER: In the event of a safety emergency a licensee may deviate from license conditions without prior NRC approval. l s SATISFACTORY: YES NO
REFERENCES:
SRO-L-10.12 (page 14) TASK IMPORTANCE: 2.6/3.8 TASK NUMBER: Generic 2.2.23 LEARNING OBJECTIVE: GA-0307-5 TRAINEE ANSWER / COMMENTS: ) JPM New-15 PAGE 10 OF 13
JPM QUESTION #2 i ~ NEW 15 QUESTION: A revision to the DG Surveillance Procedure was submitted. It is determined that a 50.59 review is necessary. What is the purposa of a 10CFR50.59 Review? l ANSWER: Allows Maine Yankee to: 1) change design 2) revise procedures or 3) conduct tests / experiments as along as the change or test does not involve: A) A Tech Spec change et B) An unreviewed safety question. SATISFACTORY: YES NO
REFERENCES:
SRO-L 10.11 (page 10) TASK IMPORTANCE: 1.8/3.3 TASK NUMBER: Generic 2.2.8 LEARNING OBJECTIVE: GA 03051 , TRAINEE ANSWER / COMMENTS: JPM New-15 PAGE 11 OF 13
1 JPM CUESTION #1 NEW.15 l QUESTION: Attachtnent Q of ECA-0.0 lists several emergency procedure actions that require notification due
; to 10CFR50.54X requirements. What is the purpose behind a one hour notification involving a 3
10CFR54Xissue? 2 l 1 l l i i ) . t l 1 1 1 i ( -) 4 I 4 i. 4 t i i i-
~.
JPM New-15 PAGE 12 OF 13
.~. - -
JPM QUESTIEN#2 NEW 15 4 QUESTION: A revision to the DG Surveillance Procedure was submitted. It is determined that a 50.59 review is necessary. What is the purpose of a 10CFR50.59 Review?
/
l
)
JPM New-15 PAGE 13 OF 13
JOB PERFORMANCE MEASURE--SRO p JPM NUMBER: New-4 TASN NUMBER: K/A 033-A1.01 l TITLE: PERFORMING LOCAL ACTIONS FOR PRIMARY SIDE EQUIPMENT DURING l LOSS OF ALL AC POWER TIME CRITICAL: O YES W NO START TIME: l ALTERNATE PATH: O YES 5 NO STOP TIME: ; PERFORMANCE ! TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR j SIGNATURE: DATE: 1 DIREGTIONS TO TRAINEE: 1
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are MOI authorized by j this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room AOs, etc.) should be directed to the evaluator, who will " role-play' these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 15 Minues IMPORTANCE RATING: 2.7/3.3 REQUIRED TOOLS AND EQUIPMENT: ECA-0.0 4 PREPARED / REVISED BY: M DATE: 7 APPROVED BY: [ DATE: 4,//3/4J REVISION #: 0 DATE: 3/21/97 JPM New-4 PAGE 1 OF 10
SAFETY CONSIDERATIONS: None EVOLUTION CONDITIONS: A loss of all AC power has occurred and ECA-0.0 is in progress. INITIATING CUES: You are the Primary AO. You have been directed to perform ECA-0.0 Attachment M, Local Operation and Vedfication of Primary Side Equipment. , l EVOLUTION STANDARDS: l l Trainee will perform ECA-0.0 Attachment M.
REFERENCES:
ECA-0.0, Loss of All AC Power SIMULATOR: N/A 4 JPM Nstw_-i PAGE 2 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
,s I
1. Obtain copy of ECA-0.0 Attachment M, Local Operation and Verification of Primary Side Equipment. Standard: Trainee is provided a copy of ECA-0.0 Attachment M when requested. O SATISFACTORY C UNSATISFACTORY COMMENTS: 1 i 2. I (.l
- Check BAST temperature greater than 120'F using surface thermometer or contact pyrometer. ,
Standard; Ae-eher
- T MIk T ' '#"
of The YouC. So ZNbitvMinis
+tal*Te S T'll'W6 a IObte r'e u"dQ*Y'1 in Th e deNTWI* * "" U"'ASJ'"
(60 / 'd f l Cue: When measured, BAST temperature is 130'F. pr y & d 6 heA. O SATISFACTORY C UNSATISFACTORY COMMENTS: JPM liby.-4 PAGE 3 OF 10 l _J
4 PERPORMANCE CHECKLIST j STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: - i ! i i l i 3. ' i ! i !-
- Check UM level greater than high suction Range for cooling pumps P 17A and B.
Standard: Checks suction flange which is at the north end of the pool approximately 3 feet under water. kre! ter ocassale dxv4 renucw;/refuef.wp, i I O SATISFACTORY O UNSATISFACTORY i : j COMMENTC: i a i l, r l i 4. t i
- Shut nanual casing vent isolation valves for LPSI and Spray pumps: CS-21,22,44 and LSI-67 ;
and 68. ' Standard: Five valves shut as above. t 4 i NOTE: These valves are located in an area which requires safety harnesses in l order to sooess by ladder. Trainee should go to top of the ladder and
; describe the loostion of the valves,as being next to the pumps on the next
- i. level. '
I 1 L O SATISFACTORY O UNSATISFACTOP.Y 1 ! COMMENTS: i. t L I ! j- t i-
) '
i
) ,.
j i - i i l JPM New-4 PAGE 4 OF 10
PERFORMANCE CHECKLIST
, ETEPS/ STANDARDS FOR SUCCESSFUL PERFORMANCE:
5.
- Shut RCP seal water inlet isolation and bypass valves SL 21,24 (RCP81); 8L 32,35 (RCPs2);
and SL-43,46 (RCPW3). Standard: Six valves shut as above. NOTE: These valves are in a high radiation area but can be seen from the HSPl valve room. Trainee should point them out to the evalustor. Cue: After these valves have been shut, cue that (1) the charging pumps have already been vented IAW OP 1 116, (2) no waste processing la in progress, and (3) no weste releases are in progress, O SATISFACTORY O UNSATISFACTORY COMMENTS: 6. Notify Control Room that ECA-0.0 Attachment M is completed. Standard: As above, O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 e JPM New_-4 PAGE 5 OF 10
EVOLUTION CONDITIONS: A loss of all AC power has occurred and ECA 0.0 is in pro 0ress.
'lNITIATING CUES:
You are the Primary AO. You have been directed to perform ECA-0.0 Attachment M, Local Operation and Verification of Primary Side Equipment. 1 I I f N) JPM New-4 PAGE 6 OF 10
JPM QUESTION #1 NEW 4 l i QUESTION: In conjunction with your supervisory actions during a loss of all AC you are required to make a report to the NRC regarding implementation of the E .iergency Plan. What is the time requirement to make this report? ANSWER: Por OP 1261, OPERATIONAL EVENT REPORTING, you must report within one hour of implementation of the E Plan per 10CFR50.72(a). 1 i l i 4 i I i SATISFACTORY: YES NO
REFERENCES:
SRO L-10.2 (page 3) OP 126-1 Attachment A
- TASK IMPORTANCE
- 2.1/4.3 4 TASK NUMBER: Generic 2.1.6 LEARNING OBJECTIVE: SNO-0302 5 TRAINEE ANSWER / COMMENTS:
i JPM New-4 PAGE 7 OF 10
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JPM QUESTION #2 . NEW-4
.s 9
QUESTION: You checked a flange at the Spent Fuel Pool. What is the function of that flange? How does it work? l ANSWER: The flange prevents the Sper)t Fuel Pool from draining in the event of a cooling system leak or rupture, if the Spent Fuel Pool level gets that low, air will be sucked into the flange, consequently causing the pumps to lose suction and also preventing a siphoning effect. SATISFACTORY: YES NO
REFERENCES:
AO-L 2.10 (;:?,na 3) TASK IMPORTANCE: 2.g/3.2 TASK NUMBER: K/A 033-K4.01 LEARNING OBJECTIVE: SFP-0401-11 TRAINEE ANSWER / COMMENTS: 4 JPM New-4 PAGE 8 OF 10
I JPM QUESTION #1 NEW 4 QUESTION: In conjunction with your supervisory actions during a loss of all AC you are required to make a report to the NRC regarding implementation of the Emergency Plan. What is the time requirement to make this report? l JPM New-4 PAGE 9 OF 10
JPM QUESUON #2 i NEW 4 i QUESTION: You checked a Mange at the Spent Fuel Pool What is the function of that flange?_ How does it work? JPM New-4 PAGE 10 OF 10
JOJ PERFORMANCE MEASURE---RO ADMIN P /4 tM 4 JPM NUMBER: New 32 TASK NUMBER: K/A 2 213 TITLE: VAllDATING WHITE TAG OUT ADEQUACY ! TIME CRITICAL: O YES N NO START TIME: O yES 5 NO STOP TIME: ; PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall 1 QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: N TO TRAINEE:
- 1. All actions in the plant will be SlM.ULATED The tralnee and examiner are llOl authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. . 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will ' role-play" these personnel.
EVALUAT'ON LOCATION: O PLANT N SIMULATOR N CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 Minutes IMPORTANCE RATING: 3.6/3.8 REQUIRED TOOLS AND EQUIPMENT: Procedure 0-14-1, Attachment A, B, and M PREPARED / REVISED BY: DATE: f7 APPROVED BY: [ DATE: 3/9) REVISION #: f 0 DATE: 3/19/97
,\X gw d
Ko JPMEeE-12., PAGE 1 OF 5
t SAFETY CONSIDERATIONS: None dVOLUTION CONDITIONS: l The plant is operating at 90% power. ' i l' INITIATING CUES:
- The SOS has just prepared a tagging order for E 5A per the tagout request form (Attachment M of j procedure 0141). The SOS has asked you to validate the adequacy of this tagout. l EVOLtJTION STANDARDS:
] When given a safety class tagging order, the tralnee will demonstrate the ability to verify tne adequacy of that tagging order, t
REFERENCES:
QA Procedure 0-141 j , FM 70A I i SIMULATOR: 1 N/A i NOTE: The Evaluator should provide a completed Attachment A & B of Procedure 0141, White Tag i Order Sheet, for E 5A, The Evaluator shall also provide a Tagging Order Request
- (Attachment M of 0141) for E 5A. The tagout of the JPM is attached, i
J 4 1 1 (# e JPM New 32 PAGE 2 OF 5
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ( 1. Trainee obtains tagging order. Standard: Student is handed previously prepared Tagging Order Sheet (procedare 0-141), Attachment A & B) and tagging Request Form (procedure 014-1, N.tachment M). NOTE: At this time, the trainee should ask all questions and clarify tho tagging request,if needed. l C SATISFACTORY C UNSATISFACTORY COMMENTS:
/
2.
' Validates adequacy of tagging order, Standard: Using FM's, trainee demonstrates boundaries necessary to isolate E 5A.
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New 32_ PAGE 3 OF 5
PERFORMANCE CHECKLIST ' STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 3.
' Signs "Tagout Adequacy Validated By'line on Tagging Order Form (Attachment A of procedure 0 14-1). 1 $
W dh 66liS[D#L i Standard: Trainee 41gns tagging order form after =t:f / !n; F-M that the tagging order is
- adequate.
1 NOTE: If the trainee feels that more tags are required, the tralnee should state what tags j should be added, if extra tags are added and do not effect the operabikty of the other service water heat exchangers (SWHX), the step is considered completed satisfactorily, if the trainee adds tags which effect the other SWHXs or deletes tags, the step is completed unsatisfactorily. O SATISFACTORY O UNSATISFACTORY ! COMMENTS: 4 i ).! I 4 r 1 i JPM New 32 PAGE 4 OF 5
EVOLUTION CONDITIONS:
- The plant is operating at 90% power.
INITIATING CUES: . The SOS has just prepared a tagging order for E 5A per the tagout request form (Attachment M of procedure 0-141). The SOS has asked you to validate the adequacy of this tagout. 1
. . 4 4
.ew =
JPM New 32- PAGE 5 OF S
i... MAINE YANKEE TAGGING ORDER MAINE YANKEE TAGGING ORDER
- Prepared By: Tags Checked and Equipment Date / /- -
Verified De-energtred/ Step 6.3.3: Issued By: Date / / Tagging Order Cleared: i i Tagged For PSS/505 Verify All Holds and Grumds idO/ PROC / ADMIN CONTh0L Removed: Tag Out . Valfdated By: Licensed ator COFONDir TACGrn AND REASDN-- Second Knowledgeable Authortzed Person (N/A1 Safety C1sss (1. 2. 3 o, IE) Yes No if Yes Independent verification is required and complete following:
- DUTY PSS SIGNATURE NOTES: O '
- 1. Permission tn release equipment 4
m
- 2. Equipment returned to service or 'I 1 functional test pendina ,
n . m ATTA09ENTS YES
- Iloid Sheet Panalaras Disabled:
Ground Tags
- Change Forms INDIV.
VERIF. IEIV. U POSITIGt VERIF. TAG VALVE. BREAKER INSTALLED INSTALLED ISIV. 12iV. FOR TAG RDfWED ROUWED POSITION BY BY DATE TAG IAG REMOVAL BY BY DATE NO. SWITOI OR SLIDE (P55/505) OPER 1 OPER 2 INSTALLED DECK CLEAkED (P55/5fE) o m .o LINK OPER 1 OPER 2 REM [NED = <n m
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Proc. No. 0 14 1 Rev. No. 18 ATTACHMENT B (Sheet 1 of 1) Page 56 of 74 o WW - EE w HBw"5 5 gs EV5
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Proc. No. 0-14 1 Rev. No. 18 Page 68 of 74 ATTACMENT H (Sheet 1 of 1)
._- TAGOUT REQUEST FORM
'fo: Plant Shift Superintendent / Shift Operating Supervisor:
It 's requested that the following equipment be tagged out, de-energized, drp'ned and depressurized as necessary to perform the maintenance described be oW. EQUIPMENT: DATE & TIME WORX WILL BEGIN: l MM: SAFETY CLASS: WORK TO BE PERFORMED: SPECIAL TAGGING INSTRUCTIONS OR SYSTEM LINEUPS: k;! , TAG TO: RESP. SECTION: SIGNATURE: REVidWED BY: Person Requesting Tags Operations DATE:
Proc. No. 0-14-1 ' Rev. No. 18 Page 68 of 74 '// ArtADeENT M (Sheet 1 of 1)
' c.c TAGOUT REQUEST FORM To: Plant Shift Superintendent / Shift Operating Supervisor:
It is requested that the following equipment be tagged out, de-enersized, drg< ned and depressurized as necessary to perform the. maintenance discribed be ow. EQUIPMENT: DATE & TIME WORX WILL BEGIN: E'5/f . WOh Q7, p p g SAFETY CLASS: f( 3 WORX TO BE PERFORMED: 0/egn an d i A6,olc f~[ femo vi ng de rvice ida Yer ll'4~ Ex<b"")ef'E"Nb'll5 SPECIAL ThiGING INSTRUCTIONS OR SYSTEM LINEUPS: Gul b2ll QA ls/g St4) < Qo] $9, // be r'eMovrCl' W 09 ls r&ntOveh ED N /988//I/L RE' S P. SECTION:jy/q,4g,,4,,c & SIGNATIFE: REVIEWED BY: Person Requesting ' lags Operations DATE:
MAINEYANKEEThGGINGORDER MAINE YANKEE TACGING ORDER NO- Page of Prepared By: Date / Tags Checked aruf Equipumt
/
Vertfled De energfred/ Step 6.3.3: Issued By: ' Date / / Tagging Order Cleared: Tagged ror Mesha// P5s/s0s vertry An noids and crounds WD/ PROC /ADNI;I CONTROL N- 99@ Removed: Tag Out Validated.Ey: Licensed ator COMPONENT TAGGED A E REASON-Second Knowledgeable Authorized Person (N/A) Safety Class (1. 2. 3 or IE) Yes #_ No If Yes. Independent vertfication is required and complete following: g DUTY PSS SIGNATURE NOTES:
- 1. Pemission to release equirent m
- 2. Equipment returned to service or M functional test pendino >
ATTAONENTS YES SQ Hold Sheet Panalams Disabled: lt Ground Tags Change forms *-* E IEIV. IEIV. U VERIF. POSITION VE RIF. TAG VALVE. BREAKER POSITION INSTALLED BY INSTALLED IEIV. !WIV. FOR TAG RDOVED REMDVED BY DATE TAG IAG 70 SWITOI OR SLIDE RIlOVAL BY BY DATE (P55/505) OPER 1 OPER 2 INSTALLED DECK yam LINK CLEARED (P55/505) OPER 1 OPER 2 REM [hTD - <= ,
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Proc. No. 0444 Rev. No. 18 ATTACHMENT B (Sheet 1 of 1) Page 56 of 74 C D
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JOB PERFORMANCE MEASURE p/ RO ADMIN E' JPM NUMBER: NEW 34 (AD-010313) TASK NUMBER: 1190100301 TITLE: Use of Survey Meters START TIME: STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are 1101 authorized by this document to actually perform any action in the plant.
- 2. High radiation areas will not be entered. Location and operation of equipment inside high radiation areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc ) should be directed to the evaluator, who will
- role play
- these personnel.
EVALUAllON LOCATION: O PLANT O SIMULATOR O CONTROL ROOM i APPROXIMATE COMPLETION TIME: 10 minutes IMPORTANCE RATING: 3.0 REQUIRED TOOLS AND EQUIPMENT: i
- 1. RO-20 PREPARED / REVISED BY: DATE:
1 APPROVED BY: DATE: 4 REVISION #: 0 DATE: 5/28/97 i LORC JPM NEW-34 (AD-0103M PAGE 1 OF 6 i
SAFETY CONSIDERATIONS: l None EVOLUTIONS CONDITIONS: The plant has experienced a large break LOCA with failed fuel. The core is being cooled in the recirculation mode. The hot leg injection valves will not operate from the EFW Pump Room. You have volunteered to enter the HPSI Valve Room to see why the valves will not open. The anticipated dose rate is 2 30 R/hr, INITIATING CUES: Report to the HP Checkpoint and obtain a RO 20 radiation dose rate meter. Inform the HP Technician that you will verify that the meter is ready for use. EVOLUTION _ STANDARDS: Trainee performs all four (4) checks to verify that the t.1eter is ready for use.
REFERENCES:
- 1. GET 20,'Use of Survey Meters"
- 2. 9 3113, CONTROL OF INSTRUMENTS
( ; .lMULATOR: N/A
\
l LORC JPM NEW-34 (AD 0103-13) PAGE 2 OF 6 e
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 1. i
- Verify current calibration label on the meter .
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: i i 3
- Verify proper physical properties. I Standard: Meter is in good physical condition, beta shield is closed.
O SATISFACTORY O UNSATISFACTORY COMMENTS: l LORC JPM NEW 34 (AD-0103-13) PAGE 3 OF 6 4 q n - , , - - , - ,-.e.,. .,--r,.. ,..,,--r... - - - - - - ,--,-,,.,.,,,,,.,n.,- -
, . , , . , . , . .,,,,,,,..,r,.,-,,... -.,-.-,-,...,,_.,n,.n.v.
- ,,a
PERFORMANCE CHECKLIST
- STEPS / STAND / ~;OS FOR SUCCESSFUL PERFORMANCE:
3.
- Perform a battery check of the instrument. i Standard: Verify both battery check positions are satisfied.
O SATISFACTORY O UNSATISFACTORY COMMENTS: 4. ( '
' Verify a source check of the instrument has been performed that day.
Standard: As above. Cue: You are now ready to enter the PAB. O SATISFACTORY O UNSATISFACTORY COMMENTS: .? s LORC JPM NEW 34 (AD-0103-13) PAGE 4 OF 6
7--....-. t PERFORMANCE CHECKLIST -l. STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: s ., 6. a i ' Ensure instrument is set for the anticipated rad!ation area. Standard: Instrument set on 50 R/hr scale.
- Cue: This completes this JPM.
l C SA?lSFACTORY- 0 UNSATISFACTORY I COMMENTS: 4 A 4 a f e. 1. I i i i ) 4 4 b i
)
i l' i i i 4
- LORC JPM NEW-34 (AD-0103-13) PAGE 5 OF 6 i
, EVOLUTIONS CONDITIONS:
The plant has experienced a large break LOCA with failed fuel. The core is being cooled in the recirculation mode. The hot leg injection valves will not operate nom the EFW Pump Room. You have volunteered to enter the HPSI Valve Room to see why the valves v.i; rot open. The anticipated dose rate is 2 30 R/hr. INITIATING CUES: 4 Report to the HP Checkpoint and obtain a RO 20 radiation dose rate meter. Inform the HP Technician that y.qu will verify that the meter is ready for use. J 4 9 I J LORC JPM NEW-34 (AD-0103-13) PAGE 6 OF 6
RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #1 Question: You are the spare RO when an ' ALERT" condition is declared per the Emergency Plan. Where do you report to during this classification? Answer. The spare RO will report to the Operations Support Center on the bottom floor of the StaN Building. i SATISFACTORY: YES NO
REFERENCES:
E-Plan Section 5, Fig 5.14 TASK IMPORTANCE: 3.3/3.1 TASK NUMBER: K/A Generic 2.4.39 LEARNING OBJECTIVE: AD-0102-11 TRAINEE ANSWER / COMMENTS
RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #1 Question: You are the spare RO when an "AIIRT" condition is declared per the Emergency Plan. Where do you repon to during this classification? . I I
RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #2 Question: What is the definition of an Unusual Event? Answer: Potential degradation of the level of safety of the plant. SATISFACTORY: YES NO
REFERENCES:
Procedure 2-50-0 TASK IMPORTANCE: 3.1/3.8 TASK NUMBER: K/A Generic 2.4.17 LEARNING OBJECTIVE: AD-0102-10 TRAINEE ANSWER / COMMENTS r
~
j RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #2 Question: What is the definition of an Unusual Event? i
n 'J rf yo RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #1 Question: You are the spare RO when an '&EBT_ condition is declared per the Emergency Plan. Where do you report to during this classification? Answer The spare RO will report to the Operations Support Center on the bottom floor of the Staff Building. ? E . SATISFACTORY: YES NO
REFERENCES:
E-Plan Section 5, Fig 5.14 TASK IMPORTANCE: 3.3/3.1 TASK NUMBER: K/A Generic 2.4.39 LEARNING OBJECTIVE: AD-0102-11 TRAINEE ANSWER / COMMENTS 1 4
. - .. 1 _ . _ ... . _ . _ _ . . - _ . _ . _ _ _ . _ _ . . _ . _ _ _ _ _ _ , . . . . _ . - . _ _ . . . ~ . . _ .
i, . i- RO ADMINISTRATIVE TOPICS t EMERGENCY PLAN j QUESTION #1 2 d Question: You are the spare RO when an "Al FRT" condition is declared per the Emergency Plan.
- Where do you report to during this classification?
1 4 1 I I 4 4 4 3 i I 4 i (- . L
RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #2 Question: What is the definition of an Unusual Event? Answer: Pc'.ential degradation of the level of safety of the plant. i T l SATISFACTORY: YES NO
REFERENCES:
Procedure 2 50-0 TASK IMPORTANCE: 3.1/3.8 4 TASK NUMBER: K/A Generic 2.4.17 LEARNING OBJECTIVE: AD-0102-10 TRAINEE ANSWER / COMMENTS 4 s s d i t t
./ RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #2 Question: What is the definition of an Unusual Event?
4 i< f
i ,
*g' d'
JOB PERFORMANCE MEASURE---RO ADMIN l JPM NUMBER: New-28 TASK NUMBER: K/A Generic 2.1.2 TITLE: PERFORMING CONTROL ROOM ACTIONS FOR SECURITY CODE RED TIME CRITICAL: NYES O NO START TIME: ALTERNATE PATH: 0 ESY 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are tLQl authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. i
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will ' role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR N CONTROL ROOM APPROXIMATE COMPLETION TIME: 15 minutes .h IMPORTANCE RATING: 3.0/4.0 REQUIRED TOOLS AND EQUIPMENT: 1, AOP 2 51
- 2. OP 1-12-6 PREPARED / REVISED BY: DATE: [/8/f7 APPROVED BY: DATE: t/[3)#7 /
REVISION #: e 0 DATE: 3/26/97 JPM New-28 PAGE 1 OF 10
SAFEiY CCeNSIDERATIONS: None EVOLUTION CONDITIONS: Security has just announced, " Security Code Red" over the FEMCO. INITIATING CUES: You are the Primary RO. The SOS has implemented AOP 2-51, RESPONSE TO SECURITY EVENTS, [ and has directed you to perform Attachment A. 4 EVOLUTION STANDARDS: j' Trainee performs Control Room response actions per AOP 2 51, Attachment A. 5
REFERENCES:
AOP 2 51, RESPONSE TO SECURITY EVENTS , OP 1-12-6, CONTROL ROOM VENTILATION j SIMULATOR:
- 1. Initialize to a full power IC.
- 2. Freeze simulator and tumover to trainee, 4
1 k 4
, JPM New-28 PAGE 2 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 1. _
- Shut both Control Room sliding doors.
Standard: Within 45 seconds el start time, perform the following:
- 1. Direct CAS officer to shut front door, ,
- 2. Shut rear door and report closure to CAS.
Cue: CAS officer reports that front sliding door is shut. NOTE: Record all times to nearest second. Once trainee has AOP 2-51 in hand,- then record the following times:
- 1. Start time (time trainee has procedure in hand):
- 2. Time both sliding doors shut:
i O SATISFACTORY O UNSATISFACTORY COMMENTS:
- 2. -
*Announce over FEMCO: " Security Code Red. Operators take defensive positions."
Standard: Within 60 seconds of start time, make above announcement. NOTE: Record time announcement made: O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-28 PAGE 3 OF 10
I PERFORMANCE CHECKLIST i STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
- Monitor the Security frequency on the Control Room radio console.
Standard: Within 60 seconds of start time, initiate monitoring of the Security Channel. While no action may be required to do so by STAR, the trainee should ensure the volume control is adjusted high enough to allow monitoring, as follows:
- 1. If Security Channel NOT selected, then ensure the UNSELECTED volume control is tumed up sufficiently to monitor communications on the right speaker.
- 2. If Security Channel SELECTED, then ensure the SELECTED volume controlis tumed up sufficiently to monitor communications on the left speaker.
NOTE: Record time volume control is verified to be turned up sumclently to ensure monitoring: O SATISFACTORY O UNSATISFACTORY CC/MMENTS: 4 j i
- 1 W
4 s JPM New-28 PAGE 4 OF 10 m
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4. Station c licensed operator in CAS to assist Security. Standard: Within 90 seconds, station a licensed operator in CAS or request that the SOS or PSS ensure this is done. (Most likely, the Secondary RO will be assigned to
- per.~orm this function unless an extra licensed operatorjust happens to be in the Control Room.)
NOTE: Record time that licensed operator is stationed in CAS: ) - O SATISFACTORY C UNSATISFACTORY COMMENTS: d 4 .I 1 i
- Request the PSS or SOS to contact the Security Ueutenant/ Sergeant in SAS directly and confirm that (1) the code RED is valid, (2) the intruder is in the protected area, a .d (3) the 1-security event is not a driil.
4 Standard: As above, i Cue: PSS or SOS has contacted SAS directly and cor. finned all of the above. O SATISFACTORY O UNSATISFACTORY COMMENTS: E JPM New-28 PAGE 5 OF 10
, PERFORMANCE CHECKLIST l
STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 6. 1 l
' Isolate the Control Room by shutting MOV-6014,6013,6010, and 6017.
l , Standard: As above. l l-1 i O SATISFACTORY O UNSATISFACTORY COMMENTS: i
- 7.
- Trip the plant and enter E-0, EMERGENCY SHUTDOWN FROM POWER OR SAFETY INJECTION.
Standard: Trainee trips the reactor manually. Cue: Secondary RO has been directed to perform E 0 immediate actions. SOS directs you to continue with AOP 2-51 Attachment A. , O SATISFACTORY O UNSATISFACTORY j COMMENTS: 4 JPM New-28 PAGE 6 OF 10
[ - PERFORMANCE CHECKLIST I l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ) t; . . a g, , 1' 'Take manual control of feedwater and increase SG levels to approximately 66% narrow range
- j. as quicidy as possible. i
- Standard
- Trainee raises SG levels to 66% NR quickly using MFW bypass valves or EFW t FCVs, as necessary. ,
i i i i i SATISFACTORY- 0 UNSATISFACTORY . 4 j COMMENTS. ! i l a ! 9. , m. i ! *When all SG levels are stable a. approximately 66%, then stop all RCP's. Standard: All RCPs are stopped. l' 1-4 i I SATISFACTORY O- UNSATISFACTORY C,OMMENTS: i 4 i -: t i i-1 3 J i l l-t l j' JPM New-28 PAGE 7 OF 10 1
- ~ - , , ,,w-,..- -- + , , , . - - , . - ...v.e-- e- -m-- --.w n- -- 4 4 -n,. e-we-y u -,e, - w..rw, ea-
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 10. Verify natural circulation. Standard: Check the following:
- 1. Core region subcooling greater than 21*F.
- 2. SG pressures' stable or decreasing.
- 3. WR T-hots stable or decreasing,
- 4. Core region temperatures stable or decreasing.
- 5. WR T-colds at saturation temperature for intact SG pressures (using MPT curve or steam tables).
Cue: After trainee checks these indications, then report that the Secondary RO will monitor these indications. NOTE: These items are listed in sisveral EOP attachments, such as ES-0.1 Attachment E. O SATISFACTORY O UNSATISFACTORY COMMENTS: I l JPM New-28 PAGE 8 OF 10
PERFORMANCE CHECKLIST s STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- Initiate breathing air supply (AW 1-12-6, Control '<oom Ventilation, Standard: Perform the following to isolate Control Room operations at Reactor Operating Conditions 4,5,6, or 7:
- 1. Dispatch an AO to ensure FN 15, Control Room exhaust fan is off, (See Cue.)
- 2. Ensure MOV-6017,6010,6013, and 6014 are shut. (Done in JPM step 6.)
- 3. Align both trains of Coritro! P,oom ventilation as follows:
Train A Train B FN 7A running FN-7B running D-6A and D-7A open D-6B and D 7B open FN 11A running FN-118 running D-4 and D-5 shut D-4 and D 5 shut 4, Verify breathing air supply is between 40 and 60 SCFM for mach train. Cue: a, it is not yet safe for operator movement (for stopping FN-15),
- b. After OP 1-12-6 ventilation Sneup has been completed, then cue that JPM is complete.
- c. Breathing air supply flow rate is 55 SCFM on each train.
U SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-28 PAGE 9 OF 10
l
, EVOLUTION CONDITIONS:
Security has just announced, ' Security Cod) R:d' cv;r ths FEMCO.
! 'NiTIATING CUES: l 1
You are the Primary RO. The SOS has implemented AOP 2 51, RESPONSE TO SECURITY EVENTS, and has directed you to perform Attachment A. 2 I 4 1 i l I I 1 i 4 i f i i JPM New-28 PAGE 10 OF 10
1 JOB PERFORMANCE MEASURE--RO 41 p l JPM NUMBER: New-8 TASK NUMBER: 062-A4.01
- TITLE: ,
Restoring Site Power from the 115KV Switchyard During Loss of All AC Power ' TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: O YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All act' .ns in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described,
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 30 Minutes - IMPORTANCE RATING: RO-3.3, SRO-3.1 REQUIRED TOOLS AND EQUIPMENT: ECA-0.0 OP 1-22-3 b PREPARED / REVISED BY: DATE: APPROVED BY: DATE: REVISION #: 0 DATE: 3/11/97 JPM New-8 PAGE 1 OF 26
SAFETY CONSIDERATIONS: Nono dVOLUTION CONDITIONS: A loss of all AC power has occurred and ECA 0.0 is in progress. All DGs and the 345KV Switchyard are unavailable. The 11SKV Switchyard has just become available up to Breakers 3R and 4R. All work on Buses 3 thru 6 has been completed. All ground trucks have been removed. Workers are clear of the Busses. 4 INITIATING CUES: 1 4 You are the secondary RO (BOP). The SOS has directed you to restore power to Buses 3 and 5 from
- the 11SKV Switchyard per ECA-0.0 Attachment P.
- EVOLUTION S rANDARDS
Trainee will energize Buses 3 and 5 from the 115KV Switchyard IAW ECA-0.0 Attachment P. }
REFERENCES:
- ECA-0.0, Loss of All AC Power j OP 1-22-3, Station Service Power Operation and Breaker Operation 1
, SIMULATOR: l 1 initialize to a 90% IC.
- 2. Insert malfunctions EG06 (failure of DG-2), EG04A and B (DG trip), ED03A and B (loss of X14
, and X16), EG02A and B (loss of main transformers). , 3. Place Breakers DG-1A, DG-18,4T6, STS,3R and 4R in PTL. Perform manual reactor trip and j perform actions of ECA-0.0 up to Step 10.
- 4. Clear malfunctions ED03A (X14) and ED03B(X16).
- 5. Reset all overcurrent/undervoltage relays. (remote function YP101) d
- 6. Freeze simulator and turn over to trainee.
V h i s 4 r 4 e j l l JPM New-8 PAGE 2 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 1.
Ensure control switches in ECA 0.0 Step 9 have been placed in PTL. Standard: Following are checked in PTL:
- LPSI pumps (P-12A, P-128, P-61S)
- Containment spray pumps (P-61 A, P-618, P 61S) -
- RCP4 (P-1-1, P 12, P 1-3)
- Primary water pumps (P-24A, P-248)
- Boric acid pumps (P-6A, P-6B P-6C) e HPSI pumps (P-14A, P-148, P-14S)
- Pressurizer heaters (E-2PA, E-2PB, E-2A thru E-2F) e EFW pumps (P 25A, P-25C) e MFW pumps (P-2A, P-28) e Heater drain pumps (P-62A, P-628) e Condensate pumps (P-27A, P-278, P-27C) e Raw water pumps (P 60A, P-608)
- Circulating water pumps (P-26A thru P 26D) e Screen wash pumps (P-63A, P 638) e EHC pumps (P-55A, P-558) e Turbine AC lube oil pumps (P-87, P-49, P-88) e Containment recirculation fans (FN.17-1 thru FN 17-6) e One PCC pump (P-9A or P-98)
- One SCC pump (P-10A or P-108)
O SATISFACTORY O UNSATISFACTORY COMMENTS: l JPM New-6 PAGE 3 OF 26
. _. .-. .. . =-= - - .-- - . . - - - -- . . - - - - - - - - - -
PERFORMANCE CHECKLIST
- STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
I
- 2.
l
- Verify transformer X-14 is available.
2 Standard: X-14 is available IAW evolution conditions. O SATISFACTORY O UNSATISFACTORY COMMENTS: e i i l 3.
- Obtain switching orders from Dispatcher to.re-energize reserve station transformers.
Standard: Dispatcher called. l ' Cued From Dispatcher - close T14H, synchronize across and close K69-7. j- v> O SATISFACTORY O UNSATISFACTORY ! COMMENTS: l ? 4 E 6 1 i JPM New-8 PAGE 4 OF 26 f
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 4. ,
'Close T14H.
Standard: Switch for T14H taken to close and then released. O SATISFACTORY O UNSATISFACTORY COMMENTS: 5.
- Synchronize across and close K69-7.
I Standard: SYN K69-7 placed ON, K69-7 closed, SYN K69-7 placed OFF. O SATISFACTORY O UNSATISFACTORY COMMENTS: JoM New-8 PAGE 5 OF 26
PERFORMANCE CH3CKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 6. Re-energize 4160 Gus 3 and 5. Standard: OP 122-3 section 6.15 obtained. i O SATISFACTORY O UNSATISFACTORY COMMENTS: 7. i Verify all work on Bus 3 is completed and workers are clear of the Bus. Standard: As above. Cue: Work is complete and workers are clear of Bus 3. O SATISFACTORY O UNSATISFACTORY COMMENTS: Il JPM New-8 PAGE 6 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 8. Verify no alarms on Section RS except for X-16 (RS-3-3, RS-4-3). Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS:
- 9. _
Ensure X-14 is energized and available to power Buses 3 and 4. Standard: 1. Check 115KV Section 69 bus voltage greater than 112 KV.
- 2. Check K-69-7 Section 69 load breaker shut.
4 3. Check T-14H X-14 disconnect shut O SATISFACTORY U UNSATISFACTORY COMMENTS: T JPM Nem-B PAGE 7 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 10. Ensure all ground trucks are removed from the Bus 3 cubicles or that Electrical Maintenance has verified that the ground truck is properly setup for energizing the Bus. Standard: AO would be sent to check this. Cue: Ground trucks are removed. O SATISFACTORY O UNSATISFACTORY COMMENTS: 11. Ensure Breakers 3R,3U in PTL. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM N_eyy-3 PAGE 8 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 12. Ensure following pumps and breakers in PTL: Bus _3 3091 3090 3111 3110 3131 3130 P 26A and C P.27A P-62A Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New 8 PAGE 9 OF 26
1 1< PF.RFORMANCE CHECKLIST , 3 J t
- STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
f , i 4 i 13.
- )
! Ensure the PT fuses are installed for Bus 3. . Standard: AO would be sent to protected switchgear room to C.o this, " l . i s Cue:~ s PT Buses are installed for Bus 3. V O SATISFACTORY O UNSATISFACTORY ! COMMENTSl
- P k
14. Ensure the DC Control Power breaker for Bus 3 is closed. Standard: AO would be sent to do this, Chk .3 DC Bus 1 BKR 19 is shut. -
.J
^
O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 l JPM New 8 PAGE 10 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 15. Ensure the Bus overcurrent relays are reset. Standard: 863 UHR and 863 RHR reset. C Both relays are reset. (Have simulator operator reset them,if nerassary.) O SATISFACTORY O UNSATISFACTORY I COMMENTS: l i 16. Rack up 3R. Standard: AO would be sent to do this, Cue 3R is racked up. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM Newd PAGE 11 OF 26
PERFORMANCE CHECKLIST
- STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
17.
' Shut reserve supply breaker 3R.
Standard: As above. , I O SATISFACTORY O UNSATISFACTORY COMMENTS: ENERGlZING BUS 5 FROM BUS 3 18. Reset trip flags on relay devices which may have fired. Standard; As above, s Cue: Relay flags are reset. O SATISFACTORY - O UNSATISFACTORY COMMENTS: JPM New-8 PAGE 12 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 19. Align 480V Bus power per applicable section of OP 122 3. Standard: See cue. Cue: Personnel have been dispatched to align 480V bus power. O SATISFACTORY O UNSATISFACTORY COMMENTS: f 20. Energize Bus 5 from Bus 3. Standard: OP 122 3 Section 6.18 obtained. O SATISFACTORY O UNSATISFACTORY COMMENTS: i l JPM New-8 PAGE 13 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: t 21. Verify all work on Bus S is completed and workers are clear of the Bus. l Standard: See cue. Cue: Work is complete and workers are clear of Bus 5. O a/La,aCTORy 0 UNSATISFACTORY
. . . , . ~ .
COMMENTS: 22 Ensure all ground trucks are removed from the Bus 5 cubicles or that Electrical Maintenance has verified that the ground truck is properly set up for energizing the bus. Standard: AO's would be asked to check this. Cue: Ground trucks are removed. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-8 PAGE 14 OF 26
PERFORfAANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 23. l Ensure Breaker STS is PTL. Standard: As above. l l 0 SATISFACTORY 'O UNSATISFACTORY COMMENTS: l I
~
24. Check DG 1 A output breaker in PTL. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-8 PAGE 15 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 25.
' Ensure Bus $ undervoltage relay is reset.
Standard: 27Y 5 reset. (white light is on) O SATISFACTORY O UNSATISFACTORY COMMENTS:
- 26. ,
l
- Ensure SIAS is reset.
Standard: Verify Si not actuated by checking 86 devices on back of IACB, or annunciators (- and ECCS lightbox indications. If actuated, then reset using SIAS reset switches. ' O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New 8 PAGE 16 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 37. Ensure the PT fuses are installed for Bus 5. Standard: AO would be sent to protected switchgear room to do this. (Cue PT fuses are installed for Bus 5. O SATISFACTORY O UNSATISFACTORY COMMENTS: 28. Ensure the DC Control power breaker for Bus 5 is closed. Standard: AO would be sent to check this. Cue: DC Bus 1 BKR 18 is shut. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-8 PAGE 17 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:- (,,. 29. Ensure following pumps and breakers in PTL: Bus 3 P 14A and S P 01A and S P 12A P 9A and B P 25C
'5071 5070 SR -
- Standard: As above.
I i l 0 SATISFACTORY O UNSATISFACTORY - COMMENTS: l l.
' t l
i . JPM New-8 PAGE 18 OF 26 i
...w - . , , , . , , - . - , , , _ - , , . , .,.-,,,,,r,- . . , , - . . , . - - , , , , , , . , ,---a, , + , - . - , . . , . . , . . , , , -
m ,. ..,.w. . . , .nm,.e,.,-
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 30.
- Ensure 3T5 is racked up.
Standard: AO would be sent to check this. Cue: 3TS is racked up. O SATISFACTORY C UNSATISFACTORY COMMENTS: 39. Ensure seismic wheel chocks installed on all breakers for Bus 5 that are to remain racked down. Standard: AO would be sent to check these. Cue: Wheel chocks are installed on all the Bus 5 breakers that remain racked down. O SATISFACTORY O UNSATISFACTORY COMMENTS:
)
y JPM New-8 PAGE 19 OF 26
l PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 32.
' Ensure Bus Tie enable switch SS 3T5 is in NORMAL.
Standard: Checks chrome key switch in normal. O SATISFACTORY O UNSATISFACTORY l COMMENTS: 4 i ( 33.
' Shut tie breaker 3T5.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: , jo\ 5 JPM Neydl PAGE 20 OF 26
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 34. Ensure breakers 3T5 is charged after closing. Standard: Trainee contacts AO to verify breakers charged after closing. l Cue: Breakers are charged, trip flags have been reset. O SATISFACTORY O UNSATISFACTORY COMMENTS: l l l f I JS. Align 480V power. Standard: See cue. i Cue: 480V power is being aligned, O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New 8 PAGE 21 OF 26 ;
EVOLUTION CONDITIONS: A loss of all AC power has occurred and ECA 0.0 is in progress All DGs and the 345KV Switchyard are unavailable. The 115KV Switchyard has just become available up to Breakers SR and 4R. All work on Buses 3 thru 6 has been completed. All ground trucks have been removed. Workers are clear of the Busses. INITIATING CUES: You are the secondary RO (BOP). The SOS has directed you to restore power to Buses 3 and 5 from the 115KV Switchyard per ECA 0.0 Attachment P. 4 JPM New 8 PAGE 22 OF 26 _J
JPM QUESTION #1 i -. NEW-8 QUESTION: What is the significance of the white light above 1R,2R,3R, and 4 R being out (i.e., not lit)? l ANSWER: There is no control power available or 115KV power is lost. 4 SATISFACTORY: YES. NO
REFERENCES:
R O L 5.2 TASK IMPORTANCE: 4.3/4.5 TASK NUMBER: 056 AA2.44 LEARNING OBJECTIVE: AC-0101 16(C) TRAINEE ANSWER / COMMENTS: JPM New-8 PAGE 23 OF 26
JPM QUESTION 62 NEW-8 QUESTION: What is the purpose of the reclose circuit on 115KV breakers (line 207 reclosing)(what does it do if in the *0n* position)? ANSWER: Associated breaker will reclose one second after tripping from a line protection signal if; A. Both sides of breaker are in phase or l B. One side of breaker is de-energized. ' l r - (k a'
,7, :
SATISFACTORY: YES NO
REFERENCES:
R O-L 5.2 l TASK IMPORTANCE: 3.3/3.1 l TASK NUMBER: 062 A4.01 LEARNING OBJECTIVE: AC-0101-4 TRAINEE ANSWER / COMMENTS: l 1 I i i JPM Haw.-J PAGE 24 OF 26
JPM QUESTION #1 NEW-8 QUESTION: What is the significance of the white light above 1R,2R,3R, and 4 R being out (i.e., not lit)? l l JPM New-B PAGE 25 OF 26
JPM QUESTION #2 NEW-8 QUESTION: What is the purpose of the reclose circuit on 11SKV breakers (line 207 reclosing)(what does it do if in the 'On" position)? I l . l I JPM New-8 PAGE 26 OF 26
JOB PERFORMANCE MEASURE---RO P JPM NUMBER: SNO-0905 1 2 TASK NUMBER: K/A 015A1.01 TITLE: PERFORMING NI CAllBRATION I TIME CRITICAL: O YES N NO START TIME: I ALTERNATE PATH: l O YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE; 1. All actions in the plant will be SIMULATED. The trainee and examiner are MQI authorized by this document to actually perform any action in the plant. t
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations. 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation. 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR D CONTROL ROOM APPROXIMATE COMPLETION TIME: 15 minutes-IMPORTANCE RATING: 3.5/3.8 REQUIRED TOOLS AND EQUIPMENT:
- 1. 3-1 31
- 2. Simulator Modcomp available PREPARED / REVISED BY: DATE: N APPROVED BY:
g [ DATE: h3/97 i-REVISION #: 10 DATE: 3/11/97 JPM SNO-0905-1-2 PAGE 1 OF 16 { I
SAFETY CONSIDERATIONS: None i EVOLUTION CONDITIONS: l The plant is steady state at power.
- INITIATING CUES
l You are the primary RO. You are to complete a daily calorimetric adjustrnent of Channel A in l accordance Procedure 3131, RPS CHANNEL ADJUSTMENT. > l EVOLUTION STANDARDS: After receiving the initiating cue, the trainee will complete an Ni calibration on Channel A.
REFERENCES:
3131, RPS CHANNEL ADJUSTMENT 3-12 3, SHORT FORM CALORIMETRIC PRR 92 041 PRR 92120 PRR 93-010 PRR 96:109 PRR 96102 SIMULATOR:
- 1. Reset to a steady state rated power IC.
- 2. Bring in the trainee and conduct a tumover. -
.6 JPM SNO-0905-12 PAGE 2 OF 16 I
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESv 'UL PERFORMANCE: 1. Obtain a copy of 3131, RPS CHANNEL ADJUSTMENT. f* l Standard: Trainee is provided a copy of 3131 when referenced. Procedure 3-12 3 may also be requested. O SATISFACTORY O UNSATISFACTORY COMMENTS: f sammu , 2. Complete BACKGROUND DATA and PARAMETER Se etion of Attachment B. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: - e f'# f r** f a. fN> ?,r ,
/
4,. A' f;/ 6
@9 9 ' > /"
d n. JPM SNO-0905-1-2 PAGE 3 OF 16
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: l 3. Check RPSCIP DVM calibration. I Standard: 1) METER IrJPUT switch placed in METER INPUT position. I
- 2) The three (3) reference voltage test pushbuttona (zero, +10V, 10V) depressed individually and indication checked within 5 mV of applied voltage (1.005V).
O SATISFACTORY O UNSATISFACTORY COMMENTS: 4. Check nuclear and AT amplifier calibration. Standard: 1) METER INPUT switch to NUCLEAR PWR position.
- 2) Calibrate pushbutton, depressed.
- 3) 200% i 1% indicated.
- 4) Repeat 1) thru 3) for AT PWR position.
O SATISFACTORY O UNSATISFACTORY COMMENTS: i JPM SNO-0905-1-2 PAGE 4 OF 16
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ! 5. - I* l
- Determine calorimetric power level.
Standard: Power level determined from PTID 1690 on MODCOMP. 4 O SATISFACTORY O UNSATISFACTORY COMMENTS:
- 6. _
V,
'Obtain Calorimetric Power, RPS excore power, and RPS AT power.
Standard: Data entered on CALORIMETRIC DATA section of Attachment B. O SATISFACTORY O UNSATISFACTORY COMMENTS: 9 JPM SNo-0905-1-2 PAGE 5 OF 16
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 7. i
- Calculate CALADJ.
Standard: CALADJ Data entered Attachment B. l O SATISFACTORY O UNSATISFACTORY l COMMENTS: 8. Record AS FOUND NUCLEAR PWR CAUBRATE Ni pot setting. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 4 JPM SNO-0905-12 PAGE 6 OF 16
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 9. l- ' Check nuclear power DVM indication within 5% of calorimetric power, then adjust to calorimetric power. Standard: 1) METER INPUT switch to NUCLEAR PWR.
- 2) Verify DVM reading within i 5% of power levelin JPM Step 5 (calorimeter '
power). 4 3) Unlock NUCLEAR PWR CALIBRATE pot.
- 4) Slowly adjust pot until DVM reading equal to calorimutric power. ,d l
i O SATISFACTORY O UNSATISFACTORY l COMMENTS: i a d i { 10. Engage pot locking device.. Standard: 1) As above.
- 2) If DVM indication shifts due to the locking action, pot is readjusted and j locked until satisfactory. .,
O SATISFACTORY O UNSATISFACTORY COMMENTS: k i i 4 JPM SNO-0905-12 PAGE 7 OF 16
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 11. Record AS LEFT NUCLEAR PWR CAllBRATE pot setting. Standard: As above. g,8 O SATISFACTORY C UNSATISFACTORY COMMENTS: 12. Record AS FOUND AT POWER CAllBRATE pot setting. Staridard: As above, O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM SNO-0905-1-2 PAGE 8 OF 16
~ ' ' - - ~ ~ - ' - - - ^
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCEGSFUL PERFORMANCE: 13.
' Check AT power DVM indication within i 5% of calorimetric power, then adjust to calorimetric power, Standard: 1) METER INPUT switch to AT PWR position.
l 2) Verify DVM reading within 15% of calorimetric power.
- 3) Unlock AT POWER CALIBRATE pot.
I /) Slowly adjust pot until DVM reading equal to calorimetric power. O SATISFACTORY O UNSATISFACTORY COMMENTS: I 14. Engage pot locking device Standard: 1) As above.
- 2) lE DVM indication shifts due to the locking action, THEN pot is readjusted -
and locked until satisfactory. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM SNO-0905-1-2 PAGE 9 OF 16
- . _ _ - . - . . . . . - . _ . - . - . _ _ = . - - . - - - - - . - ..-.. - . - -
l PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 15. Record AS LEFT AT POWER CALIBRATE pot setting. Standard: As above. 4 O SATISFACTORY O UNSATISFACTORY COMMENTS: 16. Check that DVM and MCB chart recorders for both nuclear power and AT power agree within 1 SR Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: . JPM SNO-0905-1-2 PAGE 10 OF 16
1 PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 17. E-Document latest TQ values. Standard: 1) Request TQ output on the Control Room INCA terminal by selecting Control Room INCA option from main menu.
- 2) Log the TQADJ factors from the OPERATIONS OUTPUT of the INCA output in the TO ADJUSTMENT DATA section of Attachment B.
O SATISFACTORY O UNSATISFACTORY [ COMMENTS: i 5 i JPM SNO 0905-1-2 PAGE 11 OF 16
EVOLUTION CONDITIONS: The plant is steady state at power. INITIATING CUES: You are the primary RO. You are to complete a daily calorimetric adjustment cf Channel A in accordance with Procedure 3131, RPS CHANNEL ADJUSTMENT, l I i e JPM SNO-0905-1-2 PAGE 12 OF 16
QUESTION #1 SNO-0905-1-2 QUESTION: How does the power range nuclear instrument signal enter the reactor protection circuitry (what prevents / allows a power range NI channel signal to be used as ' power
- signalin RPS)?
ANSWER: The power range NI channel enters the RPS in the TM/LP calculator. Here it is compared against that channels AT power signal and the higher of the two is auctioneered and passed through as the ' power level
- signal to RPS.
i SATISFACTORY: YES NO
REFERENCES:
RO-L-4.5 page 26, RO-L-4.2 page 23, drawing RPS-12 TASK IMPORTANCE: 4.1/4.2 TASK NUMBER: K/A 015 - K1.01 LEARNING OBJECTIVE: RPS-0101-4 TRAINEE ANSWER / COMMENTS: JPM SNO-0905-1-2 PAGE 13 OF 16
QUESTION #2 SNO-0905-1-2 QUESTION: The high voltage bistable is lit on the power range NI. What is the significance with respect to RPS channel operability? ANSWER: The RPS channel is considered operable by Tech Specs. (the HV B/s is tripped 1) when card is removed,2) if power supply fails or 3) if trip test switch is on. This will cause a symmetric offset trip signal to be sent to the RPS trip circuitry. As long as the channel is in the " tripped" condition it is operable per T.S. 3.9.) l . t SATISFACTORY: YES NO ) ,
REFERENCES:
RO-L-4.2, page 19, T.S. 3.9 TASK IMPORTANCE: 3.9/3.9 - TASK NUMBER: K/A 015-A3.03 LEARNING OBJECTIVE: NI-0102-5 TRAINEE ANSWER / COMMENTS: JPM SNO-0905-1-2 PAGE 14 OF 16 1
)
QUESTION #1 SNO-0905-1-2 QUESTION: How does the power range nuclear instrument signal enter the reactor protection circuitry (what prevents / allows a power range NI channel signal to be used as ' power" signalin RPS)? JPM SNO-0905-1-2 PAGE 15 OF 16
QUESTION #2 SNO-0905-12 QUESTION: The high voltage bistable is lit on the power range N1, What is the significance with respect to RPS channel operability? 9 JPM SNO-0905-1-2 PAGE 16 OF 16
JPM NUMBER: PPC-0901-1 2 TASK NUMBER: K/A 010-A4 01 TITLE: PERFORMING PORV VALVE STROKE TESTS TIME CRITICAL: O YES N NO START TIME: ALTERNATE PATH: 0 YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O FAIL QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this dncument to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and err;:gency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will" role-play' these personnel.
EVALUATION LOCATION: O PLANT h SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 5 minutes IMPORTANCE RATING: 3.7/3.5 REQUIRED TOOLS AND EQUIPMENT: OP 1-7 OP 3-1-20.4 PREPARED / REVISED BY: DATE: APPROVED ET DATE: REVISICN #: 4 DATE: 3/18/97 JPM_EP_C-0901-1-2 PAGE 1 OF 12 l _N
SAFETY CONSIDERATIONS:
~N:ne A
EVOLUTION CONDITIONS: The plant is shutdown and is preparing for a cooldown for a refueling outage. INITIATING CUES: i You are the Primary RO. You have been directed to perform PORV valve stroke testing per Or -7.- Section 6.2, Preparation for Plant Cooldown. I EVOLUTION STANDARDS: After receiving the initiating cue, the trainee will test both PORVs and ensure they are not leaking IAW OP 1-7 '
REFERENCES:
OP 1-7, PLANT COOLDOWN OP 3-1-20.4, IST VALVE TESTING AT COLD SHUTDOWN PRR 92-041 PRR 92-120 PRR 96-162 SIMULATOR:
- 1. Reset to a HSD IC.
- 2. ! Bring in the trainee and conduct a turnover. -
JPM PPC-0901-1-2 PAGE 2 OF 12 1
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. Obtain a copy of OP 17, PLANT COOLDOWN, and OP 3-1-20.4, IST VALVE TESTING AT COLD SHUTDOWN. F andard: Trainee is provided copies of procedures 1-7 and Section 6.24 of 3-1-20.4 when requested. O SATISFACTORY O UNSATISFACTORY COfc1MENTS: 2. Reference WO system to determine if components require function testing or Work Order not complete. Standard: Check with SOS. - Cue: No Work Orders or Functional Testing. ; O SATISFACTORY O UNSATISFACTORY - COMMENTS: JPM PPC-0901-1-2 PAGE 3 OF 12 u
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3. Reference surveillance procedure 3-1-7. Standard: 3-1-7 referenced. Cue: When trainee goes to get 3-1-7, say BOP will reference 3-1-7. O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 - Verify plant cooldown is in progress and OP 1-7 has directed the PORVs to be tested. Standard: As above per initiating condi. ions. O SATISFACTOF Y O UNSATISFACTORY COMMENTS: 1 N. JPM PPC-0901-1-2 PAGE 4 OF 12
PERFORMANCE C:- CKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: p r 5.
' Obtain PSS permission to perform this subsection.
Standard: As above. l l Cue: PSS permission obtained. l 0 SATISFACTORY- 0 UNSATISFACTORY COMMENTS:
~1
' Shut pressurizer PORV isolation MOVs PR-M 16 and 17.
Standard: As above. ' O SATISFACTORY O UNSATISFACTORY COMMENTS: w JPM PPC-0901-1-2 PAGE 5 OF 12 l _J
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 7.
- Cycle pressurizer PORV PR-S-14 and verify proper position indication.
Standard: 1) Place control switch in OPEN.
- 2) Verify red light on.
- 3) Place control switch in AUTO. / b
- 4) Verify green light on and red light out.
O SATISFACTORY O UNSATISFACTORY COMMENTS: I d.
- Cycle pressurizer PORV PR-S-15 and verify proper position indication.
Standard: 1) Place control switch in OPEN.
- 2) Verify red light on.
- 3) Place control switch in AUTO. ) M
- 4) Verify green light on and red light off.
C 0 SATISFACTORY O UNSATISFACTORY COMMENTS: JPM PPC-0901-1-2 PAGE 6 OF 12
i PERFORMANCE CHECKLIST j STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: (. *
* - 9.
*Open PR-M-16 and 17.
i Standard: As above. 4 . O SATISFACTORY O UNSATISFACTORY I COMMENTS:
- 10. _
s (":
- Monitor for indications that PORVs are NOT leaking.
Standard: 1) TE-106, PORV LINE TEMP - approximately 130-140*F (Tl-150). l 2) QT Level and pressure - constant (LI 116K, PI-116K).
- 3) Pressurizer pressure - constant (PC-101X 101Y; PR 101X, Y).
~
- 4) Acoustic accelerometer - not alarming (HI ALARM LEDs off).
Cue: JPM is complete. O SATISFACTORY O UNSATISFACTORY COMMENTS: i I i U JPM PPC-0901-1-2 PAGE 7 OF 12
. EVOLUTION CONDITIONS:
The plant is shutdown and is preparing for a cooldown for a refueling outage. INITIATING CUES: You are the Primary RO. You have been directed to perform PORV valve stroke testing per OP 1-7, Section 6.2, Preparation for Plant Cooldown. JPM PPC-0901-1-2 PAGE 8 OF 12
QUESTION #1 PPC-0901-1-2 QUESTION: How are the backup heaters operated from the switchgear room? Which buses have backup heaters associated with them? ANSWER: Buses 9,10,11,12,13, & 14 each have a backup heater powered from the respective bus. Heaters are operated by taking the normal / emergency switch to emergency and pressing the open/close pushbuttons as desired. l l SATISFACTORY: YES NO
REFERENCES:
RO-L-2.4, (page 12) TASK IMPORTANCE: 3.0/3.4 . TASK NUMBER: K/A 010-K2.01 LEARNING OBJECTIVE: PPC-0102-10 TRAINEE ANSVER/ COMMENTS: JPM PPC-0901-1-2 PAGE 9 OF 12
QUESTION #2--
- PPC-0901 1-2
- QUESTION: What are two (2) reasons for minimum spray bypass flow?
ANSWER: Prevent thermal shock to spray nozzle and equalize RCS and PZR boron concentration. i l 3 SATISFACTORY: YES NO
REFERENCES:
RO-S-2.3 (page 8) TASK IMPORTANCE: 2.7/2.9 TASK NUMBER: K/A 010-K4.01- -
- LEARNING OBJECTIVE: PPC-0102-9 TRAINEE ANSWER / COMMENTS:
w JPM PPC-0901-1-2 PAGE 10 OF 12
QUESTION #1 PPC-0901-1-2 QUESTION: How are the backup heaters operated from the switchgear room? Which buses have backup heaters associated with them? l 9 JPM PPC-0901-1-2 PAGE 11 OF 12 o
QUESTION #2.
- PPC 0901-1-2 QUESTION: : What are two (2) reasons for minimum spray bypass flow?
i l p_ 3
.i.
4 JPM PPC-0901-1-2 PAGE 12 OF 12
JOB PERFORMANCE MEASURE---ROA h Id* JPM NUMBER: New - 23 TASK NUMBER: K/A 003 A4.01
'~ ESTABLISHING RCP START CRITERIA FOLLOWING REACTOR TRIP TITLE:
TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: O YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
, 3. All controlled references normally available may be used. Control Room procedures and
._ emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will" role play" these personnel.
EVALUATION LOCATION: O PLANT h SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 minutes IMPORTANCE RATING: 2.9/2.9 REQUIRED TOOLS AND EQUIPMENT: ES-0.2 PREPARED / REVISED BY: DATE: I APPROVED By: DATE: s i
'- REVISION #: 0 DATE: 3/18/97 JPM New-23 PAGE 1 OF 15
SAFETY CONSIDERATIONS: None dVOLUTION CONDITIONS: An l&C technician error inadvertently caused a reactor trip from 90% power. The transfer of Buses 1
- and 2 to the reserve transformer occurred slower than normal and resulted in all three RCPs tripping on uno'srvoltage. Following completion of ES-0.1, a trancition was made to ES-0.2, INITIATING CUES:
You are the primary RO. You have been directed to try to start RCP #1 LAW ES-0.2, Step 1. L, EVOLUTION STANDARDS: l Trainee will start RCP#1 LAW ES-0.2.
REFERENCES:
ES-0.2, Natural Circulation Cooldown 4 SIMULATOR: (1) Initialize to a 90% IC. (2) Manually trip reactor. 4 (3) Stop all RCPs and place all RCP bearing lift pump "ma3ter" switches in OFF on back of MCB. (4) Perform stabilizing actions of ES-0.1 up to and including Step 9. (5) Freeze simulator and turn over to trainee. r 1 JPM New-23 PAGE 2 OF 15
PERFORMANCE CHECKLJST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: p 1. Obtain EOP ES-0.2. Standard: Control Room EOP Book opened to ES-0.2. O SATISFACTORY O UNSATISFACTORY COMMENTS: l 3 2. Go to Attachment A of ES-0.2. Standard: EOP ES-0.2 opened to Attachment A. Cue: If asked, total seal cooling has not been lost greater than 30 minutes. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-23 PAGE 3 OF 15
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3. Verify CIS "86" devices reset. Standard: Check ECCS lightbox indications normal (CIS A and CIS-B white lights off) and CIS "86" devices C1SA1, C1SA2, C1SA6, C1SB3, C1SB4, and C1SBS reset on back of main control board (white light on). O SATISFACTORY O UNSATISFACTORY r COMMENTS: l l l
- 9. ,
- Check power available to RCPs.
Standard: Check Bus 1 energized by voltage indication. O SATISFACTORY O UNSATISFACTORY COMMENTS: l JPM New-23 PAGE 4 OF 15
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5. Check RCS hot and cold leg loop isolation valves open. Standard: Check RCS Loop 1 loop isolation valves RC-M 11 and 12 open. Note: Power is normally tagged removed to these valves, so they have no position Indication. Trainee may check tags in place and rely on prior shift operation at full RCS loop flow to Infer they are open, or may request an AO to check position locally. Tag check and prior shift experience is sufficient for this step. Cue: When asked, RC-M-11, and 12 are open. O SATISFACTORY O UNSATISFACTORY COMMENTS: 6.
- Check RCP #1 oil pumps running in AUTO.
Standard: On back of MCB, place master switches for RCP #1 bearing lift and backstop oil pumps in AUTO. On front of MCB, place RCP#1 oil pump control switch in AUTO and verify tw.g red lights above the oil pump control switch come on. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-23 PAGE 5 OF 15
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 'C-7, I Check PCC System in operation. Standard: PCC Pump P 9A or P-9B running. l 0 SATISFACTORY O UNSATISFACTORY COMMENTS: 8. Check pressurizer spray valves closed. t Standard: Check PR-A-1 and PR-A-2 closed. O SATISFACTORY O UNSATISFACTORY COMMENTS: j i _JPM New-23 PAGE 6 OF 15
, PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 9 Check NPSH sufficient for RCP operation per TDB Figure 1.2.3 series. Standard; As above. RCS pressure-temperature point is above and to left of the RCP NPSH curve on TDB Figure 1.2.3.1. O SATISFACTORY O UNSATISFACTORY COMMENTS: 10 Check RCS WR Tcolds less than minimum pressurization temperature (411*F). Standard: WR T-colds are greater than 411'F. Note: RCS WR T-colds should be greater 411*F at this point (expected) therefore, no action is required in this step. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-23 PAGE 7 OF 15
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 11. If PCC to RCP motors and seals not in service, but seal water has remained in service, then establish PCC cooling IAW AOP 2 50 prior to starting an RCP, Standard: Check PCC-M-150,219, 252, and 254 open. Determine that PCC IS in service to RCP motors and seals and that performance of AOP 2-50 is NOT required. O SATISFACTORY O UNSATISFACTORY COMMENTS: I ? 12. l If both PCC and seal water supply flow not in service, then place in service IAW AOP 2-50 prior l to restarting an RCP. Standard: Determine that PCC IS in service per Step 11 above and that performance of AOP 2-50 is NOT required. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-23 PAGE 8 OF 15
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 13. If seal water supply is not in service but PCC has remained in service, then establish it IAW AOP 2-50, Standard: Determine that seal water supply IS in service with flow to the seals and that performance of AOP 2-50 is NOT required. - O SATISFACTORY O UNSATISFACTORY j COMMENTS: l l l l \ 14. Check seal water return valve for RCP#1 open. Standard:- SL-M-29 is open. Note: Per STAR, trainee should also check SL-A 92 and SL-A-53 open to complete seal return path to VCT. However, this is not a critical task per ES-0.2 guidance. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-23 PAGE 9 OF 15
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 15.
' Start RCP #1, Standard: As above. Place RCP P-1 1 control switch to START, check that amps peg high
, and return to normal range. Note: By STAR, before startire RCP, verify that two red lights to right of RCP control switch are on (indicates lift oil pressure 1900 psig interlock is satisfied) White light to right of RCP control switch is not used. O SATISFACTORY O UNSATISFACTORY l COMMENTS: 9 ( JPM New-23 PAGE 10 OF 15
EVOLUTION CONDITIONS: An l&C technician error inadvertently caused a reactor trip from 90% power. The transfer of Buses 1 and 2 to the reserve transformer occurred slower than normal and resulted in all three RCPs tripping on undervoltage. Following completion of ES-0.1, a transition was made to ES-0.2. INITIATING ut)ES: You are the primary RO. You have Deen directed to try to start RCP #1 LAW ES-0.2, step 1. JPM New 23 PAGE 11 OF 15
JPM QUESTION #1 l l NEW 23 QUESTION: What effect does stopping an RCP (assume three i.re operating) have on the reactor protection system trip bins? t ANSWER: This condition will generate a low flow trip on each channe! vt .1PS (due to low SG differential pressure (trip comes in @93% flow)). i SATISFACTORY: YES NO
REFERENCES:
RO-L-4.5 TASK IMPORTANCE: 3.9/4.2 . TASK NUMBER: K/A 003 - K3.04 LEARNING OBJECTIVE: RPS 01012 TRAINEE ANSWER / COMMENTS: i JPM New-23 PAGE 12 OF 15
JPM QUESTION #2 NEW 23 QUESTION: Why is it necessary to rapidly pass through the 1025 psig to 1250 psig region when performing a plant heatup (WRT the RCP)? ANSWER: This is the point at which the thrust on the RCP shaft shifts from downward to upward (thrust reversal). i SATISFACTORY: YES NO
REFERENCES:
OP 1 1 (Caution on page 26) TASK IMPORTANCE: 3.4/3.4
- TASK NUMBER: K/A 003 - A1.07 LEARNING OBJECTIVE: RCP - 0902 2 TRAINEE ANSWER / COMMENTS:
JPM__ New 23 PAGE 13 OF 15
. . - - _.=.-_- - . -. =-. -,
l JPM QUESTION #1 NEW 23 i l l ' QUESTION: What effect does stopping an RCP (assume three are operating) have on the reactor protection system trip bins? l l l 1 ( l JPM New 23 PAGE 14 OF 15
JPM QUESTION #2 NEW 23 QUESTION: Why is it necessary to rapidly pass through the 1025 psig to 1250 psig regior) when performing a plant heatup (WRT the RCP)? JPM New-23 PAGE 15 OF 15
JOJ PERFORMANCE MEASURE---RO N h JPM NUMBER: EAS-0901-1-1 TASK NUMBER: K/A 029 EA1.12 TITLE: PERFORMING FR S.1 IMMEDIATE ACTIONS . TIME CRITICAL: O YES W NO START TIME: 1 ALTERNATE PATH: NYE< O NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: OL.t of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE: 1. All actions in the plant will be SIMULATED. The trainee and examiner are NQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high alrborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room 3rocedures and emergency station procedures should not be removed from their storage ocations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play' these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 10 Minutes IMPORTANCE RATING: 4.1/4.0 REQUIRED TOOLS AND EQUIPMENT: None PREPARED / REVISED BY: ' JA) DATE: h APPROVED BY: [ DATE: 1,//3/9/ REVISION #: f 1 DATE: 3/18/97 JPM EAS-0901-1-1 PAGE 1 OF 14
SAFETY CONSIDERATIONS: None i EVOLUTION CONDITIONS: A The plant was at 100% power when a reactor trip was attempted. Plant response was that rods did flQIinsert. INITIATING CUES: You are the RO on watch. The SOS directs you to perform all the immediate actions of FR S.1. These actions are to be performed from memory. (You are to perform actions on both sides of MCB.) EVOLUTION STANDARDS: After assuming the controls in the Simulator, the trainee wul perform all the required immediate actions of FR S.1 from memory.
REFERENCES:
FR S.1, NUCLEAR POWER GENERATION /ATWS PRR 96109 PRR 96162
SIMULATOR:
- 1. Reset to an at power IC.
- 2. Insert malfunctions RD08A and RD088.
- 3. 10 Buses 9 & 12 feeder breakers closed (BKRS 3090,3091, and 4120,4121).
- 4. Drop two rods to provides a realistic reason to require a reactor trip (RD01).
- 5. Bring in the trainee and conduct a turnover. -
k. I JPM EAS-0901-1-1 PAGE 2 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1.
' Attempt reactor trip by depressing Rx trip buttons.
=t Standard: Depress RT 1 and RT 2 reactor trip pushbuttons. N, depress RT 3 and RT-4 pushbuttons.
O SATISFACTORY U UNSATISFACTORY COMMENTS: 2.
' Verify reactor RQI tripped, Standard: 1. Trip breakers verified closed.
- 2. WR power levels verified not decreasing.
- 3. More than one rod bottom light verified not lit.
O SATISFACTORY O. UNSATISFACTORY COMMENTS: JPM EAS 0901 1 1 PAGE 3 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
' Depress ATWS DSS A Trip and B Trip pushbuttons simultaneously. ,
Standard: Depress ATWS DSS A Trip and B Trip pushbuttons simultaneously (MG 1 A and MG-1 B). O SATISFACTORY O UNSATISFACTORY COMMENTS: l t.
- Check CEDM Bus undervoltage lights not lit.
Standard: 4 red lights off (UVC-1,2,3,4) O SATISFACTORY O UNSATISFACTORY COMMENTS: s JPM EAS-0901 1-1 PAGE 4 OF 14
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 l 5.
' Manually open 480V supply breakers to Buses 9 and 12. -
Standard: ACB 4121 to TRIP. ACB 3091 to TRIP. O SATISFACTORY O UNSATISFACTORY COMMENTS: 6.
'3Reclose 480V supply breakers to Buses 9 and 12.
Standard: ACB-4121 to CLOSE. ACB 3091 to CLOSE. O - SATISFACTORY O UNSATISFACTORY COMMENTS: JPMEAS-0901-1-1 PAGE 5 OF 14 , o
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 7.
- Manually trip turbine from MCB.
Standard: Place TT 1 and TT 2 to TRIP, O SATISFACTORY O UNSATISFACTORY COMMENTS: s 8,
- Ensure all turbine stop, governor, intercept and reheat stop valves are closed.
Standard: All 16 green CLOSED light on for turbine valves (SLL, SLU, SRL, SRU, GLL. GLU, GRL, GRU,1RL,1RR,2RL, ill, ilR,2lL, and 21R). O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM EAS-0901-1-1 PAGE 6 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 9,
- Ensure minimum feed for decay heat removal.
Standard: Recognizes that a main feed pump with MFRV bypass valves at 32% open position constitutes minimum feed for decay heat removal (HIC 1212,1222, 1232 output meters at approximately 32% with either P 2A or P 2B running). 1 O SATISFACTORY O UNSATISFACTORY COMMENTS: i ' O.
- Ensure at least 60 gpm running EFW pump, if initiated, Standard: If initiated, then P 25A and P 25C su,,,,, % sith HIC 1201 A,8, C allindicating greater than 60 gpm per running EFW pump.
O SATISFACTORY O UNSATISFACTORY COMMENTS: ( JPM EAS-0901 1-1 PAGE 7 OF 14 l
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 11. o k/
' Initiate Emergency Boration. 0 l
Standard: 1. Two boric acid pumps m ually started (P-6A, B C)
- 2. At least one charging p mp running (P 14A, B)
- 3. Boric acid valve o _to applicable charging pump (BA M 36 for P 14BC 4.(WA M 37 for P-14A)flC 212, CH-F 38 controller taken to manual and increased to maxiinum.
- 5. FIC 101 P,0 letdown flow controller adjusted as necessary.
O SATISFACTORY O UNSATISFACTORY COMMENTS: 12.
- Check PZR Pressure less than 2385 psig.
Standard: Check pressure <2385 psig on PR 102X or 102Y (PZR WR pressure). O SATISFACTORY C UNSATISFACTORY COMMENTS: JPM EAS-0901-1-1 PAGE 8 OF 14 w
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 13.
' Check VCT ievelless than 82%.
Standard: LIC 205 <82% indication. O SATISFACTORY O UNSATISFACTORY COMMENTS: 14.
' Manually insert control rods in manual sequential mode.
Standard: Control rod drive lever to IN position and MS pushbutton depressed until LIT. Rods observed driving in. Cue: End of JPM. 4 C SATISFACTORY O UNSATISFACTORY COMMENTS: JPM EAS-0901 1-1 PAGE 9 OF 14 l
EVOLUTION CONDITIONS: pla as at 100% power when a reactor trip was attempted. Plant response was that tods did INITIATING CUES: You are the RO on watch. The SOS directs you to perform all the immediate actions of FR S.1. These actions are to be performed from memory. (You are to perform actions on both sides of MCB.) o i 4 JPM EAS-0901-1 1 PAGE 10 OF 14
JPM QUESTION #1 EAS 09011 1
- f. .
QUESTION: ES-0.1,' Reactor Trip Response
- Step 4 RNO requires 2200 gallons of boric acid to be added for each stuck CEA. If the RCS boron concentration is 1000 ppm and two (2) CEAs were stuck, what is the final RCS boron concentration?
ANSWER: Approximately 1700 ppm boron. SATISFACTORY: YES NO
REFERENCES:
TDB Curve 1.2.5.1, ES 0.1 (step 4) TASK IMPORTANCE: 3.2/3.6 TASK NUMBER: K/A 004 A4.04 LEARNING OBJECTIVE: CRC-010197 TRAINEE ANSWER / COMMENTS: 1 JPM_E AS-0901-1-1 PAGE 11 OF 14
JPM QUESTION #2 EAS 09011 1 QUESTION: What is the relationship between symmetric offset and core power changec? Why do they occur? (Assume the RCS Temperature Program is used.) ANSWER: As core power increases, S.O. decreases and vice versa. They are caused by changes in the axial flux profile due to 1) changes in RCS temperature which affects MTC and 2) magnitude that MTC at top of core is greater than at bottom of core. SATISFACTORY: YES NO
REFERENCES:
RO L 1.12 (page 14) TASK IMPORTANCE: 3.4/3.7 TASK NUMBER: K/A 001 A2.06 LEARNING OBJECTIVE: CRC-010191, CRC-0101-107 TRAINEE ANSWER / COMMENTS: JPM EAS-0901-1-1 PAGE 12 OF 14
JPM QUESTION #1 EAS 0901-1 1 QUESTION: ES 0.1,
- Reactor Trip Response
- Step 4 RNO requires 2200 gallons of boric acid to be added for each stuck CEA. If the RCS boron ccncontration is 1000 ppm and two (2) CEAs were stuck, what is the final RCS boron concentration? l i
f 1 i i k 4 i s 1 N .. JPM EAS 0901-1-1 PAGE 13 OF 14
JPM QUESTION #2 EAS-0901 1 1 1 QUESTION: What is the relationship between symmetric offset and core power changes? Why do they occur? (Assume the RCS Temperature Program is used.) b JPM EAS-0901 1-1 PAGE 14 OF 14 T\
v Y
, JOB PERFORMANCE MEASURE--RO N k+ ,s JPM NUMBER: RMS-0901-1 2 TASK NUMBER: K/A 073 A4 02 TITLE: PERFORMING DAILY CHECK OF THE HIGH RANGE PVS MONITOR RM-3903 TIME CRITICAL: O YES 5 NO START TIME:
ALTERNATE PATH: < O YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE - . RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE;
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are NQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Com; loom 3rocedures and emergency station procedures should not be removed from their storage !ocations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will' role play' these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR h CONTROL ROOM APPROXIMATE COMPLETION TIME: 2.5 minutes IMPORTANCE RATING: 3.7/3.7 REQUIRED TOOLS AND EQUIPMENT: 3.1.29 PREPARED / REVISED BY: J b DATE: 7 APPROVED BY: [ DATE: L/!S/U REVISION #: 7 DATE: 3/1c/97 JPM RMS-0901-1-2 PAGE 1 OF 11
SAFETY CONSIDERATIONS: None 4 EVOLUTION CONDITIONS: The plant is steady state at power. INITIATING CUES: You are the secondary RO. You are to complete the daily check of high ran9e PVS monitor, RM 3903 IAW procedure 3.1.29, DAILY RADIATION MONITORING SYSTEM OPERATION TEST. EVOLUTION STANDARDS:
. After receiving the initiating cue, the trainee will corrplete the daily checks on the PVS high range noble -
gas monitor, RM 3903.
REFERENCES:
3.1.29, DAILY RADIATION MONITORING SYSTEM OPERATION TEST. PRR 92 041 PRR 92120 PRR 90-109 PRR 96162 SIMULATOR:
- 1. Reset to a power IC.
- 2. Bring in the tralnee and conduct a tumover.
I . kv JPM RMS-0901-1-2 PAGE 2 OF 11
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1.
) Obtain a copy of 3.1.29, DAILY RMS OPERATION TEST.
Standard: Trainee is provided a copy of 3.1.2g signed off up to the procedural step required.
- /
d g O SATISFACTORY O UNSATISFACTORY COMMENTS: 2. Verify proper operation by checking for normal indications. Standard: 1) Digital readout a 0.00 mR/hrif on scale.
- 2) Bar graph below readout agrees with digital readout if >0.3 mR/hr.
- 3) WARN light off.
- 4) HIGH light off.
- 5) FAlllight off.
- 6) RANGE light off (on if reading less than 0.1 mR/hr).
- 7) CHECK SOURCE light off.
O SATISFACTORY O UNSATISFACTORY COMMENTS: i JPM RMS-0901-12 PAGE 3 OF 11
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 3.
- Depress WARN pushbutton and verify digital readout indicates 4 mR/h.
Standard: As above. I f O SAT lSFACTORY O UNSATISFACTORY COMMENTS: n 4.
' Depress HIGH pushbutton and verify digital readout indicates 8 mR/h.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM RMS-0901 12 PAGE 4 OF 11
1 PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: r 5.
' Depress CHECK SCURCE pushbutton.
Standard: 1) CHECK SOURCE light on.
- 2) Digital readout increases to approximately 5 R/h.
- 3) Bar graph increases to app;oximately 5000 mR/h.
NOTE: WARN and HIGH alarm lights may come on, depending on setpoints. O SATISFACTORY O UNSATISFACTORY COMMENTS:
, S.
- Depress CHECK SOURCE pushbutton agair.
Standard: 1) CHECK SOURCE light off.
- 2) Digital readout and bar graph decrease to normal.
NOTE: Alarm lights should clear. . O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM RMS-0901-1-2 PAGE 5 OF 11
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: \ ,r 7. Verify proper operation by checking for normalindications. I Siandard: 1) Digital readout a 0.00 mR/hr if on scale. l 2) Bar graph below readout agrees with digital readout if >0.3 mR/hr.
- 3) WARN light off.
- 4) HIGH light off.
- 5) FAlllight off.
- 6) RANGE light of (on if reading less than 0.1 mR/hr.)
- 7) CHECK SOURCE light off.
O SATISFACTORY O UNSATISFACTORY COMMENTS: t 6. Check if it is the first Monday of the quarter. Standard: Check date. Cue: It is not the first Monday of the quarter. O SATISFACTORY O UNSATISFACTORY COMMENTS: (.- JPM RMS-09011-2 PAGE 6 OF 11
EVOLUTION CONDITIONS: The plant is steady state at power. \ h INITIATING CUES: F F ) You are the secondary RO. You are to complete the daily check of high range PVS monitor, RM 3903 LAW procedure 3.1.29, DAILY RADIATION MONITORING SYSTEM OPERATION TEST. 2
/
e 4 I 6 JPM RMS-0901-1-2 PAGE 7 OF 11 m
JPM QUESTION #1 ; RMS 0901-1-2 I l' QUESTION: Where are the main steam line radiation monitors physically located? ANSWER: Over the main steam lines in the Steam and Valve House near the SG safeties. 1 SATISFACTORY: YES NO
REFERENCES:
RO-L-9.5 (page 11) TASK IMPORTANCE: 2.8/2.9 TASK NUMBER: 072-K1.05 LEARNING OBJECTIVE: RMS-0101 1 TRAINEE ANSWER / COMMENTS: JPM RMS-0901-12 PAGE 8 OF 11
JPM QUESTION #2 RMS-0901-1-2 QUESTION: How does a Maine Yankee RMS Geiger Mueller detector respond when in an excessively high radiation area? 4
- ANSWER: A ' holding
- circuit keeps the reading high, rather than failing low.
J i SATISFACTORY: YES NO
REFERENCES:
RO-L-9.5 (page 7) TASK IMPORTANCE: 3.4/3.6 TASK NUMBER: K/A 072-A1.01 i LEARNING OBJECTIVE: RMS-0101-4 TRAINEE ANSWER / COMMENTS: 4 W
. s JPM RMS-0901-1-2 PAGE 9 OF 11
JPM QUESTION #1 RMS-0901-12 QUESTION: Where are the main steam line radiation monitors physicaly located? i JPM RMS-0901-1-2 PAGE 10 OF 11
.. ___ ___ _ N
JPM QUESTION #2 RMS-0901 1-2 QUESTION: How does a Maine Yankee RMS Geiger-Mueller detector respond when in an excessively high radiation area? a t JPM RMS-0901-1-2 PAGE 11 OF 11
JOB PERFORMANCE MEASURE-RO 41 @ JPM NUMBER: DG-0901-3-1 TASK NUMBER: KJA 064-A4.07 TITLE: PARALLELING DG-1A ONTO BUS 5 TIME CRITICAL: 0 YES N NO START TIME: ALTERNATE PATH: 0 YES 5 NO . STOP TIME: 1 PERFORMANCE TRAINEE: PERFORMANCE REWLTS: O PASS O FAll QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are NO.I authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally avait c le may be used. Control Room procedures and i emergency station procedures should r.-.t be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 5 minutes IMPORTANCE RATING: 3.4/3.4 REQUIRED TOOLS AND EQUIPMENT: 3-1-4.A, DG-1 A SURVEILLANCE TESTING PREPARED / REVISED BY:
' k DATE: b APPROVED BY: [ DATE: t/,/3/92 REVISION #:
, 9 DATE: 3/18/97 JPM DG-0901-3-1 PAGE 1 OF 12
SAFETY CONSIDERATIONS: , None EVOLtJTION CONDITIONS: A problem is discovered with DG-18. To prove Technical Specification operability of DG-1 A, it will be paralleled onto the emergency bus. INITIATING CUES: , The Secondary AO reports DG-1 A warmed up and at 950 rpm. You are directed to parallel it onto the emergency bus and adjust the KW and KVAR loadin0 IAW surveillance procedure 3-1-4.A. EVOLUTION STANDARDS: The trainee will flash the field, adjust voltage and speed, synchronize the diesel to tt e bus and adjust KW and KVAR loading to required amounts.
