IR 05000446/1992002
| ML20126D642 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/18/1992 |
| From: | Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20126D630 | List: |
| References | |
| 50-445-OL-92-02, 50-445-OL-92-2, 50-446-OL-92-02, 50-446-OL-92-2, NUDOCS 9212280080 | |
| Download: ML20126D642 (58) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Examination Report:
50-445/0L 92-02 50-446/0L 92-02 Operating License:
NPF-87 Construction Permit:
CPPR-127 Licensee:
Tu Electric Skyway Tower 400 North Olive, L.B. 81 Dallas, Texas 75201 Examinations at:
Comanche Peak Steam Electric Station Examinations Conducted:
September 30 and December 2,1992 Chief Examiner:
Ryan E. Lantz, Examiner, Operations Section Division of Reactor Safety Approved by:
NymtdO)@UmL ljll8kl
{ _ j/J. L. Peylet, Chief, Operations Section D' ate Division of Reactor Safety
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Summaty NRC Administered Examinations Conducted September 30 and December 2. 1992 (Examination Report 50-445/0L 92-02: 50-446/0L 92-02)
NRC administered unit differences examinations to 19 reactor operators and 28 senior reactor operators. NRC also administered simulator only retake requalification examinations to one reactor operator and one senior reactor operator. All operators passed all parts of the examinations.
9212280080 921218 PDR ADOCK 05000445 V
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-2-DETAllS
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PERSONS EXAMINED SR0 R0 Total Unit Differences Examinations:
Pass -
19
Fail -
0
Requalification Examinations:
Pass -
1
Fail -
0
2.
EXAMINERS R. E. Lantz, Chief Examiner S. L. McCrory 3.
EXAMINATION REPORT Performance results for individual operators are not included in this
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report as _it will be alaced in the NRC Public Document Room and these results-are not subject to pualic disclosure.
3.1 Examination Material The licensee submitted material for examination construction as required by NUREG-1021, " Operator Licensing Examiner Standards," Sections 201 and 601, for-the unit differences written exambations and the requalification dynamic simulator examinations, respectively.
The material was found to-be acceptable-with some minor deficiencies noted.
3.1.1 Unit Differences Written Examination The unit differences examination bank and lesson plans submitted by the-facility were sufficient for development-of the written examination.
Several examination bank questions had low cognitive value, but this was evaluated as acceptable, given the limited scope of the examination.
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The facility conducted a pre-and cost-examination review.
The resultant comments.were accepted and incorporated into the examinations and answer-keys, with the exception of one post-examination review comment on the September 30'
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The comment recommended accepting two answers as correct'to a-examination.
L question tnat required the examinee to recall the normal position of XCW-0323, L
a Unit 2 component cooling water valve that could potentially cross connect.
Unit I with Unit 2.
The facility contended that not all of the operators had returned to shift since the normal position of XCW-0323 had changed from locked closed to closed (2 months prior)_and had therefore not received-
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I-3-adequate training.
The facility further noted that the locked valve list still required XCW-0323 to be locked closed, although the system operating procedure and system drawings showed it to be only a closed valve.
The NRC rejected the comment and stated that the identified anomaly between the governing procedures did not alleviate the operator from knowledge of the correct and current information.
The comment is attached as an enclosure to this report.
3.1.2 Requalification Dynamic Simulator Scenarios The simulator scenario examination bank submitted by the facility was sufficient for developing the dynamic simulator examinations, and no generic weaknesses weri --ted.
3.2 EXAMINATION ADMINISTRATION 3.2.1 Unit Differences Written Examinations Unit Differences written examinations were administered in accordance with NUREG-1021, " Operator Licensing Examiner Standards," Section 402 (ES-402), to 47 licensed operators.
All operators passed the written examinations, with an average score for all examinations of 93 percent.
3.2.2 Requalification Dynamic Simulator Examinations Dynamic simulator examinations were administered in accordance with NUREG-1021, " Operator Licensing Examiner Standards," Section 604 (ES-604) and 605 (ES-605), to one crew, partially composed of the two operators being reexamined.
Both operators passed the examinations.
Emergency action level identification, event classification, and initial eme.gency plan implementation was accurate and timely.
No weaknesses were noted during the dynamic simulator examinations.
3.3 EXIT MEETING No exit meeting was held for these examinations.
3.4 SIMULATION FACillTY REPORT The simulation facility operated with no adverse conditions or infidelities noted, as indicated on the attached report.
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l SIMULATION FAClllTY REPORT Licensee: TV Electric Dockets:
50-445; 50-446 Operating Tests Administered at: Comanche Peak Steam Electric Station Operating Tests Administered:
December 2, 1992
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This report does not constitute an audit or inspection and is not, without-further verification and review, indicative of non-compliance with 10 CFR Part 55.45(b).
These observations do not affect.NRC certification or a) proval of the simulation facility other than to provide information which may 3e used in future evaluations.
No licensee action-is required in response to these
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observations.
During the conduct of the operating examinations identified above, the following items were observed:
o None
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t Comancho Peak SRO Unit Differences Exam 9/30/92 Post Exam Review Comment Question: 004 System drawings M10210 and M2 0210 show XCW 0323, U2 CW BSTR PMP SPLY, to be a closed valvo only.
SOP 310A, Circulating Water System valve lineup sheet, page 62 of 90, shows 'XCW 0323, U2 U2 CW BSTR PMP SPLY, to be normally closed.
- may be opened if supplying the Unit 2 Cire Water Boostor Pumps.
owl-103, Operations Locked Component List, page 9 of 65, shows "1CW-0323, U2 CW BSTR PMP SPLY, to be a locked closed valvo.
Recommendation: Accept answer b. or c. as correct 2.? : : L O To Ji'J :
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" 1CW 0323 and XCW 0323 are the same valvo
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QPERAT20NS LOCMED CoaPONENT L7ST
[AEQUl k #
POSITIONED l-IDCKED AND IDCRED VERIFIED 2ALVE NO. NOMENCIATURE
'POSITIOff w CRITERION 1 NIT /DATE INIT/DATE
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Air supply valves to air operated components require only a locked va
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tag to administrative 1y control their position, No lock is required.
This, applies to all valves with an AS extension only.
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4.9 2 HV.2931. AS, EJECTOR WATER SUPPLY AS CLOSED
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Tt'RB BLDC 7 7 8 '
TPCV HX TO CEV PtHP AREA i
4.10 1CV 0006, U1/2 XTIE ISOL CLOSED
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4.11 2.HV4H181, OUTPALL 101 CAGCED TO UNIT m2 SYSTEM VLV CLOSED
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4.12 2.HV.VH181 AS, OUTPALL 101 TO UNIT 2 SYSTEM VALVE AS CLOSED
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T4"'13 MICv;0323'.,'.3.U2. ' CV B5TR. *I pgp $pty
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5.0 TURBINE PIANT COOLING UATf!R UNIT 2 5.1 2TW.0178. TW U1 SPLY HDR ISOL CLOSED
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5.2 2W.0179, W U1 RET HDR ISOL CLOSED
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5.3 2W 0311, CA COMPR 2 01 U1 SPLY CLOSED
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5.4 2 W.0312 CA COMPR 2 01 U1 RET CLOSED
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TURBINE BLDG 778' BY TPCV RX 5.5 XW.0028, U2 RET HDR XTIE CLOSED
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5.6 XTW 0031, XTV 028 BYP CLOSED
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5.7 XTV 0045, TV PMP
$UCT HDR XTIE CLOSED
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OVI.103 4 PACE 9 0F 65 REV. I s\\ &
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CPSES PROCEDURE NO, i
OPERATIONS DEPARTMENT ADMINISTRATION MANUAL ODA.403 OPERATIONS DEPARTMENT IDCKED COMPONENT CONTROL REVISION NO. 2 PACE $ OF 12
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4.7 Criterion 4 -
Safety Related Flowpsths
4.1 - Technical Specifications require either frequent surveillance of valve position or locking the valves.
Locking valvos reduces exposure (ALARA) and reduces the time r6 quired to verify valve positions.
Criterion $.
Safety Related Throttle Valves
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This applies to valves which are throttled to balance flow in a system.
