ML20215D311
| ML20215D311 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/02/1986 |
| From: | Cooley R, Pellet J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20214K187 | List: |
| References | |
| 50-482-OL-87-01, 50-482-OL-87-1, NUDOCS 8612160314 | |
| Download: ML20215D311 (83) | |
Text
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REQUALIFICATION PROGRAM AUDIT AND OPERATOR LICENSE EXAMINATION REPORT OL 87-01 Licensee: Kansas-Gas and Electric. Company P. O. Box 208 Wichita, Kansas 67201 I
Docket: 50-482 License No: NPF-42 Operator License and Requalification Program Audit examinations at Wolf Creek Generating Station (WCGS).
Chief Examiner: A II'N ' b John L. Pellet, Examiner Date Signed Approved By: -
ld-d--)h Date Signed RalphjA. Cooley,SectigChief ,
Summary:
NRC administered three Reactor Operator (RO) and two Se'nior Reactor Operator (SR0) license examinations and performed the agreed upon pilot Licensed Operator Requalification Program Audit at Wolf Creek Generating Station (WCGS),
during the week of October 6,1986.
The five license candidates successfully completed the required examinations and have been issued the appropriate license, i
The pilot requalification program audit involved NRC review of a facility developed examination set and its administration and grading, plus evaluation of facility administered operating examinations. Based on this effort, the WCGS Licensed Operator Requalification Program is evaluated as satisfactory.
l 8612160314 861205 PDR ADOCK0500g2
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2 REPORT DETAILS
- 1. PERSONS EXAMINED License Examinations: TYPE: SRO R0 TOTAL PASS: 2-100% 3-100% 5-100%
FAIL: 0-0%
0-0% 0-0%
Requalification Examinations: TYPE: SR0 R0 TOTAL
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PASS: 6-100% 2-100% 8-100%
, FAIL: 0-0% 0-0% 0-0%
- 2. EXAMINERS J. Pellet, NRC (Chief Examiner)
R. Cooley, NRC L. Defferding, NRC (PNL)
- 3. EXAMINATION REPORT ,
Individu'al perforinance results are not included in this report because these reports are piace in the NRC Public Document Room.
- a. EXAMINATIOSREUENCOMMENTRESOLUTION In general, editorial comments or changes made during the examination, review, or subsequent grading reviews are not addressed by this resolution section. This section reflects resolution of substantive comments made by the WCGS staff. The modifications discussed below are included,in the master examination key which is included elsewhere in this report (see 3.e.), as are all other changes mentioned above but not discussed herein. Note that comments are paraphrased below for brevity. Comments are only resolved once.
Comments like "Sams as . . ." are not addressed or noted herein.
1.09.a. Gap contamination by fission products can also lead to this.
Resp.: ACCEPT. Key modified.
2.02.g. Seal water heat exchanger valves get a signal but return valves do not.
., Resp.: ACCEPT. Key modified.
2.06.b. Answ:r #1 should be either.
Resp.: ACCEPT. Key modified.
2.06.c. Accept opposite if stopping engine.
Resp.: ACCEPT. Key modified.
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-2.08.b. Also failure of NN01 or NN04 stops switchover.
Resp.: ACCEPT. Key modified.
2.10.a Accept " manual."
Resp.: REJECT. Question asks for " condition."
3.04 1 deg's F error band appears small.
Resp.: ACCEPT. Key modified for larger range of answers.
3.10.b. P-12 can be considered protective.
Resp.: ACCEPT. Key modified.
3.11.b. MFW pump discharge valves auto close from MFP trip not FWIS.
Resp.: ACCEPT. Key modified.
4.06 Subcooling acceptance criteria are 0 deg's F by curve or 30 deg's F by meter so "b" is also correct.
Resp.: ACCEPT. Key modified to accept "b" if stated assume subcooling by curve, not meter.
4.10.c. Accept 3 rem /qtr with valid NRC-4.
Resp.: ACCEPT. Key modified.
5.02. At WCGS, Local Power Density (KW/FT) is frequently referred to as FQ(z).
Resp.: ACCEPT. Key modified.
5.05.a. Cooldown limit is 50 deg's F per hour, not 25.
Resp.: ACCEPT. Key modified. t 5.05.b. Accept RCS integrity as alternate answer.
Resp.: ACCEPT. Key modified.
5.05.c. Accept DNB per Tech Specs.
Resp.: ACCEPT. Key modified.
5.06 Accept as alternate answer the center of the core.
Resp.: ACCEPT. Key modified.
5.07.c Accept description of locked rotor or slipped poles.
Resp.: REJECT. No supporting reference provided.
5.12 Philosophy of emergency procedures and HT&FF concepts dictate that "a" is the correct answer. We believe the cited reference supports this.
Resp.: REJECT. When a head steam bubble experiences a pressure increase, it is compressed by doing work on it. This ,tork I results in a temperature increase. This can be easil) seen from a review of the Mollier diagram. The current key is therefore correct and no change is appropriate.
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6.02.a. - EMG-ES-11 also requires that' availability of power be checked.
Res p.': ACCEPT. Key modified.
6.02.c Accept removing power from the containment sump valves or breakers.
Resp.: ACCEPT.- Key modified.
6.03 Based on the reference provided, accept the following answers: a. 2, b. 4 & 5, c. 4, d. 2, e. 1, f. 4, g. 1, h. 3 Resp.: ACCEPT. Key modified.
6.05 . Accept answer which includes discussion of the MD AFW pump discharge throttle valves which automatically limit flow.
Resp.: ACCEPT. Key modified.
6.06.b. Accepttomaintainshutdowncoolingwhile'liriingupother RHR train to safeguard mode to satisfy mode 4 Tech Specs.
Resp.: ACCEPT. Key modified.
6.07.a. Accept alternate answers per ALR-00-079C, attached.
Resp.: ACCEPT. Key modified.
6.07.c. The P/A converter is frequently called the " PULSER."
Resp.: ACCEPT. Key modified. ,,
6.08 -Accept steam generator low-low: level due~to shrink effects.
Resp.: REJECT. No reference provided. Analysis indicates this may not occur due to preexisting steam gene'rator conditi.ons.
6.10 Reference error. Corrected copy is attached.
Resp.: ACCEPT. Key modified.
6.11 Any CPIS will initiate CRVIS.
Resp.: ACCEPT. Key modified.
7.01 The question does not ask "why," so key should not require it. Question does not state that SHP approval has not been given, so accept assumption that it has. Limit is 500 mr for gestation period.
Resp.: ACCEPT. Key modified to allow full credit for proper answer with no explanation. If assumptions made and stated, allow full credit for answers correct for stated assumptions.
7.02 The generator is placed online before placing steam dumps in Tavg, blocking power range trips, or putting the feedwater reg valves in auto.
Resp.: ACCEPT. Key modified.
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5 7.03 Accept _ answers per'0FN-00-009 (#1 &.#3 of key wrong).
. Resp.: . ACCEPT. Key modified.
7.08.b. This is no longer a limit except Tech Spec is 583 deg's' F.
Resp.: ACCEPT. Question part deleted and other parts re-weighted.
8.05.c. Forms are kept under glass on SS desk, S0 desk, Shift Clerk desk, & any KG&E blue phone book.
Resp.: ACCEPT. Key modified.
8.07 Rev 12 adds "if all devices can be seen at the same time."
Resp.: ACCEPT. Key modified.
8.11.a Can also be addressed in a procedure if.it restores system to the proper configuration.
Resp.: ACCEPT. Key modified.
- b. OCTOBE+'. 8, 1986 EXIT MEETING
SUMMARY
At the conclusion of the site visit, the NRC examiners met with representatives of plant staff to discuss the site visit. The following personnel were present:
NRC KG&E J. Pellet H. Chernoff R. Cooley D. Fehr B. Bartlett J. Gilmore R. Guyer>
R. Hubbard G. Pendergrass
- E. Taylor J. Zell Mr. Pellet started the discussion by noting that the examiners as a group had encountered a positive, helpful attitude in everyone concerned. The following general topics were discussed.
(1) Due to the recent change in NUREG-1021, the Examiner Standards, preliminary results are no longer provided.
(2) NRC will attempt to return formal, final results within 30 days.
(3) Due to the small number of candidates exacined, no generic areas of weakness were observed.
(4) The pilot requalification program audit seemed to go well.
There were no obviously significant differences between the observed facility exams and NRC exams.
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6 (5) Examinations are tentatively scheduled in 1987 in June and October.
(6) The reference material provided for this examination was marginally acceptable. In the future, WCGS should provide either controlled copies, or, as a minimum, tabbed and indexed material organized similarly to controlled copies,
- c. GENERIC COMMENTS No generic comments were generated during grading of the written examinations or regional review of the oral examinations,
- d. REQUALIFICATION PROGRAM EVALUATION NRC conducted an audit of the WCGS Licensed Operator Requalification Training Program during this site visit. This audit was conducted in accordance with the pilot program documented in Enclosure 2 of the W. T. Russell, Director, DHFT, NRR to E. H. Johnson, Director, DRS&P, RIV memorandum, dated May 22, 1986 (copy attached, see 3.f.).
NRC reviewed the facility developed written examinations per the guidance contained in ES-601, Revision 2, and the facility requalification program learning objectives, concentrating on format, content, and length. The examinations fully met the appropriate standards in all areas.
NRC observed the administration on written requalification examinations during the site visit. Facility administration was fully in accordance with the appropriate standards.
Six examinations were parallel graded and two were reviewed in depth by NRC after facility grading. The facility and NRC grading were in very close agreement. Such close agreement also indicates that partial credit breakdowns were provided in the key as needed.
Facility grading was fully in accordance with the appropriate standards.
For the written examinations observed and reviewed, all examinees performed satisfactorily and all pass / fail decisions were fully justified. Therefore, the requalification written examinations conduct and performance are satisfactory.
Three operating examinations were observed by NRC certified examiners during the facility operating examination. In addition, five previously completed operating examinations were reviewed for documentation of areas covered and evaluation reliability.
7 The operating examinations observed and reviewed were fully satisfactory. However, in comparison with current NRC operating examinations, there appeared to be several differences that should be noted:
(1) Scenarios were more linear, or single track. Current NRC practice uses multiple failures concurrently, to assure that the operating crew, and especially the Shift Supervisor, can adequately allocate resources. The facility scenarios were less complex in this regard.
(2) Scenarios, with one exception, involved less severe transients than normally used in NRC scenarios. The one exception involved loss of both safeguards buses, concurrent with loss of the TD AFP. However, this was the only major failure that was complex.
RIV normally tries to challenge each crew with at least one transient that is extremely complex (e.g., steam generator tube rupture concurrent with loss of offsite power or SBLOCA).
(3) Most of the reviewed operating examinations had many more subject areas evaluated than required by the examiner standards.
(4) The facility examiners frequently asked questions of examinees that did not apply to the operations being performed by the crew, which acted as a distractor.
Several areas normally covered on most NRC operating examinations were covered on less than 20 percent of the facility operating examinations. These areas included:
(1) RADCON principles and practices, (2) Fuel Handling, (3) ESF surveillance testing, and (4) Event classi11 cation and Emergency Plan activation.
Also, several operating examinations contained substantive negative comments, that would be expected to require an unsatisfactory evaluation for at least the specific case in question, but all evaluation blocks on all operating examinations were evaluated as satisfactory, even if the described performance warranted otherwise.
These weaknesses found during review of the operating examinations are not considered to be substantive.
8 Fcn the operating exarninations observed and reviewed, all examinees performed satisfactorily and all pass / fail decisions were fully justified. Therefore, the requalification operating examinations conduct and performance are satisfactory.
In summary, the written and operating ~ requalification examinations observed and reviewed at WCGS. provide sufficient information to judge that the facility requalification program is satisfactory.
- e. EXAMINATION MASTER COPY Master copies (questions and answers) for the SR0 and R0 and license examinations follow the requalification program evaluation on the next page.
- f. ALTERNATE APPROACH TO REQUALIFICATION EVALUATIONS A copy of the above titled memorandum, from W. T. Russell, Director, DHFT, NRR to E. H. Johnson, Director, DRS&P, RIV memorandum, dated May 22, 1986, is attachad following the master copies of the examinations.
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1 e e OVERALL REQUALIFICATION PROGRAM EVALUATION Facility: Wolf Creek Generating Station Examiners: J. Pellet, R. Cooley, 1. Defferding Dates of Evaluation: October 7-8, 1986 Areas' Evaluated: XX Written XX Oral XX Simulator Written Examination Evaluation of NRC Examination Results (if given): Not Applicable Oral / Simulator Examination
- 1. Overall Evaluation: Satisfactory
- 2. Number Observed: 3 Number Conducted: 0 Overall Program Evaluation ;
Satisfactory: XX Marginal: Unsatisfactory:
REASON FOR EVALUATION The WCGS Licensed Operator Requalification Program evaluation was based on the pilot program as described in W. T. Russell memorandum to regional Division Directors. Evaluation consisted of: -
o Review of facility-developed written examination. Review was similar to one performed for a contractor-developed examination. The examination was found to be satisfactory, o Observation of the written examination administration by facility personnel, which was found to be satisfactory.
o Evaluation of the facility administered oral / simulator exaninations.
