ML20215N667
| ML20215N667 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/24/1986 |
| From: | Cooley R, Pellett J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20215N648 | List: |
| References | |
| 50-267-0L-86-02, 50-267-L-86-2, NUDOCS 8611070142 | |
| Download: ML20215N667 (119) | |
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REQUALIFICATION PROGRAM AUDIT AND OPERATOR LICENSE EXAMINATION REPORT
-Examination Report 50-267/01-86-02 Docket: 50-267 License No: DPR-34 License: Public Service Company of Colorado P. O. Box 840-Denver, Colorado 80201 Operator License and Requalification Program Audit examinations at Fort St.
Vrain (FSV).
Examination Conducted: . September 15, 1986 Chief Examiner: @ M IO 3 Jolin L. Pellet, Examiner Date Signed Approved By: I m b. 2 , /0M/fh Date Sitjned F:alph. f.' Cooley, Sectior(j;hief ,
Summary:
NRC administered six Senior Reactor Operator license examinations (one Limited to Fuel Handling) at FSV during the week of September 15, 1986. Four of the six license candidates successfully completed their examinations and have been
-issued the~ appropriate license.
NRC administered 11 Requalification Program Audit examinations (2 Reactor Operator and 9 Senior. Reactor Operator) at FSV during the week of' September 15, 1986. Ten.of the eleven licensed individuals evaluated passed the NRC-administered requalification program. audit examinations. Combining these results with those from the May examinations, 74 percent of the licensed individuals evaluated passed the NRC-administered requalification program audit l
8611070142 861028 PDR ADOCK 05000267 V PDR
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examinations during 1986. The excellent results of the oral examinations, ongoing facility efforts to improve the training program and' facility management response to the May results, as well as results on recent license examinations, indicate substan'ial improvement in the operator training program. Therefore, the Fort St. Vrain Requalification Program is now evaluated as satisfactory.
4 As a result, the restrictions imposed on license renewal in our report OL 86-01, transmitted to you in an August 4, 1986 letter, are no longer required.
Operator license renewals may now be granted based on facility certification of completion of the requalification program. Based on these results, NRC plans to reevaluate the Fort St. Vrain Requalification Program during the 1987 requalification cycle to assure that the ability of operators to safely operate and shutdown the facility is being satisfactorily maintained..
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, REPORT DETAILS J m
- 1. PERSONS EXAMINED License Examinations': . TYPE:- SRO-LFH SR0' TOTAL PASS: 1-100% 3-60%- 4-67%i FAIL: 0-0% 40% 2-33%
a Requalification Examinations: TYPE: R0 SRO TOTAL PASS: 2-100% 8-89% 10-91%
FAIL: 0-0% 1-11%. 1-9%
- 2. EXAMINERS
~J. Pellet,NRC(ChiefExaminer)
J. Whittemore, NRC R. Eaton, NRC
- 3. - EXAMINATION REPORT. ,
Individual performance results are not included in this report because these reports are place in the-NRC!s Public Document Room.
- a. EXAMINATION REVIEW COMENT RESOLUTION -
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 in Public Service Company of Colorado (PSC) letter P-86564; dated September 24, 1986. 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 from theLletter referenced are paraphrased below for. brevity. The full text of.the comments is available in the referenced letter, which is attached (see 3.f). Question numbers prefaced by "R" are from the requalification examinations, while questions prefaced by "L" are- ~
Tfrom the license examinations. ~ Coments are only resolved once. -
-Comments like "Same as . . . ." are not addressed or noted herein.-
R1.01.b/d Accept no change if_ depleted is defined as complete.
- Resp.: ACCEPT. Key modified.
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_ i, _ R1.06.b- ' Accept enhances flow stability per HTGR Tech. course.
Resp.: -ACCEPT. Key modified.
R1.07. Question may be answered in wide variety of ways, depending on assumptions about power history.
Resp.: ACCEPT. Key modified to account for power history.
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4 RI.09. Accept decreasing steam temperature decreases efficiency.
Resp.: ACCEPT. Key modified.
R2.02.b' Accept the following additional impurities: CH4, Kr, Ar, Xe, C0.
Resp.: ACCEPT. Key modified.
.R2.03. Accept system 46, loops 1 & 2 for a, 005 loop for b.
Resp.: ACCEPT. Key modified.
R2.05. Accept 152 second scram time per TS.
. Resp.: ACCEPT. Key modified.
R2.08. Physical location of equipment is appropriate for Equipment Operators not Reactor Operators.
Resp.: REJECT. Location of important equipment is considered appropriate material for licensed personnel.
R2.09.a Accept loss of the three room complex with LOFC per TS.
Resp.: ' ACCEPT. Key modified.
R2.09.b Accept also Fire Prot. (45), Service Water (42), He Purification (23), Liquid Nitrogen (25), Purification Cooling (47) Water, Circ Water Makeup (41), RSS (12),'Rx
-Plant Ventilation (73), and Plant Lighting.
Resp.: ACCEPT. Key modified.
R3.01.b Accept range of answers, not exact setpoints.
Resp.: ACCEPT.- Key modified. ,
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R3.02. Accept two-loop trouble scram from 4 circulator trip.
Resp.: REJECT. Question asks for condition, not PPS; signal.
R3.05. Accept concept, not verbatim.
Resp.: ACCEPT. Key modified.
R3.06.a This question should be thrown out because it is based on training material that was found to be in error-too late to inform NRC.
Resp.: ACCEPT. Question removed and other parts re-weighted.
R3.07. Question does not ask for locations so should not be required.
Resp.: ACCEPT. Key modified.
R 3.08.b Accept also to mitigate large dryer leak.
Resp.: ACCEPT. Key modified.
R4.05.b Accept also to' equalize core outlet temperatures or minimize region mismatch.
Resp.: ACCEPT. Key modified.
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R4.09. Accept concept not verbatim.
~ Resp.: ACCEPT. Key modified.
R5.03. Accept reducing barrel irradiation for b and backscattering for c.
Resp.: REJECT. Key modified for backscatter. Irradiation rejected because no reference given.
R5.04. - Accept concept rather than verbatim.
Resp.: ACCEPT. Key modified.
R5.05. Accept concept rather than verbatim.
Resp.: ACCEPTS Key modified.
R5.06. Accept NTC magnitude will be smaller or have less effect.
Resp.: . ACCEPT. Key modified.
R5.08. Also accept higher power production, low helium flow, high heat flux, and unequal helium flow or power production as factors in hot spot evaluation.
Resp.: ACCEPT. Key modified.
R5. 09. - Accept closed discharge valve allows pump pressure to increase rapidly to prevent pump damage.
Resp.: REJECT. Suggested wording does not say why this is necessary.
R7.01.b Question is invalid since it asks for a single reporting location when several are possible.
Resp.: REJECT. Alternate locations added to key. I required.
R7.01.c Accept concept rather than verbatim.
Resp.: ACCEPT. Key modified.
R7.04. Accept unexplained reactivity change operator deems unsafe.
Resp.: ACCEPT. Key modified.
- R7.08. Reference not provided in key.
[ Resp.: ACCEPT. Key modified.
. R8.02. Accept alternate answers provided.
Resp.. : REJECT. Answers requested are same as original key..
R8.05. LSO is not required to report to the control room but'HP tech is per APM G-5, p. 6, step 4.4.1.
Resp.: REJECT. LSO is required per reference in key. HP tech l accepted per reference provided, and key modified.
i R8.06.b Accept that individual issued key must retain until returned l
to Shift Supervisor.
j Resp.: ACCEPT. Key modified.
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6 R8.09. Accept also, assure personnel safety, notify operators equipment -is not available, & show steps necessary.to restore to operation.
Resp.: ACCEPT. Key modified.
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L5.11.a Accept.due to.bi-metallic weld between EES & superheater.
Resp.: ACCEPT. Key modified..
L8.11. Question is invalid since rots memorization of Technical Specifications (TS) is required to answer.
Resp.: REJECT. Question may'be answered adequately based on general knowledge of TS requirements for subject area.
SRO-LFH exam category values do not. match those given in PSC TPAM.
Resp.: NRC examinations are not governed by PSC TPAM. Exam meets all NRC requirements for category weighting.
LN.03. Answer is incorrect. Total well~ capacity is equivalent of 70 full length elements with maximum of 56 fuel elements.
Resp.: ACCEPT. Key modified.
. LN.04. Question does not apply do SRC-LFH duties.
Resp.: ACCEPT. Question dropped.
LN.09. HSF floor drains discharge through system 61 to draining station, recycle, or liquid waste sump. Any of above are acceptable answers.
Resp.: ACCEPT. Key modified. -
LO.08. Checklist steps are not memorized, and order lis not sensitive.
Resp.: ACCEPT. For future reference.
LP.06. Parenthetical answer on b is wrong.
Resp.: ACCEPT. Key modified.
LP.09. Accept also systems 63, 23, 11, 13, 14, 21, and 22.
Resp.: ACCEPT. Key modified.
LP.10. Additional material provided is necessary for fully correct answer.
Resp.: REJECT. Key gives concept for full credit. Additional material cited is not required and not added to key, t
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- b. SEPTEMBER 18.1986: EXIT MEETING SUPHARY 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' PSC J. Pellet T Borst r J. Whittemore S. Willford.
P. Michaud R. Rivera ,
-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 in the exit' meeting.
(2) NRC will attempt to return formal, final results within 30 days.
(3) The following areas of weakness were observed in more than one candidate and are presented for the use'of the facility. Note that an area-of weakness does not imply unacceptable performance but is simply an area where knowledge or skill.-is less H
completely developed than in others.-
(a) Classifying events using the RERP appeared corifusing and often resulted in erroneous classification.
(b) Determining operability of nuclear. instruments when readings did not: agree was difficult and could not be
. referenced to plant procedures..
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-(c) Understanding of routing systems for procedure changes, and other mechanisms to assure currency with governing-documentation was weak.-
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(d) Understanding and calculation of shutdown margin was poor.
(e) Several individuals had difficulty. retrieving surveillance procedures required for TS testing.
.(f) Knowledge of CRD power supplies and control room documentation on them was poor.
(g) There appeared to be some confusion about the shear number
'of different tags in.use on the control boards.
(h) Items a-c above are similar to weaknesses documented in the
- previous examination report. No significant improvement was observed in these areas.
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- c. GENERIC COMMENTS The generic comments below were generated during grading of the written examinations, and regional review of'the oral examinations.
They are provided for the benefit of the facility and no response or corrective actions are required.
(1) The generic deficiencies identified in the May report were substantially corrected with respect to the written examinations.
(2) Behavior of control-rods during abnormal circumstances was poorly understood, based on oral examinations as previously stated.-
- d. REQUALIFICATION PROGRAM EVALUATION NRC administered eleven Requalification Program Audit examinations (2 Reactor Operator and 9 Senior Reactor Operator) at FSV during the week of Septsmber 15, 1986. Ten of the eleven licensed individuals evaluated passed the NRC-administered requalification program audit examinations. To arrive 'at an' overall program evaluation for 1986, the results .of the May site visit are combined with this visit.
Seventy-four percent (fourteen of nineteen) of the total number of licensed individuals evaluated in both visits passed the NRC-administered requalification program audit examinations during 1986.
These results, plus ongoing facility efforts to improve the training program and facility management response to the May results, as well as results of recent license examinations, indicate substantial improvement in the' operator training program. Therefore, the Fort St. Vrain Requalification Program is now evaluated as satisfactory.
As a result, operator license renewals may now be granted based on facility certification of completion of the requalification program.
Based on these results, NRC plans to' reevaluate the Fort St. Vrain Requalification Program during the 1987'requalification cycle to assure that the ability of operators to safely operate and shutdown the facility is being satisfactorily maintained.
- e. EXAMINATION MASTER COPY Master copies (questions and answers) for the SR0 and SRO-LFH license examinations and R0 and SR0 requalification examinations follow the requalification program evaluation on the next page.
- f. FACILITY EXAMINATION COMMENTS r
The facility examination review comments in the form of PSC letter P-86564 follow the examination master copies.
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9 OVERALL REQUALIFICATION PROGRAM EVALUATION Facility: Fort St. Vrain "
Examiners: J. Pellet, R. Cooley, J. Whittemore, R. Eaton Dates of Evaluation: May 20-22, 1986 and September 16-18, 1986 Areas Evaluated: XX Written XX Oral Simulator Written Examination Evaluation of NRC Examination Results (if given): Marginal (14/19 P)
Oral. Examination
- 1. Overall Evaluation: Satisfactory (19/20 P)
- 2. Number Observed: None Number Conducted: 20 Overall Program Evaluation Satisfactory: XX Marginal: Unsatisfactory:
REASON FOR EVALUATION
- Marginal written results (74% pass) are mitigated by:
- 1. 95% pass ratio on oral requalification examinations.
I 2. Facility management response to the May results.
- 3. Results of recent license examinations.
- 4. Ongoing facility efforts to improve the training program.
- - Overall program is evaluated as SATISFACTORY.
L Submitted: Forwarded: Approved:
I h A j Examiner Se'cti gn Chief Branch Chief
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U. S. NUCLEAR REGULATORY. COMMISSION-REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: _EIz_SIi_VB81N___________
REACTOR TYPE: _HISB-68_________________
DATE ADMINISTERED:_RklD241k________________
EXAMINER: _EELLElt_Jz______________
CANDIDATE: _________________________
IN*IBUCIl0NS_IQ_Q8NQlD81El Road the attached instruction page carefully. This examination replaces tho current c'yc le facility. administered requalification examination.
Rotraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your. training staff. Points for each question are indicated in
,perentheses after the question. The passing grade requires at least 70%
in each category and a final grade of at least-80%. Examination papers will be picked up four (4) hours after the examination starts.
% OF-CATEGORY %' 0F CANDIDATE'S : CATEGORY
__V8LUE_ _IQI8L. ___1GQBE___ _V8LUE__ ______________Q81EGQBl_____________
_2520D__ _25tDQ ___________ ________ 1. PRINCIPLES'0F NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER-AND FLUID FLOW
_2EAQQ__ _2510Q ___________ ________ 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
_25A00__ _252QQ ___________ ___._____ 3. INSTRUMENTS AND CONTROLS
_2EAQQ__ _25z0Q ___________ ________ 4. PROCEDURES - NORMAL,-ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL IQQiDQ__ ___________
Totals Final Grade All work done on this examination is my own. I have neither given nor received aid.
Candidate's Signature l
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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 cnd 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 gDiy to facilitate legible 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 gBGb ecction of the answer sheet.
- 8. Consecutively number each answer sheet, write "End of Category __" as cppropriate, start each category on a Dig page, write 2DlY 20 2DR fidt 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.
i 11. Separate answer sheets from pad and ploae finished answer sheets face down on your desk or table.
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- 12. Use abbreviations only if they are commonly used in facility 111gtgigtg.
- 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 REBEiDit only.-
- 17. You must sign the statement on the cover sheet that indicates that the cork 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.