The mispositioning of these valves could prevent the
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system from performing its design function.
Criterion 6 Special Cases
6.1 -
Single valves whit.a provide overpressure protection at high to low pressure interfaces or which could defeat overpressure protection shall be secured in a safe position.
6.2 -
Fire protection isolation or sectional control valves that are not electrically monitored shall be secured.
i 6.3 - Valves which could bypass high Energy Line Break (HELB)
mitigation shall be locked closed in all modes.
6.4 - Valves which are required by vendors to be locked in position for proper component operation.
6.5 -
Valves that are ccasidered inaccessibis by normal means and are locked to minimire the frequent verification of valve position.
This provides an adminf.strative control to monitor valve position.
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Critarion 7 -
ANS Condition II Design Raquirement
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7.1 Valves, if mispositioned. could cause an ANS Condition II event as defined in the FSAR.
Criterion 8 -
Environmental flowpath or release pathvay
8.1 -
Locked components as required to control an environmental flowpath or release pathway.
4.8 Comoonent - Any valve or circuit breaker determined to be administratively controlled by this procedure.
This definition only applies to ODA 403 and
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CPSES ST., TEM OPERATING FROCEDURI SOP *310A w...
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g CIRCULATI!!C VATER SYSTEM RIVISION NO. 6 PACE 62 OT 90
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ATTACHMENT 1 FAGE 12 0F 21 VALVE LINEUP SHEET I
VALVE 30.. NOMElv AWJR VALVE POSITION fNITIALS M,5 X~J.0035 PRI tLV 01 UPSTRM ISOL OPEN 14. 6 XC%OO44 PRI VLV 01 DNSTEM ISOL OPEN 14.7 XCU.0036 PRI ':.T VNT CHLR HDR V7tr C14 SED
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14.8 1CV 0350 TB DRNS DISCH SMPL CLDSED 14.9 7.UJ.0069 I.TV-2939 BTt CLOSED
14.10 XCV.0070 K.W 2939 CUT ISOL OPEN 1&.11 XCU.0068 X.W-2939 IN ISOL OPEN 14.12 XCV 0066 X.TV.2939 DRN CLOSED 14.13 XCV.0053 X.TV 2938 BYF CIASED 14.14 XCV.0052 X.W.2938 OUT ISOL OPEN 14.15 XCV.0058 X.W.2938 DEJi CLDSED
" TV.2938 IN ISOL OPEN 14.16 XCV.0051
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.Q[NMJhwbee.u,,U2iCW12BSTR' FMP.!SFLL.VLV CCi!.Ildf *C1,0 SED pi.'./.,
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14.18 LCV 0252 TPCV KX IN TC CLOSED AND CAPPED
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- XCV-0323 may be opened if supplying the Unit 2 Circ Water Booster Pumps.
COM.ENTS:
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-l U. S. NUCLEAR REGULATORY COMMISSION SITE SPECIFIC EXAMINATION.
SENIOR OPERATOR LICENSE REGION
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CANDIDATE'S NAME:
FACILITY:
Comanche Peak 1
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REACTOR TYPE:
PWR-WEC4
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DATE ADMINISTERED:
92/09/30 INSTRUCTIONS TO CANDIDATE:
Uco the answer sheets provided to document your answers.
Staple this cover.
choot:on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The-passing grade requires-a final grade of at least 80%.
Examination papers will be picked up four (4) hours after the examination starts.
CANDIDATE'S TEST VALUE SCORE
%
,
20.00
%
. TOTALS FINAL GRADE i
All work done on this examination is my own.
I have neither given nor received aid.
Candidate's-Signature
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SENIOR REACTOR OPERATOR Pago
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3 TION: 001 (1.00).
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Tno Unit 2 Process computer will combine which of the following i
functions into one system?
a.-
P-2500, RM-11, ERF functions b.
P-2500, DAS, ERP functions c.
DAS, P-2500, RM-11 functions
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d.
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-QUESTION: 002 (1.00)
During dual unit operation, which Unit Supervisor will be responsible for the common systems operation?
a.
Each. Unit supervisor will be responsible for common systens located in their respective unit areas.
b.
Unit 2 Unit Supervisor c.
Unit 1 Unit Supervisor d.
The Shift Supervisor will assign responsibilities _each shift.
_ _ QUESTION: __003 (1.00)
Units 1 and 2 are in Mode 1 with minimum crew staffing.
An'on-coming i
crew Auxiliary Operator that is a fire brigade' member for the:on-coming crew reports by telephone that he will be arriving one hour late for work.
What action must be taken?
a.
-Someone must be immediately' identified.tct fill the fire _ brigade position, b.
_ Verify that at least one of the Rad. Waste Operators is qualified as fire brigade. leader.
_The position'can be left unfilled for a maximum of one hour,
-c.
d.
No action is required based on assumptions made in " minimum crew
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SENIOR REACTOR OPERATOR Pcgo
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'9 TION: 004 (1.00)
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nnich of the following will be the nornal configuration during dual unit oporations for XCW-0323, "U2 CWS BSTR PMP SPLY VLV?"
a.
closed and spool piece removed.
b.
closed and spool piece installed.
c.
locked closed and spool piece installed.
d.
locked closed and spool piece rem,oved.
QUESTION: 005 (1.00)
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Ascume both units are operating at 75% power.
Due.to a steam generator wnter level control malfunction, Unit i #1 S/G level is at 78% and-If~the same malfunction were to occur on the Unit 2 rising at 1%/ min.
- 1 S/G resulting in the same rate of level increase, which unit will reach the P14 HI+HI setpoint first, and in how-many minutes? Assume the affected Unit 2 S/G also starts at 78% and no-operator action.
a.
Unit 1, 3.5 minutes.
b.
Unit 2, 4.4 minutes.
c.
Unit 1, 4.4 minutes.
d.
Unit 2, 3.5 minutes.
QUESTION: 006 (1.00)
How does the feedwater splitflow bypass flow to the respective Unit's Steam Generators differ?
a.
Unit l'has a higher bypass flow.
b.
Unit 2 has a higher bypass flow.
c.
The bypass flows are essentially equal'.
d.
- Unit 2 S/G's do not use a' bypass flow.
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SENIOR REACTOR OPERATOR Page
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'STION: 007 (1.00)
l voit 2 $9 at 100% with all systems in their norTnal alignment except TPCWP 2-02 is in service with TPCWP 2-01 in standby (AUTO).
If TPCWP 2-02 trips on overcurrent while in this alignment, what would be the rocponse of the TPCWP 2-017 a.
auto-start immediately and supply TPCW loads.-
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b.
auto-start on loss of flow from TPCWP 2-02 only.
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c.
auto-start on loss of TPCW systern pressure only, d.
No automatic actions occur and TPCW temperatures increase.
QUESTION: 008 (1.00)
A Main Feedline break has just occured on Unit 1 S/G #1.
The Reactor han tripped and SI initiated.
-In the excitement, the SPift Supervisor accidently trips and is knocked unconscious.
Who will assume the role of Emergency Coordinator?
a.
Unit 1 Unit supervisor, b.
Unit 1 STA.
c.
Unit 2 Unit supervisor.
d.
Unit 2 STA.
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SENIOR REACTOR OPERATOR Page
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'STION: 009 (1.00)
unit 1 is in Mode 6 performing CORE ALTERATIONS and Unit 2 is operating at 103% power.
If both Units receive an RWST Temp HI alarm and confirm actual tank temperatures are 122 degrees F for both Units, which of the following actions are required per Technical Specifications?
a.
Unit 1 must suspend all operations involving CORE ALTERATIONS or positive reactivity changes, b.
Unit 2 must isolate the RWST and commence a shutdown to hot standby immediately.
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c.
Unit 2 must reduce RWST temperature to < 120 degrees F within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or commence a shutdown to hot standby.
d.
Unit 1 must make preparations to re-install the reactor vessel head within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
QUESTION: 010 (1.00)
Which of the following best describes the Unit 1 and 2 refueling
~achines?
a.
neither machine auto positioning available.
b.
only Unit 2 has auto positioning available and tested.
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c.
only Unit 1 has auto positioning available and tested.
d.
both units have auto positioning available and teste._.