Review was similar to one performed when evaluating an NE or contractor examiner. All were found to be satisfactory, o The written examinations were observed above were graded concurrently with the facility, and the results were compared. In addition, two exams were administered prior to the site visit, so the facility grading was reviewed, similar to the review for an NRC administered examination. All results were in close agreement.
Submitted: Forwarded: Approved:
$am nerON h' Sect / ion Chief H r
' Branch Chief i (/
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U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _WQLE_GBEEK______________
REACTOR TYPE: _EWR-WEQ3________________
DATE ADMINISTERED:_D6/1D/DZ________________
EXAMINER: _EELLEIt_Ji______________
CANDIDATE: _________________________
INSIBUCIl0N5_IQ_C8NQlD81El Uco separate paper for the answers. Write answers on one side only.
Stcple question sheet on top of the answer sheets. Points for each qu0stion are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at locst 80%. Examination papers will be picked up six (6) hours after tho examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__V8LUE_ _IQI8L ___SCQBE___ _Y8LUE__ ______________G81EEQBl_____________
_25tDD__ _2520D ___________ ________ S. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS
_2520D__ _25200 ___________ ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
, _25tDQ__ _25tDD ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL i '
_25tDD__ _25100 ___________ ________ 8. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS IQQtDQ__ ___________ Totals Final Grade 4
All work done on this examinat, ion to my own. I have neither given
, nor received aid.
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Candidate's Signature i
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or- possibility of cheating.
- 3. Use black ink or dark pencil 90lY to facilitate leg ib le reproductions.
- 4. Print your name in the blank provided on the cover sheet of the oxamination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of gash 1 section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as cppropriate, start each category on a Dgg page, write 2DlY 20 202 Eidt of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least ibtgg lines between each answer.
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- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility 111gtgiurg.
, 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the REamiDRE only.
- 17. You must sign the statement on the cover-sheet that indicates that the work is your own and you have not received or been given ass is t anc e in completing the examination. This must be done after the examination has been completed.
- , _ . , , - - . . - . . , - , , - -,,,--,m,,, -
..-mr, . , - . _ . , ..m.
- 18. When you complete your examination, you shall:
0.- Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
'St__IBE98Y_9E_N9GLE88_E9 WEB _EL6NI_9EEBoIIQNt _ELUIQ3t_68Q PAGE 2 IHEBdQQ1N8dICS QUESTION 5.01 (2.50)
How would the Estimated Critical Position (ECP) calculated for a startup to bo performed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a trip from 100% power differ from the Actual Critical Position (ACP) for each of the following events. Consider each independently. Limit your answer to ECP is HIGHER, LOWER, or SAME as ACP.
- c. The fourth coolant pump is started _two minutes before criticality.(0.5)
- b. The startup is delayed until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the trip. (0.5)
- c. The steam dump pressure setpoint is increased to a value just below the Steam Generator PORV setpoint. (0.5)
- d. Condenser Vacuum is reduced by 4 inches of mercury. (0.5)
- o. All Steam Generator levels are rapidly being raised by 5% while approaching criticality. (0.5)
QUESTION 5.02 (2.50)
- c. What power distribution limit is observed at Wolf Creek to prevent exceeding the fuel temperature limit. (0.5)
- b. If the fuel temperature limit is 4700 deg's F and the cladding temperature is 2200 deg's F, what limit must be observed to prevent exceeding the cladding temperature limit when the fuel temperature is above 2200 deg's F? (0.5)
- c. What controls fuel rod surface temperature AND why does it peak towards the top of the core? (1.5)
QUESTION 5.03 (3.00)
The reactor is at 100% power with equilibrium xenon and all rods out when the boron concentration is reduced, causing a deep insertion of control rod bcnk 0 to maintain Tave constant. Describe how the axial core power distribution will change WITH TIME as a result of this action.
ASSUME NO FURTHER ROD MOTION. (3.0)
(***** CATEGORY 05 CONTINUE 0 ON NEXT PAGE *****)
.it__IBE981_DE_NUGLE88_EQWEB_EL8HI_9EEB8IIONt_ELUIQSt_8NQ PAGE 3 18E85001N851G3
~ QUESTION 5.04 (1.50)
State how (MORE negative, LESS negative, or NO EFFECT) each of the following will affect the Moderator Temperature Coefficient? No oxplanation is required.
- o. The charging pump suction is switched to the Refueling Water Storage Tank. (0.5)
- b. The core ages from BOL to EOL. (0.5)
- c. The RCS is cooled down from 550 deg's F to 450 deg's F. (0.5)
QUESTION 5.05 (2.00)
During a natural circulation cooldown:
- o. Why is the cooldown rate limited? (1.0)
- b. What is the reason for the RCS maximum pressure limit? (0.5)
- c. What is the reason for the RCS minimum pressure limit? C0.5)
QUESTION 5.06 (1.50)
If DNB occurs in the core, where is it most likely to occur, and WHY? (1.5)
QUESTION 5.07 (3.00)
- c. Why does a single RCP pump running during hot shutdown draw more motor emperage than when one of four running at power? (0.75)
- b. Why does a RCP running at cold conditions draw more motor emperage than at hot conditions? (0.75)
- c. Why is RCP motor emperage higher when starting the pump than when running? (0.75)
- d. Why should operating a pump with too much flow and no discharge pressure be avoided? (0.75)
(***** CATEGORY 05 CONTINUED ON NFXT PAGE *****)
St__IHE0BY_DE_ NUCLE 88_EQWEB_ELeNI_QEEB8IIONt_ELVID$t_8NQ PAGE 4 IHEB5001NedICS QUESTION 5.08 (2.00)
- c. How does chemical shimming (Boron control) help reduce local temperatures and hot channel factors in the core? (1.0)
- b. How AND why does boron differential worth change with Tave? (1.0)
QUESTION 5.09 (2.00)
- c. Which is larger, the fraction of fission neutrons born delayed (beta) f rom thermal f ission of U-235 and Pu-239, or the fraction from the fast fission of U-2387 (0.5)
- b. From BOL to EOL, does the average delayed neutron fraction increase, decrease, or remain the same? (0.5)
- c. For POSITIVE reactivity additions, will the startup rate be faster, slower, or the same at BOL as compared to EOL7 (0.5) ,
- d. For NEGATIVE reactivity additions, will the period be longer,-shorter, or the same at BOL as compared to EOL? (0.5)
QUESTION 5.10 (3.00)
Explain how each of the parameters listed are affected by the transients bolow. Continue your answer until stable conditions are achieved. Assume rod control in manual, no operator action, no protective function cctuations, and EOL conditions. Values are NOT required.
- c. One steam dump valve fails open with the reactor critical below the point of adding heat. (1.5)
- 1. Tavg.
- 2. Tfuel.
- 3. Reactor Power.
- b. One control rod drops at 50% power with turbine in automatic. (1.5)
- 1. Tavg.
- 2. Tfuel.
- 3. Reactor power.
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
St__IHE0BI_9E_NMCLE88_E9 WEB _ELeNI_9EEBoIIQNt_ELMIQS t_8NQ PAGE 5 IHEBdQQ1NedICS QUESTION 5.11 (1.50)
Explain how it is possible to be adequately subcooled with accurate pressurizer level indication and still f orm a steam bubble in the vessel hoad during natural circulation cooldown. (1.5)
QUESTION 5.12 ( .50)
Ansume a steam bubble has formed in the reactor vessel head as a result of dopressurization during a natural circulation cooldown and the RCS has been repressurized per procedures. Which of the following statements is most correct about the steam bubble in the head after repressurization? (0,5)
- c. The steam will condense (change phase) due to the pressure increase.
- b. The steam temperature will increase due to the pressure increase.
- c. The steam quality will decrease due to the pressure increase,
- d. The steam enthalpy will remain constant during the pressure increase.
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(***** END OF CATEGORY 05 *****)
62__EkeNI_111IEMS_DE11GNt_G9 NIB 9Lt_8NQ_IN11BudENIeIIQN PAGE 6 QUESTION 6.01 (3.00)
O. What is the normal atmosphere inside the Pressurizer Relief Tank (PRT)?
Why is this atmosphere maintained? (1.0)
- b. When relieving pressurizer safety valves into the PRT, what are two design features that ensure the safe operating pressure of the PRT is not exceeded? (1.0)
- c. What are 2 methods available to cool the PRT and what is the ADVANTAGE of one method? (2 methods and advantage of 1 for full credit) (1.0)
QUESTION 6.02 (2.50)
- c. What is one preparatory operator action required prior to automatic switchover to RHR Cold Leg recirculation? (0.5)
- b. The RHR pumps must be stopped during a manual switchover to prevent loss of pump suction. Why is this necessary? (1.0)
- c. How can an "AUT0" switchover be prevented? (0.5)
- d. How is continued flow assured during manual switchover? (0.5)
QUESTION 6.03 (2.00)
MATCHING. Match each of the areas below with the appropriate type of fire protection. (2.0)
AREA TYPE OF FIRE PROTECTION
___ a. Diesel Fire Pump Room 1. Halon 1301 system
___ b. Cable Spreading Rooms 2. Wet-pipe sprinkler system
___ c. Puel Oil Storage Tank 3. Water spray system
___ d. Auxiliary Boiler Room 4. Preaction sprinkler system
___ e. ESF Switchgear Rooms 5. Foam system
- f. Diesel Generator Rooms
___ g. Computer Rooms
___ h. Turbine Driven Aux. Feed Pump
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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62__PL8NI_SI11EN3_DE310Nt_QQNIBQLt_8NQ_IN$IRUNENI8IIQN PAGE 7 1
QUESTION 6.04 (2.00)
For the following components, indicate whether they will receive an OPEN, CLOSE, or N0 signal upon a manual safety inj ect ion initiation.
- c. Control Room outside air isolation valves (0.2)
- b. Main Feedwater bypass valves (0.2)
- c. Cold Leg Accumulator isolation valves (0.2)
- d. Charging header isolation valves (0.2)
- o. Main steam isolation valves (0.2)
- f. RWST to centrif ugal charging pumps suction valves (0.2)
- g. RCP seal water return isolation valve (0.2)
- 1. CCW isolation valve from letdown heat exchanger (0.2)
- j. Steam supply valves to turbine-driven AFW pump (0.2)
QUESTION 6.05 (2.50)
- n. Explain how and why Auxiliary Feedwater flow is limited. (1.5)
- b. Explain how the Auxiliary Feedwater System (AFW) can be considered a safety system when it's normal water supply is not considered to be a safety related component. The answer should include specific conditions that act to ensure adequate AFW flow in the event that the normal source is lost. (1.0)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
Et__ELANI_SISIEUS_DESIGNt_GQNIBQLt_oND_INSIRUNENI611QN PAGE 8 QUESTION 6.06 (2.50)
- e. In order to supply Safety Injection or Centrifugal Charging pump suction from the RHR pumps, at least two (2) flow paths must be isolated to satisfy interlocks. State the flow paths or interlocks AND explain why isolation is necessary. (1.5)
- b. During plant startup, the RHR pumps are stopped but one train is left in service until RCS pressure is increased. Explain why this lineup is necessary. (1.0)
QUESTION 6.07 (2.00)
- c. What are 2 of the 3 conditions that may cause a " Computer Rod Deviation" alarm? (0.75)
- b. What 2 signals are compared to provide a " Rod Position Indication" deviation alarm? (0.5)
- c. Explain how the Rod Insertion Limit Computer Comparator receives the actual rod position for compar ison to the limit. (0.75)
QUESTION 6.08 (1.00)
If the reactor trip due to turbine trip fails to actuate, what are two other Reactor Protection System trips that would cause a reactor trip?(1.0)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
Et__EkeNI_SISIENS_QESIGNt_CONIBQLt_8NQ_INSIBMMENIeIIQN PAGE 9 QUESTION 6.09 (2.50)
- c. What is the purpose of the Rod Control System DC Hold Cabinets? (1.0)
- b. In the Rod Control System, there are the same number of Slave Cyclers as there are: (Choose the most correct answer below.)
- 1. Control Rods
- 2. Logic cabinets
- 3. Rod groups j
- 4. Power cabinets (0.75)
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i c._ The Bank overlap unit decides which control rods.to move utilizing direct input from: (Choose the most correct answer below.)
- 1. Slave Cyclers
- 2. Step counters
- 3. Master cycler
- 4. P/A converter (0.75)
QUESTION 6.10 (2.50) ;
) While performing a surveillance on the Emergency Diesel Generator, with the diesel tied on the bus and partially loaded;
- c. How would the diesel generator respond to a LOCA actuation signal?(1.5)
- b. How is starting air blocked or disabled in this condition? (1.0) 4 QUESTION 6.11 (2.50)
- e. What are 5 specific conditions that place the control room heating, ventilating, and air conditioning system into the emergency mode of operation? Setpoints are NOT required. (1.5)
- b. Describe how the control room atmosphere is maintained habitable during accident conditions. (1.0) l I
(***** END OF CATEGORY 06 *****)
.Z2__EBOCEQUBE1_ _NQBMeLt_8BNQBUekt_EMEBGENGl_8NQ PAGE 10 BeQIQLDSICAL_GQNIBQL -
~ QUESTION 7.01 (3.00)
Hcs a Wolf Creek administrative limit or control on exposure been exceeded?
Consider each case separately.