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- 18. When you complete your examination, you shall: ,
- c. Assemble your examination as follows: '
(1) Exam questions on top. ,
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(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures wh'ich are part of the as._ w e r .'
- b. Turn in your copy-of.the examination and all pag'es used to an'swer the examination questions. .
c.- Turn in all scrap paper and the balance of the paper that.you did '
not.use for answering the questions.
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- d. Leave the examination area, as defined by the examiner. If after leaving, you are found in this area while.',the examinati'on is still in progress, your license may be denied or'revcked.
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'12__EBINCIELE1_QE_ NUCLE 88_EQWEB_ELANI_QEEB8IIQNt PAGE 2
-IHEB50DINedIQ1t_HE6I_IBeNSEEB_8HD_ELUIQ_ELQW
-QUESTION- 1.01- (4.00,
- o. How does. removing spent fuel increase core reactivity? (1.0)
- b. How doac. removing spent- f uel decrease core reactivity? (1.0)
- c. How and why does removal of reflectors affect core reactivity? (1.0)
- d. How does removing a depleted neutron source affect reactivity? (1.0)
QUESTION 1.02 (1.50)
'How does the outermost radial fuel zone differ from the others? (1.5)
QUESTION 1.03 (3.00)
What are the two (2) maj o r reasons that orifices are used in the Fort S t ..
Vrain-core? (3.0)
QUESTION 1.04 (3.00)
What are three (3)Ltypes of core changes'that can cause a power-to-flow imbalance in a refueling region with the core at balanced overall-power-to-flow? (3.0)
QUESTION 1.05 (3.00)
- a. Why should a centrifugal pump be started with the discharge valve closed? (1.5)
- b. What is operating a pump with too much flow and no discharge pressure called AND'why should this condition be avoided? (1.5)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
li__EBINCIELER_DE_ NUCLE 8B_EQWEB_EL8HI_QEEB8IIQNm PAGE. 3
-IHEBdQQIN8MIGli_HE8I_IB8HIEEB_8NQ_ELUIQ_EL9W QUESTION! 1.06 (3.00)' 3.
- c. .Why are steam temperatu'res.in the. steam generators at Fort St. Vrain limited to'1000 deg's F? (1.0)
- b. - Why is the second superheater des igned ' f or co-current flow, which is .
less efficient than counterflow as used in the EES and reheater? (1.0) c.- .What'is the "pinc'h point" of's steam generator? (1.0) 9
- QUESTION 1.07 (3.00)
Answer the following questions comparing plant conditions after a slow (~10' hours) versus a fast (~2 hours)~ power reduction from 70% to 50% reactor power with the same equilibr$dm initial conditions. ' Assume N0 operator action and rod control in MANUAL'following the powerJdecrease. -(3.0)
- e. Which. power reduction (SLOW or' FAST) will require the'most rod insertion during the power reduction? (1.0)
- b. Which-' power reduction (SLOW or FAST)' will have'the' highest final, steady state power? (1.0)
- c. Given the above conditions, how long after the fast power change will steady. state conditions be achieved (power stops changing)? (1.0) e QUESTION 1.08 (2.00)
How will an: INCREASE in. primary coolant flow rate affect reactivity and roactor power? Assumu flow is increased'unifo'rmly across'the core. (2.0)
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t QUESTION 1.09 (2.50) ,
- c. What are' two negative consequences if reheat were not used in the
, ' secondary system? ,
( 1 '. 0 )
- b. What.are two reasons that overall plant efficiency decreases at ,
low power? 4 (1.5) t l
(***** END OF CATEGORY 01 *****)
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2t__EL8HI_ DES 19N_ INCL 901NG_S6EEIY_8ND_EMEBGENGl_213IEU$ PAGE 4 QUESTION 2.01 (2.00)
What are two (2) functions of the Helium Circulator Compressor Inlet? (2.0)
QUESTION 2.02 (4.00)
- c. .What are four (4) users of purified helium from the Helium Purification
. System (System 23)? Normal or Fuel Handling related are acceptable for full credit. (2.5)
- b. What are four impurities removed by System 23? (1.5)
QUESTION 2.03 (3.00)
- e. Name the three cooling supplies to the f uel storage wells (FSW). (1.8)
- b. Name the two backup cooling supplies to the FSW. (1.2)
QUESTION 2.04 (3.50)
For the helium circulator water turbine drive system:
- a. How is turbine speed controlled? (1.0)
- b. How is flashing in the turbine cavity. prevented?_ (1.0)
- c. What is the normal power.(water) source for the turbine? (0.5)
- d. What are two (2) backup power (water) sources for the turbine? (1.0) t l- QUESTION 2.05 (3.00)
- a. During a scram, what controls rod insertion speed? (1.5)
- b. What is-the maximum allowed scram insertion time? (0,5)
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- c. What keeps reactor pressure changes during normal operation from breaking the reserve shutdown system rupture d is ks ? (1.0) l I
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
2t__EL6NI_DE11GN_ INCLUDING _18EEIX_6NQ_EMEBGENC1_111IEMS PAGE 5
, QUESTION 2.06 (3.00)
- c. 'When is the redistribution mode of the PCRV Cooling Water system (System-46) used? (0.5) 1
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- b. .How is redistribution of system 46 accomplished? (1.25).
- c. What ~ is accomplished by redistribution of system 467 (1.25)
' QUESTION 2.07 (2.00)
- e. How are fuel storage wells divided into vaults for ventilation? (1.0) b.. Compare' vault' flow during normal and emergency conditions. (1.0)
-QUESTION 2.08 (2.00)
MATCHING. EMatch'each.of the electrical distribution system components with
, the appropriate location. Each location may be used more than once or not- ,,
aat all, as' appropriate. (2.0)
' COMPONENT LOCATION
___ a. 1A Battery' Charger 1. Building 10 480V Room Northeast i
___ b. 1A Battery Bank ~2. 480V Room Northeast
.___ c. 1B Battery Charger 3. 480V Room Northwest j- ___d.- 1B Battery Bank- -4.-Auxiliary Electric Room i
___ e. 1C Battery Charger 5. 480V Room South-Wall
___ f. 1C Battery Bank 6. Building 10 480V Room Mezzanine
! ___ g. '10 Battery Charger 7 ~. 480V Room Mezzanine
___ h. 125V DC Bus 1A 4
QUESTION 2.09 (2.50)
- e. For'what combination of events is the Alternate Cooling Method (ACM) system 48 REQUIRE 0? (1.5) I
- b. -What are two other system operations necessary to mitigate the consequences of an sccident requiring ACM? (1.0) 6 4
(***** END OF. CATEGORY 02 *****) l
2i__INSIBudENIS_8ND_GQNIBQL1 PAGE 6 QUESTION 3.01 (3.00)
- c. What automatic actions occur if the steam / water dump system is actuated on high primary pressure? (2.0)
- b. What is the setpoint for the high pressure trip in the steam / water dump-system? (1.0)
QUESTION 3.02 (2.00)
What two (2) conditions will cause t'he PPS to initiate a turbine trip immediately after a reactor scram? (2.0)
QUESTION 3.03 (1.50)
TRUE or FALSE?
- o. Startup range nuclear instrumentation uses the cambelling technique to eliminate gamma pulses from the count rate circuit. (0.75)
- b. The wide range log power channels use U-235 lined f ission chambers located in detector wells 3, 4, and 5. (0.75).
QUESTION 3.04 (3.00)
What are two (2) ways that the Reserve Shutdown-System may be actuated from OUTSIDE the Control Room? (3.0)
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
22__INSIBUMENIS_8NQ_CDNIBDLS PAGE 7 1
_ QUESTION 3.05 (3.50)
A sume the plant is in a normal configuration at 50% reactor power and turbine load and turbine load is increased to 60%. A simplified schematic of-the steady state controls is attached. Continue your answers until
.oteady state conditions are achieved. (3.5)
- c. How is turbine load normally increased? (0.5) b .- How and WHY does feedwater flow change? (1.0)~
- c. How and WHY does reactor power change? (1.0)
- d. How and WHY does. helium flow change? (0.5)
- e. How is any error in main or reheat steam temperature adj usted once at the new load condition? (0.5)
QUESTION 3.06 (3.00)
TRUE or FALSE?
- o. Primary coolant moisture'hi alarm (MM-9306/7) is -30 deg's F or -45 deg's F. -(Question deleted per facility comments - ref. error.)(0.0)
-b. A loop shutdown and steam water dump due to high moisture is inhibited by a circulator seal malfunction trip. (1.0)
- c. A two loop trouble scram REQUIRES two high level. moisture monitor trips. (1.0)
- d. At an average core exit temperature of less than 725 deg's F, the basis for Technical Specification is oxidation of graphite components. (1.0)
QUESTION 3.07 (3.00)
What protective instruments are used to monitor the main turbine steam cystem ~ radiation due to a reheater leak? (3.0)
-(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
2t__1NSIBUMENIS_8ND_GONIBQLS PAGE 8 QUESTION 3.08- (3.00)
- c. What automatic realignment takes ' place in the Instrument and Service Air systems-as Instrument' Air pressure decreases below 70 psig? (1.5)
- b. What potential' problem is this realignment attempting to. mitigate?(1.5)
QUESTION 3.09 (3.00)
For each of the rooms below, describe in detail how the Halon fire protection system can be actuated. For manual initiation, where
.cpplicable, explain any controls and their location. For automatic Ectuation, as applicable, explain the type of detector (s) and logic. (3.0)
- e. Auxiliary Electric Room. (1.5)
- b. Control room. (1.5)
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(***** END OF CATEGORY 03 *****)
32__EBOCEDUBES_=_NDBU8Li_8BNQBU8Li_EMEBQENC1_8NQ PAGE 9 E8DIQLQQIC8L_GQNIBQL QUESTION 4.01 (2.50)
Explain the difference in a channel check and a channel test as defined in Tcchnical Specifications. (2.5)
QUESTION 4.02 (3.00)
.What are each person's three (3)- individual responsibilities per the rediation protection plan as _ listed in SUSMAP-47 (3.0)
-QUESTION 4.03 (2.50)
What are the five (5) immediate actions required following a reactor scram?
Specific steps to accomplish each action are NOT required. (2.5)
QUESTION 4.04 (3.00)
Dofine, per Technical Specifications:
- e. Shutdown for refueling. (1.5)
- b. Irradiated fuel. (1.5)
QUESTION 4.05 (3.50) c.. What should the following switch positions be prior to withdrawing control rods for startup? (2.0)
-1. Reactor Mode Selector Switch.
- 2. Manual Scram Switch.
- 3. Rod Group Sequence Bypass Swicch.
- 4. Interlock Sequence Switch.
- b. When increasing power from 20%, WHY should the operator perform the j following balancing actions? (1.5)
- 1. Adj ust helium flow orifice valves.
- 2. Adj ust steam generator feedwater flow.
i
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'ai__EBQGEDUBES_ _N9Bdekt_eBNDBueLt_EMEEGENGI_eNQ PAGE 10 BeQIQLQQICeL_G9NIBQL QUESTION 4.06 (1.50)-
'What parameter (s) are used to verify that the main steam turbine is chutdown after a turbine trip? (1.5)
QUESTION 4.07 (3.00)
Hcw does.the symptom-action Matrix format of the emergency procedures identify which member of the operating crew should perform required actions
.cnd/or make required decisions? (3.0)
QUESTION 4.08 (3.00)
What three (3) concepts are used concurrently 'to accomplish the goal of controlling exposure ALARA? (3.0) 0UESTION 4.09 (3.00)
Under what circumstances may personnel deviate from an approved station procedure without prior' approval? (3.0)
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A t_ _8 D dINISIB 8IIV E _E B Q C E'Q U B E S t_G Q N DIIIQ NS t _ e N Q _ LIMII6IIQ N g PAGE 11 QUESTION 8.01 (2.00)
What are the four reasons that a Radiation Work Permit (RWP) may be ccncelled? -(2.0)
QUESTION 8.02 (2.00)
What requirements must a mechanical maintenance worker meet to gain access to a Health Physics controlled ares? (2.0)
QUESTION 8.03 (2.00)
What three (3) concepts are used concurrently to accomplish the goal-of controlling exposure ALARA? (2.0)
QUESTION 8.04 '(2.00)
When do Technical Specifications require that two (2) Licensed operators be in the Control Room? (2.0)
QUESTION 8.05 (3.00)
On back shift, for what personnel (by job title) are assigned the Control Room as their personnel accountability station? (3.0) l l QUESTION 8.06 (2.50)
- a. Whst 2 circumstances must exist to issue the vital access door key?(1.0) l
- b. What 2 requirements must be met by the individual to whom the key is issued? (1.5) l l
f (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
Az__8DdINISIB8IIVE_EB9CEDMBESt_CQNDIII9NSt_8ND_LIMII8IIQNS. PAGE 12 QUESTION 8.07 (2.00)
-Under what circumstances may personnel deviate from an approved station procedure without prior approval? (2.0)
-QUESTION 8.08 -(2.00)
. What five (5) calls must be made by the emergency coordinator for an crergency classified as an " Unusual Event?" (2.0)
QUESTION 8.09 (2.00)
- c. Why is a " clearance" (non-operational status) assigned to equipment? (0.5)
- b. Who is issued the card or tag indicating a clearance? (0.5)
- c. What are two (2) purposes of operation deviation system status tags? (1.0)
QUESTION 8.10 (2.00)
- o. Technical Specifications require that the Technical Advisor be in the ~
Control Room within what time period after an emergency call? (0.5)
- b. For how long may the Fire Brigade be at less than minimum staff to accomodate unexpected absence of members, per Tech. Specs? (0.5)
- c. What are two functions of the Technical Advisor, per Tech Specs? (1.0)
QUESTION 8.11 (2.00)
What are four of the five conditions required per Technical Specifications LCO 4.2.7 to pressurize the PCRV above 100 psia? (2.0) i 1
- (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
- At__80BINISIB8IIVE_EBQCEDMBEftlGQNQIIIQNit_8NQ_LIMII8IIQN3 PAGE 13
. QUESTION 8.12 (1.50)
~What are the three (3) conditions for control rod operability for.all control rod pairs not fully inserted per interim Tech Spec LCO 3.1.1? ( 1. 5 ) .
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(************* END OF EXAMINATION ***************)
_ ~ __ . _ . . _ , _ . _ _ , _ . _ _ _ _ _ _ _ . ,. __ _ _ _ _ ___._ _ .. . . , , . , _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ .
Ez__IHEQBX_DE_NUGLE6B_EQWEB_EkeNI_QEEB8IIQNt_ELVIQSt _8NQ PAGE 14
-IHEBdQQ1NedIGH ANSWERS --- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER 5 01 (3.00) s .~ - Increases reactivity by removing fpp (including Xe &'Sm)~ (0.75)
- b. Decreases reactivity by removing f issionable materials. (0.75)
- c. Removal-decreases react. by allowing increased neutron le ak ag e .- -(0.75)
- d. Decreases reactivity. (0.75)
Accept NONE for b & d if spent 1 depleted defined as complete.