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Sh!NIORREACTOROPERATOR Page
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'9 TION: 011 (1.00)
nnich of the following correctly describes the difference in OT N16 catpoints between Units 1 and 27
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a.
Both setpoints are the same, although the margin to thermal limits is greater on Unit 2.
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b.
Unit 2 setpoint is approximately 15% power higher than Unit i setpoint.
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c.
Unit i setpoint is approximately.7% power lower than Unit 2 setpoint.
d.
Unit 2 setpoint is higher, and Unit 2 penalties were removed.
-QUESTION: 012 (1.00)
How'will seismic monitors installed on Unit-1 affect Unit 2 operations?
Unit 1 seismic monitors are OPERABLE.
a.
No effect.
Unit 1 monitors will only cause alarms on Unit 1.
b.
Unit 1 monitors will cause identical'alarns on-both units.
c.
Unit 1 monitors will cause a " Unit 1 seismic" alarm on Unit 2.-
d.
No effect.
Unit 1 alarm repeaters installed on Unit 2 are spares and are not active.
QUESTION: 013 (1.00)
The Circulating Water System (CWS) supply for. Ventilation Chiller Units 05 through 09 is described by which of the following?
a.
Unit 1 CWS can1only supply chillers 07, 08 and 09, and Unit.2 CWS can only supply chiller 05 and 06, b.
Unit 1 CMS can only supply chillers 05 and 06, and Unit 2 CWS-can only supply chiller 07, 08 and 09.
- c.
Unit 1 is the normal CWS1 supply for chillers 05'through_09,' with-Unit 2 CWS-as a backup source, d.
Unit 1 and Unit 2 CWS-~ supplies can be. cross connected such that either unit'can supply flow.
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SENIOR REACTOR OPERATOR Paga 10
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'STION: 014 (1.00)
nny are quatrefoil tube support plate holes used in Unit 2 Steam Gtnerators?
reduced internal stresses in the support plate to minimize a.
susceptability to stress corrosion cracking.
b.
improved flow chacteristics resulting in increased thermal efficiency of the U tube.
lower differential pressure acros,s tube support plate improves c.
circulation ratio and steam quality.
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d.
reduced volume of sludge buildup at support plate to minimize the-magnitude of tube denting.
QUESTION: 015 (1.00)
Why has a second relief valve been installed in the Unit O CVCS RCP seal return relief line?
Increase two-phase relief flow capacity during blackout.
a.
conditions.
b.
Minimize cycling of the original, larger relief valve following a Safety Injection actuation.
The original relief capacity was insufficient to prevent lifting c.
of CCP discharge relief valves when seal return was isolated.
d.
Second relief installed as a backup to the original, larger relief valve.
QUESTION: 016 (1.00)
Why are Unit 2 S/G Lo-Lo level trip setpoints different than Unit 1 and how are they different?
a.
The' Unit 2 S/G is larger; setpoint is higher.
b.
The Unit 2 S/G'is smaller; setpoint is lower.
c.
New NR Level tap locations; setpoint is-higher.
d.
New NR Level tap locations; setpoint is_ lowe _
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SisNIOR REACTOR OPERATOR Paga 11
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""tSTION : 017 (1.00)
aring dual unit operations with Unit 1 at 95% and Unit 2 at 80% power, the SS directs transformer XST2 to be doenergized due to overheating problems.
After completing the electrical lineup, a fault causes the ground switch for XST1 to close.
What would be the resulting supplies to the 6.9kv 1E buses?
a.
Unit i energized from XST1 and Unit 2 energized from the diesels, b.
Unit 2 energized from XST1 and Unit 1 energized from the diesels,
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c.
Both Units energized from XST1.
d.
Both Unito energized from the diesels.
QUESTION: 018 (1.00)
How do the primary heatup and cooldown curves dif fer between the units and what affect dono it have on operations?
a.
Unit 2 curves are slightly more limiting and are incorporated into Technical Specifications to apply to both units, b.
Unit 1 curves are slightly more limiting and are incorporated into Technical Specifications to apply to both units.
c.
Unit 2 curves are slightly lens limiting and are incorporated into Technical Specifications to apply to Unit 2 only.
d.
Unit 2 heatup curves are slightly more limiting anu are incorporated into the Unit 1 curves in Technical Specifications to apply to both units.
QUESTION: 019 (1.00)
WHICH ONE of the following is the ALTERNATE power supply to the UNIT 2
.clasa 1E 6.9kv buses?
a.
345 kv startup transformer XST2.
b.
138 kv startup transformer XST1.
l c.
Unit 2 Emergency Diesel Generators.
d.
345 kv startup transformer 2ST.
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SENIOR REACTOR OPERATOR Page 12 P
0"ESTION: 020 (1. 00)
leak has developed from the Unit 2 CCW Surge Tank, and you have just received a "CCW SRG TK TRN A/B EMPTY" alarm.
WHICH of the following will occur (immediately following the alarm) if the leak is on side
"A" and the A CCW pump was the operating pump, with the
"B" CCW pump in ctandby?
a.
CCW flow to the RCPs is lost, b.
The A CCW pump trips and the B CCW pump starts.
c.
The B side safeguard loop isolati*on valves close.
d.
Makeup from the reactor makeup water system initiates.
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(********** END OF EXAMINATION **********;
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SENIOR REACTOR OPERATOR
- Page 1 ANSWER KEY f
k MULTIPLE CH0 ICE 001 b
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002 c
003 a
004 b
005 d
006 b
007 a
008 c
009 c
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010 c
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011 c
012 b
013 d
014 d
015 b
016 c
017 d
018 b
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'I U. S. NUCLEAR REGULATORY COMMISSION SITE SPECIFIC EXAMINATION REACTOR OPERATOR LICENSE-REGION _ 4 CANDIDATE'S NAME:
.
FACILITY:
Comanche Peak i REACTOR TYPE:
PWR-WEC4 DATE ADMINISTERED:
92/09/30 INSTRUCTIONS TO CANDIDJ.TE:
Uso-the answer sheets provided to document your answers.
Staple this cover sheet on top of the answer sheets. -Points for each question are indicated in parentheses after the question.
The passing-grade requires a final grade-of
,
at least 80%.
Examination papers will be picked up four (4) hours-af ter the examination starts.
CANDIDATE'S t
TEST VALUE SCORE __
20.00
%
TOTALS FINAL GRADE
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All work done on this examination is my own.
I have neither given nor received aid.
Candidate's Signature i:
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REACTOR' OPERATOR-Page 5-e
'9 TION: 001-(1.00)
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ano Unit 2 Process. computer will combine which of the following functions into one system?
a.
P-2500, RM-11, ERF functions b.
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c.
DAS, P-2500, RM-11 functions d.
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-QUESTION: 002 (1.00)
-Acsume both units are operating at 75% power.
Due to a steam generator water level control malfunction, Unit 1 #1 S/G 1evel is at 78% and'
rising at it/ min.
If-the same malfunction were to occur.on the Unit 2
- 1 S/G resulting in the same rate of level-increase, which unit will-reach the'P14 HI-HI setpoint first, and in h v many minutes? Assume the affected Unit 2'S/G also starts at 78% and_no operator action, a.
Unit 1, 3.5 minutes.
b.
Unit 2, 4.4 minutes.
c.
Unit 1, 4.4 minutes, d.
Unit 2, 3.5 minutes.
QUESTION: 003 (1.00)
How does the feedwater splitflow bypass flow to the respective Unit's Steam Generators differ?
a.
Unit 1 has a higher bypass flow, b.
Unit 2 has a* higher bypass flow, c.
The bypass flows are essentially equal.
d.
Unit 2 S/G's do not use a bypass flow.
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c""STION: 004 (1.00)
.41t 2 is at 100% with all systems in their normal alignment except TPCWP 2-02 is in service with TPCWP 2-01 in standby (AUTO).
If TPCWP 2-02 trips on overcurrent while in this alignment, what would be the retponse of the TPCWP 2-017 a.
auto-start immediately and supply TPCW loads.
b.
auto-start on loss of flow from TPCWP 2-02 only.
c.
auto-start on loss of TPCW system pressure only.
d.
No automatic actions occur and TPCW temperatures increase.