- o. A minor enters the Radiation Controlled Area (RCA) and receives NO exposure. (1.0)
- b. A pregnant woman enters the RCA and receives a dose of 25 mr. (1.0)
- c. An individual receives in the weeks noted the following exposure: (1.0)
June 17-23: 225 millireme (mr)
June 24-30: 250 mr July 1-7: 200 mr July 8-14: 225 mr July 15-21: 175 mr July 22-28: 225 mr Total dose for 6 weeks in question: 1300 mr QUESTION 7.02 (1.50)
Arrange the following events in order of occurrence during a startup from hot standby to minimum load.
- a. Block Power Range Low Power trips
- b. Place the Turbine Generator on the line.
- c. Place Main Feedwater Pump Turbine Speed controls in auto.
- d. Block the Source Range Flux Doubling Transfer trip.
- e. Start one Main Feedwater Turbine Pump
- f. Block the Source Range High Flux trip.
- g. Place the Steam Dum,p Mode Controller in Tavg mode.
- h. Place the Main Feedwater Control Valve Bypass Valves in manual and increase Steam Generator level to 55-65%.
QUESTION 7.03 (2.50)
List five conditions that require immediate boration. (2.5)
(***** CATEGORY 07 CONTINUE 0 ON NEXT PAGE *****)
Zm__EBQQEQUEES_=_NQBd8kt_8ENQBd8Lt_EMEBGENQX_8NQ PAGE 11 B8DIDLQQIQ8L_QQNIBQL QUESTION 7.04 (2.50)
- e. Which critical safety function has the-top priority? (0.5)
- b. What is the purpose of a Functional Restoration Guide? (1.0)
- c. What action is required for a red symbol in a status tree? (1.0)
QUESTION 7.05 (2.00)
For each of the four parameters below, describe how they should respond if natural circulation flow exists as per ENG ES-03 (SI TERMINATION). (2.0)
- e. Core exit thermocouples.
- b. Steam Generator pressures,
- c. RCS hot leg temperatures.
- d. RCS cold leg temperatures.
QUESTION 7.06 (1.00)
For a dropped control rod, Tave/ Tref mismatch is initially maintained by tcking manual control of which of the following?
- a. turbine load.
- b. individual control rod banks.
- c. individual control rod groups,
QUESTION 7.07 (2.50)
- e. What action is required by the RO before leaving the control room if the control room must be evacuated with the reactor at power? (1.0)
- b. How does the RO obtain guidance for immediate and followup actions to be performed after leaving the control room? (0.75)
- c. What must the R0 have in his possess ion when the control room is evacuated? (0.75)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
l
-Zi__EBQGEQUBES_=_NQBU8Lt_8HNQBM8Lt_EUEBQENQ1_8NQ PAGE 12 E8DIQLQQIG8L_GQNIBQL QUESTION 7.08 (2.50)
Ccmplete the following statements utilizing information found in the Plant Heatup procedure (GEN 00-002).
- c. For normal heatup of the pressurizer, a rate of _______ deg's F/ hour will not be exceeded. (0.625)
- b. Spray flow into the pressurizer will NOT be initiated if the temperature difference between the pressurizer and spray fluid exceeds
_______ deg's F. (0.0)
- c. At least one Reactor Coolant Pump should be in operation before RCS temperature exceeds ________ deg's F. (0.625)
- d. Heatup must be terminated or spray initiated if pressurizer boron concentration approaches ________ ppm less than RCS loop conc. (0.625)
- o. When RCS temperature narrow range indication is off-scale, RCS temperature is determined by the _________ (HIGHEST or LOWEST) reading of the wide range temperature indications. (0.625)
QUESTION 7.09 (2.50)
Por the Radiation Protection Manual (WCHP-01) and 10CFR20:
- a. Every effort should be made to maintain weekly exposure as far below what level as practicable? (0.5)
- b. Health Physics should be informed of any unplanned weekly exposure greater than what level? (0.5)
- c. What is the 10CFR20 whole body exposure limit, per quarter? (0.5)
- d. TRUE or FALSE? Exposures during medical treatment must be reported to Health Phys ics for inclusion in dose calculations. (0.5)
- e. TRUE or FALSE 7 A " Calendar Quarter" is defined as any time period consisting of 13 consecutive weeks within a calendar year. (0.5)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
Zt__EBOCEDUBE1_=_NQBd8Lt_8BNDBd8Lt_EMEBGENCY_8NQ PAGE 13 BaQIQLQGIG8L_GQNIBQL QUESTION 7.10 (2.00)
What is the exposure rate at which posting is requ8ced for each of the creas listed below, as defined in the Radiation Protection Manuul?
- o. Clean Area (Maximum exposure rate-from fixed contamination). ( 0. 5)-
- b. Radiation Area. (0.75)
- c. High Radiation Area. (0.75)
QUESTION 7.11 (1.50)
What are three of the four ways to identify a ruptured Steam Generator per Emergency Procedure EMG E-3, " Steam Generator Tube Rupture"? (1.5)
QUESTION 7.12 (1.50)
List three of the conditions which require an immediate shutdown of a CCP per the Chemical and Volume control System startup procedure. (1.5)
(***** END OF CATEGORY 07 *****)
Si__8DDINIIIB8IIVE_EB9CEDWBEft_G9NDIIIONit_eNQ_LINIIeIIQN1 PAGE 14 e
1 QUESTION 8.01 (3.00) i
- c. Explain how the barrier model is used in the emergency classification procedure. (1.0)
! b. Classify each of the events below, BASED on the barrier model. (2.0) 4
- 1. During refueling, a spent fuel element is dropped into the reactor vessel and substantial fuel damage in confirmed. This is confirmed by increasing indications on the containment radiation monitors.
- 2. A design basis main steam line break occurs INSIDE containment.
f QUESTION 8.02 (2.50) 1 c. What are four (4) responsibilities of the Outy Emergency Director (DED) that CANNOT be delegated? (2.5) 1 2
QUESTION 8.03 (2.50) i The Shift Supervisor may authorize action that departs from a license
! condition or technical specification in an emergency.
- a. Under what two (2) conditions is the above statement true? (2.0)
- b. TRUE or FALSE. Notification to the NRC MUST be made PRIOR to taking any such action. (0.5) l
- QUESTION 8.04 (2.00)
! What are the two methods by which the requirement for independent i vorification may be satisfied? (2.0) 1 I
l (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
A2__8051NISIB8IIVE_EBQQEQUBESt_QQNQIIIQN2i_8NQ_LINII8IIQN1 PAGE 15 QUESTION 8.05 (3.00)
If you answer the phone in the control room and it is a bomb threat:
- a. What are three questions you should attempt to ask the caller? (1.5)
- b. What are three OTHER specific pieces of information you should try to determine about the event? (1.0)
- c. Where in the control room are the bomb threat forms located? (0.5)
QUESTION 8.06 (1.50)
- c. What is the reactor coolant Pressure Safety Limit setpoint? (0.5)
- b. What must be done to satisf y Technical Specif ications if it is exceeded at power? (Administrative Tech Spec requirements NOT required.) (1.0)
QUESTION 8.07 (2.00)
- c. When may a Clearance without a ONO Tag be authorized? (1.0)
- b. When is it appropriate to consider using this kind of Clearance? (1.0)
QUESTION 8.08 (2.00)
Briefly outline the duties and responsibilities of the Shif t Supervisor for Post Trip Review as set forth in ADM 02-400.
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
Bi__8061N11IBeIIVE_E80GEQUBElt_GQNDIIIONit_eWQ LIMIIeI1QN1 PAGE 16 QUESTION 8.09 (2.50)
In the event of a plant emergency requiring implementing the Energency Plan, who, by title:
- o. Initially assumes the duties of the Outy Emergency Director? (0.5)
- b. Can relieve the Duty Emergency Director (Both Titles)? (1.0)
- c. Initially assumes the responsibilities of the Operations Emergency Coordinator? (0.5)
- d. Is the normal relief for the Operations Emergency Coordinator? (0.5)
QUESTION 8.10 (2.00)
What is the general responsibility of the Shift Supervisor for Technical '
Specification Surveillance Testing in the below listed specific areas?
l O. Pre-test responsibility. (1.0)
- b. Post-test with unsatisfactory results. (1.0)
. QUESTION 8.11 (2.00) i
- c. When may a temporary modification be made to a system without issuing a Temporary Modification Order or hanging Temporary Modification Tags? (1.0)
- b. How often must outstanding Temporary Modifications be reviewed? (1.0)
I
{
i I
(***** END OF CATEGORY 08 *****) l
, (************* END OF EXAMINATION ***************) i i
St__IHEQBI_QE_NUGLE68_EDWEB_EL8NI_9EEB8IIONt_ELUIDSt_8NQ PAGE. 17 IHEBdQQ1NedICS ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 5.01 (2.50)
REFERENCE WC Rx. Theory, Pg. 238-241 ANSWER 5.02 (2.50)
- c. Loc Pwr Dens (KW/FT) OR FQ(z). (Full credit for description of how operator maintains non-observable limits in specification end 1/2 -
credit for any power distribution limit.) (0.5)
- b. OND or DNDR (accept either answer) (0.5)
- c. Fuel surface temperature is a function of both heat flux (0.S) and coolant temperature (0.5). Moderator temperdture is h ig h e r- et the top of the core (0.5). (1.5)
REFERENCE WC Thermal-Hydraulics Ch. 13, Pg. 8,9,20,27 ANSWER 5.03 (3.00) l l Rod insertion causes flux shift towards bottom of core (0.5). With time, nonon buildup in top of core due to less burnout and xenon reduction
- in bottom of core due to increased burnout causes flux to shift towerde the bottom of the core even more (1.0). Later, xenon butidup in bottom of the l
core due to increased production and xenon reduction in top of the core due l to xenon decay causes a flux swing towards the top of the core (1.0).
l These feedback effects between xenon and power result in on axiil power occillation (0.5). (3.0)
- St__IHEQBl_QE_NUGLE88_EQWEB_EL8NI_QEEB811QNt_ELQlD$t_8NQ PAGE 18 IHEBBQQ1NedICS ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
REFERENCE WC Rx. Theory Pg. 272,273 ANSWER 5.04 (1.50)
- a. LESS NEGATIVE. (0.5)
- b. MORE NEGATIVE. [0.5)
- c. LESS NEGATIVE. (0.5)
REFERENCE WC Reactor Theory, Pg. 177-180 ANSWER 5.05 (2.00)
- e. Head cooldown is limited in nat. cire. (0.5) so rate limit is to avoid head voiding (0.5). (1.0)
- b. Preclude brittle fracture / preserve RCS integrity. (0.5)
- c. Maintain subcooling (voiding) / DN8. (0.5)
REFERENCE WC QB HT-N8 ANSWER 5.06 (1.50)
DNB is most-likely to occur where power density is high (0.5) and tcmperature is approaching Tsat (0.5). This is most likely to occur in the upper half (6*9 feet up the core) &/OR center of the core (0.5). (1.5)
REFERENCE l WC QB HT-M8
. . s' ,
4 Si__IHE981_9E_NUGLE88_E9 WEB _EkeNI_9EEB8II9Ni_ELVIQ1t_8NQ PAGE 19 IHEBdQDINedICS ANSWERS 1-- WOLF CREEK -86/10/07-PELLET, J.
4 h,
ANSWER 5.07 (3.00)'.
- c. A single pump running has a higher flow than when all 4 are operating (due to reduced discharge pressure) so more work is done and more emperage drawn. (ACCEPT CONCEPT.FOR ALL PARTS) . (0.75)
- b. At cold conditions, fluid density is higher,. so more mass is moved so more work is done and more emperage drawn. (0.75)
- c. It'must accelerate more mass, which requires more work, and amps.(0.75) ,
- d. Operating at runout may cause pump demage/ trip on overcurrent. (0.75)
REFERENCE WC QB HT-J24 ANSWER .5.08 (2.00)
- c. Boron allows ARO operation, which yields a flatter (axial) flux profile, which reduces local temp. and hot channel factors. (1.0)
- b. BDW is less negative for higher values of Tave, due to the density decrease removing boron from the core. (1.0)
REFERENCE WCGS Reactor Theory Student Handout, p. 224, 225 ANSWER 5.09 (2.00)
- a. From U-238.
- b. Decreases, e
- c. Slower.
- d. Same. (4 answers e 0.5 ea.)
REFERENCE WCGS RQ EXAM LR 00 986 00, 05.01 i
- -- , _ , . , ~ . . , , - - ..- - - . m- , ~ - , r . ..r-, - . - - - . _ . - . , - < - -
-Si__IHEQBY_QE_NUQLE88_EQWEB_EL8HI_QEEB6110Nt_ELUIDSt_8NQ PAGE 20 IHEBdQDINedICS ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 5.10 C3.00)
- a. 1. Tavg decr on excess steam flow until rx pwr incr to match sim.
- 2. Tfuel incr from POAH to turn power.
- 3. Power will incr to match steam flow. (3 answers e 0.5 ea.)
- b. 1. Tavg will decrease to correct the power mismatch. (0.5)
- 2. Tfuel will decr near the dropped rod & incr. elsewhere. (0.5)
- 3. Rx pwr will decr pn rod then iner on MTC, ending at same value.