REFERENCES:
! 3-1-4.A, DG-1 A SURVEILLANCE TESTING PRR 92-041 PRR 92120
'~'
PRR 95-013 PRR 96-109 PRR 96-162 SIMULATOR:
- 1. Roset to power IC. .
- 2. Start DG-1 A.
- 3. Bring in the trainee and conduct a tumover.
JPM DG-0901-3-1 PAGE 2 OF 12 o
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 1. Obtain a copy of 314.A, DG-1A SURVElLt.ANCE TESTING. Standard: Trainee is provided a copy of 314.A signed off up the procedural step required.
./
O SATISFACTORY O UNSATISFACTORY COMMENTS: l 2.
- Flash the field.
Standard: Field flash pushbutton FF-DG1 A is depressed until a voltage of about 4 KV is indicated on VM-DG-1 A. Voltage should stabilize at about 4160 VAC. Cue: This is an "even" month. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM DG-0901-3-1 PAGE 3 OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
'Tum on synchroscope.
Standard: Insert red handle into SYN-DG1 A and place in ON. f C SATISFACTORY O UNSATISFACTORY COMMENTS: 1 4. ((:' ,,
- Adjust engine speed for synchronization.
Standard: Diesel Generator speed adjusted using SPD DG1 A until the synchroscope is rotating slowly in the fast (clockwise) direction (<2 RPM). O SATISFACTORY O UNSATISFACTORY COMMENTS: s-JPM DG-0901-3-1 PAGE 4 OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5.
' Adjust DG 1 A to match incoming and running voltages.
Standard: Diesel Generator output voltage adjusted using VR-DG1 A to match running (VM-SSR) and incoming (VM-SSI) voltmeters within i 1 volt. O SATISFACTORY O UNSATISFACTORY COMMENTS: 6.
- Parallel DG-1A onto Bus 5.
Standard: Shut DG-1A output breaker ACB-SDG1A when the synchroscope has made at least one complete revolution AND reaches a position of about 2 minutes of 12. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM DG-0901-3-1 PAGE 5 OF 12
r PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESS.~UL PERFORMANCE: (s
. 7.
3
' Load OG-1 A to 500 KW and O' KVARs.
Standard: Pick up 500 KW by placing SPD-DG1A to RAISE. Adjust KVARs to zero using VR-DG1 A (lower for KVARS IN, RAISE for KVARS OUT direction), e i O SATISFACTORY O UNSATISFACTORY COMMENTS: h 8. Turn off synchroscope. Standard: SYN-DG1 A to OFF position. O SATISFACTORY O UNSATISFACTORY COMMENTS: s. JPM DG-0901-3-1 PAGE 6 OF 12 l
- - - - _ _ _ . \
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 9.
- increase load to surveillance load.
Standard: Trainee adjusts load as appropriate, as follows:
- 1) SPD-DG1 A to RAISE to increase KW.
- 2) VR-DG1 A to RAISE to increase KVARS in OUT direction (clockwise).
Monthlv Load Parameters 2400 to 2500 KW 0 to 100 KVARS out , Cue: ,.lfMedfteljfaiq9egute /nonMt.dedlangeQBtirWMbu
\lsgmplete C SATISFACTORY O UNSATISFACTORY COMMENTS:
.~.
10. Compare the readings at the other location to verify that they are within 200 KW. Standard: Sends AO to DG-1 A room. Cue: They are within 200 KW and 250 KVAR. O SATISFACTORY O UNSATISFACTORY COMMENTS: y
./
JPM DG-0901-3-1 PAGE 7 OF 12
EVOLUTION CONDITIONS: A problem is discovered with DG-18. To prove Technical Specification operability of DG 1A, it will be paralleled onto the emergency bus. INITIATING CUES: The Seconog AO reports DG-1A warmed up anu at 950 rpm. You are directed to parallelit onto the emergency bus and adjust the KW and KVAR loading LAW surveillance procedure 3-1-4.A. i i 4 JPM DG-0901-3-1 PAGE 8 OF 12
-_-____--_.A
JPM QUESTION #1 DG-0901-3-1 4 QUESTION: What is the purpose of the 3T5 (4T6) normal / emergency keylock switch on the electrical board i (specifically, when would this switch be placed in emergency and why)? ANSWER: When in emergency it will open 3T5/4T6 when an SIAS signalis received. This prevents an overload of the diesel when it is paralleled to buses 3 and 4 during a loss of offsite power. 4 i l SATISFACTORY: YES NO
REFERENCES:
RO-L-5.4 (page 52) TASK IMPORTANCE: 3.6/3.9 ' TASK NUMBER: K/A 064-K3.03 LEARNING OBJECTIVE: DG-0102 5 TRAINEE ANSWER / COMMENTS: JPM DG-0901-3-1 PAGE 9 OF 12
JPM QUESTION #2 DG-0901-3-1 b QUESTION: ! What is the purpose of the load limit knob on the diesel generatorwoodward govemor? What position must it always be in? (Show picture of govemor to candidate.) ANSWER: The load limit knob allows the diesel to accept load by allowing the fuel rack to open/close the quantity of fuelinjected into the cylinders dependent on EDG load. The load limit knob must always be in the " Max Level" position when diesel is operable. 1 i F SATISFACTORY: YES NO
REFERENCES:
DG Tech Manual TASK IMPORTANCE: 3.1/3.2 TASK NUMBER: K/A 064 - A2.05 LEARNING OBJECTIVE: DG-0101-5, AD-0102-8 TRAINEE ANSWER / COMMENTS: JPM DG-0901-3-1 PAGE 10 OF 12
JPM QUESBON #1 DG-090131
- QUESTION: What is the purpose of the 3T5 (4T6) normal / emergency keylock switch ori the electrical board (specificaly, when would this switch be placed in emergency and why)?
4 JPM DG-0901-3-1 PAGE 11 OF 12
JPM QUESTION #2 DG-0901-3-1 QUESTION: What is the purpose of the load limit knob on the diesel generator woodward governor? What position must it always be in? (Show picture of govemor to candidate.)
/
I l L JPM DG-0901-3-1 PAGE 12 OF 12 l
JOD PERFORMANCE MEASURE---RO M p ( - JPM NUMBER: New-9 _ TASK NUMBER: K/A 055 EA2.03 TITL'E: PERFORMING LOCAL ACTIONS FOR PRIMARY SIDE EQUIPMENT FOR SBO l . TIME CRITICAL: NYES U NO START TIME: j NYES O NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside high these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will ' role-play" these personnel.
EVALU/sTION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 30 Minutes IMPORTANCE RATING: 3.9/4.7 REQUIRED TOOLS AND EQUIPMENT: AOP 2-48 PREPARED / REVISED BY; b DATE: !O APPROVED BY: [ DATE: L//'3h/ o i REVISION #: 0 DATE: 3/17/97 JPM New-9 PAGE 1 OF 13
SAFETY CONSIDERATIONS: None EVOLUTION CONDITIONS: A loss of all AC power has occurred with DG-2 available. AOP 2-48 is in progress. t INITIATING CUES:
~ You are the Primary AO.- You have been directed to perform AOP 2-48, Attachment A, Local Operation and Verification of Primary Side Equipment for SBO.
EVOLUTION STANDARDS: Trainee will perform AOP 2-48, Attachment A.
REFERENCES:
AOP 2-48, LOSS OF ALL AC DG-2 AVAILABLE/ STATION BLACKOUT. , SIMULATOR: N/A l JPM New-9 PAGE 2 OF 13
, a
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. Obtain a copy of AOP 2-48, Attachment A, Local Operation and Verification of Primary Side Equipment for SBO. Standard: Trainee is provided a copy of AOP 2 48 Attachment A when requested. I NOTE: Record start time: . O SATISFACTORY O UNSATISFACTORY COMMENTS: 2.
- Ensure VP-A-5 is shut.
Standard: Weehuse INd,cdTIva m 7pg of 4c7v anc iS cheMed O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-9 PAGE 3 OF 13 a
PERif0RMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
- Restart FN-25, steam and valve house exhaust fan if not, block open following doors:
. Door 2301, between Rx MCC Room and outside.
Door 105, between Rx MCC Room and Steam and Valve House. Door 2203, both double doors between CTMT hatch area and Steam and Valve House. Door 2201, both double doors between CTMT hatch area and outside. Standard: All four doors blocked open within 30 minutes of JPM start. Cue: FN-25 will NOT start. ggj ggo s ON mot 5l NOTE: MrS 9301 OMcI 9003 ON N"" E Okh a e< s:d e . ] While security doors should NOT actually be blocked okn for this JPM, the trainee should indicate specifically how he would block each door open. NOTE: Record time last door blocked open: O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
'Open breaker for MS-M-161.
Standard; As above. At MCC 8B in Rx MCC Room. O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 JPM New-9 PAGE 4 OF 13
PERFORMANCE CHECKLIST
, STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
5,
' Verify EFCV air compressors C-10A and/or C-10B running and pressurizing the EFCV al-header.
Standard: As above. Cue: C 10A is running as necessary to keep the EFCV air header fully pressurized. O SATISFACTORY O UNSATISFACTORY COMMENTS: l l I 6.
*Open MS-M-161 using manual operator.
Standard: Clutch lever depressed. Handwheel turned in counterclockwise direction until valve is open. O SATISFACTORY O UNSATISFACTORY COMMENTS: I JPM New-9 PAGE 5 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 7. Report to the SOS that MS-M-161 is open. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 8.
- Shut MS-M-255 using the manual operator.
Standard: Clutch lever depressed. Handwheel tumed in clockwise direction until valve is closed. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-9 PAGE 6 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL FERFORMANCE: 9.
- Ensure P-258 is operating normally by local verification.
Standard:g Enscharge Les7 of STCMS Thor 660ld he ehecKd -- hot ta Pmdar pressure checked. Steam inlet pressure checked. Govemor lube oil checked. Lube oil temperature checked. f Cue: P 258 is operating normally. O SATISFACTORY O UNSATISFACTORY COMMENTS: 10.
~~
- Ensure CS-M-91 and CS-M-92 are shut by localindication.
Standard: As above, C SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-9 PAGE 7 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 11,
- Ensure VP-A-1 is shut.
Standard: As above. Cue: , Valve is shut when trainee describes location when at locked door. O SATISFACTORY O UNSATISFACTORY COMMENTS: l 12. I Notify SOS that AOP 2-48 Attachment A actions have been completed. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-9 PAGE 8 OF 13
EVOLUTION CONDITIONS: A loss of cli AC power has occurred with DG-2 cvailable. AOP 2-48 is in progress. INITIATING CUES: You are the Primary AO. You have been directed to perform AOP 2-40, Attachment A, Local Operation and Verification of Primary Side Equipment for SBO. I 4 i JPM New-9 PAGE 9 OF 13
JPM QUESTION #1 New-9
' QUESTION: You would like to change the direction of a throttleable MOV in mid-stroke. What happens to the MOV if you abruptly change direction and how can you recover from this condition?
ANSWER: The motor may trip on over torque when abruptly changing d:rections, if this occurs you can:
- 1. Take valve switch to original direction valve was moving, the torque switch should reset, '
W > OR
- 2. Wait for the Belleville and washer spring pack to expand and reposition the worm to mid-position which will reset the torque switch.
NOTE: Either number 1 or 2 for full credit. l i SATI5 FACTORY: YES NO
REFERENCES:
RO-L-4.1 (page 18) . TASK IMPORTANCE: 4.2/4.5 TASK NUMBER: 068 AK 3.18 LEARNING OBJECTIVE: SNO-0101-4 TRAINEE ANSWER / COMMENTS: JPM New-9 PAGE 10 OF 13
)
i JPM QUESTION #2 i NEW-9 QUESTION: What is the significance of FN-35A and/or B being inoperable? (EFW pump room ventilation) ANSWER: If an EFW pump's associated fan is inoperable then that EFW pump is also inoperable (Fans are train separated FN-35A (MCC-7B/ Train B/P-25A) FN-358 (MCC-7A/ Train A/P-25C). These fans cooi all components inside the EFW Pump Room). ' i SATISFACTORY: YES NO ,
REFERENCES:
RO-L-3.13 TASK IMPORTANCE: 4.3/4.5 TASK NUMBER: 068 AA1.02 LEARNING OBJECTIVE: AFW-0101-22 TRAINEE ANSWER / COMMENTS: JPM New-9 PAGE 11 OF 13 I
JPM QUESTION #1 New 9 QUESTION: You would like to change the direction of a throttleable MOV in mid-stroke. What happens to the MOV if you abruptly change direction and how can you recover from this condition?
/
i JPM New-9 PAGti 12 OF 13
JPM QUESTION #2 NEW-9
' QUESTION: What is the significance of FN-35A and/or B being inoperable? (EFW pump room ventilation)
-L I
i h-i t
~I /
JPM New-9 PAGE 13 OF 13
bd JOB PERFORMANCE MEASURE-RO ALTERNATE 5 JPM NUMBER: Ne).10 TASK NUMBER: ____ K/A 009 EA1.04 TITLE: , ALIGNING P 7 TO A HPSI TRAIN TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: O YES M NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS C Fall QUESTION RESULTS: Out of Correct EVALUATOR DATE: SIGNATURE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. H!gh radirtion, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. I 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures snould not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR C CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 minutes IMPORTANCE RATING: 3.7/3.5 REQUIRED TOOLS AND EQUlF' MENT: AOP248 PREPARED / REVISED BY; #h . DATE: / [ APPROVED BY: [ DATE: 3/97
~..
REVISION #: (? 0 DATE: 3/19/97 JPM New-10 PAGE 1 OF 12
SAFETY CONSIDERATIONS: None EVOLUTION CONDITIONS: ) A loss of all AC power has occurred with DG 2 available. AOP 2-48 is in progress. L INITIATING CUES:
)
You are the Primary AO. You have been directed to perform AOP 2 48 Attachment B, Aux Charging to
*B' Train.
j EVOLUTION STANDARDS: Trainee will align P 7 to the *B' HSPI header IAW AOP 2-48 Attachment B.
/
REFERENCES:
AOP 2-48, LOSS OF ALL AC DG 2 AVA"dBLE/ STATION BLACKOUT. SIMULATOR: N/A i 4 JPM New-10 PAGE 2 OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1.
~,,
i, Obtain a copy of AOP 2-48, Attachment B, Aux. Charging to HPSl *B' Train. Standard: Trainee is provided a copy of AOP 2-48, Attachment B when requested. Cue: Men asked which HPSI header to align, evaluator will specify *B' header. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New 10 PAGE 3 OF 12
PERFORMANCE CHECKLIST
, STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
^
2. l ' Align the following valves: Vglyg Nomenclatga Position CH M-53 P 7 suction from RWST open CH-M 55 P 7 suction from VCT shut CH-56 P 7 suction from VCT/RWST open CH-58 P 7 suction from BAMT shut CH-60 P 7 suction from PWST shut T tA CH 155 P-7 PCVisolation open f ,M h CH 90 P 7 chem addition shut f CH 63 P 7 discharge open
, Y i
$ CH 113 P 7 suction from BATPs shut e Inlet to P 7 alt. cooler open
,,i' g Ihd LO-61 LO-60 Inlet to P 7 norm cooler shut (OD(i FN-61 P-8 alt, cooler fan Qd(),h start CH-57 PC 227 P 7 suction pressure
$$ ,\9 switch isolation open Oi P 7 alt cooier vent open (A. LO-63 H-65 P-7 disch to chg header shut
' CH-66 P 7 disch to fill header shut CPU 23 RWST suction to P 7 and P-8 locked open Stondard: As above, f
O SATISFACTORY C UNSATISFACTORY COMMENTS: f a JPM New.10 PAGE 4 OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
*lf aligning to HPSI Header B, then open the following:
I Valy.a Nomenclature HSI-49 P 7 disch to HPSI B header HSI-M-11 HPSI B to Loop 1 , HSI M 21 HPSI B to Loop 2 HSI M 31 HPSI B to Loop 3 l Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
- Increase P-7 discharge safety valve CH-P 156 pressure to 2350 psig on PC-401.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: I JPM New 10 PAGE S OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i
. 5.
I
' Set speed control lever to high speed per posted instructions, l Standard: As per posted instructions.
C SATISFACTORY O UNSATISFACTORY COMMENTS: 6, Verify suction pressure greater than 5 psia on PC-227. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 JPM New-10 PAGE 6 OF 12
. PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
7.
, Notify SOS at the ASP that P-7 is ready for operation. '
Stendard: As above.
, O SATISFACTORY O UNSATISFACTORY COMMENTS:
8. Ensure P 7 operation is satisfactory. I Standard: i Check (1) no abnormal noises, (2) oil level within normal band, and (3) pump discharge pressure less than PC-401 setting. L Cue: Cue that conditions are as listed in the standard above. O SATISFACTORY C UNSAT'SFACTORY COMMENTS:
\
JPM_Neye.10 PAGE 7 OF 12
. EVOLUTION CONDITIONS:
A loss of all AC power has occurred with DG 2 available. AOP 2-48 is in progress. INITIATING CUES: You are the Primary AO. You have been directed to perform AOP 2-48 Attachment B, Aux Charging to
*8' Train, i ) ;t 1
1 j s -- i e i i i-l: ia!, ) i i 1 1 I O 1 i t 1 4 . i I i s
- JPM New.10 PAGE 8 OF 12
- - . _ - - , . , _ _ . _ - , . - . _ , . - - - _ . _ - _ - - _ _ - - = . _ , _ _ _ _ _ _ , - _
JPM QUESTION #1 NEW 10 L QUESTION: What is the purpose of the P 7 normal / emergency switch on the PAB Emergency Panet? What
- is the relationship between local (PABEP), Altemate Shutdown Panel (ASP) and control room control of P 77 l ANSWER:
l The ASP Switch has ultimate control of P 7. If it is in normal P 7 it is controlled via the PABEP normal (control room)/ emergency (PABEP) switch. When the ASP switch is in altemate the ASP has control of P-7. i 0 SATISFACTORY: YES NO
REFERENCES:
RO-L-2.5 (page 65), STM Chap 34 (page 33) TASK IMPORTANCE: 3.8/3.4 TASK NUMBER: K/A 004-A4.08 LEARNING OBJECTIVE: CVCS-0103-5 TRAINEE ANSWER / COMMENTS: JPM New-10 PAGE 9 OF 12
JPM QUESTION #2 NEW 10 QUESTION: What is the flow path of vented gases from the Charging Pump Suction during normal operation? During SlAS? y
' 9 ANSWER:
g/ From pump suction through vent piping / tanks in upper level PAB to the PDT during normal ! operation. During SIAS it is automatically isolated. ' 4 1 i ?
, t SATISFACTORY: YES NO
REFERENCES:
RO-L-2.5 (pkge 29) 3 TASK IMPORTANCE: 2.8/3.1 TASK NUMBER: K/A 004-AK6.15 , LEARNING OBJECTIVE: CVCS-010214 TRAINEE ANSWER / COMMENTS: i
)
JPM New-10 PAGE 10 OF 12
JPM QUESTION #1 NEW-10 QUESTION: What is the purpose of the P 7 normal / emergency switch on the PAB Emergency Panel? What is the relationship between local (PABEP), Attemate Shutdown Panel (ASP) and control room control of P 77 a JPM New-10 PAGE 11 OF 12
JPM QUESTIUN #2 > NEW 10 r QUESTION: What is the flow path of vented gases from the Charging Pump Suction during normal operation? During SIAS? i l JPM New-10 PAGE 12 OF 12
JOB PERFORMANCE MEASURE--RO 40 U JPM NUMBER: NEW 3 TASK NUMBER: K/A 069 AA1.01 TITLE: ISOLATING CONTAINMENT LOCALLY DURING LOSS OF ALL AC POWER TIME CRITICAL: O YES W NO START TIME: ALTERNATE PATH: O YEG N NO STOP TIME: 3 PERFORMANCE l TRAINEE: l PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, generai work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play" these personnel.
EVALUATION LOCATION: NPLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 Minutes IMPORTANCE RATING: 3.5/3.7 REQUIRED TOOLS AND EQUIPMENT: ECA-0.0 PREPARED / REVISED BY: V M DATE: f !k7 APPROVED BY: DATE: 4 3/97 REVISION #: i 0 DATE: 3/17/97 JPM New-3 PAGE 1 OF 10
t SAFETY CONSIDERATIONS: None
, s EVOLUTION CONDITIONS:
A loss of all AC power has occurred and ECA-0.0 is in progress. The ECCS lightbox indicates that three CIS valves are NOT in their safeguards positions. INITIATING CUES: , 1 o You are the Primary AO. You have been directed to locally close LM-A-45, C A 15, and HPD A 17 LAW ECA-0.0, Attachment L.
, EVOLUTION STANDARDS:
Trainee will close LM-A-45, C-A 15, and HPD A 17 IAW ECA-0.0, Attachment L. ; 4
REFERENCES:
i ECA 0.0, LOSS OF ALL AC POWER. ! 4 SIMULATOR: l,', 1 i 1 4 4 4 s J i , JPM New-3 PAGE 2 OF 10
. , _ _ , - __ , . _ _ _ _ _ _ __ _ .~
PERFORMANCE CHECKLIST _ STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 1. -
Obtain a copy of ECA-0.0, Attachment L, Manual Actions for Containment isolation. 4 Standard: Trainee is provided a copy of ECA-0.0, Attachment L when requested.
/
O SATISFACTORY O UNSATISFACTORY COMMENTS: 2. 4F (. 'Close LM A-45, containment pressure sensing header isolation valve. Standard: Close IA-767 and bleed off the supply air regulator. Cue: Once air has been bled off, cue that LM A 45 has closed. O SATISFACTORY O UNSATISFACTORY COMMENTS: (- JPM New-3 PAGE 3 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
'Close C A 15 containment cerdox supply header valve.
Standard: # Cue: Close y,*ll have lA 1001 To IbiN r d r and 6/a bleed on the suNair reduhator. I L (- &/)lg)
, Once air has been blod o#, cue that C A 15 has closed.
1 , O SATISFACTORY O UNSATISFACTORY l COMMENTS: l 4.
.. *Close HPD A-17, main steam line header drains to condenser isolation valve.
Standard: Close IA 997 and bleed on the supply air regulator. Cue: Once air has been bled on, cue that HPD-A 17 has closed. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-3 PAGE 4 OF 10 ,
4 PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5. I Notify the Control Room that the valves have been closed IAW ECA 0.0, Attachment L. Standard: As above. i O SATISFACTORY C UNSATISFACTORY COMMENTS: l 4 JPM New-3 PAGE 5 OF 10 _a
EVOLUTION CONDITIONS:
^
A loss of all AC power has occurred and ECA-0.0 is in progress. The ECCS lightbox indicates that three l CIS valves are NOT in their safeguards positions, INITIATING CUES: I You are the Primary AO, You have been directed to locally close LM A-45, C-A 15, and HPD A 17 IAW ECA-0.0, Attachment L-l r (+ JPM New-3 PAGE 6 OF 10
JPM QUESTION #1
. NEW-3 QUESTION: During a containment isolation caused by a LOCA, what indications could an Operator use to verify that the containment sump pumps are not discharging their contents outside the containment building?
ANSWER: (Any one (1) answer for credit) '
- 1. Monitor the ADT levels to verify that isolation has taken place. (i.evels could be monitored on the PAB panel.)
OR
- 2. Locally check PD-A-124 in lower level PAB (this valve is in a High Radiation Area, Letdown Area southwest comer).
OR 3/. Verify PD-A-122 and/or PD-A 124 valve position on ECCS lightbox (SIAS/CIS section). OR
$. \'erify PD-A 122 and/or PD-A 124 valve position on ESF lightbox.
SATISFACTORY: YES NO
REFERENCES:
RO L 2.12 (page 18) TASK IMPORTANCE: 3.9/4.2 TASK NUMBER: K/A 103-A3.01 LEARNING OBJECTIVE: C-0101-12 TRAINEE ANSWER / COMMENTS: JPM New-3 PAGE 7 OF 10
JPM QUESTION #2 NEW-3 QUESTION: Where can you vertfy (other than locally) the position of LM A-55, 56,57 and 587 ANSWER: In the Control Room on the rear of Section 'C' above the SIAS/CIS/ RAS /CSAS 86 Devices.
/ '
I f SATISFACTORY: YES NO
REFERENCES:
Control Board TASK IMPORTANCE: 3.2/3.3 TASK NUMBER: K/A 103-A4.01 LEARNING OBJECTIVE: C-01015 TRAINEE ANSWER / COMMENTS: JPM New-3 PAGE 8 OF 10
JPM QUESTION #1 l --. NEW-3 l l QUESTION: During a containment isolation caused by a lor 41st indications could an Operator use to verify that the containtnent sump pumps are e ..diarging their contents outside the containment building? JPM New-3 PAGE 9 OF 10
JPM QUESTION #2 NEW13
/
QUESTION: Where can you verify (other than locally) the position of LM A-55,56, 57 and 587 1 j , A. o JPM New-3 PAGE 10 OF 10
MAINE YANKEE REACTOR OPERATOR EXAM FOR REVIEW COPY I l ALL ITEMS ON THIS EXAM ARE NElY
$ , ()
RO fiX AM RtiVil!W Generic Question A steam generator tube rupture is in progress. The steam generator subcooled margin monitor ! reads 38 E What must be done to equalize steam generator and RCS pressures? l l A. Open the turbine bypass valves to reduce steam generator pressure. B. Open the pressurizer spray valves to reduce RCS pressure. , C. Isolate the steam generators to increase steam generator pressure. D. Energize the pressurizer heaters to increase RCS pressure. i Answer: B j - Justificehn
- a. This action will increase the SMM reading.
- b. CORRECT. This actmn willl reduce the reading and equalize pressures
- c. This action will not change the SMM reading.
d This action will increase the SMM reading 1 Que%on Topic RelationsNp between subcooled marDin and S!G pressure v RO y SRO KIA Rating 34/36 CFR* RO $5 41 (b)(10) SRO $s 43 (b)($) System. Generic K/A # 2.1 32 ELOs RCS-0902-1
Reference:
E-3, SGTR I 4 l Page 1 of 100 4!13/97 v---- *- ""
RO EXAM REVIEW Generic Ouenon: The plant has just completed a chemistry hold at 2096 power and is escalating power at 109Vhour to $596. As plant temperature is changed, all four (4) power range channels receive an N1/ delta T power alarm. What action is required by the operators? A. The power increase can continue until 55% power at which time an Ni calibration and ) adjustment must be perfonned. B. The power increase should be tenninated and the operator can manually adjust the Ni potentiometer to clear the alarm. C. The power increase can continue as long as the N1/ delta T power deviation does not go offscale on the RPSCIP panel. D. The power increase should be terminated and an N1 calibration and adjustment should be performed to restore alarm operability. Answer. D Justircation:
- a. Tech Spec 4.1 1 requires that a calibration and adjustment be perfonned when in power operating condition if alarm is received.
- b. Manually adjusting the N1 potentiemeter is not allowed nor desirable as a less power limiting setpoint may be inserted
- c. Alarm is set at plus or minus 2.590. Once alarm is in, action should be taken to correct the deviation.
- d. CORRECT. This complies with the requirements of Tech Spec and RE guidance Ouestion Topic: Abihty to recognize TS entry criteria for Nt/dena T power Q RO 'y SRO K/A Rahng 3 44 0 CFR8 RO 55 41(b)(5) SRO $5 43(b)(2)
. System Genenc KIA # 2.1.33 ELOs SNO-0303-13 4 Reference; TS 4.1 (Table 411), RE 0.10 Page 2 of 100 4I13/97
RO I!X Ahi IlliVit!W Generic Quesbon-Which one of the following is an adverse consequence of containment control air pressure being less than 70 psig when in E-0," Reactor Trip and Safefy injection"? A. The pressurizer spray valves will fail open and result in loss of pressurizer pressure control i 4 B. The containment air recirculation fans will not maintain containment pressure <70 psia on
- LOCA.
! C. The primary component cooling supply to the reactor coolant pumps will be lost. D. The seal water supply and return How to the reactor coolant pumps will be lost. ! Answer. C Jusbimabon'
- a. The spray valves fail closed on a loss of air.
] b. The fans are not used for containment cooling once pressure rises above 35 psia.
- c. CORRECT. PCC A-252 will fail closed and result in a loss of cooling water Dow.
- d. The seal water pressure and How control valves are unaffected by this loss.
Ouestion Topic: Knowledge of system setpoints for EOP entry
& RO y SRO K/A Ratog 3 9i4.1 CFR#. RO 5s 41 (b)(10) SRO 55 43 (b)(s)
System Genenc K!A s- 2 4.02 ELos EAS 0101-7
Reference:
E-0 Step 34 Page 3 of 100 4/13'97
RO liXAM REViliW Generie Ovesbon During an accident, the following EOP's are entered (in order of entry):
- Entered E-0,"RX Trip' Safety injection" & EXITED at Step 10 due to loss of heat sink; Entered FR li.1, "lx>ss oflicat Sink", and referred to E-0 at Step 16 to complete immediate actions of E-0, - Continues in FR-il.1 and EXITED at Step 25 RNO for PORVs failing to close with heat sink re-established; Entered E-1," Lots of Primary or Secondary Coolant", and EXITED at Step 11 due to liPSI and spray pumps unable to supply adequate flow to RCS; Entered ECA 1.1, " Loss of Cold Leg Recirculation", and EXITED at Step 32 to " Return to Procedure and Step in Affect."
l At this point the operator will l A. RETURN to E-O to complete any missed actions out to Step 25 when CSF Status trees are monitored. B RETURN to FR-li i to complete any missed actions associated with restoration of the heat sink. C. RETURN to E-1 to complete actions required for loss of primary coolant. D. RETURN to ECA 1.1 Step I to ensure continuous flow of coolant is available to the core. Answer C JustMesbon a - Do not re enter E-0, as most steps have already been accomplished in ECA 1.1.
- b. Do not re enter FR ll.1 because a heat sink has been established via PORVs.
- c. CORRECT. E-1 is the correct procedure and step in effect.
- d. Do not remain in ECA 1.1, as conditions for cold leg recirculation have been restored.
Ouestion Topic: Know; edge of EOP unplementabon tverarchy y RO y SRO K/A Rating 3 0/4 0 CFRs. RO 55 41(b)(10) SRO 55 43 (b)(5) System Genenc K/A #_ 2 4.16 ELO#. EAS 01019 ' Reference. OP 120016 Page 4 of 100 4'13/97
l RO liX AM RiiVilIW Generic Question' i Thennal mussel control operations are in progress on the south service water header. While perfonning this routine maintenance, the Operator must verify that the outboard heat exchanger (E.
- 4A) delta P is not more than 2 psid higher than the inboard heat exchanger delta P (E SA). What adverse consequence would result if this condition were allowed to occur?
A. The "A" train of ECCS would be inoperable due to inadequate flow through the outboard heat
- exchanger.
B. The "B" train of ECCS would be inoperable due to inadequate now through the inboard heat exchanger. C. The "A" train of ECCS would be operable, but necessitate starting an additional service water pump. 4 , D. The "B" train of ECCS would be operable, but necessitate starting an additional service water pump Answer. A Just6 cation: l a CORRECT, if the outboard heat exchanger has a high delta P, then its now will go inboard and render this train inoperable. b The "B" train is already inoperable with the south header OOS.
- c. "A" train is not operable because the Dow may be passing through the inoperable train.
d The "B" train is not operable in this con 0guration. Question Topic Service water headet loss effects on TS V RO y SRO K!A Rating 3 3/3 7 CFR#. RO 55 41(b)(7) SRO 55 43(b)(5) System: Gene KlA #= 2 4 24 ELOs. SW-G SW-0902 3 Heference C ,s 3; STM Chapter 48, AOP 2 31 Page $ of 100 4/13/97
RO EX AM Rl!VIPN Generic Queston: A note in ES-0.2, " Natural Circulation Cooldown" states that "LTOP criteria cannot be met during natural circulation condit.cns without the HPSI flow restrictor in service." With a natural circulation cooldown occurring that is greater than 25 F/hr., why is the dedicated operator stationed? A. Natural circulation cooldown could create an adverse inermal stress on the reactor vessel wall. B. Natural circulation cooldown is difficult to control when cooling down greater than 25 F/hr. C. Natural ciemlation cooldown is the least desirable method, therefore, additional plant monitoring is required. D. Natural circulation cooldown will create voids that are not observable without PITS. Answer A Justification;
- a. CORRECT Cooldomi stresses at the 1/4T position are most limiting.
- b. While it is true that it is difficult to control, this has no effect on stationing of the dedicated operator,
- c. This is not a true statement. Cooldown on natural circulation is a well documented and controlled evolution.
- d. This procedure assumes that voids will be created. Analysis indicates that void growth will not interfere with NC flow.
.Ouestion Topic: Knowledge of imphcations of EOP notes, caution M RO y SRO K/A Rating 3 3/4 0 CFRs. RO $5 41(b)(10) SRO 55 43 (b)(5) i System. Genenc K/A 8. 2 420 l ELOL EAS-01017 i
Reference:
ES-0 2 BKGD Document (Step 8. Note 1) Page 6 of 100 4/13/97 _____. o
RO EXAM REVIEW Generic Question While perfomiing operability surveillance for DG 2, with DG 2 paralleled to MCC-9BI, the operator records the following information:
- DG-2 amperage at 200 amps;
- DG-2 voltage at 490 volts.
In an effort to verify that DG 2 is in the minimum amperage condition, the voltage level knob is turned in the raise (clockwise) direction and DG-2 amps increase. Why is the meter responding in this manner? A. DG-2 is oserexcited and is supplying lagging VARS out to MCC-9Bl. B. DG-2 is overexcited and is absorbing leading VARS in from MCC-9Bl. C. DG-2 is underexcited and is supplying lagging VARS out to MCC-9Bl. D. DG-2 is underexcited and is absorbing leading VARS in from MCC-9Bl. Answer A Justification l a. CORRECT. In this cendition the operator is overexciting DG-2 and VARS flow out to MCC 98.
- b. This would occur if the voltage level knob were lowered (counterclockwise) and DG-2 amps decreased.
- c. This would occur if the voltage level knob were raiseu (clockwise) and DG-2 amps decreased.
- d. This would occur if the voltage les el knob were lowered (counterclockwise) and DG-2 amps increased.
Question Topic: Know1 edge of RO tasks performed outside CR (oG-2 ops) v RO ] SRO K/A Rating 3.8/36 CFR*. RO 55 41 (b)(7) I System Genenc K/A #. 2 4.34
- ELO#- AC-0101-41.50.52.56.57.58 & 79
Reference:
Surveillance 3-1-23 (Sect 2.0 & 6.0) Page 7 of 100 4!13/97 _ _ _ _ _ _ _ _ _ _ . - . I
RO EXAM REVIEW Generic Queshon: The reactor is operating at 100% power when a main feed regulating valve (FW-F 207) fails open. What is the most likely sequence of events if P-2C is in operation and no operator action is taken? A. Feed water header pressure decreases, standby MFW pump auto starts, P-2C speed increases,
- feed water header pressure increases, P-2C suction pressure increases.
B. Feed water header pressure decreases, P 2C speed decreases, standby MFW pump auto starts, feed water header pressure increases, P-2C suction pressure increases.
= C. Feed water header pressure decreases, P-2C speed decreases, P 2C suction pressure decreases, standby condensate pump auto starts, P-2C speed increases.
D. Feed water header pressure decreases, P 2C speed increases, standby MFW pump auto starts, P-2C suction pressure decreases, standby condensate pump auto starts. Answer. D Justificaton;
- a. Decreasing FW HDR pressure & P-2 A/B auto start do not override initial P-2C speed increase.
- b. When FW header pressure decreases, then P-2C speed will increase,
- c. When P-2C speed decreases the suction pressure should increase and the condensate pump will not auto start.
- d. CORRECT. P-2C speed will immediately increase when header pressure decreases.
' Question Topic: Main feed regulating valve fails open; indications seen M RO Q SRO K/A Rating 4.0/4.3 CFR*: RO_ ss.41 (bX10) SRO 44.43 (bK5) ; System: Genenc K/A s. 2 4.04 ! ELos. MFW 09021, MFW-0902-2,ISR-0301-8 j
Reference:
Simulator response 4 Page 8 of 100 4/13!97
RO EXAM REVIEW Generic Ouesbon-Following a refueling outage, the plant is returning to power and is at a 5% hold for S/G chemistry. Pressurizer pressure starts to rapidly decrease and then the primary RO reports that the "A" train SIAS pumps have automatically started. Why is the reactor tripped and E-0, " Reactor Trip or Safety injection" entered? A. To evaluate plant conditions. B. To fire both trains of SlAS. C. To prevent a loss of offsite power. D. Because an ATWS is in progress. Answer B Justfication-. a E-O is not only entered, but the operator must fire SlAS.
- b. CORRECT. OP memo requires conservative decision making for this event even ifit appears to be inadvertant.
- c. There is no indication that a loss of offsite power will occur. -G
- d. "A" train SIAS pumps starting is not indicative of an ATWS.
- . - . - - . - - - . - - - . ~ . . . - - - . .--. - _ . . - . . _ - - . . . . - . . .. - ~ . ,
Quesbon Topic: KnoMedge of EOP entry condtions 7 RO -Q SRO K/A Rating 43'46 CFR# RO 55 41 (b)(10) SRO $5 43 (b)(5) System: Generic K/A #. 2 4 01 ELos EAS-0101-8 Reft rence: E-O entry cntena; OP Memo 9-E-12 Page 9 of 100 4/13/97 l
RO EXAM REVIEW Generic ouestion. During refueling operations you are the operator in the Control Room. The last three readings of 1/M are 1.1, .95, and .82. What actions are taken during refueling operations when 1/M values are decreasing? A. Suspend refueling operations; verify decreasing audible countrate; ensure no dilution flow paths exist; verify RCS boron > refueling boron concentratation. B. Continue refueling operations; verify increasing audible countrate; verify boration flow path available; notify plant personnel involved in any primary system realignments. C. Suspend refueling operations; verify increasing audible countrate; verify boration flow path availability; prepare to commence emergency boration; verify RCS boron concentration. D. Continue refueling operations; decrease multiplier on audible countrate instrument; notify personnel in containment; commence emergency boration. Answer: C Justifcaton:
- a. With 1/M values decreasing the RO should anticipate increasing counts.
- b. Continuing refueling operations is a non-conservative decision.
- c. CORRECT Once you verify problem, operator should prepare to commence emergency boration.
- d. Decreasing multiplier on audible countrate could mask increasing counts on the instruments.
_Question Tope: Knowledge of RO duties dunng refuehng
~Q RO *'] SRO K/A Rating 35/3.3 CFRs. - RO 55.41 (b)(12) l System: Genenc K/A s. 2.2,32 l ELos. EAS-0903-6 Reference. OP 1200-10 i
Page 10 of 100 4/13/97 j .. . . . .
RO EXAM REVIEW Generic Queston: Which statement describes the switch position required for automatic operation of the PORV's when RCS temperature is below the mininium pressurization temperature? A. HPSR/VPSR switch in "HPSR" with PORV switch in " AUTO" and PORV block valve open. l B. HPSR/VPSR switch in "VPSR" with PORV switch in " CLOSED" and PORV block valve open. C. HPSR/VPSR switch in "HPSR" with PORV switch in " AUTO" and PORV block valve closed. D. HPSR/VPSR switch in "VPSR" with PORV switch in " AUTO" and PORV block valve open. Answen D Jusbicabon-a PORV's will not open in HPSR.
- b. PORV will not auto open when the switch is in the closed position.
- c. The block valve will not automatically open in this condition.
- d. CORRECT. This is the proper valve combination to get the PORV to work.
i Queshon Topic: Operabon of PORVs when cooled down
'd RO f SRO K!A Rabng 4.2/3 9 CFR# RO 55 41 (b)(7)
System: Genenc K/A 8. 2.1.31 ELos. CVCS 0902-2 Reference. STM Chapter 4 Page 11 of 100 4/13/97
l RO EXAM REVIEW . Generic Quesbon: While monitoring Critical Safety Functions during a steam generator overfill / steam line break event, the operators have noted a greater than 100 F/hr. cooldown rate. Pressurizer pressure and wide range Teold are to the leh of Limit A Curve, necessitating entry into a Functional Restoration Procedure. Which procedure would be entered and why? A. Enter FR P.1 due to concerns for thermal shock caused by rapid cooldown and to prevent flaw growth in the reactor vessel during repressurization. B. Enter FR-P.1 due to concerns for thermal shock caused by rapid cooldown and to arrest compressive stresses on the inner wall during repressurization. C. Enter FR l.1 due to concerns for brittle failure caused by rapid cooldown and to prevent flaw growth in the reactor vessel during repressurization. D. Enter FR l.1 due to concerns for crystalline structure shif from face center to body center cubic which could lead to ductile failure. Answer. A Jusbfication:
- a. CORRECT. This is the basic PTS event for which FR P.1 was wrinen.
- b. Cooldown stresses are tensile on the inner wall. -
- c. FR-l.1 is not entered for a PTS situation.
- d. Although C/D will shift the crystalline structure, ductile failure is not a concern during a PTS event.
Queston Topic: Know1 edge of procedures and CSF entry conditons j V RO si SRO K/A Ratng 3.7/4.3 CFRs. RO 55 41(bX10) SRO $5.43 (b)(s) 3 I System: Generic - KIA #, 2 4.21 i ELOs. RCS-0101 16.28.29.30, EAS-01013
=
Reference:
FR-P.1 BKGD Document w__.__ , Page 12 of 100 4/13/97 _ _ _ _ _ _ _ _ _ _ _ _ _ 1
. RO EXAM REVIEW Generic ombon.
What is the relationship between the Maine Yankee Technical Specifications and the Facility i
; Operating License issued by the NRC?
A. The Technical Specifications ensure protective action guidelines in the Emergency Plan are not exceeded. B. The Technical Speci0 cations are part of the Operating License issued to the plant. C. The Technical Specifications are used to verify Appendix D accident compliance in the FSAR. D. The Technical Specifications are used to verify equipment availability for the Core Operating Limits Report. Answer: B Jushficabon:
- a. E Plan PAG's are based on actual / projected release data.
~ b. CORRECT. Technical Speci0 cations reDect conditions of the license.
- c. Technical Speci0 cations ensure that 10 CFR100 limits are not exceededi
- d. ' Technical Specifications verify equipment availability for all operating conditions, not just those in the COLR.
~ Question Topic: Knowledge of license conditions and hmitations 7 RO y SRO KlA Rabng 2.7/3.9 CFR8 RO 55 41(b)(10) - SRO 55.43(b)(1)
> System: Generic K/A #. 2.1.10 l
i ELO#. SNO-0303 ,
Reference:
.10 CFR 50.36 & MY Operabng License i !
Page 13 of 100 4/13/97 J
RO EXAM REVIEW Group 1 Plant Quesbon . The following conditions exist:
- PAB ventilation exhaust fan (FN-2) has tripped;
- Containment gas monitor (RM-6102Y) is in alarm;
- Primary vent stack gas monitor (RM 3902Y) is in alarm;
- Containment ventilation supply fan (HV-9) has tripped;
- VP-A-1,2,3,4, & 5 have tripped closed.'
t l Which scenario would be responsible for these conditions and alarms? A. A containment " refueling" purge was in progress. l B. A containment "on-line" purge was in progress. C. The waste gas surge tank has ruptured in the PAB upper level. D. The loop seal between the waste gas surge tank and the primary vent stack was lost.- Answer: B Justficaton. a, in " refueling" manipulator crane or containment low range will also alarm but will not cause a trip, b.- CORRECT. These are indications of an on-line purge problem.' ; c.' This scenario would not affect the containment gas monitor, but FN-2 would trip.
- d. This scenario would not affect the containment gas monitor, but FN-2 would trip.
Queston Topic: RMS alarm and astuabng signals M RO.Q SRO KlA Rahng 3.6/3.8 CFR#: RO $5.41(b)(11) SRO 55 43(b)(4) i System: 071 . K/A #. A3.02 i ELO#. RMS-01017; RMf>-0902-2
Reference:
STM Chapter 20 - Page 14 of 100 4/13/97
RO EXAM REVIEW ' Group 1 Plant
- Queston:
The plant is critical at 10-l% power with the following RPS conditions :
- The stan-up rate trip for channel D is in bypass via the Trip Inhibit Bypass key;
- The channel D amber indication light is lit (H1 SUR level),
in this configuration, which combination oflogic metrixes will generate a stan up rate (SUR) 1 l reactor trip? l l A. The AB, AC, and BC logic matrixes. ; B.' The AB, AC, and AD logic matrixes. C. The BC, BD, and CD logic matrixes. D. The AA, BB, and CC logic matrixes. Anser: A Jushficabon:
- a. CORRECT, This is the 2/3 logic necessary for a trip.
- b. The AD logic matrix will not generate a reactor trip.
- c. The BD and CD logic matrixes will not generate a reactor trip.
- d. These are not logic matrixes.
Queston Topic: Trip bypasses / logic matrixes
!R RO i] SRO - K/A Ratng - 3.8/3.9 -- CFR8: - RO 55 41 (b)(6) i System: 015 K/A #: A4 03 ELO#: - RPS 01012 l
Reference:
STM Chapter 11 i u Page 15 of 100 4f13fg7
RO EXAM REVIEW Group i Plant Oueshon: The plant has experienced a small break LOCA during a station blackout and P-258, the turbine driven AFW pump, is unable to provide feed flow. Core temperatures are rising along with piessurizer pressure with an average CET temperature of 750 F and pressurizer pressure of 1800 psia. The core region subcooled margin monitors will: A. Continuously Cash a 129 F indication on MCB Section "B." B. Continuously Cash a +129 F indication on MCB Section "B." C. Continuously Gash a 75 F indication on MCB Section "B." i l l D. Continuously Gash a -50 F indication on MCB Section "B." l Answer; D Jushfication '
- a. The SMM bottoms out at -50 F, therefore,-129 F will not be shown.
- b. There is a 129 F difference in Tsats, however, this is an invalid calculation.
- c. This is an invalid calculation as the monitor bottoms out at -50 F.
- d. CORRECT. This is a loss of subcooling that bottoms out at -50 F.
;Oueston Topic: Saturaton and subcoohng of water ;y; RO p SRO K/A Ratng 3.7/4.0 CFRs. RO 55 41(b) SRO 55 43 (b)
{ System: 017 K/A s. K5.02 I ELO#. RCS-0101 14,22 and RCS.0902 2 {
Reference:
STM Chapter 2 Page 16 of 100 4/13/97
RO EXAM REVIEW Group 1 Plant Queston: The computer room air conditioners are unable to maintain computer room temperature and a manual shutdown of the plant computer is required. In an effort to verify Technical Specification 3.9, how can the operator read CET temperatures? A. Access the Remote Instrumentation Room, use a calibrated thermometer, disconnect leads at measuring junction, read CET temperatures. B. Access the Reactor MCC Room, use a calibrated thermometer, disconnect leads at measuring junction, read CET temperatures. C. Access the Computer Room, use a calibrated thermometer, disconnect leads at reference junction, read CET temperatures. j D. Access Reactor MCC Room, use a calibrated thermometer, disconnect leads at reference junction, read CET temperatures. Answet C Justricaton;
- a. Must access the Computer Room and measure at referencejunction.
( a
- b. Must access the Computer Room and measure at referencejunction.
- c. CORRECT. This sequence allows you to read CET temperatures.
- d. Must access Computer Room.
Queston Topic: Actualin-core temps /how to read them Q RO y SRO K/A Rating 3.8/4.1 CFRs. RO 55 41(bX7) SRO 55 43 (bX6)
- System: 017 K/A #. A4.01 Elo#. RCS-010213; INCA 0101-10
Reference:
STM Chapter 2 Page 17 of 100 4/13/97
RO EXAM REVIEW Group 1 Plant Queston: The reactor has tripped from a total loss of offsite power and the emergency diesels (DG 1 A and IB) sre operating and supplying their respective emergency buses. Breakers IR,2R,3R, and 4R are " green flagged open" and breakers 1U,2U,3U, and 4U are " red flagged open". Undervoltage lockout relays 27Y-5 and 27Y-6 cannot be reset. What action is necessary to reset these relays? A. Bieakers 3R and 4R must be placed in " PULL-TO-LOCK" before the 27Y-5 and 27Y-6 relays will reset. B. Breakers 3U and 4U must be placed in " PULL-TO-LOCK" before the 27Y-5 and 27Y 6 relays will reset. C. Breakers 1R and 2R must be placed in " PULL-TO LOCK" before the 27Y 5 and 27Y-6 relays will reset. D. Breakers 1 U and 2U must be placed in " PULL TO-LOCK" before the 27Y-5 and 27Y-6 relays will reset. Answer; B Justification-
- a. Breakers 3U and 4U are required to reset the relays.
- b. CORRECT. This prevents inadvertant paralleling with offsite power.
- c. Breakers 3U and 4U are required to reset the relays.-
- d. Breakers 3U and 4U are required to reset the relays.
Queston Topic: Abdity to evaluate electncal reset criteria
% RO g SRO K/A Rating 3.7/4 4 CFR#. RO $5 41 (b)(7) SRO 55 43 (b)(5)
System: Genenc K/A #. 2.1.07 ELO#: AC-0902-1 j
Reference:
RO-L 5.2 4 Page 18 of 100 4/13/97
' RO EXAM REVIEW Groun i Plant - Queshon:-
While at 100% power with P 2C in semce, the P.2C recirculation valve fails wide open. How'- does the condensate system respond? AJ The standby condensate pump auto starts on low feed pump discharge pressure. B. The' standby condensate pump recirculation valve closes, C. The condensate gland exhaust condenser bypass valve opens. D. The standby condensate pump auto starts on low feed pump suction pressure. Answer; D- - Just6 cation:
- a. Condensate pump does not auto start on low feed pump discharge pressure.
b.> Condensate recirculation valve is not open at 100% power, c.~ The bypass valve maintains delta P across the gland exhaust condenser and is blocked in
. position.
- d. CORRECT. The pump starts on low feed pump suction pressure.
Queston Topic: Loss of condensate pump Q RO. 7 SRO K/A Rating 2.6/2.8 CFRs. RO 55 41 (b)(7) SRO 55 43 (b)(5)-
~. System: 056 - K/A #: A2.04
- ELO#: CD-0101 11 i
Reference:
STM Chapter 26 m Page 19 of 100 4/13/97 _ ____J
RO EXAM REVIEW Group 1 Plant -
. ouenon: ,
The S/G wide range channel is being used to control S/G level during a plant cooldown. With containment temperature at 90 F, S/G pressure at 300 psig, and indicated wide range level at 300", what is the actual level in the S/G? (Use the attached figure) ,, A. 260" B. 312" l C. 350" D. 400" Answer C Justfication
- a. This answer is reached from entering right versus left side of graph.
b This answer is reached when reading directly across graph without accounting for S'O pressure.
- c. CORRECT. This is the correct compensated level. '
- d. Thir answer is reached vchen failing to compensate for S/G pressure and reading up the indicated pressure lines.
Queston Topic Control and monitor S/G levets V RO Q SRO
~
K/A Rating 39/4.2 CFR8 RO 55 41 (b)(10) SRO 55 43(b)(5) System: 061 K/A 8. A1.01 ELO#. PPM-0107-6 & 8
Reference:
TDB Figure 1.4 2 , _ . . ~ . _ _ . _ _ . _ - _ . . _ _ _ _ .._ _ _ _ _ . , _ _ - Page 20 of 100 4/13/97
( PORC Mtg 8 9W052 ,, Dene 6- 15-9 5 FIGURE 1.4.2 Revowed by A Dese 6-el*IPrepared by - - STEAM GENERATOR LEVEL CORRECTION FOhiVIDE RANGE CHANNELS LI- 1214,1224 & 1234 4 , ,i p 0 - J N Exanvie. -4 x Indemed t.evel 331 behoe s. -2 4 X Cantenment Temperature 130F SteemGeneratorProonure W g
'd
,g .16 ' N' c ,'x Aneume that the reference leg temperature equale containmort g-20 temperature. From graph at right, o -24 Indcsied Level Correction 6 inchee 0 -28 N '
l \ Correa dindiceied Level 331-s 325inchee ! -32 : , K
" 46 : , . : , '(
Enter the graph along lines of conected i ' ' ' i
* -40 ev 400 60 80 100 120 140 160 180 200 220 240 260 280 300 Containment Temperature
.fi'l y
% JW
^
l M e- 'vc m m
.0, ico 325 7 W 'I D c
!l l
1== 'N _ l l ii j275 7 Ml l 1
!l r [g 250 j l l l -
!o 225 7 I -
I I ' i l l i* 225 200 l l 175
$ l 6 17.
150 150 E 125 ! I s l i i - - - 125 N 100 "' ! ! ! 100 0 l l l l l l l l i 75 ' 75 50 50 25 . 25 4 0 ! ! I I
-- 0 0 100 200 300 400 500 600 700 800 900 1000 Steam Generator Pressure (psig) 1
.._______._._._U y -
RO EXAM REVIEW Group 1 Plant Ouesbon> Prior to operating the boron recovery system (EV.1) to process hydrogenated waste from the PDT, the degasiners are run to remove hydrogen and other radioactive gases. How is oxygen instrusion into the waste gas system prevented when the degasifier system has cooled down and is in standby? - I A. The degasilier on-line vents remain open to allow the waste gas surge tank to Doat on the degasifiers. B. The degasilier vent cooler bypasses open to allow the waste gas surge tank to 00at on the degasiners. l C. The degasilier vent cooler bypasses open to allow the in service waste gas decay drum to Goat l on the degasifiers. D. The degasifier on line vents remain open to allow the in senice waste gas decay drum to float on the degasiliers. Answer; B Justiricabon: a - The degasifier on line vents open at 222 F to provide 5 scfin to the surge tank.
- b. CORRECT. This alignm nt is achieved when degasilier temperature is <222 F.
- c. The surge tank, not the decay tank, is aligned to the degasifier.
- d. See 'a' and 'c' above. !
-Question Topic: X-connectons between liquid and waste gas W RO Q SRO K/A Rating 2.5/2 6 CFRs: RO 55 41(b)(13) SRO 55 43(b)(4) ; System: 068 K/A 8. K1.02
- ELO#. . BRO-0401 14
{
Reference:
. STM Chapter 36; AO L 2.14 Page 21 of 100 4/13/97
RO EXAM REVIEW Group 1 Plant
'j Questeon:
l The plant is operating at 80% power when an RPS calibration is performed based on the " steam flow" calorimetric. As power is returned to 100%, steam flow power indication is less than delta T power indication. Why does this occur? l l A. The hotter water when greater than 80% power has increased neutron leakage and the RPS N1
- detectors now see more neutrons.
B. The steam flow calorimetric introduces an overly conservative value for power level when at 80%. C. The auxiliary steam loads at 80% poiver were not accounted for in the steam flow calorimetric. D. The delta T power instrument was not recalibrated for the higher Teold value at 100% power. Answer: C Justification-
- a. This is a true statement, but not applicable for this condition.
- b. This value is less conservative.
- c. CORRECT, These loads are upstream of the, steam flow measurement.
- d. It is unlikely that this instrument would require recalibration.
Ouesbon Topic: NIS cahbration by heat balance 7 RO p SRO K/A Rating 35/38 CFR#. RO $5 41 (b)(5) & (14) . SRO 55.43 (b)(2) & (5) System: 015 K/A 8. A1.01
' ELOs PPM 0103-2. MS-09021; PPM-0102-9
Reference:
Cha.actenstes of Core PWR Indicabons (RE 8/91) Page 22 of 100 4/13/97
RO !!XAM REVIIIW Group 1 Plant
- Quesbon.
While at 100% power, high vibration alarms are received on #3 RCP, While investigating the alarm locations on the RCP vibration monitor, the reactor trips on low flow.
- The green and amber lights on #3 RCP control switch are lit; The 86 device (86 P 1-3) on the breaker cubicle is " tripped";
- Overcurrent devices on two phases (SI A and SI-C) on #3 RCP are tripped.
l What is the probable cause and effect of this event? i- ! A. An RCP seized rotor and challenge to the fuel centerline melt safety limit. B. An RCP sheared impeller and challenge to the DNBR safety limit. C. An RCP seized iotor and challenge to the DNBR safety limit. D. An RCP sheared impeller and challenge to the fuel centerline melt safety limit. Answer: C Justificahon:
- a. Seized rotor will challenge DNBR before centerline melt.
b.- Sheared impellor will not bring in overcurrent trips.
- c. CORRECT. This is a DNBR challenge event.
- d. Neither answer is met by conditions in the stem.
l Question Topic: Loss of RCP effect on RCS N RO V.SRO K/A Rating 3.7/4.0 CFR#. RO 55.41(bX14) SRO $5 43(bX6)
- 4 System: 003 - K/A #. K3.01 ELO# RCP-0101-14; PPM-010310
Reference:
RO-L-2,1; STM Chapter 2 Page 23 of 100 4/13/97 s
RO EXAM REVIEW Group 1 Planj Quesbon: The plant has experienced a total loss of off-site power and the plant is tripped. The control room was evacuated due to noxious fumes eminating from the electrical board. An operator in the EFW pump room is preparing to start P 25A following an overspeed trip of P-25B, What conditions are
. required to start P 25A7
- Ai ASP normal / alternate switch in "ALTERI! ATE", DG 1 A running with its output breaker shut, i-P-25A ASP control switch to "CLOSE "
B. ASP normal / alternate switch in " NORMAL", DG 1B running with its output breaker shut, P-l 25A ASP control switch to "CLOSE." l C. ASP normal / alternate switch in " ALTERNATE", DG-1B running with its output breaker shut, P-25A ASP control switch to "CLOSE." D. ASP nonnal/ alternate switch in " NORMAL", DG 1 A running with its output breaker shut, P-25A ASP control switch to "CLOSE." Answer: C Jushficabon. A. P-25A is powered from BUS 6 (common misconception).
- b. The pump will not start in NORMAL.
- c. CORRECT, This sequence of events will start the pump.
- d. Requires power from BUS 6 (DG-lB).
'ouesbon Topic: EFW pump power supphes (9. RO " SRO K/A Rabng 3.7/3.7 CFRs. RO 55.41(B)(4) '
System: 061 K!A 8. K2 02
} ELOt. AFW 0101-4. AFW-0902-1
Reference:
AOP 2 90-1 Page 24 of 100 4/13!97 l
_ _ _ _ _ - _ _ _ - _ = - - _ _ _ - _ _ _ _ _ _ _ _ - _ _ . RO EXAM REVIEW Group 1 Plant
. Quesbort The wide range logarithmic channels each have three (3) fission chambers per detector. The l source range nuclear instruments utilize all three (3) fission chambers while the wide range nuclear instruments use only one (1) fission chamber. if the fission chamber that feeds the wide range instrument fails low on a power increase, that cha'nnel's output would:
' A. Lower the CPS output in the source range and slightly lower the value at which the Level 1 (2%) and Level 2 (10-4%) bistables are actuated. l B. Not affect the CPS output in the source range, but will prevent the Level 1 and 2 bistables from
- actuating at 2% and 10-4% respectively.
C, Lower the CPS output in the source range and will prevent the Level 1 and 2 bistables from actuating at 2% and 10-4% respectively. D. Not affect the CPS output in the source range and slightly lower the value at which the Level 1 (2%) and Level 2 (10-4%) bistables are actuated. Answer: C' Justficabon:
- a. Loss of the wide range would imply no output to the Level 1 and 2 B/S.
- b. Source range output is affected by the loss of one detector.
- c. CORRECT. The source range instrument will not reach this high an indication.
- d. See 'a' and 'b' above.
Queston Topic Brstable and logic cucuits V; RO y SRO K/A Ratng 2.913 2 CFR#. RO $5 41 (b)(2) SRO 55 43 (b)(5) System: 015 - K/A # K6.01 ELO#: N1-0101-3 and 6
Reference:
STM Chapter 14 Page 25 of 100 4/13!97
- RO EXAM REVIEW Group 1 Plant - . Question:~
Following a steam line break accident the Si termination procedure (ES 1.1) calls for throttling of HPSI flow before resetting SIAS. How is HPSI flow throttled in this conditior,? j A. HSI-M-41 and 42 NORMAIJBYPASS keys to BYPASS; HSI-M 11,12,21,22,31, and 32 ' throttled as riecessary. B. HSI-M-41 and 42 NORMA 1/ BYPASS heys to NORMAL; HSI-M-41 and 42 throttled as
- necessary.
C. HSI-M 41 and 42 NORMAL > BYPASS keys to BYPASS; HSI-M-41 and 42 throttled as necessary, D. HSI M-41 and 42 NORMAL / BYPASS keys to NORMAL; HSI M 11,12,21,22,31, and 32 throttled as necessary. Answer: C Justification
- a. HPSI loop vah es cannot be throttled without resetting SI.
- b. HPSI header valves cannot be throttled without switch in bypass.
c.. CORRECT. The keylock switch must be in bypass.
- d. See 'a' and 'b' above.
- Question Topic: Throtthng HPSI flow for Si termination 9 RO p SRO K/A Rating 3 3/3.7 CFR*. RO 55 41 (b)(7) $$ 43 (b)(5) . System: 013 K/A
- K4.10 ELO# ECCS-01017
Reference:
.. RO-L 2.6 _ ~- - . . . . - . . - . _ _ _ . - _ _ _ ,
RO EXAh1 REVIEW Group 1 P! ant Queston: The plant is at 50% power when a Train "A" HELB signal is actuated in the PAB. Which of the following calculations / systems would be directly or indirectly affected by Trait "A" HELB actuation?
- A. MWth, HV 7 heating steam, and VCT level.
B. MWth, seal water temperature, and PAB general area ventilation (FN 2).
- C. S/G radiation monitors, MWth, and BWST heating.
D. Letdown radiation monitor, MWth, and Spray Building pressure. Answer; C ~ Justficaton:
- a. HV.7 heating steam is from the Spray Building.
- b. FN-2 does not use any auxiliary steam.
- c. CORRECT. All these indications',ystems are effected by a loss of blowdown, letdown and PAB auxiliary steam.
- d. Spray building temperature and not pressure will be affected by a loss of auxiliary steam and this is a PAB not Spray Building actuation.
Queston Topic: initaton signals for ESF logic. HELB Q RO- 7 SRO *JA Ratng 42/4 4 CFR8. RO 55 41 (b)(7) SRO 55.43(b)(5) System: 013 K/A 8. K1.01 ELOW. HELB-0101 3 '.
Reference:
STM Chapter 6 (Secton 3.2.7) Page 27 of 100 4113/97
RO EXAM REVIEW Group i Plant ouestion. Which of the following indications could be used to differentiate between an actual low pressurizer level and a low failure nf the "in service" pressurizer level control channel? A.- All heaters are de-energized. I B. . Standby charging pump in " AUTO" starts. C. Minimum letdown How is indicated on the letdown Dow controller. l D. Maximum charging How is indicated on the charging flow controller. Answer: A Jus + 6 cation a, CORRECT. This is the only action that could differentiate between the two since heaters are de-energized by an LIC separate from the level control circuit.
- b. This function comes off the level control circuit and can be caused by actual low level OR the level control channel failing low.
- c. This function comes off the level control circuit and can be caused by actual low level OR the level control channel lailing low.
- d. This function comes off the level control circuit and can be caused by actual low level OR the level control channel failing low.
Question Topic: Loss of PZR level
'. Q RO y SRO K/A Rating 39/42 CFRs. RO $5 41(b)(7) SRO 55 43(b)(5)
System: 004 K/A # A2.02 ELos PLC-01012 & PLC-0101-4 Reference- STM Chapter 3 (Section 4.2) Page 28 of 100 4/13/97
RO EXAM REVIEW -
. Oggso 1 Plant Queston:
Which of the following conditions will result in a boration of the RCS? A. Placing the makeup mode selector switch in " BORATE" with the boric acid flow control valve (BA-F-30) set at 0 gpm and CH-F-38 in " AUTO." B. Placing an emergency boration valve switch (BA-M-37)in "OPEN" with VCT pressure at 20 psig while on normal letdown with CH F-38 in " AUTO." C. Placing an emergency boration valve switch (BA-M-37)in "OPEN" while on alternate letdown with CH M-87 shut and CH F 38 in " AUTO." l l D. Placing the boric acid now control valve (BA F-30) at 15 gpm with the makeup mode selector switch in " DILUTE" and CH F-38 in " AUTO." Answer: C Justincabon.
- a. Flow will only occur if the valve leaks by.
- b. VCT pressure will prevent boric acid now.
- c. CORRECT. The imbalance between charging and alternate letdown in this condition results in a drawdown of the BAST.
- d. Valve will not open with switch in " DILUTE" 1 Ouestion Topic: Emergency borabon valves operaton . !
y RO y SRO K/A Ratog 4.314 i CFRs. RO 55 41(b)(5) SRO 55 43 (b)(6) System: 004 K/A s. A4.18
' ELO*. CVCS-0103-2
Reference:
. STM Chapter 4 (Section 2 4 7) l
. , . . . - . . . . - _ . - - . - - _ . _ _ . _ _ --?
Page 29 of 100 4/13/97
RO EXAM REVIEW Group 1 Plant Queston: The plant is in a mini-outage to conduct fuel sipping operations in the spent fuel pool (SFP). While moving an assembly in the SFP a spent fuel pool area monitor radiation alarm is received. What automatic action occurs as a result of this alarm? A. The upender cannot enter the SFP in this condition. B. The new fuel elevator upward motion is inhibited. l C. The SFP ventilation system is automatically shut dowrt l i D. The SFP crane trolley movement is inhibited. Answer: 8 Jusbication-
- a. The upender is not affected by this alarm.
- b. CORRECT, Upward motion is inhibited by this alarm.
- c. There are no automatic actions associated with the ventilation system.
- d. The SFP crane is not affected by this alarm.
-Question Topic: Fuel handhng operations
'Q RO V SRO K/A Ratng 3.113.5 CFR#. RO 55.41(b)(11) SRO 55 43 (b)(7)
System: 072 K/A 8. K3.02
- ELos. RMS-01017
. Reference. Refuehng procedure 13-4 Page 30 of 100 4/13/97
RO EXAM REVIEW Group 1 Plant Quesbo': While maintaining a hot shutdown condition, the #1 RCP seal water return flow high alarm is received and the opeotor has indications that all three seals are failed. The operator notes that the
#1 RCP seal water return indication on the MCB is pegged high and the other two RCP's seal water return flows are <1 gpm. How does this condition efTect the operation of the #1 RCP?
A. The #1 RCP may remain operating but the seal water return valve (SL-M 29) should be closed. B. As long as seal water injection flow is greater than seal water return flow, the # 1 RCP may continue running. C. All the RCP's must be immediately secured in this condition and their iespective seal water return valves closed. D. The #1 RCP should be tripped and the seal water return valve (SL-M 29) closed. Answer: D Justricaton.
- a. This condition is not allowed by the manufacturer. The RCP must be tripped before closing SL-M 29.
- b. This is partially true but not in a condition with three failed seals.
- c. It is not necessary to trip all the RCPs in this condition.
- d. CORRECT. This is required to prevent further damage to the seal.
Oueshon Topic: Seal return flow degradabon V RO 'y SRO K/A Rahng 3.5!39 CFRs RO 55 41(bX5) SRO 55 43(bX5) System: 003 K/A s A2 01 ELos EAS-01504: EAS-0903-15
Reference:
STM Chapter 4; AOP 2-50 Page 31 of 100 4!13/97 i ( (
RO EXAM REVIEW Group 1 Plant Quesbon. The plant has tripped on a low steam generator pressure signal followed by EFCV closure due to a catastrophic failure of the main steam header in the turbine hall. In order to open the #2 S/G main feed regulating valve, the operator must: A. Bypass both trains of feed water isolation AND reset the turbine trip signal. B. Bypass one train of feed water isolation OR reset the turbine trip signal. C. Bypass both trains of feed water isolation AND press the " Steam Dump Override" push button D. Bypass one train of feed water isolation AND reset the turbine trip signal. Answer- A JustJication
- a. CORRECT. If the turbine trip signal is r.ot reset, the valve will not open.
- b. Both trains must be bypassed to remove closure signal and the turbine must be reset.
- c. Pressing steam dump override restores control to B/P valve only.
d Both trains must be bypassed to remove closure signal.
. - . - . . . . - - . - . - - . . ~ . - . . - . - - - - - .
Question Tope Feeduater rsolabon and reset v RO y SRO K/A Rating 3 2!3.3 CFRs RO 55 41 (b)(7) SRO 55 43(b)(5) Systern 059 K/A # A3.06 ELOs MFW.0103 7 Reference STM Chapter 27
. .~ - - -.--- - -
..--.-.--~.- --
Page 32 of 100 4/13/97
i ( llO EX AM REVil!W Group 1 Planj Oueshon During CEA exercising (Surveillance Proc. 318) a group 5 CEA drops into the core while nt 80% l power. The operators employ the "long term slow recovery" method to restore the dropped rod per AOP 2 21. " Misaligned (dropped) CEA", because of problems with that rod's power supply. Why , is power reduced in this situation? A Power reductions prior to rod recovery control xenon oscillations and symmetric offset limits. B. Power reductions prior to rod recovery minimize flus peaking and limit peilet clad interactions. ' C. Power reductions prior to rod recovery increase the KW/IT value and decrease the FRT Nit. D. Power reductions prior to rod recovery climinate the need for additional beration Answer, 13 Justrication-
- a. Xenon oscillations are a function of axial Ilux distribution and can be minimized when withdrawing the rod, but not eliminated.
- b. CORRECT. The xenon concentration in the area of the dropped rod is increasing with time and presents challenges to the pellet.
- c. KW/IT value will decrease with decreasing power.
- d. Boration is required because rod insertion exacerbates the peeking in the area of the dropped rod.
Queshon Topic Recovery of dropped tod V RO Q SRO k'A Rating 3 9 4.1 CFRs. RO 55 41 (b)(5) SRO $5 43 (b)(6) Systeer 001 K/A 8. K4 09 ELos CEDS-0902-1
- Reference AOP 2-21
( Page 33 of 100 4/13/97
- j
RO liX AM RtWil!W Group 1 Plant Question Reactor Engineering information for symmetric offset control includcs guidance on movement of CEA's when controlling symmetric ofTset (TDB Figure 1.1.4). If the steady state value of symmetric ofTset is less than zero (negative value) why are rods pulled outward? A. To allow for stabilization of KW/FT values. l l B. To minimize xenon oscillations. C. To balance the radial flux profile. D. To increase upper core power production Answer D Justification a KW/FT values are primarily influenced by power level. b This could make the oscillation worse as you are unaware of the way in which So is changing.
- c. This does effect radial flux profile, but this is an axial flux profile concern.
- d. CORid CT. Power will move to the upper cdre.
.- - ...-- --.-.._ ~. . ..
Question Topo F.ftect of sod motion on core power distnbution V RO SUO K/A Rating 3 9/41 CFRs RO 55 41 (b)(5) System 001 K/A #. K5.10
. ELO#. CEDS 0902 2 Reference OP 18-1 (Sect 2 0), TDB Figure 1.14
- w. - -
~ - - . . - . - . - . . . . . , . _ .
Page 34 of 100 4/13/97
RO EXAM REYlEW QtouD 1 Plan _t Ouestion The " AUTOMATIC" mode of primary water and boric acid makeup to the VCT is unavailable due to a problem with the VCT level sigma indication. If the operator chooses to perform a
" MANUAL" makeup with the makeup mode selector switch in the " MANUAL" position, what actions must occur to add makeup to the VCT7 A. The boric acid transfer pump (P 6 A, B, C)is started " AUTOMATICALLY" and the makeup supply valve to the VCT (BA A 32) must be " MANUALLY" opened.
B. The boric acid transfer pump (P 6 A, B, C)is started " MANUALLY" and the makeup supply valve to the VCT (BA A 32) will be " AUTOMATICALLY" opened 1 l C The boric acid transfer pump (P 6 A, B, C)is started " AUTOMATICALLY" and the makeup supply valve to the VCT (B A A 32) will be " AUTOMATICALLY" opened D. The boric acid transfer pump (P 6 A, B, C)is started "MANUAll.Y" and the makeup supply valve to the VCT (BA A 32) must be " MANUALLY" opened. Answer. O Justification
- a. Boric acid pump will not start automatically in this mode.
b BA-A 32 will not open autoinatically in this mode.
- c. Boric acid pump and BA A-32 require manual starting / operation
- d. CORRECT. This action r: quires maneal operator action.
Question Topic. Batch contf of an manual
;V RO SRO K/A Rating 31/33 CFR8 RO $s 41 (b)(6)
System 004 K!A # K613 ELO8 CVCS.0103 9.17
. Reference STM Chapter 4 Page 35 of 100 4/13/97
_ _.m __. _ _ _ . _ _ . . - - _. - _..__-._ ._ _ . _ 110 !!XAM Rl!Vil!W Group 1 Plant Ouesbon: During a design basis accident, the containment is cooled by the containment spray system. The normal cooling water supply for containment recirculation fans (PCC A 238) can be isolated either.
; A. Automatically on e Train "A" CIS OR manually from the T rain "A" ESF panel.
f3. Automatically on a Train "A" CSAS CR manually from the Train "A" ESF panel. C. Manually on a Train "A" CIS (at the MCB) OR automatically from the Train "A" ESF panel. D. Manually on a Train "A" CSAS (at the MCB) OR automatically from the Train "A" ESF panel. Answer: B Justification a PCC A 238 must remain open on a CIS to cool containment.
- b. CORRECT. Either action will close PCC A 238.
- c. PCC A 238 will not close on ESF without manual operator actions.
- d. PCC A 238 cannot be closed from . ,e MCB Question Topic. Automatic contariment isolation for PCC A.236 V RO SRO K/A Rating 3 614 0 CFR*. RO 55 41 (b)(7)
System 022 K/A
- K4.03 ELOs. CS-0902-3 Reference STM Chapter 8 Page 36 of 100 4/13/97
RO !!XAM RiiViliW
.QLqup 2 Plaqt Quesbon. .
Which of the following describes the method used to to ensure the SlT isolation valves (SIA %11, 21, and 31) are available for use during Condition 7 operations? A. The MOVs have a breaker and disconnect that are locked closed to ensure power and valve position indication is always available to the valve. B. The MOVs have a breaker and disconnect that are locked open. Valve position indication is provided by an alternate DC power source. C. The MOVs have a breaker and disconnect that are locked open but downstream of the control power transfonner allowing continuous valve position indication. D. The MOVs have a breaker and disconnect that are locked closed Valve position indication is provided by an alternate DC power source. Answer 13 Jushficabon-a The MOV disconnect is locked open in Condition 7. Valve indication from AC contial power is not provided for these valves
- b. CORRECT. The disconnect is locked ol'en while a separate DC power source provides valve position indication.
- c. DC control power is used to provide continuous salve position indication.
- d. The MOV disconnect is locked open in Condition 7.
. . . . - - - - . - - . - . . . _ . - - - . . . - - . , - - . - . - --- .------- - ~ -. . - . .
Queshon Topic. SIT vane posmon becabon
- V RO y SRO K/A Rabng 3 4/3 9 CFR8. RO 55 41 (b)(7) SRO 55 43 (b)(2)
System: 006 K/A 8. K6 03 iELO8 ECCS-0101 16
- Referexe. FSAR Chap 6.TS 319 A Page 37 of 100 4!13'97 i
RO EXAM REVIEW Group 2 Plant Oueshon. A containment recirculation fan power supply change was necessitated due to a LOCA scenario. Which of the following describes the change (s) made to pievent diesel generator overload? A. FN-17 2,4, and 6 were moved from BUS 8 and are powered from MCC-9C located in the protected switchgear room. B FN 171,3, and 5 were mmed from BUS 7 and are powered from MCC 9C located in the protected switchgear room. C. FN 17-2,4, and 6 were moved from BUS 8 and are powered from MCC 9C located in the unprotected switchgear room. D. FN 171,3, and 5 were moved from BUS 7 and are powered from MCC 9C located in the unprotected switchgear room. Answer. A Justafication.
- a. CORRECT. This prevents DG 1B overload conditions during certain LOCA based scenarios.
- b. FN 17-1,3, and 5 remain powered from BUS 7.
- c. MCC 9C is located adjacent to MCC-7A in the protected switchgear iaom.
- d. See "b" and "d" above.
- . - . .._- -. . . . - _ . _ - . . . . . - - . . - - _ . . . ~ . .
Question Topic Sigrvficance of DG toad hmns V RO 'v SRO K/A Rating 3 2/3 5 CFR#, RO $$ 41(bX7) SRO $$ 43(bX2) System 062 K/A t A1.01 ELO8 AC 010119 Reference EDCR 94 57 Page 38 of 100 4/13/97
l' RO EXAM RiiVIEW Group 2 Plant Queston: A plant cooldown is in progress The #1 and #2 S/G EFCV switches have been placed in "OPEN,"
#3 EFCV switch was inadvertantly left in " AUTO," Which of the following statements identifies plant response on decreasing steam generator pressure?
A. When 2/4 steam generator pressures in #3 S/G are <400 psig, all EFCV's will close. B. When 4/4 steam generator pressures in #3 S/G are <400 psig, only #3 S/G's EFCV will close. C. When 2/4 steam generator pressures in #3 S/G arc <400 psig, only #3 S/G's EFCV will close. D.- When 1/4 steam generator pressures in #3 S/G are <400 psig, all EFCV's will close. Answer; A
- l. Justficabon.
- a. CORRECT. When #3 gets to 400#, even those valves in OPEN will shut.
- b. Logie is 2/4, not 4/4, and all EFCV's will go CLOSEDI
- c. Even though # 1 and #2 are in open, all 11 ree (3) EFCV's will close on a low S/G pressure signal.
- d. Logic is for 2/4, not 1/4.
t Oueston Topic: Ability to monnot auto isolabon of mam steam m EFCVs M RO Q SRO K/A Retog 3.1/3 s CFRW; RO $5 41 (b)(7) SRO 55 43 (b)($) System. 039 K/A W. A3.02 -
- ELO8 MS-01014 and 6 Reference. STM Chapter 22 Page 39 of 100 4/13!97
RO EXAM REVIEW Group 2 P[Lnj Ove & n The following conditions exist when in hot shutdown:
- PAB upper level ambient temperatures are >l30 F;
- RCS ternperature is being maintained via AS P 3 and MS A 162 opening;
- CH F 38 flow is in:reasing with charging header pressure decreasing; Main steam non return valves (MS M 10,20 and 30) are closed;
- Blowdown is aligned to the primary vent stack; A four times nonnal radiation level spike was recorded on the PVS gas monitor (RM 3902Y).
Initial discussion among the crew seems to indicate that a steam generator tube leak may be in progress What mechanism should the operator use to confirm the S/G tube leak? A. Allow a few minutes to pass then note any increasing radiation levels on the blowdown monitors. H Use the main steam line monitor to note any increasing radiation level trends. C. continue trending the PVS radiation level and off pas filter radiation levels. D. Monitor the steam generator levels and EFW llow. Answer. D Justification
- a. The blowdown munitors are isolated when llELB is activated due to high PAB temps.
- b. In this condition of fairly stagnant flow, the main steam line monitors may be unable to see increasing radiation levels.
- c. The PVS spike is now isolated with blowdown secured and will not be a reliable indication.
- d. CORRECT. This is the only confirmation action that should yield positive S/G tube leak indications.
Ovestion Topic: Recognibon of S/G tube leak on red levels W RO p SRO KiA Rating 41/4 4 CFRs RO 55 41 (b)(10) & (11) SRO 55 43 (b)(4) & (5)
' System: 035 K/A s. A4 08 ELos. EAS-0903 5 and 14: SG-0902-2
Reference:
E.3 BKGO Document (Step 4) Page 40 of 100 4!13/97
RO EXAhi RiiYlfiW Group 2 Plant Quesbon The SFP demineralizer (1-4) hasjust received a fresh charge of unborated H OH resin and has been improperly placed in service. Over the next several hours: A. SFP 15 minute gross gamma should decrease, boron concentration should increase, and negative reactivity in the SFP should increase. B. SFP 15 minute gross gamma should decrease, boron concentration should decrease, and l negative reactivity in the SFP should increase. C. SFP 15 minute gross gamma should increase, boron concentration should increase, and negative reactivity in the SFP should decrease. D. SFP 15 minute gross gamma should decrease, boron concentration should decrease, and negative reactivity in the SFP should decrease. Answer. D Jusbficaten a Boron concentration will increase due to improper resin boration. I
- b. If boron concentration decreases, then shutdown margin will also decrease.
- c. Gross gamma will always decrease with a new resin change and boron concentration should decrease.
- d. CORRECT. This is the expected response for an unborated demineralizer.
Question Topic: Abdity to predict impact of inadequate SDM V RO y SRO K/A Rahng 3 Or3 $ CFRs RO $5 41 (b)(5) SRO 55 43(b)(7) System 033 K/A # A2 01 ELos CVCS-0102 24 Reference OP 1 171 Page 41 of 100 4 ' ' '5 7
RO !!XAM RiiViliW GrOUD 2 Plant QueMion An on line purge of containment is in progress. During your control board walkdown, you note that the valve position indications for VP.A 1,2,3, and 5 are both lit (red and green indications on). What would this condition indicate? A. That a high containment gas or PVS gas radiation level alarm hasjust cleared and the valves are traveling to the full open position. I il That a containment low range or manipulator crane alarm wasjust received and the valses are i traveling to the closed position. C. That a purge is about to begin as soon as the valves reach their full open position. D. That a purge is in progress and all four (4) valves are positioned according to procedural restrictions. Answer D Justirication
- a. Valves are mechanically blocked when in on line mode b Valves do not shut on these signals d' iring on line purging.
- c. Full salve opening when on line is not allowed
- d. CORRECT VP-A 1,2,3, and 5 are 50"h open Question Topic. Cont!ol features of auto purge isolation y RO y SRO KJA Rating 3 2/3 5 CFR#. RO 55 41 (b)(4) SRO 55 43(b)(1)
System' 029 K/A # K4 03 ELC# CP-01015 Reference. OP 1 121 A Page 42 of 100 4'13/97
RO EXAM REVIEW Group 2 Plant Ouestion. - l What are the possible adverse consequences to the containment spray velves (CS M l&2)if offsite power is in a degraded voltage condition? l A. The MOVs may aevelop insuf0cient torque to start valve movement. B. Insumcient voltage will not be available to the control power circuit to operate the 42 device in-line contactors. C. The motors may operate at a slower than acceptable speed as outlined in the accident analysis. D. DC control p(mer will close the breakers but the motors may be unable to open the valves. Answer A Justification-
- a. CORRECT. The MOVs are not reliable with less than 90% of terminal voltage available at the motor.
b This is not the most limiting aspect of valve operation.
- c. Frequency, hence speed, is not affected by motor voltage.
d MO',"s are controlled by AC and not DC control power. Question Topic Power supply to sprmy MOVs (RO onM
& RO , SRO KlA Rating 2.7/2 9 CFRs RO 55 41 (b)(10)
System 026 K/A e K2 C2 ELos AC-010171 and 73 Reference Memo Moultan B to Smith. S . 7/11/96 (stroking MOVs) Page 43 of 100 4/1397 __________--a
4 RO EXAM REVIEW Group 2 Plant ouesbon. Following a reactor trip caused by an actual seismic event, the operator notes that numerous rod bottom lights are not lit. The first out annunciator panel indicates that a thermal r.iargin' low pressure trip (Thi/1.P) was the Orst signal received. Without any operator action, what control room indications could confirm that adequate rods were inserted on a trip? A. Computer pulse height indication and CEA DVM indication. B. Rod drive MG set " LOAD" amps (generator ammeter) are zero (0). 1 l C. Reactor trip breaker position. D Wide range SUR reading 1/3 DPM. Ans*ct. D Justification a Computer pulse height indication must be reset following a reactor trip.