REFERENCE FSV LESSON NO. 39.00, p. 3 ANSWER 5.02 (2.00)
- e. All reflectors adj acent to fuel (0.5) are replaced at the refueling of that region (0.5) (1.0)
- b. 'All 'other reflectors (that aren' t adj acent to fuel) are permanent.(1.0)
REFERENCE FH 033.00, I I I .- A . , p. 6 ANSWER 5.03 (2.00)
- b. Power peaking (at the core-reflector interface). (0.5)-
- c. In-leaking / backscatter neutrons (from the reflector). (0.5)
REFERENCE FH 033.00, III.H.1.,'p. 11
5t__INEQBY_QE_NVQLE88_EQWEB_EL8NI_QEEB8IIQNt_ELUIQ1t_8NQ PAGE 15 IHEBdQDINedIQ1 ANSWERS'-- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER 5.04 (1.00) c, a, b (or Th-232, U-233, U-235)(0.5 for.each swap req'd to correct order)
REFERENCE FH 033.00, III.I., p.15 ANSWER 5.05 (2.00)
Since bypass flow does not pass through an orifice (0.5), it is at a higher pressure than the coolant in the channels (0.5). Because of this higher pressure, some of the bypass flow will enter the channels in the fuel. column-(0.5) via the end gaps (0.5). (CONCEPT)
REFERENCE R0 120.00.01.01.2 ANSWER 5.06 (2.00)
- 1. Different refueling regions may differ in age and burnup by as much as 6 years (0.5). The newer regions produce more heat and so need more flow to maintain a constant outlet temperature (0.5). (CONCEPT)
- 2. Any region with a higher than average power density has a higher than
~
average flow resistance (0.5). Without orificing, the higher powered regions would receive lower flow (0.5). (CONCEPT)
REFERENCE R0 120.00.01.02.1 ANSWER 5.07 (2.00)
- e. Temperature coefficient (0.5) becomes less negative (0.5). (1.0)
- b. Beta factor (0.5) decreases (0.5). (1.0)
REFERENCE FSV Reactor Physics LP on Core Changes
52__IHEQBl_QE_NWQLE88_EQWEB_EL8HI_QEEB8IIQNt_ELUIQ1t_8NQ PAGE 16 IHEBdQQ1NedIQ1
~ ANSWERS.-- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER 5.08 (2.00)
- 1. Core / fuel burnup.
- 2. Control rod movement.
- 2. Orifice position change. (CONCEPT) (3 answers.e.0.667 ea.)
REFERENCE R0 120.00.01.07.1
. ANSWER 5.09 (1.00)
- 1. Fuel element dimensional variance.
- 2. Thermal conductivity uncertainty.
- 3. Coefficient of thermal expansion uncertainty.
- 4. Irradiation-induced dimensional change. data.
- 5. Heat-transfer correlation uncertainty.
- 6. Radial power peaking factor uncertainty.
- 7. Axial power peaking factor.
- 8. Fuel loading tolerance.
9.- Exit coolant temperature measurement tolerance. (Any 2 0 0.5 es.
- 10. High power / flux at hot spot.
- 11. Unequal / low helium flow.
REFERENCE R0 120.00.01.06.1 ANSWER 5.10 (2.00)
- a. A closed discharge valve minimizes the starting power required by reducing the initial mass flow. (CONCEPT) (1.0)
- b. Runout (0.5) - overcurrent trip may result (0.5) (CONCEPT) (1.0)
REFERENCE-R0 118.00.01.07
52__IHEQB1_QE_NUGLE88_EQWEB_EL8HI_QEEB8I1QNt_ELU1QSt _8NQ , PAGE 17 IHEBdQQ1Ned1G1 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER 5.11 (3.00) ,
- c. Metal technology at the time of design (bi-metallic weld). (1.0)
- b. Min. metal temp. e hot end of tube (OR enhance f low stability). (1.0)
- c. Minimum temp. difference of working fluids (in ceg's F). (1.0)
REFERENCE R0 129.00.01.05/04/06 ANSWER 5.12 (3.00)
In each case, neg. reactivity will be inserted, due to Xe' buildup (1.0).
In the case of the fast downpower, there is less time over which XE can contribute and more rods must be inserted to achieve the new power (1.0).
Therefore, the final power (after XE decay) will be LOWER for the fast downpower (1.0). (3.0)
~ Accept alternate answers if assumptions about power history are stated and Xe behavior is correct for stated assumptions.
REFERENCE LR 008.00.01.07 4
,-, , _.r-- . - . - _ -.,.---w . - - . . - . . , . - ~ . - , _ ---.m- - - - -- _,,7- --- - . - , . . - -
61__EL8HI_SISIEdf_QESIGHz_C9 NIB 9Lt_8HD_INSIBUUENI6II9N PAGE 18 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER 6.01 .(2.00) 1.- Direct helium flow (exially) into compressor (blading). (1.0)
- 2. Monitor flow in the primary circuit. (1.0)
REFERENCE FH 034.00, p. 7 ANSWER 6.02 (3.00)
- o. 1. Buffer Helium makeup.
- 2. . Purge helium for HTFA.
- 3. Purge helium for CRD's.
- 4. Pressurizing helium for interspace PCRV penetrations.
- 5. PCRV safety relief valves. (Any 4/5 e 0.5 ea.)
- b. 1. Fission-produced isotopes.
- 2. tritium.
- 3. dust.
- 4. condensed water.
- 5. water vapor.
- 6. carbon compounds
- 7. hydrogen. 'CAny 4/8 e 0.25 es.)
- 8. noble gases.
REFERENCE' FH 034.00, p. 4-9
~ ANSWER 6.03 (2.00)
- 1. Loc'i a relay pushbuttons on level 10. (1.0) i 2. . Local ACM through hook up of flexible hoses. (1.0)
I-REFERENCE FH 030.00, p. 11 i
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_ _ _ - . _ . . _ . _ - , . , . . ~ _ _ . . _ . _ . _ - -
62__PL8MI_3ISIEd3_QESIGNt_QQNIBQLt_8NQ_INSIBydENI8IIQN FAGE 19 ANSWERS -- FT. ST. VRAIN ~ -86/09/16-PELLET, J.
1 ANSWER 6.04 (2.50)
- e. 1. Helium purge.
- 2. RPCCW.
- 4. PCRV Aux Cooling Loops 1 & 2. (Any 3/4)
- b. 1. Fire Water.
- 2. Booster fan and dampers. (5 answers e 0.5 es.)
- 3. 00S PCRV Aux Cooling Loop. (Any 2/3)
REFERENCE FH 041.00.01.05.1 ANSWER 6.05 (2.50)
- e. Reactor building sump. (0.5)
- b. Liquid waste sump (via sys 61 to draining sta., recycle, or sump).CO.5) c RB sump is not normally contaminated and can be discharged from the plant separately C.75). The effluent from the HSF is normally contaminated (.75). (1.5)'
REFERENCE FH 044.00.01.03.1 4
~ . _ , . _ _ . . , _ . . - , - . , , , - , _ . - - - , . . , . . , , - - - - . . . . _ , - . - . , , , , - - . - . - - . . - . - .. . . ,
.t.. ~ * ~ . .
Ei__EL6HI_SISIEdi_DESIGNt_G9NIBQLt_8N0_IN11BudENIeIIQN PAGE 20
-ANSWERS - 'FT. ST. VRAIN .-86/09/16-PELLET, J.
ANSWER 6.06 (3.50) a.. Load is increased by opening the main turbine admission valves. (0.5)
- b. This causes a decrease in throttle press. '(0.5). .The steam press.
controller causes the setpoint-for afw flow to be raised (0.5).- (1.0)
- c. The change in 1st-stage press. provides.a feed-forward signal to the
. flux controller to anticipate the required increase in reactor power.
setpoint (0.5).. The dev. between reactor power and setpoint causes the neutron flux control loop to withdraw the reg. rod (0.5). . (1.0)
~
d
'. A feed-forward flow signal to the he1ium circ ~. speed control antici-pates the superheat outlet error and causes incr. He flow (0.5). (0.5)
- o. At the new load condition, any error'in main or' reheat steam
~
temperature is removed by the feedback control loops which trim
. circulator speed and reactor power (0.5). (0.5)
For ALL, accept CONCEPT.
REFERENCE LR 112 7
i ANSWER 6.07 (2.00)
- c. ,.b. T, c. F, d. F (3 answers e 0.666 ea.)
(part a. deleted per facility comment due to error in~ reference material.)
REFERENCE R0 132 i ,
ANSWER 6.08 (1.00)
To assure the gradual cooldown (0.3) of the heat transfer surfaces in the oteam generator (0.4) under stagnant conditions (0.3). (CONCEPT) (1.0).
REFERENCE j OPOP VIII i
I
62__EL8HI_21SIEd3_ DESIGN 1_CDNIB9Lt_8NQ_INSIBudENI8IIQN PAGE- 21 ANSWERS -- FT. ST..VRAIN -86/09/16-PELLET, J.
ANSWER. 6.09 (2.00)
- c. 1. Pre-selected loop is dumped. (0.75)-
- 2. Other . loop is depress. to just above primary press-(~8508). (0.75)
- b. 775# e 100% or 53 +/-5# > program. (0.5)
REFERENCE R0 127.00 ANSWER 6.10 (1.50)
- 1. Reactor pressure low. (0.75)
- 2. All 4 circulators tripped. (0.75)
-REFERENCE R0 005.01.01.04 ANSWER 6.11 (2.00)
- 1. Pump 1A is running.(0.5) due to a manual start (0.5)
- 2. Pump 1B is running (0.5) due to an automatic start (0.5).
REFERENCE RO 091 ANSWER 6.12 (1.00)
- c. False, b. True REFERENCE RO 003.01,'p. 4, 8
Zt__EBQCEQUBEs_=_NQBuelt_8BNQBN8Lt_EMEBGENGl_8NQ PAGE 22-88010LQGIC8L_GQNIBQL' 1 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J ..
ANSWER 7.01 (3.50) s.- Fire (0.5) or Radiological (0.5) alarm. (1.0)
- c. 1. Contamination (> 2x background) found at exit monitor.
- 2. Exit via crash bars or emergency exits (due to imminent danger).
- 3. Exit monitors show > 500 com background. (Any 2/3 0.0.5)
- d. . Verify ratemeter operating properly (0.5) a not alarming (0.5). (1.0)
-OR habitability.
REFERENCE G-5, p. 3, 4, 7, 11 ANSWER 7.02 ('.00) 3
- 1. Follow procedures and practices, to maintain exposure ALARA.- (1.0)
- 2. Identify to supervisor, rad.. work procedures & practices that need to be upgraded.- (1.0)
- 3. . Request & attend rad. prot. training suf f icient to discharge . assigned responsibilities. (CONCEPT for all 3) (1.0)
REFERENCE SUSMAP-4 ANSWER 7.03 (3.00)
- e. Non
, b. -Non
- c. Emer '
.d. Non
- o. Emer
- f. Non (6 answers G-0.5 es.)
i REFERENCE Energency Procedures l
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'Zm__EBQGEDUBE1_=_NQBM8Lt_8BNQBM8Lt_EMEBGENGY_8NQ PAGE 23 88DIQLQEIG8L_GQNIBQL
-ANSWERS'-- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER' '7.04 (2.00) l'. Loss of-force'd. coolant' flow-(0.5) for' require'd time (0.5).
- 2. Can't insert enough rods for req'd SOM (0.5) e hot S/D.(0.5).
- 3. Reactor'can't be maintained S/D C0.5) after a-scram or.S/D (0.5).-
- 4. Unexplained react. change unsafe to the operator. '(Any 2/4 e 1.0 ea.)
REFERENCE SOP 12-05, Rev. 8, p. 4 ANSWER 7.05 (2.50)
- 1. Insert a manual scram. (0.5)
. 2. Place ISS on Low Power Position. (0.5)
- 3. Ensure transfer of house power. (0.5) 4.. Ensure turbine trip. .
(0.5)
- 5. Ensure / establish stable core cooling' conditions. (0.5)
REFERENCE EP APP B-1,-p. 7-9 ANSWER 7.06 (2.00) i
- s. Mode _ switch is LOCKED in the refueling position (0.5) simultaneous with either hot or cold shutdown conditions (0.5). (1.0)
- b. Has a radiation level (0.5) greater than 100 mr/hr 81 foot (0.5).(1.0) i
' REFERENCE
- .Tochnical Specifications, Section 2 i
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. - . - - - . . - - _ . . .r. , - _ . . . , , , , ~ , - - _ - , . _ . , -
., _ ,~ . - , _ . . . . . _ - . - . . . - - . ...,.. .- --- --,
--Zi__EBQQEQWBES_:_NQBd8Lt_8BNQBd8Lt_EMEBGENQ1_8NQ PAGE 24 B&Q1DLQQ198L_QQNIBQL !
ANSWERS _- FT. ST. VRAIN -86/09/16-PELLET, J. l 1
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1 ANSWER. 7.07 (2.00) !
- c. 1. Run
- 2. Normal
- 3. Normal-
- 4. Start (4 answers 8 .25) l
- b. l '. To equalize reheat steam outlet temperatures. (0.5)
OR to " region / core outlet temperatures.
- 2. To equalize main steam header outlet temperatures. (0.5)
REFERENCE OPOP III, p. 6, 20, 21 ANSWER 7.08 (2.00)
- 1. Initiate actions to mitigate the event.
- 2. Assign (preliminary) rad. assess. responsibilities.
- 3. Initiate protective actions for station personnel.
- 4. Classify the event.
- 5. Make management contacts.
- 6. Complete appropriate (RERP) checklist (s). (Any 2/6 8 1.0 es.)
REFERENCE PT 004.01.01.02 ANSWER 7.09 (1.00)
When the reactivity change is beyond the compensating ability of the regulating rod. (1.0)
REFERENCE EP APP'E, p. 52 ANSWER 7.10 (1.00)
Speed is decreasing (& SV/CV position). (1.0) .
- - - - , , - . - , , - , - , ,._----.,-,-_--.-_..e- .-.w--- , - --e-a w, _ _ _ _ - , _ , , _ - , , , , , ,- _,
'Z2__EBQGEQUBE2_:_NQBdelt_eRNQBdeLi_EUEBQENGI_eNQ PAGE 25 BeQIQLQQICAL_GQNIBQL ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
REFERENCE.
EP APP F-1, p. 2
-ANSWER 7.11 (3.00)
The EP's use a box format keyed like below. Accept picture or description.
W:st (reactor) SS East Cturbine) i xx- xx xx 1 Box' is marked so that:
West (reactor) actions are xx'ed at left. (Operator ~0.5, format 0.5)
East (turbine) actions are xx'ed at r ight . (as above 1.0)
SS actions are xx'ed at center. (as above 1.0)
REFERENCE EP INTRO, p. 2 i
l l-L l
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I-r
- - - - - + - . .,- , .- , -. .. , - ..-- _ - - -
~Bi__8051NISIB8IIVE_EBQGEDWBEft_GQNDIIIDNii_eND_LIMIIeII9N2 PAGE 26
-; ANSWERS --'_FT. ST.;VRAIN -86/09/16-PELLET,-J.
t
, (ANSWER 8.01 (2.00)
- 1. LTime expired.