(Local pwr will be lower near rod & higher away.) (0.5)
REFERENCE WCGS RQ' EXAM LR 00 986 00, 05.05 ANSWER 5.11 (1.50)
During nat. cire, cooldown, bypass flow is minimal (0,5). Therefore, the water in the upper head is decoupled frm the cooldown of the RCS (0.5).
When this occurs, water (a metal) in the upper head may stay warm enough to flash to steam when the RCS is depressurized, even though the bulk temperatures in the '.C S are cool (0.5).
(CONCEPT) (1.5)
REFERENCE WCGS RQ EXAM LR 00 986 00, 05.08 ANSWER 5.12 ( .50) b REFERENCE WCGS RQ EXAM LR 00 986 00, D.5.09 l ,
I i
62__ELeNI_SISIEUS_DESIGNt_G9NIBQLt_8NQ_INSIBudENI8II9N PAGE 21 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 6.01 (3.00)
- e. Nitrogen (0.5), to prevent inleakage of air and accumulating a mixture of hydrogen and oxygen (0.5)
- b. PRT relief is discharged through a sparger, underwater. (0,5)
The rupture disk bursts before the design pressure is exceeded. (0.5)
- c. 1. Spraying with cool reactor makeup water. (0.33)
- 2. Circulating water through the RCOT HX. (0.33)
Accept either for advantage;
- 1. Spraying is much quicker; OR
- 2. Recircing does not generate waste. (0.34)
REFERENCE NPS 215 Ch. 3 Pg. 26,27 ANSWER 6.02 (2.50)
- e. Accept any one of the following:
- 2. Check RWST level.
- 3. Check Sump level. (0.5)
- 4. Verify AC power available as required.
- b. An interlock (0.5) prevents opening the containment sump valve with the same side RWST valve open (0.5). (1.0)
OR rack out the power to the appropriate breakers.
- d. By switching over only one train at a time. (0.5)
REFERENCE WC ECCS, Pg. 43,44; EMG-ES-11, p. 10 i
6t__EL8MI_SISIEdi_DE11GNt_CONIB9Lt_8ND_INSIBudENI8IIQN PAGE 22 ANSWERS -- WOLF-CREEK -86/10/07-PELLET, J.
ANSWER 6.03 (2.00)
- c. 2, b. 3, c. 4&5, d. 2, e. 1, f. 4, g. 1, h. 3 (8 answers e 0.25 es.)
REFERENCE SNUPPS NPS-229, p. 2 2-18 ANSWER 6.04 (2.00)
(;.2 0 pts each)
- e. CLOSE
- b. CLOSE
- c. OPEN
- d. CLOSE
- o. N0
- f. OPEN
- g. CLOSE
- h. NO
- i. NO
ANSWER 6.05 (2.50)
- a. The feed lines to each S/G contain orifice flow restrictors that function to: (0.5)
- 1. Limit containment pressure on a steam rupture. (0.33)
- 2. Limit pressure drop on Aux. Feed in case of a feed line break. (Assure flow to intact loops.) (0.33)
- 3. Limit pump runout. (0.33)
(Plus MDAFWP dis, valves throttle to limit ficw - NR FC)
- b. ESW serves as a backup supply (0.5) that will be automatically provided if an AFAS exists (0.25) and suct. pressure is low (0.25). (1.0)
6t__ELeNI_SYSIEUS_DE110Nt_GQNIBQLt_eND_INSIB95ENIeIIQN PAGE 23 g; ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 6.06 (2.50)
- e. Flow paths: 1. RHR hot leg suction.
t 2. SI Pump recirc to RWST (0.35 ea.)
Reasons: 1. Prevent overpressurization of SI and CCP suctions.
- 2. Prevent recirculation of radioactive water through SI Pump miniflow lines. (0.4 ea.) (1.5)
- b. To provide adequate letdown flow (0.5) and maintain purification flow rate. (0.5) (1.0)
OR to satisfy TS ECCS mode 4 requriements.
REFERENCE LP, RHR, p. 12,16 ANSWER 6.07 (2.00)
- a. 1.. Control bank D out of sequence.
- Bank D > 220 steps.
- 2. S/D bank out of sequence.
- 3. Power range flux tilt.
- Lower / upper +/- 2% f[om average.
- Any channel +/- 2% from average.
- 4. Rod deviation.
- Any rod +/- 12 steps from bank average.
- Any rod +/- 12 steps from bank demand.
- 5. S/D bank <18 or >220 steps.
- 6. NSSS computer malfunction or failure. (Any 2 0 0.375 es.)
- b. Bank demand position (0.25), and individual DRPI (0.25) (0.5)
- c. A pulse / analog convertor (PULSER) gets same signal as the step counters (0.375). The convertor converts these pulses to an analog output proportional to bank position (0.375). (0.75)
REFERENCE NPS 227, Ch. 3, Pg. 11-13 ANSWER 6.08 (1.00)
- 1. High RCS Pressure.
- 2. Overtemperature delta T.
- 3. High pressurizer level. (Any 2 8 0.5 each) i I
. _ . _ _ _ . - - _ .. .. _.- ___ . . . . _ _ , , _ . _ _ . _ _ _ _ . _ . ._. , . ~ . . . . . . . . _ _ _ _ _ _ _ _ .
6t__fL8HI_SISIEd1_DESIGNt_C9 NIB 9Lt_8NQ_INSIBMdENI8IIQN PAGE 24 ANSWERS ---WOLF CREEK -86/10/07-PELLET, J.
REFERENCE NPS 227, Ch. 5, P. 22 ANSWER 6.09 (2.50)
- c. Provide power to the stationary gripper coils of any 1 rod group. (1.0)
- b. 4. (0.75)
- c. 3 -
(0.75)
REFERENCE LT, RCS, p. 18,21 ANSWER 6.10 (2.50)
- o. 1. DG output breakers open.
- 2. Loads shed.
- 3. LOCA sequencer loads vital loads (3 8 0.5 ea. - 1.5)
(1 DG runs in standby if offsite available.)
- b. When EDG engine speed is grestrer than 85 rpm, the air start solenoid gets a shut signal. (1.0)
REFERENCE WCGS RQ EXAM LR 00 986 00, D6.03 ANSWER 6.11 (2.50)
- c. 1. Chlorine 5. CIS "A" 8. Any other CPIS
- 2. Control rm. gas, act. 6. Cont. purge hi gas. act.
- 3. FB vent, isol. s ig . 7. Cont. atmos. hi gas. act.
- 4. SI Signal. (Any 5, 0.3 each) (1.5)
- b. Outside air is isolated and the system goes on internal recirculation (0.5). Simultaneously, the CR is pressurized with filtered air (0.5)
(tc prevent inleakage). (1.0)
REFERENCE NPS ?21, Ch. 4, Pg. 42,43
.Z2__ERQGEQUBES_=_N0Bd8Lt_8ENQBd8Lt_EMEBGENCY_8NQ PAGE 25 88D19LQQ198L_GQNIBDL ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 7.01 (3.00)
For each of the answers below, CONCEPT and understanding more important than whether a limit violated. Accept YES/NO for FC if no expl. given.
c.
~
YES, an administrative control has been exceeded (0.2). SHP approval is required for RCA-entry by a minor (0.8).
- b. YES, administrative control exceeded (0.2) because prior approval by SHP is required (0.8).
- c. NO, none violated; 'all < 250 mr/ week & 1300 mr/qtr (CALENDAR) (1.0)
REFERENCE ADM 03-005 ANSWER 7.02 '(1.50) d, f, h, e, b, a, c, g There are seven arrangement shif ts possible for the worst case. Each shift in worth 0.214 pts when the minimum number of shifts are made to achieve the correct order.
REFERENCE WCGS GEN 00-003, REV 1 pgs 5-11.
ANSWER 7.03 (2.50)
- 1. Control rod height below the insertion limit.
- 2. >/= 2 rods fail to insert following a trip or shutdown.
- 3. Uncontrolled RCS cooldown.
- 4. Unexpected or uncontrolled reactivity increase.
- 5. Inadequate SOM. (0.5 each)
REFERENCE WCGS NPS 217-2,pg 38 i
i i
Z4__EBQGEQUBE2_:_NQBM8Lt_8ENQBd8Lt_EMEBQENCY_8NQ PAGE 26 88DIDLQQIQ8L_00NIBQL ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 7.04 (2,50)
- e. Sub:riticality. (0.5)
- b. Direct operator action (0.5) to recover / restore the degraded CSF (0.5)
(dependent on which CSF is challenged & extent of degradation). (1.0)-
- c. Operator should immediately stop ORG (0.5) and start FRG to restore the CSF under extreme challenge (0.5). (1.0)
REFERENCE WCGS ERGS ANSWER 7.05 (2.00)
, s. Core exit T/Cs - stable or decreasing. (0.5)
- b. S/G press. - stable or decreasing. (0.5)
- c. RCS hot leg temp. - stable or decreasing. (0.5)
- d. RCS cold leg temp. - at sat. temp. for S/G pressure. (0.5)
REFERENCE WCGS EMG ES-03, ATTACHMENT A ANSWER 7.06 (1.00) 8.
REFERENCE WC OFN 00-011,P.1 ANSWER 7.07 (2.50)
- a. Trip the reactor (0.5) and fast close the MSIV's (0.5) (1.0)
- b. Uses copy of 0FN (Appendix). (0.75)
- c. Keys for the emergency locker and security doors. (0.75)
REFERENCE WC OFN 00-017, P. 3 & ATT C.
Zi__EB0GEDVBE1_:_N9Bd8Lt_8BN9Bd8Lt_EMEBGENGI_8NQ PAGE 27
.B8DIDLQGIG8L_CQNIBQL.
ANSWERS -- WOLF CREEK -86/10/07-PELLET, J..
ANSWER 7.08 (2.50)
- c. '100
- h. Deleted per facility comments. No longer a reuquirement.
- c. 160
- d. 50
- o. highest (0.625 each for 2.5)
REFERENCE GEN 00-002, Pp.1-3 ANSWER 7.09 (2.50)
- e. 100 mrem.
- b. 300 mrem.
- c. 1.25 rem /qtr.
- d. False,
- o. False.- (5 answers e 0.5 es.)
REFERENCE WCGS RPM, Rev. 3, p. 6-6, 6-7, 6-8, 10CFR20 ANSWER 7.10 (2.00)
- c. 0.1 mR/hr above background. (0.5)
- b. Dose > 5 mrem /hr or 100 mrem in 5 days / 1 week. (0.75)
- c. Dose > 100 mrem /hr. (0.75)
REFERENCE WCGS Radiation Protection Manual, Rev. 3, p. 6-13, 6-14 r
J
+, - , , - , , . .--,-,,a -yw---v - - - - - , - - - - , , ~ - --------s-w-- -, - - -
)
Z2__EBOCEDVBES_ _NDBd8Lt_8BNQRd8Lt_EMEBGENC1_8NQ PAGE 28 B8DIQLQGIQ8L_QQNIBQL
= ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 7.11 (1.50)
- 1. Unexpected rise in SG 1evel.
- 2. High-turbine-driven AFW pump exhaust radiation.
- 3. High radiation from any SG' relief or safety plume monitor.
- 4. Check SG blowdown and sample not isolated. Cany 3/4 4 0.5 es.)
REFERENCE WCGS RQ EXAM LR 00 986 00, 7.02 ANSWER 7.12 (1.50)
- 1. Oil leaving thrust bearing high temperature (>160 deg's F).
- 2. Sudden drop in discharge pressure.
- 3. Loss of CCW (cooling) to a running pump.
- 4. Lube oil pressure drops (to'0). (any 3/4 4 0.5 ea.)
. REFERENCE WCGS RQ EXAM LR 00 986 00, 7.08
, . . . ,v.. - - -, , , , . - - , _ - - - . . _ , . . -----.----.---,----..,-y-- _ - _ , ----,.-,.,-.7
az__eDMINISIB6IIVE_PBQQgQUgggt_CQNQ1IlgNgt_8NQ_LINII8IlgNg PAGE 29 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 8.01 (3.00)
- b. 1. Alert. I fpb barrier breached by the event (1 by ops not incl.).
REFERENCE WC RERP, 2.2-2.4 ANSWER 8.02 (2.50)
- s. - Classification of emergency event
- Notification of of fsite emergency authorities
- Making protective action recommendations to offsite emergency authorities
- Authorization for emergency workers to exceed 10CFR20 radiation exposure limits (0.625 each)
' REFERENCE Radiological Emergency Response Plan, pg 1.2-3, Rev 15
' ANSWER 8.03 (2.50)
- e. - When this action is necessary to protect the health and safety of the public (1.0)
- No action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent (1.0)
- b. False (0,5)
REFERENCE ADM 02-003, Shift Supervisor Qualifications and Responsibilities, Rev 6, p9 3
l l
At__eQUINISIB8IIVE_EBQGEDMBESt_GQNQIIIONSt_8ND_LIMII8IIONS PAGE 30 l
'ANSWdRS -- WOLF CREEK -86/10/07-PELLET, J. l ANSWER 8.04 (2.00)
--Two appropriately qualified individuals shall independently verify the procedure step has been accomplished. (1.0)
- One verification without local observation may be performed using plant instrumentation, annunciators, valve position indicators, etc if the indication is a positive indication of the locking device position (CONCEPT). (1,0)
REFERENCE I ADM 02-102, Control of Locked Component Status, Rev 11, pg 2 ANSWER 8.05 (3.00)
- c. What kind of bomb is it?