QUESTION: 005 (1.00)
During a complete loss of A/C electrical power to the Unit 2 containment personnel airlock hydraulic system, how would personnel inside Unit 2 containment be able to exit?
a.
Hydraulic units in the Unit 1 safeguards building are cross connected to open the Unit 2 containment and safeguards personnel airlock doors, b.
Porta-power units (and hose connections) located in containment and in the safeguards building are manually operated to open both airlock doors.
c.
Porta-power units (and hose connections) located in the airlock
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are manually operated to open both airlock doors, d.
Porta-power units (and hose connections) located in containment
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and in the airlock are manually operated to open both airlock doors.
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r 0"ESTION: 006 (1.00)
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.it 1 is in Mode 6 performing CORE ALTERATIONS and Unit 21is. operating.
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'at 100% power.
If both Units receive an RWST Temp HI alarm and confirm j
actual-tank temperatures are-122 degrees F;for both Units, which of the followingl actions are required per Technical Specifications?
a.
Unit 1 must suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
b.
Unit 2 must isolate the RWST and commence a-shutdown to hot'
H standby immediately.
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c.
Unit 2 must reduce RWST temperature to < 120 degrees F within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or commence a shutdown to hot standby.
d.
Unit 1 must make preparations to re-install the reactor vessel head within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
-QUESTION: 007 (1.00)
Which of the following best describes the Unit 1.and 2 refueling machines?
a.
neither machine auto positioning available.
b.
only Jnit.2 has auto. positioning available'and tested, c.
only Unit i has auto positioning available and tested, d.
both units have auto positioning available and-tested.
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4 OUESTION:008- (1.00)
ring dual unit operations with all systems in their normal-alignment, an internal fault occurs in XST1, resulting in the opening _of its motor operated air switch, MOAS-8085 (DXSTl) and the closing of high speed ground switch 8083 (GXST1).
Which of the following describes the status of both units?
a.
Both units Safeguards Electrical Buses will be powered from their respective Alternate Offsite Electrical Power Source.
b.-
Both units Safeguards Electrical Buses will be powered from their'
respective Preferred Offsite Electrical Power Source, c.
Both units Safeguards Electrical Buses will be powered from the same source.
d.
A fast transfer of the Unit 2 Safeguards Buses will occur; Unit 1 is not affected.
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QUESTION: 009 (1.00)
How has deletion of RCS Hot leg thermowells impacted Unit 2 operations?
a.
Strap on RTDs will be used to backup the N16 Thot indication.
b.
No operational impact, only a loss of backup RTD capability, c.
N16 Thot indication will only be available on the process computer.
d.
N16 Thot and NIS input will calculate a backup Thot indication.
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.4 9 TION: 010 (1.00)
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naich of the following correctly describes the difference 1Ln OT N16 cetpoints between Units 1 and 27 Both setpoints are the same, although the margin to thermal a.
limits is greater on Unit 2.
b.
Unit 2 setpoint is approximately 15% power higher.than Unit 1 setpoint.
Unit i setpoint la approximately.7% power lower than Unit 2 c.
setpoint.
d.
Unit 2 setpoint is higher, and Unit 2 penalties were removed.
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QUESTION: 011 (1.00)
How will seismic monitors installed on Unit 1 affect Unit 2 operations?
-Unit i seismic monitors are OPEl'.ABLE.
a.
No effect.
Unit 1 monitors will only cause alarms on Unit 1.
b.
Unit 1 monitors will cause identical alarms on both units.
Unit 1 monitors will cause a " Unit 1 seismic"' alarm on Unit 2.
c.
d.
No effect.
Unit 1 alarm repeaters installed on Unit 2 are spares and are not active.
- QUESTION: 012 (1.00)
The Circulating Water System (CWS) supply for Ventilation Chiller Units 05.through 09 is described by which of the following?
a.
Unit 1 CWS can only supply chillers 07, 08 and 09, and Unit 2 CWS can only supply chiller 05 and 06.
b.
- Unit 1 CWS can-only supply chillers 05 and 06,_and Unit _2 CWS can only supply chiller 07, 08 and 09.
Unit 1 is the normal'CWS supply for chillers 05 through 09," with c.
Unit-2 CWS as a backup source.
d.
Unit 1 and Unit 2 CWS supplies can be cross connected such that either unit can supply flow.
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REACTOR OPERATOR-Page 10.
1.-
OTTESTION: 013 (1.00)
f are quatrefoil tube support plate holes used in Unit 2. Steam-Generators?
a.
reduced internal stresses in the support plate.to minimize susceptability to stress corrosion cracking.
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b.
improved flow chacteristics resulting in. increased thermal efficiency of the U tube, c.
lower differential pressure across tube support plate' improves circulation ratio and steam quality, d.
reduced volume of sludge buildup at support plate to minimize the magnitude of tube denting.
QUESTION: 014 (1.00)
Why has a second relief valve been installed in the Unit 2 CVCS RCP seal return relief line?
a.
Increase two-phase relief flow capacity during= blackout conditions.
b.
Minimize cycling of the original, larger relief valve following a Safety Injection actuation.
c.
The original relief capacity was-insufficient to prevent lifting of CCP discharge relief valves when seal return was isolated, d.
Second relief installed as a backup to the original,; larger relief valve.
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'9 TION: 015 (1.00)'
..aw are _ the Unit 2 D/G air dryers, air _ receivers, associated piping and instrumentation protected from high temperatures if the aftercooler fan motor fails?
An interlock is_provided between the starting air compressor and a.
the aftercooler fan motor, b.
An interlock is provided with the aftercooler fan motor _to start a standby fan motor, c.
An additional " air dryer high inlet temp" and "high-temp auto shutdown" has been added to the engine control panel.
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d.
An additional " air dryer high inlet temp" and "high temp auto-shutdown" has been added to the main control board.
QUESTION: 016 (1.00)
Why are Unit 2 S/G Lo-Lo level trip setpoints different than Unit 1-and how are they different?
a.
The Unit 2 S/G is larger; setpoint'is higher.
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b.
The Unit 2 S/G is smaller; setpoint is lower.
c.
New NR Level tap locations; setpoint is higher, d.
New NR Level tap locations; setpoint is-lower.
-QUESTION: 017 (1.00)
How is the programmed steam' generator water level'different on Unit' 2 from Unit 17 Unit 2 is
a.
2.5% higher at all power levels, b.
2.5% lower at all power levels.
c.
2.5% higher when_above-15%_ power (Pimp).
d.
2.5% lower when above 15% power (Picp).
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c'"'STION : 018 ( l'. 0 0 ) -
. ring dual unit operations with Unit 1 at 95% and Unit 2 at 80% power, the SS' directs transformer XST2 to be deenergized due to overheating-problens.
After completing the electrical lineup, a fault causes the-ground switch for XST1 to close. 'What-would be the resulting supplies to the 6.9kv 1E buses?
a.
Unit 1 energized from XST1 and Unit 2. energized from the diesels.
b.
Unit 2 energized from XST1 and Unit i energized from the diesels, c.
Both Units energized from XST1.
- d.
Both Units energized from the diesels.
QUESTION: 019 (1.00)
How do the primary heatup and cooldown curves differ between the units and what affect does it have on operations?
a.
Unit 2 curves are slightly more limiting and are incorporated into Technical Specifications to apply to both units.
b.
Unit 1 curves are slightly more lLmiting and are -incorporated into Technical Specifications to apply to both units.
c.
Unit 2 curves are slightly less' limiting and are incorporated-into Technical Specifications to apply to Unit 2 only, d.
Unit 2 heatup curves are slightly more limiting and are incorporated _into the Unit 1 curves in Technical Specifications to apply to both units.
i QUESTION: 020 (1.00)
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a.
345 kv startup transformer XST2.
b.
138 kv startup transformer XST1.
c.
Unit 2 Emergency Diesel Generators.
d.
345 kv startup transformer 2ST.