- b. Rod drive load amps are not available in the control room and there is still load on the MG set from Group SB rods.
- c. The trip breakers being open does not conGrm rods on the bottom.
d CORRECT. Because the reactor tripped on TM/LP the potential exists for ejected rods. Quesbon Topic: RPI OOS on RX top . how to mrbgate (RO only) V RO SRO K/A Rating 39/41 CFR#, RO $5 41 (b)(6) System. 014 KIA #. A2 05 ELos CEDS 01021,2 and 4, CEDS 0902-2
Reference:
STM Chapter 12 (Section 2) Page 44 of 1CU 4/13/97
RO I!X AM RiiVit!W Group 2 Plant Queshon-Following a load rejection anticipated operational occurrence (AOO), the reactor fails to trip on signals generated by the reactor protection system. What backup system will provide core protection during the AOO? A. Diverse scram system (DSS) on high pressurizer prusure two (2) out of four (4), opening M'G set output breakers. B. Diverse scram system (DSS) on low S/G water level two (2) out of two (2), opening M/G set output breakers. l C. Diverse turbine trip (DTT) on low S'G level two (2) out of two (2), energizing 20 AST and i dumping auto-stop oil.
. D. Diverse scram system (DSS) on high pressurizer pressure four (4) out of four (4k opening M G set output breakers.
eswer: A Justification
- a. CORRECT. This is the correct logic and input for DSS.
- b. DSS works on pressurizer pressure inputs, not S/G level.
- c. DTT works on low S/G level and energizes 20 AST, but sends its signal only to the turbine.
- d. This logic is 2/4, not 4/4.
Quesbon Topic: DSS tnp cucurts for AOO V RO V SRO K/A Rating 2 9'31 CFRs RO $5 41 (b)(7) SRO 55 43 (b)(5) System: 012 K/A 8. K6 02 ELO*. RPS-0902 2
Reference:
STM Chapters 11 (Section 2 9) and 24 (Fig 2411) Page 45 of 100 4 f13/97
l RO EXAM REVIEW Group 2 Plant Ouestion A plant trip occurs on low S'G level near the end of cycle. The operator notes increasing counts on the letdown radiation monitor (RM 3102). The demineralizer bypass valve (LD T 36)is open (to demineralizer), but the le:down pressure control valve (LD F-16) has automatically closed. The VCT cubicle area radiation levels have increased. What is the probable cause of this event? A. A crud burst has occurred and caused LD-F 16 to close on high pre Olter D'P. H. A fuel faliure has occurred and caused LD F-16 to close on high demineralizer D.'P. C. A crud burst has occurred and caused LD F 16 to close on high demineralizer D'P. D A fuel failure has occurred and caused LD-F-16 to close on high pre Alter D:'P. Answer A Jul0hCat:00
- a. CORRECT. The increasing radiation lesel in the VCT is attributable to lifting of LD S 14 sending contamination directly to the VCT.
- b. LD T 36 shuts on high demineralizer D/P, not LD-F-16.
- c. The demineralizers will not see a high D/P because the crud is removed in the pre-Olter.
- d. If the pre-Olter becomes clogged, the most likely event is a crud burst.
Question Topic: High activity m UD. actions to mrbgate y RO V SRO K!A Ratng 32/33 CFR#. RO 55 41 (b)(11) SRO 55 43 (b)(4) System Genenc K/A #. 21.28 ELos RMS 0902 2. CVCS-0102 5. CVCS4902-2 Reference STM Chapter 4, AOP 2 25 Page 46 of 100 4'13'97
RO IIXAM RiiviliW Group 2 Plant Question. A loss of secondary heat sink has occurred. The reactor head subcooled margin monitor is reading 10 F and is decreasing. As the reactor head subcooled margin monitor approaches 0 F, pressurizer level indication will: A. Increase due to voiding in the P7.R heater area. l H. Increase due to voiding in the reactor vessel. l C. Increase due to voiding in the S'O tube bundle region. D. Increase due to voiding in the PZR reference leg. Answer: B Justifcation a Voiding may occur in this region, but it will be insignificant compared to that in the head
- b. CORRECT. The head region of the vessel will void first.
- c. It is unlikely for the S'G's to be hotter than the RCS in this condition.
d This will caase an increase in indicated level, but in this condition it is unlikely. Question Topic PZR level odication when RCS rs t.aturated v RO -v SRO K/A Rating 36i40 CFRs RO $$ 41 (b)(5) SRO $5 43(t:)(5) System 011 K/A 8. K515 ELOW PLC-0902 2
Reference:
STM Chapter 2 (3.2.2) Page 47 of 100 4/13'97
, u -
RO liXAM RiiVi!M' Group 2 Plant Queshon The spare containment spray pump (P-elS)is aligned as a "B" train LPSI pump during normal operations. A total loss of offsite power and SIAS actuation signals are initiated oue to a seismic event. How does P 61S respond during this transient? A P-61S starts immediately due to 27Y-5 actuation. B. P-61S starts on time delay due to 27Y.5 actuation. C. P 61S starts immediately due to 27Y.6 actuation. D. P-61S starts on time delay due to 27Y-6 actuation. Answer D Jushficabon
- a. When 27Y 5(6) actuates the pump always starts on a time delay.
- b. Aligned as a B pump will require a 27Y-6 trip.
- c. To prevent diesel overload, the pump starts on time delay.
- d. CORRECT. There is a time delay for pump start.
. . _ _ _ . . _ . _ _ . . . . _ , _ _ . . _ _ . ._ ~ ._. _ _ ~ . . _ _ . _.
Queshon Topic: ECCS pump power supphes v RO V SRO K/A Rabog 3 6/3 9 CFRs RO $5 41 (b)(7) SRO 55 43 (b)(5) System: 006 K/A W. K2 01 ELos ECCG-0101 12
Reference:
STM Chapter 6 Page 48 of 100 4/13'97 __ __ __ __ ]
RO EXAM REVIEW Group 2 Plant Ouestion The primary iriventory trend system (PITS) provides reactor vessel level indication during accident conditions. Which condition ensures proper reference leg operation for PITS indication? l A. The RCP's are coasting down and the seal pot is continuously filling the reference leg. B. The RCP's are off and CET density compensation of PITS is operating. l C. The RCP's are running and the RTD density compensation of PITS is operating. l l D. The RCP's are off and the seal pot is continuously filling the reference leg. Ahswef; h Justification
- a. RCP coastdown still creates dynamic head pressure on PITS indication.
- b. Density compensation is provided by RTD's not CET's.
c RCP's must be off to read d CORRECT. Seal pot reference leg fill ensures accurate reference leg indication. Out stion Topic. RX vesselievelindication causeleffects R RO @ SRO K/A dating 3 Sf3 7 CFRW RO 55 41 (b)(3) & (7) SRO 55 43 (b)(5) System 002 K!A 8 K1.07
.ELos RCS-0102-11, RCS-0102 9 Reference STM Chapter 2 (Section 3 21)
PaDe 49 of 100 4/13/97 I l 1
RO I!XAM RiiViliW Group 2 Plant Oueshon-A waste gas release is in progress. The " charcoal Alter Gre gaseous discharge" annunciator (S 31) alarms due to high heat sensed at the charcoal Glters. With no automatic actions available , the operator should: A. Continue the waste gas release until veri 0 cation of a problem by the primary auxiliary operator. B Secure the waste gas release because the dilution How may be affected and result in an explosive mixture. l l C. Continue the waste gas release, but align the release to the unaffected Glter bank. l l D Secure the waste gas release because both Glter banks should be in service when discharging l waste gas. l Answer. B Justficibon
- a The release may exacerbate the high temp condition by providing a source of fuel (H2) to the Gre.
b CORRECT. High H2 sontent will result in potential for an explosive mixture.
- c. The release may exacerbate the high temperature condition by providing a source of fuel (hydrogen) to the Gre.
- d. The gas release can be realigned to the unafTected Glter bank.
Quesbon Topic: Actuabon of fue detection in a charcoal fdter bank V RO SRO K/A Rating 2903 CFR8 RO $5 41 (b)(4) Systern 086 K/A 8. A3 03 ELos FP-0902 2 Refevence: AOP 2.37.S (Annunciator S-13) Page 50 of 100 4!!347
)
RO !!XAM Rl!Vil!W Grouc 2 Plant Oueobon There is an automatic start of the emergency diesel generators (DG 1 A and IB) following a surveillance run where inadequate fuel oil is left in the integral tank (i.e., no fuel oil pressure develops). How would the diesel air start system respond to this condition? A. Selector switch on exciter cabinet selects first set of air start motors to engage (preferred). Starting sequence is as follows: Both sets of air star. motors engage and crank engine for three (3) seconds, preferred set of air start motors engage and crank engine for three (3) seconds, non-preferred set of air start motors engage and crank engine for three (3) seconds. B. Last surveillance run selects the set of air start motors to engage (preferred). Starting sequence l is as follows: Both sets of air stan motors engage and crank engine for three (3) seconds, prefened set of air start motors engage and crank engine for three (3) seconds, non preferred set of air stan motors engage and crank engine for three (3) seconds. C. Selector switch on exciter cabinet selects first set of air start motors to engage (preferred). Starting sequence is as follows: Preferred set of air stan motors engage and crank engine for three (3) seconds, both sets of air start motors engage and crank engine for three (3) seconds. non. preferred set of air start motors engage and crank engine for three (3) seconds.
- D. Last surveillance run selects the set of air start motors to engage (preferred) Starting sequence is as follows: Preferred set of air stan motors engage and crank engine for three (3) seconds, both sets of air start motors engage and crank engine for three (3) seconds, non preferred set of air start motors engage and crank engine for three (3) seconds.
Answer. C JustJication-
- a. The preferred set will engage first.
- b. Preferred set will engage before both air motors will. Both sets engage only on a manual start from the EDG room.
- c. CORRECT. This is the correct auto-start sequence for the diesel.
- d. The EDG surveillance only dictates where the diesel will be staned from manually,
$0uestion Topic: Auto start of EDG RO [ SRO K/A Ratog 4114 0 CFRW. RO $5 41 (b)(7) l System: 064 K/A #: A3 01 -lELOS DG-0102 8 i
Reference:
STM Chapter 34 L__._._ ___,_____._.. _ -. _ _ _ Page $1 of 100 4/13!97
RO IIX AM Rl!YltiW Group 2 Plant ouestion DG-1 A has completed a two (2) hour surveillance run when the operator sees smoke coming from the vicinity of the turbo charger. An emergency diesel shutdown is being performed. If an auto start signal were to occur with the diesel breaker open, but not in pull to lock, the diesel would: l A. Restart and come up to 900 rpm unless both "STOP" push buttons are energized and the fuel { cutoff valve is " CLOSED." 13 Restart and come up to 900 rpm unless the fuel rack is held in the "NO FUEL" position until diesel is <450 rpm. C. Restan and come up to 900 rpm unless both "STOP" push buttons are energized and the fuel rack is held in the "NO FUEL" position until the diesel stops. D. Restart and come up to 900 rpm regardless of the fuel rack position, fuel shutoff valve position, or "STOP" push buttons. Answer C Justifcation. a Diesel restans and electrical fue? oil pump provides fuel oil pressure.
- b. Start failure will prevent diesel shutdown unless dieselis allowed to stop
- c. CORRECT. The diesel must come to a complete stop.
d One or more of these conditions will prevent the diesel from running. _ _ _ _ _ _ _ . _ . . _ _ _ . _ . . _ _ _ . _ __ _._. _ . , ~ Ouesbon Topsc Local and remote operation of the EDG V RO SRO KIA Ratog 4 O!4 3 CFRs RO $$ 41 (b)(7) System 064 K/A s, A4 01 ELO*. DG-0102-7,DG-04016, DG 0902-3 Reference Survedlance 31.4A(B). RO-L $ 4 Page $2 of 100 4/13'97
RO EXAM REVihW group 2 Plant Ouestion An " Operator Workaround" is denned as an equipment deficiency (including design deficiencies) which can impact operator response during a transient or accident. Which of the following when at hot full power, would be designated as an Operator Workaround? l A. The north entrance to the steam and valve house is temporarily blocked by scaffolding in the Reactor MCC Room. i B. An operator is stationed at the feedwater section of the MCB to manually control #1 S/G main I feed regulating valve for 15 minutes. 1 C. Train "A" CIS annunciator for " Trip Signal: RCP Trip Criteria" is continuously lit on the MCB annunciator panel. D. The MCB switch for the diesel fire pump (P-5)is being replaced due to a design deficiency (auto-start is available) l Answer. C Jatification'
- a. Access to the room is still available, however, for certain Appendh R events, this could be a problem.
- b. Control system will automatically shut valve on a turbine trip and this is not a long term coadition.
- c. CORRECT. This indicates that a problem exists which will not alert the operator in an accident condition.
- d. The pump can still auto > tart and P-4 is also available if needed Ouestion Topic Knowdedge of operator responsibilities v RO V SRO K/A Rabnp 30/40 CFRs RO 55 41 (b)(10) SRO $$ 43(b)(3)
System, Generte K/A # 2102 ELOs. AD-01021
Reference:
OP 120015 2 Page 53 of 100 4t13,97 N 1
RO EX AM REVil!W Group 2 Plant Quesbon. How are radiation levels trended inside the containment during an accident that releases large amounts of radionuclides? l A. The high range radiation monitors (RM-6113A/B) have chart recorders that are automatically activated. 1 B. The low range radiation monitor (RM 6105) has a chart recorder that is automatically activated. C. The manipulator crane radiation monitor (RM 6104) has a chart recorder that is automatically activated. D The low range radiation monitor (RM 6105) automatically activates a historical record on the plant computer. Ans-en A Justification
- a. CORRECT. This is the method used to trend containment radiation levels.
- b. This function is provided by the high range only.
- c. This function is provided by the high range only.
- d. Historical records can be accessed but are not automatically activated.
Queston Topic: Morutomo changes viradiationlevels
'v RO -y SRO K/A Rating 3 2/3 $ CFRs. RO 55 41 (b)(11) SRO $5 43 (b)(5)
System 073 K/A # A1.01 ELO# RMS-09021 Reference. STM Chapter 20. RO-L-9 5 Page 54 of 100 4t13/97
RO EXAM REVIEW Group 2 Plant Question
- Instrument air header pressure is decreasing and the cause is unknown. What automatic action occurs FIRST to restore instrument air header pressure?
l A. SA P 56 will shut at 75 psig and isolate the service air header. 1
- 13. IA A 27 will open at 75 psig and supply the instrument air header.
1 C. SA P-56 will shut at 75 psig and isolate the instrun cnt air header. D. lA A 27 will open at 75 psig and supply the service air header. Answw A Jtratification:
- a. CORRECT. SA P-56 isolates the service air header.
- b. IA-A-27 will perform the function listed, but not until SA P 56 closes.
- c. SA P-56 isolates service, not instrument air.
- d. I A-A-27 provides bypass air to instrument air.
Question Topic Cross connects of station to instrument ar v RO , SRO K/A Rating 2 90 2 CFRs. RO 55 41 (b)(7) System 079 K/A s K4 01 ELos CA-0101 7 Reference STM Chapter 42. OP 1231 Page 55 of 100 4/13/97 j J
RO EXAM REVIEW Group 2 Plant ouestion Which of the following groups ofindications, trips, and alarms will be effected if any one pressurizer pressure safety channel is lost (PT-102 A, B, C, or D)? A.11igh pressure trip unit, PORV block valve auto open, diverse scram system. B. TM/LP trip unit, SlAS actuation, LO LO pressure alann. C. SPDS input, SlAS actuation, low pressure heater cutout. D. PORV actuation, diverse turbine trip, high pressure trip unit. Anmer: B Justification
- a. Block valve auto open comes from control channels X and Y.
- b. CORRECT, The low pressure alarm is from control channels X and Y. The low low alarm originates in the SIAS trip unit.
- c. There is no low pressure heater cutout.
- d. DTT actuates on low S G level, not RCS pressure.
Queston Top c: PZR pressure malfunction effect on RPS V RO 7 SRO K/A Rating 4 O!41 CFR#. RO 55 41 (b)(7) SRO 55 43 (b)(2) System. 010 K/A # K3 02 ELOs. PPC-0102 3
Reference:
STM Chapters 3 and 11 Page 56 of 100 4/15/97
RO liX AM Rl!ViliW Group 3 Plant Ouestxan The ZURN strain:r isolations on the inlet to the Senice Water heat exchangers must be shut immediately in the event of an SlAS during " power Hushing" Why is this required? A. The ZURN strair tr outlet piping is not seismically qualined and will fail if a water hammer event occurs. B. This would prevent an inadvenant relcase path if a PCC or SCC heat exchanger failed (bypassing Service Water RMS). C. The service water pumps are not designed to handle the Gaw rates that accompany " power l Hushing " l D The SW heat exchangers need to receive full cooling water How to meet the heat loading
- requirements from an accident.
Answer. D Justfication
- a. The piping downstream of the ZURN valve is not qualined, but a water hammer event is unlikely.
- b. This does bypass Service Water RMS, but no release path exists because the water did not travel through the heat exchanger.
- c. Flow thru the heat exchanger, not the pump supply Dow,is the limiting factor for emergency heat loads.
- d. CORRECT. An operator must be stationed at the power Hushing vahe to close it in the event of an accident.
' Question Topic: Power flushing of the SW heat exchangers V RO 7 SRO K!A Ratng 37/37 CFR8 RO 55 41 (b)(8)
Systern 076 K!A s A3 02 ELO* AD-0102-8
Reference:
OP 1 15-3 (Section 5.9)
, _ _ _ _ _ _ _ . _ . . . . _ _ _ _ _ _ _ _ _ _ . . ~ _ . _ _ _ _ . . _ . . _ , _ . _ . . _ . . _ . _ . . _
Page 57 of 100 4/13/97
RO EXAht REYlEW Group 3 Plant Ouestion Which of the following describes the sequence of events that occurs when main generator relay 86 BU actuates when connected to the grid? A. Tripping of relay 86 BU sends a signal directly to all four (4) RPS channels to initiate a loss of load reactor trip. B. Tripping of relay 86 BU sends a signal to 20 AST which energizes and initiates opening of the MG set output breakers. C. Tripping of relay 86 BU sends a signal to the auto stop oil pressure switches subsequently initiating a turbine, then reactor trip. D. Tripping of relay 86 BU sends a signal to 20 ET which closes all four (4) stop va ves subsequently initiating a reactor trip Answer: D Justfication-a There is no direct signal from the main generator to the RPS.
- b. 20 AST does not open the MG-set output breakers.
- c. 86 BU does not send a signal to auto stop oil.
- d. CORRECT. 86 BU sends a signal to both 20 AST and 20 ET tripping solenoids.
. . . - _ . _ _ . _ . _ . . _ . ..m__.. ._, ._ . . _ __._ _. . _ _ _ _
Question Topic: Interrelationship between RPS and man gen
@ RO y SRO V/A Ratng 36'37 CFRs RO $$ 41 (b)(8) SRO 55 43 tc)(5)
System 045 K/A # K1.18 ELO# MG 0101 14. MT-01019
Reference:
STM Chapter 28 Page 58 of 100 4'1r97
RO EXAM REVIEW Group 3 Piant Ouestion: An inadequate core cooling event has left the core uncovered for about 1/2 hour prior to reflooding. A BENDIX hydrogen sample of containment indicates 6% hydrogen. What is the probable cause of the hydrogen formation? A. The radiolytic decomposition of water has accelerated due to high core temperatures, therefore, liberating hydrogen. B. A self-sustaining Zirc-water reaction has occurred due to high core temperatures, therefore. l liberating hydrogen. C. Cracking of the fuel cladding has released elemental helium which disassociates into hydrogen under the strong gamma flux. 1 { D. Sodium hydroxide from the SCAT has reacted with the carbon steel liner and created elemental oxygen and hydrogen Answer B Justifiertson.
- a. While radiolytic decomposition does liberate 112, it does not require high temps,just gamma and neutron Dux.
- b. CORRECT. The zirc-water reaction is the major source of hydrogen.
- c. llelium does not change into hydrogen under a gamma Hux.
- d. NaOH reacts with aluminum. The containment liner is carbon steel.
Question Topic. AMty to predict H2 concentration (RO only) v RO SRO K/A Ratog 29/36 CFRs. RO $5 41(bX5) System 028 K/A #. K5 03 ' ELO*. AD-0102-8 Reference RO-L 2 9 Page 59 of 100 4/t 3/97
RO EXAM REVIEW Group 3 Plant Quesbon: During a LOCA inside containment (SlAS/CIS actuation) PCC surge tank level is decreasing rapidly What automatic action occurs to ensure that the PCC system remains available during the accident? A. PCC M 219 (supply to RCP's) closes to maintain PCC surge tank level and NPSH to the PCC l pump. l l B. The PCC pumps trip on low suction pressure to facilitate refilling the surge tank and restarting the pumps. C. PCC A-252 (retum f RCP's) closes to maintain adequate NPSil to the PCC pumps l D. The PCC pumps trip on high PCC flow to facilitate leak isolation and restart of PCC pumps. Answer: A Justficatiorr
- a. CORRECT. PCC M-219 closes in 20 seconds to maintain >1000 gpm in the PCC surge tank
- b. The PCC pumps do not have a low suction pressure trip.
- c. PCC-A-252 closure does not afford PCC system protection inside the containment.
- d. The PCC pumps trip on high current, not high flow.
. _ _ . - . - . . - . _ . . . - - . - . . . _ . . _ - - . . - . - - - - . . _ _ - ~ - . . . - - . .
'Quesbon Topic. Auto actions of CCW on STAS
~d, RO "7SRO K/A Rabng 3 6/3.7 CFRs. RO 55 41(b)(3)&(10)
System: 008 K/A s. A3 08 ELOs CC-09021 Reference. ACP 2-33 (Section 2 0) Page 60 of 100 4/13/97 l
RO EXAM REVIEW
' Group 3 Plant oueshon= .
The reactor is in a Cold Shutdown condition (150 psia & 200 F) with RHR flew being maintained by LSl F 59 at 2500 gpm. Electrical Maintenance has requested that Operations minimize plant L slectrical load by reducing flow to 1000 gpm. What adverse efTect could this reduction in flow
%. ave on plant safety?
! A. The RHR pump would start to overheat because this is the minimum flow at which an RHR pump should be operated. r i l B. The RHR pump would start to cavitate due to vortexing at the RHR pump suction valves (RH- ; M-1 & 2). 5 C The RHR system would not provide adequate LTOP protection in the event of an inadvertant charging pump start.
]
i 11 The RHR ;ystem would not provide adequate LTOP protection when RH-M 1 & 2 shut on low-RHR flow. A tswer. C Jushfication-
- a. OP l-13-1 step 6.3.6 minimum RHR pump flow is 500 gpm (as read).
- b. Vortexing only occurs when in reduced RCS volume conditions.
- c. CORRECT. This flow ensures adequate mixing to prevent LTOP problems.
- d RH-M-1 & 2 shut on high pressure (585 psig).
Question Topic Pressure transient protecta.uunng CSD R RO y SRO K/A Rating 3 547 CFRs. RO 55 41(b)(8) SRO 55 43(b)(2)& (3)
?: System: OC5 K/A #. A2.02 ELc1 RCS-010113; AD-0102-8
Reference:
MYP 87-923 (PRR 90 013). RO-L 7 6 k Page 61 of 100 4/13/97
RO EXAM REVIEW u Group 3 Plant l ouesim The plant is at 45% power. One containment air compressor (C-5A)is wh9e tagged out for maintenance when C5 B trips on overload. Cross-connect air is unavailable at this time. What action is required? A. The sixth containment recirculation fan must be started.
- l. B. The reactor end the RCP's must be tripped.
l C. The reactor must be tripped and Group 5B must be inserted. D. The RCS must be borated until the plant is shutdowrt Answer: B ' Justficabon:
- a. The reactor must be tripped in this condition due to loss of PCC to the RCP coolers.
- b. CORRECT. This action is necessary to protect plant components.
- c. Inserting Group SB in this condition will result in damaging the CEDM coils.
- d. The reactor must be tripped in this condition due to loss of PCC to the RCP coolen .
Question Topic: Loss of containment control air to ,,omponents Q GO ;'SRO K/A Rat ng 3 413 6 CFR#, RO 55 41 (b)(6 & 10)
; System: 078 K/A #. K3.02
; ELO#. CA 0101-11: EAS-OiS0-5
Reference:
AoP 2 29 Page 62 of 100 , 4/14/97
RO EXAM REVIEW
- Group 3 Plant Question What would be an adverse consequence of failing to recirculate the RHR system prior to placing it Din senice?-
A. The RHR heatup limit of 1260 F/hr. will be exceeded when RH M-1 and 2 are opened with RH- - 4 closa?
- 3. Excess positive reactivity will be added to the RCS even with the RCS borated to the Cold i Shutd.swn condition. ' C. The RHR spring reliefs (RH S-24 and 25) may lift prematurely due to the delta T between the body and bonnet.
D. The RHR heat exchangers may de >elop RCS to component cooling system leaks caused by thermal shock to the RHR heat exchanger U-tubes. Answer; B Justification:
- a. The hourly heatup limit is not exceeded, but the restriction for heatup! min would be challenged (21 F/ min).
- b. CORRECT. The accident analysis assumes that the RHR system is recirculated to equalize boron concentration.
- c. RHR spring reliefs are unaffected by thermal shock.
- d. RHR heat exchangers may undergo thermal shock, but this condition is seen durirg an RAS.
* ~ - -
Question Topic: RHR en service without proper warmup l M RO ~i v SRO KIA Ratng 3.3/3 9 CFR#_ RO 55.41(b)(G) SRO 55 43(b)(2)
' System: Generic K/A #. 2.4.09 ! ELO#. RHR 0101 11
Reference:
' FSAR Chapter 14, STM Chapter 7
\
Page 63 of 100 4/13/97 l J
RO EXAM REVIEW Group 3 Plcnt Ouestion: Both PORVs have lifted following a loss of load accident and the quench tank has remained intact. Both PORVs now indicate closed on the MCB. The accoustic accelerometers are not available for verifying valve closure. Which of the following would provide the most accurate information to verify the PORVs ciosed? A. Reactor core subcoole d margin, Th, containment pressure. B. Reactor head subcooled margin, CET temperature, quench tank pressure. C. Reactor core subcooled margin, CET temperature, quench tank pressure. D. Reactor head subcooled margin, Th, containment pressure. Answer: C Justf::ation-
- a. Cannot determine due to relationship between subcooled margin and Thot.
t
- b. Can provide, out not most accurcte/ valid solution because you don't know what the head temp is. >
- c. CORRECT. By knowing subcooled margin and CET temperature, you could determine pressunze.r pressur:
- d. Containment press' ire indication is only good if rupture disc was broken.
_ - _ _ . . _ . _ . _ _ _ _ _ _ _ _ . . , _ _ _ . _ _ _ _ ______ __ _ _ _ _ _ _ . ~ . _ Ouestion Topic: Identifying a PORV/ code safety that rs not closed
- Q RO SRO K/A Ratng 36!38 CFR8 RO 55 41 (bX14) e ystem 007 K/A # A4.10 ELos. PPC-0101-7 Ref erence- RO-L-2 4 Page 64 of 100 4t13/97 o .. nw -
RO EXAM REVIEW Groun 1 EPE over,non. The "A" traveling water screen has failed due to high differential pressure. The "A" condenser waterbox has been removed from service to clean debris off the inlet tube sheet. An operator verifying valve alignment inadvertantly shuts the "B" waterbox outlet to the vacuum priming tank causing condenser difreiential pressure to rise. What actions should be taken to prevent turbine damage?
'A. Continue to monitor condenser differential pressure and manually trip the turbine when this value is greater than 3.5" Hg.
B. Place the EJ-2A and B condenser hoggers in service to minimize the main condenser differential pressure. l C Monitor directional thrust on the main turbine shaft and manually trip the turbine if thrust is excessive. l D. Monitor turbine supervisory instrumentation until turbine vibrations exceed the 18 mil setpoint for safe operations, then trip the turbine. Answer: .A Justfhabon: - [ a. CORRECT. OP l-3 and /.OP 2-2 direct this action.
- b. Hogger operation is insufficient to correct a condenser delta P.
cJAlthough some directional thrust will occur on concenser delta P, it will be insufficient to generate a turbine trip.
- d. Turbine damage may result if you wait for the 18 mil setpoint to be reached.
Queston Topic: Conditons for RX tnp on loss of vacuum Y RO ';/ SRO K/A Ratng 39141 CFR#: RO 55 41 (b)(4) SRO 55 43 (b)(5) System: 051 K/A 8 AA2.02 ELos: MT-010122
Reference:
OP 1-3; AOP 2 2
=
Page 65 of 100 4/13/97 _______________.J
RO EXAM REVIEW
- Group 1 EPE Queshon
During normal at power operations, the letdown monitor (RI 3102) counts are trending upward. Chemistry has notified Operations that primary system samples indicate several fuel rods may have failed. Your actions to determine the extent of fuel damage and minimize radiation levels are based on: l - A. Excessive fission products in the reactor coolant system whicF ay inhibit the heat transfer surfaces in both the S/G and reactor core. B. Protection of the health and safety of the public per 10 CFR 100 in the event of a steam generator tube rupture. C. Protective action guidelines per the Emergency Plan that are required to be pre-scripted during a fuel failure scenario in the event of evacuation D. Known limitations with the current radiation monitoring circuitry to effectively chart increases y in RCS activity. d Answer B Jusuficaton:
- a. There are no adverse consequences on heat transfer due to high FPA.
b CORRECT. RCS activity is a concern because of release during a SGTR.
- c. PAG's are based on projected' actual measurements after an accident has occurred.
- d. Independent analysis by che,c.istry will always verify current RMS activity indications.
Quesbon Topic: Correcbve accons for fission product acevity V RO if liRO K/A Rahng 2.9/3 6 CFR#. RO 55 41(bX12) SRO 55 43(bX4) System: 076 KIA #. AK3 05 ELO#: EAS-0903-6; SNO-0304-1; AD-0102-8
Reference:
AOP 2 25 Page 66 of 100 4/13/97
RO EXAM REVIEW Group 1 EPE ovesson - The plant is at 55% power during CEA testing. A voltage spike affecting both timer module power supplies causes a Group SA rod to drop. How long does the operator have, per Technical Specifications, to commence correction of the CEA misalignment? A. The cperator must immediately correct the rod misalignment.
- B. The operator has 15 minutes to initiate corrective actions.
C. The operator has 30 minutes to initiate corrective actions. D. The operator has I hour to initiate corrective actions. Answer: B
. Jushficahon.
- a. Tech Spec 3.10.A.3 requires action within 15 minutes,
- b. CORRECT. Tech Spec 3.10.A.3 requires action within 15 minutes.
- c. Tech Spec 3.10.A.3 requires action within 15 minutes.
[ ' d. Tech Spec 3.10.A.3 requires action within 15 minutes. Z
.Queston Topic: Tech Spec hmits for fod mesmatch i9. RO 7,SRO K/A Rating 3.6/4.1 CFRs. RG 55 4: #5)(7) SRO 55 43 (b)(2)
{ System: 005 K/A # AK3.03
- ELos. CEDS 0102-5.6; SNO-0303-10. AD-0104-10 i
Reference:
TS 3.10.A.3 Page 67 of 100 4/13/97 l
RO EXAM REVIEW C,coun 1 EPE Queshon: During verification ornatural circulation conditions, the primary side RO reports that core region subcooling margin monitor is not available for operator use. Which of the following would provide the best indication of natural circulation flow? A. S/G pressure, Pressurizer level, Thot, CETs, and steam tables. B. S!G pressure, Pressurizer pressure, Tcold, CETs, and steam tables. C. RCS pressure, Pressurizer level, Thot, CETs, and steam tables. D. RCS pressure, S!G level, Teold, CETs, and steam tables. Answer: B Justificaton:
- a. Does not provide Tcold or RCS pressure indications.
I
- b. CORRECT This information could be used to determine all elements of natural circulation except for That data.
. c. Does not provide Tcold or S/G pressure indications.
- d. Does not provide Thot or S/G pressure indications.
. Question Topic: Development of NC flow /Use of RCS instruments
'v RO V SRO K/A Ratng 4.414.5 CFR8. RO 55 41 (bv5) SRo rE 43 (b)(5)
System: 015 K/A s. AA1.21
~ELO#, PPM-010314
Reference:
- E S-0.1 Page 68 of 100 4/13/97
RO EXAM REVIEW Group i EPE ouesnon:- An emergen(y baration of the RCS is required following entry into FR-S.1," Nuclear Power Generation /A'l WS." Which of the following flowpath actions will meet FR S.1 criteria for emergency boration? A. Verify a charging pump operating, open HSI-M-50 and 51, take LD-A 51 to "PDT", start two boric acid transfer pumps. B. Start two boric acid transfer pumps, maximize charging flow, verify a charging pump ! operating, close CH-M 1. C. Start two boric acid transfer pumps, increase auxiliary chu[ing pump (P 7) flow to at least 15 gpm, close CH M-87, open BA-M-36 and 37.- D. Verify a charging pump operating with CH F-38 open, start two boric acid transfer pumps, open BA-M-36 and 37, close CH-M-87. Answer; D Justfecabon: a Flow will continue from the VCT because CH M-1 and 87 are open. (Higher pressure than RWST.). b.. No boric acid flow due to BA-M-36 and 37 closure and BA-A-80 was not opened.
- c. Does not meet flowpath requirements of Attachment A in FR-S.I.
- d. CORRECT. This flowpath meets FR-S.1 emergency boration requirements.
.Queshon Topic: Actions for emergency boraton in FR S.1
- 7 RO y SRO KlA Rating 4.2/4 4 CFRw: RO 55.41(b)(5) SRO 55.43 (b)(5)
' System: 024 K/A s. AK3.02 i
, ELOs. CVCS-0902 3; EAS-01014 l
i
Reference:
FR-S.1 (Step 4) i Page 69 of 100 4/13/97 J
RO EXAM REVIEW Group 1 EPE - Question-The plant is at HFP.- During inspections it is discovered that the reactor trip breaker manual pushbutton wiring is not in compliance with the IEEE standard. What action is required? A. Place the reactor in hot standby within six (6) hours and in hot shutdown in the following thirty (30) hours. - B. Attempt to repair in the next seventy-two (72) hours (as allowed by the remedial action statement). C. Commence a reactor shutdown within one (1) hour and place the plant in hot shutdown within six (6) hours. D. Immediately trip the reactor via the ATWSeuSS pushbuttons and be in cold shutdown within six (6) hours. Answer: C Jushficatio'. *
- a. Does not meet requirements of Technical Specification 3.0.A.
- b. This remedial action is non applicable for the manual reactor trip unit.
c.. CORRECT. This meets the Technical Specifications requirements.
- d. Undesirable to trip reactor when a controlled S/D is allowed and available.
-- ._. - . _ . _ - . - . . . - - _ _ . . , - - . - _ . . ~ . . . . . - . - . . . - , . ~ . -_.
Queshon Topic: Kno# edge of one hour TS acton(system) V RO y SRO K/A Rating 3.0/38 CFRs. Ro 55.41 (b)(10) SRO 55 43 (t)(2) System- Genenc K/A s: 2.1.11 ELOs.- AD-01044 Reference. TS 3.9 A and 3.0 A - Page 70 of 100 4113/97
-s
RO EXAM REVIEW Group 1 EPE Quvsbon: The plant has experienced a LOCA with failed fuel. The containment spray system is operating in the recirculation mode. RHR heat exchanger tube leaks h A spread contamination throughoat the PCC and SCC systems. Chemistry wants to increase the recirculation flow rate through ti,e PCC and SCC chemical addition tanks to > 20 gpm (bypassing the heat exchangers) to facilitate degassification. Why is this situation undesirable? A. It could lead to an unmonitored release via the off gas filters and primary vent stack. B. Increased degassification with residual system chromates can form chromic acid which will accelerate piping corrosion. C. Inadequate PCC/ SCC Cow through the PCC and SCC heat exchangers could violate conditions in the accident analysis. D. The PCC/ SCC surge tanks become a point source for radiation in an uncontained and l unfaielded area of the plant. Answer: C Jushficabon-I
- a. Although a release could occur, it is NOT via an unmonitoied path.
- b. Residual system chromates deter rather than accelerate piping corrosion.
- c. CORRECi. There is a 20 gpm limit on recirculation Dow,
- d. Although the surge tanks will become point sources, the system is contained and temporary shielding can be erected.
Question Topic: Cause of possible CCW loss V RO g SRO K/A Rabng 29'3.6 CFRs RO $5 41 (b)(7) SRO 55 43(b)(5) System: 026 K/A #. AA2.02 ELO8. CC-09021 Reference. OP 1 15-1 (2.0,4.21)- EDCR 94-53 . Page 71 of 100 4/13'97 I l 4
RO EXAM REVIEW Group i EPE Question: Which of the following would indicate that the pressurizer is in a saturated condition? A! On a reactor coolant system insurge, RCS pressure increases until the PORV setpoint is-reached. B. On a reactor coo: ant system outsurge, RCS pressure decreases to the TM/LP trip setpoint. C. On a reactor coolant system insurge, RCS pressure increases rapidly as the bubble compresses. D. On a reactor coolant system outsurge, RCS pressure decreases slowly as the steam / water interface flashes. Answer; D Justificabon.
- a. Indicates presence of non-condensibles in steam bubble.
- b. PZR is not in a saturated condition.-
- c. Indicates p:esence of non-condensibles in steam bubble.
- d. CORRECT. The PZR is saturated and water flashes to steam on the outsurge.
- Queshon Tope: Defn of sat. temp based on pn insurDeloutsurge (R/O only) f9RO'^SRO K/A Reung 3.1/3.4 CFR8-. RO 55.41 (b)(5)
! System: 027 KIA 8. AK1.01 ELOs. PPM-0106-2
Reference:
STM Chapter 3 (Section C.3) - L.__..__._.._. _ Page 72 cf 100 4/13/97 l
RO EXAM REVIEW Group 1 EPE Queston A main steamline elbow upstream of the #2 non-return valve breaks while at 100% power and results in entry into E-0," Reactor Trip or Safety injection." An operator fmds all three blowdown valves (BD-T-12,22 and 32) still open when verifying ECCS valve alignment. Funher analysis indicates that the HELB blowdown valves (BD T-141 thru 146) are also open. Why is this condition a concern for this accident situation? A. BD T-141 thru 146 should have closed on low S!G level to prevent an excessive cooldown and possible return to criticality. B. BD-T-12,22, and 32 should have closed on the SlAS/CIS signal to preserve feedwater for decay heat removal. C. BD-T-12,22, and 32 should have closed on low S!G level to prevent an excessive cooldown and possible return to criticality. D. BD-T-141 thru 146 should have closed on the SI A S'CIS signal to preserve feedwater for decay heat removal. l l k.swer: A Justrication: a CORRECT. The EDCR was done to remove restrictions placed on a return to criticality during a SLB event.
- b. The closure signal is correct, but preservation of the containment integrity boundary is the reason these valves go shut.
- c. These valves close on SlAS!CIS or high blowdown tank pressure, not on low S'G level.
- d. These valves close on a HELB signal or low S!G level. The HELB signal is for preservation of safety related equipment in the RAD controlled area Question Topic: Reactivity effects for SLB (effect of CID)
V RO y SRO K/A Ratng 41/4 4 CFRs. RO 55 41 (bX7) SRO 55 43(bX3) System: 040 K/A #. AK1.05 ELos. EAS-0903-13. 80-0101-1 Reference' EDCR 94 50 Page 73 of 100 4/13/97
RO EXAM REVIEW Group 1 EPE ouestion. A fire in the protected cable tray room (AOP 2-90-1) has spread into the control room ceiling and an evacuation of the control room is imminent. A station blacko'it must be created by the operator: A. In order to prevent spurious PORV operation when de-energizing MCC-7A and 8A. B. In order to prevent overloaded diesels because 3T5 and 4T6 will fait closed. C. Due to the inability to control systems that may be operating. D. Due to the inability to cool key plant components, such as RCP's. Answer: D Justficaton
- a. Spurious PORV actuation is a major concern, but they are not powered from these MCC's.
l
- b. 3T5 and 4T6 do not fail closed on a station blackout..
- c. CORRECT. Control of operating systems ;s the major concern.
- d. The RCPs wou!d be secured in this condition.
Question Topic Vitat equipment and controf systems mantained
& RO ^) SRO K/A Rating 33'40 CFRs. RO 55 41(b)(10) SRO $5 43 (b)(5)
' System: 067 K/A s AA2.16 ELO# AD-0102 8
Reference:
AOP 2-90-1 Page 75 of 100 4/13/97
,,------,-,-.,--------,,--,,-,-,,-v,:- RO EXAM REVIEW I E Grouc 1 EPE Quesbon:. The plant is in a cooldown using AOP 2 90-8," Plant Cooldown From Alternate Shutdown Panel." Several times in this procedure the operator is cautioned that the RCS cold shutdown boron concentration is not reached unless pressurizer level is increased to 80% at some point during the cooldown. Why must the pressurizer be filled to this level? A. Pressurizer level instrument (LI.106) on the ASP is hot calibrated,80% PZR level ensures that the PZR will have a bubble during the cooldown.-
- d. This guarantees adequate shutdown margin is achieved for the cold shutdown condition by ensuring sufficient RWST water is injected into the RCS.
C This ensures the cold shutdown boron concentration listed in the TDB, even with rods fully withdrawn, is achieved. D. This ensures adequate RCS volume in the event that normal power cannot be restored and a seal water return MOV does not close.
' Answer: B Justification:
- a. LI-106 is a hot calibrated instrument. It will read somewhat inaccurately during the cooldown but basis for 80% is boron concentration.
- b. CORRECT. 80% PZR level ensures adequate boron is injected.
- c. The rods being fully withdrawn are not included when cooling down in this condition.
- d. While RCS volume considerations must be taken into account if a seal return MOV does not close the PZR level, requirements are based on boron concentration.
_ _ _ _ _ - . _ _ . - - _ _ _ _ _ _ _ _ . . . _ . ~ _ _ . - _ - _ . _ . - . . . _ _ _ . _ - . . Question Topm: Actons for fre onsne/why acheve 80% pzt level 7.RO' 7 SRO KlA Ratog 3.3/4.1 CFR#. RO $$ 41 (b)(10) SRO 55 43 (b)(5) System: 067 KIA 8. AK3.04 ELO#. EAS-01504
Reference:
AOP 2-90-8 s Page 76 of 100 4!13/97 ir
RO EXAM RiiVIEW-Group 1 EPE Ouestion; During a fire, the PSS mans the alternate shutdown panel (ASP) and proceeds to gain control of equipment necessary to minimize loss of RCS inventory. - Which components must be controlled to stop RCS leakage? A. Drain header isolation valve (DR-M-3) to "CLOSE"; EFCVs (MS 11,22, and 33) to "CLOSE"; letdown temperature control valve (LD-T 5) to "CLOSE."
- Bi Drain header control valve (DR-A-6) to'"CLOSE"; letdown temperature contrst valve (LD-A-
- 68) to "CLOSE"; RCP seal water return valves (SL-M- 29,40 and 51) to "CLOSE."
C. Drain header isolation valve (DR-M 3) to "CLOSE"; letdown temperature control valve (LD-A-
- 68) to "CLOSE"; RCP seal water return valves (SL-M 29,40 and 51) to "CLOSE."
D. Drain header control valve (DR-A-6) to "CLOSE"; letdown temperature control valve (LD-T ") to "CLOSE"; RCP seal water return valves (SL-M-29,40, and 51) to "CLOSE." Answer. D Justification. i
- a. EFCVs are not used to control RCS inventory loss on an Appendix 'R' fire. Switches are used to prevent the EFCVs from failing open.
- b. The seal water return valves require altemate power via MCC-9Bl.
- c. ~DR M 3 and LD A 68 are not controlled at the ASP, although they perform similar functions as DR-A-6 and LD-T-5.
- d. CORRECT. The seal retum valves require ASP supplied _ power in order to shut the valve'at the ASP.
Questum Topic: Auxiliary shudown panellayout V RO .Q SRO KlA Ratog -3 9/4.0 CFRs. RO 55 41(b)(4) SRO $5 43(b)(5) i System: 068 K/A s. AK2 01 i ELos. APPR 0101-4
' Reference; STM Chapter 34: AOP 2 90-1 Page 77 of 100 4/13!97 l
RO EXAM REVIEW Group 1 EPE Quesbon: While in FR C.1, " inadequate Core Cooling," the Operator notes LPSI flow oscillations when running a containment spray pump and a LPSI pump from the same safeguards sump. Assuming , adequate water level in containment and the desire to run the LPSI pump during RAS to avoid inadequate core cooling, what action in the Control Room would mitigate LPSI pump cavitation in this condition? A. Reset the RAS signal, throttle LSl M-11,21, and 31 (LPSI loop stops), monitor pump amps, and discharge pressure. B. Reset the SIAS signal, throttle LSI-F 59 (RHR flow control), monitor pump amps, and - discharge pressure. l C. Reset the RAS signal, throttle LSI-F-59 (RHR flow control), monitor pump amps, and discharge pressure. D. Reset the SIAS signal, throttle LSI-M-11,21, and 31 (LPSI loop stops), monitor pump amps, and discharge pressure.
,- Answer: D Justficabon:
- a. While reset ;ng, the RAS signal has no deliterious effects on the system. You will be unable to thrente 1. PSI ficw.
- b. Throttling LSI F-59 cannot be accomplished unless several other barriers are removed (i.e., must leave Control Room.).
- c. Throttling LSI-F-59 will help the cavitation condition, but must be put into service from outside the Control Room.
- d. CORRECT.- The SIAS signal must be reset to throttle LSI-M-il,21, and 31. This wili allow continuous LPSI flow without challenging NPSH requirements.
Queshon Topic: Interretabonship between inadeq cool /LPSI pps ! Q RO Q SRO K/A Rahng 3 9/4.1 CFR8- RO 55 41 (bX10) SRO $5 43(bX5) I System: 074 - K/A #. EK2.05 ELOs. ECCS-0101 17; ECCS-0902-1 Refererv:e: FR-C.1 BKGD Document (Step 2)
. _ _ . . - a Page 78 of 100 4/13/97
l l RO EXAM PEVIEW Group 1 EPE Question: The main turbine has numerous protective devices assuring plant and equipment safety including less direct methods of tripping the turbine. Which of the following methods will generate a remote turbine trip signal? A. With TlH, KG 1, and KGl-375 open, the turbine will trip on a one minute time delay (anti-motoring). B. With two-out-of four (2/4) intercept valves closed and two-ot t-of four (2/4) reheat valves closed, the turbine will trip. C. With a low #2 S/G water level on channels A & B level indications (2/2 taken twice), the turbine will trip. D Closure of all three (3) EFCV's, automatically or manually via operatcr action, will trip the turbine on low steam pressure. Answer C Justficaton a With these breakers open, you do not satisfy anti-motoring logic.
- b. This is ii. sufficient information for determining if a trip signal will be generated.
- c. CORRECT. This signal will trip the turbine,
- d. EFCV closure will not trip the turbine.
. - _ - . . . - ~ . - _ _ . - . - - - - - - - . - - . . . . . - - - . - . . .
Queston Topic Manual trip of reactor & turbine Q RO y SRO K/A Ratng 4.3!4.5 CFR*. RO 55 41 (b)(10) SRO SS 43 (b)(5) System 068 K/A 8 AA1.23 ELOS MT 0101-9
Reference:
RO-L-3 5 (ESK 9C,9E. BAA,8AB,8AC & 8AD) Page 79 of 100 4/13/97 _~. -
RO EXAM REVIEW Group 1 EPE oueston: . In preparation for restoring AC power following a total loss of AC, ECA-0.0," Loss of All AC Power," requires the operator to place most MCB operated plant equipment in PULL-TO-LOCK except for the PCC and SCC pumps, where one of each is left in AUTO. Why are the PCC and SCC pumps left in AUTO? A. To supply linmediate cooling water to the RCP seal in order to minimize seal damage. B. To provide immediate loading on the EDG in order to prevent overspeed. l C. To supply immediate cooling for the RHR heat exchangers to continue plant cooldown. D. To allow for immediate cooling of the EDG to prevent overheating. Answer; D Jushficabon:
- a. The RCP seal is not an immediate concern at this time.
- b. The chargirig pump will provide immediate loading on the diesel,
- c. No guarantee that cooling water is needed for the RHR heat exchangers.
- d. CORRECT. The EDG's require immediate cooling to prevent overheating.
Queston Tnpic Restoraton of AC/why close PCC breakers? ly. RO P SRO - K/A Rabng 4 3/4.5 CFRs. RO 55 41(b)(10) SRO 55 43 (b)(5)
- System: 055 KIA #: EA1.07 ELO*. EAS-01017 i
Reference:
. ECA-0.0 (Step 9) Pagt 80 of 100 4/13/97
RO EXAM REVIEW
' Group 2 EPE Quesbon:
The following conditions exist during a refueling outage with the plant in Condition 3, Cold Shutdown:
- The RCS is at the refueling boron concentration;
- The "A" diesel generator (DG-1 A) is tagged out for maintenance; The RHR pumps are available, but isolated for recirculation tests;
- X-16 is tagged out foryerification of transformer taps; .
- Pressurizer level is 85%.
Chemistry and operations have decided to reduce the RCS boron concentration to the cold shutdown requirement. What actions are required before reducing RCS boron concentration?
- A. The charging pump (P-14B) must be aligned to the RCS and providing a minimum 150 gpm Cow of borated water,
- B. Place letdown in service with a minimum 40 gpm Dow.
C. X-16 must be aligned to a 6900 volt bus and an RCP staned. I f D. An RHR pump must be aligned to the RCS providing a minimum 2000 gpm Dow. Answer:- D Justificanon:
- a. - A boration How path must be established but is not required to be in operation.
- b. This is not a requirement to reduce RCS boron concentration.
- c. Boron concentration cannot be reduced unless an RCP is in operation but the pressurizer must be <80H. level.
- d. ' CORRECT. Boron concentration cannot be reduced unless an RHR pump is in operation at a minimum Dow of 2000 gpm.
Ouesbon Topic; Knowledge of LCO's and safety hmsts Q RO p SRO K/A Rabng 3.4/4.1 CFR#-. RO 55 41 (bh6' SRO 55 41(b)(2) System: Genenc K/A # 2.2.22 j ELos. RCP-0902-1
Reference:
. TS 3 3 A & 3 4.0 i _ _ _ . _ _ _ _ . _ _ _ Page 81 of 100 4/13/97 i
i l RO EXAM REVIEW Group 2 EPE , ouesbon. h The reactor has tripped from 100% power due to a loss of feedwater. In an effort to restore feed - Dow to a S/G following a reactor trip, the operator is cautioned in FR-il.1 to verify that blowdown
, flow has been secured. Blowdown flow should have been isolated by:
A. Automatic action from the diverse scram system (DSS). B. Automatic action on a low S/G level (35%). f C. Automatic action on a diverse turbine trip (DTT).
- D. Automatic action on a low S/G pressure. .
Answer: B Justification.
- a. The diverse scram system does not affect these valves.
b, CORRECT. FSAR margin to restart on a SLB was improved by isolating B/D Gow. c The DTT actuates at 35% S/G level, but is a different signal than that for the B'D vahes.
- d. Low S/G pressure isolates normal and eraergency feedwater, but does not isolate S/G blowdowit
! Question Topic: Blowdown flow from S/G on RX tnp Q RO y SRO K/A Rating 3.7/41 CFR8; Ro 55 41(bX10) SRO 55 43(bX5)
, System: 007 K/A 8. EK1.06
.ELO# EAS-01017; BD-0101 1
Reference:
FR H.1 BKGD Document Page 82 of 100 4/13/97 _ _o
RO EXAM REVIEW Group 2 EPE
- Quesbon:
Reactor trip breaker positions are shown on the attached drawing. Which statement identifies the most likely result if TCB-2 and TCB-6 are immediately reclosed? A. The reactor trips due to loss of power to the output AC contactors. B. The reactor remains operating due to redundant CEDM power supplies. C. The reactor trips due to improper paralleling of MG sets. D. The reactor remains operating due to automatic sychronization.
. Answer; C Justificabon:
a Power is not lost to the CEDM buses until the lack of synchronization.
- b. M.e reactor will trip due to paralleling out of phase.
- c. CORRECT. The MG sets must be paralleled across the tie breaker.
- d. There is no auto synchronization of these buses.
Ouestion Topic: RX tnp status panet, pareuehng cut of phase V RO y SRO KIA Rating '. 5/3 6 CFR8. RO $$ 41 (b)(7) SRO 55 43(b)(5)&(6)
' System: 007 K/A 8. EK2.03
- ELos: CEDS.0101-4. 0101-5,01016
Reference:
OP 1-22 7 (Attachment A). STM Chapter 11 (Fg 11-16) Page 83 of 100 4/13/97
CEDM POWER SUPPLY BUS-9 BUS-12 0
- MANUALINPUT -
ACINTERRUPTERS
\ INPUT AC CONTACTORS #
#1 MOTOR GENERATORS #2:
< 240VAC 35 :
O MANUAL McB-1 -OUTPUT CKT BREAKER CB-2 -
.9. pOUTPUT A ACTORS
--g
) o---
$ @ t C.LOS60 e" fels Q - O&1lkbl.-
B r FROM - -
. 08 7 --
FROM RPS g/ 6 T 3 RPS
/
o ',a
'g_ _
CB TCB 9/ _ _ , O vm INDIVIDUAL CEDM i T INDMDUAL CEDM CEDM - P P AA ME S CONTROL SYSTEM pkO q i ; I I k V k r--- r---g CEDM _J CEDM r _. CEDM CEDM -J CEDM p-. CEDM COILS COILS COILS COILS l___,3 COtLS COtLS CEDM 1 3/2&96 R O-L 4.4 AO.L-4.1 1 _0
L-RO EXAM REVIEW Grouc 2 EPE Queston-During the feed and bleed termination sequence of FR H.1," Loss of Secondary Heat Sink," three steps must be completed: 1.) Throttling of HPSI flow (<l 50 gpm); 2.) Checking RCS status
- (SMM, PZR level) and; 3.) Isolating the bleed paths (closing PORVs). Why is HPSI floi" throttled during the termination sequence?
A. To ensure HPSI flow is adequate to remove decay heat even without a steam generator available. B. If HPSI flow cannot be throttled the operator would be required to exit FR-H. I and enter E-3,
" Steam Generator Tube Rupture."
C. With HPSI flow throttled to <150 gpm, the normal charging flow path will be able to meet RCS inventory requirements. D. Because the PORVs must be closed before the operator can exit FR-H.1 in the event of a suberiticality or core cooling red path. Answer: C Justficabon:
- a. You would be unable to exit FR-H.1 unless one S/G was established with level >41% (52%).
- b. If HPS! flow cannot be throttled, the operator may be required to enter E-1, " Loss of Primary or Secondary Coolant."
- c. CORRECT. Eventually core decay heat is low enough to allow restoration of normal charging and letdown,
- d. This violates rules of usage for FRP's. The operator may exit any time a higher priority CSF is met.-
Queshon Topic: ECCS termenaton/ttwotthng entena V RO Q SRO K/A Raung 4 0/4.5 CFRs. RO 55 41(b)(10) SRO .45 43 (b)(5) System; 008 K/A W. AK3 05 ELO#: EAS-0101-7
Reference:
FR H.1 BKGD Document (Step 25) Page 84 of 100 4!13/97
O ^ RO EXAM REVIEW ! Group 2 EPE ; ouestiou - ' The plant has experienced a small break LOCA and containment pressure has stabilized at 6.5 L psig. The ECCS lightbox indication for PCC M 219 shows BOTH the blue and green lights l l flashing. A check of PCC M 219 on the MCB shows both the red and green valve position lights lit. In this condition PCC M 219 is: l
- A. Completing its closure stroke and will indicate a green " closed" light in a few moments.
. B. Completing its opening stroke and will indicate a red "open" light in a few moments.
C. Without AC control power due to inadvertant opening of the MCC-78 supply breaker. D. Tripped on overload and may require manual actions to close the valve.
- Answer: D 4
- Justifcation:
4 a. Only the green ECCS light would be Dashing in this condition. . b, PCC-M 219 closes on a CIS to isolate PCC to containment.
- c. If AC control power was NOT available, the MCB indicating lights would be out.
- . d. CORRECT. MOV overload is indicated by both lights Gashing MCB indicating lights lit.
Question Topc- Containment isolation system. PCC.M-219 loss of power RO Q SRO K/A Rating 4.0/4.1 CFR8, RO 55 41(b)(7) SRO 55 43(b)(5) j System- 009 KlA 8. EA1.08
' ELO#: ESF-0101-3
Reference:
STM Chapter 6 , L_ __ _ _ , . _ . . . _ _ _ _ _ . _ - _ _ _ - - _ _ - -- )' i 3 7 Page 86 of 100 4/13/57
\
RO EXAM REVIEW Group 2 EPE Question: Procedure FR-S.1, " Nuclear Power Generation /ATWS," was entered from E-0, ' Reactor Trip or Safety injection" when it was determined that the reactor was not shutdown. A caution in FR-S.1 states, "If all S!G's are faulted, maintain total EFW flow at least 60 gpm per running EFW pump AND balance now to each S/G." What is the reason for both of these requirements? A. Maintaining 60 gpm now ensures adequate cooling flow through the pump while the balanced flow ensures the S/G's remain ' wetted' which minimizes thermal shock to the tubes and tube sheet. 4 B. Maintaining 60 gpm flow provides minimum indication of pump operability while the balanced flow ensures the S/G's tube bundle area will not dry out causing sludge densification and possible tube failure. ! C. Maintaining 60 gpm Dow ensures adequate cooling Dow through the pump while the balanced now ensures the S!G's tube bundle area will not dry out causing sludge densi0 cation and possible tube failure. D. Maintaining 60 gpm now provides minimum indication of pump operability while the balanced flow ensures the S!G's remain ' wetted' which minimizes thermal shock to the tubes and tube shec. Answer: A Justification
- a. CORRECT. These are the conditions defined in the background documents.
- b. There is no minimum indication speci0 cation on these pumps.
- c. Dryout will cause sludge hardening, but there is no documentation of this condition damaging tubes.
- d. See 'b' and 'c'.
Question Topic- EOP actions for ATWS (RO only) V RO 7 SRO K/A Rahng 44/4.7 CFR8. RO $5 41 (b)(10)
- System: 029 K/A 8. EK312 ELO# EAS-0101 7
Reference:
FR.S.1 BKGD Document Page 87 of 100 4/13/97
l l RO EXAM REVIEW j Group 2 EPE Ovesbon: The plant has undergone a large break LOCA. During review of the Critical Safety Function l Status Trees the STA reports that core region temperatures are greater than 700 F and recommends transitioning to FR-C 2, " Degraded Core Cooling." Prior to transitioning to FR-C.2, the Shift Operating Supervisor asks you to verify that core exit thermocouples (CETs) do in fact indicate greater than 700 F on an inadequate core cooling event. What action is required to verify the existence ofinadequate core cooling? A. Verify the average temperature of all CETs read greater than 700 F using the CET map. B. Verify only one (1) CET reads greater than 700 F using the CET map, C. Verify all operational CETs read greater than 700 F using the CET map. D. Verify at least Ove (5) CETs read greater than 700 F using the CET map. Answer: D Justficabon
- a. Redux cooling fron: the steam generators could keep core periphery CETs well below 700 F and average temperatures ofless than 700 F.
- b. This does not account for failed CETs and, therefore, is not a desirable decision for FRP entry.
- c. It may be impossible for this condition to be reached on the CET map due to reaux cooling.
- d. CORRECT. Westinghouse BKGD Documents suggest this number to prevent failed detector entry OR renux cooling bypassing.
Queston Topic Venftcabon of adequate core cookng (RO only) V RO _ SRO K/A Rahng 4.5/4.7 CFR#. RO 55 41 (b)(5&14)
. System- 011
. K/A #. EA2.10
- ELO#. EAS-0101 10 Reference-. OPS Memo RAM 7/24/96 4
4 Page 88 of 100 4/13/97
RO EXAM REVIEW Group 2 EPE Oueston:
. Your crew is performing actions during a small break LOCA. You have transitioned from E-0, -]
" Reactor Trip or Safety injection," to E-1, " Loss of Primary or Secondary Coolant," and are ]
checking to see if HPSI flow should be reduced. - Several parameters, such as core rer, ion ' subcooling, secondary heat sink, pressurizer pressure and level must be satis 0ed. If you were to misdiagnose secondary heat sink availability and entered ES-1.1, "Si Termination," how could this effect pur recovery actions? A. Because HPSI now could be maintaining core region subcooling, when now is reduced the lack of heat removal could require reinitiation of the HPSI flow. B. Because core region subcooling is the most direct indication that core cooling is being maintained, it is unlikely that the recovery actions will be inhibited by inadequate heat sink.
~ C. Because pressurizer RCS pressure and level are satisfied, the break size is such that in reduced .
HPSI Hew conditions, there will always be suf0cient RCS inventory for core cooling. D. Because HPSI Dow could be maintaining core region subcooling, when How is reduced the lack of heat removal could require entry into FR C.1, " inadequate Core Cooling." Answer; A Justificabon , .
- a. CORRECT. All four (4) criteria must be met or HPSI flow cannot be reduced.
- b. While it is true that subcooling is the most direct indication of heat removal, it is about to be reduced and, therefore, may require reinitiation.
- c. Inventory alone is not a sufGcient measure of adequate core cooling.
- d. Although this is a possibility, the reinitiation of HPSI flow would be sufGeient to restore core -
cooling and only a boni0ed loss of heat sink would require entry into FR-H.1, and not FR-C. I. i Queshon Topic: A tors for sman break LoCA lV RO y SRO K/A Rahng 4.2/4.5 CFRs. RO 55 41(b)(10) SRO 55 43(b)(5) { System: 009 K/A s. EK3 21
!ELO*. EAS-0903-1; EAS-0101 7
Reference:
E 1 BKGD Document (Step 6) l L I i ) i Page 89 of 100 4!t 3/97
. . . - , n .. ,.
RO EXAM REVIEW Group 2 EPE Oueston c During a reactor startup, while in the manual sequential mode, a continuous rod withdrawal accident occurs and the RPS fails to activate a plant trip. Choose the list of operator actions that would act to mitigate this accident. A. Place the ATWS/ DSS switch on the rear of the MCB to " TEST", press both "ATWS/ DSS trip ( MG 1 A-1B" buttons on the MCB, open supply breakers to buses 9 and 12 (remotely). B B. Press at least one "ATWS/ DSS trip MG-l A 1B" button on the MCB, open supply breakers to <
%se o and 12 (remotely), open supply breakers to MCC's 9 and 12 (locally). =
C. Press both "ATWS' DSS trip MG 1 A-1B" buttons on the MCB, open supply breakers to buses 9 and 12 (remotely), open supply breakers to buses 9 and 12 (locally). D Open supply breakers to buses 9 and 12 (remotely), de-energize both pressurizer pressure control channel instruments (PT-102X and PT-102Y), press both "ATWS' DSS trip MG 1 A-1B" buttons on the MCB Answer C , Aistricahon-a The ATWS/ DSS test switch will NOT open the MG set output breakers.
- b. Both ATWS/ DSS buttons must be depressed to actuate ATWS' DSS.
- c. CORRECT. Although not normally accomplished from the control room, openirig the bus supply breakers will trip the MG sets.
- d. The PZR pressure input to DSS comes from safety channels PT.102 A, B, C, and D, not control channels 102X and Y.
Queston Topic: Actons on CRW it auto tnp fads to work (RO only)
'V. RO SRO K/A Raung 45/48 CFRs. RO 55 41 (b)(6)
System- 001 K/A #. AA2 03 ELO# CEDS-0902-1, EAS 0101-6
Reference:
STM Chapter 11 and 12. EDCR 89-57 r Page 90 of 100 4/13/97
RO EXAM REVIEW Group 2 EPE Question: The reactor is cooling down with the "A" RHR pump and the "A" RHR heat exchanger m service. l The "B" RHR pump and the "B" RHR heat exchanger are operable and in standby. The RCS is not yet adequately vented per OP l-7, " Plant Cooldown." PORV "A"_VPSR setpoint fails high. The "A" train PORV (PS S-14) immediately opens. What action is required? A. Shut PR-M-16, determine the cause of the PORV opening and align the RWST to the RHR pump to compensate for lost inventory. B. Shu'. PR-M-i6, start the "B" train RHR pump (P-128) and align SCC to E-3B in order to . maintr in core cooling. C. Shut PR-M-16, stop P-12A because RH-M-1 closes, then align an alternate flowpath for core cooling. D. Shut PR-M 16, open RH T-12 and LSI-F-59 to the full open position to facilitate venting of RHR piping and valves to RCS. Answer: C Justfcation:
- a. The PORV opens due to exceeding the VPSet setpoint. Adding inventory is not a concern at this time.
- b. Starting the B pump will only exacerbate the problem as a loss of suction is in progress.
- c. CORRECT. When PIC-103 fails high, RH-M-1 will auto close at 585 psig. An alternate Dowpath must be immediately aligned.
- d. Opening LSI-F-59 and RH-T-12 could result in excessive cooldown rate and under no condition vents the RHR piping.
Question Topic: SNftng to attemate nowpath for RHR j2 RO y SRO K/A Rating 31/34 CFRs. RO 55 41(b)(7) SRO 55 43 (b)(5) i System: 025 K/A # AK3 01 ELOs; ISR-03013; RHR.01015; PPC-0902-2
Reference:
AOP 2-34; STM Chapter 3 I__ . _ . _ . . . . _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ - - . - Page 91 of 100 4f13!97
RO EXAM REVIEW 1 l Group 2 EPE j - Quesbon. , e The reactor is being started up following an extended refueling outage The fission chambers swap i from CPS to % PWR at 1000 cps and 10-6% power respectively, if the reactor must be shut down after critical rod data is obtained, what relationship exists between CPS and % PWR indication as the reactor enters the source range?
-A. Counts per second (eps) and % power have no relationship because of the number of detectors used by the source and wide range instruments.
B. Counts per second (eps) and % power are inversely related, that is 10-6% power equals 1000 cps; 10-7% power equals 10,000 cps, etc. C. Counts per second (eps) and % power are directly related, that is,10-6% power equals 1000 cps; 10 7% power equals 100 cps, etc. D. Counts per second (eps) and % power are inversely related, that is,10-6% power equals 1000 cps; 10-7% power equals 100 cps, etc. Answer; C Justificabon'
- a. There is a direct relationship between source and wide range readings.
- b. As count rate decreases so does the value of % power.
- c. CORRECT. There is a direct correlation between % power and CPS.
- d. This is a direct, not an inverse, relationship.
Quesbon Topic: Overlap of source to wde range Nrs
;7, RO p SRO K/A Rahng 3.1/35 CFRs. RO 55.41 (b)(6) SRO $5 43 Q)(6)
- j. System: 032 K/A #: AA2.04 ELOs. NI-0101-3, NI-0101 13 i
Reference:
STM chapter 14 (Secuon 2.1) , l i
^
Page 92 of 100 4/13/97
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N 1 1 RO EXAM REVIEW i: ) Group 2 EPE ouestion- ! A #3 steam generator tube rupture is in progress and the plant has been cooled and depressurized } to minimize RCS flow into #3 S/G. At this time, the operator is required to check #3 S/G pressure
- to determine ifit is stable or increasing, it is determined that the ruptured steam generator is continuing to lose pressure and cannot be maintained 250 psig greater than the intact S/G's. Why is l the ruptured S/G pressure continuing to decrease?
- A. #3 S'G has multiple tube ruptures which is causing pressure in the S/G te decrease.
i [' B. The intact S/G's were overcooled and the high pressure in #3 S/G is backfeeding into the RCS. ! C. When safety injection was blocked in the preceding steps, the operator did not maintain RCS
- temperature stable.
i l D. #3 S/G is also undergoing a steam or feedline break (faulted). i [ Answen D Justification: l a. This condition will not cause #3 S/G to continue its depressurization. [ b. It is impossible to overcool the intact S!G in this situation. #3 S/G is faulted and that is why it continues to depressurize. l
- c. Maintaining RCS temperature will only affect subcooling requirements and temperature
! necessarv to terminate cooldown.
- d. CORRECT. You must exit E-3 (Step 23) and go to ECA-3.1.
Question Topic: Actions in EOP's for SGTR V.RO p SRO K/A Rating 42/44 CFR#. RO 55 41(b)(10) SRO 55 43 (b)(5)
. System 037 K/A 8' AK3 07 l
~ELO# EAS-0101-7 .
~,
Reference:
E-3 BKGO Document (Step 23) Page 93 of 100 4113/97
.,,,v,- m n,- . ~ , -.. n. ,,y. v w,,w-~-
-. s -- - _,
RO EXAM REVIEW Group 2 EPE I Queston. l The plant has tripped on a main steam header rupture in the turbine hall. The EFCV's have closed ) and steam generator pressures are hovering around 400 psig. What must be done to open the EFW butterfly valves? A._ Place the excess flow check valves in the " CLOSED" position. B. Place the EFW-A-338,339, and 340 "NORMAUALTERNATE" T switch in the EFW pump room to " ALTERNATE." C. Verify adequate instrument air pressure in the receivers m the EFW pump room so that the valves will open. - D. " MANUALLY" open the EFW butterfly valves (EFW-A 338,339, and 340) from the EFW pump room. Answer; B-Jushficaton:
- a. This signal has no effect on the EFW valves.
- b. CORRECT. This de-energizes the solenoid and the valves fail open.
- c. The valves are held shut with air pressure. A loss of air causes the valves to fail open.
- d. No method'is availat,le to manually open these valves.
Queston Topic: AFW controis meludog att sources (EFW.A-338,339,340) .V RO y SRO K/A Rahng 4 5/4 4 CFR#. RO $5 41 (b)(7) SRO 55 43 (b)(5)
- System. 054 K/A s AA1.01 ELO*. AFW 09021 & 2
Reference:
STM Chapter 28 (Secton 3.0); ESK-7GA Page 94 of 100 4/13/97
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, RO EXAM REVIEW
- Group 2 EPE
' Oueshon:
} During maintenance of battery bus #3 (disconnected from the bus), a loss of DC bus #3 occurs (the 4-
- vital AC bus is still available). The plant does not trip. The RO reports that one PORV (PR-S 15)
! ; and its associated block valve (PR M 17) are energized and one (l) set of proportional heaters (E. _ , 2PB) are deenergized. Do you concur with the analysis of this situation? Why? ! A. Yes, because you verify that the indicating lights for E-2PB are ofTand the lights for PR-S 15
- and PR-M 17 are on.
B. No, because if E-2PB has lost its indication, then PR-S-15 and PR-M 17 should also have lost their indications. C. Yes, because PR-S-15 and PR-M-17 retain DC control power on a loss of DC bus #3. D. No, because the proportional heaters have lost indication only. The E-2PB breaker is still closed. Answer D Jusbficabon:
- a. E-2PB lights are off because of a loss of DC control power to bus 8 components.
- b. PR-S-1.5 and PR-M-17 are supplied from MCC 8B. Their indication is provided via AC control power of the MCC breaker.
- c. These valves are AC control power supplied.
- d. CORRECT. The breaker did not reposition on a loss of bus 3. It only lost its indication and control.
- Ouesbon Topic: Venfcabon of loss of DC Bus #3 Q. RO Q SRO K/A Rabng 2.7/4.1 CFRs. RO 55 41(bX10) SRO 55 43 (bX5) 1 System: 058 K/A 8. AA2 01 ELOW: DC-0902 2;ISR-0303-11; PPC-0101-11; AC-0101 19
( Reference; AOP 2-13 I i i l l Page 95 of 100 4/13/97
1 RO EXAM REVIEW , Group 2 EPE Ovestxm: During alignment for a liquid waste release, contractors moving equipment through the PAB inadvertantly bump and raise the setting for the flow controller (FC-3802) which was set for automatic operation at 50% open. Approximately fifteen (15) minutes into the release, the auxiliary operator reports a high differential pressure (40 psid) across the test tank release Olter (FL-66) and the filter is bypassed. Which group of statements represents indications you would expect to see on the liquid waste disposal system monitor (RM-3801)? A. The initial radiation level on RM-3801 is LOWER than expected when the release begins and LOWER than expected after the filter is bypassed. B. The initial radiation level on RM 3801 is HIGHER than expected when the release begins and HIGHER than expected after the filter is bypassed. C. The initial radiation level on RM 3801 is HIGHER than expected when the release begins and LOWER than expected after the Otter is bypassed. D. The initial radiation level on RM-3801 is LOWER than expected when the release begins and HIGHER than expected after the Olter is bypassed. Answer: B Justification:
- a. Although Cow blockage occurs, the release rate (60 gpm versus 15 gpm) should result in higher than nonnal radiation readings.
- b. CORRECT. The release rate is four (4) times that listed on the release permit.
- c. Once the tiller is bypassed, you would expect to see higher radiation levels.
d Even with an initially high Glter differential pressure, you would expect a higher than normal radiation reading due to the high flow rate. Question Topic: Radioactrve hquid morutor release (RO only) Q RO SRO K!A Rating 2.7/2 8 CFR#. RO 55 41(b)(13) System: 059 K/A s. AK2 01 ELos. BRD-0404-1&2 Reference AOP 2-25, OP 1 19-2 Page 96 of 100 4/13/97 l
4 RO EXAM REVIEW Group 2 EPE Quesbon. An operator has been sent to the lower level PAB to start the auxiliary charging pump (P-7) during a control room evacuation. The pump was aligned as follows:
- The speed control lever is set on the lowest speed;
- The pump is running with no abnormal noises with the RCS at normal operating pressure and temperature.
The PSS at the ASP notes that PZR level has not increased for 15 (fifteen) minutes. What is the cause of this problem? A. The attemate cooler for P-7 was not aligned and the hydraulic oil is overheating. B. The setpoint on CH-P-156 needs to be adjusted to 2335 psig. C. The speed control needs to be adjusted to the high speed setting. D. The RCS must be depressurized using the atmospheric steam durap before a level increase will be seen. Answer: B
- Justfcabon.
- a. If P-7 attemate cooler was not aligned, the pump would fail when the hydraulic fluid overheated
- b. CORRECT. This setpoint is too low for the current RCS pressure.
- c. Although this is required by procedure, the minimum setting wil! still pump 10 gpm into the RCS.
- d. Depressurization will help inject fluid, but is not required in this situation.
Queshon Topic: CVCS UD & CHG 2 RO y SRO K/A Rahng 3 413.3 CFR#-. RO $5 41(b) SPO 55 43(b) i System: 022 K/A S. AA1.01 ELO*. CVCS-0102-8 & 9
Reference:
AOP 2 90-1 (Attachment D) Page 97 of 100 4!13/97 j
RO EXAM REVICW Group 3 EPE . Ques 6on: The plant is at hot zero power when pressurizer level control channel LIC-10lX fails. What _ indications would the operator see if the channel failed fow? 1 A Maximum charging, minimum letdown, all heaters OFF, pressurizer pressure decreasing, spray valves closing. B. Maximum charging, minimum letdown, backup heaters OFF, pressurizer pressure increasing, spray valves opening. l C.' Maximum charging, minimum letdown, all heaters OFF, pressurizer pressure increasing, spray i valves opening. D. Maximum charging, minimum letdown, backup heaters OFF, pressurizer pressure decreasing, spray valves closing. Answer: C Justricabon:
- a. Pressurizer pressure will increase and the spray valves will open.
- b. All heaters are affected, not just the backups.
- c. CORRECT. Pressurizer pressure will increase because the steam bubble is being compressed, then the spray valves will open.
- d. All heaters are affected, as well as system pressure.
Queston Topic: EOP actons for PzR level mattuncton Q RO [ SRO K/A Rabng 3.7'4.1 CFRs. . RO 55 41 (b)(5) Systerw 028 K/A # AK3.05 = FLO#: P 6C-01018
Reference:
Simulator response Page 98 of 100 4/13/97
RO EXAM REVIEW Group 3J25 ouesbon. i
- The plant is at 90% power when the following symptoms are noted:
-- Main condenser absolute pressure is increasing; - PCC and SCC temperatures are decreasing; - Feed wate.r heater levels are decreasing; . - Containment temperatures are increasing; - Main generator temperatures are increasing.
What is causing this conditions? l A.- A loss of service water has occurred. 1 B.. A loss of containment control air has occurred. C, A loss of condenser vacuum has occurred, D. A loss of control air has occurred. Answer: D Jushficabon:
- a. Loss of service water will cause PCC and SCC temps to rise.
- b. Loss of containment control air would not cause decreasing condenser vacuum ar.d feed heater
. levels. -
- c. Loss of condenser vacuum would not cause decreasing feed heater levels.
- d. CORRECT, A loss of control air causes maximum service water now through the heat exchangers, fails open the feed heater level control valves, causes loss of cooling to containment recirculation fans and main generator SCC supplied components.
Queshon Topac: Tnppvig RX on loss of instrument er V. RO [ SRO K/A Rahng 3 6/4.2 CFRW. RO 55 41(bX5)
, System: 065 K/A # AA2 06 ' ELO#- CA-010'1-11 i
Reference:
AOP 2-28 Page 99 of 100 4/13/97
RO EXAM REVIEW Group 3 EPE ) ovestr.t During a large break LOCA with RAS, the following conditions exist:
- HIS-M 50 & 51 are flashing green in the SlAS lightbox;
- LSI M-40 & 41 are flashing green in the RAS lightbox; i
- PCC-M 219 is solid green in the CIS lightbox; l - PW-A-78 is solid grm in the SIAS/CIS lightbox; I - RWST level is less than 100,000 gallons;
- Containment pressure is 26 psia and decreasing.
l The STA states that an ORANGE path exists for containment and recommends entry into FR-Z.2, j " Containment Flooding " Based on the information available, which of the following would be the likely source of any extra water that has been dumped into the containment during this accident? 3 A. The PCC system has ruptured and dumped its contents into the containment. B. The RWST outlet isolation RAS bypass switch was left in " BYPASS" C. The containment sump level indication is high due to harsh containment environment. D. The primary water header has ruptured inside the containment. Answer: 8 Justficate r
- a. PCC-M-219 is closed therefore this is an unlikely source of the water.
- b. CORRECT. With this switch left in the " BYPASS" position, the RWST will continue to empty at this containment pressure.
- c. Containment sump level is not affected by harsh containment cond;tions.
- d. The primary water header isolates on an SIAS signal.
Ouesbon Topic: Knowledge of EOP bases for a SGTR recovery M RO g SRO K/A Rahng 27/36 CFR8. RO 55.41(bX10) SRO 55 43 (bX5) ; l System- Genene K/A # 2 4.16 ELO#: EAS-0903-1&s j
Reference:
FR Z.2 BKGD Document I Page 100 of 100 4/13/97
MAINE YANKEE SENIOR REACTOR OPERATOR EXAM FOR REVIEW COPY l ALL ITEMS ON THIS EXAM ARE NEW zh\ D g 01
~' -
SkO LXAM REVIEW Generic oueetion. What is the relationship between the Maine Yankee Technical Specifications and the Facility Operating License issued by the NRC7 A. The Technical Specifications ensure pro;ective action guidelines in the Emergency Plan are not exceeded. B. - The Technical Specifications are part of the Operating License issued to the plant. C. The Technical Speci6 cations are used to serify Appendix D accident compliance in the FSAR. D.- The Tech..: cal Specifications are used to verify equipment availability for the Core Operating -. Limits Report. Answer: B Justird ation:
- a. E-Plan PAG's are based on actual / projected release data.
- b. CORRECT. Technical Speci6 cations reDect conditions of the license.-
- c. Technical SpeciGeations ensure that 10 CFR100 limits are not exceeded.
- d. - Technical Speci6 cations verify eqd.oment availability for all operating conditions, not just those in the COLR.
Question Topic Knowledge of hconse con $tions and hmitabons y RO p, SRO K/A Rating 2.7/3.9 CFRs. RO 55.* 1(b)(10) SRO 55 43(b)(1) System: Genenc K/A 8. 2.1.10 ELO*; SNO-0303-3
Reference:
10 CFR 50.36 & MY Operatng Ucense Page 1 of 100 4/13!97
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SRO EXAM REVIEW Generie Queshon: A_ waste gas release is in progress per OP l-213, " Waste Gas Release." The primary vent stack APD (RM 3902X) hasjust gone into alann on " LOW FLOW." The primary side AO reports that P-169 (PVS air particulate pump)is not running and that P-140 (PVS air particulate pump)is tagged out. What action is required and why? A. Continue the release, but lower the trip setpoint on the waste gas release valve (WD P-21 l) ta ; within 25 CPM above background because oflow flow, i B. Immediately terminate the release because a low primary vent stack How(<20,000 CFM) wil: trip shut the waste gas release valve (WD P 211). - C. Continue the release, but lower the waste gas release rate (CFM) to one half ,,,,: value specified 1 in the r: lease permit because oflow dilution flow. D. Immediately tenninate the release because oflack of flow through the iialogen and particulate sampling device on the primary vent stack. Answer; D Justfw:ston:
- a. With PVS APD inoperable, the release must be terminated immediately,
- b. . A low vent stack flow will shut WD-P-211, but not in this situation.
- c. Lowering the release flowrate is not viable to meet ODCM limits.
- d. CORRECT. .The monitor is considered inoperable anytime Dow does not go through this portion of the monitor.
_ - - - - - . . -,- . - - . ~ . . . . - -
- Oueshon Topie Knowdedge of process for planned gas release
!D RO G SRO K/A Rahng 2.3/3.2 _ CFR#, SRO 55.43 (b)(4) System: Generic K/A #. 2.3.08 ELO#. SNO-03041
Reference:
OP 1213 Page 2 of 100 4/13/97
SRO EXAM REVIEW Generic Question: . l With power at 1% Engineering informs you that some EFW suction pipe hangers in the EFW pump room do not meet seismic requirements (some bolts are not the proper specification but can be repaired in about 4 hours). At this point you should: 1 A. Declare the EFW system inoperable and immediately con:mence a reactor shutdown per Technical Specification 3.0.A. l B Keep power below 2% and enter the remedial actions allowed uy Technical Specification 3.8. C. Declare the EFW system operable as long as the operability of the EFW flow control and isolation valves is assured. D. Maintain the hot standby condition between 10-2% and 1% for the next sixteen (16) hours and consult with Operations management. Answer- 3 Just:fication-
- a. Although this would be conservative, Tech Spec 3.0.A allows you to perform any remedial oction before a reactor shutdm"n in one hour.
- b. CORRECT. If the seismic flow path is not operable, the reactor should not be in the power operating condition
- c. Technical Specifications require all subsystems to also be operable.
d The plant would be allowed in thi3 condition for at least 6 hours but would not meet the requirements of Tech Spec 3,8 Question Topic AbMy to apply TS to a system. EFW sersmic concerns
, RO y SRO K/A Rating 2 9/4 0 CFRs. SRO 55 43 (b)(2)
System Genenc K/A #. 2.1.12 ELO*. SNO-030M & 10
Reference:
TS 3 8 (TS Interpretation 3 8 7/18/96) Page 3 of 100 4/13/97
i i SRO EXAM REVIEW i Genede ouesbon: The plant hasjust completed a chemistry hold at 20% power and is escalating power at 10Whour to 55%. As plant temperature is changed, all four (4) power range channels receive an N!/ delta T power alarm. What action is required by the operators? A. The power increase can continue until 55% power at which time an N1 calibration and adjustment must be performed. B. The power increase should be terminated and the operator can manually adjust the Ni potentiometer to clear the alarm. C. The power increase can continue as long as the N1/ delta T power deviation does not go offscale on the RPSCIP panel. D. The power increase should be terminated and an N1 calibration and adjustment should be performed to restore alarm operability. Answer. D Jushfication.
- a. Tech Spec 4.1-1 requires that a calibration and adjustment be performed when in power operating conditien if alann is received.