Where is the bomb located?
When will it explode?
What does it look like?
Did you place the bomb?
Why?
What is your name?
What is your address? Cany 3 0 0.5 ea.)
- b. Caller's Sex, age, race, voice char., language used, background sounds, length of call, and number at which received. (any 3 e 0.33 ea.)
- c. 1. File cabinet by desk; OR
- 2. Book case in SS office. (Any answer G 0.5)
- 3. SS/SO/Cleark desk (under glass).
- 4. Any blue KGRE phone book.
REFERENCE WCGS ADM 10-004, REV 0, pg 3 FORM 1600-53 ANSWER 8.06 (1.50)
- a. 2735 psig. (0.5)
- b. Be in hot stdby with pressure within limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. (1.0)
(Admin TS are NOT reg'd for full credit. Accept if correct.)
- At__eD51NISIB811VE_EB00EQUBESt_G9NDIII9Nat_8ND_LIMII6IIQN2 PAGE 31 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
REFERENCE WCGS RQ EXAM LR 00 986 00, 8.07 ANSWER 8.07 (2.00)
- s. A Clearance without DNO Tag may be used for a job if all isolation devices can be monitored from a single location. (1.0)
- b. It would be used for jobs of a trouble shooting or adj usting nature which may require that a component be isolated or deenergized and then restored several times over a short period of time to allow for work and then test. (1.0)
(CONCEPT ONLY)
REFERENCE WCGS ADM 02-100, Rev 13, pgs 12, 13 ANSWER 8.08 (2.00)
DATA COLLECTION Hard copy information - logs, strip charts, computer readouts, etc.
Operator statements - written statements for all operators involved.
POST-TRIP INVESTIGATION Event reconstruction Comparison with similar past events An alys is and Evaluation Preliminary safety assessment Trip c lass if ic at ion Notifications (1.0 f or each major heading or partial credit for individual sub headings]
REFERENCE WCGS ADM 02-400, REV 1, pgs 4-8 i
Az__eQUINISIBeIIME_EBQGEQUBESt_GQNDIIIQNSt_eND_LIMII8IIQNS PAGE 32 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 8.09 (2,50)
- o. The Shift Supervisor (0.5)
.b. 1. The Plant Manager
- 2. The Call Superintendent (0.5 each) (1.0)
- c. The Supervising Operator (0,5)
- d. The Superintendent of Operations (or his designee) (0.5)
REFERENCE EPIP, ADM 12-1.2, pp 1,3 GLJ 120 ANSWER 8.10 (2.00)
- o. 1. Determine and attain proper plant conditions. (0.5)
- 2. Ensure performance is saf e. (0.5) (1.0)
- b. Document results (0.333), determine equipment operability (0.333) and reportability (0.333) (1.0)
. REFERENCE WC ADM 02-300, Pp.5,13 ANSWER 8.11 (2.00)
- c. Temporary Modification Orders / Tags are not required:
- 1. On hoses temporarily installed for venting, draining, or providing suppl gas for portable pneumatic equipment. (0.5)
- 2. For trouble shooting and equipment replacement when the activity is approved by the Shift Supervisor and the cognizant Group Supervisor and is completed without lengthy interruptions. (0.5)
OR when approved procedure addresses installation a removal of the mod.
(CONCEPT ONLY)
- b. Semi-annually (twice yearly) (1.0)
REFERENCE WCGS ADM 02-101, REV 11 pgs 2, 5.
TEST CROSS REFERENCE PAGE 1 s.
-QUESTION VALUE REFERENCE 05.01 2.50 JJP0001273 05.02 2.50 JJP0001274 05.03 3.00 JJP0001275 05.04 1.50 JJP0001276 05.05 2.00 JJP0001277 05.06 1.50 JJP0001278 05.07 3.00 JJP0001279 05.08 2.00 JJP0001280 05.09 2.00 JJP0001281 05.10 3.00 JJP0001283 05.11 1.50 JJP0001284 05.12 .50 JJP0001285 25.00 06.01 3.00 JJP0001013 06.02 2.50 JJP0001019 06.03 2.00 JJP0001286 06.04 2.00 JJP0001288 06.05 2.50 JJP0001289 06.06 2.50 JJP0001290 06.07 2.00 JJP0001292 06.08 1.00 JJP0001293 06.09 2.50 JJP0001294 06.10 2.50 JJP0001295 06.11 2.50 JJP0001287 25.00 07.01 3.00 JJP0001265 07.02 1.50 JJP0001296 07.03 2.50 JJP0001297 07.04 2.50 JJP0001298 07.05 2.00 JJP0001299 07.06 1.00 JJP0001301 07.07 2.50 JJP0001302 07.08 2.50 JJP0001303 07.09 2.50 JJP0001304 07.10 2.00 JJP0001305 07.11 1.50 JJP0001306 07.12 1.50 JJP0001307 25.00 08.01 3.00 JJP0001308 08.02 2.50 JJP0001309 08.03 2.50 JJP0001310 08.04 2.00 JJP0001311 08.05 3.00 JJP0001312 08.06 1.50 JJP0001313
TEST CROSS REFERENCE PAGE 2 QUESTION VALUE REFERENCE 08.07 2.00 JJP0001314 08.08 2.00 JJP0001315 08.09 2.50 JJP0001316 08.10 2.00 JJP0001317 08.11 2.00 JJP0001320 25.00 100.00 Y
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-,-----m- ,-eer , n , w----,, - ,, ,a- ~ , - , - - ..-,v-----m-,a ,_, -- - - - - --,-y- w, e-n , - . --
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U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _WQLE_QBEEK______________
REACTOR TYPE: _EMB-WEQd________________
DATE ADMINISTERED: _QQllD/DZ________________
EXAMINER: _EELLEIz_Jz______________
CANDIDATE: _________________________
INSIBUGIl0NE_IQ_G8NQlD81El Uno separate paper for the answers. Write answers on one side only.
Stcple question sheet on top of the answer sheets. Points for each qusstion are indicated in parentheses after the question. The passing grade requires at least 70% in each category and a final grade of at losst 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__V8LUE_ _IQI8L ___5GQBE___ _V8LUE__ ______________G81EQQBI_____________
_2520D__ _25tDQ ___________ ________
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
_25AQQ__ _25tDQ ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
_251DH__ _25200 ___________ ________ 3. INSTRUMENTS AND CONTROLS
_25100__ _2520Q ___________ ________ 4. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL IQQtDQ__ ___________
Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature
- -- , , - - . - , . . - - . . , . --, - ,-...,,-,,n , - . - -
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:
- 1. Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
- 2. Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of chaating.
- 3. Use black ink or dark pencil 201Y to facilitate leg ib le reproductions.
- 4. Print your name in the blank provided on the cover sheet of the examination.
- 5. Fill in the date on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
- 7. Print your name in the upper right-hand corner of the first page of gggb section of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a Dew page, write 2DlY 2D 202 Eldt of the paper, and write "Last Page" on the last answer sheet.
- 9. Number each answer as to category and number, for example, 1.4, 6.3.
- 10. Skip at least 1Drgg lines between each answer.
- 11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility 111grgigtg.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
- 14. Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
- 15. Partial credit may be given. Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examination are not clear as to intent, ask questions of the gggm1DRE only.
- 17. You must sign the statement on the cover sheet that indicates that the work is your own and you have not received or been given ass is t anc e in completing the examination. This must be done after the examination has been completed.
I
_ _ _ _ _ . _ _ . - - . ~ , _ . . , _ . . . , _ . . _ . _ .-. . _ , . _ _ . ___.__ ,___..m -_ _ _ _ _ _ . - _ ,
a
- 18. When you complete your examination,'you shall:
^
- c. Assemble your examination as follows:
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are.part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the. examination questions.
. c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while the examination is still in' progress, your license may be denied or revoked.
4 1
.. , - . _ . . _ . . _ - - . _ - - _ - - - - - - _ , _ . . . , . . _ . . - , . - . _ . , . , , , , _ _ _ _ . . . . . . ~ . - _ _ . . , . _ _ . , - - - - - , . _ . - - - , . . - , . -
'It__EBINGIELES_QE_NUGLE6B_EQWEB_EL8HI_QEEB8IIQNt PAGE 2 IHEBdQQ1N8MICSt_HEeI_IB8HSEEB_8NQ_ELUID_ELQW h
-QUESTION. 1.01 (2.50)
How would.the Estimated Critical Position (ECP) calculated for a startup to bo performed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after a trip from 100% power differ from the Actual Critical Position (ACP) for each of~the following. events. Consider each independently. Limit your answer to ECP is HIGHER, LOWER, or SAME as ACP.
- e. The fourth coolant pump is started two minutes before criticality.(0.5)
- b. The startup is delayed until 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after the trip. (0.5)
- c. The steam dump pressure setpoint is increased to a value just below the Steam Generator PORV setpoint. (0.5)
- d. Condenser Vacuum is reduced by 4 inches of mercury. (0.5)
- e. All Steam Generator levels are rapidly being raised by 5% while approaching criticality. (0.5)
QUESTION. 1.02 (2.50)
- a. What power distribution limit is observed at Wolf Creek to prevent exceeding the fuel temperature limit. (0.5)
- b. If the fuel temperature limit is 4700 deg's F and the cladding temperature is 2200 deg's F, what limit must be observed to prevent exceeding the cladding temperature limit when the fuel temperature is above 2200 deg's F? (0.5)
! c. What controls fuel rod surface temperature AND why does it peak towards the top of the core? (1.5)
QUESTION 1.03 ( .50)
Which of the following statements concerning the effects of the increase in Pu-237 and Pu-240 concentration over core life is correct? (0.5)
- o. The buildup of Pu-240 increases the average delayed neutron fraction.
- b. The buildup of Pu-239 decreases the core Reproduction factor.
- c. The buildup of Pu-239 causes the MTC to become more negative.
I
- d. The buildup of Pu-240 causes the Doppler Coefficient to become more negative.
(***** CATEGORY 01 CONTINUE 0 ON NEXT PAGE *****)
Iz__EBINGIELES_QE_NV9LE88_EQWEB_EL6NI_QEEB6IIQNt PAGE 3 IHEBdQDIN8dICSt_BE8I_IB8NSEEB_8ND_ELUID_ELQW QUESTION 1.04 (3.00).
The reactor is at 100% power with equilibrium xenon and all rods out when the boron. concentration is reduced, causing a deep insertion of control rod bank D to maintain Teve constant. Describe how the axial core power distribution will change WITH TIME as a result of this action.
ASSUME NO FURTHER ROD MOTION. (3.0)
QUESTION 1.05 (1.50)
State how (MORE negative, LESS negative, or NO EFFECT) each of the following will affect the Moderator Temperature Coefficient? No oxplanation is required.
- a. The charging pump suction is switched to the Refueling Water Storage Tank. (0.5)~
- b. The core ages from BOL to EOL. (0.5)
- c. The RCS is cooled down from 550 deg's F to 450 deg's F. (0.5)
QUESTION 1.06 (2.00)
.During a natural circulation cooldown:
- a. Why -is the cooldown rate limited? (1.0)
- b. What is the reason for the RCS maximum pressure limit? (0.5)
- c. What is the reason for the RCS minimum pressure limit? (0.5)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
'12__EBINCIELE1_DE_NUGLE88_EQWEB_EL8HI_DEEB8IIQNm PAGE 4 IHEBUDDIN8 DIG 1t_HE8I_IB8HIEEB_8NQ_ELUID_ELQW LQUESTION- 1.07- (2.00)
TRUE or FALSE?-
- c. A reactor power increase puts the plant FURTHER from DNB. (0.5)
'b. A pressurizer pressure decrease puts the plant'FURTHER from DNB. (0.5)
- c. A reactor coolant flow increase puts the plant FURTHER from DNB. (0.5)
- d. A cold leg temperature increase puts the plant FURTHER from DNB. (0.5)
QUESTION 1.08 (3.00)
- a. Why does a single'RCP pump running during hot shutdown draw more motor emperage than when one of four running at power? (0.75)
- b. .Why does a RCP running at cold conditions draw more motor emperage than-at hot conditions? C0.75)
- c. Why is RCP motor emperage higher when starting the pump than when running? (0.75)
- d. Why should operating a pump with too much flow and no discharge pressure be avoided? (0.75)
QUESTION .1.09 (2.00) a.- Why does fuel temperature increase and then decrease over core life, for a constant power output? ( 1. 5 ) .
- b. If reactor power is increased by deboration, which coefficient changes reactor power first: Moderator Temperature Coefficient or Doppler?CO.5)
QUESTION 1.10 (2.00)
- a. How does chemical shimming (Boron control) help reduce local temperatures and hot channel factors in the core? (1.0)
- b. How AND why does boron differential worth change with Tave? (1.0) 4 i
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
It__EBINCIELES_9E_NMGLE68_E9 WEB _EL8NI_9EEBeII9Nt PAGE 5 IHEBd90XNedIC3t_HE6I_IB6NSEEB_eND_ELUID_ELQW QUESTION 1.11 (2.00)
- e. What negative effect(s) are incurred in the secondary system if the plant is operated with primary (RCS) Teve held constant? (1.0)
- b. What negative effect(s) are incurred in the primary system if the plant is operated with secondary steam pressure held constant? (1.0)
QUESTION 1.12 (2.00)
- c. What is the most s ignif icant factor affecting overall plant efficiency as power level changes (e.g., from 50% to 100%)? (0.5)
- b. Why does increasing circulating water flow increase overall plant efficiency? (1.5)
(***** END OF CATEGORY 01 *****)
2t__EL6NI_ DESIGN _INGLUDING_S6EEII_eND_EdEBGENGl_SYSIEd3 PAGE 6 QUESTION 2.01 (3.00)
- e. What is the normal atmosphere inside the Pressurizer-Relief Tank (PRT)?