- 2. Job completed.
3.-' Job cancelled.
<4 . Conditions change.- (4 answers e 0.5 ea.)
REFERENCE LR 029.00, p. 6, 7 ANSWER 8.02 (2.00)
- 1. .HP Tech accompanied, (0. 5)-
OR (0.25)
- 2. RWP, (0.5)
OR ~
- 3. 'under HP direction (operators only) (NOT REQUIRED FOR FULL CREDIT)-
-AND (0.25)
- 4. HP authorization.- (0.5)
REFERENCE FH 058.00.01.07.1 i
f i
ANSWER 8.03 (2.00)
- 1. Time (of exposure'should be minimized). (3 answers e 0.667 ea.)
- 2. Distance (from source should be maximized).
- 3. Shielding (from the source should be used whenever possible).
REFERENCE FH 060.00, p.5-i b ANSWER 8.04 (2.00) 8 l
- 1. - Startup.
- 2. Shutdown.
- 3. Recovery (from reactor ^ trip).- (3 answers e 0.667 ea.)
i
-.m.-----,,,-,-,-.-
- Bi__8DMINISIB8IIVE_EBQGEDUBEst_GQNDIIIQN2t_8NQ_LIMII6IIQN1 PAGE 27 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
REFERENCE TS 7.1.1.2.b, p. 7.1-3 ANSWER 8.05 (3.00)
- 1. - Shift Supervisor.
- 2. _ Reactor. Operators.
L3. Auxiliary Tenders.
- 4. -Equipment Operators.
- 5. Duty Technical Advisor.
- 6. Lead Security Officer. (6 answers e 0.5 ea.)
- 7. Off-duty Shift Supervisor - not required for full credit.
- 8. HP Tech - not required for full credit.
REFERENCE G-6, Attachment G-5A,-Rev. 18, p. 11, 12
. ANSWER- 8.06 (2.50).
- a. 1 Card. reader failure (s). (0.5)
AND
- 2. Plant emergency exists. (0.5)
- b. 1. . Individual to whom the key is issued must have authorized access to all areas unlocked by the key. ,
- 2. Individual possessing' the key may not exit.the protected area until.the key is returned to the SS.
- 3. Individual issued key retains until returned to SS.(2/3 0 0.75ea.)
REFERENCE SO 011.00.01.06 ANSWER 8.07 (2.00)
Porsonnel may deviate without prior approval 'in emergency situations (0.7) when essential to mitigate conditions (0.6) that will adversely affect porsonnel or public safety (0.7). (CONCEPT) (2.0)
REFERENCE LR 017.00.01.09 G-2, Rev. 19, Section 4.4.2.a, p. 9 i
w ,x-- , c, , - ,- , ,, .n.,. .-g -
-.w.-.v--.rn-.
- - , , - ,-.-.~,---,,---r-,.-v--,-ne., .,-+-n , - , - ,r.-, . , , --vr - - - - , - w - --
7 Ai__8DMINISIB8IIVE_EBQGEQUBESt_GQNDIIIQNSt_8NQ_LIMII8IIQNS PAGE -2 8 '
ANSWERS -- FT. ST.~VRAIN -86/09/16-PELLET, J.
ANSWER 8.08 (2.00)
- 1. . Duty TA.
- 2. Management contact.
- 3. NRC.
- 4. State (EOC).
- 5. Governor's office. (5 answers e 0.4 ea.)
REFERENCE LR 019
- ANSWER 8.09 (2.00)
- c. requiring maintenance or modification. (0.5)
OR assure safety, notify ops inop, or recover instructions.
- b. the individual intending to direct performance of the work. ( 0 . 5 )' ~
- c. 1. identify & document deviant operational situations.
- 2. authorize an operation status change.
- 3. control operations in respect to servicing and maintenance work on equipment.
- 4. restore deviant situations to normal through' orderly procedures.
(For part C, any 2/4 answers e 0.5 es.; for all parts, CONCEPT)
REFERENCE LR'018.00.01.06/7/8 P-2, Rev. 13, Section 3.1, 3.2, p. 1, 2 ANSWER 8.10 (2.00)
- e. I hour. (0.5)
! ~b. 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. (0,5)
- c. 1. Maximize safety by providing tech assist. during events.
'2. Review AOP/EP's.
- 3. Assist. ops in applying TS.
- 4. Evaluate other fac. LER's. (Any 2 0 0.5 es.)
4 m -, _. _ _ . . . , - _ , . - __ - - - - . - --
Az__8DMINISIB8IIVE_EBQGEDUBEft_99NDIIIDNSt_8NQ_LIMII8110NS PAGE 29 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
REFERENCE LR 023.00 TS, p. 7.1-2, 3, 4 ANSWER 8.11' (2.00)
- 2. All pri. & sec. penet. closures & hold-down plates operable. #
- 3. Pri-sec interspaces > pri press w/ helium. (Any 4/5 e 0.5 es. CONCEPT)
- 4. 3 except SG penet. closures can be.< pri. but > cold reheat press.
- 5. 1 set of SV & rupture disks for-SG & circ. closures opergble.: ,
REFERENCE ,
LR 031.00.01.05, TS 4.2.7, p. 4.2-5 ,
< y.
Ir
- ANSWER 8.12 (1.50) '.
- 1. Scram time </= 152 seconds. ,
(0.5)
- 2. Rod drive motor temperature </= 250 deg's F. < CGe5)
- 3. He purge flow to'es. .CRD penet. when reactor p"ress. > 100 psia. ( .5)
REFERENCE * '
s LR 032.00.01.01 Interim TS 3.1.1, p. 3/4 1-1 ,
o.
9
.n ,
9 tr g.
e s
1 v
k f
TEST CROSS REFERENCE PAGE 1 QUESTION. VALUE REFERENCE 05.01 3.00 JJP0001161 05.02 2.00 JJP0001162 F 05.03 2.00 JJP0001163 05.04 1.00 JJP0001164~
05.05 2.00 JJP0001165 05.06 2.00 JJP0001166 05.07 2.00 JJP0001167 05.08 '2.00 JJP0001168 05.09 1.00 JJP0001169 05.10 2.00 ~ JJP0001170
-05.11 .3.00 JJP0001171 05.12 3.00 JJP0001172 25.00 06.01 2.00 JJP0001173 06.02 3.00 JJP0001174 06.03 2.00 JJP0001175
-06.04 2.50 JJP0001176 06.05 2.50 JJP0001177 06.06 3.50 JJP0001178 06.07 2.00 JJP0001179 06.06 1.00 JJP0001180 06.09 2.00 JJP0001181 06.10 1.50 JJP0001182 06.11~ 2.00 ' JJP0001183 06.12 1.00 JJP0001184 25.00 07.01 3.50 JJP0001185 07.02 -3.00 JJP0001186 07.03 3.00 JJP0001187
'07.04 2.00 JJP0001188 07.05 2.50 JJP0001189-07.06 2.00 JJP0001190.
07.07 2.00 JJP0001191' 07.08 2.00 JJP0001192-07.09 '1.00 JJP0001193 1 07.10 1.00 JJP0001194 l 07.11 3.00 JJP0001195 25.00 08.01 2.00 JJP0001196 08.02 2.00 JJP0001197 08.03 2.00 - JJP0001198
'08.04 2.00' JJP0001199 08.05 3.00 JJP0001200 08.~06 2.50 JJP0001201
- r,--- -
e., ,, - n -- ,.,,--__,.,,-,m --w-,---
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TEST CROSS REFERENCE PAGE'* 2 i
QUESTION VALUE REFERENCE . , i 08.07' 2.00 'JJP0001202 t 08.08 2.00 JJP0001203 '
08.09 2.00 JJP0001204 '
08.10 2.00 JJP0001205 08.11 2.00 JJP0001206 08.12 1.50 JJP0001207
______ i ,
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______ N.
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.. ~ s U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: _EIt_ sit _VB81N___________
REACTOR TYPE: _BISB:68_________________
DATE ADMINISTERED:_RhlD241h________________
EXAMINER: _EELLEIt_Jt______________
CANDIDATE: _________________________
INSIBUGIl0NS_IQ_Q8NQlD81El Road the attached instruction page carefully. This examination replaces ~
the current cycle facility administered requalification examination.
Rotraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by
- your training staff. Points for. each question are indicated in parentheses after the question. The passing grade requires at least 70%
in each category and a final grade of at least 80%. Examination paper's will be picked up four (4) hours'after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY
__V8LUE_ _IQI8L ___SQQBE___ _Y8LUE__ ______________Q81EEQBl_____________
_25tDD__ _25109 ___________ ________ 5. THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS
_2520D__ _2510D ___________. ________ 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
_2520D__ _25tDD ___________ ________ 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL
.25100__ _25200 ___________ ________ 8. ADMINISTRA1 VE PROCEDURES, CONDITIONS, AND LIMITATIONS 7.
10Q19Q__ ___________
Totals Final Grade All work'done on this examination is my own. I have neither given nor received aid.
Candidate's Signature N
I
-- . , , _ . _- - . - - - - , _ _ , - _ . - , _ _ _ _ , _.__,__._._._y-- - . _ , _ _ . _ _
., _ +.
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 SDIY to facilitate legible 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 a n s w'e r s . ;
- 7. Print your name in the upper right-hand corner of the first page of ASGb
.nection of the' answer sheet.
> 8. Consecutively number each answer sheet, write "End'of Category __" as 4
sppropriate, start each category on a Dag page, write 2DlY 2D 201 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 ibret 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 111gc31gtg.
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 ~1ndicated 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 RERE1Dgt only.
t
- 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 assistance in completing the examination. This must be done after the examination has been completed.
~18.:When you complete.your examination, you.shall:
- a. Assemble your examination as follows:
(1) Exam questions on top.
~C2) 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.
i l
Si__INEDBY_DE_NUGLEeB_EQWEB_EL8HI_DEEB8IIONt_ELVIQSt_eNQ PAGE 2 IHEBdQDINedICS QUESTION 5.01 (4.00)
- c. How does removing spent fuel increase core reactivity? (1.0)
- b. How does removing spent fuel decrease core reactivity? (1.0)
- c. How does removal of reflectors affect core reactivity? (1.0)
- d. How does removing a depleted neutron source affect reactivity? (1.0)
QUESTION 5.02 (3.00) e.- Which reflector elements are replaced and when are they removed.from the core? (2.0)
- b. Which reflectors are permanent? (1.0)
' QUESTION 5'.03 (3.00)
- e. How does the outermost radial fuel zone differ from the others? (1.0)
- b. What ef f ect is this difference attempting to control? (1.0)
-c. What causes this ef f ect in the outermost fuel region? (1.0)
QUESTION 5.04 (3.00)
Explain why 15% of the primary coolent enters the core as " bypass flow" but l only 6% leaves the core as " bypass flow." (3.0)
QUESTION 5.05 (3.00) i
. What are the two (2) maj o r reasons that orifices are used in'the Fort St.
Vrain core? (3.0) l
(***** CATEGORY 05 CONTINUED ON NEXT PAGE *****)
52__IHE981_DE_NUGLE8B_E9 WEB _EL8HI_9EEB8IIQNt_ELUIQHt_8NQ PAGE 3
.IBEBdQQ1NedIGS QUESTION 5.06 (3.00)
What two (2) core operating characteristics change between 800 and EOC due to the buildup of U-233 for use as fuel? (3.0)
QUESTION 5.07 (3.00)
What are three (3) types of core changes that can cause a power-to-flow itbalance in a refueling region with the core at balanced overall pcwer-to-flow? (3.0)
QUESTION 5.08 (1.00)
What are two (2) factors accounted for in hot spot evaluation? (1.0)
. QUESTION 5.09 (2.00)
- a. Why should a centrifugal pump be started with the discharge valve closed? (1.0)
- b. What is operating a pump with too much flow and no discharge pressure called AND why should this condition be avoided? (1.0)
I l.
I 1
1 l'
l l
l (***** END OF CATEGORY 05 *****)
6t__EL8HI_SISIEUS_DE110Nt_QQNIBQLt_eND_INSIBUMENI8IIQN PAGE 4 QUESTION- 6.01 (4.00)
- e. What are four (4) users.of' purified helium from the Helium Purification System (System 23)? Normal or Fuel Handling related are acceptable for full. credit. (2.0) b .~ What are four impurities removed by System 23? (2.0)
QUESTION 6.02 (2.00)
What are two (2) ways that the Reserve Shutdown System may.be actuated from OUTSIDE the Control Room? (2.0)
QUESTION 6.03 (3.00)
- o. Name the three cooling supplies to the' fuel storage wells (FSW). (1.8)
- b. Name the two backup cooling supplies to the FSW. (1.2)
. QUESTION 6.04 -(3.00)
~
- c. What is the collection point for the fuel deck floor drains? (0.5)
- b. What is the collection point for.the Hot Service Facility floor drains? (0.5)
- c. Why are there different collection points for the fuel deck and Hot Service' Facility floor drains? (2.0)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
6t__EL8HI_SISIEUS_DESIGNz_GONIBQLt_8ND_INSIBUBENI8IIQN PAGE 'S QUESTION 6.05 (4.00)
Assume the plant is in a-normal configuration at 50% reactor power and turbine load and turbine ~1oad is increased to 60%. A simplif ied schematic of the steady state controls is attached. . Continue your1 answers until oteady state conditions are achieved.- (4.0)
- e. How is turbine load normally increased? (1.0)
- b. How and WHY does feedwater flow change? (1.0)
- c. How and WHY does reactor power change? (1.0)
- d. How' an'd WHY does helium flow change? -(0.5)
- o. How is any error in main or reheat steam temperature adj usted once at the new load condition? (0.5) 1 QUESTION 6.06 (2.00)
True or false?
- a. Primary coolant ~.woisture hi alarm.(MM-9306/7) is -30 deg's F or -45 deg's'F. (Qu'estion deleted per facility comment - ref. error.) (0.0)
~
- b. A loop shutdown and steam water dump due to high moisture is inhibited by a circulator seal malf unction trip. (0.667)
- c. A two loop trouble scram REQUIRES two high level moisture monitor trips. (0.667).
id . At so average core exit-temperature of less than 725.deg's F, the basis for Technical Specification is oxidation of graphite components. (0.'667) a
. QUESTION 6.07 (3.00)'
- s. What automatic actions occur if the steam / water dump system is actuated on high primary pressure? '(2.0)
- b. What is the setpoint for the high pressure trip in the steam / water dump system? (1.0)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
6t__EL8HI_SYSIEMS_QESIGNt_CQNIBQLt_8NQ_INSIBMUENI8IIQN PAGE 6 QUESTION 6.08 (2.00)
What-two (2). conditions will cause the PPS to initiate a turbine trip icmediately after a reactor scram? (2.0)
QUESTION 6.09 (2.00)
Given the following I_05 pump indications, which of the hydraulic oil' pumps are running and how was each running pump started? (2.0).