(********** END OF EXAMINATION **********)
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REACTOR.0PERATOR Page 1 ANSWER KEY
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MULTIPLE CH0 ICE 001 b
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002 d
003 b
004 a
005 d
006 c
007 c
008 c
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b 010 c
011 b
012 d
013 d'
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016 c
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017 b
018 d
019 b
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- Y U. S. NUCLEAR REGULATORY COMMISSION SITE SFiCIFIC EXAMINATION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION REGION 4 CANDIDATE'S NAME:
FACILITY:
Comanche Peak 1 REACTOR TYPE:
PWR-WEC4 DATE ADMINISTERED:
92/12/02 INSTRUCTIONS TO CANDIDATE:
Read the attached instruction page carefully.
This examination replaces the current cycle facility administered requalification examination.
Retraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff.
Points for each question are indicated in parentheses after the question.
The passing grade requires a final grade of at least 80 %.
Examination papers will be picked up four (4)
hours after the examination starts.
CANDIDATE'S TEST VALUE SCORE
%
_
30.00
%
TOTALS FIRKE GRADE All work done on this examination is my own.
I.have neither given nor received aid.
Candidate's Signature
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SENIOR REACTOR OPERATOR'
Page 5
"""STION: 001 (1.00)
...e Unit 2 Process computer'will combine which of the following-functions into one system?
a.
P-2500, RM-11, ERF functions b.
DAS, P-2500, RM-11 functions d.
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QUESTION: 002 (1.00)
During dual unit operation, which Unit Supervisor will be responsible-for the common systems operation?
a.
Each Unit supervisor will be responsible for common systems located in their respective unit areas.
b.
Unit 2 Unit Supervisor c.
Unit 1 Unit Supervisor
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d.
The Shift Supervisor will assign responsibilities each shift.
QUESTION: 003 (1.00)
-Which of the following events would result-in-both units'-6.9 KV 1E
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buses being powered from the:same transformer?
a.
Unit 1 6.9 Kv IE buses slow transfer to the.XST2 startup transformer.
b.
Unit 1 6.9 Ky IE buses fast transfer to the-XST2 startup transformer, c.
Unit 2'6.9 Kv-lE buses slow transfer to the.XSTI startup transformer, d.
Unit-2 6.9 Kv.lE buses-slow transfer to the XST2'startup transformer.
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""'STION: 004 (1.00)
.aring dual unit operations, both units at 100% reactor power, when is it allowed to have less-than seven Auxiliary Operators on the shift crew?-
a.
For a maximum of one hour while additional personnel are called in to meet minimum manning requirements.
b.
The Shift Supervisor may take credit for any fire brigade qualified RWO to meet minimum manning requirements.
c.
One less A0 may be present if one of the RW0s is fire. brigade
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leader qualified.
d.
One less A0 may be present if one of the Unit Supervisors is fire brigade leader qualified.
QUESTION: 005 (1.00)
Unit 1 is at 100% and Unit 2 is-in Mode 4.
The Shift Supervisor directs both Unit Supervisors to coordinate activities to align Ventilation rhillers 05 and 06 cooling water supply from Unit 2 Circulating Water
' tem (CWS). -Which of the following actions is correct?-
a.
Unit 2 CWS can not be aligned to Ventilation Chillers 05 and 06 since there is no crosstie valves.
b.
Unit 2 CWS can only be aligned to Ventilation Chiller 05.
c.
Align Unit 2 CWS to Ventilation Chillers 05 and 06.
d.
Align Unit 2 CWS to Ventilation ChillersL01 through 09.
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"""STION: 006 (1.00)
...its 1 and 2 are.in Mode I with minimum crew staffing. An on-coming crew Auxiliary Operator that is a fire brigade member for the on-coming crew reports by telephone that he will be arriving one hour late for work. What action must be taken?
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a.
Someone must be immediately identified to fill the fire brigade position.
b.
Verify that at least one of the Rad. Waste Operators is qualified as fire brigade leader.
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c.
The position can be left unfilled for a maximum of one hour.
d.
No action is required based on assumptions made in " minimum crew staffing."
QUESTION: 007 (1.00)
Which of the following will be the normal configuration during dual unit operations for XCW-0323, "U2 CWS BSTR PMP SPLY VLV?"
a.
closed and spool piece removed.
b.
closed and spool piece installed.
c.
locked closed and spool piece installed.
d.
locked closed and spool piece removed.
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"STION: 008 (1.00)
. sume both units are operating at 75% power. Due to a steam generator cater level control malfunction, Unit 1 #1 S/G level is at 78% and-rising at 1%/ min.
If the same malfunction were to occur on the Unit 2
- 1 S/G resulting in the same rate of level increase, which unit will reach the P14 HI-HI setroint first, and in how many minutes? Assume the-affected Unit 2 S/G also starts at 78% and no operator action.
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a.
Unit 1, 3.5 minutes, b.
Unit 2, 4.4 minutes.
c.
Unit 1, 4.4 minutes, d.
Unit 2, 3.5 minutes.
' QUESTION: 009 (1.00)
How does the feedwater splitflow bypass flow to the respective Unit's-Steam Generators differ?
a.
Unit I has a higher bypass flow, b.
Unit 2 has a higher bypass flow.
c.
The bypass flows are essentially equal.
d.
Unit 2 S/G's do not use a bypass flow.
-QUESTION: 010 (1.00)
Unit 2 is at 100% with all systems in their normal alignment except TPCWP 2-02 is in service with TPCWP 2-01 in standby (AUT0).
If TPCWP 2-02 trips on overcurrent while in this alignment, what would be the response of the TPCWP 2-0l?
a.
auto-start immediately and supply TPCW loads.
b.
auto-start on Ir,ss of flow from TPCWP 2-02 only.
c.
auto-start on loss of TPCW system pressure only.
d.
No automatic actions occur and TPCW temperatures increas ;.
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""*STION: 011 (1.00)
...th dual unit-Technical Specifications and the words " Unit I and 2" inserted, how is an entry into an LC0 requiring both units to be shutdown avoided?
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Dual LCOs exist in instances where a shutdown is required.
a.
b.
An LC0 exists that will allow only the affected unit be shutdown unless the affected system / component is common, Both units must connence a shutdown while the unaffected unit is c.
proven OPERABLE.
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d.
The shutdown LCO will be unit specific and will identify any shared systems.
QUESTION: 012 (1.00)
A Main Feedline break has just occured on Unit 1 S/G #1. The Reactor has tripped and SI initiated.
In the excitement, the Shift Supervisor accidently trips and is knocked unconscious.
Who will assume the role of Emergency Coordinator?
a.
Unit 1 Unit supervisor.
b.
Unit 1 STA.
c.
Unit 2 Unit supervisor.
d.
Unit 2 STA.
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"""STION: 013 (1.00)
...it 1 is in Mode 6 performing CORE ALTERATIONS and Unit 2 is operating at 100% power, if both Units receive an RWST Temp Hi alarm and confirm actual tank temperatures are 122 degrees F for both Units, which of the following actions are required per Technical Specifications?
a.
Unit I must suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
,
b.
Unit 2 must isolate the RWST and commence a shutdown to hot standby immediately, c.
Unit 2 must reduce RWST temperature to < 120 degrees F within I hour or commence a shutdown to hot standby, d.
Unit 1 must snake _ preparations to re-install the reactor vessel head within I hour.
QUESTION: 014 (1.00)
Which of the following best describes the Unit I and 2 refueling machines?
a.
neither machine auto positioning available.
b, only Unit 2 has auto positioning available and tested, c.
only Unit I has auto positioning available and_ tested.
d.
both units have auto positioning available and tested.
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'"'Sil0N: 015 (1.00)
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....ich of the following correctly describes the difference in 01 NTE setpoints between Units 1 and 27 a.
Both setpoints are the same,.altnough the margin.to thermal limits is greater on Unit 2.
b.
Unit 2 setpoint is approximately 15% power higher than Unit 1 setpoint.
c.
Unit I setpoint is approximately 7% power, lower than Unit 2 setpoint, d.
Unit 2 setpoint is higher, and Unit 2 penalties were removed.
QUESTION: 016 (1.00)
While operating Unit 2 at 100% power, the. B0P operator notices TPCW flow is about 2000 gpm. What-action-should the Turbine Building A0 be directed to take?
a.
throttle open on the TPCW recirculation line valve.
b.
fully closa the Primary Water temperature control valve.
c.
throttle close on the TPCW recirculation line valve.
d.
fully open the Primary Water temperature control valve.