- b. Manually adjusting the Ni potentiometer is not allowed nor desirable as a less power limiting setpoint may be inserted.
- c. Alarm is set at plus or minus 2.5%. Once alarm is in, action should be taken to correct the deviation,
- d. CORRECT. This complies with the requirements of Tech Spec and RE guidance Question Tope Ab*ty to recognee TS entry entena for Nt/deha T power V RO y SRO K/A Rahng 34/40 CFR8. RO 55 41(b)(5) SRO 55 43(b)(2)
System: Genene K/A # 2133 ELOs. SNO.030313
Reference:
TS 4.1 (Table 41 1). RE 0.10 Page 4 of 100 4/13/97
SRO EXAM REVIEW GRotds oue non
- A reactor startup is about to commence. Which condition ensures 115 KV line operability for Section 697 A. P-2A is operating and 115 KV line voltage is 113 KV.
B. P-2A is operating and P 2B is in pull-to lock. C. P 2A and P-2B are both in automatic. D. Section 69 does not meet 115 KV line operabili y requirements. Answer; B Justfication:
- a. Line voltage is too low for operability requirements.
- b. CORRECT A main feed pump cannot be in automatic.
- c. P-2B cannot be aligned for automatic operation.
- d. Section 69 has limitations for voltage and feed pump alignment.
hueston Topic: 115 Kv kne operabihty i C RO q SRO KIA Rating 3 5/3.8 CFRs. SRO $5 43(b)(2) } f System: Genenc K/A #. 2 4 48 j ELOs, SNO-0303-6
Reference:
TS 3.12 B i .____ _ _ _ Page 5 of 100 4/13/97 l 9
SRO EXAM REVIEW l Generic Quesbon: A steam generator tube rupture is in progress. The steam generator subcooled margin monitor reads 38 F. What must be done to equalize steam generator and RCS pressures? A. Open the turbine bypass valves to reduce steam generator pressure. B. Open the pressurizer spray valves to reduce RCS pressure. C. Isolate the steam generators to increase steam generator pressure. D. Energize the pressurizer heaters to increase RCS pressure. Answer B Justfication
- a. This action will increase the SMM reading.
- b. CORRECT. This action willl reduce the reading and equalize pressures.
t
- c. This action will not change the SMM reading.
d This action will increase the SMM reading Question Topic: Relationship between subcooled margin and S/G pressure
~@ RO j SRO K/A Rating 34/38 CFRs. RO 55 41 (b)(10) SRO 55 43 (b)(5)
System: Genenc K/A 8 2.1 32 ELO# RCS-09021 Reference- E-3, SGTR Page 6 of 100 4/13/97
I L I SRO EXAM REVIEW - Generic { f During performance of white tagging for LD-A 9 (letdown flow control valve) repairs, independent verification is required per procedure 0-141, " White Tagging Procedure." It is estimated that a significant radiation exposure (>10 mrem) will be received during second verification. What j guidance would you provide the operators for independent verification in a radiation area? ! A. Independent verification is not required as long as the second checker reviews the valves j tagged with first. i I B. Independent verification is not required whenever a significant radiation exposure may be received.
- l .
j- C. Independent verification is required and is accomplished by viewing tags from a remote t
- location.
l l- D. Independent verification is required and is accomplished by observing system process parameters.- Answer; D Justification. j- a. Independent verification is always required. Reviewing tags with the first person is not i - considered a good practice.
- I j b. Even though in a radiation area, you must always verify the position of valves.
t l c. Viewing of tags does not verify valve position. 1 l d. CORRECT. By observing system process parameters, the second checker can verify correct j valve alignment. 2 i ouesbon Topec: Know4 edge of tagging procedures for double verrfication DRO ~/ SRo ' KIA Raung 3 6/3 8 CFRs. SRO 55 43 (b)(3) I j i System: Generic KIA W 2.2.13 , 4
- ELos. M-0302-9
{ l } ! Reference; . QA O-14 2 ! Page 7 of 100 4/13/97
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SRO EXAM REVIEW Generic l oue.non-Which one of the following is an adverse consequence of containment control air pressure being less than 70 psig when in E-0," Reactor Trip and Safety injection"? A. The pressurizer spray valves will fail open and result in loss of pressurizer pressure control. B. The containment air recirculation fan:, will not maintain containment pressure <70 psia on LOCA,- C. The primary component cooling supply to the reactor coolant pumps will be lost, l D. The seal water supply and return How to the reactor coolant pumps will be lost. Answer: C. Justfication:
- a. The spray valves fail closed on a loss of air.
- b. The fans are not used for containment cooling once pressure rises above 35 psia.
. c. CORRECT. PCC-A-252 wil; fail closed and result in a loss of cooling water Dow.
- d. The seal water pressure and now control vah es are unaffected by this loss. *
- c. I
; Question Topic: Knowledge of system setpoints for EOP entry lM RO Q SRO K/A Rating 3.bl4.1 CFRs. RO 55.41(b)(10) SRO 55 43(b)(5) l System: Genere K/A # 2.4.02 4
ELO#: EAS-01017 l
Reference:
E-0, Step 34 4 J ( Page 8 of 100 4/13/97
SRO EXAM REVIEW Generic Queston: - During an accident, the followieJ EOP's are entered (in order of entry): - Entered E-0,"RX Trip' Safety injection" & EXITED at Step 10 due to loss of heat sink; - Entered FR H.1, " lass of Heat Sink", and refcrred to E-0 at Step 16 to complete immediate actions of E-0; - Continues in FR-H.1 and EXITED at Step 25 RNO for PORV's failing to close with heat sink re-established; - Entered E-1, " Loss of Primary or Secondary Coolant", and EXITED at Step 11 due to HPSI and spray pumps unable to supply adequate flow to RCS; - Entered ECA-1.1, " Loss of Cold Leg Recirculation", and EXITED at Step 32 to " Return to Procedure and Step in Affect." At this point the operator will: A. RETURN to E-O to complete any missed actions out to Step 25 when CSF Status trees are monitored. B. RETURN to FR-H.1 to complete any missed actions associated with restoration of the heat sink. C. RETURN to E-1 to complete actions required for loss of primary coolant. D. RETURN to ECA-1.1 Step i to ensure continuous flow of coolant is available to the core. Answer: C Justficaton;
- a. Do not re-enter E-0, as most steps have already been accomplished in ECA-1,1.
- b. Do not re-enter FR-H.1 because a heat sink has been established via PORV's.
- c. CORRECT, E-1 is the correct procedure and step in effect. 1
- d. Do not remain in ECA-1.1, as conditions for cold leg recirculation have been restored.
Queston Topic: Knowledge of EOP implementabon Nerarchy j2 RO p SRO KIA Ratng 3 0/4 0 CFR#. RO 55.41(b)(10) SRO 55 43(b)(5) { System: Genenc K/A 8. 2.4.16 [ELO#. EAS-01019
Reference:
OP 1200-16 i Page 9 of 100 4I13/97
SRO EXAM REVIEW Generic Quesbon-Which of the following is the guidance for intentional operation under a remedial action statement for elective maintenance? A. When failure to repair a component results in enforcement a ..n by the NRC. 1 B. When maintenance procedures for component repair can be completed in less than eight (8) hours. C. When the cau3e of the inoperability of the component is known and documented in approved procedures. D. When performing component elective maintenance on-line clearly provides a net safety benefit. Answer. D 1 Justification: , 1
- a. If the valve is still capable of performing its intended function, even with a broken handwheel, it '
will not cause eaforcement action by the NRC.
- b. Time considerations are not taken into account. Remaining in a remedial action is considered non-prudent operations.
c Only when all alternative methods are reviewed, does OP l-200-10 allow work to be performed.
- d. CORRECT. This results in restoration of one train of equipment.
Question Topic: Knowledge of conduct of operations invoMng remeeal actions
. _. R O y SRO K/A Rating 37/38 CFRs. SRO 55 43 (b)(2)
System: Genenc K/A #. 2.1.01 ELO#. M-0301 1
Reference:
oP 1-200-10 Entry into Remedial Actions, Page 8 Page 10 of 100 4/13/97
SRO EXAM REVIEW Generic Question:
- A note in ES-0.2, " Natural Circulation Cooldown" states that "LTOP criteria cannot be met during natural circulation conditions without the HPSI flow restrictor in sersice." With a natural circulation cooldown occurring that is greater than 25 F/hr., why is the dedicated operator stationed?
A. Natural circulation cooldown could create an adverse thermal stress on the reactor vessel wall.
.3. Natural circulation cooldown is difficult to control when cooling down greater than 25 F/hr.
C. Natural circulation cooldown is the least desirable method, therefore, additional plant monitoring is required. D. Natural circulation cooldown will create voids that are not observable without PITS. Answer: A Justification.
- a. CORRECT. Cooldown stresses at the 1/4T position are most limiting.
- b. While it is true that it is difficult to control, this has no effect on stationing of the dedicated operator.
- c. T his is not a true statement. Cooldown on natural circulation is a well documented and controlled evolution.
- d. This procedure assumes that voids will be created. Analysis indicates that void growth will not interfere with NC flow.
Question Topic: Knowledge of irnpiicabons of EoP notes. caution
- M RO y SRO K/A Rabng
- 3/4.0 CFRs. RO 55 41(b)(10) SRO 55 43 (b)(5)
. System: Genenc K/A 8. 2.4.20 l ELO*. EAS-0101-7
Reference:
ES-0 2 BKGD Docurrent (Step 8, Note 1) Page 11 of 100 4/13/97
i ! SRO 11XAM KliVilIW l Generic j ouemon While monitoring Critical Safety Functions ouring a steam generator overfill / steam line break i event, the operators have noted a greater than 100 F/hr. cooldown rate. Pressurizer pressure and
- wide range Teold are to the len of Limit A Curve, necessitating entry into a Functional Restoration l Procedure. Which procedure would be entered and why?
? i A. Enter FR P.! due to concerns for thermal shock caused by rapid cooldown and to prevent Daw , ! gromh in the reactor vessel during repressurization. l l B. Enter FR P.I due to concerns for thermal shock caused by rapid cooldown and to arrest ! j compressive stresses on the inner wall during repressurization. i ! t i C. Enter FR 1.1 due to concerns for brittle failure caused by rapid cooldown and to prevent Oaw l j growth in the reactor vessel during repressurization. ! D. Enter FR.I.! 'ur to voncerns for crystallin structure shiR from face center to body center cubic which ccv .ead to ductile failure. Answer. A I JuaitiflCatton~
- a. CORRECT. This is the basic PTS event for which FR P.1 was written.
4
- b. Cooldown stresses are tensile on the inner wall.
- c. FR 1.1 is not entered for a PTS situation.
- d. Although C/D will shin the crystalline structure, ductile failure is not a concern during a PTS event. '
=
7 Question Topic: Knov4 edge of procedures and CSF entry conditiorr. V RO y SRO KiA Rating 3.7/4 3 CFR8 RO $$ 41(b)(10) SRO $$ 43(b)($) , System: Genenc K/A s. 2.4 21 i ELoe RCS 010116.28.29.30; EAS41013
Reference:
FR-P.1 BKGO Document L _ _ _ . _ _ - _ - _ I r PaDe 12 of 100 4/13/97
SRO EXAM REVIEW , Generic oue. bon- ~ The reactor is operating at 100% power when a main feed regulating valve (FW F 207) fails open. What is the most likely sequence of events if P 2C is in operation and no operator action is taken? A. f eed water header pressure decreases, standby MFW pump auto starts, P 2C speed increases, feed water header pressure increases, P 2C suction pressure increases. B. Feed water header pressure decreases, P 2C speed decreases, standby MFW pump auto starts, feed water header pressure increases, P 2C suction pressure increases. C. Feed water header pressure decreases, P 2C speed decreases, P 2C suction pressure decreases, standby condensate pump auto starts, P 2C speed increases D, Feed water header pressure decreases, P 2C speed increases, standby MFW pump auto starts, P-2C suction pressure decreases, standby condensate pump auto starts. Answen D Justification,
- a. Decreasing FW llDR pressure & P 2 A/B auto start do not override initial P-2C speed increase,
- b. When FW header pressure decreases, then P 2C speed will increase.
- c. When P-2C speed decreases the suction pressure should increase and the condensate pump will not auto start.
- d. CORRECT. P 2C speed will immediately increase when header pressure decreases.
Question Topic: Main feed regulabng valve fads open;indecahons seen M RO p SRO K/A Rabng 4.0,4.3 CFR8. RO 55 41(bX10) SRO 44 43 (bX5) , System. Genenc K/A 8. 2 4 04 l ELO#f MFW-09021, MFW4902-2,ISR-03018 i
Reference:
Simulator response l
~-
Page 13 of 100 4/13/97
l SRO EXAM REVIEW Generic Quesbon: Following a refueling outage, the plant is retuming to power and is at a 5% hold for S/O chemistry. Pressurizer pressure starts to rapidly decrease and then the primary RO repons that the "A" train SlAS pumps have automatically started. Why is the reactor tripped and E-0, " Reactor Trip or Safety injection" entered? A. To evaluate plant conditions. B. To fire both trains of SIAS. C. To prevent a loss of offsite power. D. Because an ATWS is in progress. Answer: B Jusbhcabon.
- a. E O is not only entered, but the operator must fire SIAS.
- b. CORRECT. OP memo requires conservative decision making for this event even ifit appears to be inadvertant.
- c. There is no indication that a loss of offsite power will occur.
- d. "A" train SIAS pumps starting is not indicative of an ATWS.
_ _ _ _ _ _ __ ._ __~ _. Quesbon Topic: Knowledge of ECP entry condtsons V RO Q SRO K/A Rating 4.3/46 CFR# RO 55 41 (b)(10) SRO $$ 43 (b)(5) System: Genenc KIA s. 2 4 01 ELO* EAS 01018
Reference:
E.O entry entena; OP Memo 9.E.12 Page 14 of 100 4/13'97
j l SRO I!XAM Rl!ViliW J Ganatie ou .m: - Leakage from the stem packing on LD-T 37 (letdown temperature trip valve) has become unacceptable and management has chosen to repair the valve on line (alternate letdown h in - service). As the SOS, what concerns should be addressed prior to valve disassembly? A, Establishing double valve boundaries, including freeze seals where applicable, to prevent inadvertant gas or liquid releases. B. Securing ventilation flow in the PAB lower level to minimize unmonitored releases during ,
. valve disassembly. :
C. Purging the hydrogenated vent header and VCT with nitrogen to minimize gas releases in the ! event of boundary failure. j i D. Allowing valve draining without filtering because the process fluid in the piping is downstream ; of the purification demineralizers and filters. i Answer: A l Just ficahorr a CORRECT. This is a conservative operator action for this condition. t
- b. Securing ventilation will allow radioactive gases to concentrate and could exceed derived air ;
concentrations (DAC) limits. i
- c. Although it is desirable to purge these boundary systems, this could result in introduction of nitrogen to the RCS when boron adjustment is required.
- d. LD T 37 is upstream of the purification demineralizers, !
Quesbon Topic: Valve repaw with potenbal for rad release [ RO y SRO K/A Rabng 2 9/3 3 CFRs. SRO 5s 43(b)(4) System: Generic K/A 8. 2 3.10 ELO8 M43012 I Reference. OP 120010 (Sechon 4.25,10) __.-.~.__ _ . _ _ _ . - . _ _ _ . . . _ _ _ _ _ _ _ . . . . _ - r Page is of 100 4/1317
SRO EXAM REVIEW Generic Que.non. The reactor hasjust tripped and the CRO is completing his immediate actions. Which example l describes the proper communication sequence? A. (3 ender)
- Primary RO, what is the status of the control rods?" (Receiver) "The rods are inserted."(Sender) "Are the immediate actions of E O done now?"
B. (Sender)" Primary RO, what is the status of E-O immediate actions?" (Receiver) " Shift Supervisor, the immediate actions are complete." (Sender) " Understand that, primary RO, immediate actions are complete." C. (Sender)" Primary RO, what's happening with E.O? Primary RO, I see that the reactor trip breakers are open." (Receiver) " Shill Supervisor, the reactor trip breakers opened automatically." D. (Sender)" Primary RO, have you completed your immediate actions yet?" (Receiver) " Shift Supervisor, the bravo charging pump has auto started." (Sender) " Primary RO, understand that bravo charging pump has auto started." Answer: B Justification.
- a. SRO did not specify who was going to verify the immediate actions of E O and no acknowledgement of receipt of repeat back.
- b. CORRECT, Order, repeat back, and acknowledgment are the correct communications.
- c. SRO did not wait for repeat back of first message and did not acknowledge that the RTB's were open.
d Primary RO does not acknowledge completion ofimmediate actions and does not acknowledge receipt of repeat back.
' Question Topic: Abikty to make accurate. clear concise reports !
[ RO y SRO K/A Ratog 3 5/3 6 CFR8 SRO s5 43 (b)(5) I j Sptem: Genenc K/A 8: 2 1.17
'ELO8. SEO 0302 3&4 - Reference- OP 13004 Page 16 of 100 4/13/97 U
, - .. - _ _ . - _ _ - -- - . -.._ ____ _-__ -- - ~.- - . - _- _-. - , y f SRO EX Ahi REVIEW Generic ouestion-
, Thermal mussel control operations are in progress on the south service water header. While ,
perfonning this routine maintenance, the Operator must verify that the outboard heat exchanger (E. !
, 4A) delta P is not more than 2 psid higher than the inboard heat exchanger delta P (E 5A). What i l
adverse consequence would result if this condition were allowed to occur? ' A. The "A" train of ECCS would be inoperable due to inadequate How through the outboard heat exchanger.
- 13. The "B" train of ECCS would be inoperable due to inadequate Dow through the inboard heat exchanger.
C The "A" train of ECCS would be operable, but necessitate starting an additional service water pump l D. The "B" train of ECCS would be operable. but necessitate starting an additional service water pump Answer- A 1 Justsfication-
- a. CORRECT. If the outboard heat exchanger has a high delta P, then its Cow will go inboard and render this train inoperable.
4
- b. The "B" train is already inoperable with the south header OOS.
- c. "A" train is not operable because the Dow may be passing through the inoperable train.
- d. The "B" train is not operable in this con 0guration
. Question Topic Serece water header loss effects on TS lV RO y SRO K/A Rating 3.3/3 7 CFRs RO 55 41(b)(7) SRO 55 43(b)(5) f System Generic K/A 8 2424
'ELOS SW-01012. SW-0902 3 l Reference; op 1 15-3, STM Chapter 48; AOP 2-31 l
t_____... . _ _ . - . _ _ _ . _ _ - - _ . - Page 17 of 100 4/13'97 i
SRO EXAM REVIEW l Group 1 Plant oueste The plant has experienced a small break LOCA during a station blackout and P-258, the turbine driven AFW pump,is unable to provide feed flow. Core temperatures are rising along with pressurizer pressure with an average CET temperature of 750 F and pressurizer pressure of 1800 psia. The core region subcooled margin monitors will: A. Continuously flash a 129 F indication on MCB Section "B."
- 8. Continuously flash a 4129 F indication on MCB Section "B."
C. Continuously flash a 75 F indication on MCB Section "B." D. Continuously flash a 50 F indication on MCB Section "B." Answer D httfication-
- a. The SMM bottoms out at 50 F, therefore,129 F will not be shown,
- b. There is a 129 F difference in Tsats, however, this is an invalid calculation.
- c. This is an invalid calculation as tir monitor bottoms out at 50 F.
- d. CORRECT. This is a loss of subcooling that bottoms out at 50 F.
Quesbon Topic: Saturation and subcoohng of water 7 RO y SRO K/A Ratng 37/40 CFR8. RO 55 41(b) SRO $5 43 (b) i System. 017 K/A
- K502 '
- ELO#. RCS-0101 14,22 and RCS+902-2 3
Reference:
STM Chaplef 2 *
. _ _ _ . _ _ . . . _ _ _ , . . _ _ _ _ _ _ . . . _ _ _ _ . _ _ _ _ _ . . _ . _ . _.J Page 18 of 100 4/13'97
i ~ SRO EXAM REVIEW ; Group 1 Plant ! oue.t.on: j The computer room air conditioners are unable to maintain computer room temperature and a i manual shutdown of the plant computer is required. In an effort to verify Technical Specification 3.9, how can the operator read CET temperatures? l A. Access the Remote Instrumentation Room, use a calibrated thermometer, disconnect leads at ; measuring junction, read CET temperatures. . It Access the Reactor MCC Room, use a calibrated thermometer, disconnect leads at measuring . junction, read CET temperatures. C. Access the Computer Room, use a calibrated thermometer, disconnect leads at reference junction, read CET temperatures. ; D. Access Reactor MCC Room, use a calibrated thermometer, disconnect leads at reference : junction, read CET temperatures. Answer: C Justifcaton:
- a. Must access the Computer Room and measure at referencejunction.
h Must access the Computer Room and measure at referencejunctioa. j
- c. CORRECT. This sequence allows you to read CET temperatures.
- d. Must access Computer Room.
Ouestion Topic: Actual tn-core temps /how to read them ! V RO y, SRO - K/A Rahng 3 8/4.1 CFR8. RO 55 41 (b)(7) SRO $$ 43 (b)(6) l
' System: 017 KIA s. A4 01 ~ELOW RCS-010213; INCA-0101 10
Reference:
STM Chapter 2 4 1 Page 19 of 100 4!1347 1
SRO EXAM REVIEW Group 1 Plant Queston While at 100% power with P.2C in service, the P 2C recirculation valve fails wide open. How does the condensate system respond? A. The standby condensate pump auto starts on low feed pump discharge pressure. l B. The standby condensate pump recirculation valve closes. , 1 C. The condensate gland exhaust condenser bypass valve opens. D. The standby condensate pump auto starts on low feed pump suction pressure. ; l An.wer: D . Josecaton:
- a. Condensate pump does not auto start on low feed pump discharge pressure. !
l l b. Condensate recirculation valve is not open at 100% power. l l c. The bypass valve maintains delta P across the gland exhaust condenser and is blocked in position. I
- d. CORRECT. Th: pump starts on low feed pump suction ~ pressure. >
r- i
'0uesbon 4 Topic: Loss of condensate pump ,
f 9 Ro y SRO K/A Ratng 2 6/2 8 CFR#. RO 55.41(b)(7) SRO 55.43 (bX5) l { System: Ob6 K/A 8: A2.04 1 ELos. CD-010111 !
Reference:
STM Chapter 26
}
l 4 l i i-i l Page 20 of 100 4t13/97 i -
. . , . - _ - , - , _ , _ . . . _ _ . _ . - _ . - - ~ _ . _ , - . _ , _ , , _ , _ _ _ . - . - ..,.m_. - , . . . _ _ _ _ _ , . _ . -. .---,-_ ~,_...._,, _
SRO EXAM REVIEW Group i Plant ouesbon . I The plant has tripped on a low steam gene *ator pressure signal followed by EFCV elosure due to a catastrophic failure of the main steam heac er in the turbine hall. In order to open the #2 S/G main i feed regulating valve, the operator must: A. Bypass both tnins of feed water isolation AND '.eset the turbine trip signal. B. Bypass one train of feed water isolation OR reset the turbine trip signal. C. Bypass both trains of feed water isolation AND press the " Steam Dump Override" push button. D. Bypass one train of feed water isolation AND reset the turbine trip signal. Answer: A Just.ficahon
- a. CORRECT. If the turbine trip signal is not reset, the valve will not open.
- b. Both trains must be bypassed to remose closure signal and the turbine must be reset.
- e. Pressing steam dump override restores control to B/P valve only.
- d. Both trains must be bypass-d to remove closure signal.
Quesbon Topic: Feedwater solabon and ter,et y RO Q SRO K/A Rabng 3 2/3 3 CFR8 RO 55 41 (b)(7) SRO s$ 43(b)(6) System 0$9 K/A # A3 06 ELOW. MFW 0103 7 Reference. STM Chapter 27 Page 21 of 100 4/13S7
SRO E.XAM REVIEW Group 1 Mant ousamon The S/G wide range channel is being used to control S/G level during a plant cooldowrt With containment temperature at 90 F, S/G pressure at 300 psig, and indicated wide range level at 300", - what is the actual level in the S/G7 (Use the attached figure) A. 260" B. 312" C. 350" D. 400" Answen C Just6cahon'
- a. This answer is reached from entering right versus left side of graph.
- b. This answer is reached when reading directly across graph without accounting for S/G pressure,
- c. CORRECT. This is the correct compensated level.
- d. This answer is reached when failing to compensate for S/G pressure and reading up the indicated pressure lines.
F Oueston Topic: Control and monttor S/G levels Q RO Q SRO K/A Rahng 3 9/4.2 CFRW. RO $5 41(b)(10) SRO $$ 43 (b)(5) System 061 KIA f. A1.01
- ELOW. PPM 0107 6 & 8
Reference:
TDB Fgure 14.2 Page 22 of 100 4/13'97
. - . -. - - . = - -
conc % e 9k032 one 6-15-95ru2unE 1.42 nm4 d W 2 one 4-++f'Prope,.d i,y . . STEAM GENERATOR LEVEL CORRECTION FOEWIDE RANGE CHANNELS LI- 1214,1224 & 1234 4 , 0 4 N Engis. 4 ,
*O N indsened Level 331 hdme '
ContanmartTenpersawe 13oF 12 x 6asem Generosor Proense % 16 X Assume eut the reference leg temperonse equale cortainmort 20 x temperehas. From paph at rigN, 24 X, Indoned W Conocean 4 W 28 N
~
Conoceed Indossed Level 331 6 = 325inchee 32 . s J .36 l j' Einer the poph along kne of conwed 4 i , L,vei 400 60 60 100 120 140 160 180 200 220 240 260 280 300 Containment Temperature 450 W 425 /
/l s
/'#l l l ,
/j
,., 375 /
'V / }' M ' #~
),o
/ s '[ Al l 350 /
/
- /
sl'"-
/,,,,'"
-< l 1325
.a
' I 325 1 3" 7 /pl- -
-- i t i sa
]3 275 y - '- l l 275 250 7
'" i 1, el o 22 ' ~
225 0 l 200 y 7l ~~ l 2m p 22 8, 175 175 150 d 150 125 , 125 li
' 100 100 75
~
75 50 50 l 25 25 l l i i I ' O 0 0,00 400 500 600 700 800 900 1000 O 100 200 Steam Generator Pressure (psig)
SRO EXAM REVIEW Group 1 Plant ou. won The plant is operating at 80% power when an RPS calibration is performed based on the " steam flow" calorimetric.- As power is returned to 100%, steam flow power indication is less than delta T power indication. Why does this occur? i A. The hotter watst when greater than 80% power has increased neutron leakage and the RPS N1
- detectors now see more neutrons.
B. The steam flow calorimetric introduces an overly conservative value for power level when at 80%. C, The auxiliary steam loads at 80% power were not accounted for in the steam flow calorimetric. D. The delta T power instrument was not recalibrated for the higher Teold value at 100% power. Answer. C Justificabon:
- a. This is a true statement, but not applicable for this condition.
- b. This value is less conservative.
- c. CORR,ECT. These loads are upstream of the. steam flow measurement.
i
- d. It is unlikely that this instrument would require recalibration.
Oueshon Topec: NIS cahtwabon by heat balance j ; 2 _RO Q CRO K/A Rabng 3 $/3.8 CFRs. RO $5 41 (bX5) & (14) SRo 55 43 (bX2)& (5) f
. System: 015 K/A #. A1.01 !
4 : j ELos. PPM-0103 2; MS.09021; PPM 0102-9 i
Reference:
Characterestics of Core PWR Indications (RE S/91) , u-...--,--- . - - - - - - , . _ . - . . . - ~ - - . _ ._. -------a j 1-Page 23 of 100 4/13!97 _ ..-.,~_..--__.; - . . . _ . . . . , . _ . . , _ _,__ _ . _.. . , , , _ . _ _ - _ _ _ _ _ . _ _ _ . , _ . - . . . , _ _ . . _ . . _ , . . . . . _ _
_ __ __-_m._..__._._ . . . . - - -- _ _ _ _ _ _ . . _ ._ _ _ . _ . . _ _ _ . I SRO IIXAM REVIEW Groun 1 Plant ou bon -
. The following conditions exist:
PAB ventilation exhaust fan (FN.2) has tripped;
. Containment gas monitor (RM.6102Y) is in alarm; Primary vent stack gas monitor (RM.3902Y)is in alarm;
. Containment ventilation supply fan (HV 9) has tripped;
. VP.A 1,2,3,4, & 5 have tripped closed.
Which scenario would be responsible for these conditions and alarms? A. A containment " refueling" purge was in progress l
)
B. A containment "on line" purge was in progress, l C. The waste gas surge tank has ruptured in the PAB upper level. D sThe loop seal between the waste gas surge tank and the primary vent stack.was lost. l Answeri B-Justificahon
- a. In
- refueling" manipulator crane or containment low range will also alann but will not cause a trip. '
i
- b. CORRECT. These are indications of an on line purge problem.
- c. This scenario would not affect the containment pas monitor, but FN.2 would trip.
- d. This scenario would not affect the containment gas monitor, but FN 2 would trip.
_ _ . . _ , . . _ _ . _ _ ~ - . . . _ _ . . _ . _ _ , _ _ . _ _. Queshon Topic: RMS alarm and actuatmo signals
. V RO y SRO K'A Rateg 3 6/3 8 CFR8 RO s5 41(bX11) SRO 55 43(bX4) ,
l System: 071. KIA # A3 02
. El.os. RMS-01017; RMS-0902 2 .
Reference:
STM Chapter 20 i
, _ _ _ . - . _ . . _ , . . _ ___ _ c
[ t ; I r Page 24 of 100 4/13!97 ws.r ri o r v ,v viv e. r w v -.-m~ww- --,<1r ,w 4 -w..--.wm-r.eer ++-rr .w, t,. w- r- e, w -t-,-, -win- ma--.wew--.w.--ww-- .. - - - ,, - wr --,r--, , , - - - r- w
SRO !!XAM REViliW Group 1 Plant cuestion-What are the possible adverse consequences to the containment spray valves (CS M l&2)if offsite power is in a degraded voltage condition? A. The MOVs may develop insumcient torque to start valve movement.
- 13. Insumcient voltage will not be available to the control power circuit to operate the 42 device in.
line contactors. C. The motors may operate at a slower than acceptable speed as outlined in the accident analysis. D.DC ,: trol power will close the breakers but the motors may be unable to open the valves Answer. A Justihcatxin
- a. CORRECT. The MOVs are not rehable with less than 90% of terminal voltage available at the motor. i
- b. This is not the most limiting aspect of valve operation.
- c. Frequency, hence speed,is not affected by motor voltage.
- d. MOVs are controlled by AC and not DC control power, l Question Topic: Power supply to spray MOVs (SRO only)
._: RO y SRO K/A Rating 2 7/2 9 CFR8 SRO 55 43(b)(5) l System 026 K/A 8 K202 ELO8 AC 010171 and 73
Reference:
Memo Mouttan, B to Smith, S , 7/11/96 (strolung MOVs) l l l Page 25 of 100 4/13/97 i J
SRO liX AM RiiviliW GTOUD 1 Plant Question * , Prior to operating the boron recovery system (EV 1) to process hydrogenated waste from the PDT, the degasiliers are run to remove hydrogen and other radioactive gases. Ilow is oxygen instrusion into the waste gas system presented when the degasifier system has cooled down and is in standby? A. The degasiner on line vents remain open to allow the waste gas surge tank to float on the degasiliers.
- 13. The degasiner vent cooler bypasses open to allow the waste gas surge tank to float on the
( degasiners. C, The degasifier vent cooler bypasses open to allow the in service waste gas decay drum to float on the degasiliers. 5 D The degasilier on line vents remain open to allow the in sersice waste pas decay drum to float on the degasiliers. Answer [3 Justification a The degasifier on line s ents open at 222 F to provide 5 sefm to the surge tank.
- b. CORRECT. This alignment is achieved when degasifier temperature is <222 F.
- c. The surge tank, not the decay tank. is aligned to the degasifier.
d See 'a' and 'c' abos c. Question Topic: x connections between bouid and waste gas v RO y SRO K/A Rating 2 5/2 6 CFRs. RO 55 41 (b)(13) SRO 55 43(b)(4) System 068 KlA t. K102 ELOs BRD-0401 14 Reference STM Chapter 36. AO-L-214 Page 26 of 100 4/13'97
\
)
SRO IIXAM Rl!Vil!W Group 1 Plant Quesbon The wide range logarithmic channels each haw three (3) fission chambers per detector. The source range nuclear instruments utilire all three (3) fissicn chambers while the wide range nuclear instruments use only one (1) fission chamber. If the fission chamber that feeds the wide range instrument fails low on a power increase, that channel's output would: A. Lower the CPS output in the source range and slightly lower the value at which the Level 1 (2%) and Level 2 (10-4?6) bistables are actuated ! IL Not affect the CPS output in the source range, but will prevent the Level 1 and 2 bistables from . actuating at 2% and 10-4% respectively. I C. Lower the CPS output in the source range and will prevent the Level ! and 2 bistables from actuating at 2'6 and 10-4*6 respectively. D. Not affect the CPS output in the source range and slightly lower the value at which the Level 1 l (2%) and Level 2 (10-4%) bistables are actuated Answer: C . Justification a Loss of the wide range would imply no output to the Lesel 1 and 2 B'S.
- b. Source range output is affected by the loss of one detector.
- c. CORRECT. The source range instrument will not reach this high an indication.
- d. See 'a' and 'b' above.
Question Topic: Brstable and logic cucuits v RO y SRO K/A Rating 29/32 CFRt RO $$ 41(b)(2) SRO $5 43 (b)(5) System 015 K/A # K6 01 ELOs Ni-01013 and 6 Reference- STM Chapter 14 _ _ _ . . . _ _ _ - _ _ . -. ._ _ _ . . _ - _ _~.__.- - -_-.._. - - - . _ - . _ - _ - . - - . - - . - - Page 27 of 100 4'13'97
SRO liX AM RiiVil!W Group 1 Plant Questior Following a steam line break accident the Si termination procedure (ES 1.1) calls for throttling of IlPGl flow before resetting SlAS. Ilow is llPSI flow throttled in this condition? l l A. IISI hi 41 and 42 NORhiAL/ BYPASS keys to BYPASS;llSI hi ll, 12,21,22,31, and 32 l throttled as necessary. B. IISl M-41 and 42 NCRMAIMYPASS keys to NORMAL;ilSI M 41 and 42 throttled as necessary. C. IISl M 41 and 42 NORMAUBYPASS keys to BYPASS;ilSI M 41 and 42 throttled as necessary. D. IISI M 4 I and 42 NORMALBYPASS keys to NORMAL; ilSI M 11,12,21,22,31, and 32 throttled as necessary. Answer C Justification
- a. IlPSI loop vahes cannot be throttled without resetting SI.
- b. HPSI header valves cannot be throttled without switch in bypass.
- c. CORRECT. The keylock switch must be in bypass.
- d. See 'a' and 'b' above.
Ouestion Topic. Throtthng HPSI flow for Si termination
& RO y SRO KIA Rating 3 3/3.7 CFR8. RO 55 41(bX7) 55 43 (bX5)
System 013 KIA 8 K4.10 ELos ECCS-01017 Reference RO-L 2 6 Page 28 o!100 4/13'97
I SRO EXAM REVIEW Group i Plant Ouestion. During CEA exercising (Surveillance Proc. 318) a group 5 CEA drops into the core while at 80% power. The operators employ the "long term slow recovery" method to restore the dropped rod per AOP 2 21, " Misaligned (dropped) CEA", because of problems with that rod's power supply. Why is power reduced in this situation? A. Power reductions prior to rod recovery control xenon oscillations and symmetric offset limits. B. Power reductions prior to rod recovery minimize flux peaking and limit pellet clad interactions. C. Power reductions prior to rod recovery increase the KW/FT value and decrease the FRT limit. D. Power reductions prior to rod recovery eliminate the need for additional boration. j Answer. 8 Justificabon
- a. Xenon oscillations are a function of asial flux distribution and can be minimized when withdrawing the rod, but not eliminated.
- b. CORRECT. The xenon concentration in the area of the dropped rod is increasing with time and presents challenges to the pellet.
4
- c. KW/FT value will decrease with decreasing power. i
- d. Horation is required because rod insertion exacerbates the peaking in the area of the dropped rod.
- Queston Topse: Recovery of dropped rod ,
y RO- y SRO KlA Rating 3 9/4.1 CFRs. RO 55 41(b)(5) SRO 55 43(bH6) .
; Systern 001 K/A 8 K4 09 .
IELos. CEDS-09021
Reference:
AOP 2 21
++-e er - . -- ,.eg m.a,..e_.me--.~=i.ww.-4. . . . . . w w --ap..e s
?
Page 29 of 100 4/13/97 3
.,.- - - - . - - . _ ~ - _ - . -.
SRO EXAM REVIEW Group 1 Plant Quev;on Winich of the l'ollowing indications could be used to difTerentiate between an actual low pressurize: level and a low failure of the "in service" pressurizer level control channel? A idl heaters are de energized. l B. Sta;2by charging pump in " AUTO" starts. C hiinir..um letueidaw it imJicated on the letdown flow controller. D. hiaximum charging flow is indicated on the charging flow controlla. Ans-en A Justification
- a. CORRECT. This is the only action that could differentiate between the two since heaters are de-energind bs an UC separate from the level control circuit.
- b. This function comes off the nel control circuit and can be caused by actual low lesel OR the level control channel failing low.
e This function comes off the level control circuit and can be caused by actual low level OR the level control channel failing low. ( d This function comes off the !cvel control circuit and can be caused by actual low level OR the l level control channel failing low. Question Topic. ioss of PZR level V RO p SRO K/A Rating 3 9/4 2 CFRs. RO 55 41(bX7) SRO 55 43 (b)(5) System- 004 K/A s A2.02 E!.Os PLC-01012 & PLC-01014 Reterence: STM Chapter 3 (Section 4.2) l l Page 30 of 100 4/13/97
SRO EXAM REVIEW d Group 1 Plant Queston. The reactor has tripped from a total loss of offsite power and the emergency diesels (DG 1 A and
- 18) are operating and supplying their respective emergency buses. Breakers 1R,2R,3R, and 4R are " green flagged open" and breakers 1U,2U,3U, and 4U are " red flagged open". Undervoltage lockout relays 27Y-5 and 27Y-6 cannot be reset. What action is necessary to reset these relays?
A. Breakers 3R and 4R must be placed in
- PULL-TO LOCK" before the 27Y 5 and 27Y-6 relays will reset.
B. Breakers 3U and 4U must be placed in " PULL TO-LOCK" before the 27Y-5 and 27Y 6 relays will reset. C. Breakers IR and 2R must be placed in " PULL-TO LOCK" before the 27Y 5 and 27Y 6 relays will reset. D. Breakers 1U and 2U must be placed in
- PULL-TO LOCK" before the 27W5 and 27Y 6 relays will reset.
Arner: 8 Justification
- a. Breakers 3U and 4U are required to reset the relays.
b, CORRECT. This prevents inadvertant paralleling with offsite power.
- e. Breakers 3U and 4U are required to reset the relays.
- d. Breakers 3U and 4U are required to reset the relays.
Question Topic: Abd.ty to evaluate electrical reset crneria
$ RO y SRO KIA Rating 3.7/4 4 C/Rs RO $5 4 e (b)(7) SRO $5 43(b)(5)
{ System: Genenc KIA # 2.1.07 l El OW. AC-09021 l
Reference:
RO15 2 Page 31 of 100 4/13/97
SRO !!XAht Rl!Vil!W Group 1 Plant Ovestion. While at 100% power, high vibration alarms are received on #3 RCP. While investigating the , alann locations on the RCP vibration monitor, the reactor trips on low flow. The green and amber lights on #3 RCP control switch are lit; ;
- The 86 device (86 P-1 3) on the breaker cubicle is " tripped"; l
- Overcurrent devices on two phases (51 A and SI-C) on #3 RCP are tripped.
What is the probable cause and efTect of this event? A, An RCP seized rotor and challenge to the fuel centerline melt safety limit. B An RCP sheared impeller and challenge to the DNBR safety limit. C. An RCP seized rotor and challenge to the DNBR safety limit. D. An RCP sheared impeller and challenge to the fuel centerline melt safety limit. Answer- C Justification a Seized rotor will challenge DNBR before centerline melt.
- b. Sheared impellor will not bring in overcurrent trips.
- c. CORRECT. This is a DNBR challenge event.
- d. Neither answer is met by conditions in the stem.
Ouestion Topic: Loss of RCP effect on RCS
%RO y SRO K/A Ratng 3 7/4 0 CFR# RO 55 41(b)(14) SRO $$ 43 (bX6)
- System 003 K/A # K3 01
. ELos. RCP-0101 14; PPM-0103-10
Reference:
RO-L-2.1; STM Chapter 2 Page 32 of 100 4113'97
SRO !!X AM RiiVtliW Group 1 Plant Quesbon The plant is in a mini outage to conduct fuel sipping operations in the spent fuel pool (SFP) While moving en assembly in the SFP a spent fuel pool area monitor radiation alarm is received. What automatic action occurs as a result of this alarm? A. The upender cannot enter the SFP in this condition. B. The new fuel elevator upward motion is inhibited. C. The SFP ventilation system is automatically shut down. D. The SFP crane trolley movement is inhibited. Answer B Justi*ication
- a. The upender is not affected by this alamt
- b. CORRECT. Upward motion is inhibited by this alarm.
- c. There are no automatic actions associated with the ventilation system.
- d. The SFP crane is not affected by this alarm.
i Question Topic Fuel handhng operations
& RO y SRO KlA Rating 31/3 $ CFR8 RO $5 41 (b)(11) SRO 55 43(b)(7)
Eysterw 072 K/A 8 K3 02 ELOs RfAS 01017 Reference. Refuebng procedure 134 Page 33 of 100 4/13/97
SRO EXAM REVIEW Group 1 Plant Quesbon' Which of the following conditions will result in a boration of the RCS? A. Placing the makeup mode selector switch in " BORATE" with the boric acid flow control valve (BA F 30) set at 0 gpm and CH F 38 in " AUTO." B. Placing an emergency boration valve switch (BA M 37)in "OPEN" with VCT pressure at 20 psig while on normal letdown with CH F 38 in " AUTO." C. Placing an emergency boration valve switch (BA M 37)in "OPEN" while on alternate letdown I with CH M 87 shut and CH F 38 in " AUTO." D. Placing the boric acid flow control salve (BA F 30) at 15 gpm with the makeup mode selector ! switch in " DILUTE" and CH F-38 in " AUTO." Answer C Jushfecabon.
- a. Flow will only occur if the valve leaks by.
- b. VCT pressure will prevent boric acid flow.
- c. CORRECT. The imbalance between charging and alternate letdown in this condition results in a drawdown of the BAST,
- d. Valve will not open with switch in "DlLUTE" Queshon Topic: Emergency borshon valves operabon k RO 'y SRO K/A Rahng 4.3/4.1 CFR#, RO $5 41 (b)(5) SRO $5 43(b)(6)
System 004 K/A #. A4.18 ELOS: CVCS-0103-2 Reference. STM Chapter 4 (Seebon 2 4 7)
.__ . _ _ _ _ ~ _ _ _ . _ . . ._ _- _ _ _ . . . _ . . _ . _ _ . . _ _ . . . -_. _
i Page 34 of 100 4/1397
SMO I!XAM Rl!Vil!W Group i Plant ouenbon: The plant is at 50% power when a Train "A" 11ELB signal is actuated in the PAB. Which of the following calculations / systems would be directly or indirectly afTected by Train "A" llELB actuation? A. MWth, llV.7 heating steam, and VCT level. B. MWth, seal water temperature, and PAB general area ventilation (FN 2). C. S/G radiation monitors, MWth, and BWST heating. D. Letdown radiation monitor, MWth, and Spray Building pressure. Answer C Jushfcabon a.11%7 heating steam is from the Spray Building.
- b. FN 2 does not use any auxiliary steam.
- c. CORRECT, All these indications / systems are effected by a loss of blowdown, letdown and PAB -
auxiliary steam. , d Spray building temperature and not pressure will be affected by a loss of auxiliary steam and this is a PAB not Spray Building actuation. Queston Topic: Inmabon signals for ESF topic.NELB
;Q RO Q SRO KIA Raung 4.214 4 CFRt. RO SS 41(b)(7) SRO 55 43(b)(5)
; System: 013 KIA # K101 I ELO8. HELB-01013
Reference:
STM Chapter 6 (Sechon 3 2.7) m... _ - _ . . . _ _ - _ _ _ . _ _ _ _ _ _ _ _ . _ _ . . _ _ _ _ _ . _ _ _ _ _ Page 35 of 100 4/13/97 -
l I SRO liXAM REVIEW l Group 1 Plant omtion. While maintaining a hot shutdown condition, the #1 RCP seal water return How high alarm is received and the operato has indications that all three seals are failed. The operator notes that the
# 1 RCP seal water return indication on the MCB is pegged high and the other two RCP's seal water retum Hows are <1 gpm. How does this condition effect the operation of the #1 RCP?
A. The #1 RCP may remain operating but the seal water return valve (SL M 29) should be closed. B. As long as seal water injection How is greater than seal water return Dow, the #1 RCP may continue running. C. All the RCP's must be immediately secured in this condition and their respectivr seat water return valves closed D. The #1 RCP should be tripped and the seal water return valve (SL-M 29) closed. Answer. D Justafication
- a. This condition is not allowed by the manufacturer. The RCP must be tripped before elesing SL-M 29.
- b. This is partially true but not in a condition with three failed seals.
- c. It is not necessary to trip all the RCPs in this condition.
d CORRECT. This is required to prevent further dama.ce to the seal. Ouestion Topic: Seal return flow degradation V RO V SRO K/A Ratng 3 5/3 9 CFRs. RO 55 41(bX5) SRO 55 43(b)(5) ' System: 003 K/A 8. A2 01 ELO*. E AS-0150-4. E AS-C90315 t
Reference:
STM Chapter 4. AOP 7 50 Page 36 of 100 4/13/97
SRO EXAM REVitiW Group 2 Plant Question: FollowinF a load rejection anticipated operational occurrence (AOO), the reactor fails to trip on signals generated by the reactor protection system. What backup system will provide core protection during the AOO7 A. Diverse scram system (DSS) on high pressurizer pressure two (2) out of four (4), opening M/G set output breakers. B. Diverse scram system (DSS) on low S/G water level two (2) out of two (2), opening M/G set
' output breakers.
C. Diverse turbine trip (DTT) on low S/G level two (2) out of two (2), energizing 20 AST and dumping auto-stop oil. D. Diverse scram system (DSS) on high pressurizer pressure four (4) out of four (4), opening M!G set output breakers. Answer: -A Justifical on-
- a. CORRECT. This is the correct logic and input for DSS.
b.- DSS works on pres >urizer pressure inputs, not S'O luel.
- c. DTT works on low S/G level and energizes 20 AST, but sends its signal only to the turbine.
- d. This logic is 2/4, not 4/4.
Question Topic: DSS trp circurts for AOO
. V. RO y SRO KlA Rating' 2 9/3.1 CFRW. RO 55 41 (b)(7) SRO 55 43 (bX5) ' System. 012 K/A # K6.02 ELOW. RPS-0902-2
Reference:
STM Chapters 11 (Section 2.9) and 24 (Fig 2411) Page 37 of 100 4/1347
1 i ' SRO EXAM REVIEW i, - , Group 2 Plant ' Oue.non i ; i Which of the following groups ofindications, trips, and alarms will be elTected if any one l l pressurizer pressure safety channel is lost (PT.102 A, B, C, or 9)7 { i t A. High pressure trip unit, PORV block valve au:o open, diverse scram system.
- i. 3 I
i B. TM/LP trip unit, SlAS actuation, LO LO pressure alann. 3 j C. SPDS input, SlAS actuation, low p essure heater cutout. 1 ! D. PORV actuation, diverse turbine trip, high p.ressure trip unit. Answer. B l j Jushricatiort l I l a. Block valve auto open comes from control channels X and Y.
- i j' b.- CORRECT. The low pressure alann is from control channels X and Y. The low low alarm i originates in the SlAS trip unit.
j i c.- There is no low pressure heater cutout. i l
- d. DTT actuates on low S/G level, not RCS pressure.
i * .
- Ouesbon Topic; PZR pressure malfunction-effect on RPS ,
f, f V RO Q SRO KIA Rabng 4 0/41 CFRs, RO 55 41(bX7) SRO SS 43 (bX2)
! System:_ 010 K/A 8. K3.02 '
.,l- '; ELO#. PPC-0102 3 - - l
Reference:
STM Chapters 3 and 11 { l - f i-i l i k Page 36 of 100 4/13/97 t r.---,_-,--., .,..,-,-....-.:--,,..-..,...;., .-.. ~..,.-.- .,. .-,. . , , , . - _ - . - . , - , - , . . ~ - .
I SRO EXAM REVIEW Group 2 Plant
. Question:
A loss of secondary heat sink has occurred. The reactor head subcooled margin monitor is reading 10 F and is decreasing. As the reactor head subcooled margin monitor approaches 0 F, pressurizer level indication will: A. Increase due to voiding in the PZR heater area. B Increase due to voiding in the reactor vessel. C. Increase die to voiding in the S!G tube bundle region. D. Increase due to voiding in the PZR reference leg. 4 Answen B-Justifcation.
- a. Voiding may occur in this region, but it will be insignificant compared to that in the head.
- b. CORRECT. The head region of the vessel will void first.
- c. It is unlikely for the S/G's to be hotter than the RCS in this condition.
- d. This will cause an increase in indicated level, but in this condition it is unlikely.
Question Tope: PZR level ndication when RCS es saturated M RO 7 SRO KIA Rating 3.6/4 0 CFR#: RO 55.41(bX5) SRO $5 43(bX5)
. System: 011 K!A 8 K5.15 ELos PLC-0902 2 Reference. STM Chapter 2 (3.2 2) l Page 39 of 100 4/13/97 l
SRO EXAM REVIEW Group 2 Plant ouestion: A plant trip occurs on low S/G level near the end of cycle. The operator notes increasing counts on the letdown radiation monitor (RM-3102). The demineralizer bypass valve (LD-T-36) is open (to demineralizer), but the letdown pressure control valve (LD-F-16) has automatically closed. The VCT cubicle area radiation levels have increased. What is the probable cause of this event? A. A crud burst has occurred and caused LD-F 16 to close on high pre-61ter D'P. B. A fuel failure has occurred and caused LD-F.16 to close on high demineralizer D/P. C. A crud burst has occurred and caused LD-F-15 to close on high demineralizer D'P. D. A fuel failure has occurred and caused LD-F-16 to close on high pre-61ter D.P. Answer. A Justifration-
- a. CORRECT. The increasing radiation level in the VCT is attributable to lifting of LD-S-14 sending contamination directly to the VCT.
- b. LD-T 36 shuts on high demineralizer D!P, not LD-F-16.
- c. The demineralizers will not see a high D.'P because the crud is removed in the pre-Gite
- d. If the pre-61ter becomes clogged, the most likely event is a crud burst.
Ouestion Topic: High activtty in L/D. actions to mitigste
? RO y SRO K/A Rating 32/33 CFR#. RO 55.41 (b)(11) SRO 55 43 (b)(4)
System: Genenc K/A 8. 2.1.28 ELO# RMS-0902-2; LVCS-0102-5; CVCS-0902-2 . Reference- STM Chapter 4. AOP 2-25 _ _ _ _ _ . _ _ _ _ _ _ _ _ ._____s Page 40 of 100 4/13!97
SRO EXAM REVIEW l Group 2 Plant ouesbon-The spare containment spray pump (P-61S) is aligned as a "B" train LPSI pump during normal l operations. A total loss of offsite power and SlAS actuation signals are initiated due to a seismic l event. How does P-61S respond during this transient? I A. P-61S starts immediately due to 27Y-5 actuation. B. P-61S starts on time delay due to 27Y-5 actuation. C. P-61S starts immediately due to 27Y-6 actuation. D. P-61S starts on time delay due to 27Y-6 actuation. Answer D Justfication
- a. When 27Y-5(6) actuates the pump always starts on a time delay.
- b. Aligned as a B pump will require a 27Y-6 trip
- c. To prevent diesel overload, the pump starts on time delay.
- d. COrdICT. There is a time delay for pump start.
Ouesbon Topic. ECCS pump power supphes i'V RO y SRO K/A Rating 3 6/3 9 CFR8 RO 55 41 (b)(7) SRO 55 43 (b)(5) System: 006 K/A 8. K2 01 ELO#. ECCS-0101-12
Reference:
STM Chapter 6 _ _ _ . _ _ _ _ _ _ _ . . _ . _ _ . _ _ _ ~_ ...___._-_ _. _ _ ______ - - - __ - - - . - _ Page 41 of 100 4/13/97
SRO EXAM REVIEW Group 2 Plant Oueston. The primary inventory trend system (PITS) provides reactor vessel level indication during accident conditions. Which condition ensures proper reference leg operation for PITS indication? A. The RCP's are coasting down and the seal pot is continuously filling the reference leg. B. The RCP's are ofTand CET density compensation of PITS is operating. C. The RCP's are rtmning and the RTD density compensation of PITS is operating. D. The RCP's are off and the seal pot is continuously filling the reference leg. Answer. D Justrficahon: a RCP cor.stdown still creates dynamic head pressure on PITS indication
- b. Density compensation is provided by RTD's not CETs.
- c. RCP's must be off to read.
- d. CORRECT. Seal pot reference leg fill ensures accurate reference leg indication.
Queston Topic: RX vessellevelindicabon causeleffects
/ RO Q SRO K/A Ratng 3.5/37 CFR#. RO 55 41 (b)(3) & (7) SRO $5 43 (b)(5)
System: 002 K/A s K1.07 ELOs RCS-010211. RCS-0102-9
Reference:
STM Chapter 2 (Secton 3 21) Page 42 of 100 4/13/97
l 4 SRO EXAM REVIEW-Group 2 Plant oue.tm An " Operator Workaround" is defined as an equipment deficiency (including design deficiencies)
- l. which can impact operator response during a transient or accident. Which of the following when at hot full power, would be designated as an Operator Workaround?
l A. The north entrance to the steam and valve house is temporarily blocked by scafTolding in the Reactor MCC Room. A B. An operator is stationed at the feedwater section of the MCB to manually control #1 S/G main I feed regulating valve for 15 minutes. I C. Train "A" CIS annunciator for " Trip Signal: RCP Trip Criteria" is continuously lit on the MCB j annunciator panel. i D. The MCB switch for the diesel fire pump (P-5)is being replaced due to a design deficiency n (auto-start is available)- Answer: C i Jushficahon. i a. Access to the room is still available, however, for certain Appendix R events, this could be a problem. 3
)
- b. Control system will automatically shut valve on a turbine trip and this is not a long term condition.
- c. CORRECT. This indicates that a problem exists which will not alert the operator in an accident condition.
- d. The pump can still auto-start and P-4 is also av:.ilable if needed.
Queshon Topic. Knowledge of operator respormbihties
- Q RO *;/ SRO K/A Rabng 3.0/4.0 CFR# RO 55 41 (b)(10) SRO 55 43 (b)(3)
System: Generic K/A #. 2.1.02
~ ELOS: AD-0102-1
Reference:
OP 1-20015 2 Page 43 of 100 4113/97
SRO EXAM REVIEW Group 2 Plant Quesbon: . - An on line purge of containment is in progress. During your control board walkdown, you note that the valve position indications for VP-A-1,2,3, and 5 are both lit (red and green indications on). What would this condition indicate? A. That a high containment gas or PVS gas radiation level alann hasjust cleared and the valves are traveling to the full open position. B. That a containment low range or manipulator crane alarm wasjust received and the valves are traveling to the closed position. C. That a purge is about to begin as soon as the valves reach their full open position. D. That a purge is in progress and all four (4) valves are positioned according to procedural restrictions. Arawer- D JustficaDon-
- a. Valves are mechanically blocked when in on line mode.
- b. Valves do not shut on these signals during on line purging.-
- c. Full valve opening when on-line is not allowed.'
- d. CORRECT. VP-A-1,2,3, and 5 are 50% open.
Question Topic: Control features of auto purge esotaton 7 RO y SRO K/A Rating 3.2/3 5 CFRS, RO 55 41 (b)(4) SRO 55 43(b)(1) System: 029 K/A #. K4.03 ELO#. CP-0101-5
?
Reference:
OP 1 12-1 A Page 44 of 100 4/13 97
SRO EXAM REVIEW Group 2 Plant Ouesbon. The SFP demineralizer (14) has just received a fresh charge of unborated H-OH resin and has been improperly placed in service. Over the next several hours: A. SFP 15 minute gross gamma should decrease, boron concentration should increase, and negative reactivity in the SFP should increase. B. SFP 15 minute gross gamma should decrease, boron concentration should decrease, and negative reactivity in the SFP should increase. C. SFP 15 minute gross gamma should increase, boron concentration should increase, and negative reactivity in the SFP should decrease. D. SFP 15 minute gross gamma should decrease, boron concentration should decrease, and negative reactivity in the SFP should decrease. Answer D Justf. cation'
- a. Boron concentration will increase due to improper resin boration.
- b. If boron concentration decreases, then shutdown margin will also decrease.
- c. Gross gamma will ahvays decrease with a new resin change and boron concentration should decrease.
- d. CORRECT. This is the expected response for an unborated demineralizer.
-Oueston Topic: Abday to predict impact of inadequate SDM l
- i,# RO p SRO K/A Rating 3 0/3 $ CFR#. RO 55 41 (b)(5) SRO 55 43(b)(7)
- System; 033 K/A #. A2 01
. ELOs. CVCS-0102-24 Reference- OP 1 171 ! t Page 45 of 100 4/13/97
1 1
}- SRO EXAM RuVIEW 7- Group 2 Plant j Queshon Which one of the following statements describes the primary plant indication of a loss of RHR F flow due to a loss of RCS inventory while the RCS is m a mid-loop configuration?
l A. Fluctuating RHR pump amps, lower reactor vessel level indication, and decreasing LSI F 59 -
. flow indication.
I B. Oscillating RHR pump amps, fluctuatig charging pump discharge pressure, and decreasing ' i LSI-F-59 flow indication. 3 J C. Decreasing RHR pump amps, lower reactor vessel level indication, and increasing LSl F-59 j' flow indication. + 1 i' D. Increasing RHR pump amps, increasing charging pump discharge pressure, and Ductuating LSI- ! F-59 flow indication. I { Answer: A Justfication: l a.- CORRECT. These indications are most likely in this condition. 1 { b. The charging pump now restrictor is in sersice and pump discharge oscillation is unlikely. 1 a 4 c. RHR pump amps will decrease, but will fluctuate, therefore, a decrease in RHR flow via LSI F-0 59.' i i d. Vortexing causes amp fluctuations, not increasing values. Quesbon Topic: H2O levelin refueling canal (SRO ordy) l J RO p SRO - KIA Rabng 2.9/3.7 ' CFR#, SRO 55 43 (b)(5) f ; System: 034 KIA #: A1.02 l ELO#. RHR-0902-2 l
Reference:
OP 1-17-8 i
.~. _
f f 4 g
?
1
)~
li Page 46 of 100 4!13/97
. , ,_- - . , _ _ - - - - , . , . - . . . _ . _ . . ~ . . _ . . - _ ---
SRO EXAM REVIEW (- Group 2 Plant I -' Quesbon. L Which of the following describes the method used to to ensure the SIT isolation valves (SIA M ll, 21, and 31) are available for use during Condition 7 operations? A. The MOVs have a breaker and disconnect that are locked closed to ensure power and valve position indication is always available to the valve. B. The MOVs have a breaker and disconnect that are locked open. Valve position indication is provided by an alternate DC power source, C. The MOVs have a breaker and disconnect that are locked open but downstream of the control power transfonner allowing continuous valve position indication. D The MOVs have a breaker and disconnect that are locked closed. Valve position indication is provided by an alternate DC power source. Answer: B Justfcahon:
- a. The MOV disconnect is locked open in Condition 7. Valve indication from AC control power is not provided for these valves.
- b. CORRECT. The disconnect is locked open while a separate DC power source provides valve position indication.
- c. DC control power is used to provide continuous valve position indication.
- d. The MOV disconnect is locked open in Condition 7.
Quesbon Tope: SIT valve posebon indcabon l2 RO Q SRO K/A Rahng 3 413.9 CFRs RO 55 41 (b)(7) SRO 55 43(b)(2) ; f System: 006 K/A # K6 03
! ELos ECCS-010116 Reference; FSAR Chap. 6.TS 3.19 A i
Page 47 of 100 4/13/97
i l l I SRO EXAM REVIEW i GrouD 2 Plant ! Question: The following conditions exist when in hot shutdown: >
- PAB upper level ambient temperatures are >130 F; - - RCS temperature is being maintained via AS-P-3 and MS-A 162 opening; - CH-F 38 flow is increasing with charging header pressure decreasing: - Main steam non-retum valves (MS-M-10,20 and 30) are closed; - Blowdown is' aligned to the primary vent stack; - A four times normal radiation level spike was recorded on the PVS gas monitor (RM-3902Y).
Initial discussion among the crew seems to indicate that a steam generator tube leak may be in progress. What mechanism should the operator use to confinn the S/G tube leak? A. Allow a few minutes to pass then note any increasing radiation levels on the blowdown monitors. B. Use the main steam !ine monitor to note any increasing radiation level trends. C. Continue trending the PVS radiation level and off-gas filter radiation levels. D. Monitor the rteam generator levels and EFW flow. Answer: - 'D Justification: a The blowdown monitors are isolated when HELB is activated due to high PAB temps.
- b. In this condition of fairly stagnant flow, the main steam line monitors may be unable to see increasing radiation levels.
- c. The PVS spike is now isolated with blowdown secured and will not be a reliable indication.
- d. CORRECT. This is the only confirmation action that should yield positive S/G tube leak indications.
Question Topic: Recognmon of S/G tube leak on rad levels 9, RO y SRO K/A Ratmg 4.1/4.4 CFR#: RO $5 41(b)(10)&(11) SRO 55.43(b)f4)&(5) I System: 035- K/A f. A4.08 { ELos. EAS4903 5 and 14; SG-0902-2 {
Reference:
E-3 BKGD Document (Step 4) Page 48 of 100 4/13/97
SRO EXAM REVIEW Group 2 Plant Queston: In preparation for core offloading, the upper guide structure (UGS)is being removed from the reactor vessel. As the bottom of the UGS clears the reactor vessel a camera detects a fuel assembly stuck to the bottom of the UGS. As SRO in charge of refueling, you should: A. Immediately reinsert the UGS while monitoring the load cell in the event the fuel assembly is wedged. B. Maintain the UGS in position and seek Operations and Engineering department assmance. C. Continue withdrawing the UGS and position the bottom of the assembly over the reactor vessel lip. D. Lower the UGS approximately six feet and nudge it with the polar crane to dislodge the assembly. Answer: B Jushficabon.
- a. The assembly should remain in as stable a condition as possible.
- b. CORRECT. Because the assembly is still within the core boundaries, this is the most conservative condition ihr the assembly
- c. Assembly could fall out in this condition.
- d. Non-conservative method to dislodge the assembly.
Oueshon Topic: Stuck fuel element while removing upper guide structures C RO p SRO K/A Raung 3.614 4 CFR# SRO 55 43(b)(7)
- System. 034 K/A s. A2 01 ELO#. FH-0902-1
Reference:
Refuehng procedure 1311 L_. . _ _ _ _ _ . _ _ _ _ _ _ . _ _ . - _ _ . - _ . . _ . _ _ _ . - _ - _ _ _ . _ _ . . , _ _ . _ _ _ _ - - - . . _ Page 49 of 100 4/13/97
1 SRO EXAM REVIEW 1 Group 2 Plant Queston:
- J A plant cooldown is in progress. The #1 and #2 S/G EFCV switches have been placed m "OPEN,"
- #3 EFCV switch was inadvertantly left in " AUTO." Which of the following statements identines ,
plant response on decreasing steam generator pressure? A. When 2/4 steam generator pressures in #3 S/G are <400 psig, all EFCV's will close. B. When 4/4 steam generator pressures in #3 S/G are <400 psig, only #3 S/G's EFCV will close. C. When 2/4 steam generator pressures in #3 S/G are <400 psig, only #3 S/G's EFCV will close. D. When 1/4 steam generator pressures in #3 S/G are <400 psig, all EFCV's will close. Answer: A-Justfcabon:
. a. CORRECT. When #3 gets to 400#, even those valves in OPEN will shut.
- b. Logic is 2/4, not 4/4, and all EFCV's will go CLOSED. .
- c. Even though #1 and #2 are in open, all three (3) EFCV's will close on a low S/G pressure signal.
. d. Logic is for 2/4, not 1/4.
'Queston Topic Abdity to monitor auto isolabon of man steam via EFCVs
-y RO y SRO K/A Ratng 3.1/3.5 LFR# RO 55 41 (b)(7) SRO 55 43(b)(5)
- System: 039 K/A #, A3.02 ELos. MS 0101-4 and 6 i I eference:
R STM Chapter 22 Page 50 of 100 4!13'97
. _.-.- - ...-. .. .. - - - --.- _=---.-.- _ - - -.--- -=-. .
1 4 SRO EXAM REVIEW i 1
; Group 2 Plart li A containment recirculation fan power supply change was necessitated due to a LOCA scenario.
)'
Which of the following describes the change (s) made to prevent diesel generator overload? f -A. FN-17-2,4, and 6 were moved from BUS 8 and are powered from MCC-9C located in the 1 protected switchgear room. B. FN-171,3, and 5 were moved from BUS 7 and are powered from MCC 9C located in the J - protected switchgear room. C. FN 17-2,4, and.6 were moved from BUS 8 and are powered from MCC-9C located in the j- unprotected switchgear room. I j D. FN 171,3, and 5 were moved from BUS 7 and are powered from MCC-9C located in the < l unprotected switchgear room. Answer: A i Justification:
- a. CORRECT. This prevents DG 1B overload conditions during certain LOCA-based scenarios.
! b. FN-17-1,3, and 5 remain powered from BUS 7.
4 l, c. MCC-9C is located adjacent to MCC-7A in the protected switchgear room. 4~
- d. See "b" and "d" above.
l Ouesbon Topic: Significance of DG toad limits 2 RO y SRO K/A Rating 3 2/3 5 - CFR#. RO $5 41 (b)(7) SRO 55 43 (b)(2) , 4 . System: 062 KIA #. A1.01 { j = ELos. AC-0101-19 ! Reference. EDCR 94 57 ; 1 .
^
4 I 9 4 b I l t i 1 4 i ! Page 51 of 100 4/13/97 .
_ - , . . - _ - ~ . - . - - - . , . - , . . - SRO EXAM REVIEW - Group 2 Plant
- Question.
How are radiation levels trended inside the containment during an accident that releases large amounts of radionuclides? A. The high range radiation monitors (RM-6113A/B) have chart recorders that are automatically . activated. B. The low range radiation monitor (RM-6105) has a chart recorder that is automatically activated. C, The manipulator crane radiation monitor (RM-6104) has a chart recorder that is automatically activated. D. The low range radiation monitor (RM-6105) automatically activates a historical record on the plant computer. Answen -A Just4featort
- a. CORRECT. This is the method used to trend containment radiation levels.
- b. This function is provided by the high range only.
- c. This function is provided by the high range only.
- d. Historical records can be accessed but are not automatically activated.
Question Topec: Monitonng changes in ra$ation levels , Q RO p SRO KlA Rahng . 32/3.5 . CFRs. RO 55 41 (b)(11) SRO 55.43 (b)(5)
- System: 073 K/A #: A1.01
- ELO#. RMS-0902-1
Reference:
STM Chapter 20; RO-L 9.5 e W Page 52 of 100 4/13/97
'.~ . .__-2 _. -_ _ - -. - . . .. . - - . - - - . . - - - ,, .-
SRO EXAM REVIEW Group 2 Plant oueston. The reactor isjust critical when the plant computer shuts down: The operator is required to verify compliance with an NRC ordered 2 psig containment pressure limit. Which of the following Control Room instrumentation is available to meet the containment integrity limits? . A. The mensor quanz manometer indication (PIT-2021). B. The volumetrics containment pressure instrument indication (PIT-2020). C. Post accident wide range containment pressure instrument (Pl-2012). D. : Narrow range containment pressure instrument (PT 2085). Answer; D Jushficabon:
- a. Not available in control room with computer OOS.
- b. Not available in control room with computer OOS.
- c. Cannot be used to satisfy NRC requirement; not accurate enough.
- d. CORRECT. Meets NRC criteria for 2 psig lithit, Queston Topic: Loss of cont otegnty m normal OPS (SRO only)
' ' RO.p SRO KIA Rahng 3.8/4 2 CFR#. SRO $5 43 (b)(2 & 3) System.103 K/A #- K3 C2 ELOs. SNO-0303-13. EAS-0150-4
Reference:
AOP 2 30 (Secton 2 0) Page 53 of 100 4/13/97
I 1 SRO EXAM REVIEW 1 Group 3 Plant l Queston. I The reactor is in a Cold Shutdown condition (150 psia & 200 F) with RHR Dow being maintained by LSI F 59 at 2500 gpm. Electrical Maintenance has requested that Operations minimize plant electrical load by reducing now to 1000 gpm. What adverse efTect could this reduction in now have on plant safety? A. The RHR pump would start to overheat because this is the minimum now at which an RHR pump should be operated. B. The RHR pump would start to cavitate due to vortexing at the RHR pump suction valves (RH-M-1 & 2). C. The RHR system would not provide adequate LTOP protection in the event of an inadvertant charging pump start. D. The RHR system would not provide adequate LTOP protection when RH M-1 & 2 shut on low RHRHow. Answer: C Justficaton:
- a. OP l-13-1 step 6.3.6 minimum RHR pump Dow is 500 gpm (as read).
- b. Vortexing only occurs when in reduced RCS volume conditions.
- c. CORRECT. This now ensures adequate mixing to prevent LTOP problems.
- d. RH-M-1 & 2 shut on high pressure (585 psig)
'Queshon Topic. Pressure transient protecton danng CSD .V RO i,7 SRO K/A Raung 3.513 7 CFRs RO 55 41 (b)(8) SRO 55 43 (b)(2) & (3) System 005 KlA s. A2.02
- ELos: RCS-010113; AD-0102 8
- Reference; MYP 87-923 (PRR 90 013); RO-L 7.6 i
Page 54 of 100 4/13/97
i
; SRO EXAM REVIEW Group 3 Ptant oveston:
The plant is at 90% power with the governor valves full open. Tave is 555 F. If a turbine trip should occur:
. A.~ The steam dump and turbine bypass system will quick open in less than three (3) seconds because Tave is greater than Tref.
B. The steam dump and turbine bypass system will quick open in less than three (3) seconds because Th is approximately 575 F. C. The steam dump and turbine bypass system will not quick open in less than three (3) seconds because Tave is not at a high enough temperature. D. The steam dump and turbine bypass system will not quick open in less than three (3) seconds because main steam pressure remains less than 765 psig. Answer-l C' Jushficabon:
- a. Tave must be 18 F > Tref (which is 547 F).
- b. Tave and not Th is the appropriate input into steam dump system.
- c. CORRECT. The steam dump controller has not generated the necessary signal.
- d. Thi's steam presst.re input is not used to generate a quick open signal.
Queston Topic: Relabonstup of Tave to steam dump eperabens [ RO y SRO K/A Ratog 30/3.3 CFR#. SRO 55 43(b)(5)- System: 041 K/A #; K4 09 jELOS SD-0101-4 ,
Reference:
STM Chapter 25 Page 55 of 100 4/13/97
SRO EXAM REVIEW - Group 3 Plant oueston
.t . Which of the following describes the sequence of events that occurs when main generator relay 86' BU actuates when connected to the grid?
A. Tripping of rela) 86 BU sends a signal directly to all four (4) RPS channels to initiate a loss of load reactor trip. B.' Tripping of relay 86 BU sends a signal to 20 AST which energizes and initiates opening of the MG set output breakers. C, Tripping of relay 86 BU sends a signal to the auto stop oil pressure switches subsequently. initiating a turbine, then reactor trip. ! D. Tripping of relay 86 BU sends a signal to 20 ET which closes all four (4) stop valves subsequently initiating a reactor trip. Answer: D Justficahon:
- a. There is no direct signal from the main generator to the RPS.
b.E 20 AST does not open the MG-set output breakers.
- c. 86 BU does not send a signal to auto stop oil.
- d. CORRECT. 86 BU sends a signal to both 20 AST and 20 ET tripping solenoids.
' Question Topic: InterrelabonsNp between RPS and man gen I !Q RO Q SRO K/A Rabng 3 6/3 7 CFR#, RO 55.41(bX8) SRO 55 43(bX5) l System: 045 K/A 8. K1.18 ! ELO#. MG-0101 14; MT 0101-9
Reference:
STM Ctiapter 28 l Page s6 of 100 4/13/97
SRO EXAM REVIEW Group 3 Plant
- What would be an adverse consequence of failing to recirculate the RHR system prior to placing it in service?
A; The RHR heatup limit of 1260 F/hr, will be exceeded when RH-M 1 and 2 are opened with RH-
- 4 closed.
. BJ Excess positive reactivity will be added to the RCS even with the RCS borated to the Cold Shutdown condition.
C. The RHR spring reliefs (RH S-24 and 25) may lift prematurely due to the delta T between the body and bonnet. D. - The RHR heat exchangers may develop RCS to component cooling system leaks caused by thermal shock to the RHR heat exchanger U-tube. Answer; B
' Justfication: - a. The hourly heatup limit is not exceeded, but the restriction for heatup' min would be challenged -(21 F/ min).
- b. CORRECT The accident analysis assumes that the RHR system is recirculated to equalize boron concentration.
c: RHR spring reliefs are unaffected by thermal shock.
- d. RHR heat exchangers may undergo thermal shock, but this condition is seen during an RAS.
Oueshon Topic: RHR in service without proper warmg V RO y SRO K/A Ratmg 3.3/3 9 CFR#; RG 55 41 (bX6) SRO 55.43(bX2) i System: Genenc KIA 8. 2.4.09
- ELos. RHR.010111
Reference:
FSAR Chapter 14, STM Chapter 7 L -- - Page 57 of 100 4/13G7
, I
. - ~..~ _ _.~ --..- -. - .-._. _ ~..--.-.-,,-. _ -
i SRO EXAM REVIEW - Group 1 EPE l oueshon
- F in preparation for restoring AC power following a total loss of AC, ECA 0.0," Loss of All AC Power," requires the operator to place most MCB operated plant equipment in PULL-TO-LOCK in except for the PCC and 3CC pumps, where one of each is left in AUTO. Why are the PCC and
- SCC pumps left in AUTO?
4 A. To supply immediate cooling water to the RCP seal in order to minimize seal damage. j B. To provide immediate loading on the EDG in order to prevent overspeed. p C. To supply immediate cooling for the RHR heat exchangers to continue plant cooldon. 6. j D. To allow for immediate cooling of the EDG to prevent overheating. ! Answer: D t-1 . Justheaton: j_ a. The RCP seal is not an immediate concern at this time. ! b. The charging pump will provide immediate loading on the diesel, i j c. No guarantee that cooling water is needed for the RHR heat exchangers. t
- j. d. CORRECT. The EDG's require immediate cooling to prevent overheating. -
Question Topic: Restorabon of AC/why close PCC breakers? j-. Q RO y SRO KlA Rahng 4.3/4.5 CFR#. RO 55 41 (b)(10) SRO 55 43(b)(5)
; System 055 K/A s EA107 1 ELo#. EAS-0101-7 l'
l
Reference:
ECA 0 O (Step 9) i l Page 58 of 100 4/13/97
'l I
. _ . . _ . .___. _- , . _ . . _ . _ . _ - - . . _ _ _ -.. - .l
SRO EXAM REVIEW Group 1 EPE i Quesbon. The reactor is at 10% power (EOL) and ready for turbine testing. The following conditions exist:
- Turbine bypass valves in AUTOMATIC, set at 825 psig; - Group 5A and 5B rods at 140 steps; - Turbine tripped; - NI and delta T power indicate 10% power; - T cold is approximately 527 F.
4 Reactor Engineering has requested that Group SA and SB rods be borated to the ARO position. After initiating the required boric acid batch addition the RO selects manual sequential rod control and moves Group 5A and 5B rods out. When the IN-HOLD-OUT switch is released, the rods continue to withdraw. What is the plant response without any funher operator action? A. The rods continue to withdraw until they reach the upper electrical limit. The negative MTC turns power and power stabilizes at approximately 10% B. The rods continue to withdraw until the power range Levei 1 bistable is enabled. The plant trips at 15% power because the turbine is tripped. C. The rods continue to withdraw until an N1/ delta T power channel deviation occurs The boration turns power but power eventually stabilizes at 10% D. The rods continue to withdraw until the wide range Level I bistable is enabled A CEA withdrawal prohibit signal will stop the rod motion. Answer: B Justficabon.
- a. Despite the value of MTC at this core life, the rods insert reactivity faster than heatup can turn power.
- b. CORRECT. With the turbine unlatched, the Level I bistable will enable at 15% and a plant trip will occur,
- c. While the boration acts to limit the power increase, the delay time for the boron to reach the core and affect the power level makes the boron ineffective in this scenario.
- d. The Level I bistable is fed off the power range channel.
.Queston Topic: Interpret uncontrolled rod withdrawal (SRO only)
T RO y SRO K/A Rabng 4.414 6 CFRs SRO 55 43(b)(6)
' System 001 K/A W. AA2.05 ELO*. ISR4301 10 ' Reference- AOP 2 22 Page 59 of 100 4113/97
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I l l SRO EXAM REVIEW ! l ! Group 1 EPE j , Queston. While in Tc coastdown, a transient causes a drop in temperature. The plant stabilizes from the j' transient with Tcold at 498.5 F. What is your response to this condition as the Shift Operating I Supervisor? A. Restore Tave to >500 F by lowering power level or commence a reactor shutdown within one
. hour.
J B. ' Restore Teold to >500 F by lowering power level or commence a reactor shutdown within one j hour. C, Maintain Tave at its present value as this is allowed during coastdown operations.
- D. Immediately trip the reactor, as recovery of system temperature will cause significant xenon l oscillations.
1 1 Answer: B
- Justficabon
- a Technical Specifications require restoration of Tcold not Tave.
~
- b. CORRECT Tc must be raised above 500 F or the reactor cannot be critical. Technical
- Specification 3.0. A. applies.
- c. Maintaining Tave is not a concern with respect to Technical Specifications, however Tcold is.
- d. Xenon oscillations will start with the recovery, but at no time during Cycle 15 operations do i thev ever become divergent per TDB graph 1.1.6, Axial Dempening Factors.
l Oueston Topic:. Tech Spec for dropped rod dumg coastdown (SRO only)
'~ RO p ORO K/A Ratng - 3.8/3 9 CFRs. SRO 55 43(b)(2) l System: 003 K/A 8. AK3.07 '
' ELos. SNO-0303 6 and 10
Reference:
OP 1-4 2 (Secton 6 4) Page 60 of 100 4113/97
-- .-.. . . . . - . . . . ~ . - . . . . - . - . .- .. _ .. - - - - - - . . ~ _ _ - - . _ - . - .
! SRO EXAM REVIEW ' l 4 Group tEPE ouesson . The plant is at 55% power during CEA testing. A voltage spike affecting both timer module power supplies causes a Group 5A rod to drop. How long does the operator have, per Technical i Specifications, to commence correction of the CEA misalignment? A. The operator must immediately correct the rod misalignment. B. The operator has 15 minutes to initiate corrective actions. 1 C. The operator has 30 minutes to initiate corrective actions. t [ D.LThe operator has I hour to initiate corrective actions. j Answer: B
- Just6cabon
i a. Tech Spec 3.10.A.3 requires action within 15 minutes. a
- b. CORRECT. Tech Spec 3.10.A.3 requires action within 15 minutes.
1
- c. Tech Spec 3.10.A.3 requires action within 15 minutes.
!- d. Tech Spec 3.10.A.3 requires action within 15 minutes.
t
- Quesbon Topic
- Tech Spec bmas for rod mismatch R RO Q SRO K/A Rating 3 6/4.1 CFR#: RO 55 41 (b)(7) SRO 55 43 (b)(2) ,
- System: 005 K/A #: AK3.03
- ELO#. CEDS-0102 5.6, SNO-0303-10. AD-0104-10 3 - Reference. TS 3.10.A.3 5
Page 61 of 100 4/13/97
SRO EXAM REVIEW l Groun i EPE - l oueston: - During a LOCA, the safety injection tanks will inject borated water into the RCS ' At some point-with wide range Thot <345 F, the SITS are required to be isolated. If the SIT's are NOT isolated ' when required, the'n you would be unable to: A. Guarantee reflux cooling as a heat remaval option due to gas binding in the tube bundle region. B. Restart the RCP's because the seal ca vity would need to be vented prior to use. C. Verify the two-phase level in the reactor vessel via the primary inventory trend system (PITS). D. Control RCS pH because the nitrogen will form nitric acid in the RCS. Answer; A Jushficabon. .
- a. CORRECT. Continuous cooling of the RCS res its in additional SIT blowdown to the RCS and loss of reilux boiling,
- b. Although this statement is true with respect to preserving the RCP seal, this would not be a concern during a large LOCA,
- c. Nitrogen injection will not affect PITS. PITS reference leg will accept any steam!noncondensible mixture.
- d. Formation of nitric acid requires flux levels that would only be seen in an operating reactor.
- - - - - - - . . , . , . . - - - - . -- . . . -- . . _ . - - - . ~
Queshon Topic. Imphcations dunng reflux boeng (SRO only) RO y SRO K/A Ratog 41/4 4 CFRs. SRO 55 43(b)(5) System: 011 K/A # EK1.01. ELos: EAS-0101-7
Reference:
- E-1 BKGD Document (Step 14)
Page 62 of 100 4/13/97
SRO EXAM REVIEW Group 1 EPE oueshon. During verification ornatural circulation conditions, the primary side RO reports that core region subcooling margin monitor is not available for operator use. Which of the following would provide the best indication of natura' circulation flow?
' A. S!G pressure, Pressurizer level, Thot, CETs, and steam tables.
B. S/G pressure, Pressurizer pressure. Tcold, CETs, and steam tables. C. RCS pressure, Pressurizer level, Thot, CETs, and steam tables.- . D. RCS pressure, S/G level, Teold, CETs, and steam tables. Ariswer: B Justification:
- . a. Does not provide Tcold or RCS pressure indications.
1-
- b. CORRECT. This information could be used to determine all elements of natural circulation
- .except for Thot data.
- c. Does not provide Tcold or S/G pressure indications. !
- d. Does not provide Thot or S/G pressure indications.
i _ _ _ _ _ . . _ . - . _ . . _ _ _ . . _ _ . _ . . . _ . _ . _ . . _ . . _ _ _ . . _ _ _ _ - - - . . . . . _ . _ _ Queshon Topic: Development of NC flowluse of RCS instruments jM RO Q SRO K/A Rating 4 4/4.5 -
~
CFRs. RO 55.41 (b)(5) SRO 55 43 (b)(5) !
)- ; System: 015 K/A # AA1.21
) ELO#. PPM-0103-14
Reference:
ES-01 i .-
- - _ _ _ . . _ . - _ - _ _ _ _ . . . - . a Page 63 of 100 4113/97
l SRO EXAM REVIEW - Group 1 EPE
. Queshon:
An emergency boration of the RCS is required following entry into FR-S.1, " Nuclear Power , Generation /ATWS." Which of the following flowpath actions will meet FR-S,1 criteria for l emergency boration? A. Verify a charging pump operating, open HSI M-50 and 51, take LD-A-51 to "PDT", start two boric acid transfer pumps. B. Start two boric acid transfer pumps, maximize charging Dow, verify a charging pump operating, close CH-M-1. C. Start two boric acid transfer pumps, increase auxiliary charging pump (P-7) Cow to at least 15 gpm, close CH-M-87, open BA-M-36 and 37. D. Verify a charging pump operating with CH F-38 open, start two boric r.cid transfer pumps, open BA-M 36 and 37, close CH-M 87. Answer: D Justification:
- a. Flow will continue from the VCT because CH-M-1 and 87 are open. (Higher pressure than RWST.).