- c. Pump 1A - Red indicator.
+
- b. Pump 1B _ Red and white indicators.
-c. Pump 10 - Green indicator.
4 P
(***** END OF CATEGORY 06 *****)
Zt__EBQQEDVBES_=_NQBd8Lt_8HNQBd8Lt_EMEBGENQ1_8NQ PAGE- 7 88010LQQIQ8L_QQNIBQL QUESTION 7.01 (3.50)
- e. Under what conditions should non-operations personnel working in.
the Reactor Building report to their personnel accountability station? (1.0)
- b. When evacuating the Reactor Building, where-is their personnel accountability station? (0.5)
- c. What are two conditions that would require that they report to the Health Physics Access Control Area when leaving the Reactor Building on the way to their personnel accountability station?. (1.0)
- d. What should the first person to report to a personnel accountability station do? (1.0)
QUESTION 7.02- (3.00)
What are each person's three (3) individual responsibilities per the rcdiation protection plan as listed in SUSMAP-4? (3.0)
QUESTION 7.03 (3.00)
, Classify each of the events below as either emergency or non-emergency bEsed only cn the infor-mation given. Consider each event independently.
- a. The reactor has been automatically scrammed due to main steam pressure low. (0.5)
- b. 1A helium circulator has tripped on speed high (I-05A 1-1). (0.5)
- c. PCRV Safety Valve' Activity High Alarm activates (I-05A 2-2) AND reactor pressure. is decreasing rapidly. (0.5)
- d. Loop I moisture.high alarm AND the reactor- has been manually shutdown because the Technical Specification limit on maximum moisture during power operations have been exceeded. (0.5)
- o. Criticality alarm is reported to be activated in the Fuel Storage
-Building. (0.5)
- f. The reactor has been automatically scrammed on high moisture AND one coolant loop has tripped and dumped. (0.5)
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
. . . .. 1 Z __EBOCEDUBE1_ _N'QB58Lt_etN9858Lt_EMEBGENGl_8NQ1 PAGE. .8 L88DIDLQGIG8L_GQNIB0L QUESTION- 7.04 (3.00)
~
What are two (2) plant conditions that require inserting 1the Reserve Shutdown System? (3.0)
QUESTION 7.05 (3.00)
What are the five (5) immediate actions. required following a reactor scram?
- Specific steps to accomplish each action.are NOT required. (3.0).
QUESTION 7.06 (4.00)
, .Dofine, per Technical Specifications:
- e. _ Shutdown for_ refueling. (2.0) b.' Irradiated-fuel. (2.0) f QUESTION 7.07 (3.50)
- s. What should the f ollowing switch positions be prior to withdrawing .
control rods for startup? (2.0)
I
[ 1. Reactor Mode Selector Switch.
2 ~. Manual Scram Switch.
!- 3. Rod. Group Sequence Bypass Switch.
- ~4. Interlock Sequence Switch.
L b. When increasing power from 20%, WHY should the operator perform the following balancing actions? ( 1. 5 ) -
- 1. Adj ust helium f low orifice valves.
- 2. Adj ust steam generator feedwater. f. l o w . -
l QUESTION. .7.08 (2.00) i List two (2) actions which should be perforemd by the Duty Shift Supervisor l in. mediately upon assuming the role of Emergency Coordinator. (2.0)
(***** END 0F CA'TEGORY 07
. *****)
Di__eDUINISIBAIIVE_fB9CEDMBEft_CONQIIIONSt_eND_LIMII8IIONS PAGE 9 QUESTION 8.01 .C3.00)
.What are the'four reasons that a Radiation Work Permit (RWF) may be ccncelled? (3.0)
QUESTION 8.02 (3.00)
What. requirements must a mechanical maintenance worker meet to gain access to a Health Physics controlled area? (3.0)
QUESTION 8.03 (3.00)
What three (3) c'oncepts are-used concurrently to accomplish the goal of controlling exposure ALARA? (3.0) .
QUESTION 8.04 (3.00)
When do Technical Specifications require that two'(2) licensed operators be in the Control Room? (3.0)
, QUESTION 8.05 (3.00)
On back shift, which personnel (by job title) are assigned the Co'ntrol Room as their personnel accountability station? (3.0)
QUES' TION 8.06 (3.00) i
- 0. What 2 circumstances must exist to issue the vital access door key?(1.5)
'b. What.2 requirements must be met by the individual to whom the key is issued?- (1.5) ;
r 7
(***** CATEGORY 08 CONTINUED ON NEXT PAGE.*****)
1 Az__8D51NISIB8IIYE_EB9CEDUBESt_CQNDIIIQNat_8NQ_L151I8IIQNS PAGE 10 l
QUESTION 8.07 -(2.00)
Under what circumstances.may personnel deviate from an approved station procedure without prior approval? (2.0)
QUESTION 8.08 (3.00)
What'five (53' calls must be made by the emergency coordinator for an caergency class if ied as an " Unusual Event?" (3.0)
QUESTION 8.09 (2.00)
- e. Why is a " clearance"~ (non-operational status) assigned to equipment? C0.5) b'. Who is issued the card or tag indicating a clearance? (0.5)
- c. What are two (2) purposes of~ operation deviation system status tags? (1.0)
(
(***** .END OF CATEGORY 08 *****)
(************* END OF EXAMINATION ***************)
Et__IHE981 9E_ NUCLE 88_EDWEB_EL8HI_QEEB8IIONt_ELUIDSt_8NQ PAGE 11 IHEBdQQ1N8 DIGS LANSWERS -_ FT. ST. VRAIN -86/09/16-PELLET, J.
i ANSWER 5.01 (4.00)
- c. Increases re' activity by removing fpp. (including Xe & Sm). (1.0)
- b. Decreases reactivity by removing fissionable materials. (1.0)
- c. Removal decreases react, by allowing increased neutroo leakage. (1.0)
- d. Decreases reactivity. (1.0)
For b & d, ACCEP NONE if defined as completely spent / depleted.
REFERENCE FSV LESSON NO. 39.00, p. 3
' ANSWER 5.02 (3.00)
- c. All reflectorc adj acent to fuel (1.0) are replaced at the refueling of
.that region (1.0) (2.0) b.. All other reflectors (that aren' t adj acent to' fuel) are permanent.(1.0)
REFERENCE FH 033.00, III.A., p. 6 l
l l ANSWER 5.03 (3.00)
! b. Power-peaking (at the core-reflector interface). (1.0) l l
- c. In-leaking / backscatter neutrons (from the reflector). (1.0) i i REFERENCE l FH 033.00, III.H.1., p. 11 l
i l
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Ez__IHEQBY_QE_NUGLE88_EQWEB_ELeNI_DEEBoIIONt_ELUIQat_eNQ PAGE .12 IHEBdQQ1NedICS ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER- 5.04 (3.00)
Since bypass _ flow does not pass through an orifice (0.75), it is at a higher pr' essure than the coolant in the channels (0.75). .Because of this higher pressure, some of the bypass flow will enter the channels i^n the fuel column (0.75).via the end gaps (0.75). (CONCEPT)
REFERENCE R0 120.00.01.01.2 ANSWER 5.05 .C3.00)
- 1. Different refuel ng regions may differ in age and burnup by as much as 6 years (0.75). The. newer regions produce more heat and so need more flow to maintain s. constant outlet temperature (0.75). (CONCEPT)
- 2. Any region with a higher then-average power density has a higher than average flow resistence (0.75). Without orificing, the higher powered regions would receive lower flow'(0.75). (CONCEPT)
REFERENCE R0 120.'00.01.02.1 ANSWER 5.06 (3.00)
- c. Temperature coefficient (0.75) becomes less negative (0.75). (1.5)
- b. Beta factor (0.75). decreases (0.75). (1.5)
REFERENCE FSV Reactor- Physics LP on Core Changes ANSWER 5.07 (3.00)
- 1. Co.re/ fuel burnup.
- 2. Control rod movement.
- 2. Orifice pos ition change. (3 answers e 1.0 ea.)
REFERENCE R0 120.00.01.07.1 I
i . __
i 5t__IHEQBY_DE_NUDLE88_E0 WEB _EL8HI_DEEB8IIONt_ELUIQSt _6NQ PAGE 13 IHEBdQQ1NedIQ1 ,
' ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.-
ANSWER 5.08 (1.00)
- 1. Fuel element dimensional variance.
- 2. Thermal conductivity uncertainty.
- 3. Coefficient of thermal expansion uncertainty.
- 4. Irradiation-induced dimensional change data.
- 5. Heat-transfer correlation uncertainty.
- 6. Radial power peaking. factor uncertainty.
- 7. Axial power peaking factor.
8.- Fuel loading tolerance.
- 9. Exit coolant temperatue measurement tolerance. (Any 2 0 0.5 ea.)
- 10. High power / flux 9 hot spot.
- 11. Unequal / low region He flow.
REFERENCE RO 120.00.01.06.1 ANSWER 5.09 (2.00)
- a. A closed discharge valve minimizes the starting power required by-reducing the initial mass flow. (CONCEPT) (1.0)
- b. Runout (0.5) - overcurrent' trip may result (0.5) (CONCEPT) (1.0)
REFERENCE R0 118.00.01.07 l
l t
64__EL8HI_SISIEMS_DE21GNt_GDNIBDLt_eND_INSIBUMENIeIIQN- PAGE- 14 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.-
ANSWER 6.01 (4.00)
- c. 1. Buffer Helium makeup.
2 2. Purge helium for HTFA.
- 3. Purge helium for CRD's. .
- 4. Presurizing helium for interspace PCRV penetrations.
- 5. PCRV safety relief valves. (Any 4/5 0 0.5 ea.)
- b. 1. Fission-produced is otop es .
- 2. tritium.
- 3. dust.
- 4. condensed water.
- 5. water vapor.
- 6. carbon compounds.
- 7. hydrogen. (Any 4/8 0 0.5 ea.)
- 8. noble gases.
REFERENCE FH 034.00,' p. 4-9 ANSWER 6.02 ~C2.00)
- 1. Loc'ai relay pushbuttons on level 10. (1.0)
- 2. Local ACM through hook up of flexible hoses. (1.0)
REFERENCE FH 030.00, p. 11
- ANSWER 6.03 (3.00) i
- s. 1. Helium purge.
- 2. RPCCW.
- 4. PCRV Aux Cooling Loops 1 & 2. (3 req'd)
- b. 1. Fire Water.
- 2. . Booster fan and dampers. (5 answers G.O.6 es.)
- 3. 00S PCRV Aux Cooling Loop. (2 req'd)
REFERENCE FH 041.00.01.05.1 l
l I
i l
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62__ELeNI_SISIEUS_DESIGNt_G9NIBQLi_8NQ_INSIBUMENI6IION PAGE 15 1 ANSWERS ' -- F T . ST. VRAIN -86/09/16-PELLET, J.
ANSWER' 6.04 ( 3. 0 0 )'
- s. ' Reactor building sump. (0.5)
- c. RB sump is not normally contaminated and can be discharged f rom the plant separately (1.0). The effluent from'the HSF is normally contaminated (1.0). (2.0)
REFERENCE FH 044.00.01.03.1 ANSWER 6.05 (4.00)-
- e. Load is increased by opening.the main turbine admission valves. (1.0)
- b. This causes a decrease in throttle press. (0.5). The steam press.
controller causes the setpoint for mfw flow to be raised (0.5). (1.0)
- c. The change in 1st-stage press. provides a f eed-f orward signal to the flux controller to anticipate the required increase in reactor power setpoint (0.5). The dev. between reactor power and calpoint causes the neutron flux-control loop to withdraw the reg. rod (0.5). (1.0)
- d. A feed-forward flow signal to the helium circ. speed control entici-pates the superheat outlet error and causes incr. He flow (0.5). (0.5)
- o. At the new load condition, any error in main or reheat steam temperature is removed by the feedback control loops which trim circulator speed and reactor power (0.5). (0.5)
For ALL - ACCEPT CONCEPT.
REFERENCE LR 112 ANSWER 6.06 (2.00)
- c. , b. .T, c. F , -d . F (3 answers e 0.667 ea.)
(A not graded per current des ign. )
62__EL8HI_SISIEUS_DESIGNt_QQNIBQLt_8NQ_INSIBudENI6IIQN PAGE 16 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
REFERENCE HR0 132 ANSWER 6.07 (3.00)
- c. 1. Pre-selected loop is dumped. (1.0)
- 2. Other loop is depress. . to j ust above pr imary press (~850#). (1.0) b.- 775# e 100% or 53+/-5#iprogram. (1.0)
REFERENCE R0 127.00 ANSWER' 6.08 (2.00)
- 1. Reactor pressure low. (1.0)
- 2. All 4 circulators tripped. (1.0)
REFERENCE R0 005.01'.01.04 ANSWER 6.09 (2.00)
- 1. Pump 1A is running (0.5) due to a manual start (0,5) 2._ Pump 18 is running (0.5) due to an automatic start (0.5).
! REFERENCE RO 091 l
'Zi__EB9CEDUBE1_=_NQBd8Lt_8BN9Bd8Lt_EMEBQENGY_8ND PAGE 17 B8DIQLQQIG8L_CONIBQL ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER 7.01 (3.50)
- e. Fire (0.5) or Radiological (0.5) alarm. (1.0)
- c. 1. Contamination (> 2x background) found at exit monitor.
- 2. Exit via crash bars or emergency exits (due to imminent danger)'.
- 3. Exit monitors show >L500 cpm background. (Any 2/3 4 0.5)
- d. Verify ratemeter operating properly (0.5) & not alarming (0.5). (1.0)
OR " habitability (1.0).
REFERENCE G-5, p. 3, 4, 7, 11 ANSWER 7.02 (3.00)
- 1. Follow procedures and practices,Eto maintain exposure ALARA. (1.0)
- 2. Identify to supervisor,i rad. work procedures & practices that need to be upgraded. ; (1.0) s,.
- 3. Request & attend rad. prot. training suf ficient to discharge assigned responsibilities. (CONCEPT for all 3) (1.0) l REFERENCE SUSMAP-4 l
ANSWER 7.03 (3.00)
- o. Non
- b. Non
- c. Emer
- d. Non l o. Emer l f. Non (6 answers e 0.5 ea.)
REFERENCE Energency Procedures
l Z2__EBQCEDVBES_:_NQBd8Lt_8BNQBd8Lt_EdEBQENGl_8NQ PAGE- 18 B8DIQLQQIG8L_GQNIBQL ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER 7.04 (3.00) 1.- Loss-of forced coolant-flow (0.75) for required time (0.75).
- 2. Can't insert enough rods for req'd SDM (0.75) e hot S/D C0.75).