QUESTION: 017 (1.00)
How will seismic monitors installed on Unit 1 affect Unit 2 operations?
Unit 1 seismic' monitors are OPERABLE.
a.
No effect. Unit I monitors will only cause alarms on Unit 1.
-b.
Unit 1 monitors will cause identical alarms on both units.
c.
Unit I monitors will cause a " Unit I seismic" alarm on Unit 2.
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No ef fect.. Unit I alarm repeaters installed on Unit 2 are spares and are not active.
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"""STION: 018 (1.00)
....ich of the following describes the difference between the auto positioners for Unit I and 2 Refueling Machines? (Construction is
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complete on Unit 2)
a.
Both units have auto positioner installed, but only Unit 2 has tested it, b.
Both units have auto positioner installed, but only Unit I has tested it.
c.
Only Unit 2 has auto positioner installed', although Unit'l has auto positioner capability, d.
Only Unit I has auto positioner installed, although Unit 2 has.
auto positioner capability.
QUESTION: 019 (1.00)
-The Circulating Water System (CWS) supply.for Ventilation Chiller Units 05 through 09 is described by which of the following?
a.
Unit 1 CWS can only supply chillers 07, 08 and 09, and Unit 2 CWS can only supply chiller 05 and 06.
b.
Unit 1 CWS can only supply chillers 05 and 06, and Unit 2 CWS can only supply chiller 07, 08 and 09.
c.
Unit 1 is the normal CWS supply for chillers 05 through 09, with Unit 2 CWS as a backup source.
d.
Unit 1 and Unit 2 CWS supplies can-be cross connected such that either unit can supply flow.
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'STION: 020: (1.00)
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...y"are quatrefoil tube-support plate holes -used in Unit 2 -Steam Generators?
a.
reduced internal stresses in the support plate to_ minimize
susceptability to stress corrosion cracking.
b.
improved flow chacteristics resulting in increased thermal efficiency of the U tube, c.
lower differential pressure across tube support plate improves circulation ratio and steam quality, d.
reduced volume of sludge buildup at support plate to minimize the magnitude of tubo denting.
- QUESTION: 021 (1.00)
During dual unit Mode 1 operations, Unit I has an SR0 licensed /STA qualified Unit Supervisor _ and Unit 2 has an SR0 licensed Unit-Supervisor.
How would the STA responsibilities be fulfilled if Unit 2 avperiences an ESF actuation?
a.
There are always two STA qualified individuals on site; the second individual will fulfill STA duties on Unit 2.
b.
The Unit 1 STA qualified US may leave Unit 1 for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to
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fulfill the Unit 2 STA position.
c.
An additional SR0 will relieve the Unit 1 US to fulfill the Unit 2 STA position.
d.
The Shift Supervisor will assume STA-duties on Unit 2.
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"""STION: 022 (1.00)
....y 'has a second relief valve been installed in the Unit 2 CVCS RCP seal return relief line?
a.
Increase two-phase relief flow capacity during blackout conditions.
b.
Minimize cycling of the original, larger relief valve following a Safety Injection actuation.
c.
The original relief capacity was insuffic.ient to. prevent lifting of CCP discharge relief valves when seal return was isolated, d.
Second relief installed as a backup to the original, larger relief valve.
QUESTION: 023 (1.00)
Why are Unit 2 S/G Lo-Lo level trip setpoints different than Unit 1 and how are they different?
a.
The Unit 2 S/G is larger; setpoint is higher, b,
The Unit 2 S/G is smaller; setpoint is lower.
c.
New NR Level tap locations; setpoint is higher,
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d.
New NR L-evel tap locations; setpoint is lower.
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h QUESTION: 024 (1.00)
Due to sizing differences in the Feedwater restriction orifices, how will the feedwater splitflow bypass flow be different on Unit 27 a.
flow will be higher than Unit 1.
b.
flow will be lower than Unit 1.
c.
. flow is not affected by the restriction orifices, d.
flow is not changed due to other offsetting difference..
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^""STION: 025 (1.00)
..aring dual unit operations with Unit 1 at 95% and-Unit 2 at.80% power, the SS directs transformer XST2 in be deenergized due to overheating problems.
After completing the electrical lineup, a fault causes the ground switch for XST1 to close. What would be the resulting' supplies to the 6.9kv IE buses?
a.
Unit I energized from XST1 and Unit 2 energized from the diesels, b.
Unit 2 energized from XSTI and Unit 1 energized from the diesels.
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c.
Both Units energized from XST1.
d.
Bc,th Units energized from the diesels.
QUESTION: 026 (1.00)
How do the primary heatup and cooldown curves differ between the units and what affect does it have on operations?
a.
Unit 2 curves are slightly more' limiting and are incorporated'
into Technical Specifications-to apply to both units, b.
Unit 1 curves are slightly more' limiting and are incorporated into Technical Specifications-to apply to both units.
c.
Unit 2 curves are slightly less limiting 'and are incorporated into Technical Specifications to apply to Unit 2 only, d.
Unit 2-heatup curves are slightly more limiting and are'
incorporated into the Unit I curves in Technical Specifications to apply to both units.
QUESTION: 027 (1.00).
WHICH ONE of the following is the ALTERNATE power supply to the UNIT 2 class IE 6.9kv buses?
a.
345 kv startup transformer XST2.
b.
138 kv startup transformer XST1.
c.
Unit 2 Emergency Diesel Generators.
d.
345 kv startup transformer 2ST.
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SENIOR REACTOR OPERATOR Page 16
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^"'STION: 028 (1.00)
..dCH of the following describes a feature of Unit 2 05 Steam Generators?
a.
Inconel tube support plates for improved corrosion resistance, b.
Round holes in the tube support plate.
c.
"U" tubes are thermally annealed, reducing residual stresses.
d.
Increased number of U-tubes over 04 for 1arger heat transfer area.
,
QUESTION: 029 (1.00)
A leak has developed from the Unit 2 CCW Surge Tank, and you have just received a "CCW SRG TK TRN A/B EMPTY" alarm. WHICH of the following will occur (immediately following the alarm) if the leak is on side "A" and the A CCW pump was the operating pump, with the "B" CCW pump in standby?
a.
CCW flow to the RCPs is lost, b.
The A CCW pump trips and the B CCW pump starts, c.
The B side safeguard loop isolation valves close.
d.
Makeup from the reactor makeup water system initiates.
>
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- STION: 030 (1.00)'
uaring' dual unit operations with Unit I at 85% and Unit 2 at 100%, a 25 gallon per minute leak develops in the Unit 1 boric acid storage
)
tank. The decision-is made to declare the tank-inoperable, drain and repair.
The Unit 2 boric acid storage tank is filled to 100% by-
transferring the drained contents of the Unit 1 tank.
WHICH_of the following statements is CORRECT after draining Unit l's and filling Unit 2 boric acid storage tank.
a.
Restore the Unit I boric acid-storage tan.k to operable'within 72 i
hrs. or be in hot standby within the next 6 hrs, b.
Restore the Unit 1 boric acid storage tank to operable within-1 hr. or be in hot standby within the next 6 hrs.
c.
If Unit 2 must. conduct operations that reduce the inventory of the Unit 2 boric acid storage tank, BOTH units must be in hot standby in the next 6 hrs.
d.
BOTH units may continue operations and are not entered into an LCO action at this time.
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(********** END OF EXAMINATION.**********)_
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ANSWER KEY
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HULTIPLE CHOICE 023 c
001 b
024 a
002 c
025 d
003 d
026 b
004 d
027 a
005 c
028 c
006 a
029 a
007.
b 030 a
008 d
009 b
a 011 b
,
012 c
013:
c 014 c-015-c 016 a
017 b
018 b
019 d
020.
d 021 c
022 b
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REACTOR' OPERATOR; Page 5
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""cSTION: 001 (1.00)
.e Unit. 2 Process computer will combine which of the following functions into one system?
a.
P-2500, RM-ll, ERF functions b.
DAS, P-2500, RM-11 functions t
!
d.
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QUESTION: 002 (1.00)
Which of the following events would result in both units' 6.9 Kv IE buses being powered from the same transformer?
a.