- b. No boric acid How due to BA-M-36 and 37 closure and BA-A-80 was not opened.
- c. Does not meet Dowpath requirements of Attachment A in FR-S.I.
- d. CORRECT. This Dowpath meets FR-S.1 emergency boration requirements.
Queshon Topic. Actions for emergency b-ration in FR-S.1
& RO y SRO K/A Rating 4.2!4 4 CFR#. RO 55 41 (b)(5) SRO 55.43(b)(5)
- System: 024 K/A s. AK3.02
- ELos. CVCS-0902-3; EAS-01016
Reference:
FR.S.1 (Step 4) Page 64 of 100 4/13/97
SRO EXAM REVIEW Group 1 EPE Quesborv The plant has experienced a LOCA with failed fuel. The containment spray system is operating in the recirculation mode. RHR heat exchanger tube leaks have spread contamination throughout the PCC end SCC systems. Chemistry wants to increase the recirculation How rate through the PCC and SCC chemical addition tanks to > 20 gpm (bypassing the heat exchangers) to facihte degassification. Why is this situation undesirable? A. It could lead to an unmonitored release via the off gas filters and primary vent stack. B. Increased degassification with residual system chromates can form chromic acid which will accelerate piping corrosion. C. Inadequate PCC/ SCC Dow through the PCC and SCC heat exchangers could violate conditions in the accident analysis. D. The PCC/ SCC surge tanks become a point source for radiatian in an uncontained and unshielded area of the plant. Answer: C Justrication:
- a. Although a release could occur,it is NOT via an unmonitored path.
b Residual system chromates deter rather than accelerate piping corrosion. I
- c. CORRECT. There is a 20 gpm limit on recirculation Dow.
- d. Although the surge tanks will become point sources, the system is contained and temporary shielding can be erected.
_ _ _ . _ _ _ _ _ _ _ _ _ _ - _ - _ - . . _ . _ _ . _ _ _ _ _ - _ - - - - - - . ~ . _ _ _ _ -
;Ouesbon Topc: Cause of possible CCW loss 'Q RO y SRO K/A Rat:ng 2 9/3 6 CFRs RO 55.41(b)(7) SRO $5 43(b)(5)
- System: 026 K/A 8. AA2.02 ELO*. CC-0902-1
Reference:
. OP 1 15-1 (2.0,4.21); EDCR 94 53 Page 65 of 100 4/13/97
i SRO EXAM REVIEW
' Group i EPE Queshon: s During an emergency boration in accordance with FR-S.1, " Nuclear Power Generatiort/ ATWE,"
the operator is required to verify that pressurizer pressure is less than 2385 psig. Why is this action
. required?
A. To ensure sufficient negative reactivity addition rates while using the charging pump (P-14 A/B) for emergency boration. -- B.' To ensure sufficient negative reactivity addition rates while using the auxiliary charging pump
- (p-7) for emergency boration.
C. To prevent a feed and bleed situation which requires exiting FR-S.1 and entering FR-H.1," Loss of Heat Sink." D. With pressure greater than 2385 psig, the Diverse Scram System (DSS)is actuated which impedes boric acid How into the RCS. Answer. A Jtstfication: I
- a. CORRECT. The charging pumps are not delivering Technical Specification required Dows when pressure is >2385 psig.
- b. The Dow rate out of the positive displacement auxiliary charging pump is not effected at these pressures.
- c. CSF status trees would always have the operator complete FR-S.1 prior to entry into FR-H.1-.
- d. It is the RCS pressure itself that impedes boric acid Dow, not the DSS actuation.
Owstion Topic: ATWS effects of boron reactwy (SRO only) - [ RO 7 SRO K/A Rahng 36/38 CFR#. SRO 55 43 (b)(6)
- System: 029 K/A #. EK1.03 ELOs. EAS-01017
Reference:
FR-S.1 BKGD Documents (Step 4) FR S 1 . 8 (' 3 Page 66 of 100 4/13/97 4
SRO EXAM REVIEW Group 1 EPE Quesbon The plant is at HFP, During inspections it is discovered that the reactor trip breaker manual pushbutton wiring is not in compliance with the IEEE standard. What action is required? A. Place the reactor in hot standby within six (6) hours and in hot shutdown in the following thirty (30) hours IL Attempt to repair in the next seventy two (72) hours (as allowed by the remedial action statement). C. Commence a reactor shutdown within one (1) hour and place the plant in hot shutdown within six (6) hours. D. Immediately trip the reactor via the ATWSOSS pushbuttons and be in cold shutdown within six (6) hours Answer C Justifenbon-a Does not meet requirements of Technical Specification 3.0.A.
- b. This remedial action is non-applicable for the manual reactor trip unit.
- c. CORRECT. This meets the Technical Specifications requirements
- d. Undesirable to trip reactor when a controlled SO is alawed and available.
Question Topic: Knowledge of one hour TS action (system) Q RO y SRO KIA Ratng 3 0'3 8 CFR8. Ro $$ 41 (b)(10) SRO $$ 43(b)(2) System: Geners K/A 8 2 1.11 , ELos AD41044 ! Reference. TS 3 9 A and 3.0 A Page 67 of 100 4/13'97
r____. _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ __ - _ . _ _ _ SRO !!X AM Rt!ViliW Group 1 EPE I oveshon . The main turbine has numerous protective devices assuring plant and equipment safety including less direct methods of tripping the turbine. Which of the following methods will generate a remote turbine trip signal? A. With TlH, KG 1, and KGI 375 open, the turbine will trip on a one minute time delay (anti-motoring)
- 13. With two out-of Ibur (2/4) intercept valves closed and two-out of four (2/4) reheat valves closed, the turbine will trip.
C. With a low 812 S/G water level on channels A & il level indications (2/2 taken twice), the turbine will trip D. Closure of all three (3) EFCVs, automatically or manually via operator action, will trip the turbine on low steam pressure. Answer C JuttiflCAtton a With these breakers open, you do not satisfy anti motoring logic. b This is insufficient information for determining if a trip signal will be generated
- c. CORRECT. This signal will trip the turbine.
d EFCV closure will not trip the turbine. Question Topic Manualinp of teactor & turbine v RO y SRO YlA Ratng 4 3/4.5 CFRs RO 55 41 (b)(10) SRO SS 43 (b)(5) System: 068 K/A W. AA123 ELos TAT 01019
' Reference. RO L 3 5 (ESK 9C. 9E. 8AA. BAB. 6 AC & BAD)
- - . - . - . _ . - . . . . - - - . . - . . ~ - . - . . _ . .-.
P Page 68 of 100 4/13'97
SRO liXAM REVIEW , Group i EPE Questgen A main steamline ellow upstream of the #2 non return valve breaks while at 100% power and results in entry into E-0,
- Reactor Trip or Safety injection." An operator finds all three blowdown valves (BD T 12,22 and 32) still open when verifying ECCS valve alignment. Further analysis indicates that the HELB blowdown valves (DD T-141 thru 146) are also open Why is this condition a concern for this accident situation?
A. BD-T 141 thru 146 should have closed on low S/G level to prevent an excessive cooldown and possible return to criticality. B. BD T 12,22, and 32 should have closed on the SlAS/CIS signal to preserve feedwater for decay heat removal. C. BD T 12,22, and 32 should have closed on low S/G level to prevent an excessive cooldown and possible return to criticality. D. BD-T.141 thru 146 should have closed on the SIAS/CIS signal to preserve feedwater for decay heat removal. Answer A Justification
- a. CORRECL The EDCR was done to remove restrictions placed on a return to criticality during a SLB event.
- b. The closure signal is correct, but presenation of the containment integrity boundary is the reason these s alves go shut.
c These valves close on Sl AS CIS or high blowdown tank pressure, not on low S'G level d These valves close on a IIELB signal or low S/G level. The llELB signal is for preservation of safety related equipment in the RAD controlled area Ovestion Topic: Reactrvity effects for SLB (effect of C/D)
~ @ RO y SRO K,A Retnig 41/44 CFRs RO $5 41(b)(7) SRO $$ 43(b)(3)
System 040 K/A
- AKt05 E LO*. EAS 090313 BD 01011 Reference EDCR 94 50
. _ , . _ _ . ~ _ _ . . _ _ _ . . _ . ,
Page 69 of 100 4113'97
SRO EXAM REVIEW Group i EPE ovenon The "A" traveling water screen has failed due to high differential pressure. The "A" condenser waterbox has been removed from service to clean debris off the inlet tube sheet. An operator verifying valve alignment inadvertantly shuts the "B" waterbox outlet to the vacuum priming tank causing condenser differential pressure to rise. What actions should be taken to prevent turbine damage? A. Continue to monitor condenser differential pressure and manually trip the turb% when this value is greater than 3.5" lig. B. Place the EJ 2A and B condenser hoggers in service to minimize the main condenser difTerential pressure. C. Monitor directional thrust on the main turbine shaft and manually trip the turbine if thrust is excessive. D. Monitor turbine supervisory instrumentation until turbine vibrations exceed the 18 mil setpoint for safe operations, then trip the turbine. Answer: A Justhcabort
- a. CORRECT. OP l-3 and AOP 2 2 direct this action.
b.11ogger operation is insumcient to correct a condenser delta P.
- c. Although some directional thrust will occur on condenser delta P it will be insumcient to generate a turbine trip.
d.- Turbine damage may result if you wait for the 18 mil setpoint to be reached. Queshon Topic:. Cordbons for Rx to on loss of vacuum
!V RO Q SRO K/A Rehng 39/41 CFR#. RO $5 41 (bX4) SRO $$ 43(bX5)
- System; 051 K/A # AA202 !
ELos. MT 010122 - t
Reference:
OP 13, AOP 2-2 i ! Page 70 of 100 4/1347 _J
SRO tiX AM RiiViliW Group 1 EPE Question-During normal at power operations, the letdown monitor (RI.3102) counts are trending upward Chemistry has notified Operations that primary system samples indicate several fuel rods may have failed. Your actions to determine the extent of fuel damage and minimize radiation levels are based on: 1 A. Excessive fission products in the reactor coolant system which may inhibit the heat transfer surfaces in both the S'G and reactor core. B. Protection of the health and safety of the public per 10 CFR 100 in the event of a steam generator tube rupture.
, C. Protective action guidelines per the Emergency plan that are required to be pre-scripted during a fuel failure scenario in the event of evacuation.
D. Known limitations with the current radiation monitoring circuitry to effectively chart increases in RCS activity. Answer. B JustAcation
- a. There are m adverse consequences on heat transfer due to high FPA.
- b. CORRECT. RCS activity is a concern because of release during a SGTR.
- c. PAG's are based on projected' actual measurements after an accident has occurred.
- d. Independent analysis by chemistry will always verify current RMS activity indications.
. . . . . _ _ _ _ . . _ . . _ _ _ . . . _ . _ _ _ _ _ _ _ _ _ . _ _ . _.._ _ . __ ~ _ . . _ _ _ _ .
Question Topic: Conective actions for fission product actwny
v RO 'y SRO K/A Ratng 2 9/3 6 CFR*. RO $5 41 (b)(12) SRO Ss 43(b)(4)
System 076 K/A 8. AK3 05
; ELos. EAS-09034. 540 03041; AD-0102-8 Reference AOP 2-25 i
Page 71 of 100 4/13'97
SRO IIXAM RIIViliW Group 1 EPE oocaton Main steam line vents (MS-48,68, and 8%) are listed in Technical Specification 3.11,
" Containment," as exceptions for containment integrity manual valves. These valves are allowed to be opened when RCS temperature is greater than 210 F. What is the basis for allowing these valves to be opened?
A. These valves can be cycled open frequently during plant operations. B. These valves can be opened during heatup for several hours when the RCS is between 210 F and 300 F. C. These valves can be opened to provide vacuum assist to the non return valves during plant cooldown. D. These valves can be cycled open briefly during steam line warmup to blowdown the steam traps. Answer. B Justfication
- a. These valves are not cycled l b. CORRECT, These valves allow for adequate venting of the steam lines.
- c. These valves do not assist the non-return valves.
- d. These valves are not used when blowing down the steam traps.
Question Topic Isolation vatie conttol for contanment mtegrity E RO y SRO K/A Rating 35/37 CFRs. SRO 55 43(b)(2)
- System 069 K/A W. AA101 j ELOW. C 010113. MS440111 l I ;
Reference:
TS 3.11 B (Bass) l i I L 1 l Page 72 of 100 4114/97 l l
_ . - . _ - . _._. _ _ - - - - _ ~ . _ _ _ _ _ - - - - . SRO EXAM REVIEW Groun 1 EPE ouesteon-During a fue, the PSS mans the alternate shutdown panel (ASP) and proceeds to gain control of equipment necessary to minimire loss of RCS inventory. Which components must be controlled to stop RCS leakage? A. Drain heawr isolation valve (DR M 3) to "CLOSE"; EFCVs (MS 11,22, and 33) to "CLOSE"; ) letdown temperature control valve (LD-T 5) to "CLOSE " l B. Drain header control valve (DR A-6) to "CLOSE"; letdown temperature control valve (LD A-
- 68) to "CLOSE"; RCP seal water return valves (SL M. 29,40 and S I) to "CLOSE "
C. Drain header isolation valve (DR-M 3) to "CLOSE"; letdown temperature control valve (LD A-
- 68) to "CLOSE"; RCP seal water return valves (SL M- 29,40 and 51) to "CLOSE."
D. Drain header control valve (DR A-6) to "CLOSE"; letdown temperature control valve (LD T 5) to "CLOSE"; RCP seal water return valves (SL M 29,40, and 51) to "CLOSE." i Answer: D Justkatiort
- a. EFCVs are not used to control RCS inventory loss on an Appendix 'R' fire. Switches are used to i prevent the EFCVs from failing open.
- b. The seal water return valves require alternate power via MCC 981.
- c. DR M 3 and LD A-68 are not controlled at the ASP, although they perform similar functions as DR A 6 and LD T 5. ,
- d. CORRECT. The seal return valves require ASP supplied power in order to shut the valve at the ASP.
l ^ I .Ouestion Topic: Austkary shutdown panellayout ' y RO Q SRO X/A Rating 3 9,4.0 CFR#. RO 55 41(bX4) SRO s5 43(bX5) { l i System: 068 K/A W. AK2 01 f ELos. APPR-01014
Reference:
STM Chapter 34; AOP 2 90-1 i i i i a + Page 73 of 100 4/13/97
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SRO 13AM REviliW Group 1 EPE Question The plant is in a cooldown using AOP 2 90 8," Plant Cooldown From Alternate Shutdown Panel" Several times in this procedure the operator is cautioned that the RCS cold shutdown Imron l concentration is not reached unless pressurizer level is increased to 8096 at some point during the cooldown. Why must the pressurizer be filled to this level? A. Pressurizer level instrument (LI 106) on the ASP is hot calibrated,8096 PZR level ensures that the PZR will have a bubble during the cooldown. B This guarantees adequate shutdown margin is achieved for the cold shutdown condition by ) ensuring sufficient RWST water is injected into the RCS. I C This ensures the cold shutdown boron concentration listed in the TDB, even with rods fully withdrawn, is achieved D. This ensures adequate RCS volume in the event that normal power cannot be restored and a seal water return MOV does not close. Answer, H Justification. a Lt.106 is a hot calibrated instrument. It will read somewhat inaccurately during the cooldown but basis for 80% is baron concentration. b CORRECT. 80% PZR level ensures adequate boron is injected.
- c. The rods being fully withdrawn are not included when cooling down in this condition
- d. While RCS volume considerations must be taken into account if a seal return MOV does not close the PZR level, requirements are based on boron concentration Question 1opic: Acbons for fue onssteMy acheve 80% prr levet V RO V SRO KlA Rating 33/4.1 CFR8. RO $$ 41 (b)(10) SRO 55 43 (b)(5)
System 067 K!A 8 AK3 04 ELOW. EAS-0150-4 ~ Reference AOP 2 90-6 Page 7e of 100 4/13/97
I SRO liX AM RiiVil!W Groun i EPE Ountion A fire in the protected cable tray room (AOP 2 901) has spread into the control room ceiling and an evacuation of the control room is imminent. A station blackout must be created by the operator: A. In order to prevent spurious PORV operation when de energizing MCC 7A and 8A.
- 13. In order to prevent overloaded diesels because 3T5 and 4T6 will fail closed C. Due to the inability to control systems that may be operating.
D. Due to the inability to cool key plant components, such as RCP's. Answer. D Just)feCabon
- a. Spurious PORV actuation is a major concern, but they are not powered from these MCC's.
- b. 3T5 and 4T6 do not fail closed on a station blackout..
- c. CORRECT. Control of operating systems is the major concern.
- d. The RCPs would be secured in this condition.
Ounbon Topic: %tal equipment and control sptems mantained V RO y SRO K/A Rating 33!40 cFR* RO $$ 41(b)(10) SRO 65 43 (b)(b) System 067 K/A W. AA216 ELO# AD-0102 6
Reference:
AOP 2 90-1 wa 4r -.es.e-m-+-we a-. e . r- ' *,4 *- *'+m+ +e +- * --%.-- " " - ' - Page 75 of 100 4 't 3'97
~. - .-._-~ - -.- . - - --- __---.-- ._ - 6 I SRO EXAM REVil!W i Group 1 EPE l' ouesuon A liquid waste release lineup is in progress for the "A" test tank. While verifying the liquid waste [ monitor response (RM 3801), the Operator informs you that ;he channel is not responding to the check source. What is your response as Shill Supervisor? : A. Declare RM 3801 inoperable; perform a double verincation of the valve lineup; then release I the test tank. ; P
- 13. Attempt to identify the cause of the instrument response using 1 & C and maintenance assistance.
i F ! C. Determine that the waste effluent valve (WD F 311) closes when RM 3801 alarms (by ; adjusting the setpoint down), then release the test tank. ;
- D. Verify that the service water radiation monitor (RM 1601)is in service and lower the alarm
! setpoint to within 10% of background per the ODCM, then release the test tank. l Answer 13 l Justf cation:
- a. With RM 3801 OOS, numerous additional checks are required to prevent exceeding release !
limits ,
- b. CORRECT. At this point every effort should be made to fix the instrument. If RM 3801 were bypassed, it would require additional sampling and recirculation.
f
- c. Esen though WD F 311 responds,it is because the Operator has lowered the setpoint, not because the instrument works. .
- d. At no point are you allowed to substitute radiation monitors during a liquid release. ODCM ,
speciDes requirements for sampling and monitoring with RM 3801 OOS. Queshon Topic Fahne modes during hquid release (SRO only)
'RO y SRO KIA Rahng 3.1/36 CFR#, SRO SS 43 (b)(4)
System: 059 KIA #: AA2 03 ELOW SNO-03041 i
Reference:
OP 119-3; AOP 2 2s l f.'
- i i
l l l i 4
- Page 76 of 100 4/13/97
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SRO !!X AM RlWiliW I Group 1 EPF. Question While moving a spent fuel pool rack with the overhead crane, the rack drops and breaks open several spent fuel assemblies in the spent fuel pool. It is raining quite heavily at the time of the accident and several local roads, including plant access, are inaccessible. As the PSS in charge of making protective action recommendations (PAR's), what are your initial concerns regarding the health and safety of the public? A. The ingestion exposure pathway is the initial concern, as the radioactive gases wash into Montsweag Bay and are absorbed in the food chain. It The plume exposure pathway is the initial concern because the precipitation will concentrate the radiation at ground level and result in external and inhalation dose. C. The site exposure pathaay is the initial concern because the unshielded portion of the yard becomes a point source for radiation and could exceed 10 CFR 100 limits at the site boundary. D. The plant exposure pathway is the initial concern because the radioactive material will be concentrated in a small unisolated area of the plant. Answer B Justirication. a The ingstion exposure pathway becomes a c6ncern aner the plume has deposited the radioactive material.
- b. CORRECT Any time precipitation is occurring during a release it tends to concentrate.
- c. The possibility for exceeding 10 CFR 100 limits is a concern because of the close proximity to tidal boundaries, however, no site exposure p'thway exists.
- d. There is no plant exposure pathway, although the most susceptible personnel are the guards and auxiliary operators Ouestion Topic. Implement E. Plan for hquid red telease (SRO only) g_' RO y SRO K/A Rating 3 2/4.5 CFRs SRO 55 43(b)(4) l System: 059 K/A 8. AK3 02 IELos EP. PAR-010102
. Reference. EP. PAR 01, Protectwe Action Recommendations
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Page 77 of 100 4/13197
l l l
%RO l'.XAM RiiViliW Group i EPE Ouette With 120 VAC vital buses I and 4 cross-connected and powered from inverter 1 (the sptre inverter is out of service) inverter i fails causing a loss of both buses The reactor operator places the "B" train PORY (PR S 15)in the " CLOSED" position. The valve indicates closed, but the acoustic accelerometer is still in alarm. What method is used to iso've the PORV7 A. Take the "B" train PORY block valve (PR M 17) to"CLOSE" and retum the PORV (PR S 15) switch to "OFF."
B. Take the "B" train "11PSR/VPSR" switch to "VPSR" and raise the setpoint to 2400 psig to close the PORV. C. Take the "B" train PORV block valve (PR M 17) to "CLOSE" and then open the PR M 17 breaker on MCC 8B D. Take the "B" train *llPSR/VPSR" switch to "IIPSR" and raise the setpoint to 2400 psig to close the PORV. Answer. C Just$fication-a The block valve and PORY will both re open in this scenario. l b Going to VPSR has no effect on the PORV. The train "A" PORY will stay shut due to loss of LTOP channel "A."
- c. CORRECT This switch spring returns to " AUTO." therefore, its power supply must be de-energized when the valve is closed.
d Going to 11PSR has no effect on the PORY. Question Topic: Auto actions on loss of vital AC/PORV opens V PO 's SRO KtA Ratng 3 6!3 9 CFR8 RO 55 41 (b)(7) SRO 55 43 (b)(5) System.157 K/A 8. AA2.20 i ELos AC-010124. PPC 01012. 5 and 8 Reference AOP 214 (Sect on 5 6). STM Chaptet 3 Page 78 of 100 t/13'97
SRO liXAM RiiVlliW Group i EPE Ouestion The plant has experienced a loss of two 120 VAC vital buses (vital buses 2 and 3). Emergency feed water control must h established in the Control Room. What is the proper sequence for re-establishing EFW flow to avoid water hammer damage? A. Close EFW valve controllers, bypass feed train trip signal, place main feed, condensate and heater drain pumps in PTL, verify EFW pump operating, throttle open EFW flow control valves. B. Bypass feed train trip signal, close EFW valve controllers, place main feed, condensate and beater drain pumps in PTL, verify EFW pump operating, throttle open EFW flow control vahes. C. Place main fe.d, condensate and heater drain pumps in PTL, bypass feed train trip signal, close EFW valve controllers, s erify EFW pump operating, throttle open EFW flow control valves 11 Place main feeJ, condensate and heater drain pumps in PTL, close EFW valve controllers, bypass feed train trip signal, verify EFW pump operating, throttle open EFW llow contrci; valves Answer D Justification a Bypassing feed train trip (FTT) before putting pumps in PTL causes feed system transient,
- b. Hypassing feed train trip (FTT) bcfore putting pumps in PTL causes feed system transient
- c. Bypassing FTT before closing EFW valves causes feed system transient.
d CORRECT This is the sequence required to prevent damage to the system. Question Topic lAanual contiol of components losing auto contiol RO y SRO KlA Rating 3 $!3 $ CFRW SRO 55 43(b)(5) System 057 K/A 8 AA1.00 ELOS AFW-0902 3, MFW OiO15 & 6.AFW 010114.PPfA 010114 Refetence AOP 214 Page 79 of 100 4/1347
- m. _ . .. _
l SRO EX AM REViliW i Grous 1 EPE A total loss of all AC power has occurred and the operating crew has entered ECA 0.0, "less of All AC Power " The secondary side NPO reports that DG 1 A is running, but control room attempts to close the DG 1 A breaker have failed. Which statement describes the next operator action that should be performed? A. Attempt to close the DG 1 A breaker at the breaker, i B. Immediately start PCC and service water pumps. l C. Provide an alternate source of cooling water to DG 1 A. i
- D. Secure DG l A until cause of breaker failure is determined.
Answer: C JustAcabort
- a. This action is desirable, but ahernate cooling must be established first.
- b. Pumps cannot be started until breaker is closed.
I i
- c. CORRECT. Establish cooling then u. tempt to close the breaker.
- d. Undesirable to secure a DG when a loss of offsite power has occurred.
Question Topec Actions in EOP for loss of oftaste PWR. diesel breaker closure
.1 RO 'p, SRO KIA Rating 4.3/4 6 CFR#, SRO $s 43(b)($)
- System 0$$ KIA #. EK3 02 Elos. EAS-01017 Reference. ECA-D 0 Caubon Step 6 Page 80 of 100 4/13/97
SRO I!X AM Rl!ViliW Group i EPE Quesbon While in FR C.1," inadequate Core Cooling," the Operator notes LPSI now oscillations when running a containment spray pump and a LPSI pump from the same safeguards sump. Assuming adequate water level in containment and the desire to run the LPSI pump during RAS to avoid inadequate core cooling, what action in the Control Room would mitigate LPSI pump cavitation in this condition? A. Reset the RAS signal, throttle LSI M ll,21, and 31 (LPSI loop stops), monitor pump amps, and discharge preasure. l B. Reset the SIAS signal, throttle LSI F 59 (R11R Dow control), monitor pump amps, and discharge pressure. C. Reset the RAS signal, throttle LSl F 59 (RllR 00,v control), monitor pump amps, and discharge pressure. D Reset the SIAS signal, throttle LSl M ll,21, and 31 (LPSI loop stops), monitor pump amps, and discharge pressure Answer. D Jushfication
- a. While resetting, the RAS signal has no deliterious effects on the system. You will be unable to throttle LPSI How.
- b. Throttling LSI F 59 cannot be accomplished unless several other barriers are removed (i.e., must leave Control Room ).
- c. Throttling LSI F-59 will help the cavitation condition, but must be put into service from outside the Control Room.
- d. CORRECT. The SIAS signal must be reset to throttle LSI M ll,21, and 31. This will allow continuous 1. PSI How without challenging NPSil requirements.
Question Topic Inteneta*;onstup between madeq coorLPSI pps
@ RO y SRO K/A Rating 3 9'41 CFRs RO $$ 41 (b)(10) Sr 3 55 43 (b)(5)
< Sys'em: 0'4
, KIA
- EK2 05 i ELO8. ECCS 010117 ECCS-0902-1
! Refercace. FR C.1 BKGD Document (Step 2)
L _. _ _.___ _ _. _ . __ . _ . . _ _ _ _ . _ _ - . . . _ _ _ . _ . _ _. _ __ _ _ . . _ _ Page b1 of 100 4/1397
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7_____._..____ 4 j $RO EXAM REViliW Group 2 EPE j l
- Question- l 1
i The VCT vent valve (PV A 2) fails to close following routine burping of the VCT, Both waste gas l 4 compressors (C-3A & 3B) are out of service. Identify the group of radiation monitors that follon j the flowpath of radioactive gas to atmosphere, t 4 A. From the high range PVS gas monitor (RM 3903) to PVS gas monitor (RM 3902Y), to . Service Building ventilation exhaust (RM 6101). i f B From the waste gas monitor (RM 3901), to PVS particulate monitor (RM 3902X), to PV5 gas j monitor (RM 3902Y). i C. From the Service Building ventilation exhaust (RM-6101), to PVS particulate monitor (RM- i 3902X), to waste gas monitor (RM 3901). I ! D. From the PVS gas monitor (RM3902Y), to high range PVS gas monitor (RM 3903), to PVS l particulate monitor (RM 3902X). Answer: D- . Justification i a. The seal pot blows out and bypasses the Service Building. 1 i ! ! b, The Waste Ga. monitor will not see these gases. l 1 I c. Service Building will not see these gases unless a leak exists. l 1 ] d. CORRECT. This is the flowpath of gases. The loop seal vents directly to the PVS. 1 j -.. _ - - - . - . _ _ - - - _ _ _ _ . ..-__. __. m__-. . . -. _ _ _ _..___.. .. ...._m.._-. Question Topic: Gas release & ventdation alignment dunng VCT burping j f RO y SRO K/A Rating 2.7/31 CFRs SRO 55 43(b)(4)
^ System. 060 KIA # AK2 02 ELos RMS 01012, RMS 0902 3
{ , , I Reference. STM Chapter 20 (Table 20-2) l P l Page 82 of 100 44347
SRO EXAM Rl!ViliW Group 2 EPE Question. The reactor is cooling down with the "A" RiiR pump and the "A" RilR heat exchanger in service. The "B" RiiR pump and the *B" RiiR heat exchanger are operable and in standby. The RCS is not yet adequately vented per OP l 7," Plant Cooldown " PORV "A" VPSR setpoint fails high. The "A" train PORV (PS-S 14)immediately opens. What action is required? l A. Shut PR M 16, determine the cause of the PORV opening and align the RWST to the RHR ! pump to compensate for lost inventory. B. Shut PR M-16, start the "B" train RiiR pump (P 128) and align SCC to E 3B in order to maintain core cooling
)
C. Shut PR M 16, stop P 12A because Ril M 1 closes, then align an alternate nowpath for core cooling D. Shut PR-M 16, open Ril T 12 and LSI F 59 to the full open position to facilitate venting of R11R piping and valves to RCS Answer. C Justification a The PORV opens due to t.xceeding the VPSR setpoint. Adding inventory is not a concern at this time. -
- b. Starting the B pump will only exacerbate the problem as a loss of suction is in progress.
- c. CORRECT. When PIC-103 fails high, RH M 1 will auto close at 585 psig An alternate Howpath must be immediately aligned.
- d. Opening LSI F 59 and Ril T-12 could result in excessive cooldown rate and under no condition vents the RilR piping.
Ouestion Topic: Shifung to atternate flowpath for RHR ' V RO y SRO KIA Rabng 31/3 4 CFR8 RO $5 41 (b)(7) SRO 55 43 (bX5) System 025 K/A 8. AK3 01
- ELoe, ISR-03013. RHR-01015; PPC-0902 2
Reference:
AOP 2 34; STM Chapter 3 _ . - _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ _ . _ . _ . ~ . - . . _ _ - - . - -- Page 83 of 100 4/11'97
l SRO liX AM REvil!W l Group 2 EPE I Quest,on' During the feed and bleed termination sequence of FR.H.1," Loss of Secondary lleat Sink," three steps must be completed: 1.) Throttling ofIIPSI flow (<l50 gpm); 2 ) Checking RCS status (SMM. PZR level) and; 3.) Isolating the bleed paths (closing PORVs) Why is 11 PSI flow throttled i during the termination sequence? A. To ensure 11 PSI flow is adequate to remove decay heat even without a steam generator available. 11 IfilPSI flow cannot be throttled the operator would be required to exit FR li. I and enter E 3,
" Steam Generator Tube Rupture "
C. With HPSI flow throttled to <l50 gpm, the normal charging flow path will be able to meet RCS inventory requirements. D. Because the PORVs must be closed before the operator can exit FR li i in the es ent of a suberiticality or core cooling red path. Answer. C Justituation a You would be unable to exit FR H.1 unless one S/0 was established with level >41% (52'6).
- b. IfIIPSI flow cannot be thf ottled, the operator may be required to enter E 1," Loss of Primary or Secondary Coolant."
- c. CORRECT. Eventually core decay heat is low enough to allow restoration of normal charging and letdown.
- d. This violates rules of~ usage for FRP's. The operator may exit any time a higher priority CSF is met Ouestion topic: FCCS termnateorwwotthng entens y RO ~y SRO K/ \ Rating 4 0/4 5 CFRs RO $$ 41 (b)(10) SRO 55 43(b)(5)
System 008 K/A W. AK3 05 ELOS. EAS-01017 Reference. FR-H 1 eKGD Document (Step 25) 4 Page 84 of 100 4t13/97
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SRO EXAM REVIEW Group 2 EPE Ouecon The following conditions exist during a refueling outage with the plant in Condition 3, Cold Shutdown: The RCS is at the refueling boron concentration; The "A" diesel generator (DG l A)is tagged out Dr maintenance; The RilR pumps are available, but isolated for recirculation tests; X 16 is tagged out for verification of transfonner taps; Pressurizer level is 85% Chemistry and operations have decided to reduce the RCS boron concentration to the cold shutdown requirement. What actions are required before reducing RCS boron concentration? A The charging pump (P-14B) must be aligned to the RCS and providing a minimum 150 ppm , now of barated water. B Place letdown in service with a minimum 40 gpm Dow. C. X 16 must be aligned to a 6900 volt bus and an RCP started. D. An R11R pump must be aligned to the RCS providing a minimum 2000 gpm Dow. ADSWef h Justification a A boration Oow path must be established but is not required to be in operation
- b. This is not a requirement to reduce RCS boron concentration.
- c. Boron concentration cannot be reduced unless an RCP is in operation but the pressuriter must be ch0% level d CORRECT. Boron concentration cannot be reduced unless an RilR pump is in operation at a minimum now of 2000 gpm.
Ouestion Topec: Knowledge of LCO's and safety hmits l I/ RO p SRO K/A Rating 3 4/4.1 CFR# RO 5$ 41 (b)(6) SRO 55 43(b)(2) System Genenc KIA W 2222 ELO#. RCP-09021
Reference:
TS 3 3A & 3 4.0
. - . _ _ . _ _ _ _ _ . _ _ _ . . _ . . . _ _ _ _ . . _ _ _ _ _ _ _ . _ _ . . . ~ . . . __
i Page 85 of 100 4/1397 m -
SRO EX AM RiiVltiW Group 2 EPE Queshon . Reactor trip breaker positions are shown on the attached drawing. Which statement identifies the most likely result if TCB 2 and TCB 6 are immediately reclosed? A. The reactor trips due to loss of power to the output AC contactors. B. The reactor remains operating due to redundant CEDM power supplies. C. The reactor trips due to improper paralleling of MO sets. D. The reactor remains operating due to automatic sychronization. Answer: C Jusbficabon a Power is not lost to the CEDM buses until the lack of synchronization.
- b. The reactor will trip due to paralleling out of phase.
- c. CORRECT. The MG sets must be paralleled across the tie breaker.
- d. There is no auto synchronization of these buses.
.Questvan Topic: RA tnp status panel, parellehng out of phase 9 RO y SRO K!A Rating 3 $/3 6 CFR#. RO $$ 41 (b)(7) SRO $$ 43(b)(5)&(6) I System 007 K/A W EK2 03 , ELO8. CEDS 01014. 01016. 01014
- Reference. OP 122 7 (Attachment A) STM Chapter 11 (F6g 11 16)
Page 86 of 100 4/13197
CEDM POWER SUPPLY BUS-9 BUS 12 8 o
- IAANUALINPUT -
N ACINTERRUPTERS AOTOR GE JER . TOR 4 240 VAC .37 : o MANUAL Mco.1 - OUTPUT CKT BREAKER ' M0s.2 - I OUTPUT , Och Aff0NTACTORS J s
) aus m
__ .. d _ _ - - _ _ i M 4 VAL
._ _ _ _ . M --
g-B@@t(fA CLOffD O-B W L " " ~ o T FROM .TB 7 - - - - F od p O 3 \ U 8 .
/ B TC , __s 1i l
INDfVIDUAL CEDM CEDM ' INDMDUA CEDM Pk$RADMESS CONTROL SYSTEM ph$[NE S i I
, i _ _ - .
, . .k . . , k r---,
CEDM I CEDM g CEDM CEDM _J CEDM r- CEDM ColLS COILS COILS ColLS ColLS
- i. ColLS.. J --- J CEDM 1 3/26/96 R O-L 4.4 AO.L-4.1
m - _ _ . . . _ _ _ . _ _ _ _ _ . - _ . _ _ _ _ _ _ _ _ . . _ _ _ . _ __ _.m SRO EXAM REVIEW , 9foun 2 EPE ] ouestm . Your crew is performing actions during a small break LOCA. You have transitioned from E-0,
" Reactor Trip or Safety injection," to E 1, " Loss of Primary or Secondary Coolant," and are <
checking to see if HPSI How should be : educed. Several parameters, such as core region subcooling, secondary heat sink, pressurizer pressure and level must be satis 0ed. If you were_ to misdiagnose secondary heat sink availability and entered ES 1.1,"Si Termination," how could this ;
- effect your recovery actions? ;
A. Because HPSI now could be maintaining core region subcooling, when How is reduced the lack of heat removal could require reinitiation of the HPSI now. B Because core region subcooling is the most direct indication that core cooling is being maintained, it is unlikely that the recovery actions will be inhibited by inadequate heat sink. C. Because pressurizer RCS pressure and level are satisned, the break size is such that in reduced ; llPSI How conditions, there will always be sumcient RCS inventory for core cooling D. Because llPSI now could be maintaining core region subcooling, when How is reduced the : lack of heat removal could require entry into FR C.1, " Inadequate Core Cooling " Answer. A Justification
- a. CORRECT. All four (4) criteria must be met or llPSI How cannot be reduced.
- b. While it is true that subcooling is the most direct indication of heat removal, it is about to be reduced and, therefore, may require reinitiation.
- c. Inventory alone is not a sufficient measure of adequate core cooling.
- d. Although this is a possibility, the reinitiation of HPSI How would be sufficient to restore core cooling and only a boni0ed loss of heat sink would require entry into FR li.1, and not FR-C.l.
- Que y , opt Actions for smat break i.OCA -
; V Rc, y SRO K/A Ratog 4 2/4.6 CFRs RO $5 41(b)(10) SRO $$ 43(b)(5)
; Syr'em: Q9 KIA # EK3 21
! ELof. EAS-0903-1; EAS.01017 Reference. E 1 BKGD Document (Step 6) i J
t Page 87 of 100 4/13'97
. _ _ , . . . _ _ . _ . _ _ . - _ _ ~ _ _ . - . . . _ _ _ . . _ . . _ _ _ . . . _ . . _ _ _ . _ _ .- , _ . . . - - . . _ . .
SRO EXAM REVIEW l Group 2 EPE l Quesbon The plant has experienced a small break LOCA and containment pressure has stabilized at 6.5 psig. The ECCS lightbox indication for PCC-M 219 shows BOTil the blue and green lights flashing. A check of PCC M 219 on the MCB shows both the red and green valve position lights lit. In this condition PCC M 219 is: A. Completing its closure stroke and will indicate a green " closed" light in a few moments. B. Completing its opening stroke and will indicate a red "open" light in a few moments. C. Without AC control power due to inadvertant opening of the MCC-78 supply breaker. D. Tripped on overload and may require manual actions to close the valve. Answer. D Jushfcabon. a Only the green ECCS light would be 11 ashing in this condition. b PCC M 219 closes on a CIS to isolate PCC to containment.
- c. If AC control power was NOT available, the MCB indicating lights would be out.
- d. CORidCT. MOV overload is indicated by both lights flashing MCB indicating lights lit.
. _ . _ _ _ . . . _ . . . _ = . _
Ouesbon Topic: Containment isolabon system. PCC-M-219 loss of power
. V RO Q SRO K/A Rabng 4 0/4.1 CFRs RO $5 41 (b)(7) SRO $s 43(b)($)
- System 009 K/A S. EA1.08 ELos ESF-01013 Reference. STM Chapter G l
1 i Page 68 of 100 4/13/97 I l
l l SRO liX AM Rl! VIEW Group 2 EPE Queste An operator has been sent to the lower level PAB to start the auxiliary charging pump (P-7) during a control room evacuation. The pump was aligned as follows:
- The speed control lever is set on the lowest speed;
- The pump is running with no abnonnal noises with the RCS at nonnal operating pressure and ,
temperature. The PSS at the ASP notes that PZR level has not increased for 15 (fifteen) minutes. What is the cause of this problem? A. The alternate cooler for P 7 was not aligned and the hydraulic oil is overheating. B. The setpoint on Cil P 156 needs to be adjusted to 2335 psig. C. The speed control neeb to be adjusted to the high speed setting. D. The RCS must be depressurized using the atmospheric steam dump before a level increase will be seen Answer: B Justification.
- a. If P-7 alternate cooler was not aligned, the pump would fail when the hydraulic Guid overheated.
- b. CORRECT. This setpoint is too low for the current RCS pressure.
- c. Although this is required by procedure, the minimum setting will still pump 10 gpm into the RCS.
d Depressurization will help inject Guid, but is not required in this situation. lV R R A ating 4/3.3 CFR8. RO $5 41(b) SRO 55 43(b) System: 022 K/A s. AA101 l ELOt. CVCS-0102 8 & 9 l
Reference:
AOP 2 901 (Attachment D) L _ - . . _ . _ _ _ - . _ . . . _ _ . _ . . . _ _. _ . _ . _ . _ . _ - . _ . _ . - . . . . _ _ , . , _ . _ . Page 89 of 100 4/13S7
-_ _ __ -_ _ - - - .- . .._.~- .- -. - _. _ . _ - _ _ _ - . -. . _ _
SRO EXAM REVIEW Group 2 EPE Questeon The reactor is on an RHR cooldown with the RCS at 150 F and 200 psig. Several trash rack and traveling water screen differential pressure alarms are received while at low tide. The AO reports L rge quantities of debris in front of the trash racks and the service water pump amps and discharge pressures are oscillating. Both PCC and SCC temperatures are rising. There is no firm estimate of the time it will take to restore service water, in this condition the operator will: A. Align firemain hoses to the PCC and SCC heat exchangers to maintain RCS temperature until service water is restored.
~
B. Prepare a steam generator heat removal loop for operation and allow the RCS to heat up to allow dumping steam. C. Align the charging pump to the RWST and windmill water through the I. PSI pump and RHR heat exchangers with RWST as heat sink. D. Align the NRV vacuum assist and bleed steam to the condenser until service water is restored Antwef . O Justification
- a. Although this can be accomplished, there are no studies documenting adequate heat remos.al using this method.
b CORRECT. With a loss of the ultimate heat sink (service water) the next option includes alignment of a steam generator as the heat sink.
- c. This method can be used when the RHR pumps are lost, but ultimately requires PCC/ SCC for heat removal d Loss of service water also implies loss of circulating water, therefore, this would not be an option.
Question Top +c: Loss of RHR dump a cooldown due to service water [ RO y SRO KIA Rating 3 9/4.3 CFR#. SRO 55 43(b)(5) System 025 K/A W. AK101
.ELO#: ISR 0301-3 r
Reference:
AOP 2 34 l Page 90 of 100 4'13/97
SRO EXAM REVIEW t Group 2 EPE oue. bon.
- The reactor is being started up following an extended refueling outage, The fission chambers swap from CPS to % PWR at 1000 cps and 10-6% power respectivr.ly. If the reactor must be shut down after critical rod data is obtained, what relationship exists between CPS and % PWR indication as the reactor enters the source range?
A. Counts per second (eps) and % power have no relationship because of the number of detectors used by the source and wide range instruments. B. Counts per second (eps) and % power are inversely related, that is 10-6% power equals 1000
- cps; 10-7% power equals 10,000 cps, etc. ,
C. Counts per second (cps) and % power are directly related, that is,10-6% power equals 1000 l' cps; 10 7% power equals 100 cps, etc, D, Counts per second (cps) and % power are inversely related, that is,10 6% power equals 1000 .
- cps; 10 7% power equals 100 cps, etc.
Answer: .C Justificebon-l l a. There is a direct relationship between source and wide range readings. - l
- b. As count rate decreases so does the value of % power.
- c. CORRECT. There is a direct correlation between % power and CPS.
- d. This is a oirect, not an inverse, re'ationship.
.- .. . . . ~ ~ - - . . .
-- . - . . - - . . - ~ . . . . . - ,
Cuestion Topic. Overtap of source to wide range Nrs jV RO V SRO K/A Rating 3.1/3 5 CFR# RO $5 41(b)(6) SRO ss 43(b)(6) System: 032 - K/A #. AA2 04
! ELO#, NI-01013, NI-0101 13
(
Reference:
STM Chapter 14 (Secbon 2.1) a } 4 1 i ! Page 91 of 100 4/13/97
. _ ~ ,, ,,... - ,,.. _ _ _... - - .._ .,,_..,, _ . _ ... _ _,._ _ ,.,,....,.. _. _ ,__.._ , . _.._ . ,.. - . _ _ _,- . . . _ . . . . -
SRO EXAM REVIEW Group 2 EPE Ouesbert A #3 steam generator tube rupture is in progress and the plant has been cooled and depressurized to minimize RCS flow into #3 S/G. At th' . time, the operator is required to check #3 S/G pressure to determine ifit is stable or increasing. It is determined that the ruptured steam generator is continuing to lose pressure and c,:. mot be maintained 250 psig greater than the intact S/G's. Why is the ruptured S/G pressure continuing to decrease? A. #3 S!G has multiple tube ruptures which is causing pressure in the S/G to decrease. B. The intact S/G's were overcooled and the high pressure in #3 S/G is backfeeding into the RCS. C. When safety injection was blocked in the preceding steps, the operator did not maintain RCS temperature stable. D #3 S/G is also undergoing a steam or feedline break (fauhed). Answer. D AtttJficallor1 1 a This condition will not cause #3 S G to continue its depressurization. , b. It is impossible to overcool the intact S'O in this situation #3 S/G is faulted and that is why it continues to depressurire.
- c. Maintaining RCS temperature will only afTect subcooling requirements and temperature necessary to terminate cooldown.
l d. CORRECT. You must exit E-3 (Step 23) and go to ECA 3.1. Question Tope. Achons in EOP's for SGTR
' V RO V SRO KiA Rating 4 2/4 4 CFR8 RO $5 41 (b)(10) SRO $5 43(b)(5) i System 037 K/A 8 AK3 07
! ELOs. EAS 01017 Refererxe: E 3 BKGD Document (Step 23) 7 1
.i.e.-w.,. - - - .=w .+--e-m_-.e-.--w.--. + - - -- mee. --- - - + . - * - - - - - - ---m -
Page 92 of 100 4/13'97 1
SRO EXAM REVIEW , Group 2 EPE Ouestion An operator controlled cooldown (with an RCP running) has been initiated during a steam generator tube rupture by dumping steam at the maximum rate to the main condenser. RCS depressurization is also occuring and resulti in a core region subcooling reading of 10 F. What action should be taken at this time? A. Stop the cooldown and restore subcooled margin before continuing. B. Continue the operator controlled cooldown and keep the RCP running. C. The RCP should be tripped on low core region subcooling as long as one charging 41 PSI pump is in sen' ice . D. Stop RCS depressurization to restore subcooled margin before continuing. Ar.swer: B Just:fcanon
- a. You are not required to secure an operator controlled cooldown.
b CORRECT. The RCP should be kept running despite the loss of SCM. They do not apply once a cooldown is initiated
- c. This is only required during small break LOCA's in order to meet Appendix K criteria
- d. This would increase the primary to secondm leak and is unacceptable.
Question Topic RCP testart cinena RO y SRO K!A Rating 3 B/4 4 CFRs. SRO 55 43(b)(5) System: 038 K'A # EA217 E L .,* EAS-01017 Reference. E 3 BKGD Document (Step 1)
..-. . - - . - - . - - . . . - - . . . - - , - . - - - - - - - . - - - - - - . - . . . . - . - . . ~ . _ - . ..
Page 93 of 100 4/13/97 l l l .- . - .. .
SRO EXAM REVIEW Group 2 EPE ovestion: l l The plant has tripped on a main steam header rupture in the turbine hall. The EFCVs have closed and steam generator pressures are hovering around 400 psig. What must be doa ' 3 open the EFW l [ butterfly valves? i A. Place the excess flow check valves in the
- CLOSED" position.
LA Place the EFW-A-338,339, and 340 " NORMAL > ALTERNATE" T-switch in the EFW pump room to " ALTERNATE." C. Verify adequate instrument air pressure in the receivers in the EFW pump room so that the valves will open. D. " MANUALLY" open the EFW butterfly valves (EFW-A-338,339, and 340) from the EFW pump room. Answer: 8 Ju%fication:
- a. This signal has no eff ect on the EFW valves.
- b. CORRECT. This de-energizes the solenoid and the valves fail open.
- c. The valies are held shut wiib air pressure. A loss of air causes the valves to fail open.
- d. No method is available to manually open these valves.
Quesuon Topic: IfW controls r i ~ " a 6 xsces (EFW-A 338,339. 340) y RO y SRO K/A Rating 6 4 > CFRs. RO 55 41(b)(7) SRO 55 43 (b)(5) System' 054 K/A #. AAt 01 ELO#: AFW-09021 & 2
' Referenca: STM Chapter 28 (Section 3.0), ESK-7GA Page 94 of 100 A/13/97
, - - - - ~_, , . _ _ - . _ _ . ._. _ _ _ . _ .. . _ _. _ _ _. _ . . _ ._.. .. _ . _ ._. 4 9 SRO EXAM REVIEW Group 2 EPE
- Queston During maintenance of battery bus #3 (disconnected from the bus), i loss (.f DC bus #3 occurs (the -
vital AC bus is still available). The plant does not trip. The RO reporis that one PORY (PR-S 15) . and its associated block valve (PR-M-17) are energized and one (1) seI of proportional heaters (E-2PB) are deenergized. Do you concur with the analysis of this situatian? Why? A. Yes, because you verify that the indicating lights for E-2PB are off and the lights for PR-S-15 and PR-M 17 are on. B. No, because if E 2PB has lost its indication, then PR-S-15 and PR-M 17 should also have lost their indications. C. Yes, because PR-S-15 and PR-M-17 retain DC control power on a loss of DC bus #3. D. No, because the proportional heaters have lost indication only. The E 2PB breaker is still closed. Answ; D Justfacaton:
- a. E-2PB lights are off because of a loss of DC control power to bus 8 components.
- b. POS-15 and PR-M-17 are supplied from MCC-8B. Their indication is provided via AC control peo e; of the MCC breaker.
- c. Rese valves are AC control power supplied.
d' CORRECT. The breaker did not reposition on a loss of bus 3. It only lost its indication and control. Queston Tope: Venficabon of loss of DC Bus #3 2 RO p SRO K/A Rahng 3.7/4.1 CFR#-. RO 55.41(b)(10) SRO 55 43(b)(5)
- System: 058 KlA W. AA2 01 ELO#. DC-0902-2;ISR-0303-11; PPC-0101 11; AC-0101 19 -
Reference:
AOP 213 Page 95 of 100 4113/97 l
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t l j' i SRO EXAM REVIEW i. j Group 2 EPE 4 Quenon: l l During routine sampling of the in service waste gas decay tank, the shift chemist reports concern that hydrogen concentration (by volume) is 6% and oxygen concentration (by volume) is 4.5%. i What actions should be tsken upon receipt of this information? s j Ac Verify the waste gas area radiation monitor is reading background and not in alarm; evacuate , personnel from the PAB; immediately stop any additions to the waste gas tank. l 4 B. Immediately suspend additions to the waste gas surge tank; notify the primary AO of problems
- with gas concentration; continue monitoring by chemistry and reduce hydrogen concentration
! when it exceeds 8% (by volume). C. Evacuate personnel from the PAB; suspend additions to the waste gas tank; take immediate ! action to reduce the oxygen concentration to less than 4% (by volume). i l D, Evacuate personnel from the PAB; suspend additions to the waste gas tank; take immediate ! action to reduce the hydrogen concentration to less than 2% (by volume). Answer: C j Justficabon: I
- a. The waste gas monitor is for releases on!y and does not orovide an area radiation indication.
- b. Misconception concerning H2 concentration in the waste gas system, although hydrogen is not-j combustible until greater than 4%, oxygen must be reduced per Technical Specifications. .
i i c. CORRECT. Must immediately reduce oxygen to less than 4% per Technical Specifications. . d. It will be difficult, if not impossible, to reduce the hydrogen concentration in this condition. l Technical Specification 3.17 requires reduction of oxygen. t i Queshon Topic: High 02 concentrabon in decay tank /achons ! ' ' RO y SRO K/A Rahng - 3 5/4 2 CFR#. SRO 55 43(b)(2&4) a- System: 061 K/A # AA2.05 , ELO#: SNO-0303-10
Reference:
TS 3.17.8 , l l l I' l Page 96 of 100 4/13/97 4
SRO EXAM REVIEW i-j Groun 2 EPE ounbon: - I The reactor has tripped from 100% power due to a loss of feedwater, in an effort to restore feed flow to a S/G following a reactor trip, the operator is cautioned in FR-H.1 to verify that blowdown J flow has been secured. Blowdown flow should have been isolated by: A. Automatic action from the diverse scram system (DSS). B. Automatic action on a low S/G level (35%). 1 l C, Automatic action on a diverse turbine trip (DTT).
- D. Automatic action on a low S/G pressure.
Answer. B Justificabon: j a. The diverse scram system does not affect these valves j b. CORRECT. FSAR margin to restart on a SLB was improved by isolating R/D flow. j c. The DTT actuates at 35% S/G level, but is a different signal than that for the B/D valves. i i d. Low S/G pressure isolates normal and emergency feedwater, but does not isolate S/G blowdown. i = Question Topec: Blowdown flow from S/G on RX tnp 5 2 RO y SRO K/A Rabng 3 7/4.1 CFRs. RO 55 41 (b)(10) SRO 55 43 (b)(5) System: 007 K/A s. EK1.06 } l - ELO#. EAS-01017; BD-0101 1 ;
Reference:
FR.H.1 BKGD Document l 1 Page 97 of 100 4/13!97 l l l 1
SRO EXAM REVIEW Group 3 EPE ou aon: You are the Refueling SRO in containment. The refueling crew has grappled a thrice burned
- ^ assembly and stans to withdraw it from the core when several basketball-sized bubbles start to eminate from the vicinity of the grappled assembly. Which actions characterize your initial response as Refueling SRO7 A. Notify the control room, notify radiation controls, stabilize the assembly, have control room >
sound the containment evacuation alarm, evacuate personnel from containment. { i B. Notify the control room, notify radiation controls, initiate the emergency plan (alert), have ! control room sound the containment evacuation alarm, evacuate personnel from containment. j C. Notify the control room, continue withdrawal to ascertain damage, stabilize the assembly, have control room sound the containment evacuation alarm, evacuate personnel from containment. D. Notify the control room, stabilize the assembly, have control room sound the containment i evacuation alarm, evacuate personnel from containment, have res.eling crew ingest potassium j iodide (KI). l- Answer: A j Jushficabon:
- a. CORRECT. This is an appropriate response per AOP 2-35 initial actions.
- b. E-Plan should not be initiated until extent of damage,if any,is known c Should immediately stabilize the assembly.
- d. KI ingestion may not be required as 23 feet of water is designed to remove 90% of elemental iodine.
Question Topic: SRO achons for fuel handling incident O RO p SRO K/A Rating 3.7/4.1 CFR# SRO 55.43(b)(7) System: 036 K/A W. AK3 02 ELos, SE04302 5;EAS-0150-5
Reference:
AOP 2 35 - Page 98 of 100 4/13/97 I J
a SRO EXAM REVIEW Group 3 EPE Oueston-The plant has experienced a total loss of AC power. ECA-0,0, " Total loss of AC Power," has been initiated. Which method will be used to initiate safety injection? A. Place the " BLOCK-AUTO-MANUAL" switch in " MANUAL" to provide auto start of safety injection pumps when power is restored. B. Place all safety injection pumps in " PULL-TO-LOCK" to allow manual start of safety injection - pumps when power is restored. C Place the " BLOCK-AUTO-MANUAL" switch in " BLOCK" to provide manual start of safety injection pumps when power is restored. D. Place all safety injection pumps in " AUTO" to allow for automatic start of safety injection pumps when power is restored. Answer: B Jushficabon:
- a. Auto start of safety injection is undesirable due to excessive loads on the EDO.
- b. CORRECT. Controlled starting of safety injection pumps is required in this condition.
- c. Blocking of safety injection is invalid because system pressure is >l685 psig.
- d. Auto start of safety injection is undesirable due to excessive loads on the EDG.
Question Topic: Manua!Iy initate safety injecuon ! 'E RO y SRO K/A Raung 38/39 CFR8: SRO 55 43(b)(5) ,
- System
- 056 K/A #, AA1.05 l ELos. ISR 03012 i
Reference:
ECA-0.0 (Caubon before Step 9) i Page 99 of 100 4/13/97
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SRO EXAM REVIEW Group 3 EPE
, ou non.
- . During a large break LOCA with RAS, the following conditions exist:
i
- HIS-M 50 & 51 are flashing green in the SIAS lightbox;
- - LSI M-40 & 41 are flashing green in the RAS lightbox;
- PCC-M 219 is solid green in the CIS lightbox; i - PW A-78 is solid green in the SIAS/CIS lightbox;
- RWST level is less than 100,000 gallons; I
- Containment pressure is 26 psia and decreasing.
I The STA states that an ORANGE path exists for containment and recommends entry into FR-Z.2, ] " Containment Flooding." Based on the information available, which of the following would be the likely source of any extra water that has been dumped into the containment during this accident? 1
- A. The PCC system has ruptured and dumped its contents into t'te containment.
s B. The RWST outlet isolation RAS bypass switch was left in " BYPASS" C. The containment sump level indication is high due to harsh containment environment. t D. The primary water header has ruptured inside the containment. I Answer: , B Justificabon:
- a. PCC-M-219. is closed therefore this is an unlikely source of the water.
I
- b. CORRECT. With this switch left in the " BYPASS" position, the RWST will continue to empty i
at this containment pressure. L
- c. Containment sump level is not affected by harsh containment conditions.
- d. The primary water header isolates on an SIAS signal.
.g
}Quesbon Topic: Knowledge of EOP bases for a SGTR recovery 2 RO Q SRO K/A Rahng 2.7/3.6 CFRs; RO 55 41(b)(10) SRO $5.43(b)(5)
[ Systemi Generic K/A #; 2 4.18 ELOs. EAS-0903-1&5
Reference:
FR-Z.2 BKGD Document 5 l Page 100 of 100 4/13/97 i
\
RO/SRO Exam Sample Plan System KIA # KlA Rating Question Topic Gencrie Generic 2 110 2 7/3.9 Knowledge oflicense conditions and limitations 1 32 3 4'3 8 Relationship between subcooled margin and S/G pressure 2133 34'40 Ability to recognize TS entry enteria for N1/ delta T power 2401 43/46 Knowledge of EOP entry conditions 2 4,02 3 9/4 i Knowledge of system setpoints for EOP entry 2404 4 0/4 3 Main feed reFulating valve fails open, indications seen 2416 30/40 Knowledge of EOP implementation hierarchy, 2420 3 3/4.0 Knowledge ofimplications of EOP rotes, caution 2421 3 7/4.3 Knowledge of parameters and logic for CSF's 2424 33/37 Senice water header loss etTects on TS Number of qugstions cuphcated.10 % of RC questions required: 13 % of SRO questions requi.ed 17
'Q V
Thursday, April 03,1997 Page I of 7 0
1 l System K/A # K/A Rating Question Topic Group 1 Plant 001 K4 09 39.'4.1 Recovery of dropped rod 003 A2.01 3 5/3.9 Seal return flow degradation K3.01 3 7/4 0 Loss of RCP cffect on RCS 004 A202 39/42 Loss of PZR level A418 43/41 Emergency boration valves operation 013 Kl.01 42/44 Initiation signals for ESF logic, HELB K410 33/3.7 Throttling HPSI flow for Si termination 015 A101 3.5/3.8 NIS calibration by heat balance K6 01 2.9/3 2 Bistable and logic circuits 017 A4 01 3 8!4 1 Actual in-core temps /how to read them K5.02 3 7/4 0 Saturation and subcooling of water 056 A2.04 2 6'2 8 Loss of condensate pump 059 A3 06 32/33 feedwater isolation and reset
- 06) A101 3 9/4 2 Control and monitor S!G levels 068 K102 2 5/2 6 X-connections between liquid and waste gas 0?! A3 02 3 6/3 8 RMS alarm and actuating signals 072 K3 02 3 1/3 5 Fuel handling operations Genenc 2.1.07 3.7/4 4 Ability to evaluate submergence issu s Number of questions duplicated IN
% of RO questions required; 23 % of SRO questions required. 19 1hursday. April 03,1997 Page 2 of 7
System K/A # KIA Rating Question Topic Groul) 2 Plann1 002 K 1.07 35/37 RX vessellevel indication causeleffects 006 K2.01 36'39 ECCS pump power supplies K6 03 34'39 SIT valve position indication 010 K3 02 4 0/4 1 PZR pressure malfunction-efTect on RPS a 011 K515 3 6/4 0 PZR level indication when RCS is saturated 012 K6 02 29'3.1 DSS trip circuits for AOO 024 K4 03 3 2/3.5 Control features of auto purge isolation 4 033 A2 01 3 O!3 5 Ability to predict impact ofinadequate SDM 035 A4 08 4.1/4 4 Recognition of S/G tube leak on rad les els 030 A3 02 3 1/3 5 Abihty to monitor auto isolation of main steam via EFC\"s 062 At 01 3 2/3.5 Significance of DG load limits 073 A101 3 2/3 5 Monitoring changes in rad levels based on detector replacemen
- Genenc 21.02 3 0/4 0 Knowledge of operator responsibilities
. 2128 32'23 High activity in L/D. actions to mitigate Number of questions duplicated 14
% of RO questions required: 20 % of SRO questions required: 17 i
4 4 4 Thursday, April 03,1997 Page 3 of 7 l
System K/A # K/A Rating Question Topic Grout) 3 Plant 005 A2 02 35/37 Pressure transient protection during CSD 045 K1.18 3 6/3 7 Interrelationship between RPS and main gen Genenc 2409 3 3/3 9 RHR in senice without proper warmup Number of questions dup'.cated 3 % of RO questions required. M % of SRO questions required: 4 Thursday, April 03,1997 Page 4 of 7
l System K/A # K/A Rating Question Topic i Group 1 EPE 005 AK3 03 3 6/4.1 Tech Spec limits for rod mismatch 015 AAl 21 44'4.5 Development of NC flow /Use of RCS instruments 024 AK3.02 4 2/4 4 Actions for emergency boration in FR S I 026 AA: 02 2 9/3 6 Cause of possible CCW loss 040 AKl05 4.1/4 4 Reactivity efTects for SLB (effect of C/D) 051 AA2 02 3 9/4.1 Conditions for RX trip on loss of vacuum 055 E Al .07 43/45 Restoration of AC/why close PCC breakers' 057 AA220 3 6/3 9 Auto actions on loss of vital AC/PORY opens (w>7 AA216 33/40 Vital equipment and control systems maintained AK30' 33/41 Actions for fire onsite/why achieve 80* pzt level 06M AA1.23 43/45 Manual trip of reactor & turbine AK2 01 3.9/4.0 AUX S/D panel layout 074 EK2 05 3 9/4 1 Interrelationship between inadeq cool'LPSI pps 04 AK3 05 2 9'3 6 Corrective actions for fission product activity Genenc 2111 3 0/3 8 Knowledge of one hour TS action (system) Number of questions cuplicated- 15
% of RO questions required- 16 % of SRO questions required: 24 Thursday. April 03,1997 Page 5 of 7
1 System K/A # KIA Rating Question Topic Group 2 EPE 007 EKl 06 3 7/4 1 Dlowdown flow from S/G on RX trip EK2 03 35/36 R'XMp status panel, parelleling out of phase 00M AK3.05 40'45 E(.CS termination / throttling criteria 009 EA1.08 4 OJ4.1 Containment isolation system, PCC M 219 loss of power EK3 21 4 2/4 5 Actions for small break LOCA 022 ' AAl 01 34'33 CVCS LO & CHG 025 AK3 01 3.1/34 Shitling to alternate flowpath for RilR 03.' AA2 04 31/35 Overlap of source to wide range N1's 037 AK3.07 4 2/4 4 Actions in EOP's for SGTR 054 AAl 01 45'44 AFW controls including alt sources (ETW-A 338,339,340) 05k AA2 01 3 7/4 i Verification ofloss of DC Bus #3 Genenc 2222 3 4/4 i Knowledge of LCOi and safety limits Number o' Questions duplicated. 12
% cf P.O c .estions required: 17 % of SRO questions required: 16 Thursday, April 03,1997 Page 6 of 7
, System KlA # K/A Rating Question Topic Group 3 EPE Generic 2418 2 7/3 6 Knowledge of EOP bases for a SGTR recovery Number of questions duplicated. I
% of RO questions required: 3
% of SRO questions required. 3 Thursday, Apri103,1997 Page 7 of 7
RO Exam Sample Plan (K/A sort) System # KlA # K/A Rating Question Topic Generic Genenc 2.1.10 2 7/3 9 Knowledge oflicense conditions and limitations 2.1.31 4 2/3 9 Operation of POR\"s w hen cooled down 2 1.32 3 4/3 8 Relationship between subcooled margin and S'G pressure 2 1.33 3 4/4 0 Ability to recognize TS entry criteria for N1/ delta T power 2232 3 5/3 3 Knowledge of RO duties during refueling 2401 4 3/4 6 Knowledge of EOP entry conditions 2402 39.'4.1 Knowledge of system setpoints for EOP entry 2404 4 0/4 3 Main feed regulating valve fails open, indications seen 2.4.16 3 0/4 0 Knowledge of EOP implementation hierarchy 2420 3 3/4 0 Knowledge ofimplications of EOP notes, caution 2421 3 7/4 3 Knowledge of parameters and logic for CSF's 4 24 3 3/3 7 Service water header loss etTects on TS 2434 38.'36 Knowledge of RO tasks performed outsidt CR (DG 2 ops)
% of RO questions required 13 Number of questions listed: 13 Thursday, April 03,1997 Page 1 of 7
System # K/A # K/A Rating Question Topic Group 1 Plag Genenc 2107 37/44 Abihty to evaluate submergence issues 015 A101 35/38 N15 calibration by heat balance 061 At 01 39!42 Control and monitor S'G levels i 003 A2 01 35/39 Seal return flow degradation 004 A2 02 3 9/4 2 Loss of PZR level 056 A2 04 26'28 Loss of condensate pump 071 A3 02 36/38 RMS alarm and actuating signals 059 A3 06 3 2/3.3 Feedwater isolation and reset 017 A4 01 3 8/4 1 Actual in-core temps'how to read them 015 A4 03 3 8/3 9 Trip bypasses' logic matrises 004 A4.18 4 3/4 1 Emergency boration valves operation 013 K1.01 4 2/4 4 Initiation signals for ESF logic, llEl B ] 06M Kl.02 25/26 X connections between liquid and waste gas 061 K202 3 7/3 7 EFW pump power supplies 003 K3 01 3 7/4 0 Loss of RCP efTect on RCS 072 K3 02 3 1/3 5 Fuel handling operations 022 K4 03 3 6/4 0 Automatic containment isolation for PCC A-238 , 001 K4 09 3 9'4.1 Recovery of dropped rod 013 K4.10 33/37 Thrcttling HPSI flow for Si termination 017 K5.02 3 7/4 0 Saturation and subcooling of water 001 K510 3 9/4 1 Effect of rod mcnion on core power distribution d 015 K6 01 2.9/3 2 Bistable and logic circuits 004 K613 3 1/3 3 Batch control in manual
' , . of RO questions required. 23 Number of questions listed: 23 Thursday April 03,1997 Page 2 of 7
Systern # K/A # F1A Rating Question Topic
\
Group 2 Plant i Genenc 2.t 02 3 O!4 0 V.nowledge of operator responsibihties i 2 1.28 32/2'. High activity in UD, actions to mitigate ; 062 Al O! 32/3$ Significance of DG load limits 1 073 At 01 3 2/3 5 Monitoring changes in rad lesels based on detector replacement 033 A2 01 3.0/35 Abihty to predict impact ofinadequate SDM 014 A2 05 3 9/4 I RPI OOS on RX trip - how to mitigate (RO only) 064 A3 01 4 i/4 0 Auto start of EDG 039 A3 02 3 1/3 5 Ability so monitor auto isolation of main steam via El C\"s 086 A3 03 29/33 Actuation of fire detection in a charcoal filter bank 064 A4 01 4 0'4 3 Local and remote operation of the EDG 035 A4 08 41/44 Recognition of S'G tube leak on rad levels 002 K107 3 5/3 7 RX vessel level indication cause'efTects ON K2 01 36'39 ECCS pump power supplies 026 K202 2 7/2 9 Power supply to spray MO\"s (RO only ) 010 K302 4 O!4 1 PZR pressure malfunction-effect on RPS 079 K4 01 29'3: Cross connects of station to instrument air 024 K4 03 3 2/3.5 Control features of auto purge isolation 011 K515 3 6J4 0 PZR level indication when RCS is saturated 012 K6 02 2 9/3 1 DSS trip circuits for AOO 006 K6 03 34'39 SIT valve position indication
% of RO questions required: 20 Number of questions listed: 20 Thursday. April 03,1997 Page 3 of 7
System # K/A # K/A Rating Question Topic 1 Groim 3 Plant Genenc 2409 3.3/3 9 RHR in sersice without proper warmup 005 A 02 3 5/3 7 Pressure transient protection during CSD 076 A3 02 3.7/3 7 Power Gushing of the SW heat exchangers 008 A3 08 3 6'3 ~/ Auto actions of CCW on Sl AS 007 A410 3 6/3 8 Identifying a PORV/ code safety that is not closed 045 K1.18 3 6/3.7 Interrelationship between RPS and main gen 078 K3 02 3 4/3 6 Loss ofcontainment air compressors 028 K5 03 29'36 Ability to predict H2 concentrate (RO only)
% of RO questions required 8 Number of questions hsted. 8 e
Thursday, April 03,1997 Page 4 of 7
_ System # K/A # K/A Rating Question Topic Group 1 EPI' Genenc 21.11 3 0/3 8 Knowledge of t ne hour TS action (system) 015 AAl 21 44/4.5 Development of NC flow /Use of RCS instruments 06R AAl 23 4 3/4 5 Manual trip of reactor & turbine 026 AA2 02 2 9/3 6 Cause of possible CCW loss OSI AA2 02 3 9/4 1 Conditions for RX trip on loss of vacuum
'>67 AA216 33/40 Vital equipment and control systems maintained 057 AA2 20 3 6/3 9 Auto actions on loss of vital AC/PORY opens 027 AK101 3 1/3 4 Defn of sat. temp based on pzt insurge'outsurge (R/O only!
040 AKI 05 4 1/4 4 Reactivity effects for SLB (etTect of C/D) 068 AK2 01 3.4/4 0 AUX $ D panellayout 024 AK3 02 42/44 Actions for emergency boration in FR S I 005 AK3 03 3 6/4 1 Tech Spec limits for rod mismatch 067 AK3 04 33/41 Actions for fire onsite/why achiese 80'. pzr les el 076 AK3.05 2996 Corrective actions for fission product activity 055 EAl 07 4.3/4 5 Restoration of AC/why close PCC breakers' 074 EK2 05 3 914.1 13 errelationship between inadeq coot 1 PSI pps
- 9. of RO questions required: I t.
Number of questions hsted; 16 Thursday, April 03,1997 Page 5 of 7
, System # KIA # K/A Rating Question Topic 1 Group 2 EPE Genenc 2222 34/4.1 Knowledge of LCO's and safety limits 022 AAl 01 34/33 CVCS llD & CHG 054 A A1.01 45/44 AFW controls including alt sources (EFW.A 338,339,340) 058 AA2 01 3 7/4.1 Verification ofloss of DC Bus #3 001 AA2 03 4 5/4 8 Actions on CRW if auto trip fails to work (RO only) 003 AA2 03 3 6'3.8 Dropped rod indication using excore NI (RO only) 032 AA2 04 31/35 Overlap of source to wide range NI's 059 AK2 01 2.7/2 8 Radioactive liquid monitor release (RO only ) 025 AK3 01 3 1/3 4 Shifting to alternate flowpath for RHR 0(* AK3 05 4 0.'4.5 ECCS termination / throttling criteria 037 AK3 07 4.2/4 4 Actions in EOP's for SGTR 009 EAl 08 4 0'4 1 Containment isolation system, PCC-M 219 loss of power Oil EA2.10 4 $/4 7 Verification of adequate core cooling (RO only) 007 EK 1.06 3.7/4 i Blowdown flow from S/G on RX trip EK2 03 3 5/3 6 RX trip status panel, parelleling out of phase 029 EK312 4 4/4 7 EOP actions for ATWS (RO only) 009 EK3.21 42/45 Actions for small break LOCA
% of RO questions required: 17 Number of questions listed: 17 Thursday, April 03,1997 Page 6 of 7
System # K/A # K/A Rating Question Topic Group 3 EPE : Genenc 2 4.18 27/3.6 Knowledge of EOP bases for 4 SGTR recovery 065 AA2 06 36/42 Tripping RX on loss ofinstrument air 028 AK3 05 3 7/4 1 EOP actions for PZR level malfunction '< of RO questions required: 3 Number of questions listed.1 Thursday. April 03,1997 Page 7 of 7
l1 l RO Exam Sample Plan' (system sort) l l l System # K/A # K/A Rating Question Topic Generic Genenc 2 1.10 2 7/3.9 Knowledge of'icense conditions and hmitations 2.1 31 4 2/3 9 Operation of POR\"5 w hen cooled down 2232 35/33 Knowledge of RO duties during refuehng 2401 4 3/4 6 Knowledge of EOP entry conditions 2404 4 0/4 3 Main feed regulating valve fails open, indications seen 2434 3.8/3 6 Knowledge of RO tasks perfotmed outside CR (DG-2 ops) 2421 3.7/4 3 Knowledge of parameters and logic for CSPs 2420 33/40 Knowledge ofimplications of EOP notes, caution. 2424 33'3.7 Service water header loss efTects on TS 2416 3.0/4 0 Knowledge of EOP implementation hierarchy 2402 3.9/4 i Knowledge of system setpoints for EOP entry 2 1.32 34'38 Relationship between subcooled margin and S.G pressure 2133 3 4'4 0 Ability to recognize TS entry criteria for Nildelta T power
% of RO questions required 13 Number of questions listed: 13 Thursday, April 03,1997 PageIof7 I
System # K/A # K/A Rating Question Topic Group 1 Plant 001 K510 3 9/4 1 Effect of rod motion on core power distribution K4 09 - 3.9'4 1 Recovery of dropped rod 003 K3 01 3 7/4 0 Loss of RCP effect on RCS A2 01 3 5'3 9 Seal return flow degradation 004 K613 31/33 Batch control in manual A418 4 3/4 1 Emergency boration valves operation A2 02 34'4 Loss of PZR level Ol' KI 01 42'44 Initiation signals for ESF logic, HELB K410 33'37 Throttling HPSI flow for Si termination 015 Kb 01 2 0/3 2 Bistable and logic circuits Al 01 3.5!3 8 NIS calibration by heat balance A4 03 3 8/3 9 Trip bypasseflogic matrixes 017 K502 3 7/4 0 Saturation and subcooling of water A4 01 3 8'4.1 Actual in-core temps /how to read them 022 K4 03 3 6/4 0 Automatic containment isolation for PCC A 238 056 A2 04 2 6/2 8 Loss of condensate pump 0$9 A3 06 32'33 Feedwater isolation and reset 061 Al 01 3.9/4 : Control and monitor S'G levels K2 02 3.7/3 7 EFW pump power supplies 068 K102 2 5:2 6 X-connections between liquid and waste gas 071 A3 02 3 6'3 8 RMS alarm and actuating signals 072 K3 02 3 1/3 5 Fuel handling operations Genenc 2107 3.7/4 4 Ability to evaluate submergence issues % of RO questions required: 23 Number of questions listed. 23 Thursday, April 03,1997 Page 2 of 7 J
System # K/A # K/A Rating Question Topic \ Group 2 Plant 002 K107 3.5/3 7 RX vessel level indication cause! effects 006 K2 01 36/3.9 ECCS pump power supplies K6 03 34'39 SIT valve position ind cation 010- K3 02 4 0/4.1 PZR pressure malfunction-effect on RPS 011 K515 3 6/4 0 PZR level indication when RCS is saturated 012 K6 02 2 9'3 1 DSS trip circuits for AOO 014 A2 05 3 9/4.1 RPI OOS on RX trip how to mitigate (RO only) 026 K2 02 2.7/2 9 Power supply to spray MO\"s (RO only) 029 K4 03 3 2/3 5 Control features of auto purge isolation 033 A2.01 3.0/35 Ability to predict impact ofinadequate SDN1 035 A4 08 4 1/4.4 Recognition of S/G tube leak on rad levels 039 A3 02 3 1/3 $ Ability to monitor auto isolation of main steam via EFC\'s 062 A1.01 3 2/3.5 Significance of DG toad limits 064 A301 4 1/4 0 Auto start of EDG A4 01 4 0/4 3 Local and remote operation of the EDG 073 Al 01 3 2/3.5 Monitoring changes in rad levels based on detector replacement 079 K4 01 2 9/3 2 Cross connects of station to instrument air 086 A3 03 29/3.3 Actuation of fire detection in a charcoal filter bank Genenc 2102 3.0/4 0 Knowledge of operator responsibilities 2.1.28 3 2/3 3 High activity in L/D, actions to mitigate
% of RO questions required: 20 Number of questions hsted. 20 Thursday, April 03,1997 Page 3 of 7
t System # KlA # K/A Rating Question Topic Group 3 Plant 005 A202 3 5/3 7 Pressure transient protection during CSD 007 A410 3.6/3 8 Identifying a PORV/ code safety that is not closed 008 A3 08 3.6/3.7 Auto actions of CCW on SIAS 0H K503 29/3.6 Ability to predict H2 concentration (RO only) 045 K1.18 3.6 '3. 7 Interrelationship between RPS and main gen 076 A3.02 3 7/3 7 Power flushing of the SW heat exchangers 078 K3 02 34'36 Loss of containment air compressors Generic 2409 3 3/3 9 RHR in service without proper warmup
% of RO questions required: K Number of questions listed. H Thursday, April 03,1997 Page 4 of 7
System # K/A r K/A Rating Question Topic Group 1 EPE 005 AK3 03 3 6/4 1 Tech Spec limits for rod mismatch 015 AAI 21 44/4.5 Development of NC flow /Use of RCS instrument > 024 AK3 02 4 2/4 4 Actions for emergency boration in FR-S 1 026 AA202 2.9/3.6 Cause of possible CCW loss 027 AKl 01 3 1/3 4 Defn of sat. temp based on pzr insurge/outsurge (R/O only) 040 AK105 4 1/4 4 Reactivity efTects for SLB (effect of C/D) 05I AA2 02 39'41 Conditions for RX trip on loss of vacuum 055 EAl 07 43/45 Restoration of AC/why close PCC breakers' 057 AA2 20 3 6/3 9 Auto actions on loss of vital AC/PORY opens 067 AK3 04 3.3/4 1 Actions for fire onsite/why achieve 80*. pzt level AA216 33/40 Vital equipment and control systems maintained 06k AK2 01 3 9/4 0 AUX SO panellayout AAI 23 43/4.5 Manual trip of reactor O turbine 074 LK2 05 3 9/4.1 Interrelationship between inadeq cool'LPSI pps 076 AK3.05 2 9'3 6 Co.rective actions for fission product activity Generic 2111 3 0/3 8 Knowledge of one hour TS action (system) % of RO questions required. 16 Number of questions listed: 16 Thursday. April 03,1997 Page 5 of 7
System # KIA # JA Rating Ouestion Topic Group 2 EPE 001 AA2 03 4 5/4 8 Actions on CRW if auto trip fails to work (RO only) 003 A A2 03 3 6/3 8 Dropped rod indication using ncore Ni (RO on!)) 007 EK2 03 3 5/3 6 RX trip status panei, parelleling out of phase E K 1.06 3.7/4 1 Blowdown flow from S/G on RX trip 008 AK3 05 4 0/4.5 ECCS termination / throttling criteria 009 EAl 08 4 O!4.1 Containment isolation system, PCC-M-219 los., of power EK3 21 42/45 Actions for small break LOCA 01l EA210 4.5/4.7 Verification of adequate core cooling (RO only ) 022 AAl 01 3 4'3 3 CVCS L/D & CilG 025 AK3 01 31/34 Shilling to alternate flowpath for RilR 029 EK3.12 44/47 EOP actions for ATWS (RO only) 032 AA2 04 3 1/3 5 Overlap of source to wide range Ni's 037 AK3 07 4 2/4 4 Actions in EOP's for SGTR 054 AAl 01 4 5/4 4 AFW controls including ah sources (EFW.A.338,339,340) 058 AA: 01 3 7/4 i Verification ofloss of DC Bus #3 054 AK2 01 2,7/2 8 Radioactise liquid monitor release (RO only) Genenc 2_2 22 3 4/4 i Knowledge of LCO's and safety limits % of CtO questions required 17 Number of questions hsted 17 Thursday. April 03.1997 Page 6 of 7
I ! i i System # - K/A # K/A Rating Question Topic i Group 3 EPE 028 AK3.05 3.7/41 EOP actions for PZR level malfunction 065 AA2 06 3 6/4.2 Tripping RX on loss ofinstrurrent air Generic 2418 2 7/3 6 Knowledge of EOP bases for a SGTR recovery
% of RO questions required: 3 Number of questions listed. 3 s
4 4 Thursday, April 03,1997 Page 7 of 7
SRO Exam Sample Plan (K/A soro System # K/A W K/A Rating Question Topic Generic Genen( 1 01 37/38 Knowledge of conduct of operations im ohing remedial actions 2 1.10 2 7/3 9 Knowledge oflicense conditions and limitations
- 1 10 2940 Ability to apply TS to a system. EFW seismic concerns
- L17 35/36 Ability to make accurate, clear concise reports
- 1 32 34'38 Relationship between subcooled margin and S/O pressure
- 1 33 3440 Abihty to recognire 15 entry criteria for N!! delta 1 power .