- 3. Reactor can't be maintained S/D C0.75) after a scram or S/D (0.75).
- 4. Any. unexplained react. operator feels is unsafe. (Any 2/4 e 1.5 es.)
REFERENCE SOP 12-05, Rev. 8, p. 4 ANSWER 7.05 (3.00)
- 1. Insert a manual scram. (0.6)
- 2. Place ISS on Low Power Position. (0.6)
- 3. Ensure transfer of house power. (0.6)
- 4. Ensure turbine trip._ (0.6)
- 5. Ensure / establish stable core cooling conditions. -(0.6)
REFERENOE EP APP B-1, p. 7-9 ANSWER 7.06 (4.00)
- c. Mode switch is LOCKED in the refueling position (1.0) simultaneous with either hot or cold shutdown conditions (1.0). (2.0)
- b. Has a radiation level (1.0) greater than 100 mr/hr e1 foot (1.0).(2.0)
REFERENCE Technical Specifications, Section 2
.c s * .
l fZi__EB9CEDUBES_=_NQBM8Lt 8BNQBM8Li_EMEBGENGI_8NQ PAGE' 19 l 88010LQ9108L_GQNIBQL l ANSWERS -- FT.'ST~. VRAIN -86/09/16-PELLET, J.
1 I
ANSWER 7.07 (3.50)
- e. -1.- Run
- 2. Normal '
- 3. Normal
- 4. Start (4 answers e 0.5)
- b. 1. To equalize reheat steam outlet temperatures. (0.75)
OR to " core outlet / region mismatches.
- 2. To equalize main steam header outlet temperatures. (0.75)
REFERENCE-OPOP III, p. 6,-20, 21 ANSWER 7.08 (2.00)
- 1. Initiate actions to mitigate the event.
- 2. Assign (preliminary) rad. assess. responsibilities.
- 3. ' Initiate' protective actions for station personnel.
.4. Classify'the event.
- 5. Make management contacts.
- 6. Complete appropriate CRERP) checklist (s). (Any 2/6 e 1.0 es.)
REFERENCE PT 004.01.01.02-i
?
. . = .
'Bi__eD51NISIB8IIVE_EBQGEQUBESt_CDNDIIIDNSt_8NQ_LIMII8IIQNS PAGE 20 ANSW'ERS -- FT. ST. VRAIN -86/09/16-PELLET,LJ.
ANSWER 8.01 (3.00)
- 1. Time expired.
- 2. Job completed.
- 3. Job cancelled.
- 4. Conditions change. (4 answers e 0.75 es.)
REFERENCE LR 029.00, p. 6, 7 ANSWER 8.02 (3.00)
- 1. HP Tech accompanied, (0.75)
OR C0.25)
-2 . RWP, (0.75)
- 3. under HP direction Coperators only) (NOT REQUIRED FOR FULL CREDIT)
AND_ (0.25)
- 4. HP authorization. (1.0)
REFERENCE FH 058.00.01.07.1 .
ANSWER 8.03 (3.00)
.1. Time.Cof exposure should be minimized). (3 answers e 1.0 ea.)
- 2. D is t anc e (from source should be maximized).
- 3. Shielding (from the source should be used whenever possible).
REFERENCE FH 060.00, p. 5 ANSWER 8.04 (3.00)
- 1. Startup.
- 2. Shutdown.
- 3. Recovery (from reactor trip). .(3 answers e 1.0 ea.)
. . . =-.
'Ai__eQUINISIB8IIVE_EBDGEDUBEft_CQNDIIIDN2t_8NQ_LIMII8IIQN1 PAGE 21 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
REFERENCE TS 7.l.1.2.b, p. 7.1-3 ANSWER- 8.05 (3.'00)
- 1. Shift Supervisor.
- 2. Reactor 0~erators.
p 3.. Auxiliary Tenders.
4.. Equipment Operators.
- 5. Outy Technical Advisor.
- 6. Lead Security Officer. (6 answers G.0.5 es.)
- 7. Of f-duty Shif t Supervisor - not required for full credit.
8.. HP Technician - not required for full credit.
REFERENCE G-6, Attachment G-5A, Rev. 18, p. 11, 12 ANSWER 8.06 (3.00)
- a. 1. Card reader failure (s). (0.75)
AND-
- 2. Plant emergency exists. (0.75) b.' 1. Individual to whom'the key is issued must have~ authorized access to all areas. unlocked by the key.
- 2. . Individual possessing the key may not exit the protected. area until the key is returned to the SS.
- 3. Individual issued the keys must keep them until he returns them to the SS. (Any 2/3 8 0.75 es.)
REFERENCE SO 011.00.01.06
' ANSWER 8.07 (2.00) l Personnel may deviate without prior approval in emergency situations (0.7) l when essential to' mitigate conditions (0.6) that will adversely affect
- porsonnel or public safety (0.7). (CONCEPT) (2.0) l
Az__80dINISIB8IIVE_EBQGEQUBESi_CQNDIII'USt_8NQ_LIMII8IIQNS Q PAGE 22 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
REFERENCE LR 017.00.01.09 G-2,: Rev. 19, Section 4.4.2.a, p. 9 ANSWER 8.08 (3.00)
- 1. Duty TA.
'2. Management contact.
- 3. NRC.
- 4. State CEOC).
- 5. Governor's office. (5 answers e 0.6 ea.)
REFERENCE
'LR 019 ANSWER 8.09 (2.00)
- c. 1. equip. requiring maintenance or modification.
2 .- Assure personnel saf ety.
- 3. Notify operations of inoperable equip.
- 4. Inform ops of how to restore. equip. (Any 1 0 0.5)
- b. the individual intending to direct performance of the work. (0.5).
- c. 1. identify & document deviant operational situations.
- 2. authorize an operation status change.
- 3. control operations in repsect to servicing and maintenance work on equipment.
- 4. . restore deviant situations to. normal through orderly procedures.
(For part C, any 2/4 answers e 0.5 es.; for~all parts, CONCEPT)
REFERENCE LR 018.00.01.06/7/8 P-2, Rev. 13, Section 3.1, 3.2, p. 1, 2
TEST CROSS REFERENCE PAGE- -1
-QUESTION' VALUE REFERENCE-05.01 -4.00 JJP0001123
.05.02 3.00 JJP0001124 05.03 3.00 .JJP0001125;
-05.04> 3.00 JJP0001127 05.05 3.00 JJP0001128' '
05.06- 3.00 JJP0001129 05.07 :3.00 JJP0001130 05.08 1.00 JJP0001131 05.09 2.00 JJP00011'32 25.00' 06.01 4.00 JJP0001134 06.02 2.00 JJP0001135 06.03 3.00 JJP0001136
.06.'04 3.00 JJP0001137 06.05' 4.00 JJP0001138-06.06 2.00 JJP0001139 06.07 3.00 JJP0001141' 06.08 2.00 JJP0001142 06.09 2.00 JJP0001143 <
25.00_
07.~01 3.50 .JJP0001144 07.02 3.00 JJP0001145 07.03 3.00 JJP0001146 07.04 3.00 JJP0001147 07.05 3.00 JJP0001148 07.06 4.00 JJP0001149
-07.07 3.50 JJP0001150 07.~08 2.00 JJP0001151 25.00-08.01 3.00 JJP0001152
'08.02 3.00 JJP0001153 08.03 3.00 .JJP0001154 08.04 3.00 JJP0001155 08.05- 3.00 JJP0001156 08.06 3.00 JJP0001157 08.07 2.00 JJP0001158 08.08 3.00- JJP0001159 08.09' 2.00 JJP0001160 25.00 100.00
ma t
U.-S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION LIMITED TO FUEL HANDLING FACILITY:' _NIz_SIf_yR81N___________
REACTOR TYPE: _BISB:E8_________________
DATE ADMINISTERED: _QhlD241h________________
EXAMINER: _PELLEIz_Jz______________
CANDIDATE: _,______g_,l_____________
IN11BMDIIDNS_IQ_DeNQ1Q61El ,
Uno separate paper for the answers. Write a'nswers on one side ,only.
Stcple question sheet on top of the answer sheets.- Pointstfor eauh qucstion are indicated in parentheses after the quisti'on. Thk paso ling grcde requires at least 70% in each category. Examination papers;Will ,
C bo picked up six (6) hours after the examination starts.
~
r ,,
CATEGORY % OF CANDIDATE'S
% OF CATEGORY z,
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__V8LUE_ _IQI8L ___1DQBE___- _V8LME__ ______[-_____1061E6 dbl _ % '~
_16tDD__ _16122 ___________ ________ M. REACTOR AND FbdL CHARACTERISTIC 5
~
_2020D__ _20td1 ___________ ________ N. EQUIPMENT, INSTRUMENTATION ANDN DESIGN DESCRIPTION ,
1
_2010D__ _20141 ___________ ________ 0. PROCEDURES AND LIMITATIONS'
_22z0D__ _22235 ___________ ________ P. EME.RGENCY SYSTMS AND SAFETY DEVICES ~
_2D20D__ _2Didi ___________ ________ Q. HEAbTHfHYSICS[5NDRADIATION, PROTECTIONe ~_ '
_SHADD__ ___________ T ot a16 ' N.- ^3 Final Grade ml w ,
All work done on this' examination is my own. I haves neithessgiven nor received aid.
- ______________-_______________D -.-.-
Candidate's Signature ;
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NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the f ollowing rules apply:
- 1. . Cheating on the examination means an automatic denial of your-application cnd could result in more-severe penalties.
- 2. Res'troom trips'are to be limited ~and only one candidate at a time may
. leave. You must avoid all con. tacts with anyone= outside .the e'xamination room.to. avoid even the appearance or possibility of chssting.
- 3. Use black inkoor dark pencil Saly to facilitate' legible reproductions.
- 24. Print your'name in the blank provided on the cover sheet of the oxamination.
~ 5. Fi'11 in-the date.on the cover sheet of the examination (if necessary).
- 6. Use only the paper provided for answers.
j 7. Print your name in the upper right-hand' corner of the first page of 33sh section.of the answer sheet.
i 4
- 8. Consecutively number each answer sheet, write "End of Category __" as
- cppropriate, start each c'ategory on a Dag page, write 2DlY 20 2Dg Ridg
'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 ihree 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 111gr31grg.
- 13. The point value tor.each question is indicated in parentheses after'the
_ question and can be used as a guide for the depth-of' answer required.
l ~ 1. 4 . .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 ANO DO NOT LEAVE ANY ANSWER BLANK.
- 16. If parts of the examinntion are not clear as to intent, ask questions of the gggsiDat 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 assistance in completing the examination. This must be done after the examination has
, been completed.
1
- a. . . _ . . . . , _ _ - _ , _ , _ _ _ . - . - , , _ _ - _ _ _ . - , - , ..~ --,---, -
-._,m ,.
t
- 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.
s
- 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.
f t
'n v
41 i
6' i
b 1
ti__BE8CIDB_8ND_EUEL_CB688CIEBISIIGS PAGE 2 QUESTION M.01, (2.00)
Explain 2 ways an adverse reaction in irradiated fuel stored in fuel otorage wells is prevented. (2.0)
- QUESTION M.02 (3.50)
- c. How does removing spent fuel increase core reactivity? (1.0)
- b. How does removing spent fuel decrease core reactivity? (1.0)
- c. How does removal of reflectors affect core reactivity? (1.0)-
- d. How does removing a depleted neutron source affect reactivity? (0.5)
QUESTION M.03 (2,00)
- c. Which reflector elements are replaced and when-are they removed from the core? -(1.5)
- b. Which reflectors are permanent? (0.5)
QUESTION M.04 (2.00)
Fill in the blanks in the following paragraph dealing with the Region Constraint. Devices (RCD). Blanks may represent one or more words or numbers. (2.0)
RCD's in most cases link together __(a)__ of __(b)__ regions, to
__(c)__ between regions. There are __(d)__ RCD's installed in-the Core.
QUESTION M.05 (2.00)
- e. How does the outermost radial fuel zone differ from the others? (1.0)
- b. .What'effect is this difference attempting to control? (0.5)
- c. What causes this effect in the outermost fuel region? (0.5)
(***** CATEGORY M CONTINUED ON NEXT PAGE *****)
Ut;_BE6CI9B_eND_EUEL_CH888GIEBISIIGS .PAGE 3
' QUEST'IO'N -M.06 (1.00)
Rank each of the materials below based on the mass of each at the beginning
~of cycle 3 (where 1st is.the most and 3rd is the least). (1.0)
- o. Uranium 235
- b. Uranium 233
- c. Thorium 232 QUESTION M.07 (2.00)
What are the-four types of fuel elements used at Fort St. Vrain? -(2.0).
QUESTION M.08 (1.50)
What is the width and height of a normal fuel element? (1.5) k
(***** END OF CATEGORY M *****)
, , . . . . . --- . - _ , - - - . . - - . - - . _ . . - . . - - . , . - . . . . ~ . .. -
Ni__E991EMENIi_INSIBudENI8119N_8NQ_ DESIGN _DE2GBIEIIQN PAGE 4 QUESTION -N.01 (3.00)
- c. Describe the seal-on the. top of a Reactor Isolation Valve (RIV). (0.5) b .- Describe the seal on the bottom of a RIV. (0.5)
- c. Besides sealing, what are 2 functions served by the RIV?. (1.0)
- d. Describe three~(3) RIV internal interlocks. (1.0)
QUESTION N.02 (1.00)
What is.the purpose of the refueling sleeve? -(1.0)
Q U E S T I O N -lN . 0 3 (1.00)
How many fuel elements and reflectors can be stored in a fuel storage well? (1.0)
QUESTION N.04 C .00)
What are two (2) functions of the Helium Circulator. Compressor Inlet?-(2.0)
.(Question deleted as inappropriate. 20.0 pts. in cat., 98.0 in enum.)