Unit 1 6.9 Kv IE buses slow transfer to tne XST2 startup transformer, b.
Unit 1 6.9 Kv IE buses fast transfer to the XST2 startup transformer.
c.
Unit 2 6.9 KV IE buses slow transfer to the XSTl startup transformer.
d.
Unit 2 6.9 Kv IE buses slow transfer to the XST2 startup transformer.
QUESTION: 003 (1.00)
-
Unit 1 is at 100% and Unit 2 is in Mode 4.
The Shift Supervisor directs both Unit Supervisors to coordinate activities to align Ventilation Chillers 05 and 06 cooling water supply from Unit 2 Circulating _ Water System (CWS). Which of the following actions is correct?
a.
. Unit'2 CWS can not be aligned to Ventilation Chillers 05 and 06 since there is no crosstie valves, b.
Unit 2 'CWS can only be aligned to Ventilation Chiller.05.
c.
Align Unit 2 CWS to Ventilation Chillers 05 and 06.
d.
Align Unit 2 CWS to Ventilation Chillers 01 through 09.
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""'STION: 004 (1.00)
...,si -) both units are operating at 75% power.
Due to a steam generator water level control malfunction, Unit I #1 S/G 1evel is at 78% and risir.g at 1%/ min.
If the same malfunction were to occur on the Unit 2 el S/G resulting in the same rate of level increase, which unit will.
reach the P14 HI-HI setpoint first, and in how many-minutes? Assume the t
affected Unit 2 S/1 alt.o starts at 78% and no operator action, a.
L' nit 1, 3.5 minutes.
b.
Unit 2, 4.4 minutes.
c.
Unit 1, 4.4 minutes.
d.
Unit 2, 3.5 minutes.
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QUESTION: 005 (1.00)
How does the feedwater splitflow bypass flow to the respective Unit's Steam Generators differ?
.
,
a-Unit I has a higher bypass flow.
b.
Unit 2 has a higher bypass flow, c.
The bypass flows are essentially equal.
d.
Ur't 2 S/G's do not use a bypass flow.
QUESTION: 006 (1.00)
Unit 2 is at 100% with all systems in their normal alignment except TPCWP 2-02 is in-service with TPCWP 2-01 in standby (AUT0).
If TPCWP 2-02 trips on overcurrent while in this alignment, what would be the response of the TPCWP 2-017 a.
auto-start immediately and supply TPCW loads, b.
auto-start. on. loss of flow from TPCWP 2-02 only.
c.
auto-start on loss of TPCW system pressure only, d._
- No automatic actions occur and TPCW temperatures increase.
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"""STION: 007 (1.00)
.
.. ring a complete loss of A/C electrical power to the Unit 2 containment porsonnel airlock hydraulic system, how would personnel inside Unit 2
'
containment be able to exit?
a.
Hydraulic units in the Unit I safeguards building are cross connected to open the Unit 2 containment and safeguards personnel
!
airlock doors.
b.
Porta-power units (and hose connections) located in containment and in the safeguards butiding are manually operated to open both
"
airlock doors.
located in the airlock Porta-power units (and hose connections) k doors.
c.
are manually operated to open both airloc
.
d.
Porta-power units (and hose connections) located in containment.
and in the airlock are manually operated to open both airlock doors.
QUESTION: 008 (1.00)
'h dual unit Technical Specifications and the words " Unit I and 2" i
4erted,-how is an entry into an LCO requiring both units to be
!
shutdown avoided?
a.
Dual LCOs exist in instances where a shutdown is required.
b.
An LCO exists that will allow only the affected unit be shutdown unless the affected system / component is common.
.
c.
Both units must commence a shutdown while the unaffected unit is proven OPERABLE.
.d.
Tho shutdown LCO will be unit specific and will identify any shared systems.
.
d
.,y.
c.
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""tSTION: 009 (1.00)
...it 1 is in hode 6 performing CORE ALTERATIONS and Unit '! is verating at 100% power.
If both Units receive an RWST Temp H1 alarm and confirm actual tank temperatures are 122 degrees F for both Units, which of the
,
following actions are required per Technical Specifications?
a.
Unit 1 must suspend all operations involving t,0RE ALTERATIONS or positive reactivity changes, b.
Unit. must isolate the RWST and commence a shutdown to hot
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stan,by immediately.
,
c.
Unit 2 must reduce RWST temperature to < 120 degrees F within 1
-
hour or commence a shutdown to hot standby.
d.
Unit 1 must make preparations to re-install the reactor' vessel head within I hour.
QUESTION: 010 (1.00)
Which of the following best describes the Unit 1 and 2 refueling machines?
a.
neither machine auto positioning available.
b.
only Unit 2 has auto positioning available and tested.
c.
only Unit I has auto positioning available and-tested, d.
both units have auto positioning available and tested.
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REACTOR UPERATOR Page 9 l
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^"tST10N: 011 (1.00)
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.. ring dual unit operations with all systems in their normal alignment, an internal fault occurs in XST1, resulting in the opening of ita motor
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operated air switch, M0AS 8085 (0XST)) and the closing of high speed i
ground switch 8083 (GXSTI). Which of the following describes the status of both units?
a.
Both units Safeguards Electrical Buses will be powered from their
respective Alternate Offsite Electrical Power Source.
,
b.
Both units Safeguards Electrical Buses will be powered from their-
-
respective Preferred Offsite Electrical P'ower Source, c.
Both units safeguards Electrical Buses will be powered from the same source.
d.
A fast transfer of the Unit 2 Safeguards Buses will occur; Unit 1 is not affected.
QUESTION: 012 (1.00)
How has deletion of RCS Hot leg thermowells impacted Unit 2 operations?
a.
Strap on RTDs will be used to backup the N16 That indication.
b.
No operational impact, only a loss of backup RTD capability.
c.
N16 Thot indication will only be available on the process computer.
d.
N16 That and NIS input will calculate a backup That indication, i
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""tSTION: 013 (1.00)
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-..ich of the following correctly describes the difference in OT N16 setpoints between Units 1 and 27 a.
Both setpoints are the same, although the margin to thermal limits is greater on Unit 2.
b.
Unit 2 setpoint is approximately 15% power higher than Unit I setpoint.
l c.
Unit I setpoint is approximately 7% power lower than Unit 2 setpoint.
d.
Unit 2 setpoint is higher, and Unit 2 penalties were removed.-
QUESTION: 014 (1.00)
While operating Unit 2 at 100% power, the B0P operator notices TPCW flow is about 2000 gpm. What action should the Turbine Building A0 be directed to take?
a.
throttle open on the TPCW recirculation line valve, b.
fully close the Primary Water temperature control valve, c.
throttle close on the TPCW recirculation line valve.
,
d, fully open the Primary Water temperature control valve.
QUESTION: 015 (1,00)
How will. seismic monitors installed on Unit 1 affect Unit 2-operations?-
Unit I seismic monitors are OPERABLE.
a.
No effect.
Unit I monitors will only cause alarms on Unit 1.
b.
Unit 1 monitors will cause identical alarms on both units, c.
-Unit 1 monitors will cause a " Unit I seismic" alarm on Unit 2.
d.
No effect. Unit I alarm repeaters installed on' Unit 2 are spares and are not' active.
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""tSTION: 016 (1.00)
....ich of the following describes the difference between the auto positioners for Unit I and 2 Refueling Machines? (Construction is complete on Unit 2)
a.
Both units have auto potitioner installed, but only Unit 2 has tested it.
b.
Both units have auto positioner installed, but only Unit I has tested it.
c.
Only Unit 2 has auto positioner installed, although Unit I has auto positioner capability, d.
Only Unit I has auto positioner installed, although Unit 2 has auto positioner capability.
,
QUESTION: 017 (1.00)
'
The Circulating Water System (CWS) supply for Ventilation Chiller Units 05 through 09 is described by which of the following?
a.
Unit 1 CWS can only supply chillers 07, 08 and 09, and Unit 2 CWS
'
can only supply chiller.05 and 06.
b.
Unit-1 CWS can only supply chillers 05 and 06, and Unit 2 CWS can only supply chiller 07, 08 and 09.
c.