1 2 13 3 6'3 8 Knowledge of tagging procedures for double serification l 3 oh 3/3 : Knowledge of process for planned gas telease
- 3 10 o'33 Vah c repair with potential for rad release 2401 43/I6 Knowledge of EOP entry conditions
- 4 02 3 o'4 i Knowledge of s) stem setpoints for LOP entry 2404 4043 Main feed regulating vahe fails open, indications seen 4 les 3 0'4 0 Knowledge of EOP implementation hierarch)
- 4 20 33'40 Knowledge ofimplications of EOP notes, caution 2421 3 7/4 3 Knowledge of parameters and logic for CSF's
- 4 24 3 3') 7 Senice water header loss effects on TS
- 4 48 35/38 115kv line operabilit)
% of SRO questions required 17 I
Wumber of questions listcd 17 i i i d lliursday, April 03,1997 Pageiof7 l t i
System # KlA # K/A Rating Question Topic Group 1 Plant Gerwnc 2107 37/44 Ability to evaluate submergence issues 015 Al 01 3 $/3 8 NIS calibration by heat bal.nce 061 Al 01 3 9:4 2 Control and monitor S'G lesels 003 A2 01 3509 Seal return flow degradation 004 A202 39:4: Loss of P7.R les el 056 A2 04 06/28 Loss of condensate pump 071 A300 36!38 RMS alarm and actuating signals 054 A3 06 32/33 Tecdw ater isolation and reset 017 A4 01 38'41 Actualin core temps"how to read them DN A418 43/41 Emergency boration valves operation 013 K101 42'44 Initiation signals for ESI logic, llELil N4 Ki 0: 2 5/2 6 X-connections between liquid and waste gas 026 K: 02 2 7/: 9 Power supply to spray MOVs (SRO only) 003 K3 01 3 7/4 0 Loss of RCP efTect on RCS 07' K3 00 310 $ ruel handling operations 001 K4 00 39/4.1 Te ;overy of dropped rod 013 K4 V, 33/37 Throttling ilPSI flow for Si termination l 017 '.s$ 07 3 7/4 0 Saturation and subcooling of water ! 015 K6 01 29/32 !!istable and logic ciresits i
' , . of Sr4 questions required. 19 Nure/ er of questir 1s hsted 19 I
l l 'l lhursday. April 03,1997 Page 2 of 7 i E
l l l l System # K/A # K/A Rating Question Topic Group 2 Plant Generg 2102 30'40 Knowledge of operator responsibihties 2128 32/33 Ili;h activity in L/D, actions to mitigate 062 Al 01 3205 Significance of DG load limits 073 A101 3 2/3 5 hionitoring changes in rad levels based on detector replacement 034 A102 2907 Il:0 les el in refuchny canal (SRO only) 033 A2 01 3 0'3 $ Ability to predict impact ofinadequate SDh1 034 A2 01 3 6'4 4 Stuck fuel element while remodng upper guide structures 039 A3 02 3 1/3 $ Ability to monitor auto isolation of main steam via ETC\"s 035 A408 4 1/4 4 Rxognition of S'O tube leak on rad levels 002 K107 3 5/3 7 RX vesselleselindication cause/etTect5 (66 K2 01 36'39 ECCS pump power supplies 010 K3 02 4 0!4 I p2R pressure malfunction-efTect on RpS , 103 K3 02 3 E'4 2 Loss of cont integrity in normal ops (SRO only) 029 K4 03 3 2/3 $ Control features of auto purge isolation 011 K515 3 6'4 0 p2R level indication w hen RCS is saturated 012 K6 02 29,'3.1 DSS trip circuits for AOO Omi Kb 03 34/39 SIT vah e position indication te of SRO questions requirect 17 Number of quentiens liste d. 17 l l I l l T hursday. April 03,1997 page 3 of 7
System # K/A # K/A Rating Question Topic Group 3 Plant Genenc : 4 09 33/39 RHR in senice without proper warmup (ki$ A: 00 35/3.7 Pressure transient protection during CSD 045 K1 18 36'37 Interrelationship between RPS and main yen 041 K4 09 30/33 Relationship oflate to steam dump operations
*<, of SRO questions required. 4 Number of questions listed: 4 l
1 ) i d E 4
'I hursday. April 03.1997 Page 4 OI 7
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._ - _ - - . .. - . _ . . . _ - - - - - . _ _ _ . - . _ _ _ - . . _ - . _ _ . _ ~ .
System # KIA # KIA Rating Question Topic i Group 1 EPE Genenc 2111 3 0!3.8 Knowledge of one hour TS action (system) 069 AAl01 3 5/3 7 Isolation valves, dampers & E/P devices 057 AAl 06 35/35 Manual control of components losing auto control 015 AAlli 4 4/4 5 Development of NC flow,l'se of RCS instruments 06N AAl 23 43/45 Manual trip of reactor & turbine 026 AA2 02 29/36 Cause of possible CCW loss OSI AA2 02 3 9/4 1 Conditions for RX trip on loss of vacuum 0$9 AA2 03 3 1/3 6 Failure modes during liquid release (SRO only) 001 AA: 05 4446 Interpret uncontrolled rod withdrawal (SRO only) 067 AA216 33/40 Vital equipment and control systems maintained 057 AA: 20 3 6'3 o Auto actions on loss of vital AC/PORY opens 040 AKI 05 4 1/4 4 Reactivity etTects for SLB (effect of CO) 068 AK2 01 3 9'4 0 AUX S/D panellayout 024 AK3 02 42/44 Actions for emergency boration in FR S 1 059 AK3 02 32/45 Implement E. Plan for liquid rad release (SRO only) 005 AK3 03 3 6/4 1 Tech Spec limits for rod mismatch 067 AK3 04 33/41 Actions for fire onsite/why achieve 80'. pn level 076 AK3 05 2 9/3 6 Corrective actions for fission product actisity 003 AK3 07 38'39 Tech Spec for dropped rod during coastdown (SRO on!> ) 055 EAI 07 4.3!45 Restoration of AC/why close PCC breakers? 011 EKi 01 4 1/4 4 Implications during reflus boiling (SRO only) 029 EK103 3 6'3 8 ATWS effects of boron reactivity (SRO only) 074 EK2 05 39'41 Interrelationship between inadeq cool'LPSI pps 055 EK3 02 43/46 Actions in EOP for loss of ofTsite PWR, diesel breaker closure
% of SRO questions required: 24 Number of questions listed: 24 i 1hursday, April 03.1997 Page 5 of 7 l
. . - - - - - . - _ . - - . . - _ ~ _ . . - - _ _ _ _ - - - -.
l System # KIA # KlA Rating Question Topic Group 2 EPE Genenc 2222 3 4'4 I Knowledge of LCO's and safety hmits t 022 AAI01 34'33 CVCS UD & CilG 034 AAl01 4$/44 AFW controls including sh sources (ETW.A 338,339,340) 0$h AA2.01 3 7/4 1 Verification ofloss of DC Bus #3 032 AA2 04 31/3$ Overlap of source to wide range NI's 06 AA205 3 5/4 2 SUgh 02 concentration in decay tank, setions 02$ AKI01 3o'43 t.d e #RilR dunny a cooldown due to senice w ater 060 AK202 2 7/3 1 Cas release & ventilation alignment during VC1 burping 02$ AK3 01 3 1/3 4 Shifting to alternate flowpath for RilR W AK3 0$ 40/45 ECCS termination /throtthng criteria 037 AK3 07 42/44 Actions in E0P's for SGTR Om EAl 08 4 O!4.1 Containment isolation system, PCC-M 219 loss of power 03R EA217 38/44 RCP restart criteria 007 EK106 3 7/4 1 Blowdown flow from S'G on RX trip EK2 03 3 $/3 6 RX trip status panel, parelleling out of phase l 009 EK3 21 42'45 Actions for small break LOCA l
% of SRO questions required: 16 I Number of questions listed. 16 l
l i l i. T hursday. April 03,1997 Page 6 oI7
i
, System # KIA # K/A Rating Question Topic G roup 31:PI',
Generx 4 lb :7/36 knowledge of EOP bases for a SGT R recosery 056 AA105 38'39 Manually initiate safety in,iection 036 AR3 00 3 7/4 1 SRO actions for fuel handling incident
% of SRO questions required 3 Number of questions listed 3 lhursday. April 03,1997 Page 7 of 7
I l l SRO Exam Sample Plan (systeni soro System # K/A # K/A Rating Question Topic l Gencric Genenc 2400 3 9/4 1 Knowledge of system setpoints for EOP entry 2.3 08 23/3: Knowledge of process for planned gas release 2110 27/39 Knowledge oflicense conditions and limitations
- 1.12 9'40 Abihty to apply 1S to a systent Eiw seismic concerns ,
l 2.1 33 34'40 Ability to recognize 15 entry criteria for NI' delta T power 1 2448 35/38 115kv hne operabihty
- 13 36.'38 Knowledge of tagging procedures for double verification 2416 30.'40 Knowledge of EOP implementation hierarchy 2424 33/37. Service water header loss effects on T5 2420 3 3/4 0 Knowledge ofimphcations ofi'OP notes, caution
- 4 21 37/43 Knowledge of parameters and logic for CSI"s 2404 40/43 Main feed regulating vah e fails open, indications seen i
l 2401 43/46 Knowledge of EOP entry cor. il ns
- 3 10 2 9/3 3 Valve repair with notentia! for rad release
- 1.17 35/36 Ability to male accurate, clear concise reports 2101 3 7/3 8 Knowledge of conduct ofoperations involving remedial actions 213: 34'38 Relationship between subcooled margin and S'G pressure I
i
*. of SRO questions required: 17 Number of questions hsted; 17 i
1hursday, April 03,1997 Page I of 7 i
System # KlA # K/A Rating Question Topic Group i Plant , 001 K4 00 3 9:4 1 Recovery of dropped rod 003 A2 01 35/39 Seal return flow degradation K3 01 3 7/4 0 Loss of RCP etTect on RCS 004 A 02 39'42 Loss of PZR level A418 4 3/4 1 Emergency boration valves operation 013 K410 33/37 Throttling IIPSI flow for Si termination Kl 01 42/44 initiation signals for EST logie Hell 3 , 015 K601 2 9/3 2 13istable and logic circuits Al 01 3$/38 NIS calibration by heat balance 017 KS 02 3.7/40 Saturation and subcoolmy of water A4 01 3 8/4 1 Actualin core temps'how to read them 0.'6 K2 02 2 7/2 9 Power supply to spray MO\"s (SRO only) I 05t , A 04 26'28 Loss of condensate pump 059 A3 06 3 2/3 3 Teedwater isolation and reset 061 Al 01 3 9'4 2 Control and monitor S'O levels 06k K102 2 5'2 6 X-connections between liquid and waste pas 071 A3 02 36')8 RMS alarm and actuating signals 072 K3 02 3 1/3 5 fuel handhng operations Genenc 2 107 3 7/4 4 Ability to evaluate submergence issues i l % of SRO questions required: 19 l ! Number of questions hsted 19 l l i l l l
~I hursday, April 03,1997 Page 2 of 7
I System # K/A # KIA Rating Question Topic Group 2 Plant 002 K107 3$/37 RX vessel les el indication cause' effects l 00 K2.01 36/39 ECCS pump power supplies K6 03 3409 SIT vahe position indication 010 K302 4 0/4 1 PZR pressure malfunction-efTect on RPS 011 K515 36'40 PZR level indication when RCS is saturated 012 K602 29/31 DSS trip circuit 6 for ADO 029 K4 03 32 ') $ Control features of auto purge isolation 033 A2 01 30'35 Ability to predict impact ofinadequate SDN1 034 A2 01 36!44 Stuck fuel element while removing upper guide structures A102 29/3.7 1120 level in refueling canal (SRO only) 035 A4 08 4 1/4 4 Recognition of S'G tube leak on rad levels 039 A3 02 31/3$ Ability to monitor auto isolation of main steam via ET C\"5 Ot>2 A101 320.5 Significance of DG load hmits 073 Al 01 32'35 hionitoring changes in rad lesels based on detector replacement 103 K3 02 3 8'4 2 Loss of cont integrity in nonnal OPS (SRO only ) Genene 2128 32/33 High activity in L/D, actions to mitigate 2102 3 0.'4 0 Knowledge of operator responsibilities % of SRO questions required 17 Number of questions listed. 17 1hursday April 03,1997 Page 3 of 7
System # K/A # K/A Rating Question Topic Group 3 Plant 003 A0 02 3 $/3 7 Pressure transient protection during CSD 041 K4 00 3 O!3 3 Relationship of Tate to steam dump operations 045 Kl 18 3 6!3 7 Interrelationship between RPS and main gen Genens 2409 3 3/3 9 RilR in senice without proper warmup
% of SRO questions required: 4 Number of questions hated: 4 i
Thursday, April 03,1997 Page 4 of 7
__. _ . . _ _ _ ._ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ m__. .___ _ _ _ _ _ _ _ _ _ __ Systerr, # K/A # K/A Rating Question Topic Group 1 EPE 001 AA2 05 4 4/4 6 Interpret uncontrolled rod withdrawal (SRO only) 003 AK3 07 38'39 Tech Spec for dropped rod during coastdown (SRO only) 005 AK3 03 36/41 Tech Spec limits for rod mismatch 011 EK101 4 1/4 4 Implications during reDus boiling (SRO only) 015 AAl.21 44'45 Development of NC flow /Use of RCS instruments 024 AK3 02 42/44 Actions for emergency boration in TR S 1 026 AA2 02 29/36 Cause of possible CCW loss
, 029 EKI 03 36'38 ATWS cfTects of boron reactivity (SRO only )
040 AKI05 41/-l4 Reactivity efTects for SLD (effect of C/D) 0$1 AA2 02 3 9/4 1 Conditions for RX trip on loss of vacuum 055 EK3 02 4 3/4 6 Actions in EOP for loss of ofTsite PWR, diesel breaker closure EAl 07 43/45 Restoration of AC/why close PCC breakers 057 AA2 20 3 6/3 9 Auto actions on loss of vital AC/PORY opens AA106 35/35 Manual control of components losing auto control 059 A A2 03 3I/36 Failure modes during liquid rclease (SRO only) AK3 02 32/45 Implement E. Plan for liquid rad release (SRO only) 067 AA 16 33/40 Vital equipment and control systems maintained AK3 04 33/41 Actions for fire onsite'why achies e 80% pzr level OM AK201 .1 9/4 0 AUX S/D panellayout AAl 23 43/45 Manual t.. s of reactor & turbine 069 AAl01 35.'37 Isolation valves, dampers & E/P devices 074 EK2 05 39'4.1 Interrelationship betweeninadeq cooll. PSI pps 076 AK3 05 2 9/3 6 Corrective actions for fission product activity Generit 2 1.11 3 0/3 8 Knowledge of one hour TS action (system) I
% of SRO questions required. 24 Number of questions listed: 24 i
n 3 Thursda) April 03,1997 Page5or 7 l l l
System # K/A # K/A Rating Question Topic Group 2 EPO 007 EKI 06 37/41 Illowdown flow from S 'G on RX trip EK2 03 35.'36 RX trip status panel, parellehng out of phase 00k AK) 05 40'45 ECCS tennination /throtthng criteria 009 EK3:) 4 2'4 5 Actions for small break LOCA EAl 08 40/4i Containment isolation sptem. PCC M 219 loss of power 0:2 A Al 01 34'33 CYCS L/D & CllG 025 AK3 01 31/34 Shillius to alternate flowpath for RilR AK101 3 9'4.3 Loss of Rilk dunnF a cooldown due to senice water 032 AA2 04 31/3$ Oserlap of source to wide range N!'s 037 AK3 07 4 *./ 4 4 Actions in EOP's for SGTR 038 EA: 17 38'44 RCP restart criteria 034 AAi01 4$/44 ATW controls including ah sources (ETW.A.338,339,340) 038 AA:01 3 7/4 i Venfication ofloss of DC llus #3 060 AK 02 07/31 Gas release & ventilation abgnm2nt during VCT burping 061 AA: O! 35/42 liigh 0: concentration in decay tank! actions Genenc ::: 3 4'4 1 Knowledge of LCO's and safety limits
% of SRO questions required 16 Number of questiens listed 16 Thursda), April 03,1997 Page 6 of 7
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ta. . . . . . . .
System # K/A # K/A Rating Question Topic I Group 3 EPE 036 AK3 00 37/4.1 SRO actions for fuel handling incident 036 AAI05 3 8'3 0 Manually initiate safety injection Genenc : 4 18 7/3 6 Knowledge of EOP bases for a SGTP, recovery
% of SRO questions required: 3 Number of questions listed 3 1hursday, April 03,1997 Page 7 of 7
1991/1992 RO NRC Exam Questions Question # Question Topic 1 RCP seal failure determination 2 hiinimum pressure to operate RCP 3 Purpose of'tCP
. backstop desice 4 Why close seal return h10V on RCP 5 Horic acid PP auto stan criteria 6 LD l' 16 (UD pressure control) auto action 7 1/D flow control fa&-Jrx2 les el 8 RCP sealleakotT@ 3 psig & SIAS 0 Paralleling CEDh1 breakers using X tie 10 CEA withdrawal prohibit signal 11 l unction of reed switch position indicators 12 Reed switch deviation value 13 X connect for loss of containment c.ontrol air 11 Restart air comp on loss of power 15 Auto unblock of Sl AS 16 Inputs for blocking of SI AS 17 RAS cfrect on LPSI pumps 18 Inadvertant CS AS actuation 19 hianual stan permissise for P 615 20 NaOH into spray system, How
21 P 10B breaker location 2 Purpose of Hi PZR pressure trip 23 RPS signal for turbine trip 24 Zero mode bypass .o 'B P @l 5's 25 Auto shut on DG 1 A following auto stan 26 EFW isolation valve cetrol switch OPS 27 Auto stan of EFW/AFW pumps Thursda), April 03,1997 Page 1 of 7
Question # Question Topic i 2R TK 25 supplies on loss oflA 29 Inputs to Shthi 30 Auto start of standby PCC pump 31 PCC response to CIS 3 Oserpressure protection RHR 33 B'P of SThi dump control waey 34 Quick open signal for SThi dump control 35 NE' switch for P 87 to emer (13RG lift pp on turbine) 30 PR rod drop 11/5 function 37 PR safety channel hi voltage 38 NIindications on ASP 39 Auto trip of P.2A or il 40 h1Dh1FP isolation & recire vahe OPS 4I h1Dh1FP start following }{l S'O level trip 4: Containment purge 'ofTline' auto close signals 43 Fire protection'halon areas 44 1.oss of DP'ilU to P 2C cfTects 45 Open cold ley RTD on control channel 46 120 VAC bus cross ties 47 Fault gas monitor OPS for L1 A 48 PZR les el channel fails low @ 50". 40 Isolation of S/G blowdown (auto)
$0 RRS first stage fails high @ PWR 51 Rad monitor paperdrive switch
$2 Auto CIS valve operable criteria 53 Yellow % lack tape during tagouts 54 til rad entry locking requirements
$5 RPhi admin limits on WB exposure 56 Requirements for life sa,ing exposure Thursda), April 03,1997 Page 2 of 7 J
Question # Question Topic
$7 Protectis e equipment for 480V breaker OPS 58 Actions for electrical shock 59 Appros ed procedure usage 60 Confined space entry reqts' standby person OPS 61 Procedure usage capital M step 62 Red phone linkup to control room 63 Log sheets out of tolerance reading 64 E Plan when io man EOC/OSC 65 CE A inoperable initial actions 66 Natural circulation flow enhancement 67 rn.S 1 cmcryency boration flow path 68 RCP stop within 45 seconds wby?
60 PCC leak surge tank levelincrease 70 Most hkely PTS event 71 Rupture of atmos STM dump'AFW pump supply line 72 Manual trip on high condenser pressure 73 ECA-0 0 security door blocking 74 ECA-0 0 CEF status tree monitoring 75 Loss of DP/l AC (a 100*i w hat trip RX/ turbine? 76 Fire following loss of PWR/ securing diesel 77 AOP 2-90-0 fire brigade members 78 Procedure used for control RM evac or SDO 70 Control RM evac: PABEP controls what' 80 Conditions for containment integrit) 81 Misaligned CEA When it is required 82 Responsible person for CSFST monitoring 83 EOP set entry condition E 0 or ECA 0 0 84 EOP procedure usage vertical star criteria 85 E-O ETW isol to S/G based on? Thursday, April 03,1997 Page 3 of 7
i i Question # Question Topic - 4 80 Verifying PORVs closed how? 87 liarsh containment criteria 88 CSFST heirarchy 89 Throttling RilR pump for casitation correction 90 less of SW cfTects to P 12A 91 AOP 2 34 RilR casitation caution why? 92 Ilow is leaktate determined 93 SG tube leak PWR reduction to 50*. why* 94 U-tube uncmery during SGTR 95 ES-31 S/G backfill method 96 Change flow restrictor OPSc375# 97 Loss of DC bus 3 with loss of AC efTect' 98 Why ill llPSI flow required during harsh containment 99 Reduce 112 pressure to 2 PSIG if ofTsite power lost 100 EC A 01 restoration of FW with NR levels <56'.
/9 9 3. -+ 101 PRZ control failure causiny 1 CCS
$ 7arr 5 hert 102 Computer problem, actions to take l 103 Ilreaker status in control room 104 S/G 11'D tank vent to PVS problem
- 105 AOP 2 2 entry conditions 106 DPil AC ioss cause of RX/ turbine trip (repeat) 107 AOP 2 45 seal return htOY why isolated (repeat) 108 Indication of partialloss ofload 109 hiinimum PCC surge TK level wh>'
110 Fire in Prot cable vault open MCC 711 & 813 why? l Ill OP 126 3 shift turnover duties 112 Checking valve in close position i13 RCP seat failure (repeat)
)
114 Orange valve label tag Thursday April 03,1997 Page 4 of 7 NP
l l Question # l , Question Tople l i 115 Auto CIS vahe operability (repeat) 110 Esposure in radiation area , 117 Protecthe year 480 vae breaker OPS (repeat) 118 Procedure usage (repeat) 110 M step (repeati 100 Red phone (repeat) 121 005 log reading (repeat) 100 EOF /OSC manning (repeat) 123 PAllEP OPS (repeat) 124 EOP rules of usage (repeat) 105 CilG flow restrictor (repeat) 126 L.oss of DC 11U5 3 (repeat) 107 AOP 21 stabilire Tcold how' 128 111 rad on PVS during release action 109 Enhance NC flow in RCS 130 RCP trip {i PWiUParameter response 131 Calorimetric input error 130 Control rod PDillimits 133 Ilreak in CilG 11DR indications 134 PZR STM space leak indications 135 EDG OPS load & voltage OPS 136 RCP OPS basis for 3rd pump run 137 incere use during accidents 138 Functions ofincore T/C 130 Control rod testing when cold RPS trips ll'P' 140 Placing CEAS during RX S/U 6 step pull why9 141 RX S1' limit for dilution of1/2 DPM 1.t: MFRV IFP auta signal override why' 143 OP 17 secure a RCP last why' Thursda3, April 03,1997 Page $ of 7
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Question # Question Topic 144 S D OPS 10 tad. containment purge S'D how' 145 FR S 1 why press <2385a for emergency boration 146 PRZ les el fails low @ $0* 6 (repeat) 147 PORY position indication (repeat) 148 Quench TK OPS' discharge into tank 149 Liquid waste llDR alignment 1$0 LD T 5 auto close OPS 151 Cont spray info question i ! 152 1 solation of VCT on SI why' , 15.1 Isolation of S'O !!'D why' 154 S'O level response fo press comp failure 155 Cont- purge OPS during refuehng (repeat) l 156 Fuel transfer tube design 157 ElCV design (repeat) 15h STM dump ll!P OPS (repeat) 159 Main turbine OVSPD l 160 Mi P isolation (repeat) I 161 TK 25 OPS (repeat) 162 Fire protection HDR press status 16.1 EFW OPS (repeat) 164 RilR in sersice PIC 103 VPSR pegs Hi action 165 Liquid release RI.1801 alarm why' 166 E 1 closure of SIT isolation vahes 167 E 0 no turbine trip what action required l 168 Isolation of FW to faulted S/G l 164 E 3 rupture S/G depress slow why' l l 170 Shut EFC\"s on RX trip when?
- 171 Use of PITS when' 172 P-6A boric acid auto start when' Thursda,s. April 03,1997 Page 6 of 7 1
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Question # Question Topiw 173 Cooling CEDht's during litt how? 174 p.2C turbine trip switch to ll'P why' 17$ Improper tagging @ SFP fuel pool draining 176 LPS!!RilR OPS 177 hianual It'P of spray w hy' 178 Waste gas press control vahe shuts auto w hy' 179 li'U tag out of SIT h10Vs why? 180 WGDT O'P protection 181 PC.10lX/PC.10lY control signal for' 182 IIELil actuation re.open S'G II/D vahes 183 L512 small breaker LOCA EFW flow increase 184 Loss of125 VDC effects on RTin 185 llot' cold calinstruments for PZR lesel 186 Closure of SI A-hi 53 &54 on RAS why? 187 CEA withdrawal OPS oriented Q? , 188 SCC non safeguard isolation 180 RRS TH failslow response (repeat) 190 PWR range N1's why no gamma comp 191 i R-C 1 why S'G rapid depressurize? 192 Why 490 GPhi flow for ECA-0 0 193 TR S I alternate preferrred boration methods 194 l 131 concentration on PWR change 195 Loss of feed How to get condensate into S!G 196 Caution for feeding dry S'G 197 FN 2 trips due to H1 rad what did it 198 Loss of PCC 45 see trip (repeat) 199 AOP 2 30 what constitutes loss ofintegrity 200 FR-H 1 why trip RCP's Thursday April 03,1997 Page 7 of 7 l i i
1992/1993 SRO NRC Exam Questions Question # Question Topic 1 1992 RO Exam
- 1 2 1992 RO Exam
- 2 3 1992 RO Exam a 4 4 NDTT w hat is it' 5 1992 RO Exam a 5 6 199 RO Exam # 6 7 1992 RO Exam # 7 8 1992 RO Exam
- 8 9 Considerations for loss of cont integrity 10 1992 RO Exam # 9 11 1992 RO Exam a 10 12 1992 RO Exam # 13 13 1o02 RO Exam 815 14 Tagging controlled by QPD 15 1991 RO Exam # $3 16 Eocked 111 rad area requirement 17 Rad area exposure problem (time limn) 18 PPE for 480 sac breaker racking 19 Electrical shock' ist action required 20 Procedure usage 21 1991 RO Exam t 60 22 1992 RO Exam # 19 23 1992 RO Exam # 20 24 1992 RO Exam
- 21 25 Fire in plant P3S out of CR where's he go' 26 1992 RO Exam # 22 27 PSS notification in emergency 28 1992 RO Exam W 23 29 1992 RO Exam
- 24 30 1992 RO Exam # 25 31 1992 RO Exam # 25
'Ihursday. April 03,1997 Page I of 7 l
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Question # Question Topic 32 EOP procedure usage FR il.2 w/o ofTsite pwr 33 1992 RO Exam # 27 34 Condition to depart for license or Tech Spec 35 Adequate core cooling during SBl.OCA 36 Grid penurbation Q OPS action 37 1991 RO Exam # 93 38 1992 RO Exam
- 29 39 1992 RO Exam # 30 40 1992 RO Exam
- 31 1
1 41 1992 RO Exam # 32 42 1992 RO Exam # 33 43 1992 RO Exam # 34 44 1992 RO Exam # 35 45 1992 RO Exam # 36 46 1992 RO Exam # 37 47 1992 RO Exam # 38 48 RX trip P1rs what does not happen 49 ATW5' DSS testing'RPS tnp signal'CEDM response 50 1992 RO Exam A 39 51 1992 RO Exam # 40 52 1992 RO Exam # 41 53 1992 RO Exam # 42 54 1992 RO Exam
- 43 55 1992 RC Exam # 44 56 1992 RO Exam # 45 57 1992 RO L*am # 46 58 1992 RO Exi m # 47
$9 1992 RG Exam # 48 60 Basis for B'P of demin on hi temp 61 1992 RO Exam # $1 62 1992 RO Exam # 52
( 63 Auto isolation of S/G D'D i 64 1992 RO Exam # 54 T hursda). April 03,1997 Page 2 of 7
i Question # Question Topic 65 1992 RO Exam # $5 66 Refueling machine Q grapple operate tones 67 1992 RO Exam # 57 68 1992 RO Exam # 58 69 1992 RO Exam # $9 70 1992 RO Exam # 60 71 1992 RO Exam
- 62 72 1992 RO Exam
- 63 73 1992 RO Exam # 64 74 1992 RO Exam # 65 75 Orange path on S /no rod bottom lights do w hat?
76 1992 RO Exam # 66 77 1992 RO Exam # 67 78 1992 RO Exam # 68 79 1992 RO Exam # 69 80 1992 RO Exam
- 70 81 1992 RO Exam # 71 82 1992 RO Exam
- 72 83 Loss ofinstr air (A A 27) closure how?
84 1992 RO Exam
- 73 85 1992 RO Exam # 77 86 1992 RO Exam # 78 87 1992 RO Exam # 79 88 1992 RO Exam
- 81 89 1992 RO Exam
- 82 90 integ plant OPS invohing heating PZR 1120 91 Moving irradiated fuel wait?
92 1992 RO Exam # 84 93 1992 RO Exam # 85 94 Core geometry changes SR indication req'd 95 Realign CEA using long term' slow recovery 96 1992 RO Exam
- 87 97 Dropped CEA core efTects Thursda), April 03,1997 Page 3 of 7
)
, Question # Question Topic
~ 08 1992 RO Exam # 91 99 1992 RO Exam n 92 100 1992 RO Exam a 93 l% 2 - ,101 Routime surv tech spec implications 5 102 Operator expected regt's per OP 1 200 10 h ert-103 SOS is refueling super fire in T bdig w ho is Til leader 1 104 fire protection T S regt's
)
105 Cable' clip for locked vah e lef) ' free' 106 S G parameter w/TS regt j 107 Tagging order clearance 108 Temp mod req'd yellow tagging 109 Tagging violation who reinstates 110 Locked rad area why? 111 Priority RWP pre job brief by' 112 Mas dose to extremities to protect vital equip 113 Lowest event class for EOF /TSC/OSC manning i14 Mb imum PAG for general emergency i15 White phone hotline usage 116 Procedure type for TPC process 117 DCR drawing type not getting PSS/ SOS approval 118 P 61S aligned as spray /what trips P-615 on RAS 4 119 CE A mimic indicating lights 120 RX trip breaker combo for opening 121 NLa-trippable CEA works how? 122 CEA withdrawal prohibit generation 123 DifTerence between sheared & locked rotor 124 Operating RCP's w/o sealinjection 125 Demineralizer release of boron to RCS 126 CilG pump control on CR esac 127 Transferring normal to alternate charging & letdown 128 Use of BA-A 80 129 MU to RCS w/ alternate UD 130 MS-219 shut <50*. why? , 1hursda), April 03,1997 Page 4 of 7
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l Question # Question Topic I i s 131 P. C trips @ 75% pwr what happens' 132 Response of EFW valves to system press (good IPQ) 133 TK 25 air D'U for' 134 D/G stan CKTRY power supplies 135 Core uncovery WR log channel does what' 136 B'S for SOT causing trip >l5% 137 Crosstied MCC's O'C tripindication on Ltic 138 ATWS' DSS functions how' 139 plTS reference leg cooling 140 Prevent RCS loop Tc valve opening 141 IPQ about ECCS during LOCA @ RCS of 200 psia 14: Flow path for hot leg injection 143 HPSI tech spec based on CB 144 DG l A failure & loss of ofTsite pwr affects PORVs how' 145 Conseg of PZR Br0 valve closed 146 PZR level control based on PZR level 147 Basis for progra amed PZR lesel 148 RPS trip protecting SAFDL specs 149 IPQ on RPS 11. PZR press trip 150 Purpose of LPMS 151 Norm'Emer key for DG-1 A in normal 152 DG start failure how? 153 Cont integ T.S 154 RPS main turb trip 155 PCC restart on load shed 156 STM dump & turb B'P Q O signal 157 Turb B 'P mode select switch 158 Time hmit for hotleg injection 159 PZR htr bras: handle key to ' emergency' 160 CEA misalignment problem 161 Two CEA's inoperable / continued OPS 160 Dropped CEA'long term slow recovery why 50'6 163 Dropped CEA' turbine load down to match' 1 hursday, April 03,1997 Page 5 of 7
1 Question # Question Topic 164 Continuous CEA withdrawalIPQ 165 LOCA sice SLB indications 166 LOCA w/25 degree Scht no RCP's why' 167 Turbine trip failure how to respond 168 PTS event 169 RCP seal failure question 170 RCP trip criteria 171 DG 1 A cooling B U on loss of PCC 172 ATWS'emer. boration'ait source' 173 l'R-C 2 orance & FR il I red w/ loss of all A'C do what? 174 liarsh cont criteria 175 CSFST order 176 hianual RX trip on condenser pressure 177 DP/ LAC loss initial actions 178 AOP's for firevwhy authorize T.S violations 179 When E O for a lite' 180 PADEP actions on CR evacuetich 181 Operator who trips turbine on CR evac 182 One train of 51 activates @ full pwr 183 PZR code safety leaking / downstream ternp 184 Bullets for EOP's used 185 Nat circ C/D & depress head voiding indication 186 ES 1.2 isolate SIT's (d 80aS!G press why? 187 E-O when initiate on SGTR? 188 AOP 2-49 RCS loop stops shut why? 189 SGTR level >U tubes why? 190 Concern during post SGTR C/D 191 Chg flow restrictor<375#' 192 Air bound LPSI during RIIR cause? 193 Loss of RilR/H'U to 212 degress to use S'Cis 194 TS PZR htr req'd >$00 degrees F why' 195 Feed water restoration S!G level <56'. why? 196 Tech spec regt's for RhtS? T hursday, April 03,1997 Page 6 of 7
Question # Question Topic _ _ _ _ 197 Valves failing open on loss ofI A 198 PZR les el indicated > actual how' 199 AOP 2 46 why are NRVs shut 200 181S isolation of purge by w hat' I i 4 .n i P J r l l
'Ihursda3. April 03,1997 Page 7 of 7
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) ES 301 Adminttrativs Topics Outline Form ES-301 1 I j Facility: Maine Yankee Date of Examination: June 9-12.1997 Exam Level (Circle)h/SRO (l) / SRO (U) Operating Test No.: , A.1 Conduct of K/A Generic 2.1.33 (3.4/4.0) AD-0104 7 l Operations Are you allowed to change plant conditions (condition 5 to 6) if you are in a 4 Remedial Action Statement? Where do you verify this? j l- , i K/A Generic 2.1.3 (3.0/3.4)' AD 0101-1 l
- Oncoming control room operator turnover
- Securcy Generic 2.1.2 (3.0/4.0) l JPM New 28 Performing control room actions for secunty Code Red (N)(T)(C).
J
, A.2 Equipment Generic 2.2.13 (3.6)
- Control JPM New 32 Validating White Tag out adequately (N)(C) 3 A.3 Radiation Generic 2.3.5 (2.3/2.5) AD-010313
- < Controi JPM New 31 Perform a hand and foot frisk. (N)(P)(R) l A4 Emergency K/A Generic 2.4.39 (3.3/3.1) AD-010211 Plan You are on your spare week when an " Alert
- condition is declared. Where do you
- report to during this classification?
4 K/A Generic 2.4.17 (3.1/3.8) AD-010210 What is the definition of an Unusual Evtc.t? j Put necessary abbreviations here: i
- _ Examination Standards Rev 8, PUBLIC
] NOTE i l= A.3-Justification for K/A less than 2.5 for RO- We frisk as we leave the RCA buildings to outsioe of the buildings in order to prevent spreading contamination to the ground. This .. makes fnsking at Maine Yankee an environmental as well as a personnel contamination issue. The SRO importance factor is 2.5 l for this K/A. The CRO at Maine Yankee certainly should have the same importance factor as the SRO on this task. i I .. i i i [
g. i ES 301 IndMdualWalk Through Test Outline Form ES 3012 Facility: Maine Yankee Date of Examination: June 9-12.1997 Exam Leve (Circle): /SRO (l) / SRO (U) Operating Test No.: System /JPM Title / Type Safety Function Planned Follow-ui Qa tions: Codes
- K/A/G //Importance.n U .2nption 4
- 1. 062/New #8 (N)(S) #6 a. 056-AA2.44(4.3/4.5) AC-0101 16
. Restoring site power What is significant of white light out for IR,2R,3R, & 4R
. from 115KV during loss control switches?
'\
- b. 062-A4.01 (3.3/3.1) AC-0101-4 What is the purpose of the reclose circuit on breaker?
- 2. 015/SNO-0905-12 #7 a. 015-K1.01 (4.1/4.2) RPS-01014 (D)(S) N1 Calibration How does the Ni signal enter the RPS ccuitry?
- b. 015-A3.03 (3.9/3.9) NI-0102 5
. Significance of HV B/S lit for RPS channel operability.
- 3. 010/PPC-090112 #3 a. 010-K2.01 (3.0/3 4) PPC-0102-10 (D)(S);L) PORV testing Backup HTR OPS from switchgear.
- b. 010-K4.01 (2.7/2.9) PPC-0102-9 Reasons for spray bypass flow.
- 4. 003/Nerf23/(N)(S)(L) #4 a. 003-K3.04 (3.9/4.2) RPS-01012 Establishhg RCP start Effect of stopping an RCP on RPS.
criteria fdiowing Rx trip
- b. 003 A1.07 (3.4/3.4) RCP-0902-2 Thrust reversal on an RCP during H/U.
- 5. 001/EAb-090111 #1 a. 004-A4.04(3.2/3.6) CRC-0101-97 (S)(A)(D) Stuck CEAs/ Final Boron Concentration required.
FR-S 1 immediate actions b. 001-A2.06 (3.4/3.7) CRC-010191 & 107 Relationship between SO & power level.
- 6. O'3/RMS-0901 12 #7 a. 072-K1.05 (2.8/2.9) RMS-0101-1 (O)(S)(C) Location of Main Steam Line Monitors Performing daily check of hp range PVS b. 072-A1.01 (3.4/3.6) RMS-0101-4 monitt,. (RM 3903) GM Tube protection in high rad area.
- 7. 054/DG-09013-1/(D)(S) #6 a. 064-K3.03 (3.6/3.9) DG-0102 5 Paralleling DG-1 A on to What is the purpose of the 3TS/4T6 normal / emergency Bus #5. keylock switch?
B. 064-A2.05(3.1/3.2) AD-0102-8, DG-01015 What is Se purposa of load limit knob on the Woodward Governor?
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, (L)ow Power, (P)lant, (R)CA (T)ime Critical Ex:mination Standards Rev. 8, PUBLIC
ES-301 Individual Walk-Through Test Outline Form ES-3012
; Facility: Maine Yankee Date of Examination: June 9-12 1997 Exam level (Circle)h/SRO (1) / SRO (U) Operating Test No.:
System /JPM Title / Type Safety Function Planned Follow-up Questions: Codes
- K/A/G // Importance // Description
- 8. 055/New #9 (N)(R)(A)(T) #9 a. 068-AK3.18 (4.2/4 5) SNO-0101-4 Perform local actions for Changing throttleable MDV direction.
primary side equipment for station blackout. b. 068-AA1.02 (4.3/4.5) AFW-0101-22 Significance of EFW Pump Room fan being inoperabic.
- 9. 001/EAS-0906-3-1 #1 a. 001-K3.02 (3.8/3 8) CEDS-0101 9 (P)(D) Interlock Logic associated with reed switches.
Manual operation of CEDM & Rx trip b. 012-A3.02 (3.6/3.6) AC-010173 breakers UV bistables/ relays on RPS breaker panel. 10.103/New #3/(N)(R) #5 a. 103-A3.01(3.9/4.2) C 010112 Isolating containment Verification of no sump pump discharge outside the locally during loss of all containment. A/C.
- b. 103-A4.01 (3.2/3.3) C-0101-5 Verification of position for leakage monitoring valves.
- 11. 061/EAS-09012-9 #4 a. 061-K4.02 (4.5/4 6) AFW-0101 12 (D)(S) Placing SS-EFW-Block switch in " Block".
Recovery from FW isolation b. 059-A2.07 (3.0/3.3) MFW-0102-17 Plant Trip Logic associated with MFP trip.
- 12. 004/New #10/(N)(R) #2 a. 004 A4.08(3.8/3 4) CVCS-0103-5 Aligning P 7 to a HPSI P-7 N/E switch on PABEP train.
- b. 004-AK6.15 (2.8/3.1) CVCS-0102-14 Vent paths for charging pumps
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, (L)ow Power, (P)lant, (R)CA (T)ime critical.
Extmination Standards Rev. 8, PUBLIC l l l l
ES 301 Administrativ2 Tepics Outlin) Form ES 3011 Facility: Maine Yankee Date of Examiration: June 9-12.1997 l ( Exam Level (Circle): RO /SRO (1) ho (U)'pperanng Test No.: A.1 Conduct of Genenc 2.4.28 (2.3/3 3) . , , SEO-0303-2 Operations Code Red FEMCO notification. '- Generic 2.1.5 (2.3/3.4) SNO-0302-10 What is the minimum operations shift staffing compliment required by Maine Yankee procedures. Generic 2.2.11 (2.5/3.4) GA 0302-1 Intent Change to a procedure Generic 2.2.30 (2.6/3.5) SURV-0301 3; SNO-0303-8 Required ventlaton lineup in the Fuel Building during fuel movement. A.2 Equipment Genenc 2.2.13 (3.6/3.8) Control JPM New 33 Tagging a Safety Class Component (N)(C)(S) A.3 Radiation Generic 2.3 5 (2.3/2.5) Control JPM New 34 Use of Survey Meters. (N)(P) A.4 Emergency Genenc 2.4.38 (2.2./4.0) Plan JPM-AD-0901 2 Implementing E-Plan Due to Loss of MCB Annunciators. (D)(T)(P or S) Put necessary abbreviations here: Ex:mination Standards Rev. 8. PUBLIC i
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i ES 301 Individual Walk Through Test Outline Form ES 3012 [ ' Facility: Maine Yankee Date of Examination: June 9-12 1997 Exam Level (Circle): RO /SRO (I) / SRO (U) Operating Test No/ Systam /JPM Title / Type Safety Function l Planned Follow-up Ouestions: Codes
- K/A/G // Importance // Desenption
- 1. 013/ESF-090111 #2 (D)(S) Performing ESF a. 013-K4.12 (3.7/3.9) SNO-0303-3-13 ESF-0101-4&S Actions & Conditions to block RAS.
Panel OPS to recover from inadvertent STAS b. 013-A2.05(3.7/4.2) ECCS-0101 3 Loss of Control Power for SIAS 86 Device ( 2, ' 005/New #25 (N)(S)(L) #4 Performing RHR FAST a. 005-A2.02(3.5/3.7) RHR-0101-5&B RHR protection from overpressure transients. S/U dunng Post-LOCA Cooldown
- b. Generic 2.1.33 (3.4/4.0) ISR 03013, SNO 0303-9&13 Purpose of dedicated operator.
1
- 3. 015/NI-090111(D)(S) #7 a. 015-A3.03 (3 9/3.9) INCA-0101-3, SNO-0303-9&10 Establishing Altemate l incere Alarms /Venfy Validity.
Symmetric Offset l
- b. 071-K4.06 (2.713.5) SNO-03041 Use of ODCM During Gas Release 4.
064/New #15/(N)(A)(P) #6
- a. Generic 2.2.23 (2.6/3 8)
Startng DG-1B locally GA-0307 5 Purpose of 10CFR50.54X Implementation during SBO.
- b. Generic 2.2.8 (1.8/3.3) GA-0301 5 Purpose of 10 CFR 50.59 review
- 5. 033/New #4 (N)(R)(T) #8
- a. Generic 2.1.6(2.1/4.3)
Performing local acdons SNO-0302 5 Short Term , Event Reporting for primary side equipment during loss of all AC. b. 033-K4.01 (2.9/3.2) SFP-0401 11 Purpose of suction flange in Spent Fuel Pool
- 6. 059/MFW-090121 #4 a. 059-K4.02 (2.3/3.5) MFW-010217, MT-01019 (D)(P)(A)(T) Local X Effect of a MFWP Trip on Main Turbine.
Tnpping of P-2C
- b. 059-K6.09/2 4/2.6) MFW 010219 P-2C recire valve position
* - Type (P)lant, Codes:
(R)CA (T)ime (D)irect Cntcal.from bank, (M)odified from bank. (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, (L)ow Po Examination Standards Rev. 8, PUBLIC I i l g5
ES 301 Administrative Topics Outline Form ES-301 1 Fccility: Maine Yankee Date of Examination:. June 9-12.1997 Exam Levol(Circle): RO /SRO (l) /@RO(UNperating Test No.: A.1 Conduct of Generic 2.4.28 (2.3/3.3) SEO-0303-2 Operations Code Red FEMCO notification. Generic 2.1.5 (2.3/3.4) SNO-0302-10 ) What is the minimum operations shift staffing comphment required by Maine Yankee procedures. Generic 2.2.11 (2.5/3.4) GA-0302-1 Intent Change to a procedure Generic 2.2.30 (2.6/3.5) SURV-0301-3; SNO-0303-8 Required ventilation lineup in the Fuel Building during fuel movement. A.2 Equipment Generic 2.2.13 (3.6/3.8) Control JPM New Tagging a Safety Class Component. (N)(C)(S) A.3 Radiation Generic 2.3.5 (2.3/2.5) Control JPM New Performing a hand and foot frisk. (N)(P) A.4 Emergency Generic 2.4.38 (2.2./4.0) Plan JPM-AD-0901 2 Implementing E-Plan Due to Loss of MCB Annunciators. (D)(T)(P or S) Put necessary abbreviations here: Ex:mination Standards Rev. 8 PUBLIC
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- --.~ . - -. - . - . . - -
ES-301 Individual Walk Through Test Outline Form ES 3012 Facility:- Maine Yankee Date of Examination: June 9-12.1997 Exam level (Circle): RO /SRO (1) / SRO (U) Operating Test No.: System /JPM Title / Type Safety Function - Planned Follow-up Questions: Codes
- K/A/G // Importance // Description
- 1. 013/ESF-0901 1-1 #2 a. 013-K4.12 (3.7/3.9) SNO-0303-3-13 ESF-01014&S (D)(S) Performing ESF Actions & Conditions to block RAS.
Panel OPS to recover from inadvertent SlAS b. 013-A2.05(3.7/4.2) ECCS-0101 3 Loss of Control Power for SlAS 86 Device
- 2. 005/New #25 (N)(S)(L) #4 a. 005-A2.02(3.5/3.7) RHR 01015&B Performing RHR FAST RHR protection from overpressure transients.
S/U during Post-LOCA Cooldown b. Generic 2.1.33 (3.4/4.0) ISR-03013, SNO-0303 9&13 Purpose of dedicated operator.
- 3. 015/NI-0901-1-1(D)(S) #7 a. 015-A3.03 (3.9/3.9) INCA-0101-3, SNO-0303-9&10 Establishing Alternate incore Alarms /Venfy Validity.
Symmetric Offset
- b. 071 K4.06 (2.7/3.5) SNO-0304-1 Use of ODCM Dunng Gas Release
- 4. 064/New #15/(N)(An #6 a. Generic 2.2.23 (2.6/3.8) GA-0307-5 Starting DG-1B locally Purpose of 10CFR50.54X Implementation during SBO.
- b. Generic 2.2.8 (1.8/3.3) GA-0301 5 Purpose of 10 CFR 50,59 review
- 5. 033/New #4 (N)(R)(T) #8 a. Generic 2.1.6(2.1/4.3) SNO-0302-5 Performing local actions Short-Term Event Reporting for primary side equipment during loss of all AC. b. 033-K4.01 (2.9/3.2) SFP-0401-11 Purpose of suction flange in Spent Fuel Pool
- 6. 059/MFW-0901-2-1 #4 a. 059-K4.02 (2.3/3.5) MFW-0102-17, MT-0101-9 (D)(P)(A)(T) Local Effect of a MFWP Trip on Main Turbine.
Tripping of P-2C
- b. 059-K6.09/2.4/2,6) MFW-010219 P-2C recirc valve position
* -Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ttemate path, (C)ontrol room. (S)imulator, (L)ow Power, (P) lint, (R)CA (T)ime Critical.
Ex:rnination Standards Rev. 8. PUBLIC
ROCC/SROCC 97-01 SCENARIO #1 l EVALUATED EVENTS: 1. SG Pressure' Instrument Failure. i
- 2. Dropped Rod
- 3. Partial Loss of Off Site Power and Loss of Heat Sink.
INITIAL CONDITIONS / SHIFT TURNOVER: 90% power, Turbine Driven Main Feed Pump (P-2C)in operation, ! Emergency Feed Pump P-25C Out-Of-Service,24 hours into remedial action for Technical Specification 3.8E due to maintenance of P-25C. DISCUSSION: The scenario objectivos are to:
- 1. Evaluate the crew response to a failure of a SG Pressure instrument.
- 2. Evaluate the crew in their use of AOP 2-21, MISALIGNED (DROPPED) CEA.
- 3. Evaluate the crew response in their use of FR-H.1, LOSS OF SECONDARY HEAT SINK.
The crew will receive a shift turnover. Shortly after the crew assumes the watch, there will be a failure low of #1 SG Channel A Pressure instrument. Technical Specification 3.9, " Operational Safety Instrumentation, Control Systems and Accident Monitoring Systems," should be referenced for operability requirements of low SG pressure instrument channel. Next, a control rod will drop into the core. The control rod wi!l be prevented from withdrawal for at least 15 minutes so that a power reduction will take place to meet the requirements of Technical Specification 3.10. "CEA Group, Power Distribution, Moderator Temperature Coefficient Limits and Coolant Conditions." The crew will also reference AOP 2-21, MISALIGNED (DROPPED) CEA. PREPARED / REVISED BY: DATE: 7 REVISION NO: a 0 DATE: 4/4/97 APPROVED BY: DATE: 8/h/f 7 7 / [ SCENARIO #1 Page 1 of 13
SCENARIO #1 I
-OlSCUSSION: (Continued)
A rightning strike in the 345 KV yard will cause a Loss of 345KV. A coincident Loss of Reserve Transformer X-16 will occur. The plant will trip with a loss of Bus 1 and Bus 2. The crew should enter E-0 and transition to ES 0.1. Emergency Feedwater Pump P-25A will fail to Auto Start on low SG level due to an electncal failure. The crew should recognize there is no feedwater and attempt to start the turbine driven i Jxiliary Feedwater Pump P-25B. MS-T-173 will be found in the tripped position and cannot be reset. The crew will transition to FR-H.1, LOSS OF SECONDARY HEAT SINK, when the Critical Safety Functions are evaluated. The crew should attempt to restom feedwater flow by reducing SG pressure and using the condensate aumps, it may be necessary for the crew to establish a primary " Feed and Bleed" i" plant conditions deteriorate. The scenario will terminate when feed via the condensate system per FR-H.1 has been established or feed and bleed has been initiated. SCENARIO #1 Page 2 of 13
SCENARIO #1 SIMULATOR OPERATORS SCHEDULE t NOTE: Times may be adjusted at the discretion of the examiner and changes should be noted. INITIAL CONDITIONS: 90% POWER, P25C WTO 1 MALF # EVENT # TIME (min.) I/O # DESCRIPTION O IC-15 90% Power P-25C PTL P-25C WTO. P-14B running 1 5 1/0 RP,MTR page override Fails LIA 1213V Low (SG #1 Level, PIC-1013A,0 RPS CH. C) 2 15 RD01,,,41 Drops rod 41 and prevents withdrawal. 3 30 FWO3A Failure of P25A-Bearing very hot to or as soon as the touch and acrid smell. a 2% Rx power drop is CV20(A,B, or C) Failure of STBY HPSI Pump to start. observed Can start manually. resulting from operator FWO4 Failure of P258-cannot reset boration, overspeed trip ED07A,,4 Failure of K378-1 ED07D,,4 Failure of KG1/375 EG02A,,4 Failure of X-1 A ED038,,4 Failure of X-16 Termination Point: Crew has transitioned to FR-le.1, restored feed water flow, and is in the process of terminating feed and bleed operations. (NOTE: Terminating Feed and Bleed operations m:ay not occur if it was never initiated.) i 4 4 1 i I 4 SCENARIO #1 Page 3 of 13
! SCENARIO #1 l Page 1 of 3 i EVALUATION GUIDE NO 1 EVENT NO. 1 dVENT DESCRIPTION: SG Pressure Instrument Failure RELATED TASKS IMPORTANCE FACTORS 1199030102 3.7 SAT -S UNSAT -U POSITION EXPECTED BEHAVIOR NOT OBS. - NO SOS Diagnoses the event as a failure of SG #1, Channel A Pressure instrument. (TI-122CC) COMMENTS: l SOS Notifies I&C of pressure instrument failure. COMMENTS:
-SOS References Technical Specification 3.9, " Operational Safety Instrumentation, Control Systems, and Accident Monitoring Systems,"
and determines Channel A is operable and therefore does not enter remedial action. COMMENTS: PRO Recognizes by indications and alarms that SG #1, Channel A Pressure instrument has failed low and informs the SOS. COMMENTS: SCENARIO #1 Page 4 of 13
. .... _._... . . ._ ......_ _ _ . _ .~ _ _ . . . . _ .
__.____.__..___._._.._.7-.._.._. - SCENARIO #1
- Page 2 of 2 F
i EVALUATION GUIDE NO.1 - - EVENT NO. 1- !d 6 VENT DESCRIPTION: SG Pressure Instrument Failure l-. SAT -S i UNSAT -U i POSITION. EXPECTED BEHAVIOR- NOT OBS. - NO i i ALL Exchanges complete and relevant information per OP 1-300-6,
- OPERATIONAL COMMUNICATIONS.
l- COMMENTS: i Termination Point: When the inoperable instrumentation has been identified and Technical Specification 3.9 has been referenced. COMMENTS: ADDITIONAL COMMENTS: l SCENARIO #1 Page 5 of 13 1 l
- - . - . - . - . ... . . .- . .-- . .-. . - - - . . ,- =
l SCENARIO #1 Page '1 of 4 EVALUATION GUIDE NO.1 EVENT NO. ._2_. 1 cVENT DESCRIPTION: Dranaad Rod - I l RELATED TASKS IMPORTANCE FACTORS l l 0009300501 3.1 1199030102 3.7 CREW CRITICAL TASKS Crew conducts a power reduction by at least 10% within E minutes from the time the rod dropped LAW Technical Specification 3.10 and O 1-4. CEAs must be maintained above the predrop power level Power Dependant insertion Limit (PDIL). SAT. -S UNSAT -U POSITION ' EXPECTED BEHAVIOR NOT OBS. - NO SOS References AOP 2-21, MISALIGNED (DROPPED) CEA. COMMENTS: SOS Notifies I&C Department, Reactor Engineering, and the Manager of l Operations Department. COMMENTS: SOS * ~ Directs power reduction by at least 10% within E minutes from the time the rod dropped LAW Technical Specification 3.10 and OP 1-4, i while maintaining CEA's above the predrop power, Power Dependent-
- Insertion Limit (PDIL).
i COMMENTS: SOS. Directs or ensures BOP operator has balanced turbine load to stabilize T between 500*F and 551.3'F. COMMENTS: l-SOS Directs PRO to select manual individual on the dropped CEA and attempt to realign it. { COMMENTS: i
' Safety Critical Task i
i
' SCENARIO #1 Page 6 of 13
SCENARIO #1 i Page 2 of 4 EVALUATION GUIDE NO,1 EVENT NO. _2_.
.iVENT DESCRIPTION: Droceed Rod RELATED TASKS IMPORTANCE FACTORS 0009300501 3.1 0019030502 2.9 0019010502 3.0 SAT -S UNSAT -U POSITION EXPECTED BEHAVIOR NOT OBS. - NO SOS Directs the control rod withdrawal IAW AOP 2-21, MISALIGNED (DROPPED) CEA.
COMMENTS: PRO Interprets annunciators and indicators to determine there is a single dropped rod #41 and informs the SOS. COMMENTS: PRO Resets the computer pulse indicating system to reflect the misaligned CEA height. COMMENTS: PRO Selects manual individual on the misaligned CEA and attempts to align it. COMMENTS: PRO / BOP
- Initiate s a power reduction as dimeted by SOS to decease power at least 10% within 20 minutes fron the time the rod dropped, IAW Technical Specification 3,10 and OP 1-4. Maintain CEA's above the predrop power level Power Dependent Insertion Limit (PDIL).
COMMENTS:
*Sofety Critical Task SCENARIO #1 Page 7 of 13
!' SCENARIO #1
< Page 3 of 4 j EVALUATION GUIDE NO.1 EVENT NO. _2_
- e ll ! dVENT DESCRIPTION: Dronood Rod-4
- RELATED TASKS IMPORTANCE FACTORS ;
4 0009300501 3.1 . i 0459010502- ' 3.0 i-4 SAT -S ' i - . UNSAT -U l POSITION EXPECTED BEHAVIOR . NOT OBS. - NO p - i PRO. Performs control rod withdrawal IAW AOP 2-21, MISALIGNED (DROPPED) CEA, as directed by the SOS. ! COMMENTS: i BOP Balances turbine load to stabilize T, between 500*F and 551.3*F as ll directed by the SOS. ! COMMENTS: J t j ALL Correctly implements procedures, including following procedure steps j in correct sequence. Abiding by cautions, precautions, and initial
- _ conditions.
4 4 COMMENTS: 1 1 i 2-ALL Exchange complete and relevant information IAW OP 1-300-6,- OPERATIONAL COMMUNICATIONS. 4 i COMMENTS: i Termination Point: Reactor Power has been decreased by at least 2% ,- by boration.
- j. COMMENTS:
t-p i i F 3 1
- SCENARIO #1 Page 8 of 13 i-
~ . _ . . _ , _ _ _ _ _
i E SCENARIO #1 Page 4 of 4 1 EVALUATION GUIDE NO.1 EVENT NO. _2_ -
'i'
, .iVENT DESCRIPTION: Dronned Rod ,
-1 1
.l 4
RELATED TASKS IMPORTANCE FACTORS 4 -! i SAT - S i . UNSAT -U POSITION . EXPECTED BEHAVIOf: NOT OBS. - NO , CREW Crew commences a power reduction by at least 10% within 3Q minutes
- from the time the rod dropped IAW Technical Specification 3.10 and
< OP 1-4. CEAs must be maintained above the power level Power
- Dependent insertion Limit (PDIL).
i COMMENTS: ! Additional Comments: s 1 .i L 4 L i ? 1 \ v i I i j 'Safaty Critical Task 4 i SCENARIO #1 Page 9 of 13
+- * - . - - _ - ----
, .- ___,.a e+c- -e---- g x
SCENARIO #1 Pcg21 of 4 EVALUATION GUIDE NO.1 EVENT NO. __3_
.-VENT DESCRIPTION: Loss of All Feed REl.ATED TASKS IMPORTANCE FACTORS l 0009190501 4.7 CREW CRITICAL TASKS Crew restores feed via the Condensate System per FR-H.1 or initiates " Feed and Bleed
- if plant conditions deteriorate to initiation criteria of FR-H.1.
SAT -S UNSAT -U POSITION EXPECTED BEHAVIOR NOT OBS. - NO SOS Ensure the Critical Safety Function (CSF) status trees are monitored when requi ed. - COMMENTE: SOS
- Verifies the inImediate action steps of E-O are performed when the plant trips.
COMMENTS: SOS
- Transitions out of E-0 to ES 0.1 and then to FR-H.1 due to critical safety function status trees.
COMMENTS: SOS
- Continues to direct the steps of FR-H.1, and directs initiation of " Feed and Bleed",if necessary.
COMMENTS: SOS Continues to direct the steps of FR-H.1 and attempts to restore feed via the condensate system. COMMENTS: SCENARIO #1 Page 10 of 13
SCENARIO #1 Page 2 of 4 ) EVALUATION GUIDE NO.1 EVENT NO. _3 1 I .iVENT DESCRIPTION: Loss of All Feed RELATED TASKS IMPORTANCE FACTORS 0009020502 3.9 0009010502 4.6 SAT -S UNSAT -U POSITION EXPECTED BEHAVIOR NOT OBS. - NO SOS Directs BOP to start the turbine driven auxiliary feed pump, P-258. COMMENTS: SOS Continues to direct steps in FR-H.1. COMMENTS: SOS Investigates the failure of plant equipment and initiates action to repair the equipment. COMMENTS: PRO Performs further actions of E-0, ES-0.1, and FR-H.1 as directed by the SOS. COMMENTS: PRO Maintains primary inventory control as directed by SOS. COMMENTS:
' Safety Critical Task SCENARIO #1 Page 11 of 13
SCENARIO #1 Pcga 3 of 4 EVENT NO. _3_ EVALUATION GUIDE NO.1
? ' cVENT DESCRIPTION: Loss of All Feed IMPORTANCE FACTORS 4
RELATED TASKS 3.3 0619010502 3.2 0619030502 SAT -S UNSAT -U NOT OBS. - NO POSITION EXPECTED BEHAVIOR BOP
- Recognizes emergency feed water purnp P 25A did not Auto Start and attempts to start P-25A. Informs the SOS.
COMMENTS: BOP
- Recognizes that there is no feed flow to the steam generator and attempts to start P 258, turbine driven auxiliary feed pump, and informs the SOS. (The fact that there is not feed flow may be picked up by other crew members at the onset of the event.)
COMMENTS: BOP Performs further actions of E-0, ES-0.1, and FR H.1 as directed by the SOS. COMMENTS: ALL Correctly implements procedures including following procedural steps in correct sequence, abiding by cautions, precautions, and initial conditions. COMMENTS:
- Safety Critical Task l
Page 12 of 13 SCENARIO #1 l
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=
SCENARIO #1 i Page 4 of 4 EVALUATION GUIDE NO.1 EVENT NO. ._3_ ( iVENT DESCRIPTION: Loss of All Feed SAT- -S UNSAT' - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO ALL Exchange complete and relevant information per OP 1-300-6, OPERATIONAL COMMUNICATION. e COMMENTS: i J 4 Termination Point: Crew has transitioned to FR-H.1 and has restored feed flow or have initiated feed and bleed. COMMENTS: CREW
- Crew restores feed via the Condensate System per FR-H.1 or initiates
" Feed and Bleed
- if plant conditions deteriorate to initiation criteria of FR-H.1.
COMMENTS: ADDITIONAL COMMENTS:
'Stfety Critical Task i
l SCENARIO #1 Page 13 of 13 l 1 1
RO/SRO 97-01 SCENARIO #2 EVALUATED EVENTS: 1. Tcking P-2C out of service (pow;r dccrsass)
- 2. Loss of Instrument Bus DP/ PAC l
- 3. SG tube leak (power decrease) 1 4. SG tube rupture.
I INITIAL CONDITIONS / - - SHIFT TURNOVER: 60% POWER, P-2C in operation. Take P-2C out of service and decrease power at 10%/hr due to a small EHC leak at the intercept valve. No equipment Out of Service and no Technical Specification remedial actions. DISCUSSION: The scenario objectives are to: . 1. Evaluate the crew taking the Turbine Driven Main Feed Pump (P-2C) out of service and commence a power decrease IAW OP 1-4, OPERATIONS AT POWER.
- 2. Evaluate the crew on their use of the AOP 2-11, LOSS OF INSTRUMENT BUS.
- 3. Evaluate the crew on their use of the STEAM GENERATOR TUBE LEAK procedure, AOP 2-49 and T.S. 3.14.
- 4. Evaluate the crew in mitigating a Steam Generator Tube Rupture (SGTR) by equalizing Reactor Coolant System pressure with the rup;ured steam generator pressure.
The operators will assume the watch with the plant at 60% power with a power decrease in progress P-2C will be shutdown IAW - OP 1-104-5, TURBINE FEED PUMP OPERATION AND ONE MOTOR DRIVEN FEED PUMP will be placed in operation. A SG tube leak will develop at 4 GPM. AOP 2-49 should be referenced and a power reduction started. (A power reduction is already in progress so they may continue with it) Also Tech. Spec. 3.14 "RCS Leakage" should be referenced. 1 The SG tube leak will become a rupture and the plant will be tripped. The operators should reference E-0 and E-3. On the trip, a CEA will be stuck out and a turbine stop valve will fail to close. ~ PREPARED / REVISED BY: DATE: b REVISION NO: 0 DATE: 02/19/97 - - APPROVED BY: > DATE: MN47
- /
SCENE #2 PAGE 1 OF 10
SCENARIO #2 SIMULATOR OPERATORS SCHEDULE
- !- Initial Conditions
- 60% POWER, P-2C in operation. Take P-2C OOS and decrease power at 10%/hr. No equipment out of service and no TECH. SPEC.
remedial actions. 3 Mate: Times may be adjusted at the discretion of the examiner and changes should be i noted. i
. - MALF #
EVENT # TIME (min.) I/O # DESCRIPTION O 60% PWR IC P-2C in service 1 0 Decrease power and take P-2C OOS. 2 20 ED12A Loss of DP-PAC. 3 30 SG02B,,,4- SG Tube Leak @ 4 GPM. Ensure at least a 2% pwr decrease across the whole scenario to this point before moving on to the stuck CEA 4 40 RD02,,,53 - STUCK CEA TC09A- Failure of Turbine Stop Valve to Close SG01 B,,,5 SG TUBE RUPTURE - 200 GPM When an NPO is directed to make the loop stops operable, Loop 2 Tc will - not be able to be energized. Termination Point: Within 45 minutes the RCS has been depressurized to the ruptured SG pressure. SCENE #2 PAGE 2 0F 10
7 _ .__ _ _ _ __. _______.__.._.._.__._.___.._.__.._____.__7... , i'- SCENARIO #2 Pegs 1 of 1
't EVALUATION GUIDE NO._2_ EVENT NO. _L i EVENT DESCRIPTION: Takina P-2C Out of Service y
RELATED TASKS IMPORTANCE FACTORS l 0599020101 3.0 - 4 CREW CRITICAL TASKS i NONE 4 l SAT - S UNSAT-: - U
- - POSITION EXPECTED BEHAVIOR NOT OBS, - NO I, SOS Directs the BOP to take P-2C OOS service IAW OP 1-104 5, TURBINE DRIVEN FEED PUMP OPERATION, COMMENTS
i , BOP Correctly takes P-2C OOS service IAW OP 1-104 5, TURBINE DRIVEN FEED PUMP OPERATION and commences a power j decrease IAW OP 1-4, OPERATIONS AT POWER. 4 COMMENTS: } PRO Commences a power decrease IAW OP 1-4, OPERATIONS AT POWER. If COMMENTS: ALL Correctly implements procedures, including following procedure steps in correct sequence abiding by cautions, precautions, and initial l conditions. 4 COMMENTS: ALL Exchange complete and relevant information IAW OP 1-300-6, j OPERATIONAL COMMUNICATION, COMMENTS: Termination point: MDFP has been placed in service and a power decease has commenced. COMMENTS: i
,- ADDITIONAL COMMENTS:
I a , ' Safety Gntical Task SCENE #2 PAGE 3 0F 10 J,
SCENARIO #2 l Pcgn 1 of 2 -! l g EVALUATION GUIDE NO. 2. EVENT NO. 2.
._ EVENT DESCRIPTION: Loss of Instrument Bus DP/ PAC
, I i
- RELATED TASKS IMPORTANCE FACTORS
- 0009240501 2.9
. CREW CRITICAL TASKS i NONE L SAT - S f . - - UNSAT - U
! POSITION ' EXPECTED BEHAVIOR NOT OBS,- NO i ' SOS Diagnoses the transient as a loss of DP/ PAC instrument bus. COMMENTS:
)
i. SOS- Directs a transfer to the alternate power supply for DP/ PAC per AOP ; 2-11, LOSS OF INSTRUMENT BUS. COMMENTS: j I SOS Directs the subsequent actions of AOP 2-11 for loss of DP/ PAC. l COMMENTS: PRO Performs actions of AOP 2-11 as directed by SOS. COMMENTS: -;
-I BCP Recognizes by indications and alarms that a loss of DP/ PAC has occurred and informs SOS.
COMMENTS: BOP Transfer DP/ PAC to the alternate supply as directed by the SOS. COMMENTS: 1
- Safety Critical Task SCENE #2 PAGE 4 OF 10 l
4
SCENARIO #2 Paga 2 of 2 EVALUATION GUIDE NO. 2_ EVENT NO. 2. EVENT DESCRIPTION: Loss of instrument Bus DP/ PAC SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO ALL Correctly implements procedures, including following procedural steps in correct sequence, abiding by cautions, precautions and initial conditions. COMMENTS: ALL Exchange complete and relevant information LAW OP 1300-6, OPERATIONAL COMMUNICATIONS. COMMENTS: Termination Point: Alternate power to DP/ PAC has been selected and the plant stabilized. COMMENTS: COMMENTS: COMMENTS:
- Safety Critical Task SCENE #2 PAGE 5 0F 10
SCENARIO #2 Paga 1 of 2 EVALUATION GUIDE NO._2_ EVENT NO. _3. EVENT DESCRIPTION: SG Tube Leak - i RELATED TASKS IMPORTANCE FACTORS 0009130501 5.0 0029030502 3.3 1199030102 3.7 CREW CRITICAL TASKS NONE SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO SOS Diagnose the event as a SG tube leak in #2 SG. COMMENTS: SOS References AOP 2-10, LOSS OF PRESSURE CONTROL /RCS LEAK, AOP 2-25, HIGH RADIATION LEVELS or AOP 2-49, STEAM GENERATO 1 TUBE LEAK. COMMENTS: SOS
- References Technical Specification 3.14, PRIMARY LEAKAGE, and enters into remedial action.
COMMENTS: SOS
- Directs the actions of AOP 2-49 to include a power reduction corresponding with leakrate or A/E RMS value.
COMMENTS: PRO Diagnoses alarms and indications as a SG tube leak of approximately 4 GPM and informs the SOS. COMMENTS:
- Safety Critical Task SCENE #2 PAGE 6 0F 10
! SCENARIO #2 l- , Pcga 2 of 2 EVALUATION GUIDE NO. 2._ EVENT NO. 3. EVENT DESCRIPTION: SG Tube Leak i \ i
~
SAT: -- S = UNSAT - U . POSITION EXPECTED BEHAVIOR NOT OBS. - NO i PRO Perform the actions of AOP 2-49 to include a power reduction as
- j. directed by SOS.
j OOMMENTS: i i p , j ALL Correctly implements procedures, including following procedure steps ! in correct sequence abiding by cautions, precautions, and initial . conditions. 1 - l COMMENTS: i ALL Exchange complete and relevant information LAW OP 1-300-6, OPERATIONAL COMMUNICATION. COMMENTS: Termination Point: A power reduction has been started IAW AOP 2-49. COMMENTS: ADDITIONAL COMMENTS:
- Safety Critical Task SCENE #2 PAGE 7 0F 10
i SCENARIO #2 Page 1 of 3
. EVALUATION GUIDE NO. 2_ EVENT NO. _4_
i' j - EVENT DESCRIPTION: SGTR RELATED TASKS IMPORTANCE FACTORS 0029030502 3.3 1199030102 3.7 I
- 1 CREW CRITICAL TASKS l l-Crew diagnoses steam generator tube leak greater than 10 gpm, trips the plant and enters E-0. Crew mitigates tube rupture within d5 minutes of the trip by equalizing RCS pressure with ruptured SG.
i SAT - S UNSAT - U ! POSITION EXPECTED BEHAVIOR NOT OBS. - NO 4 SOS Diagnoses the problem as a SG tube rupture. COMMENTS: i , SOS
- Directs the PRO and BOP to trip the plant when RCS leakage is greater than 10 GPM.
l COMMENTS: i-4 SOS Ensures. Critical Safety Function (CSF) status trees are monitored j when required. i i COMMENTS: 1 i. j SOS * - Within 45 minutes of the trip the RCS pressure is equal to the 4 ruptured SG pressure. 1 COMMENTS: i-SOS
- Verifies the immediate actions of E-0 are performed when the plant :
i- trips. l
- COMMENTS
- l ie _
l
.
- Safety Critical Task i
l SCENE #2 PAGE 8 0F 10 L w - - - -
, ._-,e,_ ---- - --r- - - - - , - - --
SCENARIO #2 Page 2 of 3 EVALUATION GUIDE NO._2_ EVENT NO. 4 EVENT DESCRIPTION: SGTR _. 0%* RELATED 1 ASKS IMPORTANCE FACTORS 0009010501 4.3 0009130501 5.0 0009010502* 4.6 CREW CRITICAL TASKS NONE SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO SOS
- Continues to direct steps of E 0 and correctly transitions to E 3.
COMMENTS: SOS niinues to direct the steps of E 3. MMENTS: PRO Diagnoses from the annunciators and indicators that there is a SG leak and informs the SOS. COMMENTS: PRO
- Recognizes tnat there is a stuck CEA and informs the SOS.
COMMENTS: PRO Performs further actions of E-0 and E 3 as directed by the SOS. COMMENTS: BOP
- Recognizes the turbine stop valve did not cMO, places EHC pumps in PTL, and informs SOS.
COMMENTS:
- Safety Critical Task SCENE #2 PAGE 9 0F 10
SCENARIO #2 Pcge 3 of 3 EVALUATION GUIDE NO._2_ EVENT NO. ,f. EVENT DESCRIPTION: SGTR t SAT - S UNSAT - U { POSITION EXPECTED BEHAVIOR NOT OBS. - NO l i BOP Performs further actions of E 0 and E 3 as directed by the SOS. ! COMMENTS: ALL Correctly implements procedures, including following procedure 1,teps in correct sequence abiding by cautions, precautions, anc 3 ' tial conditions. COMMENTS: ALL Exchange complete and relebnt information LAW OP 1300 6, OPERATIONAL COMMUNICATION. I COMMENTS: Termination Point: Wilen RCS pressure equals the ruptt'ed SG pressure. COMMENTS: Crew diagnoses steam generator tube let.k greater than 10 gpm, trips the plant r.nd enters E-0. COMMENTS: Crew mitigates tube rupture within 45 minutes of the trip by equalizing RCS pressure with ruptured SG pressure. COMMENTS: ADDITIONAL COMMENTS:
' Safety Critical Task SCENE *2 PAGE 10 0F 10
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I ROCC/SROCC 97-01 SCENARIO #3
' EVALUATED EVENTS: 1. Running charging pump trips and Reactor Coolant Pumps
' (RCP) middle and lowur seal failure.
- 2. Nuclear Instrumentation detector failure.
- 3. Cold Leg Coolant Leak
- 4. Cold Leg Large LOCA INITIAL CONDITIONS /
- SHIFT TURNOVER: 30% power, MOL, holding power until SG chlorides come into spec.
Motor Driven Feed Pum P 2A in service, no major equipment Out Of Service, no Technical S ecification remedial actions. DISCUSSION: The scenario objectives are to:
- 1. Evaluate the crew in the use of the " Reactor Coolant Pumps Abnomialities" procedure, AOP 2 50.
- 2. Evaluate the crew response to a failure of a power range nuclear instrument fallure.
- 3. Evaluate the crew in the use of the " Loss of Pressure Control /RCS Leak" procedure AOP 210 and subsequent required power decrease.
- 4. Evaluate the crew in the use of E-1," Loss of Primary or Secondary Coolant" for a large break LOCA.
The crew will receive a turnover on the initial conditions. The crew will be told to maintain power. The running charging pump will fall due to a faulty Fuction pressure switch. The standby charging pump should start. I'he seal flow oscillation will cause the lower and middle seals of #2 RCP to fall. The operators should reference AOP 2 50," Reactor Coolant Pump Abnormalities", for guidance on operation with two seals failed. Technical S secification 3.6, "ECCS and Containment Spray , Systems," s1ould be referenced and the remedial action of C.2 should be entered until the cause of the pump trip is determined or the spare pump is aligned to the faulted train. The next event is a power range Nuclear Instrument lower detector failed High. Technical Specification 3.9 should be referenced and either the remedial action entered or the exception if l&C has been notified and is troubleshooting the fault. PREPARED / REVISED BY: DATE: f7 REVISION NO.: - 0 DATE: 02/19/97 APPROVED BY: [M M DATE: N,.U SEN#3 PAGE 10F 13
ROCC/SROCC 97-01 SCENARIO #3 A 20 GPM cold leg coolant leak u then initiated and ramped in over
; DISCUSSION (Cont'd):
15 minutes. The suml) level alarms and containment radiation alarms should iend the opere1or to determine there is RCS leakage into
- containment. A leak rate calculation should be performec and l AOP 210 and T.S. 3.14 should be referenced. At this point the crew I j may commence a power reduction, if they do not commence a
' power reduction within 5 minutes of entering AOP 210, the PSS will order a power reduction at 15% per hour based on the seal failures ' and the increasing leak rate. , A large LOCA la ram aed in over five minutes and when pressure controlis lost, a plans trip should be directed. The operators should
- handle the event with E-0 and E-1.
i . The operators should transition to FR P.1 upon evaluation of the CSF status trees. On the plant trip, the Low Pressure Safety in to start and will have to be manually started.jectionMain Feed A.mp,pump."A" P 2A, will fai will also trip. These two problems should be recognized during E-0. i 4 4 3 SEN#3 PAGE 2 OF 13
. ~ - , - - . ., - , - n.-,...- - , ,n- -- , , - - - - -, . - -- -,, . - - , , -
SCENARIO #3 SIMULATOR OPERATORS SCHEDULE i Initial Conditions- 30% power, MOL, holding power until SG chlorides come into s ac, Motor Driven Main Feed Pump P 2A in operation, no major equ pment Out Of Service no Technical Specification remedial actions. Ensure chart recorders are advanced and steady state. Nnte: Times may be adjusted at the discretion of the examiner and changes should be noted. MALF # EVENT # -TIME (min.) l/O # DESCRIPTION 0 30% PWR with P 2A in service 2.0 turns blowdown 1 5 CV12 (A) Falls the running charging um due to low suction pressure swa llure. C = spare pump Middle seal failure #2 RCP. CV15B Lower seal failure #2 RCP. CV148 2 15 N102C Falls Channel A lower detector high. 3 25 RC04C,,,10,00:15 Loop 3 Cold Leg Coolant Leak
@20GPM ramped in over 15 minutes.
PSS will order power reduction @ 15% per hr 5 minutes into AOP 210. Ensure a 2% power reduction is performed 4 40 RH05A Prevents the A LPSI pump from starting in SIAS. Pump can be manually started. RC04C,,,100,00:05 Laige break cold leg LOCA. FWO2A Trips P 2A MDFP, locks out 86 device. Termination Point: After the transition to E-1, and the CSF's monitoring has started. SEN#3 PAGE 3 0F 13
SCENARIO #3 Page 1 of 3 EVALUATION GUIDE NO._1 EVENT NO. 1 i EVENT DESCRIPTION: Runnino Charoina Pumo Trios and The RCP Middle and Lower Seal Failure , RELATED TASKS IMPORTANCE FACTORS 0039010502 3.0 0049010502 2.9 0039030502 2.9 CREW CRITICAL TASKS NONE
, SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO SOS Ensures the standby charging pump automatically starts or directs PRO to manually start the standby charging pump.
COMMENTS: SOS Informs PRO of RCP operationallimits with two seals damaged. COMMENTS-PRO Recognizes from alarms and indicators that the running charging pump has tripped. COMMENTS: PRO Recognizes from alarms and indicators that the lower and middle seals on #2 RCP has failed. COMMENTS: PRO Ensures the standby charging pump automatically starts or manually starts the standby pump when directed. COMMENTS:
- Safety Critical Task SEN#3 PAGE 4 0F 13 U
SCENARIO #3 Page 2 of 3 EVALUATION GUIDE NO. 3_. . EVENT NO. 1 i 2 VENT DESCRIPTION: Runnina Charoina Pumo Trios and The RCP Middle and Lower Seal Failure RELATED TASKS IMPORTANCE FACTORS 0039030502 2.9 0039010502 3.0 1199030102 3.7 0049010502 2.9 CREW CRITICAL TASKS NONE SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO SOS Diagnoses event as a loss of the running charging pump with subsequent failure of the lower and middle seals of #2 RCP. COMMENTS: I SOS References AOP 2 50, REACTOR COOT. ANT PUMP ABNORMAllTIES, for operational guidance with two failed seals. COMMENTS: SOS
- References and enters Technical Specification 3.6 remedial action for loss of High Pressure Safety injection (HPSI) pump until either the cause is determined and declared operable in standby or the spare HPSI pump is lined up for operation.
COMMENTS: SOS Directs investigation into the cause of the charging pump trip and calls for Maintenance / PED's assistance. COMMENTS:
' Safety Critical Task SEN#3 PAGE 5 0F 13
SCEt4ARIO #3 EVALUATION GUIDE @A gg Pa 3 3 EVENT DESCRIPTION: Runnino Charaina Pumo Trios and The RCP Middle and Lower Seal Failure RELATED TASKS IMPORTANCE FACTORS SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO ALL Correctly implements procedures, including following procedural i steps in correct sequence, abiding by cautions, precautions, and I initial conditions. j COMMENTS: 1 ALL Exchange complete and relevant information LAW OP 1300-6, OPERATIONAL COMMUNICATIONS. COMMENTS: Termination Point: Standby charging pump is running, Technical Specification 3.6 remedial action has been entered and #2 RCP seal failures have been identified. COMMENTS: ADDITIONAL COMMENTS:
- Safety Critical Task SEN#3 PAGE 6 0F 13
SCENARIO #3 Page 1 of 2 i EVALUATION GUIDE NO._3_ EVENT NO. _2 EVENT DESCRIPTION: Nuclear Instrumentation Detector Failure RELATED TASKS IMPORTANCE FACTORS 0159030502 3.0 1199030102 3.7 CREW CRITICAL TASKS NONE SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO l SOS Diagnoses the event as a failure of Nuclear Instrumentation (NI) l Safety Channel A lower detector high. I COMMENTS: l SOS Notifies l&C of Detector failure. COMMENTS: PSS/ SOS
- References Technical Specification 3.9 and either enters the remedial action or the exception if the criteria is met.
COMMENTS: PRO Recognizes power range Nuclear Instrumentation safety Channel A lower detector failed high by alarms and indicators and informs the l SOS. COMMENTS: ALL Exchanges complete and relevant information IAW OP 1-300-6, OPERATIONAL COMMUNICATIONS. COMMENTS:
- Safety Critical Task SEN#3 PAGE 7 0F 13
SCENARIO #3 Page 2 of 2 EVALUATION GUIDE NO. 2 EVENT NO. _2 I EVENT DESCRIPTION: p*- Instrument =tian Dae-r+ar Faihire RELATED TASKS IMPORTANCE FACTORS SAT - S l UNSAT - U ! POSITION . EXPECTED BEHAVIOR NOT OBS. - NO Termination Point: When the detector has been identified and Technical Specification 3.9 has been referenced. COMMENTS: ADDITIONAL COMMENTS:
' Safety Cntical Task SEN#3- PAGE 8 OF 13
SCENARIO #3 Page 1 of 2 , EVALUATION GUIDE NO. L EVENT NO. L I EVENT DESCRIPTION: Small RCS Laak in Containment RELATED TASKS IMPORTANCE FACTORS 0029030502 3.3 0009520501 3.9 1199030102' 3.7 CREW CRITICAL TASKS NONE SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. NO SOS Diagnoses the event as a RCS leak in containment. COMMENTS: SOS References AOP 210, LOSS OF PRESSURE CONTROL /RCS LEAK. COMMENTS: SOS
- References Technical Specification 3.14, " Primary Leakage," and enters into the remedial action which willinclude a plant shutdown LAW T.S. 3.0A.
COMMENTS: SOS Directs actions of AOP 2-10. COMMENTS: PRO Diagnoses alarms and indications as RCS leakage in containment. COMMENTS: PRO Performs actions of AOP 2-10 when directed which will include a power decrease. COMMENTS:
'S:fety Critical Task SEN#3 PAGE 9 0F 13
)
l l SCENARIO #3 i Page 2 of 2 EVALUATION GUIDE NO. 3 ] EVENT NO. 3_ j i EVENT DESCRIPTION: Small RCS Leak in Containment RELATED TASKS IMPORTANCE FACTORS SAT - S UNSAT - U ! POSITION EXPECTED BEHAVIOR NOT OBS,- NO ALL Correctly implements procedures, including following procedural steps in correct sequence, abiding by caution, precautions, and initial conditions. COMMENTS: ALL Exchange complete and relevant information IAW OP 1300-6, l OPERATIONAL COMMUNICATIONS. COMMENTS: Termir'ation Point: Leak has completely ramped in for five minutes and reactor power has been reduced by at least 2% by boron control or rods. COMMENTS: ADDITIONAL COMMENTS:
- Safety Critical Task SEN#3 PAGE 10 0F 13
~
i ! , SCENARIO #3 Page 1 of 4 ! EVALUATION GUIDE NO. 2 EVENT NO. d EVENT DESCRIPTION: LOCA RELATED TASKS IMPORTANCE FACTORS 0009020502' 3.9 0009010501 4.3 0009010502* 4.6 i l CREW CRITICAL TASKS Crew stops all Reactor Coolant Pumps within 45 seconds of receiving a Containment isolation Signal (CIS). Crew recognizes 'A' Low Pressure Safety injection (LPSI) pump did not start on Safety injection Actuation and manually starts the pump. SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. NO SOS Ensures Critical Safety Function (CSF) status trees are monitored when required. COMMENTS: SOS
- Verifies immediate action steps of E 0 are performed when the plant trips.
COMMENTS: SOS
- Continues to direct steps of E-0 and transitions to E 1.
COMMENTS: SOS Continues to direct steps in E-1 to handle the loss of primary coolant. COMMENTS: SOS
- Transitions to FR-P.1 upon evaluation of the Critical Safety Function Status Trees.