Why is this atmosphere maintained? (1.0)
- b. When relieving pressurizer safety valves into the PRT, what are two design f eatures that ensure the safe operating pressure of the PRT is not exceeded? (1.0)
- c. What are 2 methods available to cool the PRT and what is the ADVANTAGE of one method? (2 methods and advantage of 1 for full credit) (1.0)
QUESTION 2.02 (2.00)
For the following components, indicate whether they will receive an OPEN, CLOSE, or N0 signal upon a manual saf ety inj ec t ion initiation.
- a. Control Room outside air isolation valves (0.2)
- b. Main Feedwater bypass valves (0.2)
- c. Cold Leg Accumulator isolation valves (0.2)
- d. Charging header isolation valves (0.2)
- o. Main steam isolat ion valves (0.2)
- f. RWST to centrif ugal charging pumps suction valves (0.2)
- g. RCP seal water return isolation valve (0.2)
- 1. CCW isolation valve from letdown heat exchanger (0.2)
- j. Steam supply valves to turbine-driven AFW pump (0.2)
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
-. -_ - - -- _ - . .. - . _ . . _ _ ~ _ - .
.2t__EL6HI_DESION_ INCLUDING _SeEEIY_6ND_EMEBGENCY_111IEd3 PAGE 7 7
QUESTI0'N 2'.03 _
(2.50)
- e. What plant parameter, at what setpoint, can cause the letdown orifice isolation valves to automatically close? (1.0)
- b. -What does the letdown pressure control valve control during normal operation and what f unction does this accomplish? (2 answers) (0.75)
- c. What does the letdown pressure controi valve control during solid plant operation and what f unction does this accomplish? (2 answers) (0.75) j
. QUESTION 2.04 (2.50)
- e. What is one preparatory operator action required prior to automatic switchover to RHR Cold Leg recirculation? (0.5)
, b. The RHR pumps must be stopped during a manual switchover to prevent
! loss of pump suction. Why is this necessary? (1.0)
- c. How can an "AUT0" switchover be prevented? (0.5)
- d. How is continued flow assured during manual switchover? (0.5) 4 a
QUESTION 2.05 (2.50)
- e. -Explain how and why Auxiliary Feedwater flow is limited. (1.5)
- b. Explain how the Auxiliary Feedwater System (AFW) can be considered a i safety system when it's normal water supply is not considered to be a j safety related component. The answer should include specific ,
conditions that act to ensure edequate AFW flow in the event that the j normal source is lost. (1.0) 4 i
i i
' i i I
- )
a (***** CATEGORY 02 CONTINUED ON NEXT PAGE S
1 i
__ _ _ _ _ ____ - _ -__ _ -- _ =_____-_._-. _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ . _ _ . _ - _ - _ _ _ _ - . _ _ _ - _ _ _ _ - . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ . _
L 2t__EL8HI_ DESIGN _ INCLUDING _SeEEI1_6ND_EMEBGENC1_SYSIENS PAGE 8
-QUESTION 2.06 (3.00)
- s. List four (4) conditions that must be satisfied to manually close a Diesel Generator (D/G) output breaker. Values not required. (1.0)
- b. For the D/G trips listed, state if they are in effect when the 0/G is operated in PARALLEL, NOT in PARALLEL, or in either mode. (1.0)
- 1. Overcurrent
- 2. Voltage restrained overcurrent
- 3. Loss of field
- 4. Reverse power
- 5. Diesel Engine trip
- c. What are four (4) functions of the 0/G control system Low Speed (125 RPM) Relay? (1.0)
QUESTION 2,07 (2.50)
- o. What are four (4) RCS connections or penetrations that extend INTO the coolant flow path? Do not list common connections. (1.0)
- b. Explain how and why the Reactor Vessel Head Vent flow rate is limited. (0.75)
- c. Wnat are the inputs to the Core Subcooling Monitoring System? (0.75)
QUESTION 2.08 (2.00) o Excluding air and power, what conditions must be satisfied to open Letdown Isolation Valves BG LCV-450 or 4607 (0.5)
- b. What events or occurrences will cause auto opening of the valves between the Refueling Water Storage Tank (RWST) and the charging pump suction? (0.75)
- c. Describe three of the possible flow paths for Excess Letdown. (0.75) s
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
c' ~ -
)
22__EL8NI_DE119N_ INCLUDING _18EETY ANQ_EMEBQENQY_$13IEd$ ,
, PAGE 9 QUESTION 2.09 (2.50) ,
- c. In order to supply Safety Injection or Centrif ugal Charging pump '
suction from the RHR pumps, at least two (2) flow paths must be'-
isolated to satisf y interlocks. State the flow paths or in t e r l'o c ks ,
AND explain why isolation is necessary. (1.5) l
- i
- b. During plant startup, the RHR pumps are stopped but'one train Es 'left in service until RCS pressure is increased. Explain why this lineup is necessary. (1.0)
QUESTION 2.10 (2.50)
- o. What are 5 specific conditions that place the control room heating,' '
ventilating, and air conditioning system into the emergency mode of operation? Setpoints are NOT required. (1.5)
- b. Describe how the control room atmosphere is maintained habitable during accident conditions. (1.0) l l
l l
i l /
(***** END OF CATEGORY 02 *****)
L
'22__INIIBUBENIS_8BD_CONIBQL2 PAGE 10 QUESTION 3.01 (2.00)
'c. What are 2 of the 3 conditions that may cause a " Computer Rod Deviation" alarm? (0.75)
- b. What 2 signals are compared to provide a " Rod Position Indication" deviation alarm? (0.5)
- c. Explain how the Rod Insertion Limit Computer Comparator receives the actual rod position f or comparison to the limit. (0.75)
QUESTION 3.02 (1.00)
If the reactor trip due to turbine trip fails to actuate, what are two other Reactor Protection System trips that would cause a reactor trip?(1.0)
QUESTION 3.03 (1.00)
What parameters are compared to determine the positioning signal received by the steam dump I/P convertor for:
.o. Load rej ect ion? C0.5)
- b. Plant trip? C0.5)
QUESTION 3.04 (3.00)
For each case below EXPLAIN the resulting method of reactor coolant system temperature control AND indicate the approximate final RCS
- Tevg. Assume all systems normal except as stated, no operator ection. CONSIDER EACH CASE SEPARATELY
- e. The normal steam pressure setpoint is reduced by 92 psi while in Hot Standby awaiting reactor startup. (1.0)
- b. The train A Steam Dump Selector Switch is placed in the "off" position while at 5% power awaiting turbine startup. (1.0) 4
- c. The train B reactor trip breaker fails to open upon a tr ip signal while at 78% power. NOTE: The train A breaker opened. (1.0) i
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
% y eg
- 2t__INSIBUUENISieNQ_GQNIBQ(g' PAGE 11
'w
~
QUESTION 3.05 C2.00)
- e. What are the containment parameters available to the operator as Post Accident Monitoring (PAM) indication? (2.0)
-QUESTION 3.06 (3.00)
- c. . Explain'how a Source Range detector detects neutrons AND. gammas. (1.5)
~
b.. Describe the axial positioning of-excore' detectors and explain why they are positioned as described. (1.5)
QUESTION 3.07 (2.00)
Describe how power can be supplied to a typical Safety Related 120VAC
-Instrument bus AND the interlocks associated with the different bus power supplies. (2.0)
-QUESTION 3.08 (2.50) s.- What are'tGd (2) advantag'es to be obtained by controlling feed pump speed to maintain a differential pressure (dp) between the main steam system and the feed pump discharge? (1.0)
- b. Explain hows the dp is programmed and maintained. 1.0.75)
- c. Explain why a signal from excore nuclear power is used to control the Feedwater Bypass Contro1' Valve. (0.75) t l
(***** . CATEGORY 03 CONTINUED ON NEXT PAGE *****)
22__INSIBMBENII_6NQ_CQNIBQL1 PAGE 12 QUESTION 3.09 (2.50)
- c. What is the purpose of the Rod Control System DC Hold Cabinets. (1.0) b.. In the Rod Control System, there are the same number of Slave Cyclers as there are: (Choose the most correct answer below.)
- 1. Control Rods
- 2. . Logic cabinets
- 3. . Rod groups
- 4. Power cabinets (0.75)
- c. The Bank overlap unit decides which control rods to move utilizing direct input from: (Choose the most correct answer below.)
- 1. Slave Cyclers
- 2. Step counters
- 3. Master cycler
- 4. P/A converter (0.75)
QUESTION 3.10 (3.00)
- c. Explain how a Tave signal is obtained for reactor control AND why is the signal obtained considered the most conservative? (1.5)
- b. What are the specific protective functions provided by the Loop Tavg signal? (1.5)
QUESTION 3.11 (3.00)
- c. List all initiating signals for the P-14 Permissive and a Feedwater Isolation Signal (FWIS). (1.25)
- b. List ALL automatic actions that will result from reaching the P-14 setpoint and receiving a FWIS. (1.75) s
(***** END OF CATEGORY 03 *****)
At__fB9CEQMBEl_:_N9Bd8Lt_8BN9Bd8Lt_EMEB9ENQ1_8NQ PAGE 13 88DIQLQQIC8L_CQUIBQL' QUESTION 4.01 (3.00)
If you answer the phone in the control room and it is a bomb threat:
- e. What are three of the prescribed questions you should attempt to ask the caller? (1.5)
- b. What are three OTHER specific pieces of information you should try to determine about the event? (1.0)
- c. Where'in the control room are the bomb threat forms located? (0.5)
QUESTION 4.02 (2.50)
Arrange the following events in order of occurrence during a startup from hot standby to minimum load.
- a. Block Power Range Low Power trips
- b. Place the Turbine Generator on the line.
- c. Place Main Feedwater Pump Turbine Speed controls in auto.
- d. Block the Source Range Flux Doubling Transfer trip.
- e. Start one Main Feedwater Turbine Pump
- f. Block the Source Range High Flux trip.
- g. Place the Steam Dump Mode Controller in Tavg mode,
- h. Place the Main Feedwater Control Valve Bypass Valves in manual and increase Steam Generator level to 55-65%.
QUESTION 4.03 (2.50)
List five conditions that require immediate boration. (2.5)
QUESTION 4.04 (2.50)
- e. Which critical safety function has the top priority? (0.5)
- b. What is the purpose of a Functional Restoration Guide? (1.0)
- c. What action is required for a red symbol in a status tree? (1.0)
(***** CATEGORY 04 CONTINUE 0 ON NEXT PAGE *****)
st__EB9CEDUBES_=_NQBdekt_8EN9Bdekt_EMEEGENCY_660 PAGE 14 B8DIDLQQIC8L_GQNIBPL QUESTION 4.05 (2.00)
For each of the four parameters below, describe how they should respond if nctural circulation flow exists as per EMG ES-03 (SI TERMINATION). (2.0)
- c. Core exit thermocouples.
- b. Steam G2nerator pressures,
- c. RCS hot leg temperatures,
- d. RCS cold leg temperatures.
QUESTION 4.06 (1.00)
Arsuming a secondary heat sink is available, which ONE of the following eituations would allow SI termination? (1.0)
PZR LVL SUBC00 LING PRESSURE
- e. 4% 60 degrees stable
- b. 25% 25 degrees increasing
- c. 20% 65 degrees decreasing
- d. 10% 55 degrees stable QUESTION 4.07 (1.00)
For a dropped control rod, Tave/ Tref mismatch is initially maintained by tcking manual control of which of the following?
- a. turbine load.
- b. individual control rod banks.
- c. individual control rod groups.