Unit 1 is the normal CWS supply for chillers 05 through 09, with Unit 2 CWS as a backup source.
d.
Unit 1 and Unit 2 CWS supplies can be cross connected such that either unit can supply flow.
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""cSTION: 018 (1.00)
..y are quatrefoil tube support plate holes used in Unit 2 Steam Generators?
a.
reduced internal stresses in the support plate to minimize susceptability to stress corrosion cracking.
b4 improved flow chacteristics resulting in increased thermal efficiency of the U tube, c.
lower differential pressure across tube support plate improves
'
circulation ratio and steam quality.
d.
reduced volume of sludge buildup at support plate to minimize the -
magnitude of tube denting.
QUESTION: 019 (1.00)
Why has a second relief valve been installed in the Unit 2 CVCS RCP seal return relief line?
a.
Increase two-phase relief flow capacity during blackout conditions.
b.
Minimize cycling of the original, larger relief valve following a Safety injection actuation.
c.
The original-relief capacity was insufficient to prevent lifting-of CCP discharge relief valves when seal roturn was isolated, d.
Second relief installed as a backup to the original, larger relief valve.
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^" CST!UN: 020 (1.00)
se are the Unit 2 D/G air dryers, air receivers, associated piping and
,
instrumentation protected from high temperatures if the aftercooler fan motor fails?
a.
An interlock is provided between the starting air compressor and
the aftercooler fan motor.
b.
An interlock is provided with the aftercooler fan motor to start-
'
a standby fan motor.
c.
An additional " air dryer high inlet temp"~ and "high temp auto shutdown" has been added to the engine control panel.
d.
An additional " air dryer high inlet temp" and "high temp auto shutdown" has been added to the main control board.
QUESTION: 021 (1.00)
Why are Unit 2 S/G Lo-Lo level trip setpoints different than Unit I and -
how are they different?
a.
The Unit 2-5/G is larger; setpoint is higher.
b.
The Unit 2 S/G is smaller; setpoint is lower.
c.
New NR Level tap locations; setpoint is higher, d.
New NR Level tap locations; setpoint is lower.
. QUESTION: 022 (1.00)
Due to sizing differences in the feedwater restriction orifices, how
,
will the feedwater splitflow bypass flow be different on Unit 27 a.
flow will be higher than Unit 1.
b.
flow will be lower than Unit 1.
L c.
flow is not affected by the restriction orifices.
,
d.
flow is not changed due to'other offsetting differences.
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""rSTION: 023 (1.00)
w is the programmed steam generator water level different on Unit 2 from Unit 17 Unit 2 is
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a.
2.5% higher at all power levels.
b.
2.5% lower at all power levels, c.
2.5% higher when above 15% power (Pimp).
,
d.
2.5% lower when above 15% power (Pimp).
,
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QUESTION: 024 (1.00)
During dual unit operations with Unit I at 95% and Unit 2 at 80% power, the SS directs transformer XST2 to be deenergized due to overheating problems. After completing the electrical lineup, a fault canes the ground switch for XSTI to close. What would be the resulting supplies to the 6.9kv IE buses?
a.
Unit 1 energized from XSTl and Unit 2 energized from the diesels, b.
Unit 2 energized from XSTI and Unit 1 energized from the diesels,
-
c.
Both Units energized from XST1.
d.
Both Units energized from the diesels.
QUESTION: 025.(1.00)
How do the primary heatup and cooldown curves differ between the units and what affect does it have on operations?
a.
Unit 2 curves are slightly more-limiting and are incorporated-into Technical Specifications to apply to both. units, b.
Unit I curves are slightly more limiting and are incorporated into Technical Specifications to apply to both units.-
c..
Unit 2 curves ~are slightly less limiting and are incorporated-into Technical Specifications to apply to Unit 2 only.
d.
Unit 2 heatup curves are slightly more limiting and are
' incorporated into the Unit I curves in Technical Specifications to apply to both units.
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REACTOR OPERATOR Page 15
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""cSTION: 026 (1.00)
..1C61 ONE of the following is the ALTERNATE power supply to the UNIT 2 class lE 6.9kV buses?
a.
345 kv startup transformer XST2.
b.
138 kv startup transformer XST1.
c.
Unit 2 Emergency Diesel Generators.
d.
345 kv startup transformer 2ST.
_
QUESTION: 027 (1.00)
WillCH of the following describes a feature (f Unit 2 05 Steam Generators?
a.
Inconel tube support plates for improved corrosion resistance.
b.
Round holes in the tube support plate, c.
"U" tubes are thermally annealed, reducing residual stresses, d.
Increased number of U-tubes over 04 for larger heat transfer area.
_
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"" CST 10N: 028 (1.00)
...ile conducting an initial valve lineup on UNIT 2 CCW, you discover that a _small vent isolation valve is on a different elevation / location than in UNIT 1, and the location is not in accordance with the lineup shaet.
This is determined to be a minor procedural discrepancy.-
WHAT action (s) should you take?
.
!
a.
Complete the lineup, initiate a Technical Evaluation (TE) per STA-820 " Reporting and Evaluating Unit Differences."
'
b.
Complete the lineup, initiate a procedure'/ form change form per STA-205, " Changes-to Proceduros."
c.
Terminate the lineup, then initiate a procedure / form change form per STA-205, " Changes to Procedures, d.
Terminate the lineup, initiate a Technical Evaluation (TE) per STA-820, " Reporting and Evaluating Unit Differences", and initiate a procedure / form change form per STA-205, " Changes to Procedures."
i STION: 029 (1.00)
A leak has developed from the Unit 2 CCW Surge Tank, and you have just received a "CCW SRG TK TRN A/B EMPTY" alarm. WHICH of the following will occur (immediately following the alarm) if the leak is on side "A" and the A CCW pump was the operating pump, with the "B" CCW pump in standby?
a.
CCW flow to the RCPs is lost, b.
The A CCW pump trips and the D CCW pump starts.
c.
The B side safeguard loop isolation valves close, d.
Makeup from the reactor makeup water system initiates.
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"""STION: 030 -(1.00)
.. ring dual unit operations with Unit I at 85% and Unit 2 at 100%, a 25 gallon per minute leak develops in the Unit-I boric acid storage tank.
The decision is made to declare the tank inoperable, drain and repair. The Unit 2 boric acid storage tank is filled to 100% by transferring the drained contents of the Unit I tank.
WHICH of the following statements is CORRECT after draining Unit l's and filling Unit 2 boric acid storage tank, a.-
Restore the Unit I boric acid storage tank to operable within 72 hrs. or be in hot standby within the next'6 hrs.
,
b.
Restore the Unit I boric acid storage tank to operable within I hr. or be in hot standby within the next 6 hrs.'
c.
If Unit 2 must conduct operations that reduce the inventory of the Unit 2 boric a:id storage tank, BOTH units must be in hot standby in the next 6 hrs.
d.
BOTH units may continue operations and are not entered into an 1.C0 action at this time.
.(**********
END OF EXAMINATION **********)
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e-REACTOR OPERATOR Page 1
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ANSWER KEY
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HULTIPLE CHOICE 023 b
001 b
024 d
002 d
025 b
.
003 c
026 a
,
004 d
027 c
005 b
028 b
006 a
029 a
,
007-d 030 a
008-b
'009 c
c 011 c
012 b
013 c
014 a-015 b
.016 b
,
017 d
018 d
'019 b
020 a
021 c
022 a
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(**********
END OF EXAMINATION **********)
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bec w/ enclosure (except Master Examination and Answer Key):
bec to dist by RIV:
J. L. Milhoan, RA Resident Office RIV file L. Hiller, TTC DRS (J. L. Pellet)
L. Hurley CPPD:0SP Reading (MS:
7-H-17)
S. McCrory T. Bergman, NRR Project Manager (13-H-15)
B. Holian, NRR Project Manager (13-H-15)
Licensee & Debt Collection Branch, ATTN:
Leah Tremper (MNBB 4503)
.
bcc w/ complete enclosure:
bcc to DMB (IE42)
Chief Examiner (R. Lantz)
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Chief Examiner Reading File (C. Gordon)
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RLantz/cjg JPellIt
)dCo/ lins / ABB)ach f Nbp[
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