COMMENTS:
' Safety Critical Task SEN#3 PAGE 110F 13
SCENARIO #3 Page 2 of 4 u EVALUATION GUIDE NO._3_ EVENT NO. -. 4 EVENT DESCRIPTION: LOCA SAT - S UNSAT - U POSITION EXPECTED BEHAVIOR NOT OBS. - NO PRO' Stops the Reactor Coolant Pumps within d5 seconds of receiving a Containment Isolation Signal (CIS). COMMENTS:
~
PRO' Recognizes 'A' Low Pressure Safety injection (LPSI) pump did not start, manually starts the pump, and informs the SOS of the pump failure. COMMENTS: 1 PRO Performs further actions of E 0 and E 1 as directed by the SOS. COMMENTS: BOP' Recognizes that P 2A Motor Driven Main Feedwater Pump trips, takes appropriate action to ensure adequate Feedwater for decay heat removal and informs the SOS. COMMENTS: BOP Correctly performs further actions of E-0 and E 1 as directed by the f SOS. COMMENTS: l
- Safety Critical Task SEN#3 PAGE 12 OF 13
SCENARIO #3 Pa 4 EVALUATION GUIDE NO. L - g , 1 EVENT DESCRIPTION: LOCA RELATED TASKS IMPORTANCE FACTORS 0009010502 4.6 0009010501 4.3 0009070501 4.7 CREW CRITICAL TASKS NONE SAT - S UNSAT- - U POSITION EXPECTED BEHAVIOR NOT OBS. NO ALL Correctly implements procedures, including following procedural steps in correct sequence, abiding by cautions, precautions, and initial conditions. COMMENTS: Termination Point: The crew has transitioned to FR P.1. COMMENTS: CREW Crews stops all Reactor Coolant Pumps within 15 seconds of receiving a Containment Isolation Signal (CIS). COMMENTS: CREW Crew recognizes 'A' Low Pressure Safety injection (LPSI) pump did not start on Safety injection Actuation and manually starts the pump. COMMENTS:
- Safety Cntical Task SEN#3 PAGE 13 0F 13
JOB PERFORMANCE MEASURE---SRO 1 i JPM NUMBER: ESF 0901 1 1 TASK NUMBER: K/A 006-A4 08 TITLE: PERFORMING ESF PANEL OPERATIONS TO RECOVER FROM INADVERTENT SIAS TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: O YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these arr'as should be described. 3 All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will ' role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 6 minutes IMPORTANCE RATING: 4.2/4.3 REQUIRED TOOLS AND EQUIPMENT: ES-1,1 PREPARED / REVISED BY: DATE: f7 APPROVED BY: m [MI., DATE: 4//3[97 REVISION #: 6 DATE: 3/19/97 JPM ESF-0901-1-1 PAGE 1 OF 9
SAFETY CONSIDERATIONS: 1 None ! I I EVOLUTION CONDITIONS: 1 An inadvertent initiation of SIAS has occurred. SlAS has been reset LAW ES 1,1, Si TERMINATION. INITIATING CUES: You are the Primary RO. You are to reset and retum to normal the following valves:
- 1. Containment sump pump discharge valves, PD-A 122,124,
- 2. CO, fire protection to Containment, C A 14,15.
- 3. Containment APD lines to Containment, IA A 98,107.
EVOLUTION STANDARDS: The trainee will reset the designated system valves at the ESF panels to demonstrate his knowledge of
, ESF Panel operations.
REFERENCES:
ES-1,1, St TERMINATION PRR 92120 PRR 92-120 PRR 96162 SIMULATOR:
- 1. Reset to a power IC.
1 2. Manually fire trains A & B of Safety injection and retum to AUTO.
- 3. Perform operator actions of E-0 & ES-1.1 up to and including SIAS RESET.
! 4. Bring in the trainee and conduct a tumover, JPM ESF-0901-1-1 PAGE 2 OF 9
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. Obtain a copy of ES 1.1, Si TERMINATION. Standard: Trainee is provided with a copy of ES 1.1 when referenced. NOTE: The valves do not have to be reset in a specific order. For purposes of this JPM, only the valves listed below need be done. Intent is NQI to do all valves on Attachment B. Cue: ES 1.1 has been completed up to step for aligning secondary plant equipment per Attachment B. O SATISFACTORY O UNSATISFACTORY COMMENTS: 2,
' Reset containment sump discharge v.. ves.
Standard: 1) ESF A control switch for PD-A 122 taken to reset.
- 2) ESF B control switch for PD-A 124 taken to reset.
- 3) Status lights verified to go out.
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM ESF 0901-11 PAGE 3 OF 9
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 3.
- Reset CO, fire protection valves.
Standard: 1) C-A 14 reset on ESF A.
- 2) C A 15 reset on ESF B.
- 3) Valve status lights verified to go out.
O SATISFACTORY O UNSATISFACTORY 1 COMMENTS: s
- Reset containment APD valves.
Standard: 1) lA-A 98 reset on ESF B.
- 2) lA-A-107 reset on ESF B.
{ 3) Valve status lights verified to go out. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM ESF 09011-1 PAGE 4 OF 9
~ . _ - _ _ .-
EVOLUTION CONDITIONS: An inadvertent initiation of SlAS has occurred, SlAS has been reset IAW ES 1.1, Si TERMINATION. k. INITIATING CUES: You are the Primary RO. You are to reset and retum to normal the following valves:
- 1. Containment sump pump discharge valves, PD-A 122,124.
- 2. CO fire protection to Containment, C A 14,15.
- 3. Containment APD lines to Containment, IA A 98,107.
JPM ESF-0901-1-1 PAGE 5 OF 9 e i
JPM QUESTION #1 ESF4901-1 1 QUESTION: What are the required sctions and conditions necessary to block RAS? ANSWER: When 3/4 PZR pressure channels are <1720 psig, place the RAS select switch to
- BLOCK",
SATISFACTORY: YES NO
REFERENCES:
NOP 17, RO-L-4.7 (page 13) TASK IMPORTANCE: 3.7/3.9 TASK NUMBER: K/A 013-K4.12 LEARNING OBJECTIVE: SNO 030313. ESF 101-4, ESF 01015 TRAINEE ANSWER / COMMENTS: JPM ESF-0201-1-L PAGE 6 OF 9
JPM @UESTION #2 1 t ESF-0901 1-1 i l 4 QUESTION: How is the onorator alerted to a loss of control power for an SIAS related 86 device? ANSWER: Annunciator RH 3 3 "SIAS 86 Device Trip Path Fault" monitors control power to various SIAS 86 devices. 4 SATISFACTORY: YES NO
REFERENCES:
RO-L 2.6 (page 54), RO-S 2.8 TASK IMPORI ANCE: 3.7/4.2 TASK NUMBER: K/A 013 A2.05 LEARNING OBJECTIVE: ECCS-01013 TRAINEE ANSWER / COMMENTS: a JPM ESF 0901-11 PAGE 7 OF 9
1
'JPM QUESTION #1
, ESF 0901 1-1 i
- QUESTION: What are the required actions and conditions necessary to block RAS?
I t l i (- i i 4 s l w. 1 e l l-l l i JPM ESF-0901-1-1 PAGE 8 OF 9 .
,--..,.r--.. n..._-,_,.... ~ ~_,,m ,_,,,,.,,,__,.,....w.m,..,,,,,,__m,m,,_m.
,,,,,,,,m, , , . . .., , , .,, ,.,.~.,yp.._,,,,_,,,. . . , . _ _ . . , , .,,,.,,,,,y.- . , . - , . .,
JPM QUESTION #2 ESF-0901 1 1 QUESTION: How is the operator alerted to a loss of control power for an SIAS related 86 device? I
)
JPM ESF-0901 1 1 PAGE 9 OF 9
i JOB PERFORMANCE MEASURE---SRO 2 JPM NUMBER: New-25 TASK NUMBER: K/A 011 EA111 TITLE: PERFORMING RHR SYSTEM FAST STARTUP DURING POST LOCA COOLDOWN ' TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: O YES W NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contaminatio[1 areas will not be entered.
Lo, cation and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 Minutes IMPORTANCE RATING: 4.2/4.2 REQUIRED TOOLS AND EQUIPMENT: AOP 2 56 PREPARED / REVISED BY: / DATE: / /f7 APPROVED BY: [, DATE: p Vh.h 7 REVISION #: 0 DATE: 3/20/97
.JPM NEW-25 PAGE 1 OF 18
SAFETY CONSIDERATIONS: None i EVOLUTION CONDITIONS: ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION,is in progress. The plant has just reached RHR entry conditions. Containment and and Spray Building Lower Level are inaccessible due to high radiation levels. TSC has recommended fast startup of the RHR System. INITIATING CUES: You are the primary RO. You have been directed to place Train "A" RHR in service IAW OP 2 56, RESIDUAL HEAT REMOVAL SYSTEM FAST STARTUP. EVOLUTION STANDARDS: The trainee will place Train "A" RHR in service IAW OP 2 56.
REFERENCES:
- 1. ES 1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION.
- 2. AOP 2 56, RESIDUAL HEAT REMOVAL SYSTEM FAST STARTUP.
SIMULATOR:
- 1. Initialize in cooldown IC#18 ready to place RHR inservice.
2. Align plant equipment to match actions in E-0, E-1, ES-1.2 flowpath. (RCP #1 running, CIS Reset, normal charging restored, letdown isolated, SIAS blocked, SITS isolated, etc.).
- 3. Initiate fuel clad failure. (Malfunction CRO1,100%).
- 4. Initiate 50 gpm RCS leak (Malfunction RC04A,25%).
5. Ensure RCS less than 317 psig and 340'F for proper RHR cut-in prerequisites (Containment conditions will be normal for this scenario. Will need to use pressurizer PORV to reduce pressure to less than 317 psig and will need to use steam dump to cool down to less than 340'F. It is desirable to have pressurizer level on scan but not required for this JPM.)
- 6. Freeze simulator and tum over to trainee.
JPM NEW-25 PAGE 2 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. Verify RCS borated to cold shutdovm. Standard: As above. Cue: Adequate boron has been injected into the RCS for cold shutdown. O SATISFACTORY O UNSATISFACTORY COMMENTS: 2. Verify RCS temperature less than 340'F and stat!e or decreasing. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: P 1 JPM NEW 25 PAGE 3 OF 18
1 1
\
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3. Verify RCS pressure less than 317 psig (210 psig for harsh ctmt) and stable or decreasing. Standard: As above If not, then trainee establishes these conditior - sing aux spray or PORV and steam dumps, as necessary. O SATISFACTORY O UNSATISFACTORY COMMENTS:
- 4. _
Verify SIAS, RAS, and CSAS have been reset. Standard: Check ECCS lightbox for SIAS, RAS, and CSAS white lights out. Can also check associated annunciators off (RH 3-1, RH-3 7, RH-3-4). O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 JPM NEW-25 PAGE 4 OF 18 l l
' PERFORMANCE CHECKLQT STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
S. l 1 Verify ECCS routine testing OP 312.1, SAFEGUARDS LOCKED VALVE LIST and OP 312.2, PRE POWER VALVE CHECKLIST are in place. Standard: As above. Cue: These procedures are in place. O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 .- f Clear white tags and shut breakers and disconnects for RH M-1 and RH-M-2. Standard: Dispatch an AO to perform the above actions. CLe: fter performing remote function RH120, report local actions completed. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEW-25 PAGE 5 OF 18 i
PERFORMANCE CHECKLIST - STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ' I 7. t Place P-12A in PTL. Standard: As above. l O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 4 8. l Align HPSI P-14A suction to RWST or place in PTL. Standard: Open P-14A suction valve to RWST, HSI-M-50 or place P-14A in PTL, NOTE: Since RWST level will be full in this scenario, opening HSI-M-50 is preferable to placing pump in PTL but either choice satisfies procedure step. < 0 SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEW-25 PAGE 6 OF 18
PERFORMANCE CHECKLIST
- STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
-l 9.
l Place Train "A" Containment Spray Pump P-61 A in PTL. Standard: As above. l 0 SATISFACTORY O UNSATISFACTORY - COMMEivts: I { 10.
- Align the following valves:
- Shut LSI M-41, CS-M-91, and CS-M *
- Throttle open PCC-M 43.
e Shut LSI-55. o Open RH-6,EH-9, and RH-11. e Shut LSI-47, CS-13, and CS-31, Standard' As above. Direct an AO to perform the last three bullet items. Cue: After performing remote functions RH104 (close LSI-47), RH108 (close LSt 55), RH106 (open RH-6), RH101 (open RH9), RH115 (open RH-11), and CS111 (close CS-13), then AO reports that LSI-55, LSI-47, CS-13, and CS-31 are shut and that RH-6, RH-9, and RH-11 are open. O SATISFACTORY O UNSATISFACTORY CCMMENTS: JPM NEW-25 PAGE 7 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 11. Secure operating LPSI pump and place in PTL. Standard: As above, if P 128 is running, then stop it and place it in PTL. , O SATISFACTORY O UNSATISFACTORY COMMENTS: 12. Shut CS-A 55 and CS A-56. Standard: As above. Cue: If asked, LPSI pump vent valves LSI-67 and 68 are open. (inaccessible in this scenario.) O SATISFACTORY O UNSATISFACTORY COMMENTS: JPMMEW-25 PAGE 8 OF 18
. - . . . . . .. . . . .=. -. .
PERFORMANCE CHECKLIST ! STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: s 13. I Verify LSI F 59 controller is fully open. Standard: As above. NOTE: LSI-F-5P valve is blocked full open in the Spray Building and is inaccessible. For this scenario, this valve will remain fully open at all times. O SATISFACTORY O UNSATISFACTORY COMMENTS: 14. Open RH T-12 to 20% on the controller. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEV/-25 PAGE 9 0F 18
. . . = . . . - - - - . . - . _ - . - . . - . .. - . -. .. -. .
PERFORMANCE CHECKLIST J STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 15. Shut LSI M 11,21, and 31, Standard: As above. l l O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 16. Throttle open LSI-M-31 just off its seat. Standard: LSI-M-31 is jogged open until intermediate position indication is observed, O SATISFACTORY O UNSATISFACTORY COMMENTS: i JPM NEW-25 PAGE 10 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: l 17.
*Open RH M-1 and RH-M-2.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NEW-25 PAGE 11 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 18.
]
- Commence RHR System heatup as follows:
- 1. Start RHR Pump P-12A.
- 2. Slowly open LSI-M-11 and LSI-M-31.
- 3. Slowly cycle RH-T-12 full stroke.
Standard: As above. RHR System warmup rate should not exceed 21'F/ hour. P12A bearing temperature should not exceed 250'F. At least 500 gpm should be maintained through the RHR pump. NOTE: Per notes preceding this step, trainee should monitor (1) RHR pump bearing , temperatures (plant computer group 5-01), (2) RHR System heatup on TR-351X/Y or TI-352/353X/Y, (3) RHR flow to Loops 1 and 3 on F1312/FI 332, and (4) PCC flow through RHR hx using F1-1708/Fl 3408 or pump amp changes. Since these actions are in a note vs an action step, they are not considered critical for the pumoses of this JPM. Once it is observed that the trainee can control the 21'F/ hour RHR System warmup rate, then to save time, trainee may be prompted to assume RHR System is fully warmed up and to proceed accordingly. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 JPMEJW-26_ PAGE 12 OF 18
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 19.
' Control RCS temperature as follows:
- 1. Throttle open RH-T-12 to allow flow through the RHR hx.
- 2. Throttle PCC-M-43 and balance the flow with RH-T 12.
Standard: As above. To decrease cooldown rate, close RH T-12, and/or PCC-M-43. To increase cooldown rate, open RH-T-12 and/or PCC-M-43. Cue: Direct trainee to establish an obsentable cooldown rate using RHR . Once established, then direct trainee to stop the cooldown. Once evaluator is confident that trainee can control cooldown rate using RHR, then cue that JPM is complete. NOTE: To see the full effect of the trainee's actions to control the RCS cooldown rate, make sure that the SGs are not cooling down the RCS due to steaming and feeding before asking him to start and stop a cooldown on RHR. C SATISFACTORY O UNSATISFACTORY COMMENTS: l JPM NEW-25 PAGE 13 OF 18
EVOLUTION CONDITIONS:
.ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION,is in progress. The plant has just reached RHR entry conditions. Containment and Spray Building Lower Level are inaccessible due to i high radiation levelsi TSC has recommended fast startup of the RHR System.
INITIATING CUES: You are the primary RO. You have been directed to place Train "A" RHR in service IAW OP 2 56, RESIDUAL HEAT REMOVAL SYSTEM FAST STARTUP. JPM NEW-25 PAGE 14 OF 18
JPM QUESTlON #1 NEW 25 i QUESTION: How is the RHR piping protected from overpressure transients during cold shutdown conditions? l i ANSWER: The RHR spring reliefs (RH-S-24 and 25) and auto closure of RH-M-1 & 2 on high pressure (585 psig). 1
)
SATISFACTORY: YES NO.
REFERENCES:
RO-L-2.7 (page 5) TASK IMPORTANCE: 3.5/3.7 TASK NUMBER: K/A 005-A2.02 LEARNING OBJECTIVE: RHR-0101-5, RHR-0101-8 TRAINEE ANSWER / COMMENTS: JPM NEW-25 PAGE 15 OF 18
JPM QUESTION #2 , NEW - 25 i QUESTION: During normal procedure conditions, the RHR System auto isolates with PZR level greater than 80% What actions are required? (RCS is not vented). ANSWER: Within six hours perform one of the following: 1, Restore the required condition.
- 2. Station a dedicated operator to prevent RCS overpressurization and within 72 hours place the plant in a condition where LTOP is not required.
SATISFACTORY: YES NO
REFERENCES:
Tech Spec 3.4.D.3 TASK IMPORTANCE: 3.4/4.0 TASK NUMBER: K/A Generic 2.1.33 LEARNING OBJECTIVE: lSR-0301-3, SNO-0303-13, SNO-0303-9 TRAINEE ANSWER / COMMENTS: JPM NEW-25 r; GE 16 OF 18
_.. _ . _ - _ . _ . _ . _ . _ _ . . _ . _ . _ . _ . _ . _ . . _ . _ _ _ . . _ . _ _ . _ _ _ . . _ _...._...____..i_,._._...___.. 1 JPM QUESTlON #1 ' NEW 25
- i.
QUESTION: - Howis the RHR piping protected from overpressure transients during cold shutdown conditions? ] l ! l i .i i e JPM NEW-25 PAGE 17 OF 18
JPM QUESTION #2 NEW - 25 . QUESTION: During normal procedure conditions, the RHR System auto isolates with PZR level greater than 80%. What actions are required? (RCS is not vented), JPM NEW-25 PAGE 18 OF 18
i 1 i 1 JOB PERFORMANCE MEASURE->-SRO 3 JPM NUMBER: NI-0901-1-1 TASK NUMBER: K/A 015-A3 03 i TITLE: ESTABLISHING ALTERNATE SYMMETRIC OFFSET LIMITS TIME CRITICAL: O YES W NO START TIME: ALTERNATE PATH: O YES 5 NO STOP TIME: PERFORMA."CE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: _ Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are LLOI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references norrially availa'ble may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play' tr.ese personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETlON TIME: 5 minutes IMPORTANCE RATING: 3.9/3.9 REQUIRED TOOLS AND EQUIPMENT:
- 1. Technical Data Book
- 2. OP 1-4-1 PREPARED / REVISED BY: DATE: f 2 APPROVED BY: [ DATE: t/[3/97 REVISION #:
f 3 DATE: 3/20/97 JPM NI-0901-1-1 PAGE 1 OF 9
SAFETY CONSIDERATIONS: None. dVOLUTION CONDITIONS: The plant is steady state at power. The plant computer (OSS)is out of service. INITIATING CUES: You are the Primary RO. RPS must be plac6d in attemate symmetric offset for Technical Specification concems. You are to place RPS channels in ALTERNATE LAW OP 14-1. EVOLUTION STANDARDS: After receiving the initiating cue, the trainee will ensure the plant is within attemate symmetric offset limits of TDB Figure 3.1.2.2 and then place the RPS channels in Al TERNATE.
REFERENCES:
Technical Data Book PRR 92-120 PRR 96-162 SIMULATOR:
- 1. Reset to an IC of 45% power or less.
- 2. Ensure power and symmetric offset are within altemate symmetric offset limits.
- 3. Sign off OP 1-4-1 to step 5.5.2. Check the box for power reduction to within SO pretrip band.
- 4. Bring in the trainee and conduct a tumover, JPM NI-0901-1-1 PAGE 2 OF 9
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 l' Reference Technical Data Book Figure 3.1.2.2 for symmetric offset limits. Standard: Verify plant symmetric offset is within pre-trip limits of TDB Figure 3.1.2.2. ll 0 SATISFACTORY O UNSATISFACTORY COMMENTS: 2-
~__
- Select one RPS channel to ALTERNATE and verify symmetric offset is within limits.
Standard: 1) Normal / Alternate switch taken to ALTERNATE (on RPS SOTC drawer).
- 2) Trips and pre-trips verified clear by absence of white and red status lights on SOTC trip bin (can also check absence of alarm R-1-12).
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NI-0901-1-1 PAGE 3 OF 9
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
- Select ALTERNATE position on the three remaining channels, Standard: Each remaining channel placed in ALTERNATE on RPS SOTC drawers and trips and pre-trips verified clear, by absence of white and red status lights on SOTC trip bins (can also check for alarm R-1-12 clear).
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM NI-0901-1-1 PAGE 4 OF 9
EVOLUTION CONDITIONS: The plant is steady state at power. -The plant computer (OSS) is out of service, t
, -INITIATING CUES:
j You are the Primary RO. RPS must be placed in altamate symmetric offset for Technical Specification concems. You are to place RPS channels in ALTERNATE LAW OP 14-1. j s 1 e t I i i a 6 i f i' i JPM NI-0901-1-1 PAGE 5 OF 9 1
1 JPM QUESTION #1 NI-0901-1-1 QUESTION: What immediate actica is required for four (4) or more coincident, valid incore instrumen; alarms? How is validity of alarm detemlined in the Control Room? ANSWER: Immediately reduce power to clear alarms per T.S. 3.10.C.3. Alarm validity is determined by an INCA printout LAW OP 1-8-1, POWER DISTRIBUTION AND MTC CONTROL. ! SATISFACTORY: YES NO
REFERENCES:
Tech Spec 3.10.C.3, RO-L-4.3 (page 20), SRO-L-10.8 (page 40), OP 18-1 TASK IMPORTANCE: 3.9/3.9 TASK NUMBER: K/A 015-A3.03 LEARNING OBJECTIVE: INCA-0101-3, SNO-0303-9, SNO-0303-10 TRAINEE ANSWER / COMMENTS: 9 JPM NI-0901-1-1 PAGE 6 OF 9
1 l JPM QUESTION #2 j Nl-0901-1-1 I JUESTION: (This question does not relate to the JPM.) The waste gas decay tank release is in progress when the RMS Channel (P'4-3901) fails low (the flow control valve still functions). What remedial actions are required in this condition por the ODCM in order to continue the release? ANSWER: With less than the minimum number of channels operable per Table 2.2 (page 16) of ODCM, you must have at least two (2) independent samples of the drum's contents analyzed and have at least two (2) qualified individuals independently verify release rate calculations and discharge valve lineup. SATISFACTORY: YES NO
REFERENCES:
ODCM Table 2.2 (page 17) TASK IMPORTANCE: 2.7/3.5 TASK NUMBER: K/A 071 K4.06 LEARNING OBJECTIVE: SNO-0304-1 TRAINEE ANSWER / COMMENTS: JPM NI-0901-1-1 PAGE 7 OF 9
6 JPM QUESTION #1 . i NI-0901 1 1 ! QUESTION: _What immediate action is required for four (4) or more coincident, valid incore instrument
- alarms? How ir validity of alarm determined in the Control Room?
4 t i J J e i r 1 i j 5 7 M JPM NI-0901-1-1 PAGE 8 OF 9
- _ - ~ - - - . _ - . . - . - . - .- ._. - . - - - . - -
-t JPM QUESTION #2 NI-0901-1 1 QUESTION: (This question does not relate to the JPM.) The waste gas decay tank release is in progress when the RMS Channel (RM-3901) fails low (the flow control valve still functions). What remedial actions are required in this condition per the ODCM in order to continue the release?
i a e 4 i e + r JPM NI-0901-1-1 PAGE 9 OF 9
JOB PERFORMANCE MEASURE---SRO 4 JPM NUMBER: New-15 TASK NUMBER: K/A 055-EA106 i TITLE: STARTING DG-1B LOCALLY DURING SBO i TIME CRITICAL: 0 YES 5 NO START TIME:
^
%YES O NO STOP TIME:
PERFORMANCE TRAINEE: QUESTION RESULTS: Out of Correct PERFORMANCE RESULTS: O PASS O Fall DIRECTIONS TO TRAINEE: 1, All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play" these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: IMPORTANCE RATING: 4.1/4.5 REQUIRED TOOLS AND EQUIPMENT: AOP 2-48 PREPARED / REVISED BY: DATE: APPROVED BY: [ DATE: e//k/fp REVISION #: e 0 DATE: 3/21/97 JPM New-15 PAGE 1 OF 13
SAFETY CONSIDERATIONS: None .
)_ EVOLUTION CONDITIONS:
l A loss of all AC power has occurred with DG-2 available. AOP 2-48 is in progress. DG-1B auto started
. but then tripped.-
f- INITIATING CUES: You are the Spare AO. You have been directed to attempt a local start of DG-1B IAW AOP 2-48 Attachment F. EVOLUTION STANDARDS: Trainee will perform AOP 2-48 Attachment F. - As part of the evolution, he will discover that the diesel tripped on overspeed and will reset it to allow restart. He will also adjust diesel speed on two occasions.
REFERENCES:
AOP 2-48, Loss of All AC DG 2 Available/ Station Blackout (SBO) o SIMULATOR: N/A 1-i f i t 4 i JPM New-15 PAGE 2 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 1.
, Obtain copy of AOP 2-48 Attachment F, EDG 1B Manual Start and Loading.
Standard: Trainee is provided a copy of AOP 248 Attachment F when requested. O SATISFACTORY O UNSATISFACTORY COMMENTS: A
- Check DG panel alarms. 4 M
l : Standard: Trainee should investigate panel alarms, discover that the diesel tripped on overspeed, and reset it by moving overspeed trip lever clockwise to approximately the "9 o' clock" position and verifying that it latches in the set position.
,7 Cue: OVERSPEED TRIP (DG 2-6) local alarm is lit.
If asked, cue as required that the DG is tripped, the overspeed trip lever is in the tripped position, and the govemor oil level is normal. If trainee contacts Control about the overspeed trip, Control Room directs trainee to reset it and continue with the local start attempt. If asked about alarm after resetting overspeed trip, alarm is clear, O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-15 PAGE 3 OF 13 1 l
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 3. Ensure CB START I and CB START ll circuit breakers in ON position. Standard: As above. O SATISFACTORY O UNSATISFACTORY - l COMMENTS: i l 4. Ensure AC and DC control breakers in ON position. Stand $rd: As above. O SATISFACTORY O- UNSATISFACTORY am COMMENTS: JPM New-15 PAGE 4 OF 13
4 PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 5. !- Y Place SELECTOR SWITCH in LOCAL START position. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 6, Lower speed setting on the diesel to minimum, Standard: Mold GOVERNOR CONTROL in LOWER until governor setting is at O. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 6 JPM New-15 PAGE 5 OF 13
PERFORMANCE CHECKUST STEPS /S, ANDARDS FOR SU0CESSFUL PERFORMANCE: 4 7.
' Ensure overspeed trip is reset.
Standard: OVERSPEED TRIP alarm (DG 2 6) clear. Can also check the overspeed trip lever rotated clockwise to about "9 o' clock" position and latched in set position. l C SATISFACTORY O UNDATISFACTORY COMMENTS: 8.
' Press ENGINE START bu. ton to start the diesel.
Standard: As above. Cue: DG starts and accelerates to 930 rpm. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New 15 PAGE 6 OF 13
-w J
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 9.
'Ralso DG speed to 950 rpm.
Standard: Hold GOVERNOR CONTROL in RAISE till 950 rpm is reached. Cue: After GOVERNOR CONTROL placed in RAISE, DG rpm is 950 rpm O SATISFACTORY O UNSATISFACTORY COMMENTS: 10. Place SELECTOR SWITCH in AUTO position. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-15 PAGE 7 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 11. Inform the Control Room that die nl is ready for flashing. Standard: As above. Cue: After receiving this report, the Control Room flashes the diesel and requests trainee to venfy diesel speed is 900 rpm. O SATISFACTORY O UNSATISFACTORY COMMENTS: 12,
' Verify DG speed at 900 rpm after flashing.
Standard: Trainee takes GOVERNOR CONTROL to RAISE and informs Control Room. Cue: Before trainee adjustment, diesel speed is 890 rpm. After adjustment, if trainee takes GOVERNOR CONTROL to RAISE, then diesel speed increases to 900 rpm. O SATISFACTORY O UNSATISFACTORY COMMENTS: i l I l l JPM New-15 PAGE 8 OF 13
EVOLUTION CONDITIONS: A loss of all AC power has occurred with DG 2 available. AOP 2-48 is in progress, DG 1B auto started but then tripped. INITIATING CUES: You are the Spare AO. You have been directed to attempt a local start of DG 1B IAW AOP 2 48 Attachment F. i i JPM New.15 PAGE 9 OF 13
JPM QUESTlON #1 NEW 15 t QUESTION: Attachment Q of ECA 0.0 lists several emergency procedure actions that require notification due to 10CFR50.54X requirements. What is the purpose behind a one hour notification involving a i 10CFR54X issue? ANSWER: In the event of a safety emergency a licensee may deviate from license conditions without prior NRC approval. i SATISFACTORY: YES NO
REFERENCES:
SRO-L-10.12 (page 14)
- i. TASK IMPORTANCE: 2.6/3.8 ,
TASK NUMBER: Generic 2.2.23 LEARNING OBJECTIVE: GA 0307 5 TRAINEE ANSWER / COMMENTS: JPM New-15 PAGE 10 OF 13
JPM QUESTION #2 NEW 16 QUESTION: A revision to the DG Surveillance Procedure was submitted. It is determined that a 50.5g review is necessary. What is the purpose of a 10CFR50.5g Review? ANSWER: Allows Maine Yankee to: 1) change design 2) revise procedures or 3) conduct tests / experiments as along as the change or test does not involve: A) A Tech Spec change 9I B) An unreviewed
. safety question.
M- h b de gt k T.S. er (. n l/ts dhf W H ' 1
'i SATISFACTORY: YES NO
REFERENCES:
SRO L 10.11 (page 10) TASK IMPORTANCE: 1.8/3.3 TASK NUMBER: Generic 2.2.8 LEARNING OBJECTIVE:. GA-0305-1 TRAINEE ANSWER / COMMENTS: JPM New 15 PAGE 11 OF 13
.. . ___ _ J
l 1 JPM QUESTION #1 1 i NEW 15 , i QUESTION: Attachment Q of ECA 0.0 lists several emergency procedure actions that require notification due to 10CFR50.54X requirements. What is the purpose behind a one hour notification involving a 10CFR54X lasue? JPM New-15 PAGE 12 OF 13
- - - . . . - -.. .- _ .. - - - .-. - - - ..- - _ . - - .~ - - .- - - ,
JPM QUESTION #2 i i 4
}
NEW il QUESTION: A revision to the DG Surveillance Procedure was submitted, it is determined that a 50.59 review is necessary. What is the purpose of a 10CFR50.59 Review? s 1.
, 4 l
l l l i l [ I I r t f J. i JPM New-15 PAGE 13 OF 13
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JOD PERFORMANCE MEASURE---SRO s
~
JPM NUMBER: New-4 TASK NUMBER: K/A 033-A101 ( TITLE: PERFORMING LOCAL ACTIONS FOR PRIMARY SIDE EQUIPMENT DURING LOSS OF ALL AC POWER TIME CRITICAL: O YES N NO START TIME: ALTERNATE PATH: O YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct r EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All act.ons in the plant will be SIMULATED. The trainee and examiner are 1:LO.I authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will" role play" these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 15 Minues IMPORTANCE RATING: 2.7/3.3 REQUIRED TOOLS AND EQUIPMENT: ECA-0.0 PREPARED / REVISED BY: DATE: [/'2/f7 APPROVED BY: [ DATE: (//3/47 1 - l REVISION #: 0 DATE: 3/21/97 JPM New-4 PAGE 1 OF 10
SAFETY CONSIDERATIONS:
-None i
EVOLUTION CONDITIONS: A loss of all AC power has occurred and ECA 0.0 is in progress. INITIATING CUES: You are the Primary AO. You have been directed to perform ECA 0.0 Attachment M, Local Operation and Verification of Primary Side Equipment. EVOLUTION STANDARDS: Trainee will perform ECA-0.0 Attachment M.
REFERENCES:
ECA 0.0, Loss of All AC Power SIMULATOR: N/A JPM New-4 PAGE 2 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. Obtain copy of ECA-0.0 Attachment M, Local Operation and Verification of Primary Side Equipment. Standard: Trainee is provided a copy of ECA-0.0 Attachment M when requested. O SATISFACTORY O UNSATISFACTORY COMMENTS: s%;.L 2. HW _.
' Check BAST temperature greater than 120'F using surface thermometer or contact pyrometer.
Standard: As above. Cue: When measured, BAS 1 temperature is 130'F. O SATISFACTORY O UNSATISFACTORY COMMENTS: i JPM New-4 PAGE 3 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ut.3 <r.fral I
' Check SFP level greater than high suction flange for cooling pumps P 17A and B.
Standard: Checks suction flange which is at the north end of the pool approximately 3 feet under water. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
' Shut manual casing vent iso'ition valves for LPSI and Spray pumps: CS-21,22,44 and LSI-67 and 68.
Standard: Five valves shut as above. NOTE: These valves are located in an area which requires safety harnesses in order to access by lad:ier. Trainee should go to top of the ladder and describe the location of the valves as being next to the pumps on the next level. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-4 PAGE 4 OF 10 4
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5.
' Shut RCP seal water intet isolation and bypass valves SL 21. 74 (RCP#1); SL 32,35 (RCP#2);
and SL-43,46 (RCPW3). Standard: Six valves shut as above. NOTE: These valves are in a high radiation area but can be seen from the HSPI valve room. Trainee should point them out to the evaluator. Cue: After these valves have been shut, cue that (1) the charging pumps have already 1 been vented IAW OP 1 11-6, (2) no waste processing is in progress, and (3) no 4 waste releases are in progress. ' 4 O SATISFACTORY O UNSATISFACTORY COMMENTS: i l d , 6. Notify Control Room that ECA-0.0 Attachment M is completed. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: i a JPM New-4 PAGE 5 OF 10
EVOLUTION CONDITIONS: A loss of all AC power has occurred and ECA-0.0 is in progress. INITIATING CUES:
- You are the Primary AO. You have been directed to perform ECA 0.0 Attachment M, Local Operation and Verification of Primary Side Equipment.
U h
.t .
I 4 L l l 0 i i i I l 1 r 1. JPM New-4 PAGE 6 OF 10 l-P
._ ._2_. . _ . . ..._ _ _ _ . . . . _ . _ _ . _ . _ . ~ . _ _ . _ - . _ _ . , . . , _ . _ . , . - , . . _ _ _ . _ , _ - ,
i JPM QUESTION #1 NEW 4 l QUESTION: In conjunction with your supervisory actions during a loss of all AC you are required to make a report to the NRC regarding implementation of the Emergency Plan. What is the time requirement to make this report? > 1 1 i ANSWER: Per OP 1261, OPERATIONAL EVENT REPORTING, you must report within one hour of l implementation of the E Plan per 10CFR50,72(a). l SATISFACTORY: YES NO
REFERENCES:
SRO-L 10.2 (page 3) OP 126-1 Attachment A TASK IMPORTANCE: 2.1/4.3 TASK NUMBER: Generic 2.1.6 LEARNING OBJECTIVE: SNO-0302 5 l TRAINEE ANSWER / COMMENTS: l i i JPM New-4 PAGE 7 OF 10 1
~ , - . _ , , ,
, - . . _ , - - - . - - - ~ _.___..__ - . _ _ , , - , _ _ , . - . _
JPM QUESTION #2 , NEW4 1 QUESTION: You checked a flange at the Spent Fuel Pool. What is the function of that flange? How does it work? ANSWER: The flange prevents the Spent Fuel Pool from draining in the event of a cooling system leak or i rupture, if the Spent Fuel Pool level gets that low, air will be sucked into the flange, consequently causing the pumps to lose suction and also preventing a siphoning effect. 9-SATISFACTORY: YES NO
REFERENCES:
AO-L 2,13 (page 3) TASK IMPORTANCE: 2.g/3.2 TASK NUMBER: K/A 033-K4.01 LEARNING OBJECTIVE: SFP-0401 11 l TRAINEE ANSWER / COMMENTS: i I JPM New-4 PAGE 8 OF 10
JPM QUESTION #1 NEW 4 QUESTION: In conjuncton with your supervisory actions during a loss of all AC you are required to make a report to the NRC regarding implementation of the Emergency Plan. What is the time requirement to make this report? 1 JPM New-4 PAGE 9 OF 10
JPM QUESTION #2 NEW 4 QUESTION: You checked a flange at the Spent Fuel Pool. What is the function of that flange? How does it work?
' JPM New-4 PAGE 10 OF 10
j SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #1 QUESTION: What does a " Code Red
- FEMCO notification frorn Security mean?
ANSWER: That an armed intruder is inside the protected area. SATISFACTORY: YES NO
REFERENCES:
AOP 2 51 TASK IMPORTANCE: 2.3/3.3 TASK NUMBER: K/A Generic 2.4.28 LEARNING OBJECTIVE: SEO 0303 2 TRAINEE ANSWER / COMMENTS:
1 SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #1 QUESTION: What does a
- Code Ref FEMCO notification from Security mean?
4
! SRO ADMINISTRATIVE TO' ICS CONDUCT OF OPERAT 'NS QUESTION #."
QUESTION: What is the minimum operations shift staffing complement required by paine Yankee procedures. gn yv' ANSWER: One (1) PSS G jdfe)*' One (1) SOS y)4 N Two (2) CRO's Two (2) NPO's or AO's One (1) Additional operator (CRO, LNPO NPO, or AO) One (1) STA One (1) SRO shall be present in the Control Room SATISFACTORY: YES NO
REFERENCES:
OP 126-5, Step 3. l.1a TASK IMPORTANCE: 2.3/3.4 TASK NUMBER: K/A Generic 2.1.5 LEARNING OBJECTIVE: SNO-0302-10 TRAINEE ANSWER / COMMENTS: I
l 4 SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #2 QUESTION: What is the minimum operations shift staffing complement required by Maine Yankee procedures.
SRO ADMINISTRATIVE TOPICS 4 CONDUCT OF OPERATIONS QUESTION #3 l l QUESTION: What is considered an " Intent Change' to a procedure? ANSWER: Anything that:
- 1. Invalidates the existing 10CFRoo 39
- 2. Alters the stated objective of the procedure.
- 3. Alters any acceptanco criteria, or
- 4. Directs performance in a plant condition which is different from the condition when the procedure would normally be used.
SATISFACTORY: YES NO
REFERENCES:
0-06 2 (Section 6.7) TASK IMPORTANCE: 2.5/3.4 i TASK NUMBER: Generic 2.2.11 LEARNING OBJECTIVE: GA-0302-1 TRAINEE ANSWER / COMMENTS: E _ _ __ ,. _ _ _ _ . . _ - - _ , - ~
SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #3 QUESTION: What is considered an
- Intent Change' to a procedure?
SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #4 QUESTION: What is the required ventilation lineup in the Fuel Building when moving irradiated fuel that has decayed less than 60 days? ANSWER: The SFP ventilation system shall be operating and discharging through the HEPA and charcoal absorber filter train during fuel movement within the SFP. i SATISFACTORY: YES NO
REFERENCES:
Tech Spec 3.25.C TASK IMPORTANCE: 2.6/3.5 TASK NUMBER: K/A Generic 2.2.30 LEARNING OBJECTIVE: SNO-0303-8 TRAINEE ANSWER / COMMENTS:
t SRO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #4 QUESTION: What is the required ventilation lineup in the Fuel Building when moving irradiated fuel that has decayed less than 60 days?
JOB PERFORMANCE MEASURE---SRO ADMIN JPM NUMBER: New 33 TASK NUMBER: K/A 2 213 i TITLE: TAGGING A SAFETY CLASS COMPONENT TIME CRITICAL: O YES h NO START TIME: ALTERNATE PATH: 0 YES h NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE; 1. All actions in the plant will be SIMULATED. The trainee and examiner are MQI authorized by this document to actually perform any action in the plant.
- 2. High ra$ation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references norn ally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
S. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play" these personnel.
EVALUATION LOCATION: O PLANT h SIMULATOR N CONTROL ROOM APPROXIMATE COMPLETION TIME: 30 Minutes (MPORTANCE RATING: 3.6/3.8 REQUIRED TOOLS AND EQUIPMENT:
- 1. Procedure 0-14-1, Attachment A, B, C, and M
- 2. White Tags PREPARED / REVISED BY: DATE: _ [8 7 APPRO\- sY:
[ DATE: t/,/3/f7 REVISION #: 0 DATE: 3/19/97 JPM New 33 PAGE 1 OF 6
.. . . - _ . - . - - . - - - - . . . . . . - . . _ . _ - . - . . = - . - . . . - . . . . - .
d SAFETY CONSIDERATIONS:
- None ;
{ EVOLUTION CONDITIONS: The plant is operating at 90% power. i 1 .J }, _ INITIATING CUES: l Maintenance has tumed in a tagging request to clean E 58, SCC Service Water Exchanger. You are required to fill out all necessary paperwork and have all necessary checks performed to tag this Service
- Water Heat Exchanger for cleaning. The White Tags are not to be hung at this time.
EVOLUTION STANDARDS: , The trainee will demonstrate the ability to Danger Tag / White Tag a safety class component. !
REFERENCES:
} QA Procedure 0141 j ', i
- SIMULATOR
i N/A NOTE: The evaluator should provide an Attachment C of procedure 014-1, White Tag order Master index, filled out to the point that the trainee will be able to determine tne next sequential tagging order number, The Evaluator shall also provide a Tagging Order Request (Attachment M of 014-1) for E 5B. The minimum tagout required per procedure 014-1 is '. attached to this JPM. y s r JPM New.33 PAGE 2 OF 6 i
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE, i 1 Trainee understands intended work scope of tagging order. Standard: Trainee asks questions of wnrker (Evaluator) as necessary to fully understand work scope. 1 NOTE: Trainee may ask Evaluator as many questions as necessary to understand scope of work. Trainee should be told that the endbells of the heat exchanger will be removed and ends of the heat exchanger will be cleaned out. J O SATISFACTORY O UNSATISFACTORY COMMENTS: i 2.
- Trainee enters information on Attachment C for next sequential White Tagging Order number.
Standard: Trainee fills out WIT for, W/T By, Date, and Equipment while referring to Attachment M of 0-14-1. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-33 PAGE 3 OF 6
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
- Fills out Attachment A of 0141,
, Standard: Completes Attachment A referring to FMS and Attachment M of 0-14-1. l NOTE: Completed Attachment A of 0-14-1 for the minimum tagging boundary required is attat.hed to the back of this JPM. i l O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
- Realizes that ths Service Water Heat Exchanger is Safety Class and an Independent Verification is required.
Standard: Vocalizes or indicates to the Evaluator that this Tagout requires an independent verification.
/
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-33 PAGE 4 OF 6
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5. Fills out necessary information on White Tags. Standard: Fills out Order No., Tag No., Valve No., and Position on Tag. O SATISFACTORY O UNSATISFACTORY COMMENTS: 6.
- Obtains PSS permission to release equipment.
Standard- Vocalizes or indicates to the Evaluator that this Tagout requires PSS permission to release the equipment. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-33 PAGE 5 OF 6
EVOLUTION CONDITIONS: The plant is operating at 90% power. i INITIATING CUES: Maintenance has turned in a tagging request to clean E 5B, SCC Service Water Exchanger. You are required to fill out all necessary paperwork and have all necessary checks performed to tag this Service Water Heat Exchanger for cleaning. The White Tags are not to be hung at this time.
.t t
I JPM New-33 PAGE 6 OF 6
" 4 FO R TRAli2NG USE ONLY %hNb e Page 68 of 74 . ATTACHMENT M (Sheet 1 of 1)
TAGOUT REQUEST FORM To: Plant Shift Superintendent / Shift Operating Supervisor: It is requested that the following equipment be tagged out, de-energized, drained and depressurized as necessary to perform the maintenance described below. EQUIPMENT: DATE & TIME WORK WILL BEGIN:
. 2 58 .
WOf: ppgg7 SAFETY CLASS: 56-3 4 WORK TO BE PERFORMED: 0/eAd and T~dpW V F 58 SernniJ7 Seevid idalee hlend Gebe..yee eda //>e#s SPECIAL TAGGING INSTRUCTIONS OR SYSTEM LINEUPS: ^
@q/je SLC-/68 los// N Semwe/ WJiea eddbr//N 12e mesed.
TAG TO: d4d/w// RESP.SECgT SIGNATURE: ou ab REVIEWED BY: PerronRegtjestingTags Operations DATE: FO R T RA. NING USE ONLY
u m/um egw a s p u s sp a r1m - - W' 3*/ //of7&7 MAINEYANKEEhAGGINGORDER E" . r.. IG USEOND ser 6 or.xsm No. p39, / ,7 L MAINE YANKEE TAGGING ORDER Prepared By: Tags Checked and Equipment Date / / Vertfled De-e ergized/St@ 6.3.3: Issued By: Date / / Tagging Order Cleared: Tagged For 01445b4 // PSS/ SOS Verify All Holds and Grounds WO/ PROC /ADNIN CONTROL 97-9999 _ Removed: Tag Out' Validated.By'*l COMPONENT TArrIn AfD REASON-1.,l.icensed* ator-Second Knowledgeable Authortred Person (N/A) Safety Class (1. 2. 3 or IE) Yes X No If Yes. Independent vertfication is required and complete following: > N NOTES: h i m
- 2. Equipment returned to service or M functional test pending
- ATTACINENTS YES
- Hold Sheet au Panalarms Disabled: "
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Rev. No. 18 Page 63 of 74 ATTACHMENT H (Sheet 1 of 1) j TAG 0lR REQUEST FORM To: Plant Shift Superintendent / Shift Operating Supervisor: It is requested that the following equipment be tagged out, de-energized, drained and depressurized as necessary to perform the maintenance described below. DATE & TIME WORK WILL BEGIN: EQUIPMENT: SAFETY CLASS: WOf: WORX TO BE PERFORMED: SPECIAL TAGGING IN3TRUCTIONS OR SYSTEM LINEUPS: TAG TO: RESP SECTION: REVIEWED BY: SIGNATURE: Person Requesting Tags Operations _ _ . . . . DATE:
JOB PERFORMANCE MEASURE---SRO ADMIN JPM NUMBER: New-31 TASK NUMBER: K/A 2 3.5 TITLE: PERFORMING A HAND AND FOOT FRISK TIME t.,RITICAL: O YES 5 NO START TIME: ALTERNATE PATH: O YES M NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE: 1. All actions in the plant will be SIMULATED. The trainee and examiner are MQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. Ail controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 10 Minutes IMPORTANCE RATING: 2.3/2.5 REQUIRED TOOLS AND EQUIPMENT: Frisker PREPARED / REVISED BY: DATE: k7 APPROVED BY: [ DATE: t/[3/17 1 < REVISION #: 0 DATE: 3/18/97 JPM New-31 PAGE 1 OF 6
. _. .. .. . - - _ ~ - - . . - - . . .
SAFETY CONSIDERATIONS: None
.k EVOLUTION CONDITIONS:
The plant is operating at 90% power. INITIATING CUES: You are the Spare CRO and you have been asked to check that the EFW digital controllatrons are indicating zero (0) flow.
' EVOLUTION STANDARDS:
A hand and foot frisk must be performed prior to exiting the P.CS to outside. The trainee will
' demonstrate the proper method of performing a hand and foot frisk in accordance with radiological procedures.
REFERENCES:
+
Procedurs 9-3-100, RADIATION PROTECTION SURVEILLANCE. Posted instructions at the frisking station. GET Lesson Plan GT-GET-08 SIMULATOR: N/A-4 JPM New-31 PAGE 2 OF 6
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 1. i Checks background count rate of frisker. Standard: Observes count rate on frirkar and ensures countrate is less than 300 cpm. NOTE: Frisker background should be less than 300 cpm. If not, student should perform a cursory frisk to ensure that gross amounts of contamination are not present and proceed to the closest available frisker with the proper background levels. 1 0 SATISFACTORY O UNSATISFACTORY COMMENTS:
! e I
l 2. l 4
- Ensure instrument is operating with audible response and on the "x1" scale.
Standard: instrument scale is selected to the "x1" scale and audible response is present. 1
-r O SATISFACTORY O UNSATISFACTORY COMMENTS:
JPM New-31 PAGE 3 OF 6 l
t PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCEGSFUL PERFORMANCE- - I t 3.
. Ensures frisker source check date is within applicable dates.
Standard: Checks that the frisker has been source checked today. O SATISFACTORY C UNSATISFACTORY COMMENTS: 4.
- Frisks the hand that is to be used to handle the probe.
Stancard: Moves palm then the back of the hand across the instrument probe at a rate of 1" to 2" per second at a dictance of % to % inches from the hand's surface. Cue: O SATISFACTORY O UNSATISFACTORY COMMENTS: JPMjiew-31 PAGE 4 OF 6
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ( 5.
' Frisks hands and feet.
Standard: Using the hand that was determined to be free of contamination, student frisks hands, tops, sides, and bottoms of feet at a rate of 1 to 2 inches per second at a distance of % to % inches from the surface. l O SATISFACTORY O UNSATISFACTORY COMMENTS: r JPM New-31 PAGE 5 OF 6
. - . . . . - _ -,-. . . _ . . _ _ . - . . . . - . . - - . - ~ .. - . --- .. ..
- f -
- EVOLUTION CONDITIONS:
i !
\
- The plant is operating at 90% power, l
O. INITIATING CUES: You are the Spare CRO and you have been asked to check that the EFW digital controllatrons are indicating zero (0) fbw. i 1 j l t i i i i 1 JPM New-31 PAGE 6 OF 6
JOB PERFORMANCE MEASURE---SRO ADMIN JPM NUMBER: AD-0901-2-1 TASK NUMBER: K/A 2 4.38 i TITLE: IMPLEMENTING E-PLAN DUE TO LOSS OF MCB ANNUNCIATORS - SRO l ONLY j TIME CRITICA.L: NYES O NO START TIME: ALTERNATE PATH: O YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Lccation and operation of eouipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The apolication of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: O PLANT h SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 15 Minutes IMPORTANCE RATING: 2.2/4.0 REQUIRED TOOLS AND EQUIPMENT: 2-50-0 2-50-1 PREPARED / REVISED BY: - DATE: d 7 APPROVED BY: [ DATE: L/,/'3/77 , REVISION #: g 2 DATE: 3/27/97 JPM AD-09vi-1-1 PAGE 1 OF 8
SAFETY CONSIDERATIONS: None j.h pr'{'t i { p';.- EVOLUTION CONDITIONS: n g,) y M( s Plant is at 100% power. You are the Plant Shift Superintendent.
jjc
/
e INITIATING CUES: i' You are the PSS with the plant @ 100% power. The plant has just sustained a lightning strike causing a loss of Main Control Board annunciators} You are to asses EVOLUTION STANDARDS: Within 15 minutes, the trainee should declare an unusual event and make appropriate notifications.
REFERENCES:
i 2 50-0, EMERGENCY CLASSIFICATION
- 2-501, UNUSUAL EVENT PRR 95-081 PRR 96-162 SIMULATOR
*- 1. Reset Simulator to 100% IC.
- 2. Insert malfunction AN02B and C to remove MCB annunciators.
- 3. Freeze simulator.
JPM AD-0901-2-1 PAGE 2 OF 8
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 1. Trainee may ask for more information regarding the lightning strike.
- Standard: As above.
Cue: NPO reports several strikes on site., CRO reports several panalarms were received prior to the loss of annunciators. NOTE: it may be necessary at this point ta explain to the trainee that the primary focus of this JPM is E-Plan implementation. It is not the intent of the JPM that he tries to troubleshoot and solve the problem. Record Start Time O SATISFACTORY O UNSATISFACTORY I COMMENTS: 2. 1
- Reference E-Plan classification Procedure 2-50-0.
Standard: Trainee references Procedure 2-50-0 Attachment A, Emeqiency Condition Classification Matrix. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 JPM AD-0901-2-1 PAGE 3 OF 8
PERFORMANCE CHECKLIST
- STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
Lf( l 3.- l
- Classify the event as an " Unusual Event" based on 2 50-0, Attachment A, Subcategory 2.1.
Standard: As above. Cue: If asked, plant computer is ivailable and capable of displaying data requested. l. l O SATISFACTORY O UNSATISFACTORY COMMENTS: 4. Obtain copy of Procedure 2-50-1, UNUSUAL EVENT. Standard: As above. O SATISFACTORY- 0 UNSATISFACTORY COMMENTS: JPM AD-0901-2-1 PAGE 4 OF 8 U
1 PERFORMANCE CHECKLIST r . : STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
. -{ '
5.' ' Announce to Control Room that an Unusual Event has been declared.
- Standard:
As above. + 4 f f i 1-O . SATISFACTORY O UNSATISFACTORY p ~ COMMENTS: d 1 I ] - 6. 1-e Direct STA to perform emergency notifications per 2 50-5, EMERGENCY NOTIFICATION. l Standard: As above, i Cue: STA commences 2-50-5. i-O SATISFACTORY 0. UNSATISFACTORY f COMMENTS: p js i 4: JPM AD-0901-2-1 PAGE 5 OF 8
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 7. e-
- Sound evacuation alarm and make Unusual Eeunt announcement over FEMCO.
Standard: As aoove. O SATISFACTORY O UNSATISFACTORY COMMENTS: d i 8. Fill out appropriate information on 2-50-1, Attachment A, Maine Yankee Emergency Notification form. 4 Standard: Maine Yankee has declared: Unusual Event, Wind: direction and speed, Problem: Loss of Annunciators, Radiological Release: Has not occurred. PAR: None, NOTE: Current wind speed and direction is provided using SPDS on MET tower data. O SATISFACTORY O UNSATISFACTORY COMMENTS: i 4 4 JPM AD-0901-2-1 PAGE 6 OF 8 ! l l
PERFORMANCE CHECKLIST l 4 STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: I 9.
*Make emergency notification to State Police within 15 minutes.
Standard: State Police are informed of minimum information stated in Step 8 Standard , within 15 minutes of the emergency declaration time as recorded in 2-50-1, Step 6.1.1 or on Att. A. NOTE: Record notification time: O SATISFACTORY O UNSATISFACTORY - COMMENTS: 1 . 4 i JPM AD-0901-2-1 PAGE 7 OF 8
EVOLUTION CONDITIONS: . Plant is at 100% power. You are the Plant Shlft Superintendent, \ INITIATING CUES: You are the PSS with the plant @ 100% power. The plant has just sustained a lightning strike, causing a loss of Main Control Board annunciators, -You are to assess and implement the E-Plan, if required. 4 I JPM AD-0901-2-1 PAGE 8 OF 8 a . ..
JOB PERFORMANCE MEASURE---SRO ALTERNATE 9 JPM NUMBER: M FW-0901-2-1 TASK NUMBER: K/A 059 A2 07 i TITLE: TRIPMiG P-2C LOCALLY TIME CRITICAL: NYES O NO START TIME: ALTERNATE PATH: NYES O NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are tLQl authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.'
- 3. All controlled refecences normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" thee.e personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 1 Minute IMPORTANCE RATING: 3.0/3.3 REQUIRED TOOLS AND EQUIPMENT: None PREPARED / REVISED BY: DATE: [ APPROVED BY: DATE: y/'3/U
/
REVISION #: 5 DATE: 3/21/97 JPM MFW-0901-2-1 PAGE 1 OF 8 1
SAFETY CONSIDERATIONS: l l
- 1. Use CAUTION when around rotating equipment. l
- 2. Use CAUTION when around high temperature piping.
EVOLUTION CONDITIONS: ? The plant is steady state at 57% power with P-2C speed being increased prior to placing in service. P-2C is in service feeding with SGs. .s INITIATING CUES: , P-2C is at 4,000 RPM when vibrations on the turbine begin to increase. The Control Room has tried to trip P-2C but it did not trip. You have been directed to trip P 2C at the local control panel. EVOLUTION STANDARDS:
' The trainee will demonstrate the ability to trip P-2C from the local panel and via the manual hydraulic trip pushbutton. , REFERENCHS:
PRR 92-120 l PRR 96-162 i SIMULATOR: N/A l JPM MFW-0901-2-1 PAGE 2 OF 8
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: I
- l 4 ' Trip P 2C at the local control panel.
Standard: EMERGENCY TRIP pushbutton depressed. Cue: P 2C does not trip. Attempt a hydraulic tnp. O SATISFACTORY O UNSATISFACTORY COMMENTS: 2.
- Trip P-2C using the manual HYDRAULIC EMERGENCY TRIP pushbutton.
Standard: 1) Cover the pushbutton raised.
- 2) Pushbutton fully depressed.
Cue: P 2C trips. i O SATISFACTORY O UNSATISFACTORY COMMENTS: s[ ' - t JPM MFW-0901-21 PAGE 3 OF 8
EVOLUTION CONDITIONS: l The plant is steady state at 57% power,,ith P 2C speed being increased prior to placing in service. P- ; 2C is in service fooding with SGs. i INITIATING CUES: ! P 2C is at 4,000 RPM when vibrations on the turt>lne begin to increase. The Control Room has tried to trip P 2C but it did not trip. You have been directed to trip P 2C at the local control panel, i i I l f
-9 Y
i i i 1 't
?
4 JPM MFW 090121 PAGE 4 OF 8
t JPM QUESTION #1 MFW490121 ( QUESTION: What is the effect on the Main Turpine from this manual trip of P 2C7 ANSWER: No effect. (As long as a motor driven FW pump is running, the logic for MT trip is not made up.) SATISFACTORY: YES NO
REFERENCES:
RO-L-3.7 TASK IMPORTANCE: 2,3/3.5 TASK NUMBER: K/A 059 K4.02 LEARNING OBJECTIVE: MT 01019, MFW 010217 TRAINEE ANSWER / COMMENTS: JPM MFW-0901-2-1 PAGE 5 OF 8
+ E JPM QUESTION #2 MFW-0901 2.1 QUESTION: To what position does the recirc control valve go when P 2C is tripped? Why? ANSWER: The recire control valve opens to 25% open to provide cooldown recirc flow, l t 1 SATISFACTORY: YES__ NO REFERENCES; EDCR 86 36, OP 1104 5 (pg 1) TASK IMPORTANCE: 2,4/2.6 TASK NUMBER: K/A 059-KS.09 LEARNING OBJECTIVE: MFW-0102-19 TRAINEE ANSWER / COMMENTS: JPM'M FW-0901-2-1 PAGE 6 OF 8
i I JPM QUESTION #1 MFW-0901 2-1 QUESTION: What is the effect on the Main Turbine from this manual trip of P 2C7 JPM MFW-0901-2-1 PAGE 7 OF 8
JPM QUESTION #2 MFW 09012.1 QUESTION: To what position does the recirc control valve go when P 2C is tripped? Why? JPM MFW-0901-2-1 PAGE 8 OF 8
. u
JOB PERFORMANCE MEASURE--RO I JPM NUMBER: New-8 TASK NUMBER: 082-A4 01 i TITLE: Restoring Site Power from the 115KV Switchyard During Loss of All AC Power TIME CRITICAL: O YES N NO START TIME: ALTERNATE PATH: O YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: C PASS O FAIL QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TMINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who w;ll ' role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 30 Minutes IMPORTANCE RATING: RO-3.3, SRO-3.1 REQUIRED TOOLS AND EQUIPMENT: ECA 0.0 OP 1-22-3 PREPARED / REVISED BY: DATE: f' /97 APPROVED BY: [w DATE: 3/97 REVISION #: e 0 DATE: 3/11/97 JPM New-8 PAGE 1 OF 15
_~ _ ._ _ _ _ _ __ _ . . . __ -__ _. SAFETY CONSIDERATIONS: None i EVOLUTION CONDITIONS: i A loss of all AC power has occurred and ECA 0.0 is in progress. All DGs and the 345KV Switchyard are i unavailable. The 115KV Switchyard has just become available up to Breakers 3R and 4R. All work on Buses 3 thru 6 has been completed. All ground trucks have been removed. Workers are clear of the Busses. INITIATING CUES: You are the secondary RO (BOP). The SOS has directed you to restore power to Buses 3 and 5 from the 115KV Switchyard per ECA 0.0 Attachment P. EVOLUTION STANDARDS: Trainee will energize Buses 3 and 5 from the 115KV Switchyard IAW ECA-0.0 Attachment P.
REFERENCES:
ECA 0.0, Loss of All AC Power OP 122 3, Station Service Power Operation and Breaker Operation SIMULATOR: 1 Initialize to a 90% IC.
- 2. Inseri malfunctions EG06 (failure of DG 2), EG04A and B (DG trip), ED03A and B (loss of X14 and X16), EG02A and B (loss of main transformers).
- 3. Place Breakers DG 1 A, DG 18,4T6,3T5,3R and 4R in PTL. Perform manual reactor trip and perform actions of ECA-0.0 up to Step 10.
- 4. Clear malfunction ED03A (X14). Shut T14H, place SYN K69-7 in ON, shut K69-7, and then place SYN K69-7 in OFF.
- 5. Reset all overcurrent/undervoltage relays. (remote function YP101)
- 6. Freeze simulator and tum over to trainee.
JPM New-8 PAGE 2 OF 15
,g- - -- -
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 1. Ensure control switches in ECA 0.0 Step 9 have been placed in PTL Standard: Following are checked in PTL: e LPSI pumps (P 12A, P 128, P 61S) e Containment spray pumps (P-61 A, P-61B, P-61S) e RCPs (P 1 1, P 12, P 13) e Primary water pumps (P 24A, P 248) e Boric acid pumps (P 6A, P 68, P-6C) e HPSI pumps (P 14A, P 148, P 14S) e
)
Pressurizer healers (E 2PA, E 2PB, E 2A thru E-2F) ; e EFW pumps (P 25A, P 25C) e MFW pumps (P 2A, P 2B) e Heater drain pumps (P-62A, P-628) e _ Condensate pumps (P 27A, P 278, P-27C) e Raw water pumps (P 60A, P 608) e Circulating water pumps (P 26A thru P 26D) e Screen wash pumps (P-63A, P 638)
- EHC pumps (P 55A, P 558)
- Turbine AC lube oil pumps (P 87, P 49, P-88) e Containment recirculation fans (FN 171 thru FN 17 6)
** One PCC pump (P 9A or P 98) -
e One SCC pump (P 10A or P 108) Cue: Trainee should determine that attachment Step 2.A can NOT be done and that attachment Steps 2.B.1.a and 2.B.1.b have afriidy been complitid, as described in the Evolution Conditions. If asked, then cue that this is the case. O SATISFACTORY O UNSATISFACTORY COMMENTS: Ji)M New-8 PAGE '< SF 15
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 2. ;
Verify no alarms on Section RS except for X 16 (RS-3 3, RS-4 3). Standard: As above. Cue: If trainee is held up by the presence of alarm 3 2, then SOS informs him to continue with his power restoration while someone else deals with that alarm. Note: Alarm 3 2 will be in for this scenario, but it is not intended that the trainee expend any effort trying to clear this alarm. O SATISFACTORY O UNSATISFACTORY COMMENTS: 3. Ensure X 14 is energized and available to power Buses 3 and 4. Standard: Check 115KV Section 69 bus voltage greater than 112 KV, check K-69-7 Section 69 load breaker shut, and check T-14H X 14 disconnect shut. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-8 PAGE 4 OF 15
PERFORMANCE CHECKLIST ! l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
$ I.
4. i Ensure Breakers 3R,3U in PTL. Standard: As above, 4 O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 a 5. l. j Ensure following pumps and breakers in PTL: , Bus 3
- 3091 4
3090 3111 3110
- 3131 3130 1 P.26A and C P-27A
- P-62A i
Standard: As above. Cue: When asked, (1) PT fuses are installed, (2) DC control power breakers are shut, i (3) overcurrent relays are reset, and (4) Breakers 3R is racked up. O SATISFACTORY O UNSATISFACTORY COMMENTS: 3 d JPM New-8 PAGE 5 OF 15
I PERPORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
~
6. ! ' Shut reserve supply breaker 3R. 4 . 4 l Standard: As above. Cue: If asked, perform remote function YP101 to make sure all trip flags and relays have been reset, then report to trainee that trip flags have been reset and , personnel have been dispatched to align 480V bus power. , O SATISFACTOky O UNSATISFACTORY ., COMMENTS: i i ENERG: ZING BUS S FROM BUS 3 F. Ensure Breaker 3T5 is PTL. Standard: As above. , O SATISFACTORY O UNSATISFACTORY COMMENTS: l l l l l l l i l JPM New-8 PAGE 6 OF 15 -
( PERFORMANCE CHECKLIST , STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: t 8. Check DG 1 A output breaker in PTL. Standard: As above. O SATISFACTORY O UNSATISFACTORY
, COMMENTS:
9.
- Ensure Bus S undervoltage relay is reset.
Standard: 27Y-5 retet. (white lights on) O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-8 PAGE 7 OF 15 l
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ( 10.
- Ensure STAS is reset.
Standard: Verify Si not actuated by checking annunciators and ECCS lightbox indications. If actuated, then reset using SIAS reset switches. Cue: When asked, (1) PT fuses are installed, (2) Breaker 18 is closed on DC Bus 1. O SATISFACTORY O UNSATISFACTORY COMMENTS: f ll - 11, Ensuie following pumps and breakers in PTL: S.wi 3 P 14A and S P-61A and S P 12A P-9A and B P 25C 5071 5070 SR Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: a JPM New-8 PAGE 8 OF 15
PERFORMANCE CHECKLIST H I STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i I i 12. 3
- Ensure 3T5 is racked up.
Standard: As above. Cue: When asked, seismic wheel chocks are installed on all breakers that are to remain racked down. 1 0- SATISFACTORY O UNSATISFACTORY COMMENTS: 13.
' Ensure Bus Tie enable switch SS4 TS is iri NORMAL.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-8 PAGE 9 OF 15
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 14. 1
' Shut tie breakers 3T5. l Standard: As above.
O SATISFACTORY O UNSATISFACTORY COMMENTS: 15. Ensure breakers 3T5 is charged after closing. Standard: Trainee contacts AO to verify breakers charged after closing. Cue: Breakers are charged, trip flags have been reset and personnel have been dispatched to align 480V bus power, JPM is complete. O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 JPM New-8 PAGE 10 OF 15
EVOLUTION CONDITIONS: A loss of all AC power has occurred and ECA-0.0 is in progress. All DGs and the 345KV Switchyard are unavailable. The 115KV Switchyard has just become available up to Breakers 3R and 4R. All work on I i Buses 3 thru 6 has been completed. All ground trucks have been removed. Workers are clear of the Busses. INITIATING CUES: You are the secondary RO (BOP). The SOS has directed you to restore power to Buses 3 and 5 from the 115KV Switchyard per ECA-0.0 Attachment P. D JPM New-8 PAGE 11 OF 15 i
- . - . . . . . . - . - . . - . - . . . - . . . - . - - . ~ . . - . - - - - . . . - - . - - . . ~ - -
JPM QUESTlON #1 2
. NEW4 QUESTION: What is the significance of the white light above 1R,2R,3R, and 4 R being out (i.e., not lit)?
f
- ANSWER: There is no control power available l
l 4 SATISFACTORY: YES NO
REFERENCES:
RO-L 5.2 TASK IMPORTANCE: 4.3/4.5 TASK NUMBER: 056-AA2A4 LEARNING OBJECTIVE: AC-0101 16(C) TRAINEE ANSWER / COMMENTS: JPM New-8 PAGE 12 OF 15
JPM CUESTlON #2 , NEW4 QUESTION: What is the purpose of the reclose circuit on 115KV breakers (line 207 reclosing)(what does it do if in the "On" position)? 4 ANSWER: Associated breaker will reclose one second after tripping from a line protection signal if: ! A. Both sides of breaker are in phase or B. One side of breaker is de energized. j SATISFACTORY: YES NO
REFERENCES:
R O L 5.2 TASK IMPORTANCE: 3.3/3.1 TASK NUMBER: 062 A4.01 LEARNING OBJECTIVE: AC-0101-4 TRAINEE ANSWER / COMMENTS: JPM New-8 PAGE 13 OF 15
JPM QUESTION #1 NEW-8 QUESTION: What is the significance of the white light above 1R,2R,3R, and 4 R being out (i.e., not lit)? l JPM New-8 PAGE 14 OF 15 I
JPM QUESTION #2
- NEW-8 QUESTION
What is the purpose of the reclose circuit on 115KV breakers (line 207 reclosing)(what does it do if in the "On" position)' J' JPM New-8 PAGE 15 OF 15 y ..
, a m_* ea C_ . _ _ . _ - - m w h_4me.i -.-_J._ W u - A_ __m. .2J. a,__dA_ , _ _ _-. A __m-_*.+ ___Ju_ 6 4 .-,a JOB PERFORMANCE MEASURE---RO 2.
JPM NUMBER: SNO-09051 2 TASK NUMBER: K/A 015A1.01 TITLE: PERFORMING Nl CAllBRATION TIME CRITICAL: O YES h NO START TIME: ALTERNATE PATH: 3 O YES 5 NO STOP TIME: PERFORMANCE i TRAINEE: ! 4 PERFORMANCE RESULTS: O PASS O Fall i EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are N.QI autnorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be desenbed. . 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this ovaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play
- these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 15 minutes IMPORTANCE RATING: 3.5/3.8 REQUIRED TOOLS AND EQUIPMENT:
- 1. 3-1-31
- 2. Simulator Modcomp available PREPARED / REVISED BY: DATE: 7 APPROVED BY: [ DATE: h3/97 ii
( REVISION #: 10 DATE: 3/11/97 JPM SNO-0905-1-2 PAGE 1 OF 16
SAFETY CONSIDERATIONS: None i EVOLUTION CONDITIONS: The plant is steady state at power, e INITIATING CUES: You are the primary RO. You are to complete a daily calorimetric adjustment of Channel A in accordance Procedure 3-1-31, RPS CHANNEL ADJUSTMENT. EVOLUTION STANDARDS:
- After receiving the initiating cue, the trainee will complete an NI calibration on Channel A.
REFERENCES:
3131 - RPS CHANNEL ADJUSTMENT 3-12 3, SHORT FORM CALORIMETRIC PRR 92-041 PRR 92-120 PRR 93-010
^ PRR 96-109 PRR 96162 SIMULATOR:
1, Reset to a steady state rated power IC.
- 2. Bring in the trainee and conduct a tumover,
+ f e JPM SNO-0905-1-2 PAGE 2 OF 16
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 1. .
4 Obtain a copy of 3131, RPS CHANNEL ADJUSTMENT. i ' Standard: Trainee is provided a copy of 3131 when referenced. Procedure 3-12-3 may also be requested. 4 O SATISFACTORY O UNSATISFACTORY , COMMENTS: 4 m t
! 2.
Complete BACKGROUND DATA and PARAMETER Section of Attachment B. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 i e f JPM SNO-0905-1-2 PAGE 3 OF 16 _ _ -_ _ . _ _ _ _ , _ - . . _ __ c_, . . . . . .
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i . 3. Check RPSCIP DVi.4 calibration. I Standard: 1) 64ETER INPUT switch placed in METER INPUT position.
- 2) The three (3) reference voltage test pushbuttons (zero, +10V, -10V) depre: sed individually and indication checked within S mV of applied voltage (1.005V).
1 0 SATISFACTORY O UNSATISFACTORY COMMENTS: i l
- 4.
4 Check nuclear and AT amplifier calibration. Standard: 1) METER INPUT switch to NUCLEAR PWR position.
- 2) Calibrate pushbutton, depressed.
! 3) 200% i 1% indicated.
- 4) Repeat 1) thru 3) for AT PWR position.
O SATISFACTORY O UNSATISFACTORY COMMENTS: a d z J JPM SNO-0905-12 PAGE 4 OF 16
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5.
' Determine calorimetric power level.
Standard: Power level determined from PTID 1690 on MODCOMP. O SATISFACTORY O UNSATISFACTORY COMMENTS:
)
6.
'Obtain Calorimetric Power, RPS excore power, and RPS AT power.
Standard: Data entered on CALORIMETRIC DATA section of Attachment B. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM SNO-0905-12 PAGE 5 OF 16
_ . . . . = . . _ . _ _ . - . . - . - . . - . . . . - . - .- PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 4 7. t i
- Calculate CALADJ.
i
- Standard: CALADJ Data entered Attachment B.
O SATISFACTORY C UNSATISFACTORY COMMENTS: 3 d , 8. Record AS FOUND NUCLEAR PWR CAllBRATE NI pot setting. Standaro: As above. ) O SATISFACTORY O UNSATISFACTORY I COMMENTS: I 2 ) 3 2 i JPM SNO-0905-1-2 PAGE 6 OF 16
~.__ _ _ _ _.__. _ _ _.._ _._ __ _ . _ _ . . . _ _ _ _ . _ . _ _ _ _
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: l .k 1 9.
- Check nuclear power DVM indication within 5% of calorimetric power, then adjust to calorimetric power.
Standard: 1) METER INPUT switch to NUCLEAR PWR.
- 2) Verify DVM reading within 15% of power level in JPM Step 5 (calorimeter power).
- 3) Unlock NUCLEAR PWR CAllBRATE pot.
- 4) Slowly adjust pot until DVM reading equal to calorimetric power.
O SATISFACTORY O UNSATISFACTORY COMMENTS: 10. Engage pot locking device.. Standard: 1) As above.
- 2) If DVM indication shifts due to the locking action, pot is readjusted and locked until satisfactory.
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM SNO-0905-1-2 PAGE 7 OF 16
PERFORMANC 3 CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: l 11. I g Record AS LEFT NUCLEAR PWR CAllBRATE pot setting, i i Standara: As above, i O SATISFACTORY O Ulii 'ISFACTORY
. COMMENTS:
! I e i a 12. Record AS FOUND AT POWER CAllBRATE pot setting. I f Standard: Ac above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM SNO-0905-1-2 PAGE 8 OF 16
[ PERFORMANCE CHECKLIST I STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: )-
- . 13.
4 l ' Check AT power DVM indication within ! 5% of calorimetric power, then adjust to calorimetric power.
- Standard
- 1) METER INPUT switch to AT PWR position.
- - 2) Verify DVM reading within 5% of calorimetric power, ,
- 3) Unlock AT POWER CAllBRATE pot.
- 4) Slowly adjust pot until DVM reading equal to calorimetric power, I-l O. SATISFACTORY O UNSATISFACTORY COMMENTS:
l i 4
; 14.
Engage pot locking devi:e Standard: 1) As above.
- 2) lE DVM indication shifts due to the locking action, THEN pot is readjusted and locked until satisfactory.
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM SNO-0905-1-2 PAGE 9 OF 16
PERFORMANCE CHECKLIST I . STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 i l
.15. '
' Rscord AS LEFT AT POWER CALIBRATE pot setting.
3 Standard: As above. i .. !' O SATISFACTORY O UNSATISFACTORY $ COMMENTS: 1 l 16. Check that DVM and MCB chart recorders for both nuclear power and AT power agree within 1 SE Standard: As above. O SATISFACTORY O UNSATISFACTORY l
- COMMENTS:
JPM SNO-0905-1-2 FaGE 10 OF 16
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 17. Document latest TQ values. Standard: 1) Request TQ output on the Control Room INCA terminal by selecting Control Room INCA option from main menu. '. ' 2) Log the TQADJ factors from the OPERATIONS OUTPUT of the INCA ! output in the TQ ADJUSTMENT DATA section of Attachment B. O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 i i j I i JPM SNO-0905-1-2 PAGE 11 OF 16 I
EVOLUTION CONDITIONS: The plant is stea'dy state at power. INITIATING CUES: You are the primary RO. You are to complete a dally calorimetric adjustment of Channel A in accordance with Procedure 3-131, RPS CHANNEL ADJUSTMENT. l JPM SNO-0905-1-2 PAGE 12 OF 16 l
QUESTION #1 4 - SNO-0905-1-2 QUESTION: How does the power range nuclear instrument signal enter the reactor protection circuitry (what prevents / allows a power range Ni channel signal to be used as " power" signal in RPS)? ANSWER: The power range Ni channel enters the RPS in the TM/LP calculator. Here it is compared against that channels AT power signal and the higher cf the two is auctioneered and passed through as the ' power level" signal to RPS. i L. i
. SATISFACTORY: YES .NO 3
REFERENCES:
RO-L-4.5 page 26, RO-L-4.2 page 23, drawing RPS-12 TASK IMPORTANCE: 4.1/4.2 TASK NUMBER: K/A 015 - K1.01 LEARNING OBJECTIVE: RPS-0101-4 TRAINEE ANSWER / COMMENTS: JPM SNO-0905-1-2 PAGE 13 OF 16
QUESTION #2 SNO-0905-1-2 (. QUESTION: The high voltage bistable is lit on the power range NI. What is the significance with respect to RPS channel operability? ANSWER: The R/S channelis considered operable by Tech Specs. (The HV B/S is tripped 1) when card is removed,2) if power supply fails or 3) if trip test switch is on. This will cause a symmetric offset inp signal to be sent to the RPS trip circuitry. As long as the channel is in the " tripped" condition it is operable per T.S. 3.9.) SATISFACTORY: YES NO
REFERENCES:
RO-L-4.2, page 19. T.S. 3.9 TASK IMPORTANCE: 3.9/3.9 TASK NUMBER: K/A 015-A3.03 LEARNING OBJECTIVE: NI-0102-5 TRAINEE ANSWER / COMMENTS: JPM SNO-0905-1-2 PAGE 14 OF 16 , I i
QUESTlON #1 4 i SNO-0905-1-2 (
- 1 QUESTION: How does the power range nuclear instrument signal enter the reactor protection circuitry (what prevents / allows a power range Ni channel signal to be used as " power" signal in RPS)?
k i' f JPM SNO-0905-12 PAGE 15 OF 16
e QUESTION #2 SNO-0905-1-2 q QUESTION: The high v.hge bistable is lit on the power range N1, What is the significance with respect to RPS channe) operability? 6 5 JPM SNO-0905-12 PAGE 16 OF 16
JOB PERFORMANCE MEASURE--RO 3 JPM NUMBER: PPC-0901-1-2 TASK NUMBER: K/A 010-A4 01 TITLE: PERFORMING PORV VALVE STROKE TESTS TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: O YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS U FAIL QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are (LQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Reom, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM , APPROXIMATE COMPLETION TIME: 5 minutes IMPORTANCE RATING: 3.7/3.5 REQUIRED TOOLS AND EQUIPMENT: OP 1-7 OP 3-1-20.4 PREPARED / REVISED BY: DATE: [/'J 7 APPROVED BY: [ DATE: L/[3ft? i-REVISION #: 4 DATE: 3/18/97 JPM PPC-0901-1-2 PAGE 1 OF 10
SAFETY CONSIDERATIONS: None q EVOLUTION CONDITIONS: Tt.e plant is shutdown and is preparing for a cooldown for a refuehng outage. INITIATING CUES: You are the Primary RO. You have been directed to perform PORV valve stroke testing per OP 1-7, Section 6.2, Preparation for Plant Cooldown. EVOLUTION STANDARDS: After receiving the initiating cue, the trainee will test both PORVs and ensure they are not leaking IAW
~ OP 1 7.
REFERENCES:
OP 1-7, PLANT COOLDOWN OP 31-20.4, IST VALVE TESTING AT COLD SHUTDOWN PRR 92-041 PRR 92-420 PRR 96-162 SIMULATOR:
- 1. Reset to a HSD IC.
- 2. Bring in the trainee and conduct a tumover.
9. 9 JPM PPC-0901-1-2 PAGE 2 OF 10
-.. . -- . . . . - . . ~ - - . _
4 PERFORMANCE CHECKLIST ~ STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ( 1.
. Obtain a copy of OP 1-7, PLANT COOLDOWN, and OP 3-1-20.4, IST VALVE TESTING AT COLD SHUTDOWN.
Standard: Trainee is provided copies of procedures 17 and 3-1-20,4 when requested. 0 SATISFACTORY O UNSATISFACTORY ! COMMENTS: i-
, 2.
s
- Shut pressurizer PORV isolation MOVs PR-M-16 and 17.
l- Standard: As above. i 4 i> 0 GATISFACTORY O UNSATISFACTORY COMMENTS: C JPM PPC-0901-1-2 PAGE 3 OF 10
4 PERFORMANCE CHECKLIST n > STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ( 3,
- Cycle pressurizer PORV PR-S-14 and verify proper position indication.
Standard:- 1)- Place control switch in OPEN. Verify red light on. 2) ' 3) Place control switch in AUTO.
- 4) Verify green light on and red light out.
4 O SATISFACTORY O UNSATISFACTORY COMMENTS:
;. 4-
' Cycle pressurizer PORV PR-S-15 and verify proper position indication.
Standard: 1) Place control switch in OPEN.
- 2) Verify red light on.
- 3) Place control switch in AUTO.
- 4) Verify green light on and red light off.
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM PPC-0901-1-2 PAGE 4 OF 10 1 _ , _ , _ ~ - - . , . - _ . . _ . . _ . . . - , , , , - . _ - - _ . . - - _ _ ._ _. -. . . , _ . . - , , _
- , I
PERFORMANCE CHECKUST . STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 5.
4 Open PR M-16 and 17. >
- Standard: As above. -
O SATISFACTORY O UNSATISFACTORY COMMENTS:
,w 6.
*Monitsr for indications that PORVs are NOT leaking.
Standard: 1) TE-106, PORV LINE TEMP - approximately 130-140*F (Tl.150).
- 2) QT Level and pressure - constant (Ll-116K, PI-116K).
- 3) Pressurizer pressure - constant (PC-101X 101Y; PR-101X, Y).
- 4) Acoustic accelerometer- not alarming (HI ALARM LEDs off).
O SATISFACTORY - 0 UNSATISFACTORY COMMENTS: l i 1 I JPM PPC-0901-1-2 PAGE 5 OF 10 l
_._..._____q l EVOLUTION CONDITIONS: 1 The plant'is shutdown and is preparing for a cooldown for a refueling outage. l ( . INITIATING CUES:
. You are the Primary RO. You have been directed to perform PORV valve stroke testing per OP 1-7,
. Section 6.2, Preparation for Plant Cooldown. i t I. k-i
..t , 's f-l JPM PPC-0901-1-2 PAGE 6 OF i
i QUESTION #1 i PPC-0901-1-2 QUESTION: How are the backup heaters operated from the switchgear room? Which buses have backup heaters associated with them? ANSWER: Buses 9,10,11,12,13, & 14 each have a backup heater powered from the respective bus. Heaters are operated by taking the normal / emergency switch to emergency and pressing the open/close pushbuttons as desired. SATISFACTORY: YES NO
REFERENCES:
RO-L-2.4, (page 12) TASK IMPORTANCE: 3.0/3.4 TASK NUMBER: K/A 010-K2.01 LEARNING OBJECTIVE: PPC-0102-10 TRAINEE ANSWER / COMMENTS: JPM PPC-0901-1-2 PAGE 7 OF 10
. .-. . - - . . - - ._ . - - . . _ . . . ~ . .-.