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
~ . , _ . . _ . ,_ _ __ _
at__EBQCEDUBES_ _NQBM8Lt_8BNQBdelt_EMEBGENGX_8NQ PAGE 15 B8DIQLQQIC8L_CQUIBQL QUESTION 4.08 (2.50)
- c. What action is required by the RO-before leaving the control room if the control room must be evacuated with the reactor at power? (1.0)
- b. How does the RO obtain guidance for immediate and followup actions to be performed after leaving the control room? (0.75)
- c. What must the RO have in his possession when the control room is evacuated? (0.75)
QUESTION 4.09 (2.50)
Complete the following statements utilizing information found in the Plant Heatup procedure (GEN 00-002),
- c. For normal heatup of the pressurizer, a rate of _______ deg's F/ hour will not be exceeded. (0.625)
- b. Spray flow into the pressurizer will NOT be initiated if the temperature difference between the pressurizer and spray fluid exceeds deg's F. (0.0)
- c. At least one Reactor Coolant Pump should be in operation before RCS temperature exceeds ________ deg's F. (0.625)
- d. Heatup must be terminated or spray initiated if pressurizer boron concentration approaches ________ ppm less than RCS loop conc. (0.625)
- e. When RCS temperature narrow range indication is off-scale, RCS temperature is determined by the _________ (HIGHEST or LOWEST) reading of the wide range temperature indications. (0.625)
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
, fi__EBOCEDUBES_:_N9BM8Lt_8BNQBM8Lt_EMEBQENQ1_8NQ PAGE '16
-88019LDEIG8L_GQUIBQL-
_ QUESTION <4.10 (2.50)
LPor'the Radiation Protection Manual (WCHP-01) and 10CFR20:
- 0. , Every effort-should be made to maintain weekly exposure as far-below what level as. practicable? '(0.5)
- b. Health Physics.should be informed of any unplanned weekly exposure greater than what level? (0.5)
- c. -What is the'10CFR20 whole body exposure limit, per quarter? (0.5)
- d. TRUE or FALSE 7 Exposures during medical treatment must be reported to Health Physics'for inclusion-in dose calculations. (0.5)
- o. TRUE or FALSE? A." Calendar Quarter" is defined as any time period consisting of 13 consecutive weeks within a calendar year. (0.5)
QUESTION 4.11 (2.00)
Wha't is the exposure rate at which posting is required for each of the areas listed below, as defined in the Radiation Protection Manual?
- a. Clean Area (Maximum exposure rate from fixed contamination). (0.5) b.- Radiation Area. (0.75)
- c. High Radiation Area. (0.75)
- u r
j (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
r-t at__fBQGEDUBE1_=_NQBdeLt_eRN9Bdekt_EMEBGENGl_8NQ PAGE 17
-BeQ10LQ9ICAL_GQUIBQL QUESTION 4.12 (1.00)
Which of the following statements is correct concerning the status of the Nuclear Instrumentation Recorder during control bank rod withdrawal for a reactor startup?
- c. Both source range channels and the highest reading intermediate intermediate range channel are selected,
- b. The highest reading source range and intermediate range channels are selected.
- c. With proper overlap, the highest reading intermediate range is placed on the recorder.
- d. Either source range and the lowest reading intermediate range are selected.
l
(***** END OF CATEGORY 04 *****)
(************* END OF EXAMINATION ***************)
_ _ , _ - . _ _ _ _ _ _ _ . _ . _ . _ . - . . . _ -. - _ _ _ _ _ _ . . _ _ . _ ~ . - . _ _ - - _ _ . _ - - - - _ . , _ _ __ _ _ , . , _ . . . _ _
lz__EBINCIELES_QE_ NUCLE 88_EQWEB_ELeNI_QEEBeIIQNt PAGE 18 IHEBdQQ1NedICSt_BE8I_IB8NSEEB_eNQ_ELUIQ_ELQW ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 1.01 (2.50)
REFERENCE WC Rx. Theory, Pg. 238-241 ANSWER 1.02 (2.50)
- e. Loc Pwr Dens (KW/FT) or FQ(z). (Full credit for description of how operator maintains non-observable limits in specification and 1/2 credit for any power distribution limit.) (0.5)
- b. ONB or DNBR (accept either answer) (0.5)
- c. Fuel surface temperature is a function of both heat flux (0.5) and coolant temperature (0.5). Moderator temperature is higher at the top of the core (0.5). (1.5)
REFERENCE WC Thermal-Hydraulics Ch. 13, Pg. 8,9,20,27 J
ANSWER 1.03 ( .50) i d.
REFERENCE Roactor Theory Handout, p. 199
11__EBINGIELES_9E_NWGLE8B_E9 WEB _EL8HI_DEEBeIIQNt PAGE 19 IHEBU901NedIGSt_HE8I_IB8HSEEB_8ND_ELUID_ELQW ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 1.04 (3.00)
' Rod insertion causes flux shift towards bottom of core (0.5). With time, xonon buildup in top of core due to less burnout and xenon reduction in bottom of core due to increased burnout causes flux to shift towards the bottom of the core even more (1.0). Later, xenon buildup in bottom of the core due'to increased production and xenon reduction in top of the core due to xenon decay causes a flux swing towards the top of the core (1.0).
These feedback effects between xenon and power result in an axial power cocillation (0.5). (3.0)
REFERENCE WC Rx. Theory Pg. 272,273 ANSWER 1.05 (1.50)
- c. LESS NEGATIVE. (0.5)
- b. MORE NEGATIVE. (0.5)
- c. LESS NEGATIVE. (0.5)
REFERENCE WC Reactor Theory, Pg. 177-180 ANSWER 1.06 (2.00)
- n. Head cooldown is limited in oct. circ. (0.5) so rate limit is to avoid head voiding (0.5). (1.0)
- b. Preclude brittle fracture. (0.5)
- c. Maintain subcooling (voiding). (0.5)
REFERENCE WC QB HT-NS
.-. .- -_. - - - _= _
li__ESINGIELES_DE_ NUCLE 8B_E9 WEB _EL8MI_QEEB8119Ni PAGE 20 IHEBUDQ1N8dIGSt_BE8I_IB8HSEEB_8ND_ELVIQ_ELQW ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 1.07 (2.00)
- c. F , - b . F, c. T, d. F (4 answers e 0.5 es.)
ANSWER 1.08 (3.00)
- e. A single pump running has a higher flow than when all 4 are operating (due to reduced discharge pressure) so more work is done and more emperage drawn. (ACCEPT CONCEPT FOR ALL PARTS) (0.75) b.- At cold conditions, fluid density is higher, so more mass is moved so more work is done and more emperage drawn. (0.75)
- c. It must accelerate more mass, which requires more work, and amps.(0.75)~
- d. Operating at runout may cause pump damage / trip on overcurrent. (0.75)
REFERENCE WC QB HT-J24 ANSWER 1.09 (2.00)
- e. Fuel temperature ncreases early in life due to pellet densification, which increases the pellet-clad gap, resulting in poorer heat transfer across the gap (0.75). Later in core life, the pellet swells, due to the buildup of fission gases, reversing the effect and decreasing fuel temperature (0.75) (or gap may be contam. by fp, incr. ht) (1.5)
- b. Fuel or Doppler Coefficient. (0.5)
REFERENCE WCGS Reactor Theory Student Hendout, p. 200 ANSWER 1.10 (2.00)
- a. Boron allows ARO operation, which yields a flatter (axial) flux profile, which reduces local temp. and hot channel factors. (1.0)
- b. BDW is less negative for higher values of Tave, due to the density decrease removing boron from the core. (1.0) i
It__EBINCIELES_DE_NVGLE88_EQWEB_EL8NI_QEEB8IIQNt. PAGE 21 IBEBdQQIN8MICSt_BE8I_IB8HSEEB_8HD_ELUIQ_ELQW ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
REFERENCE WCGS Reactor Theory Student Handout, p. 224, 225
_ ANSWER 1.11 (2.00)
- e. For a. constant Tave, secondary pressures start high and vary too much for optimum turbine design. (1.0)
- b. For constant Pstm,-RCS volume changes-require excessive pressurizer sprays, heaters, and rod motion. (1.0)
REFERENCE WCGS Westinghouse Thermo-hydraulics, p. 12-9 ANSWER 1.12 (2.00)
- e. Extraction steam flow (FW htng) increases as power increases. (0.5)
- b. Increasing circ. water flow causes the average temperature of the circ.
water to decrease (0.5). This decreases the saturation temperature and pressure in the condenser shell (0.5). Decreased condenser pressur means more work from the turbine due to the decreased back pressure (0,5), so overall efficiency increases.
REFERENCE WCGS Westinghouse Thermo-hydraulics, p. 12-26 1
1
- 22__EL6HI_ DESIGN _INGLUDIN9_SeEEII_eNQ_EMEBGENCX_11SIEd1 PAGE 22 ANSWERS -- WOLF CREEK- -86/10/07-PELLET, J.
ANSWER 2.01 (3.00)
O. Nitrogen (0.5), to prevent inleakage of air and accumulating a mixture of hydrogen and oxygen (0.5)
- b. PRT relief is discharged through a sparger, underwater. (0.5)
The rupture disk bursts before the design pressure is exceeded. (0,5)
- c. 1. Spraying with cool reactor makeup water. (0.33)
Accept either for advantage;
- 1. Spraying is much quicker; OR
- 2. Recircing does not generate waste. (0.34)
REFERENCE NPS 215 Ch. 3 Pg. 26,27 ANSWER 2.02 (2.00)
(0.2 pts each)
- c. CLOSE
- b. CLOSE
- c. OPEN
- u. CLOSE
- e. N0
- f. OPEN
- g. NO
- h. N0
- i. NO .
J. NO REFERENCE WC SD ESF (Throughout)
I r
.. . - .- - ~ _-
22__fleNI_ DESIGN _ INCLUDING _28EEII_eND_EMEBGENGl_SISIEMS PAGE 23 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 2.03 (2.50) j o. Pzr. level = 17% or less. (Iow Pzr. level) (1.0)
- b. Controls pressure downstream of the letdown orifices (0.35) to eliminate flashing and two phase flow (0.4). (0.75)
pressure (0.4). (0.75)
, REFERENCE I WC SD CVCS, Pg. 1,7,13 ANSWER 2.04 (2.50)
- c. Accept any one of the following:
! 2. Check RWST level.
- 3. Check Sump level. (0.5)
- 4. Verify AC power available as required.
- b. An interlock (0.5) prevents opening the containment sump valve with the same side RWST valve open -(0.5). (1.0)
- OR rack out the power to the appropriate breakers.
- d. By switching over only one train at a time. (0.5) ,
i i
' REFERENCE WC ECCS, Pg. 43,44 l
4 s
i
!l l
2i__ELeNI_ DESIGN _INGLUDING_SeEEII_eND_EMEBGENGl_SYSIEUS PAGE 24 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 2.05 (2.50)
- o. The feed lines to each S/G contain orifice flow restrictors that function to: (0.5)
- 1. Limit containment pressure on a steam rupture. (0.33)
- 2. Limit pressure drop on Aux. Feed in case of a feed line break. (Assure flow to intact loops.) (0.33)
- 3. Limit pump runout. (0.33)
(Accept also MDAFWP discharge throttle valves auto limit flow - NR FC)
I
- b. ESW serves as a backup supply (0.5) that will be automatically provided if an AFAS exists (0.25) and suct. pressure is low (0.25). (1.0)
I i REFERENCE LP, AFW , p. 5,6 ANSWER 2.06 (3.00) l o. 1. Generator up to speed. ,
- 2. Generator up in voltage.
j 3. No lockout relays on ESF bus.
- 4. Sync. check relay satisf ied.
- 5. Synchroscope on. (Any 4, 0.25 ea.) (1.0)
- b. 1. Either
- 2. Not in parallel
- 3. Parallel
- 4. Parallel S. Either Mode <
- c. 1. Initiates field flashing.
- 2. Turns off Jacket water keep warm system.
! 3. Turns off Lube Oil Heater.
- 4. Shuts off Generator Space Heater.
! 5. Initiates (with time delay) Start Failure Relay.
(Accept opposite if stopping OG. Any 4 e 0.25 es.) (1.0) l REFERENCE LP, EDG, p. 22,24
. - . . , _ .-,..._.,_._._,.__._-,___._--,._,,,,,y~ , , . . - , ,c. -__ . .._,,,.,.-y __,,_.-._,-_.,,,,_,_-..~...-.,m
21__EL8HI_ DESIGN _INCLVQINQ_SeEEIY_eNQ_EMEBQENCY_SYSIEMS PAGE 25 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 2.07 (2.50)
- o. 1. Spray line
- 2. Hot leg manifold RTO connections
- 3. Nuclear Sampling system
- 4. Wide Range Temperature Detectors (0.25 ea.) (1.0)
- b. Limited by an orifice in the vent line (0.25) to prevent exceeding containment atmosphere combustible limits. ,0R; Limit flow to capacity of one CCP. (0.5) (0.75)
- c. 1. T cold wide range
- 2. T hot wide range
- 3. RCS wide range pressure
- 4. Pressurizer pressure narrow range S. Incore thermocouples (0.15 EA.) (0.75)
REFERENCE LT, RCS, p. 18-21 l
ANSWER 2.08 (2.00)
- c. Open: o Pzr level > 17% $
o Orifice Isolation Valves closed (2 answers e 0.25 es.)
- b. 1. VCT LOW-LOW Level
- 2. SI
- 3. Boron Dilution Protection signal (0.25 ea.) (0.75)
(4. NN01/NN04 failure (causes #1) - NR FC)
- c. After exiting Excess Letdown HX:
- 1. To PRT
- 2. To RCDT
, 3. To chg. pump suct. via SW HX
i REFERENCE LP,CVCS., p. 11, 20, 32
2t__EL6NI_ DESIGN _INCLUDINQ_18EEIX_sNQ_EMEBGENCX_SX2IEd1 PAGE 26 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 2.09 (2.50) o.- Flow paths: 1. RHR hot leg suction.
Reasons: 1. Prevent overpressurization of SI and CCP suctions.
- 2. Prevent recirculation of radioactive water through SI Pump miniflow lines. (0.4 es.) (1.5)
- b. To provide adequate letdown flow (0.5) and maintain purification flow rate. (0.5) (1.0)
OR to satisfy TS mode 4 ECCS requirements.