QUESTION N.05 (3.50)
- c. What are two (2) users of purified helium from the Helium Purification Sys' tem (System 23)? Normal or Fuel: Handling related are acceptable for full credit. (1.0)
- b. What are four impurities removed by System 23? ( 1. 0 ) .
i c. What parameter must be controlled to prevent carbon transport? (0.5)
- d. What is the net effect of carbon transport on the core? (1.0) i
(***** CATEGORY N CONTINUED ON NEXT PAGE *****)
Nz__E991EMENIz_INSIEWHENI8IIQN_8NQ_QESIGN_QESQBIPIIQN- PAGE' 5 QUESTION N.06 (2.00)
What are two (2) ways that the Reserve Shutdown System may be actuated from outside the Control Room? (2.0)
QUESTION N.07 (2.00)
N:me-the four (4) subsystems associated with the CRD's. (2.0)
QUESTION N.08 (2.50)
- e. Name the three cooling supplies to the fuel storage wells (FSW). (1.5)
- b. Name the two backup cooling supplies to the FSW. (1.0)
QUESTION N.09 (3.00)
- c. What is the collection point for the fuel deck floor drains? C0.5)
- b. What is the collection point for the Hot Service Facility floor drains? ,
(0.5)
- c. Why are there different collection points for the - f uel de'c k and Hot Service Facility floor drains? (2.0)
QUESTION N.10 (2.00)
What two (2) differences does the FHM detect to prevent interchanging fuel olements and reflector blocks? (2.0)
)
l
)
I l
(***** END OF CATEGORY N *****)
I
02__EB9CEDUBES_8NQ_LIMII8II9NS PAGE 6 QUESTION. 0.01 (2.00)
- c. What action (s) should personnel in the Reactor' Building take if Reactor Building activity monitors indicate that an abnormal radioactive gas release is taking place? (1.0)
- b. How would personnel working in the Reactor Building be warned that an abnormal release was taking place? (1.0)
QUESTION 0.02 (1.00)
~
When would the Refueling Supervisor normally inform the control room that a Shutdown Margin calculation should be performed? (1.0)
QUESTION 0.03 (1.00)
Other'than control rod withdrawal, what are two refueling evolutions that can cause erratic oscillation or increase on the Start-Up Nuclear instrument channels? (1.0)
QUESTION 0.04 (2.00)
What two (2) precautions should be observed when operating the Fuel Handling Machine handwheels? (2.0)
QUESTION 0.05 (3.00)
In what order should the electric and pneumatic lines of a Reactor Icolation Valve (RIV) be connected? (3.0)
QUESTION 0.06 (2.50)
Where (at what-5 locations) can the ATC be secured? (2.5)
(***** CATEGORY 0 CONTINUED ON NEXT PAGE *****)
-e: . -e .
92__EBQQEQWBES_eND_LIMII8IIONS~ PAGE 7
' QUESTION 0.07 (2.50)~
What are'the four (4) steps; required to evacuate.and backfill the FHM when it is installed.on a RIV?- (2.5)
. QUESTION 0.08 (2.50)
Put the following steps of. setting and bolting a RIV in the correct ooquence. . (List the steps in the proper order on your answer sheet, i.e.,
e, b , c, d, . . . ). (2.5).
- c. Lower the RIV onto the refueling penetration.
.b. Install support lugs at-the support points around the penetration and alignment pins.
- c. Check for cleanliness of the bottom bearing surface, the upper flange surface of the lug, and the penetration seal surface.
- d. Connect power lines and pneumatic hoses.
, e. Lubricate threads of the lug and stud support flanges and the lug support rings.
- f. Snug all lug and stud support flanges up against the bottom of the valve.
- g. Screw the support flanges all the way onto'the. support ring.
- h. Lower the flange and ring assembly-onto the support lugs,
- i. Level the valve.
J. Install lug nuts and torque to limits.
- k. . Remove refueling penetration cover.
(***** CATEGORY 0 CONTINUED ON NEXT PAGE *****)
- 94__EB9CEQUBES_8NQ_LIMII8IIQNS PAGE 8 QUESTION Of.09 (3.50)
Fill in the blanks in the following. steps from the FHM abbreviated shutdown.
procedure. Blanks may contain one or more words or numbers. (3.5) a.. If in _(1)_, go to step b. If in _(2)_,-move position controls to normal zero positions. (0.5)
- b. Depress _(1)_ switch (Master Controls) and verify _(2)_. (1.0)
- c. Close._____ and. verify it indicates closed. (0.5)
- d. Depress _(1)_ button to _(2)_. (1.0)
.o. Turn _____ off (Master Controls) and verify all power goes off. (0.5) l
.(***** END OF CATEGORY 0 *****)
22__EMEBGENCY_SYSIENS_8NQ_18EEIY_QEVICES PAGE 9 QUESTION P.01 (3.00)
Por Technical Specifications,.what three.C3) conditions must be met in order to perform any reactor vessel internal maintenance with irradiated fuel in the vessel which requires removal of both the primary and secondary closures? (3.0)
QUESTION P.02 (2.00)
Answer each part below based on Technical Specifications. (2.0)
- c. When is the reactor considered shut down for refueling purposes? (1.0)
- b. When is f uel considered to be irradiated fuel? (1.0)
QUESTION P.03 (2.50)-
- c. What process parameter is monitored, at what setpoint, to assure that irradiated fuel elements being handled with the Fuel Handling Machine are maintained less than 750 F? (1.0)
- b. What is the potential problem associated with excessive fuel element temperatures? (0.75)
- c. What non-normal condition, besides temperature, must be present for this problem to occur? (0.75)
QUESTION P.04 (2.50)
- e. What Plant Protective System scram is provided for use during fuel loading, including setpoints and logic? (1.5)
- b. How would such a scram affect fuel handling operations? (0.5) c.- If you were involved in operations from the refueling floor, what would make you aware of the scram? (0.5)
(***** CATEGORY P CONTINUED ON NEXT PAGE *****)
Ez__EMEBGENGY_SYSIEMS_8NQ_S8EEIX_QEVICES PAGE 10
-QUESTION P.05 (2.50)
- o. What is the purpose of the grapple interlock? (0.5)
- b. What conditions and logic are measured ~ or detected to satisfy the interlock?. (1.25)
- c. What condition (s) CANNOT be bypassed to satisfy the interlock? (0.75)
QUESTION P.06 (2.00)
What does each of the following alarms indicate?
- o. Plate Limit. (1.0)
- b. Servo Error. (1.0)
QUESTION P.07 (3.50)
- c. If you are working in the Reactor Building,~under what conditions should you report to your personnel accountability station? (1.0)
- b. Where is your personnel accountability station? (0.5)
- c. What are two conditions that would require that you report to the Health Physics Access Control Area when leaving the Reactor Building on the way to your personnel accountability station? (1.0)
- d. If you are the first person to report to your personnel accountability station, what should you do? (1.0)
QUESTION P.08 (2.00)
List the four (4) classif ications of emergencies in the order of INCREASING coverity. (2.0)
(***** CATEGORY P CONTINUED ON NEXT PAGE *****)
EA__EMEBGENGI_1XSIEd2_6NQ_16EEIY_QEVICES PAGE 11 QUESTION P.09- '(1.00)
What two (2) systems are identified ~ in H-3 as'possible sources of high cativity in the plant? (1.0)
QUESTION P.10 (1.00)
For what purpose is the HTFA (High Temperature Filter Adsorber) used during o LOFC (Loss of Forced Cooling) accident? (1.0) 4 f
I l
l
(***** END OF CATEGORY P *****)
n.
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F , - .
-9t__HE8LIH_EHI1101_8HQ_B8DI8I19N_ESQIECIIQN PAGE- 12 QUESTION Q.01; (2.00)
Fill in the blanks'below. Blanks may contain one or more words or numbers.-
- e. A Contaminated Area is any area in which there exists loose surface
' contamination in excess of _(1)_ and/or._(2)_. ( 1. 0 ) -
I b. A ' Radiation Area' is an accessible area .where a major portion of the whole body could receive greater than _(1)_ or _(2)_. (1.0)
QUESTION Q.02 (3.00)
~
Answer the following questions dealing with Radiation Work Permits (RWP's)..
- a. What'does your signature, as a worker, signify on an RWP? (1.0)
- b. What action should you take if you are performing work covered by an" RWP and.the-job is not completed at the end of your' shift, but will be resumed on your shift the next day? ( 1. 0 ) -
- c. What type of radiation instrument is used exclusively f or setting dose rates for personnel at FSV? C0.5) 4
- d. When entering a radiation area with a portable survey instrument, which-i~ range on the. detector should be selected prior to entry? (0.5) i QUESTION Q.03 (1.00)
State a formula which describes the relationship-between Radiation Absorbed Dose, Roentgen Equivalent Man, and Quality Factor. (1.0)
QUESTION Q.04 (3.00)
What are three (3) of the four checks which must be performed before you con use an RO - 2 to perform a radiation survey? (3.0) i a
1 a
L (***** CATEGORY Q CONTINUED ON NEXT PAGE *****)
9t__HEeLIH_EHI11CS_8NQ_B8QI8IIQN_EBQIECIIQU PAGE 13 QUESTION Q.05 (1.00)
When moving an irradiated control rod drive assembly in the ATC, where chould you, the' operator, stand in relation to the ATC to maintain your exposure ALARA? WHY? (1.0)
QUESTION Q.06 (3.00)
What are your thece (3) individual responsibilities per the radiation protection plan as listed in SUSMAP-4? (3.0)
QUESTION Q.07 (2.00)
What are four reasons for termination of an RWP? (2.0)
QUESTION Q.08 (3.00)
What requirements must YOU meet to gain access to a Health Physics controlled area? (3.0)
QUESTION HQ . 09 (2.00)
What three (3) concepts are used concurrently to accomplish the goal of controlling exposure ALARA? (2.0)
(***** END OF CATEGORY Q *****)
(*************
END OF EXAMINATION
- )
'Ut__BE8CI98_8NQ_E9EL_GH888CIEBI I191 PAGE 14 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER M.01 -(2.00)
O. The 02 content of cover gas is kept below 5% to eliminate any chance of combustion (He atmosphere is maintained). (1.0)
- b. The surface temp. of spent fuel is kept below 750 F to prevent oxidation. (1.0)
REFERENCE FSV SD 14-1, P. 3 ANSWER M.02 (3.50)
- c. Increases reactivity by removing fpp (including Xe & Sm) (1.0)
- b. Decreases reactivity by removing fissionable materials. (1.0) c.- Removal decreases react. by allowing increased neutron _ leakage. (1.0)
- d. Decreases reactivity. (0.5)
Accept NONE for b & d if' spent & depleted defined as complete.
REFERENCE FSV LESSON NO. 39.00, p. 3 ANSWER M.03 (2.00)
- m. All reflectors adj acent to fuel (0.75) are replaced at the refueling of that region (0.75) (1.5)
- b. All other reflectors (that aren't adj acent to f uel) are permanent.(0.5)
REFERENCE FH 033.00, III.A., p. 6 s
f I
Uz__BE8GIQB_8NQ_EWEL_GH888CIEBISIIGS PAGE 15 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER. M.04 (2.00)
- c. 3 (adj acent) columns
- b. 3 (adj acent )
- c. . stabilize the gaps
- d. 84 (4 answers e 0.5 es.)
REFERENCE FH 033.00, III.G., p. 10 ANSWER M.05 (2.00)
- b. Power peaking (at the core-reflector interface). (0.5)
- c. In-leaking / backscatter neutrons (from the reflector). (0.5)
REFERENCE ~
FH 033.00, III.H.1., p. 11 ANSWER M.06 (1.00) c, a, b Cor Th-232, U-233, U-235)(0.5 for each swap req'd to correct order)
REFERENCE FH 033.00, III.I., p.15
MA__BE8CIQB_8N0_EMEL_GH888CIEBISIIGS PAGE 16 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER M.07 (2.00)
- 1. ~ Fuel element
- 2. Control fuel element
- 3. Bottom control fuel element
- 4. Neutron source element (4 answers e 0.5 ea.)
REFERENCE FH 033.00.01, FSV Questions, p. 3 ANSWER M.08 (1.50) 14.2" (12~16" OK) width (0.75) by 31.2" (30~33" OK) height (0.75) (1.5)
REFERENCE FH 033.00.01, FSV Questions, p. 3
, , . , - -- - , , - ~ , - - - ~ - - - - - - - . - , , - , , , -
. . . . , . . . , - . _ . . - , - - . , - , . - . , . ,---,a
Nz__E991EMENIi_INSIBubENIeIION_eND_ DESIGN _DESCBIEIIQN PAGE 17 ANSWERS -- FT. ST..VRAIN -86/09/16-PELLET, J.
ANSWER N.01 =(3.00)
- c. A rubberized metallic "0" ring. (0.5)
- b. An inflatable seal. (0.5)
- b. 1. Provides shielding (0.5).
- 2. Serve as a platform for either.the FHM or the ATC (0.5). (1.0)
- c. 1. Differential pressure - Gate will not open unless dp above and below gate is < 1 psid.
- 2. Differential atmosphere - Gate will not open unless atmospheres are identical.
- 3. Seals inflate on loss of power.
- 4. Seal must be deflated to open gate.
- 5. Alarm if gate.is opened.
- 6. Alarm if seal pressure < 20 psig. (Any-3/6 6 0.333 ea.)
REFERENCE FSV, FH.D.49.00.01.05.06 ANSWER N.02 (1.00)
Provide accurate guidance and alignment for proper functioning of the FHM while in the PCRV penetration. (1.0)
REFERENCE SD-13-1, p.7,0 ANSWER N.03 (1.00)
Ecch well can store 14 f.1. ele. [28'h.1.) in each col. or 56 total. (1.0)
OR Ecch well can store the equiv. of 70 f. 1. ele., w/ no more than 56 fuel.
REFERENCE FSV FH 041.00, p. 7 s
k
~Nz__EDUIEMENIt_INSIBudENI6II9N_6ND_ DESIGN _DESGBIEII9N -PAGE 18 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER N.04 ( .00)
- 1. Direct helium flow (axially) into compressor-(blading). (0.0)
- 2. Monitor flow in the primary circuit. (0.0)
(Qeustion deleted, not graded. Per facility comment resolution.)
REFERENCE FH 034.00,-p. 7 ANSWER N.05 (3.50)
- c. 1. Buffer Helium makeup.
- 2. Purge helium for HFTA.
- 3. Purge helium for CRD's.
- 4. Pressurizing helium for interspace PCRV penetrations.
- 5. PCRV safety relief valves. (Any 2/5 e 0.5 ea.)
- b. 1. Fission-produced isotopes.
- 2. tritium.
- 3. dust.
- 4. condensed water.
- 5. water vapor.
- 6. carbon compounds.
- 7. hydrogen. (Any 4/7 e 0.25 es.)
- 8. noble gases.
- c. water or water vapor. (0.5)
- d. The net result is transport of core graphite into the lower temperature portions of the core (CONCEPT). (1.0)
REFERENCE FH 034.00, p. 4-9 ANSWER N.06 (2.00)
- 1. Local relay pushbuttons on level 10. (1.0)
- 2. Local ACM through hook up of flexible hoses. (1.0)
-Nt__EQUIENENIt_INSIBUNENI6IION_eWQ_ DESIGN _DESGBIEII9N PAGE 19
- ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
REFERENCE
=FH 030.00, p. 11-ANSWER ~ N.07 (2.00)
- 1. Control rod drive mechanism.
- 2. Orifice valve and drive mechanism.
2
- 3. Reserve shutdown system.
- 4. Control rod drive purge. (4 answers e 0.'5 es.)
REFERENCE-FH 031.00.01.01 ANSWER N.08 (2.50)
- c. 1. Helium purge.
- 2. RPCCW.
- 4. PCRV Aux Cooling Loops 1 & 2. (Any 3/4) l' b.. 1. Fire Water.
- 2. Booster fan.and dampers. (5 answers e 0.5 ea.)