QUESTION #2 PPC-0901-1-2
.-( )
QUESTION:' What are two (2) reasons for minimum spray bypass flow? ANSWER: Prevent thermal shock to spray nozzle and equalize RCS and PZR boron concentration. 1 i SATISFACTORY: YES NO
REFERENCES:
RO-S-2,3 (page 8) TASK IMPORTANCE: 2.7/2.9-- TASK NUMBER: K/A 010-K4.01 LEARNING OBJECTIVE: PPC-0102 0 TRAINEE ANSWER / COMMENTS: V JPM PPC-0901-1-2 PAGE 8 OF 10
QUESTION #1 4 PPC-0901-1-2 QUESTION: How are the backup heaters operated from the switchgear room? Which buses have backup heaters associated with them? i I e JPM PPC-0901-1-2 PAGE 9 OF 10
QUESTION #2 PPC-0901-1-2 i QUESTION: What are two (2) reasons for minimum spray bypass flow? JPM PPC-0901-1-2 PAGE 10 OF 10 j
JOB PERFORMANCE MEASURE---RO y JPM NUMBER: New - 23 TASK NUMBER: K/A 003 A4 01 TITLE: ESTABLISHING RdP START CRITERIA FOLLOWING REACTOR TRIP TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: 0 YES NNO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall
- QUESTION RESULTS
- Out of Correct EVALUATOR SIGNATURE: DATE:
l DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are NQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety ru'les, general work practices, and STAR (self-checking) will be examined during this evaluation.
}
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will" role play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 minutes IMPORTANCE RATING: 2.9/2.9 REQUIRED TOOLS AND EQUIPMENT: ES-0.2 PREPARED / REVISED BY: h DATE: //3[97 APPROVED BY: [ DATE: 3/97 REVISION #: 0 DATE: 3/18/97 JPM New-23 PAGE 1 OF 14 _______-._-._j
SAFETY CONSIDERATIONS: None k EVOLUTION CONDITIONS: An l&C technician error inadvertently caused a reactor trip from 90% power. The transfer of Buses 1 and 2 to the reserve transformer occurred slower than normal and resulted in all three RCPs tripping on undervoltage. Following completion of ES-0.1, a transition was made to ES-0.2. INITIATING CUES: C You are the primary RO. You have been directed toho start RCP #1 LAW ES-0.2.
- EVOLUTION STANDARDS:
Trainee will start RCP#1 LAW ES-0.2.
REFERENCES:
ES-0.2, Natural Circulation Cooldown SIMULATOR: (1) Initialize to a 90% IC.
' (2) Manual.y trip reactor.
(3) Stop all RCPs and place all RCP bearing lift pump " master" switches in OFF on back of MCB, l (4) Perform stabilizing actions of ES-0.1. (5) Freeze simulator and turn over to trainee. JPM New-23 PAGE 2 OF 14
- - . . ~ - -
i l PERFORMANCE CHECKLIST ~ STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
-4 1.
Verify CIS "86" devices reset. Standard: Check ECCS lightbox indications normal (CIS-A and CIS-B white lights off) ano CIS "86" devices C1SA1, C1SA2, C1SA6, C1SB3, C1SB4, and C1SBS reset on back of main control board (white light on). J O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 l 4 2. I
- Check power available to RCPs.
Standard: Check Bus 1 energized by voltage indication. Check RCP#1 control switch green indicating light on. O SATISFACTORY O UNSATISFACTORY s COMMENTS: JPM New-23 PAGE 3 OF 14
PERFORMANCE CHECKLIST
- _ STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE
k 3. Check RCS hot and cold leg loop isolation valves open. Standard: Check RCS Loop 1 loop isolation valves RC-M-11 and 12 open. Note: Power is normally tagged removed to these valves, so they have no position indication. Trainee may check tags in place and rely on prior shift operation at full RCS loop flow to infer they are open, or may request an AO to check position locally. Tag check and prior shift experience is sufficient for this i step. Cue: When asked, RC-M-11, and 12 are open. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
- Check RCP #1 oil pumps running in AUTO.
Standard: On bach of MCB, place master switches for RCP #1 bearing lift and backstop oil pumps in AUTO. On front of MCB, place RCP#1 oil pump control switch in AUTO and verify tw.Q red lights above the oil pump control switch come on. O SATISFACTORY - 0 UNSATISFACTORY COMMENTS: JPM New-23 PAGE 4 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 A 5. Check PCC System in operation. Standard: PCC Pump P-9A or P 9B running. C 3ATISFACTORY O UNSATISFACTORY COMMENTS: 6. Check pressurizer spray valves closed. Standard: Check PR-A-1 and PR A 2 closed. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-23 PAGE 5 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 7. c Check NPSH sufficient for RCP operation per TDB Figure 1.2.3 sene i. Standard: As above. RCS pressure-temperature point is above and to left of the RCP NPSH curve on TDB Figure 1.2.3.1. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 8. f 4 If RCS WR Tcoids less than minimum pressurization temperature, then ensure pressurizer level 1 less than 80% and SG temperature less than 100'F above RCS WR T-colds. I Standard: As above.- Refer to TDB Figure 1.2.3.4. Currently, MPT plus margin = 411*F. If RCS WR T-colds less than 411*F, then perform the following: (1) Ensure pressurizer level less than 80%. (2) Refer to TDB Figure 1.2.4. (3) Use SG pressures to obtain saurated SG temperatures. (4) Ensure SG temperatures are less than 100*F above RCS WR T-colds. Note: If RCS WR T-colds are greater than 411*F at this point (expected), then no action is required in this step. 0 SATISFACTORY O UNSATISFACTORY COMMENTS: t 4 i JPM New-23 PAGE 3 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ( 9. If PCC to RCP motors and seals not in service, but seal water has remained in service, then establish PCC cooling LAW AOP 2-50 prior to starting an RCP, Standard: Check PCC-M-150,219,252, and 254 open. Determine that PCC IS in service to RCP motors and seals and that performance of AOP 2-50 is NOT required. O SATISFACTORY O UNSATISFACTORY COMMENTS: 10. I If both PCC and seal water supply flow not in service, then place in service IAW AOP 2-50 prior to restarting an RCP. Standard: Determine that PCC IS in service per Step 10 above and that performance of AOP 2 50 is NOT required. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-23 PAGE 7 OF 14
3 PERFORMANCE CHECKLIST i STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: j
\ . \ \
- 11. l
=== .
If seal water supply is not in service but PCC has remained in service, then establish it IAW i AOP250. i 4 Standard: Determine that seal water supply IS in service and that performance of AOP 2 50 is NOT required. O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 e a I 13. 4 Check seal water return valve for RCP#1 open. l Standard: SL-M-29 is open. Note: Per STAR, trainee should also check SL-A 92 and SL-A-53 open to complete 4 seal return path to VCT. However, this is not a critical task per ES-0.2
- guidance.
i O SATISFACTORY O UNSATISFACTORY COMMENTS: I I ! l l l i l JPM New-23 PAGE 8 OF 14
i l PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: A
- 13. ,
- Start RCP #1. i 4 Standard: As above. Place RCP P-1-1 control switch to START.
Note: By STAR, before starting RCP, verify that two red lights to right of RCP control switch cre on (indicates lift oil pressure 1900 psig interlock is satisfied). White light to right of RCP control switch is not used. O SATISFACTORY O -UNSATISFACTORY COMMENTS: l l JPM New-23 PAGE 9 OF 14
EVOLUTION CONDITIONS: t An l&C technician error inadvertently caused a reactor trip from 90% power. The transfer of Buses 1 ! 4 and 2 to the reserve transformer occurred slower than normal and resulted in all three RCPs tripping on .
}'
undervoltage. Following completion of ES-0.1, a transition was made to ES-0.2. .l i
^
INITIATING CUES: . You are the pric y RO. You have been directed to try to start RCP #1 LAW ES-0.2 I l 1 i i
- ~
1
- s l
4 6 h l I l l i JPM New-23 PAGE 10 OF 14 i
N JPM QUESTION #1 . ; NEW-23
- QUESTION
- What effect does stopping an RCP (assume three are operating) have on the teactor protection system trip bins? ,.
ANSWER: This condition will generate a low flow trip on each channel of RPS (due to low O +fferential , pressure (trip comes in @93% flow)). i 2 l i j 4 4 ( SATISFACTORY: YES NO
REFERENCES:
RO-L-4.5
- TASK IMPORTANCE: 3.9/4.2
- TASK NUMBER
- K/A 003 - K3.04 LEARNING OBJECTIVE: RPS-0101-2 l
l TRAINEE ANSWER / COMMENTS: I i-i 4
.i 4
JPM New-23 PAGE 11 OF 14
JPM QUESTION #2 NEW-23
<{-
QUESTION: Why is it necessary to rapidly pass through the 1025 psig to 1250 psig region when performing a plant heatup (WRT the RCP)? t !- ANSWER: This is the point at which the thrust on the RCP shaft shifts from downward to upward (thrust reversal). 4 SATISFACTORY: YES NO
REFERENCES:
OP 1-1 (Caution on page 26) TASK IMPORTANCE: 3.4/3.4 TASK NUMBER: K/A 003 - A1.07 LEARNING OBJECTIVE: RCP - 0902-2 TRAINEE ANSWER / COMMENTS: l JPM New-23 PAGE 12 OF 14
JPM QUESTION #1' NEW-23 J QUESTION: What e7ect does stopping an RCP (assume three are operating) have on the reactor protection system trip bins? - JPM New.23 PAGE 13 OF 14
JPM QUESTION #2 - NEW-23
-e 't QUESTION: Why is it necessary to rapidly pass through the 1025 psig to 1250 psig region when performing a plant heatup (WRT the RCP)?
e JPM New-23 PAGE 14 OF 14
JOB PERFORMANCE MEASURE---RO s JPM NUMBER: EAS-0901 1 TASK NUMBER: K/A 029 EA1.12 TITLE: PERFORMING FR-S.1 IMMEDIATE ACTIONS TIME CRITICAL: 0 YES 5 NO START TIME: ALTERNATE PATH: NYES O NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of _ Correct EVALUATOR ' SIGNATURE: DATE: DIRECTIONS TO TRAINEE;
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are MQI authorized by ,
this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airoorne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described. 3, All controlled references normally available may be used. Control Room procedures and einecgency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: O PLANT h SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 10 Minutes IMPORTANCE RATING: 4.1/4.0 REQUIRED TOOLS AND EQUIPMENT: None PREPARED / REVISED BY: DATE: b APPROVED BY: [ DATE: t//3/97 REVISION #: f 1 DATE: 3/18/97 JPM EAS-0901-1-1 PAGE 1 OF 14
" SAFETY CONSIDERATIONS:
None EVOLUTION CONDITIONS: i . The plant was at 100% power when a reactor trip was attempted. Plant response was that rods did NQIinsert. INITIATING CUES: j . You are the RO on watch. The SOS directs you to perform all the immediate actions of FR S.1. These actions are to be performed from memory. (You are to perform actions on both sides of MCB.)- , EVOLUTION STANDARDS: After assuming the controls in the Simulator, the trainee will perform all the required immediate actions of FR-S.1 from memory. 3
REFERENCES:
FR-S.1, NUCLEAR POWER GENERATION /ATWS PRR 96-109 PRR 96-162 SIMULATOR: l'
- 1. Reset to an at power IC.
- 2. Insert malfunctions RD-8A and RD-88.
- 3. 10 Buses 9 & 12 feeder breakers closed (BKRS 3090,3091, and 4120,4121).
- 4. Drop two rods to provides a realistic reason to require a reactor trip (RD01).
- 5. Bring in the trainee and conduct a tumover, i
i I I i i JPM EAS-0901-1-1 PAGE 2 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: \ 1.
- Attempt reactor trip by depressing Rx trip buttons.
Standard: Depress RT-1 and RT-2 reactor trip pushbuttons. Also, depress RT-3 and RT pushbuttons. O SATISFACTORY O UNSATISFACTORY COMMENTS: 5 2. l
- Depress ATWS DSS A Trip and B Trip pushbuttons simultaneously.
Standard: Depress ATWS DSS A-Trip and B-Trip pushbuttons simultaneously (MG-1 A and MG-18). O SATISFACTORY .O UNSATISFACTORY COMMENTS: JPM EAS-0901-1-1 PAGE 3 OF 14
- n. .. . .
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: j,
- 3. -
Check CEDM Bus undervoltage lights not lit. Standard: 4 red lights off (UVC-1, 2, 3, 4)
+
0 - SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
- Manually open 480V supply breakers to Buses 9 and 12.
Standard: ACB-4121 to TRIP. ACB-3091 to TRIP. O SATISFACTORY O UNSATISFACTORY COMMENTS: i O JPM EAS-0901-1-1 PAGE 4 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ( S. Reclose 480V supply breakers to Buses 9 and 12. Standard: ACB-4121 to CLOSE. ACB-3091 to CLOSE. O SATISFACTORY O UNSATISFACTORY COMMENTS: I 6.
- Manually trip turbine from MCB.
Standard: Place TT-1 and TT-2 to TRIP. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM EAS-0901-1-1 PAGE 5 OF 14
PERFORMANCE CHECKLIST I STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: k 7. !' m. Ensure all turbine stop, govemor, ir* cept and reheat stop valves are closed. Standard: All 16 green CLOSED light on for turbine valves (SLL, SLU, SRL, SRU, GLL, GLU, GRL, GRU,1RL,1RR,2RL, ill, ilR,2il, and 2lR). O SATISFACTORY O UNSATISFACTORY COMMENTS: 8. Ensure minimum feed for decay heat removal. Standard: Recognizes that a main feed pump with MFRV bypass valves at 32% open position constitutes minimum feed for decay heat removal (HIC-1212,1222,1232 output meters at approximately 32% with either P-2A or P-2B running). 4 O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM EAS-0901 1-1 PAGE 6 OF 14
PERFORMANCE CHECKLIST
= STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
1 9. Ensure at least 60 gpm running EFW pump, if initiated. Standard: If initiated, then P 25A and P 25C running with HIC-1201 A, B, C allindicating greater than 60 gpm per running EFW pump. 4 i O SATISFACTORY O UNSATISFACTORY COMMENTS: 10.
- Initiate Emergency Boratic. .
Standard: Two boric acid pumps manually started (P-6A, B, C), at least one charging pump running (P-14A, B), boric acid valve operated to applicable charging pump (BA-M-36 for P-148, BA-M-37 for P 14A), FIC-212, CH-F-38 controller taken to ' manual and increased to maximum. O SATISFACTORY O UNSATISFACTORY COMMENTS: 1 JPM EAS-0901-1-1 PAGE 7 OF 14
PERFORMANCE 'JHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: t 11. Adjust UD flow controller, as necessary. Standard: Adjust FIC-101, P, Q to increase letdown flow as needed. O SATISFACTORY O UNSATISFACTORY COMMENTS: [ 12. ChedK PZR Pressure less than 2385 psig. Standard: Check pressure <2385 psig on PF *02X or 102Y (PZR WR pressure). O SATISFACTORY O UNSATISFACTORY COMMENTS: i J PMJ AS-0901-1-1 PAGE 8 OF 14
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: Q:
. 13.
l Check VCT levelless than 82%. Standard: - LIC-205 <82% indication, t O SATISFACTORY O UNSATISFACTORY COMMENTS: I
-14;
- Manually insert control rods in manuai saquential mode.
Standard: Control rod drive lever to IN position and MS pushbutton depressed until LIT. Rods observed driving in. ; Cue: End W Jf'M. i
'O SATISFACTORY O UNSATISFACTORY COMMENTS:
h JPM EAS-0901-1-1 PAGE 9 OF 14
EVOLUTION CONDITIONS:
-c ~
The' plant was at 100% power when a reactor trip was attempted. Plant response was that rods did NQIinsert. i INITIATING CUES:'
..You are the RO on watch. The SOS directs you to perform all the immediate actions of FR S.1. These i
. actions are to be performed from memory. (You are to perform actions on both sides of MCB.) '
1 4 i d i i i a I I 1 4 1 JPM EAS-0901-1-1 PAGE 10 OF 14
JPM QUESTION #1 EAS-0901-1-1 s t QUESTION: ES-0.1," Reactor Trip Response" Step 4 RNO requires 2200 gallons of boric acid to be added for each stuck CEA. If the RCS boron concentration is 1000 ppm and two (2) CEAs were stuck, what is the final RCS boron concentration? ANSWER: Approximately 1700 ppm boron. E f SATISFACTORY: YES NO
REFERENCES:
TDB Curve 1.2.5.1, ES-0.1 (step 4) TASK IMPORTANCE: 3.2/3.6 TASK NUMBER: _ K/A 004 A4.04 LEARNING OBJECTIVE: CRC-0101-97 TRAINEE ANSWER / COMMENTS: i / JPM EAS-0901-1-1 PAGE 11 OF 14
JPM QUESTION #2 EAS-0901-1-1 - k.- QUEGliON: What is the relationship between symmetric offset and core power changes? Why do they occur? (Assume the RCS Temperature Program is used.)
- ANSWER:
As core power increases, S.O. decreases and vice versa. They are caused by changes in the axial flux profile due to 1) changes in RCS temperature which affects MTC and 2) magnitude of MTC from top to bottom of core.
/
i SATISFACTORY: YES NO
REFERENCES:
RO-L-1.12 (page 14) TASK IMPORTANCE: 3.4/3.7 TASK NUMBER: K/A 001-A2.06 LEARNING OBJECTIVE: CRC-0101 91, CRC-0101-107 TRAINEE ANSWERICOMMENTS: JPM EAS-0901-1-1 PAGE 12 OF 14
JPM QUEST!ON #1 EAS-0901 1-1 k QUESTION: ES-0.1,-* Reactor Trip Response" Step 4 RNO requires 2200 gallons of boric acid to be added for each stuck CEA. If the RCS boron concentration is 1000 ppm and two (2) CEAs were stuck, what is the final RCS boron concentration? 4 I h JPM EAS-0901-1-1 PAGE 13 OF 14 I
JPM QUESTION #2
. EAS-0901 1 1
.j - QUESTION: .What is the relationship between symmetric offset and core power changes? Why do they
- occur? (Assume the RCS Temperature Program is used.)
9 t JPM EAS-0901-1-1 PAGE 14 OF 14
JOB PERFORMANCE MEASURE---RO v JPM NUMBER: RM S-0901-1-2 TASK NUMBER: K/A 073 A4.02 TITLE: PERFORMING DAILY CHECK OF THE HIGH RANGE PVS MONITOR RM-3903 TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: 0 YES N NO STOP TIME: PERFORMANCE . TRAINEE: PERFORMANCE RESULTS: O PASS O Fall
- QUESTION RESULTS: Out of _ Correct EVALUATOR SIGNATURE: DATE:
DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQ.I authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play' these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR N CONTROL ROOM APPROXIMATE COMPLETION TIME: 2.5 minutes IMPORTANCE RATING: 3.7/3.7 REQUIRED TOOLS AND EQUIPMENT: 3.1.29 PREPARED 6cVISED BY: J DATE: //37 APPROVED BY: - [ DATE: t/,!3,)/7 f REVISION #: 7 DATE: 3/18/97 JPM RMS-0901-1-2 PAGE 1 OF 11
-SAFETY CONSIDERATIONS:
None i EVOLUTION CONDITIONS: The plant is steady state at power. INITIATING CUES: You are the secondary RO. You are to complete 6he daily check of high range PVS monitor, RM 3903 LAW procedure 3.1.29, DAILY RADIATION MONITORING SYSTEM OPERATION TEST. EVOLUTION STANDARDS: After receiving the initiating cue, the trainee will complete the daily checks on the PVS high range noble gas monitor, RM 3903,
REFERENCES:
3.1.29, DAILY RADIATION MONITORING SYSTEM OPERATION TEST. PRR 92-041 PRR 92-120 PRR 96-109 PRR 90-162 SIMULATOR:
- 1. Reset to a power IC.
- 2. Bring in the trainee and conduct a tumover.
JPM RMS-0901-1-2 PAGE 2 OF 11
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: , .x 1.-
- Obtain a copy of 3.1.29, DAILY RMS OPERATION TEST,
. Standard: Trainee is provided a copy of 3.1.29 signed off up to the procedural step required.
O SATISFACTORY O UNSATISFACTORY COMMENTS: - 2, Verify proper operation by checkiag for normal indications. Standard: 1) Digital readout 2 0.00 mR/hrif on scale.
- 2) Bar graph below readout agrees with digital readout if >0.3 mR/hr.
- 3) WARN light off.
- 4) HIGH light off,
- 5) Fall light off.
- 6) RANGE light off (on if reading less than 0.1 mR/hr).
- 7) CHECK SOURCE light off, p
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM RMS-0901-1-2 PAGE 3 OF 11
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: I 3.
- Depress WARN pushbutton and verify digital readout indicates 4 mR/h.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
- Depress HIGH pushbutton and verify digital readout indicates 8 mR/h.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: - JPM RMS-0901-1-2 PAGE 4 OF 11
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5.
' Depress CHECK SOURCE pushbutton.
Standard: 1) CHECK SOURCE light on.
- 2) Digital readout increases to approximately 5 R/h.
I
- 3) Bar graph increases 6 approximately 5000 mR/h.
NOTE: WARN and HIGt M .mi lights may come on, Jepending on setpoints. O SATIS?ACTORY O UNSAilSFACTORY COMMENTS: 3.
- Depress CHECK SOURCE pushbutton again.
Standaro: 1) CHECK SOURCE light off.
- 2) Digital readout and bar graph decrease to normal.
NOTE: Alarm lights should clear. O $.* TISFACTORY O UNSATISFACTORY COMMENTS: JPM RMS-0901-1-2 PAGE 5 OF 11 l
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 7. Verify proper operation by checking for normalindications. Standard: 1) Digital readout = 0.00 mR/hr if on scale.
- 2) Bar graph below readout agrees with digital readcut if >0.3 mR/hr.
- 3) WARN light off.
- 4) HIGH light off.
5). FAIL light off.
- 6) RANCE light of (on if reading less than 0.1 mR/hr.)
- 7) CHECK SOURCE light off.
O SATISFACTORY . O UNSATISFACTORY COMMENTS: 9 JPM RMS-0901-1-2 PAGE 6 OF 11
EVOLUTION CONDITIONS: The plant is steady state at power. s INITIATING CUES: You are the secondary RO. You are to complete the daily check of high range PVS monitor, RM 3903 LAW procedure 3.1.29, DAILY RADIATION MONITORING SYSTEM hnATION TEST. JPM RMS 0901 i 2 PAGE 7 OF 11
JPM QUESTION #1
, RMS-0901 1-2 QUESTION: Where are the main steam line radiation monitors physically located?
ANSWER: Over the main steam lines in the Steam and Valve House near the SG safeties. t SATISFACTORY: YES NO
REFERENCES:
RO-L 9.5 (page 11) TASK IMPORTANCE: 2.8/2.9 TASK NUMBER: 072 K1.05 LEARNING OBJECTIVE: RMS-0101-1 TRAINEE ANSWER / COMMENTS: JPM RMS-0901-1-2 PAGE 8 OF 11
JPM 6UESTION #2
; RMS-0901-1-2 QUESTION: How does a Maine Yankee RMS Geiger Mueller detector respond when in an excessively high radiation ares?
l l ANSWER: A ' holding
- c!rcuit keeps the reading high, rather than failing low. l l
SATISFACTORY: YES NO
REFERENCES:
RO L g.5 (page 7) ; TASK IMPORTANCE: 3.4/3.6 TASK NUMBER: K/A 072-A1.01 LEARNING OBJECTIVE: RMS-0101-4 TRAINEE ANSWER / COMMENTS: JPM RMS-0901-1-2 PAGE 9 OF 11
__-__m.______._._______.__.__ . _ _ . _ _, 4 JPM EUEST10N #1 i i
- - RMS 090112
(: l QUESTION: Where are the main steam line radiation monitors physically located? 1 z 4 i l 4 q-1 4 i i ! I b 4 i i i-4
- 4. I i
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+ !
2 E i 4
. I s
1 1 ! j i 4 9 4 J i i i j ! 1 ! i a ? I' i 1 4 I a i ! JPM RMS-0901-12 PAGE 10 OF 11 d - i l'
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'JPM QUESTION #2 RMS 0901 12 QUESTION: How does a Maine Yankee RMS Geiger Mueller detector respond when in an excessively high radiation area?
JPM RMS-0901-12 PAGE 11 OF 11
7 JOB PERFORMANCE MEASURE---RO l JPM NUMBER: DG-0001 31 TASK NUMBER: KIA 064 A4.07 __ TITLE: PARALLELING DG 1A ONTO BUS 5 TIME CRITICAL: O YES 5NO START TIME: ALTERNATE PATH: O YES h NO STOP TIME: FERFORMANCE TRAINEE: PERFORMANCE RESULTS. O PASS O Fall OUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. _ All actions in the plant will be SIMULATED. The trainee and examiner are NQI authorized by
, this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contarrination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. A!I controlled references normally available may a used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will" role-play
- these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 5 minutes IMPORTANCE RATING: 3.4/3.4 REQUIRED TOOLS AND EQUIPMENT: 31-4.A, DG 1 A SURVEILLANCE TESTING PREPARED / REVISED BY: h DATE: APPROVED BY: [ DATE: t/./3/# REVISION #: 9 DATE: 3/18/97 JPM DG 09013-1 PAGE 1 OF 12
SAFETY CONSIDERATIONS: None EVOLUTION CONDITIONS: A problem is discovered with DG 18. To prove Technical Specification operability of DG 1 A, it will be paralleled onto the emergency bus. INITIATING CUES: The Secondary AO reports DG 1 A warmed up and at 950 rpm. You are directed to parallel it onto the emergency bus and adjust the KW and KVAR loading LAW surveillance procedure 3-14.A. EVOLUTION STANDARDS: The trainee will flash the field, adjust voltage and speed, synchronize the diesel to the bus and adjust KW and KVAR loading to required amounts.
REFERENCES:
3-1-4.A DG-1 A SURVEILLANCE TESTING PRR 92 041 PRR 92120 PRR 95-013 PRR 96-109 PRR 96 iB2 SIMULATOR:
- 1. Reset to power IC.
- 2. Start DG 1 A.
- 3. Bring in the trainee and conduct a tumover, JPM DG-09013-1 PAGE 2 OF 12 !
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: k
- 1. _
Obtain a copy of 3-14.A, DG 1 A SURVEILLANCE TESTING. Standard: Trainee is provided a copy of 31-4.A signed off up the procedural step required. O SATISFACTORY O UNSATISFACTORY COMMENTS: 2. I
' Flash the field.
Standard: Field flash pushbutton FF-DG1 A is depressed until a voltage of about 4 KV is indicated on VM DG 1 A. Voltage should stabilize at about 4160 VAC. Cue: This is an 'even" month. O SATISFACTORY O UNSATISFACTORY , COMMENTS: 4 JPM DG-0901-3-1 PAGE 3 OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: { 3.
- Turn on synchroscope.
Standard: Insert red handle into SYN DG1 A and place in ON. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
' Adjust engine speed for synchronization.
Standard: Diesel Generator speed adjusted using SPD DG1 A until the synchroscope is rotating slowly in the fast (clockwise) direction (<2 RPM). O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM DG-0901-3-1 PAGE 4 OF 12 4
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5.
- Adjust DG-1 A to match incoming and running voltages.
Standard: Diesel Generator output voltage adjusted using VR DG1 A to match running (VM-SSR) and incoming (VM SSI) voltmeters within i 1 volt. O SATISFACTORY O UNSATISFACTORY COMMENTS: 6.
' Parallel DG 1 A onto Bus 5.
Standard: Shut DG 1A output breaker ACB 5DG1A when the synchroscope has made at least one complete revolution AND reaches a position of about 2 minutes of 12. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM DG-0901-3-1 PAGE 5 OF 12
PERPORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: k 7.
' Load DG 1 A to 500 KW and O' KVARs.
Standard: Pick up 500 KW by placing SPD DG1 A to RAISE. Adjust KVARs to zero using VR DG1A (lower for KVARS IN, RAISE for KVARS OUT direction). O SATISFACTORY O UNSATISFACTORY COMMENTS: 8. Tum off synchroscope. Standard: SYN DG1 A to OFF position. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM DG-09013-L PAGE 6 OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 9.
- Increase load to surveillance load.
Standard: Trainee adjusts load as appropriate, as follows:
- 1) SPD DG1A to RAISE to increase KW,
- 2) VR DG1A to RAISE to increase KVARS in OUT direction (clockwise),
Monthlv Load Parameters 2400 to 2500 KW 0 to 100 KVARS out Cue: If asked, tell trainee to use monthly test. After standard is met, tell trainee JPM is complete. O SATISFACTORY O UNSATISFACTORY COMMENTS: s . JPM DG-0901-3-1 PAGE 7 OF 12
EVOLUTION CONDITIONS: A problem is discovered with DG 18. To prove Technical Specification operability of DG 1 A, it will be y paralleled onto the emergancy bus, 4 INITIATING CUES: The Secondary AO reports DG 1 A warmed up and at 950 rpm. You are directed to parallelit onto the emergency bus and adjust the KW and KVAR loading LAW surveillance procedure 3-14.A. JPM DG-090131 PAGE 8 OF 12
JPM QUESTION #1 4 DG 0901-31 QUESTION: What is the purpose of the 3T5 (4T6) normat/ emergency keylock switch on the electrical board (specifically, when would this switch be placed in emergency and why)? ANSWER: When in emergency it will open 3T5/4T6 when an SlAS signal is received. This prevents an overload of the diesel when it is paralleled to buses 3 and 4 during a loss of offsite power. SATISFACTORY: YES NO
REFERENCES:
RO-L-5.4 (page 52) TASK IMPORTANCE: 3.6/3.9 TASK NUMBER: K/A 064 K3.03 LEARNING OBJECTIVE: DG-0102 5 TRAINEE ANSWER / COMMENTS: n JPM DG-0901-3 1 PAGE 9 OF 12
JPM QUESTION #2 D.G-0901-3 1 i QUESTION: What is the purpose of the load limit knob on the diesel generator woodward govemor? What position must it always be in? (Show picture of govemor to candidate.) ANSWER: The load limit knob allows the diesel to accept load by allowing the fuel rack to open/close the quantity of fuelinjected into the cylinders dependent on EDG load. The load limit knob must always be in the
- Max Level" position when diesel is operable.
SATISFACTORY: YES NO
REFERENCES:
DG Tech Manual TASK IMPORTANCE: 3.1/3.2 TASK NUMBER: K/A 064 A2.05 LEARNING OBJECTIVE: DG-01015, AD-0102 8 TRAINEE ANSWER / COMMENTS: JPM DG-090131 PAGE 10 OF 12
l JPM QUESTION #1 t j DG 090131 QUESTION: What is the purpose of the 3T5 (4T6) normal / emergency keylock switch on the electrical board (specifically, when would this switch be placed in emergency and why)? JPM DG 090131 - PAGE 11 OF 12
JPM QUESTION #2 DG 090131 QUESTION: What is the purpcse of the load limit knob on the diesel generator woodward govemor? What position must it always be in? (Show picture of govemor to candidate.) W JPM DG 09013-1 PAGE 12 OF 12
t DIESEL GENERATOR GOVERNOR (EXTERNAL VIEW)
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CONTROL KNOB POWER CASE DRAIN COCK BASE m f .; DG 16 2/23/95 AO-L 5.3 REF: R1RBOCRARGED ENGINE MAINTENANCE MANUAL
i JOD PERFORMANCE MEASURE---RO f JPM NUMBER: New-9 TASK NUMBER: K!A 055 EA2.03 TITLE: PERFORM NG LOCAL ACTIONS FOR PRIMARY SIDE EQUIPMENT FOR SBO TIME CRITICAL: NYES O NO START TIME: ALTERNATE PATH: NYES O NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTION 5 TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are NQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside high these areas should be desciibed.
- 3. All controlled references normal.y available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play" these personnel.
EVALUAilOa LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 30 Minutes IMPORTANCE RATING: 3.9/4.7 REQUIRED TOOLS AND EQUlPMENT: AOP 2-48 PREPARED / REVISED uY: b DATE: APPROVED BY: [ DATE: 1.//3/4/ i < REVISION #: 0 DATE: 3/17/97 JPM New 9 PAGE 1 OF 13
SAFETY CONSIDERATIONS-None i EVOLUTION CONDITIONS: A loss of all AC power has occurred with DG 2 availab'e. AOP 2-48 is in progress. INITIATING CUES: You are the Primary AO. You have been directed to perform AOP 2 48, Attachment A, Local Operation and Verification of Primary Side Equipment for SBO. EVOLUTION STANDARDS:
. Trainee will perform AOP 2 48, Attachment A.
REFERENCES:
AOP 2-48, LOSS OF ALL AC DG-2 AVAILABLE/ STATION BLACKOUT. SIMULATOR: N/A l JPM New-9 PAGE 2 OF 13 m _ _ _ - _ - . _ - . _ _ .-
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 1. Obtain a copy of AOP 2-48, Attachment A, Local Operation and Venfication of Prirr.ary Side Equipment for SBO. Standard: Trainee is provided a copy of AOP 2-48 Attachment A when requested. NOTE: Record start time: . O SATISFACTORY O UNSATISFACTORY COMMENTS: 2.
- Ensure VP A 5 is shut.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-9 PAGE 3 OF 13
PERFORMANCE CHECKLIST l i STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
- Restart FN 25, steam and valve house exhaust fan. If not, block open following doors:
+ Door 2301, between Rx MCC Room and outside.
- Door 105, between Rx MCC Room and Steam and Val"e House.
- Door 2203, both double doors between CTMT hatch area and Steam and Valve House.
- Door 2201, both double doors between CTMT hatch area and outside.
Standard: All four doors blocked open within 30 minutes of JPM start. Cue: FN 25 will NOT start. NOTE: While security doors should NOT actually be blocked open for this JPM, the trainee should indicate specifically how he would block each door open. NOTE: Record time last door blocked open: I O SATISFACTORY O UNSATISFACTORY f-COMMENTS: 4.
'Open breaker for MS M 161.
Standard: As above.' At MCC 8B in Rx MCC Room. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-9 PAGE 4 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ( 5.
' Verify EFCV air compressors C 10A and/or C 10B running and pressurizing the EFCV air header.
Standard: As above. Cue: C 10A is running as necessary to keep the EFCV air header fully precsurized. O SATISFACTORY O UNSATISFACTORY COMMENTS: 6.
'Open MS-M-161 using manual operator.
Standard: Clutch lever depressed. Handwheel tumed in counterclockwise direction until valve is open. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-9 PAGE 5 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 7. Report to the SOS that MS-M 161 is open.
- Standard: As above.
O SATISFACTORY O UNSATISFACTORY COMMENTS: 8.
- Shut MS-M-255 using the manual operator.
Standard: Clutch lever depressed. Handwheel turned in clockwise direction until valve is closed. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-9 PAGE 6 OF 13
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: k 9.
- Ensure P 25B is operating normally by local verification. >
Standard: Dischstge pressure cleecked. Steam inlet pressure checked. Governor lube oil che:,ked. Lube oil temperature checked. Oil system operating properly. Cue: P 25B is operating normally. O SATISFACTORY O UNSATISFACTORY COMMENTS: 10.
- Ensure CS-M 91 and CS-M-92 are shut by localindication.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: i JPM New-9 PAGE 7 OF 13
PERFORMANCE CHECKLIST l STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i 11.
- Ensure VP A-1 is shut.
Standard: As above. Cue: Valve is shut when trainee describes location when at locked door. O SATISFACTORY O UNSATISFACTORY COMMENTS:
- 12. e Notify SOS that AOP 2-48 Attachment A actions have been completed.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: ) JPM New-9 PAGE 8 OF 13 l
EVOLUTION CONDITIONS: A loss of all AC power has occurred with DG-2 available. AOP 2-48 is in progress.
. f.
s INITIATING CUES: You are the Primary AO, You have been directed to perform AOP 2-48, Attachment A, Local Operation and Venfication of Primary Side dquipment for SBO. 3 s JPM New-9 PAGE 9 OF 13
JPM QUESTION #1 g New-9 QUESTION: You would like to change the direction of a throttleable MOV in mid-stroke. What happens to the MOV if you abruptly change direction and how can you recover from this condition? 4 ANSWER: The motor may trip on over torque when abruptly changing directions, if this occurs you can:
- 1. Take valve switch to original direction valve was moving, the torque switch should reset, EI
- 2. Wait for the Belleville and washer :pring pack to expand and reposition the worm to mid-position which will reset the torque switch, NOTE: Either number 1 or 2 for full credit, SATISFACTORY: YES NO
REFERENCES:
RO-L-4.1 (page 18) TASK IMPORTANCE: 4.2/4.5 TASK NUMBER: 068 AK 3.18 LEARNING OBJECTIVE: SNO-0101-4 TRAINEE ANSWER / COMMENTS: JPM New-9 PAGE 10 OF 13
JPM QUESTION #2 , NEW-9 1 QUESTION: What is the significance of FN-35A and/or B being inoperable? (EFW pump room ventilation) ANSWER: If an EFW pump's associated fan is inoperable ther.that EFW pump is also inoperable (F-ans are train separated FN-35A (MCC-7B/ Train B/P-25A) FN-358 (MCC-7ATTrain A/P-2FF These fans cool all components inside the EFW Pump Room). SATISFACTORY: YES NO
REFERENCES:
RO-L-3.13 TASK IMPORTANCE: 4.3/4.5 TASK NUMBER: 068 AA1,02 LEARNING OBJECTIVE: AFW-0101-22 TRAINEE ANSWER / COMMENTS: 2 JPM New-9 PAGE 11 OF 13
JPM QUESTION #1 New-9 4 QUEST!ON: You would like to change the direction of a throttleable MOV in mid stroke, What happens to the MOV if you abruptly change direction and how can you recover from this condition? (- 4 JPM New-9 PAGE 12 OF 13
l JPM QUESTION #2 NEW-9 l QUESTION: What is the significance of FN-35A and/or B being inoperable? (EFW pump room ventilation) JPM New-9 PAGE 13 OF 13
JOB PERFORMANCE MEASURE---RO 9 JPM NUMBER: EAS-0906-3-1 TASK NUMBER: R/A 068 AA1.14 TITLE: TRIPPING REACTOR TRIP BREAKERS AND MG OUTPUT BREAKERS LOCALLY TIME CRITICAL: 0 YES N NO START TIME: ALTERNATE PATH: O YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and oreration of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 7 Minutes IMPORTANCE RATING: 4.2/4.4 REQUIRED TOOLS AND EQUIPMENT:
- 1. AOP 2-44 PREPARED / REVISED BY: DATE: )!/3/ 7 APPROVED BY: [ DATE: t/[3!d)J g /'
REVISION #: 6 DATE: 3/17/97 JPM EAS-0906-3-1 PAGE 1 OF 10
SAFETY CONSIDERATIONS: Do NOT attempt actualimplementation of the RX Trip Breakers (RTBS) or CEDM breaker controls. k. EVOLUTION CONDITIONS: The plant was at steady state power when a chemical spill forced evacuation of the Control Room. The plant is not tripped. INITIATING CUES: You are the Secondary RO when you are forced to evacuate the Control Room because of a chemical spill, You are directed to report to the Protected Switchgear Room and trip the reactor per AOP 2-44. EVOLUTION STANDARDS: After receiving the initiating cue, the trainee will open the RTBs and CEDM MG output breakers.
REFERENCES:
AOP 2-44, CONTROL ROOM EVACUATION PRR 92-041 PRR 92-120 PRR 93-010 PRR 96-109 PRR 96-162 SIMULATOR:- N/A 4 o 4 he = JPM EAS-0906-3-1 PAGE 2 OF 10
PERFORMANCE CHECKLIST t STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. Obtain a OP 2-44, CONTROL ROOM EVACUATION, and equipment from emergency box. Standard: Trainee is provided a copy of AOP 2-44 when referenced. NOTE: The trainee may open the emergency box but no material may be removed. O SATISFACTORY O UNSATISFACTORY COMMENTS: 2.
*Open trip breakers TCB-1 through TCB-8.
Standard: Trainee simulates the ability to manually trip open the RTBs. I O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM EAS-0906-3-1 PAGE 3 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i I 3.
- Push and hold the " LOAD OFF" pushbutton for MG-1 A and MG-1B until the " LOAD ON" light goes out.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
*Open the " GEN OUTPUT BKR" for MG-1 A and MG-18.
Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM EAS-0906-3-1 PAGE 4 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 5. Announce over the FEMCO that the reactor is tripped. Standard: As above. , O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM EAS-0906-3-1 PAGE 5 OF 10
EVOLUTION CONDITIONS: The plant was at steady state power when a chemical spill forced evacuation of the Control Room. The k- - plant is not tripped. INITIATING CUES: You are the Secondary RO when you are forced to evacuate the Control Room because of a chemical spill. You are directed to report to the Protected Switchgear Room and trip the reactor per AOP 2 44. 6 JPM EAS-0906-3-1 PAGE 6 OF 10 I
JPM QUESTION #1 EAS-0906-31 i QUESTION: With respect to the Reed Switch position indication systern, what is the purpose of the shutdown insertion permissive interlock? ANSWER: Allows insertion of shutdown group rods when all regulating groups have been ir.serted to 2 steps. ( s SATISFACTORY: YES NO
REFERENCES:
RO-L-4.4 (page 32) TASK IMPORTANCE: 3.8/3.8 TASK NUMBER: KIA 001-K3.02
- LEARNING OBJECTIVE: CEDS 01019 TRAINEE ANSWER / COMMENTS:
JPM EAS-0906-3-1 PAGE 7 OF 10
JPM QUESTION #2 i
. EAS-0906-3-1 1
QUESTION: What is the purpose of the UV-1,2,3, & 4 bistables/ relays on the RPS breaker panelin the protected switchgear room? ANSWER: These bistables/ relays sense undervoltage on the CEDM buses and relay the signal to 20 AST and 20 ET to trip the main turbino. SATISFACTORY: .YES NO
REFERENCES:
ESK 9C and 9E TASK IMPORTANCE: 3.6/3.6 TASK NUMBER: K/A 012-A3.02 LEARNING OBJECTIVE: AC-0101-73 TRAINEE ANSWER / COMMENTS: 1 JPM EAS-0906-3-1 PAGE 8 OF 10
- JPM QUESTION #1 EAS-0906-3-1
-(.
- QUESTION: With respect to the Reed Switch position indication system, what is the purpose of the shutdown insertion permissive interlock?
l JPM EAS-0906-3-1 PAGE 9 OF 10 3- _ _ _ _ _ _ _ _ _ _ _ _ _ . - . _
JPM QUESTION #2 4 EAS-0906-3-1 QUESTION: What is the purpose of the UV 1,2,3, & 4 bistables/ relays on the RPS breaker panel in the protected switchgear room? JPM EAS-0906-3-1 PAGE 10 OF 10
JOB PERFORMANCE MEASURE---RO 10 JPM NUMBER: NEW-3 TASK NUMBER: K/A 069 AA1.01 TITLE: ISOLATING CONTAINMENT LOCALLY DURING LOSS OF ALL AC POWER TIME CRITICAL: O YES n NO START 'NE: ALTERNATE PATH: O YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are NQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be remo.'ed from their storage locations
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play" these personnel.
EVALUATION LOCATION: NPLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 Minutes IMPORTANCE RATING: 3.5/3.7 REQUIRED TOOLS AND EQUIPMENT: ECA-0.0 PREPARED / REVISED BY: V bh DATE: /J!h7 APPROVED BY: DATE: s/ 3/97 REVISION #:
/ 0 DATE: 3/17/97 9
JPM New-3 PAGE 1 OF 10
b SAFETY CONOIDERATIONS: None e EVOLUTION CONDITIONS: A loss of all AC power has occurred and ECA-0.0 is in progress. The ECCS lightbox indicates that three CIS valves are NOT in their safeguards positions. INITIATING CUES: You are the Primary AO You have been directed to locally close LM-A-45, C-A-15, and HPD-A-17 IAW ECA-0.0, Attachment L EVOLUTION STANDARDS: Trainee will close LM-A-45, C-A-15, and HPD-A-17 LAW ECA-0.0, Attachment L.
REFERENCES:
ECA-0.0, LOSS OF ALL AC POWER. SIMULATOR: N/A JPM New-3 PAGE 2 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1. Obtain a copy of ECA-0.0, Attachment L, Manual Actions for Containment isolation. i Standard: Trainee is provided a copy of ECA-0.0, Attachment L when requested. O SATISFACTORY O UNSATISFACTORY COMMENTS: 2.
"Close LM-A-45, containment pressure sensing header isolation valve.
Standard: Close IA-767 and bleed off the supply air regulator. Cue: Once air has been bled off, cue that LM-A-45 has closed. O SATISFACTORY O UNSATISFACTORY COMMENTS: l JPM New-3 PAGE 3 OF 10 l l
j PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 3.
*Close C-A 15 containment cardox supply header valve.
Standard: Close lA 1001 and bleed off the supply air regulator. Cue: Once air has been bled off, cue that C-A-15 has closed. O SATISFACTORY O UNSATISFACTORY COMMENTS:
- 4. __
*Crose HPD-A 17, main steam line header drains to condenser isolation valve.
Standard: Close IA-997 and bleed off the supply air regulator. Cue: Once air has been bled off, cue that HPD-A-17 has closed. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-3 PAGE 4 OF 10
~
l- < E
- PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
{ ,
.)
Notify the Control Room that the valves have been closed IAW ECA-0.0, Attachment L. Standard: As above. O SATISFACTORY- 0 UNSATISFACTORY COMMENTS: JPM New-3 PAGE 5 OF 10
- EVOLUTION CONDITIONG. A loss of all AC power has occurred and ECA-0.013 in progress. The ECCS lightbox indicates that three CIS valves are NOT in their safeguards positions, INITIATING CUES:
You are the Primary AOc You have been directed to locally close LM-A-45, C-A-15, and HPD-A-17 IAW ECA-0.0, Attachment L i JPM New-3 PAGE 6 OF 10
JPM QUESTION #1
- NEW-3 QUESTION
- D, ing a containment isolation caused by a LOCA, what indications could an Operator use to verify that the containment sump pumps are not discharging their contents outside the containment building?
ANSWER: (Any one (1) answer for credit)
- 1. Monitor the ADT levels to verify that isolation has taken place. (Levels could be monitored on the PAB panet.)
OR
- 2. Locally check PD-A-124 in lower level PAB (this valve is in a High Radiation Area, Letdown Area southwest comer).
OR
- 2. Verify PD-A-122 and/or PD-A-124 valve position on ECCS lightbox (SIAS/CIS section).
OR 3.' Verify PD-A-122 and/oc PD-A-124 valve position on ESF lightbox. SATISFACTORY: YES NO
REFERENCES:
RO-L-2.12 (page 18) TASK !MPORTANCE: 3.9/4.2 TASK NUMBER: K/A 103-A3.01 LEARNING OBJECTIVE: C-0101-12 TRAINEE ANSWER / COMMENTS: 4 JPM New-3 PAGE 7 OF 10
JPM QUESTION #21
, NEW-3 1
.: QUESTION: Where can you verify (other than locally) the position of LM-A 55,56,57 and 587 ANSWER:; in the Control Room on the rear of Section 'C' above the SIAS/CIS/ RAS /CSAS 86 Devices.
i SATISFACTORY: YES NO
REFERENCES:
Control Board TASK IMPORTANCE: 3.2/3.3 TASK NUMBER: K/A 103-A4.01 LEARNING OBJECTIVE: C-0101-5 l-TRAINEE ANSWER / COMMENTS: _. _ __ = JPM New-3 PAGE 8 OF 10 m_____ -.m___:__._.u___ _ _ _ . _
JPM QUESTION #1 5' - NEW-3 QUESTION: During a containment isolation caused by a LOCA, what indications could an Operator use to verify that the containment sump pumps are not discharc@y their contents outside the containment building? e JPM New-3 PAGE 9 OF 10
JPM QUESTION #2 NEW 3 QUESTION: Where can you verify (other than locally) the position of LM-A 55,56,57 and 58? o l JPM New-3 PAGE 10 OF 10
JOB PERFORMANCE MEASURE---RO ALTERNATE q JPM NUMBER: EAS-0901-2-9 TASK NUMBER: K/A 057 AA106 k TITLE: ESTABLISHING MINIMUM EFW FLOW DURING LOSS OF 120VAC VITAL BUSES 2 AND 4 TIME CRITICAL 0 YES 5 NO START TIME: ALTERNATE PATH: 0 YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall CUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are NQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will " role-play' these oersonnel.
EVALUATION LOCATION: O PLANT N SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 7.5 minutes IMPORTANCE RATING: 3.5/3.5 REQUIRED TOOLS AND EQUIPMENT:
- 1. E-0
- 2. AOP 2-14 PREPARED / REVISED BY:
- b DATE: / 7 APPROVED BY:
y DATE: t//3/47 r i REVISION #. 7 DATE. 3/17/97 ~ l JPM EAS-0901-2 9 PAGE 1 OF 10 l
SAFETY CONSIDERATIONS: None EVOLUTION CONDITIONS: The plant was at power when vital AC Buses 2 and 4 were lost. A trip and SIAS occurred. INITIATING CUES: You are the Secondary RO. You have been directed by the SOS to regain emergency feedwater flow to all SGs slowly over a 5-minute period to a minimum total flow of 490 gpm LAW AOP 214, Step 5.8.4. EVOLUTION STANDARDS: The trainee will establish Emergency Feedwater flow to the SGs with a minimum total flow of 490 gpm. The EFW flow controllers shall be placed at zero output prior to bypassing the Feed Train signal to prevent a waterhammer event.
REFERENCES:
E-0, EMERGENCY SHUTDOWN FROM POWER OR SAFETY INJECTION. ACP 2-14, LOSS OF VITAL AC PRR 92-041
- PRR 92-120 PRR 93-0t0 PRR 96-162 SIMULATOR:
- 1. Reset to a 100% power IC.
- 2. Fail Vital AC Bus 2 and 4. (Malfunction ED06B and ED06D),
- 3. Shut PORVs
- 4. Take initial operator actions, including acknowledging panalarms.
- 5. Freeze.
G. Bring in the trainee and conduct a tumover, t JPM EAS-0901-2-9 PAGE 2 OF 10
PERFORMANCE CHECKLIST - STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: I 1! Obtain a copy of AOP 2-14, LOSS OF VITAL AC BUS.. Standard: . Trainee is provided a copy of AOP 2-14 when referenced. O SATISFACTORY O UNSATISFACTORY COMMENTS: J
- 2. .
Ensure the feed train pumps are in PTL. Standard: Condensate (P-27A, B, C) Hester Drain (P-62A, B) and Feed pump (P-2A, B) sw;tches in PTL. 4 O SATISFACTORY O- UNSATISFACTORY COMMENTS: JPM EAS-0901-2-9 PAGE 3 OF 10
'I
PERFORMANCE CHECKLIST STEPS /STANDARDE FOR SUCCESSFUL PERFORMANCE: 1. 3.
- Ensure the EFW reg valve controllers are fully shut.
Standard: EFW flow controllers (EFW A 101,201,301) in MANLAL at zero output. NOTE: This step must be done before the next step is performed. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4.
- Bypass FW Reg Valve isolation Signal Block Train A/B signals.
Standard: Keys B 7 through B-12 inserted in keylock switches and turned to BYPASS. O SATISFACTORY O UNS ATISFAC TORY COMMENTS: 4 JPM EAS-0901-2-9 PAGE 4 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSF UL PERFORMANCE: i 5.
' Ensure an EFW pump is running.
Standard: P 25 A or C running, per MCB breaker status lights and pump amp indications. NOTE: This step may be performed in a different sequence. O SATISFACTORY O UNSATISFACTORY COMMENTS: a 6.
- Raise EFW flow slowly to at least 490 gpm.
Standard: EFW controtter outputs (EFW A-101,201,301) slowly increased on all three SGs to obtain a minimum of 490 gpm total. O SATISFACTORY O UNSATISFACTORY ( COMMENTS: JPM EAS-09012 9 PAGE 5 OF 10
EVOLUTION CONDITIONS: ij The plant was at power when vital AC Buses 2 and 4 were lost. A trip and SIAS occurred. i t i I INITIATING CUES: You are the Secondary RO. You have been directed by the SOS to regain emergency feedwater flow to i all SGs slowly over a 5 minute period to a minimum totcl flow of 4g0 gpm LAW AOP 214, Step 5.8.4. a 4
- i
? i 1 r : 1 i e 9 j f r 4 e i
,f 1
JPM EAS 09012 9 PAGE 6 OF 10
. . - . . , . - - . . ,.- . ~ . _ _ , .,, , . - - - . ~ , ~ _ . . . _ _ ,mm...,_ - . . , -, , - ~ , . - . .,. - . . - , - , , --,y.e-, , - _ . - < ,_.c, --.--e
JPM QUESTION #1 ( EAS-0901 2-9 QUESTION: What systems are affected when the SS EFW Block switch is placed in
- Block" on the rear cl the MCB (B Section)?
ANSWER: This switch blocks EFW auto start on low SG level, blowdown valve isolation on low SG level and diverse scram system trip on low SG level (all levels in SG @35%). SATISFACTORY: YES NO_
REFERENCES:
RO-L 3.13 (page 28) TASK IMPORTANCE: 4.5/4.6 TASK NUMBER: K/A 061 K4.02 LEARNING OBJECTIVE: AFW 0101 12 TRAINEE ANSWER / COMMENTS: JPM EAS-0901-2-9 PAGE 7 OF 10
JPM QUESTION #2 EAS-0901 2-9 QUESTION: What is the Main Turbine response to a trip of P 2C7 ANSWER: If P-2C trips and no MDFPs are running, the main turbine will trip. SATISFACTORY: YES NO
REFERENCES:
RO-L 3.7 (page 79) TASK IMPORTANCE: 3.0/3.3 TASK NUMBER: K/A 059 A2.07 LEARNING OBJECTIVE: MFW-0102-17 TRAINEE ANSWER / COMMENTS: JPM EAS-0901-2-9 PAGE 8 OF 10
JPM QUESTION #1 f EAS-09012 9 QUESTION:. What systems are affected when the SS EFW Block switch is placed in
- Block" on the rear of the MCB (B Section)?
g 9 JPM EAS-09012-9 PAGE 9 OF 10
1 JPM QUESTION #2 1
- t. EAS-0901-2-9 4
i f 4 l QUESTION: What is the Main Turbine response to a trip of P 2C7 i t i I a e il i r (. 1 i i s 1 f ,0 J I 3 F e t k i
- l
} 4 m d L 3 3 2 i
.I 1.
2 4 4 a 1-4 f E i a- ~ JPM EAS-0901-2 9 PAGE 10 OF 10
.. . . - . . . . . - . . - _ . . . . . , . . . , _ , . . , , , . . . _ . . , _ _ _ . . . , _ . _ _ _ _ - . . - . , _ , , , _ . , , . ~ . . _ . , , _ _ _ _ . . . . - . _ . _ . _ _ . _ _
JOB PERFORMANCE MEASURE---RO ALTERNATE it JPM NUMBER: New - 10 TASK NUMBER: K/A 009 EA1.04 i TITLE: AllGNING P-7 TO A HPSI TRAIN TIME CRITICAL: O YES 5 NO START TIME: ALTERNATE PATH: O YES M NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airborne contamination areas will r.ot be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self checking) will be examined during this evaluation.
S. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play" these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 20 minutes IMPORTANCE RATING: ? 7/3.5 REQUIRED TOOLS AND EQUIPMENT: AOP 2-48 PREPARED / REVISED BY: DATE: / f[ APPROVED BY: [ DATE: v/3/97 o - REVISION #: 0 DATE: 3/19/97 JPM New-10 PAGE 1 OF 12
SAFETY CONSIDERATIONS: None EVOLUTION CONDITIONS: A loss of all AC power has occurred with DG 2 available. AOP 2 48 is in progress. INITIATING CUES: You are the Primary AO You have been directed to perform AOP 2 48 Attachment B, Aux Charging to "B" Train. EVOLUTION STANDARDS: Trainee will align P 7 to the "B" HSPI header IAW AOP 2 48 Attachment B.
REFERENCES:
AOP 2-48, LOSS OF ALL AC DG 2 AVAILABLE/ STATION BLACKOUT. SIMULATOR: N/A JPM New-10 PAGE 2 OF 12 _ _____w,,--,-- ----- -
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: ! 1, Obtain a copy of AOP 2-48, Attachment B, Aux. Charging to HPSI *B" Train. Standard: Trainee is provided a copy of AOP 2 48, Attachment B when requested. Cue: When asked which HPSI header to align, evaluator will specify *B' header. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-10 PAGE 3 OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 2.
' Align the following valves:
Valyg Nomenclaturt Position , CH M 53 P 7 suction from RWST open l CH-M 55 P-7 suction from VCT shut ' CH 56 P 7 suction from VCT/RWST open CH-58 P 7 suction from BAMT shut i CH-60 P-7 suction from PWST shut CH 155 P-7 PCV isolation open
- ' CH 90 P-7 chem addition shut CH-63 P 7 discharge open t
CH 113 P 7 suction from BATPs shut LO-61 Inlet to P 7 alt. cooler open LO 60 Inlet to P-7 norm cooler shut ' FN61 P-8 alt. cooler fan start CH 57 PC 227 P-7 suction pressure switch isolation open LO-63 P 7 alt cooler vent open CH 65 P 7 disch to chg header shut CH 66 P 7 disch to fill header shut CPU 23 RWST suction to P-7 and P-8 locked open t Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-10 PAGE 4 OF 12
PERFORMANCE CHECKLIST STP.PS/ STANDARDS FOR SUCCESSFUL PERFORMANCE: i 3.
*1f aligning to HPSI Header B, then open the following:
yalyg Nomenclature HSI-49 P 7 disch to HPSI B header HSI M 11 HPSI B to Loop 1 HSI M 21 HPSI B to Loop 2 HSI M 31 HPSI B to Loop 3 Standerd: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 4.
*lncrease P-7 discharge safety valve CH-P 156 pressure to 2350 psig on PC-401.
Stativard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New 10 PAGE 5 OF 12
PERPORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 f 5. I
- Set speed control lever to high speed per posted instructions.
i Standard: As per posted instructions, 4 1 O SATISFACTORY O UNSATISFACTORY-COMMENTS: 4 i . + 6. I ll l Verify suction pressure greater than 5 psia on PC 227. l , i Standard: As above. f J l 0 SATISFACTORY O UNSATISFACTORY 4 COMMENTS: a i JPM New.10 PAGE 6 OF 12
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: i . 7. Notify SOS at the ASP that P 7 is ready for operation. Standard: As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: 8. Ensure P 7 operation is satisfactory. , Standard: Check (1) no abnormal noises, (2) oil level within normal band, and (3) pump discharge pressure less than PC-401 setting. Cue: Cue that conditions are as listed in the standard above. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New.10 PAGE 7 OF 12 1
- i. EVOLUTION CONDITIONS:
f) A loss of all AC power has occurred with DG 2 available. AOP 2 48 is in progress, l \- - INITIATING CUES: i You are the Primary AO. You have been directed to perform AOP 2 48 Attachment B, Aux Charging to
*B' Train.
i I i i 1-1 1 1 , I i. 5 7 1' i-1 J 1-
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i l l'
- ' 1 1
I i 1. I ! l t 1 1* i. I i i i ? i. i t i 4-i i
*~ JPM New-10 PAGE 8 OF 12
JPM QUESTION #1 NEW 10 QUESTION: What is the purpose of the P 7 normal / emergency switch on the PAB Emer0ency Panel? What is the relationship between local (PABEP), Altemate Shutdown Panel (ASP) and control room controlof P-77
. ANSWER:
The ASP Switch has ultimate control of P 7. If it is in normal P 7 it is controlled via the PABEP normal (control room)/ emergency (PABEP) switch. When the ASP switch is in altemate the ASP has control of P 7. s SATISFACTORY: YES NO
REFERENCES:
RO-L-2.5 (page 65), STM Chap 34 (page 33) TASK IMPORTANCE: 3.8/3.4 TASK NUMBER: K/A 004 A4.08 LEARNING OBJECTIVE: CVCS 0103 5 TRAINEE ANSWER / COMMENTS: JPM New-10 PAGE 9 OF 12
JPM QUESTION #2 g NEW-10 QUESTION: What is the flow path of vented gascs from the Charging Pump Suction during normal operation? During SIAS? ANSWER: From pump suction through vent piping / tanks in upper level PAB to the PDT during normal operation. During SlAS it is automatically isolated. 4 SATISFACTORY: YES NO
REFERENCES:
RO-L 2.5 (page 29) TASK IMPORTANCE: 2.8/3.1
, TASK NUMBER: K/A 004-AK0.15 LEARNING OBJECTIVE: CVCS-010214 TRAINEE ANSWER / COMMENTS: ,
JPM New 10 PAGE 10 OF 12
JPM QUESTION #1 NEW 10 ( QUESTION. What is the purpose of the P 7 normal / emergency switch on the PAB Emergency Panet? What is the relationship between local (PABEP), Altemate Shutdown Panel (ASP) and control room control of P 77 4 JPM New 10 PAGE 11 OF 12
JPM QUESTION #2 i NEW 10 !.( t i QUESTION: What is the now path of vented gases from the Charging Pump Suction during normal operation? During SlAS? i i 1 i ? 1 i s 1 3 i l a , i 2 1 : i i ) 4 'l a i 7 1 i k i j'~ l d 1 5 b i 4 i T t JPM New-10 PAGE 12 OF 12
ES 301 Administrative Topics Outline Form ES 3011 Facihty: unine Yankee Date of Examination: June 9-12.1997 l Exam Level (Circle)h/SRO (1) / SRO (U) Operating Test No.: 1
- A.1 Conduct of AD-0104 ',
K/A Generic 2.1.33 (3 4/4.0) , Operations Are you allowed to change plant conditions (condition 5 to 6) if you are in a l Remedial Action Statement? Where do you venfy this? K/A Generic 2.1.3 (3.0/3 4) AD-0101 1 Oncoming control room operator tumover ) ] i Security Generic 2.1.2 (3.0/4.0) J JPM New 28 -Performing control room actions for ,ecurity Code Red (N)(T)(C). l A2 Equipment Generic 2.2.13 (3.6) '
- Control JPM New 32 Validating White Tag out adequately (N)(C) l A.3 Radiation Generic 2.3.5 (2.3/2.5) AD-010313 i Control JPM . New 31. Perform a hand and foot frisk. (N)(P)(R) l A.4 - Emergency K/A Generic 2.4.39 (3.3/3.1) AD-010211
- Plan You are on your spare week when an " Alert" condition is declared. Where do you j report to during this classification?
K/A Generic 2.4.17 (3.1/3.8) . AD-010210
- What is the definition of an Unusual Event?
4 Put necessary abbreviations here: I 5x mination Standards Rev. 8, PUBLIC f l NOTE i i- A.3-Justification for K/A less than 2.5 for RO- We frisk as we leave the RCA buildings to outside of the buildings e in order to prevent spreading contamination to the ground, This !' makes frisking at Maine Yankee an environmental as well as a
- personnel conta nination issue. The SRO importance factor is 2.5 for this K/A. The CRO at Maine Yankee certainly should have the j same importance factor as the SRO on this task.
i i i i i
i RO ADWilNISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #1 Question: i' 7 Are you allowed to change plant conditions (e.g., from condition 5 to 6)I 4you are / in a Remedial Action statement? Where do you verify this? - Answer: No. (Entry into a higher 'oerating condition shall not be made whenever the following exists:
- 1. The provisions of Tech Spec 3.0.A.2 or 3.0.A.3 apply.
- 2. Any of the followire I.CO's is not met fo, the existing or higher condition without reliance upon the provisions contained in the Remedial Action statements 3.5.C; 3.6.A; 3.6.B,3.9.A 3.14.C)
This is verified in Technical Specification 3.0.B. (Information in parentheset is for information only. Not required for credit). SATISFACTORY: YES NO
REFERENCES:
Tech Spec 3.0.8 TASK IMPORTANCE: 3.4/4.0 TASK NUMBER: K/A Generic 2.1.33 LEARNING OBJECTIVE: AD-0104-7 TRAINEE ANSWER / COMMENTS s
g ,- - . RO ADMidlSTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #1 Question: Are you allowed to change plant conditions (e.g., from condition 5 to 6). If you are in a Remedial Action statement? Where do you venfy this? x [ i
RO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS QUESTION #2 Ouestion: Prior to assuming the watch, what shift tumover duties must the on-coming CRO perform? Answer: On-Comino Control Room Ooerator Tumover: A. Prior to assuming the watch, the on-comireg CRO shall perform the following:
- Review and initial any new entries in the Crew Document Review book, ' Prior to Shift" section, e Review the Operations Turnover with the off-going CRO.
- Review current Night Orders.
- Perform a w&lkdown of the MCB and discuss with the off going CRO's reasons for any annunciator alarms, abnormal system lineups, status of safety related systems, and equipment out-of.
service. e Review any non-routine points on trend and the reasons why these points are on trend.
- Review latest INCA and Symmetric Offset plot.
e Review Control Room Logs I and II, e Review procedures in progress with which the CP.O's may be involved including initial conditions and precautions, B. Attachment A, Operatiuns Shift Turnover Checklist, shall be reviewed and signed by the on-coming CRO's. t SATISFACTORY: YES NO
REFERENCES:
OP 126-3 (step 3.3.2) TASK IMPORTANCE: 3.0/3.4 TASK NUMBER: K/A Generic 2.1.3 LEARNING OBJECTIVE: AD-0101-1 TRAINEE ANSWER / COMMENTS l 1
RO ADMINISTRATIVE TOPICS CONDUCT OF OPERATIONS 1 QUESTION #2 l Question: Prior to assuming the watch, what shift turnover duties must the on coming CRO perform? i 9
JOli PERFORMANCE MEASURE---RO ADMIN JPM NUMBF.R: New-28 TASK NUMBER: K!A Generic 21.2 I TITLE: PERFORMING CONTROL ROOM ACTIONS FOR SECURITY CODE RED TIME CRITICAL: NYES O NO START TIME: ALTERNATE PATH: O YES N NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are MQ1 authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered. j Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-cheching) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-plc/" these personnel.
EVALUATION LOCATION: O PLANT h SIMULATOR h CONTROL ROOM APPROXIMATE COMPLETION TIME: 15 minutes IMPORTANCE RATING: 3.0/4.0 REQUIRED TOOLS AND EQUIPMENT:
- 1. AOP 2 51
- 2. OP 1 12-6
/
PREPARED / REVISED BY: DATE: [/d/f7 APPROVED BY: DATE: V/3/9/ REVISION #: r 0 DATE: 3/26/97 JPM New-28 PAGE 1 OF 10
l SAFETY CONSIDERATIONS: None i EVOLUTION CONDITIONS: Security has just announced, " Security Code Red' over the FEMCO. INITIATING CUES: You are the Primary RO. The SOS has implemented AOP 2 51, RESPONSE TO SECURITY EVENTS, and has directed you to perform Attachment A. EVOLUTION STANDARDS: Trainee performs Control Room response actions per AOP 2 51, Attachment A.
REFERENCES:
AOP 2 51, RESPONSE TO SECURITY EVENTS OP 1 12-6, CONTROL ROOM VENTILATION SIMULATOR:
- 1. Initialize to a full power IC.
- 2. Freeze simulator and tumover to trainee.
JPM New-28 PAGE 2 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 1. ,_
- Shut both Control Room sliding doors.
Standard: Within 45 seconds of start time, perform the following:
- 1. Direct CAS officer to shut front door.
- 2. Shut rear door and report closure to CAS.
Cue: CAS officer reports that front sliding door is shut. NOTE: Record all times to nearest second. Once trainee has AOP 2 51 in hand, then record the following times:
- 1. Start time (time trainee has procedure in hand):
- 2. Time both sliding doors shut:
O SATISFACTORY C UNSATISFACTORY COMMENTS: s 2.
'Announce over FEMCC; " Security Code Red, Operators take defensive positions."
Standard: Within 60 seconds of start time, make above announcement. NOTE: Record time announcement made: C SATISFACTORY C UNSATISFACTORY COMMENTS: l JPM New-28 PAGE 3 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCFSSFUL PERFORMANCE: 3. , i
- Monitor the Security frequency on the Control Room radio console.
Standard: Within 60 seconds of start time, initiate monitoring of the Secunty Channel. While no action may be required to do so by STAR, the trainee should ensure the , volume control is adjusted high enough to allow mon;toring, as follows: ,
- 1. If Security Channel NOT selected, then ensure the UNSELECTED volume control 10 tumed up sufficiently to monitor communications on the right speaker.
- 2. If Security Channe! SELECTED, then ensure the SELECTED volume control is tumed up sufficiently to monitor communications on the left i
speaker. NOTE: Record time volume control is verified to be turned up sufficiently to ensure monitoring:
- O SATISFACTORY C UNSATISFACTORY i COMMENTS
i i 4 i i f 4 4 JPM New 26 PAGE 4 OF 10 j mc .- , - , _ - , . - w , -,- -..v.- , - - -. . y v,e- -- _ __m
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PERFORMANCE CHECKLIST b STEP 6*T:34DARDS FOR SUCCESSFUL PERFORMANCE: s c.
< i 4.
Station a licensed operator in CAS to assist Security. Standard: Within 90 seconds, station a licensed operator in CAS or request that the SOS or PSS ensure this is done. (Most likely, the Secondtry RO will be assigned to perform this function unless an extra licensed operatorjust happens to be in the Control Room.) NOTE: Record time that licensed operator is stationed in CAS: O SATISFACTORY O UNSATISFACTORY COMMENTS: _ - .:.x
- 5. , ,, ,
- Request the PSS or SOS to contatt ;he .3ecunty Lieutenant / Sergeant in SAS directly and cor. firm that (i) the code RED is valid, (2) the intruder is in the protected area, and (3) the r security event is not a dill.
Standard: As above. Cue: PSS or SOS has contacted SAS directly and confirmed all of the above. O SATISFACTORY O UNSATISFACTORY COMMENTS:
= - JPM New-28 PAGE 5 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 1 6.
*lsolate the Control Room by shutting MOV-6014,6013,6010, and 6017.
Standard. As above. O SATISFACTORY O UNSATISFACTORY COMMENTS: amuu
- 7. __
- Trip the plant and enter E-0, EMERGENCY SHUTDOWN FROM POWER OR SAFETY INJECTION.
Standard: Trainee trips the reactor manually. Cue: Secondary RO has been directed to perform E 0 immediate actions. SOS directs you to continue with AOP 2-51 Attachment A. , O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-28 PAGE 6 OF 10 l .
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR' SUCCESSFUL PERFORMANCE: 8.
*Take manual control of feedwater and increase SG levels to approximately 66% narrow range as quickly as possible.
Standard: Trainee raises SG levels to 66% NR quickly using MFW bypass valves or EFW FCVs, s necessary.- , i O SATISFACTORY O UNSATISFACTORY
. COMMENTS:
1. i
*When all SG levels are stable at approximately 66%, then stop all RCP's.
Standard: - All RCPs are stopped. O SATISFACTORY O UNSATISFACTORY COMMENTS: t JPM New-28 PAGE 7 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- 10.
Verify natural circulation. Standard: Check the following:
- 1. Core region subcooling greater than 21'F.
- 2. SG pressures stable or decreasing.
- 3. WR T-hots stable or decreasing.
- 4. Core region temperatures stable or decreasing.
- 5. WR T-colds at saturation temperature for intact SG pressures (using MPT curve or steam tables).
Cue: After trainee checks these indications, then report that the Secondary RO vill monitor these indications. NOTE: These items are listed in several EOP attachments, such as ES-0.1 Attachment E. O SAT!SFACTORY O UNSATISFACTORY j COMMENTS: JPM New-28 PAGE 8 OF 10
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
- Initiate breathing air supply LAW 1-12-6, Control Room Ventilation.
Standard: Perform the following to isolate Control Room operations at Reactor Operating Conditions 4, 5, 6, or 7:
- 1. Dispatch an AO to ensure FN-15, Control Room exhaust fan is off. (See Cue.)
- 2. Ensure MOV-6017,6010,6013, and 6014 are shut. (Done in JPM step 6.)
- 3. Align both trains of Control Room ventilation as folio e-Train A TraitLEl FN-7A running FN-7B running D-6A and D-7A open D-6B and D 78 open FN-11 A running FN-118 running D-4 and D-5 shut D-4 and D-5 shut
- 4. Verify breathing air supply is between 40 and 60 SCFM for tagh train.
Cue: a. It is not yet safe for operator movement (for stopping FN-15).
- b. After OP 1-12-6 ventilation lineup has been completed, then cue that JPM is complete.
- c. Breathing air supply flow rate is 55 SCFM on each train.
O SATISFACTORY O UNSATISFACTORY COMMENTS: 6 JPM New-28 PAGE 9 OF 10
EVOLUTION CONDITIONS: Security has just announced, " Security Code Red" over the FEMCO, 1NITIATING CUES: You are the Primary RO. The SOS has implemented AOP 2 51, RESPONSE TO SECURITY EVENTS, and has directed you to perform Attachment A. 4 i JPM New-28 PAGE 10 OF 10
l JOB PERFORMANCE MEASURE---RO ADMIN JPM NUMBER: New-32 TASK NUMBER: K/A 2 213 TITLE: VAllDATING WHITE TAG OUT ADEQUACY TIME CRITICAL: O YES M NO START TIME: ALTERNATE PATH: O YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE: DIRECTIONS TO TRAINEE:
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are NRI authorized by this document to actually perform any action in the plant.
- 2. High radiation, surface contamination and high airbome contamination areas will not be entered.
Location and operation of equipment inside these areas should be described.
- 3. All controlled references normally available may be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
- 4. The application of all safety rules, general work practices, and STAR (self-checking) will be examined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play" these personnel.
EVALUATION LOCATION: O PLANT N SIMULATOR N CONTROL ROOM APPROX! MATE COMPLETION TIME: 20 Minutes IMPORTANCE RATING: 3.6/3.8 REQUIRED TOOLS AND EQUIPMENT: Procedure 0-14-1, Attachment A, B, and M PREPARED / REVISED BY: DATE: h APPROVED BY: [ DATE: L//3/9) REVISION #: r 0 DATE: 3/19/97 JPM.New -32 PAGE 1 OF 5
SAFETY CONSIDERATIONS: None 1 EVOLUTION CONDITIONS: The plant is operating at 90% power. INITIATING CUES: The SOS has just prepared a tagging order for E SA per the tagout request form (Attachment M of procedure 0-14-1). The SOS has asked you to validate the adequacy of this tagout. EVOLUTION STANDARDS: When given a safety class tagging order, the trainee will demonstrate the ability to verify the adequacy of that tagging order.
REFERENCES:
QA Procedure 0-14-1
. FM-70A SIMULATOR:
N/A NO!? The Esaluator should provide a completed Attachment A & B of Procedure 0-14-1, White Tag Order Sheet, for E SA. The Evaluator shall also provide a Tagging Order Request (Attachment M of 0-14-1) for E-SA. The tagout of the JPM is attached. I l JPM New -32 PAGE 2 OF 5
PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE: 4 1. Trainee obtains tagging order
- Standard: Student is handed previously prepared Tagging Order Sheet (procedure 0-14-1),
Attachment A & B) and tagging Request Form (procedure 0-14-1, Attachment M). NOTE: At this time, the trainee should ask all questions and clarify the tagging request, if needed. O SATISFACTORY O UNSATISFACTORY COMMENTS: e
- Validates adequacy of tagging order.
Standard: Using FM's, trainee demonstrates boundaries necessary to isolate E 5A. O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New -32 PAGE 3 OF S
f PERFORMANCE CHECKLIST
. STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
1 3.
' Signs "Tagout Adequacy Validated By"line on Tagging Order Form (Attachment A of procedure 0-14-1).
Standard: Trainee signs tagging order form after satisfying himself that the tagging order is adequate. NOTE: If the trainee feels that more tags are required, the trainee should state what tags should be added. If extra tags are added and do not effect the operability of the other service water heat exchangers (SWHX), the step is considered completed satisfactorily. If the trainee adds tags which effect the other SWHXs or deletes tags, the step is completed unsatisfactority. O SATISFACTORY O UNSATISFACTORY COMMENTS: E JPM New -32 PAGE 4 OF 5
. EVOLUTION CONDITIONS:
The plant is operating at 90% power,
- INITIATING CUES: ;
The SOS has just prepared a tagging order for E-5A per the tagout request form (Attachment M of procedure 014-1). The SOS has asked you to validate the adequacy of this tagout. il l 5 1 l 1 JPM New -32 PAGE 5 OF 5 1
3 MAINE YANKEE TAGGING ORDER No. Page of MAINE YANKEE TAGGING ORDER Prepared By: Tags Checked and Equipment Date / / Vertfled De-energized / Step 6.3.3: Issued By: Date / / Tagging Order Cleared: Tagged for ~M4FSh4// PSS/505 Verify All Holds and Grounds WO/ PROC / ADMIN CONTROL N- 9998 Removed: Tag Out g Validated.By: COMPONENT TM;f;FD AM) pr_ASON-Second Knowledgeable Authorized Person (N/A) Safety Class (1. 2. 3 vr IE) Yes / No If Yes Independent verification is required and complete following: R. DUTY PSS SIGNATURE N NOTES: g
- 1. Permission to release equipment
- 2. Equipment returned to service or ]
functional test pendino _ _ . - p G ATTAuffNTS YES 11016 Sheet { Panalares Disabled: Ground Tags '-' Change forms o INDIV. INDIV. U VERIF. POSITION VERIF. INSTN"FD INSTALLED INDIV. INDIV. FOR TAG REMOVED REMOVED TAG VALVE. BREAKER POSlif0N BY BY DATE TAG TAG REM) VAL BY BY DATE NO. SWITCil OR SLIDE (PSS/505) OPER 1 OPER 2 INSTALLED DIECKE oo-to ,o
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Proc. No. 0-14 1 Rev. No. 18 Page 68 of 74 ATTADMENT H (Sheet 1 of 1) I TAGOUT REQUEST FORM To: Plant Shift Superintendent / Shift Operating Supervisor: It is requested that the following equipment be tagged out de-energized, driiined and depressurized as necessary to perform the maintenance described be ow. EQUIPMENT: DATE & TIME WORK WILL BEGIN: WOIP: SAFETY CLASS: WORK TO BE PERFORMED: SPECIAL TAGGING INSTRUCTIONS OR SYSTEM LINEUPS: TAG TO: RESP. SECTION: SIGNATURE: REVIEWED BY: Person Requesting Tags Operations DATE:
JOB PERFORMANCE MEASURE---RO ADMIN JPM NUMBER: New-31 TASK NUMBER: K/A 2.3 5 i TITLE: PERFORMING A HAND AND FOOT FRISK TIME CRITICAL: 0 YES h MO START TIME: ALTERNATE PATH: 0 YES 5 NO STOP TIME: PERFORMANCE TRAINEE: PERFORMANCE RESULTS: O PASS O Fall QUESTION RESULTS: Out of Correct EVALUATOR SIGNATURE: DATE:
- DIRECTIONS TO TRAINEE
- 1. All actions in the plant will be SIMULATED. The trainee and examiner are HQI authorized by this document to actually perform any action in the plant.
- 2. High rad ation, surface contamination and high airborne contamination areas will not be entered.
l Location and operation of equipment insidu 'hese areas should be described.
- 3. All controlled references normally available .iay be used. Control Room procedures and emergency station procedures should not be removed from their storage locations.
i 4. The application of all safety rules, general work practices, and STAR (self-checking) will be
- exat.1ined during this evaluation.
- 5. All communications with other plant personnel (Control Room, AOs, etc.) should be directed to the evaluator, who will
- role-play" these personnel.
EVALUATION LOCATION: N PLANT O SIMULATOR O CONTROL ROOM APPROXIMATE COMPLETION TIME: 10 Minutes l IMPORTANCE RATING: 2.3/2.5 REQUIRED TOOLS AND EQUIPMENT: Frisker l PREPARED / REVISED BY: DATE: f7 APPROVED BY: DATE: y e/./3./97 REVISION #: 0 DATE: 3/18/97 JPM New-31 PAGE 1 OF 6
SAFETY CONSIDERATIONS: None k EVOLUTION CONDITIONS: The plant is operating at 90% power. INITIATING CUES: You are the Spare CRO and you have been asked to check that the EFW digital controllstrons are indicating zero (0) Sow. EVOLUTION STANDARDS: A band and foot frisk must be performed prior to exiting the RCS to outside. The toinee will demonstrate the proper method of performing a hand and foot frisk in accordance with rdiological procedures.
REFERENCES:
Procedure 9-3-100, RADIATION PROTECTION SURVEILLANCE. Posted instructions at the frisking station. GET Lesson Plan GT-GET-08 i VULATOR: N/A s I 1' JPM New-31 PAGE 2 OF 6
PERPORMANCE CHECKLIST STEPS /STANOARDS FOR SUCCESSFUL PERFORMANCE: I 1. Checks background count rate of frisker. Standard: Observes count rate on friskor and ensures countrate is less than 300 cpm. NOTE: Friskor background should be less than 300 opm. If not, studerst should pe* form a cursory frisk to ensure that gross amounts of contamination are not present and proceed to the closest availabic wisker with the proper background levels. O SATISFACTORY O UNSATISFACTORY COMMENTS: i
- 2- ,
- Ensure instrument is operating with audible response and on the "x1" scale, Standard: Instrument scale is selected to the "x1" scale and audible response is present. '
O SATISFACTORY O UNSATISFACTORY COMMENTS: JPM New-31 PAGE 3 OF 6
PERFORMANCE CHECKLIST
, 9TEPS/ STANDARDS FOR SUCCESSFUL. PERFORMANCE:
N 3. i- Ensures frisker source check date is within applicable dates. Standard: Checks that the frisker has been source checked today. O SATISFACTORY O UNSATISFACTORY COMMENTS: 4 i 7
- Frisks the hand that is to be used to handle the probe.
Standard: Moves palm then the back of the hand across the instrument probe at a rate of 1" to 2" per second at a distance of % to % inches from the hand's surface.
. Cue: .
O SATISFACTORY O UNSATISFACTORY COMMENTS: s' l JPM New-31 PAGE 4 OF 6
. PERFORMANCE CHECKLIST STEPS / STANDARDS FOR SUCCESSFUL PERFORMANCE:
I 4 5, f
- Frisks hands and feet.
Standard: Using the hand that was determined to be free of contamination, student frisks hands, tops, sides, and bottoms of feet at a rate of 1 to 2 inches per second at a distance of % to % inch 's from the surface. O SATISFACTORY O UNSATISFACTORY ' COMMENTS: JPM New-31 PAGE 5 OF 6 !
- EVOLUTION CONDITIONS:
The plant is operating at 90% power, I INITIATING CUES:
- You are the Spare CRO and you have been asked to check that the EFW digital controllatrons are indicating zero (0) flow, JPM New-31 PAGE 6 OF 6
RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #1 Question: You are the spare RO when an " ALERT" condition is declared per the Emergency Plan. Where do you report to during this classification? Answer: The spare RO will report to the Operations Support Center on the bottom floor of the Staff Building. SATISFACTORY: YES NO
REFERENCES:
E-Plan Section 5, Fig 5.14 TASK IMPORTANCE: 3.3/3.1 TASK NUMBER: K/A Generic 2.4.39 LEARNING OBJECTIVE: AD-0102-11 TRAINEE ANSWER / COMMENTS i
-{
RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #1 Question: - You are the spare RO when an "Al FRT" condition is declared per the Emergency Plan. Where do you report to during this classification?- . 4
i RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #2 Question: What is the definition of an Unusual Event? Answer: Potential degradation of the level of safety of the plant. s SATISFACTORY: YES NO i
REFERENCES:
Procedure 2-50-0 TASK IMPORTANCE: 3.1/3.8 TASK NUMBER: K/A Generic 2.4.17 LEARNING OBJECTIVE: AD-0102-10 TRAINEE ANSWER / COMMENTS
( RO ADMINISTRATIVE TOPICS EMERGENCY PLAN QUESTION #2 Question: ht is the definition of an Unusual Event? e b}}