REFERENCE LP, RHR, p. 12,16 ANSWER 2.10 (2.50)
- c. 1. Chlorine 5. CIS "A" 8. Any other CPIS
- 2. Control rm. gas. act. 6. Cont. purge hi gas. act.
- 3. FB vent. isol. s ig . 7. Cont, atmos. hi gas, act.
- 4. SI Signal. (Any 5, 0.3 each) (1.5)
- b. Outside air is isolated and the system goes on internal recirculation (0.5). Simultaneously, the CR is pressurized with filtered air (0.5)
(to prevent inleakage). (1.0)
REFERENCE NPS 221, Ch. 4, Pg. 42,43
- - - - - _ , ,--------,---e.-- - - - - . - - - - , - - - -
-, a - - - e-- - - - - , ---v - - - , - - - ,- e-,- --,n,, ,,- - - -- -
7
21__INSIBWMENIS_eND_C9 NIB 9LS PAGE 27 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 3.01 (2.00)
- o. 1. Control bank D out of sequence.
- Bank 0 > 220 steps.
- 2. S/D bank out of sequence.
- 3. Power range flux tilt.
- - lower / upper +/- 2% average.
- any channel +/- 2% average.
- 4. Rod deviation.
- Any rod +/- 12 steps from average.
- Any rod +/- 12 steps from bank demand.
- 5. S/D bank >18 steps / <220 stps.
- 6. NSCS computer malfunction or failure. (Any 2 8 0.375 ea.)
- b. Bank demand pcsition (0.25), and individual DRPI (0.25) (0.5)
- c. A pulse / analog convertor receives the same signal as the step counters (0.375). The convertor converts these pulses to an analog output proportional to bank position (0.375). (0.75)
REFERENCE NPS 227, Ch. 3, Pg. 11-13 ANSWER 3.02 (1.00)
- 1. High RCS Pressure.
- 2. Overtemperature delta T.
- 3. High pressurizer level. (Any 2 0 0.5 each)
REFERENCE NPS 227, Ch. 5, P. 22 i
ANSWER 3.03 (1.00)
- e. Load reject: Auct. high Tave, a Tref (impulse pressure). (0.25 ea.)
Plant trip: Auct. high Tave. & T-no lood. (0.25 ea.)
1 REFERENCE NPS 223, Ch. 4, Pg. 11-14 1
i
'24__INSIBUDENI1_8N0_CONIBQL1 PAGE 28 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 3.04 (3.00)
- c. The normal steam pressure setpoint of 1092 psig maintains Tavg at
~557 F, a decrease in the setpoint to 1000 psig would cause the dumps to open and cool Tavg to ~550 F (0.5) where the P-12 interlock would close all steam dumps (0.5). (1.0)
- b. Secondary pressure would rise to the setpoint of the secondary atmospheric relief valves (0.5) which would maintain pressure at 1125 psig (0.25) and primary temparature 560 +/- 10 F-(0.25). (1.0) c.- A signal by the Load Rejection controller (0.5) would control primary temp. at "No Load" Tref (+2 F dev. (dead band, 559 F)) (0.5).
(1.0)
REFERENCE WC SD MN. STM, Pg. 31,32 ANSWER 3.05 (2.00) ,
- c. 1. Pressure
- 2. Radiation
- 3. Sump Level
- 4. H2
- 5. Temperature (5 ans. e 0.4 es.)
REFERENCE WC SD PAMS, Pg. 2,4 4
ANSWER 3.06 (3.00)
- e. Neutrons interact with boron to create ion pairs, OR accept correct reaction equation. (0.75) Gamma causes ionization (0.3 (by Photoelectric effect, (0.15) Compton effect, (0.15) or by Pair Production. (0.15) (1.5)
- b. Source Range is positioned 1/4 of the way up from the bottom of the i I
core (0.33). Intermediate is centered about core midplane (0.33).
Power are centered in each half of the core (0.33) Detectors are set to detect flux where it is most predominant for es. range (0.5).
2i__INSIBUMENIS_8NQ_GQNIBQL3 PAGE 29 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
REFERENCE LP,NI, p. 2,8 ANSWER 3.07 (2.00)
Ecch bus can be supplied from a static inverter (0.5) or a regulated transformer power supply. (0.5) The Inverter output breakers are interlocked with the transformer breakers so that only one can be closed at o time. (0.5) The transformer output breakers are interlocked so that a transformer can supply only one bus at a time. (0.5) (2.0)
REFERENCE WCGS NPS-213, p. 5-12 l
t l ANSWER 3.08 (2.50)
- a. 1. Valve wear is reduced by allowing the valve to be further l
open.
- 2. Improved efficiency by reduced pumping requirements.
l 1. Control valves are positioned in a more linear operating j range. Cany 2, 0.5 ea.) (1.0)
- b. A variable signal proportional to steam flow (0.5) is added to a constant no load setpoint (of 45 psid) to control the feed pump speed.30.25) (0.75)
- c. The signal is used as an indication of anticipated steam demand (0.25) as flow signals are unstable at low power. (0.5) (0.75)
REFERENCE i LT,SGWLC, p. 16, 17, 18 i
l ANSWER 3.00 (2.50)
- c. Provide power to the stationary gripper coils of any 1 rod group. (1.0) l t
- b. 4. (0.75)
- c. 3 (0.75)
I._____-. - - , _ . . . _ . . _ _ . , _ _ . _ _ . , _ _ . . . _ _ , . _ __,_ _ _ .. ___ . . _ _ _ , _ , _ _ . _ , . _ _ _ . _ , _ _ _ _ _ , _ , _ , _ _ _ _ , _ _ , _ ,
22__INSIBUMENIS_8NQ_C9 NIB 9LS PAGE 30 ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
REFERENCE LT, RCS, p. 18,21 ANSWER 3.10 (3.00)
- o. The signal is obtained by auctioneer ing the highest of the loop Tavg signals (.75). The high signal is more conservative because low is the most common failure mode and will have no immediate effect on reactor control (0.75). (1.5)
- b. OTdT (0.2) and OPdT (0.2) are supplied from Loop Tavg to provide Rod Stop, (0.2) Turbine Runback, (0.2) and Reactor Trip (0.2).
P-12 blocks steam dumps (0.25)to limit excess cooldown (0.25) (1.5)
REFERENCE LP, RC Temp. Inst., p. 7 & questions 5,16 ANSWER 3.11 (3.00)
- c. P-14: High S/G 1evel FWIS: o High S/G 1evel o SI o Rx. trip and Low Tavg o Manual (0.25 ea.) (1.25)
- b. P-14: o Trips Feed Reg. Valve o Trips Main Feed Pumps
, o Trips Main Turbine o Closes Main Feed Isolation Valves FWIS: o Closes Feedwater Isolation Valves o Closes Main and Bypass Feedwater Reg. Valves (0.29 es.) (
1.75)
REFERENCE LP, RPS, P. 8 & NPS 221, P. 7 l
l
SA__fBQGEQUBEG_=_NQBdelt_eRNQBdekt_EMEBGENCY_8NQ PAGE 31 BeQIQLQGIGeL_GQNIBQL ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 4.01 (3.00)
.c. What kind of bomb is it?
Where is the bomb. located?
When will it explode?
What does it look like?
Did you place the bomb?
Why?.
What is your name?
What is your address? (any 3 8 0.5 ea.)
- b. Caller's Sex, age, race, voice char., language used, background sounds, length of call, and number at which received. Cany 3 0 0.33 oa.)
- c. 1. File cabinet by desk; OR
- 2. Book case in SS office. (any 1 8 0.5) 3. SS/SO/ Clerk desk (under glass).
- 4. Any KG&E blue phone book.
REFERENCE WCGS ADM-10-004, REV 0, pg 3 FORM 1600-53 ANSWER 4.02 (2.50) d, f, h, e, b, a, c, g There are seven arrangement shifts poss ib le for the worst case. Each shift is worth 0.357 pts when the minimum number of shifts are made to achieve the correct order.
REFERENCE WCGS GEN 00-003, REV 1 pgs 5-11.
ANSWER 4.03 (2.50)
- 1. Control rod height below the insertion limit.
- 2. Uncontrolled RCS cooldown.
- 3. >/= 2 rods failed to insert on trip / S/0.
- 4. Unexpected or uncontrolled reactivity increase.
- 5. Inadequate SDM. (0.5 each)
ati_EB9CEDMBE1_ _N9858Lt_8BN9858Lt_EUEBGENGl_8NQ PAGE 32 B8019LQGIG8L_GQNIBQL-ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
REFERENCE WCGS NPS 217-2,pg.38 ANSWER _4.04 (2.50)
- e. Subcriticality. (0.5)
- b. Direct operator action (0.5) to recover / restore the degraded CSF (0.5)
(dependent on which CSF is challenged a extent of degradation). (1.0)
- c. Operator should immediately stop ORG C0.5) and start FRG to restore the CSF under extreme challenge (0.5). (1.0)
. REFERENCE WCGS ERGS ANSWER 4.05 (2.00) s.- Core exit T/cs - stable or decreasing. (0.5)
- b. S/G press. - stable or decreasing. (0.5)
- c. RCS hot leg temp. - stable or decreasing. (0.5)
- d. RCS cold leg temp. - at sat. temp. for S/G pressure. (0.5)
REFERENCE WCGS EMG ES-03, ATTACHMENT A P
ANSWER 4.06 (1.00)
- d. OR b if stated assumption of subcooling by curve not meter.
REFERENCE EMG E-1, Step 6 i
i ANSWER 4.07. (1.00)
- a.
i, i REFERENCE 4
WC OFN 00-011,P.1 ,
1
. - - . ~ . _ . - _ . _ . _ _ _ _ . _ _ _ _ . _ . . _ _ . _ _ . . . - . . . . -
$x__fBQGEQMBEl_ _NQBd8Lt_8BNQBd8Lt_EMEBGENGl_8NQ PAGE 33 B8DIDLQQIG8L_GQUIBQL-ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 4.08 (2.50)
- o. Trip the reactor (0.6) and fast close the MSIV's (0.5) (1.0)
- b. Uses copy of 0FN (Appendix). (0.75)
- c. Keys for the emergency locker and security doors. (0.75)
REFERENCE WC OFN 00-017, P. 3 & ATT C.
ANSWER 4.09 (2.50)
- c. 100
- b. Deleted per facility comments. No longer required.
- c. 160
- d. 50
- o. highest (0.625 each for 2.5)
REFERENCE GEN 00-002, Pp.1-3 ANSWER 4.10 (2.50)
- e. 100 mrem,
- b. 300 mrem.
- d. False.
- o. False. (5 answers e 0.5 es.)
1 i
I REFERENCE WCGS RPM, Rev. 3, p. 6-6, 6-7, 6-8, 10CFR20 l
it__EBQCEQUBES_=_NQBeekt_6BNQBU8Lt_EMEBGENQX_6NQ PAGE 34 88DIQLQQ1G8L_GQNIBQL
. ANSWERS -- WOLF CREEK -86/10/07-PELLET, J.
ANSWER 4.11 (2.00)
- s. 0.1 mR/hr_above background. (0.5)
- b. Dose > 5 mrem /br or 100 mrem-in 5 days / 1 week. (0.75)
- c. Dose > 100 mrem /hr. (0.75)
REFERENCE WCGS Radiation Protection Manual, Rev. 3, p. 6-13, 6-14 ANSWER 4.12 (1.00) c.
REFERENCE WC GEN 00-003, P.9 i
e
o e TEST CROSS REFERENCE PAGE 1 QUESTION VALUE REFERENCE 01.01 2.50 JJP0001008 01.02 2.50 JJP0001009 01.03 .50 JJP0001010 01.04 3.00 JJP0001011 01.05 1.50 JJP0001012 01.06 2.00 JJP0001260 01.07 2.00 JJP0001262 C1.08 3.00 JJP0001263 01.09 2.00 JJP0001267 01.10 2.00 JJP0001268 01.11 2.00 JJP0001269 01.12 2.00 JJP0001270 25.00 02.01 3.00 JJP0001013 02.02 2.00 JJP0001017 02.03 2.50 JJP0001018 02.04 2.50 JJP0001019 02.05 2.50 JJP0001249 02.06 3.00 JJP0001250 02.07 2.50 JJP0001251 02.08 2.00 JJP0001252 02.09 2.50 JJP0001253 02.10 2.50 JJP0001015 25.00 03.01 2.00 JJP0001021 03.502 1.00 JJP0001022 03.03 1.00 JJPOOO1023 03.04 3.00 JJP0001024 03.05 2.00 JJP0001025 03.06 3.00 JJP0001254 03.07 2.00 JJP0001255 03.08 2.50 JJP0001256 03.09 2.50 JJP0001257 03.10 3.00 JJP0001258 03.11 3.00 JJP0001259 25.00 04.01 3.00 JJP0001027 04.02 2.50 JJP0001028 04.03 2.50 JJP0001029 04.04 2.50 JJP0001030 04.05 2.00 JJP0001031 04.06 1.00 JJP0001032 04.07 1.00 JJP0001034 04.08 2.50 JJP0001035
o e TEST CROSS REFERENCE PAGE 2
-QUESTION VALUE REFERENCE 04.09 2.50 JJP0001036 04.10 2.50 JJP0001271 04.11 2.00 JJP0001272 04.12 1.00 JJP0001033 25.00-100.00 l
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