- 3. 00S.PCRV Aux Cooling Loop. _
(Any 2/3)
REFERENCE FH 041.00.01.05.1 ANSWER N.09 (3.00)
- e. Reactor building sump. (0.5)
- c. RB sump is not normally contaminated and can be discharged from the plant separately (1.0). The effluent from the HSF is normally contaminated (1.0). (2.0) 1 i
REFERENCE FH 044.00.01.03.1 4
J
- 9 . , - - - . - . - - -.--%.,--mye---rv-,----7y c - . - m.--,- --- , - . , , _ . . . - - , . . ~ . - , , . - , , , . .m.,
Ni__EDUIEMENIi_INSIBUDENIeIIQN_8ND_ DESIGN _DE1GBIEIION PAGE 20 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER N.10 (2.00)
- 1. Elements & reflectors have dif f erent dowel pattern. (1.0)
- 2. Elements a reflectors are different weights. (1.0)
REFERENCE FH 051.00.02.01.1
-. -- . ..-. . - - - . . , - . - - - . = , . _ . -.
'92__EB9CEDUBES_eNQ_LIMII6IIQNS PAGE 21-ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
-ANSWER 0.01 -(2.00)
- c. Evacuate the RB.. (1.0)
- b. Sounding of the Radiological Alarm. (1.0)
REFERENCE FSV EP APP H-2, Rev. 51, p. 3 ANSWER 0.02 (1.00)
Nsrmally, prior to refueling a region when two control rod pairs cre retracted. (1.0)
-REFERENCE CMG-13, p. 4, 5 ANSWER 0.03 (1.00)
Moving reflector blocks (0.5) or sources. [0.5) (1.0)
REFERENCE FH 051.00.01.04.1
~ ANSWER 0.04 (2.00)
- 1. Don't move the handwheels too quickly (a servo error may result, causing the system to unclutch). (1.0)
- 2. Don't operate the handwheels when the machine is in the OFF mode. (1.0)
REFERENCE FH 051.00.01.12.1
cx
- . L e' *.
92__EBQGEQUBE1_8ND_LIMII8IIQN1 PAGE 22 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER 0 .~ 0 5 (3.00)
- 1. RIV power supply. cable. (0.5)
-2. FHM/ATC Umbilical cable or j umper plug. (0.5)
- 3. Seal source helium hose for pneumatic seals. (0.5)
- 4. Backfill hose for Helium / air. (0.5)
- 5. Vacuum (purge) hose. (0.5)
Order (Any with 1 before.3 - 0.5) (0.5)
REFERENCE FH 049.00.01.07.7 ANSWER 0.06 (2.50)
- 1. ATC storage location.
- 2. Loading port.
- 3. Fuel storage wells.
- 4. Equipment storage wells.
- 5. Reactor (during refueling conditions). (5 answers e 0.5 ea.)
REFERENCE FH 048.00.01.07.1 ANSWER 0.07 (2.50)
- 1. (With power & pneumatic hoses attached) push the " Evacuate" button (and watch gauge. (0,5)
- 2. When desired gauge value is reached, push " Push to stop cycle" PB.(0.5)
- 3. Pause to allow purge vac pumps to isolate. (0.5) 4 Select backfill method (he/ sir), turn dial to method selected, push PB until atmospheric pressure is attained. (1.0)
REFERENCE FH 049.00.01.12.2
. ANSWER 0.08 (2.50) k, b, e, g, c, h, a, i, f, j, d (10 swaps for correct position e 0.25 es.)
. , .. l
'l 02__EBQGEQUBES_8NQ_LIMII8IIONS PAGE 2:3 :
l ANSWERS'-- FT. ST. VRAIN -86/09/16-PELLET, 1 J.
I REFERENCE j FH 049.00.01.11.1 l
ANSWER 0.09 (3.50)
- c. 1. auto 2. manual (2 answers e 0.25 ea.)
- b. 1. "0FF" mode selector '(0.5)
- 2. off mode is selected.- HC1 0 ,5)
- c. Cask Valve. (0.5)
-d. 1. " Emergency Stop"- (0.5)
- 2. turn off the Z drive pumps. (0.5)
- o. Power Key Switch. (0.5)
REFERENCE FH 051.00.05.1 4-I i
f
Et__EMEBGENGl_SYSIENS_eNQ_S8EEIX_QEVICES PAGE 24 ANSWERS -- FT. ST.'VRAIN -86/09/16-PELLET, J.
ANSWER P.01 -(3.00)
- 1. The reactor vessel is depressur ized to at or below atmospheric pressure. (1.0)
- 2. The reactor average helium gas inlet temperature is </= 165 F. (1.0)
- 3. The reactor is maintained in a shutdown or refueling condition AND the reactivity of the core.is monitored continuously by at least 2 neutron flux monitors. (1.0)
REFERENCE FSV TS 4.5.2, p. 4.5-3 ANSWER P.02 (2.00)
- c. The reactor is considered shut down for refueling purposes when the-reactor mode switch is LOCKED in the " Fuel Loading" (0.5) position simultaneous with either hot shutdown or the cold shutdoun reactivity conditions (0.5). (1.0) b.. Irradiated fuel has a rad. level >/= 100 mr/hr 8 1 foot from ele. (1.0)
REFERENCE FSV TS, Section 2 ANSWER P.03 '(2.50)
- c. FHM cooling water outlet temperature (0.5) </= 150 F C0,5).
- b. Graphite oxidation. (0.75)
- c. Air ~inleakage must also have occurred. (0.75)
REFERENCE FSV TS 4.7.2, p. 4.7
.s .
Ei__EMEE9 ENC 1_SYSIEMS_eND_SeEEIY_ DEVICES PAGE 25 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER P.04 (2.50) c.- Startup count rate high, l'out of 2 logic, >/= 1.0E+5 (3 answers e 0.5) b.. Cease all. internal maintenance / fuel handling until safe. (0.5)
-c. Operator would advise OR' Facility Hazard alarm on FHM censole. -(0.5)
REFERENCE FSV EP APP B-1,-p. 2, 11 ANSWER 'P.05 (2.50)
- a. Protects against dropping of a grappled element. -(0.5)
- b. All of the following conditions must be met: (0.5)
- 1. At least 1~ dowel pin engaged. (0.25)
- 2. The plate is raised. (0.25)
- 3. Probe weight < 50 lbs. (0.25) (1.25)
- c. The probe' weight condition cannot be bypassed. (0.75)
REFERENCE FSV LESSON NO. FH 051.00, p. 66,67 ANSWER P'.06 (2.00)
- c. Grapple head plate above +2.5". (1.0)
- b. Z, R, Theta servo loop position error excessive. (1.0)
REFERENCE FH 051.00.02.02.1
'Et__EMEBGENGl_212IEMS_8NQ_38EEII_DE*i1CES PAGE 26 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER P.07 (3.50)
- c. Fire (0.5) or Radiological (0.5) alarm. (1.0)
- b. Lunchroom. (0.5)
- c. 1. . Contamination (> ?x background) found at exit monitor.
- 2. Exit via crash bars or emergency exits (due to imminent danger).
- 3. Exit monitors ~show > 500 cpm background. (Any 2/3 0 0.5)
- d. Verify ratemeter operating properly (0.5) & not alarmingoCO.5). (1.0)
REFERENCE FSV G-5, p. 3, 4, 7, 11 ANSWER P.08 (2.00)
- 1. Notification of' Unusual Event.
- 2. Alert.
- 3. Site Area' Emergency.
- 4. General' Emergency. (4 answers e 0.5 ea.).
REFERENCE SSLO Procedures Self-Study Guide, p. 26, for RERP, Section 4 ANSWER P.09 (1.00)
Sys. 13, Fuel Handling Purge. Sys. 13, FH Purge
.Sys. 63, Gas Red. Sys. 14, Fuel Stor. Bldg.
Sys. 14, Fuel Storage Building. Sys. 21, He Circ Aux.
Sys. 23, He Pur. Sys. 22, Sec. Cool. (SJAE & HRH)
Sys. 11, PCRV Aux piping. (Any 2 8 0.5 ea.)
REFERENCE SSLO Procedures Self-Study Guide, p. 35, for EP H-3
+
t +9 g 27
~
E2__EDEBGENGI_SISIEMS_eNQ_SeEEII_ DEVICES PAGE ANSWERS -- FT.:ST. VRAIN -86 / 09 /,16- P ELL E T , J.
ANSWER P.10 (1.00) .
A The HTFA'are used to begin depressurization of.the primary system ty"
-.rcmoval of primary coolant (CONCEPT). (1.0) o REFERENCE ,'
FH 035.00, p.-23 t
i u
\
v s
t 4
k~
' ?.
1 4
1
?
l J
t
92__HE8LIH_EUISIGS_8ND_B8016IIQN_EB9IEGIIDN PAGE 28 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J.
ANSWER Q.01 (2.00)
- 10. 1. 1000 dpm/100 sq cm beta-gamma. (0.5)
- 2. 10 dpm/100 sq cm alpha. (0.5)
- b. 1. 2.5 mrem in i hour. (0.5)
- 2. 100 mrem in 5 consecutive days. (0.5)
' REFERENCE FH 060.00, p. 3, 4 ANSWER Q.02 (3.00)
- e. That you understand the job requirements (CONCEPT).- (1.0)
- b. Return white copy to SS. (1.0)
- c. Ion chamber.- (0.5)
- d. . Start'on the highest range (1 range down ...). (0.5)
REFERENCE FH 058.00, p. 14; FH 059.00, p. 6, 11 ANSWER Q.03 (1.00)
Rod
- QF = REM (1.0)
. REFERENCE FH 058.00.01.04.1 ANSWER Q.04 (3.00)
- 1. Inspect for physical damage.
- 2. Check for current calibration.
- 3. Perform battery check.
- 4. Verify response to a known source. (any 3/4 e 1.0 es.)
REFERENCE
'FH 059.00.0.03.1
's !
j i
92__HE8LIH_EHISICS_8HD_B8018IION_EB9IECIIQN PAGE 29 1 ANSWERS -- FT. ST. VRAIN -86/09/16-PELLET, J. i ANSWER Q.05 (1.00) l Stand near the ATC - its shielding design generally produces lower dose rctes there. (1.0)
REFERENCE FH 060 00.01.01.1
. t ANSWER Q.06 (3.00)
, 1. Follow procedures and practices, to maintain exposure ALARA. (1.0)
- 2. Identify to supervisor, rad. work procedures & practices that need to be upgraded. (1.0)
- 3. Request & attend-rad. prot. training sufficient to discharge assigned responsibilities. (CONCEPT for all 3) (1.0)
REFERENCE SSLO Procedures Self-Study Guide, p. 28, for SUSMAP-4 ANSWER Q.07 (2.00) 1.. Time expired.
- 2. Job completed.
- 3. Job cancelled.
- 4. Conditions change. (4 answers't 0.5 ea.)
REFERENCE FH 058.00, p. 15
\
9 A
a e
sf 9t__HE8LIH_EHYSIGS_8HD_B8018IION_EBQIECIION PAGE :30 ANSWERS -- FT. ST. VRAIN -36/09216-PELLET, J.
it l '
' i ',
ANSWER Q.08 (3.00)
- 1. HP Tech accompanied, (0.75)
OR C0.25)
- 2. RWP, (0.75)
OR i 3. under HP direction (operators only) (NOT REQUIRED FOR FULL CREDIT)
AND (0.25)
- (3 4. HP authorization. (1.0)
REFERENCE FH 058.00.01.07.1
~ ANSWER Q.09 (2.00)
- 1. Time (of exposure should be minimized). (3 answers e 0.667 ea.)
- 2. Distance-(from source should be maximized).
- 3. Shielding (f rom the source should be_ used whenever possible).
REFERENCE FH 060.00, p. 5
)
1
.,-.,m. _ , _ . - .. _. . . _ _ ,
i l
TEST CROSS REFERENCE. PAGE l' QUESTION .VALUE REFERENCE
.M.01 2.00 JJP0001037 M.02 3.50 JJP0001038 M.03 2.00 JJP0001058 M.04 2.00 JJP0001059 1 M.05 2.00 JJP0001060 l M.06 1.00 JJP0001061 M.07 2.00 JJP0001062 M.08 1.50 JJP0001063 16.00 N.01 3.00 JJP0001039 N.02 1.00 JJP0001040 N.03 1.00 JJP0001041 N.04 .00 JJP0001064 ,
N.05 3.50 ' JJP0001065 N.06 2.00 JJP0001066 N.07 2.00 JJP0001067-N.08 2.50 JJP0001068 N.09 3.00 JJP0001069 N.10 2.00 JJP0001070 20.00 l 0.01 2.00 JJP0001042 0.02 1.b0 JJP0001043 0.03 1.00 . JJP0001044 0.04 2.00 . JJP0001045 0.05 3.00 JJP0001071 0.06 2.50 JJP0001072 0.07 2.50 JJP0001073 0.08 2.50 JJP0001074 0.09 3.50' - JJP0001075 20.00 P.01 .3.00 JJP0001046 P.02 2.00 JJP0001047 P.03 2.50 JJP0001049 P.04 2.50 JJP0001050 P.05 2.50 JJP0001051 '
P.06 2.00 JJP0001076-
.P.07 3.50 JJP0001077 P408 2.00 JJP0001078 P.09 1.00 JJP0001079
'P.10 1.00 JJP0001080 22.00 Q.01- 2.00 JJP0001053-
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TEST CROSS REFERENCE PAGE 2 QUESTION ~ VALUE REFERENCE Q.02 3.00 JJP0001054 Q.03 1.~ 0 0 JJP0001055 Q.04 -3.00 JJP0001056 Q.05 1.00: JJP0001057_
Q.06 3.00 JJP0001081 Q.07 2.00 JJP0001082' Q.08- 3.00 JJP0001083 Q.09 2.00- JJP0001084
____~_
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SPEED VALVES FEEDWATER FLOW SC SM pq 105 %
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> SIGNAL TO ATTEMPERATORS STEADY STATE CONTROLS l
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INSTA-Col.0R
. ... .... c..--*
,. .- a .
Public Service Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 September 24, 1986 Fort St. Vrain Unit No. 1 P-86564 M @ M OW/ M -- N.
Mr. Ralph Cooley, Section Chief !
Operating Licensing Group $@ 2 5126 :
U. S. Nuclear Regulatory Commission y Region IV -
611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Docket No. 50-267
SUBJECT:
NRC Administered Examinations
Dear Mr. Cooley:
The purpose of this letter is to provide comments to the NRC on the Licensed Requalification, SRO Upgrade, and Special Senior Licensed Operator (Fuel Handler) examinations administered at Fort St. Vrain the week of September 15, 1986.
In general, the examinations were fair and applicable to the Fort St.
Vrain facility. However, we have a few concerns which are listed in Attachments 1 through 4.
Any comments or questions concerning this matter should be made to M. H. Holmes at (303) 480-6960.
Sincerely, JLC4 im IAf d Pl6b J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG/s1 Attachments.
l 1
I' ATTACHMENT 1 REVIEW OF REACTOR OPERATOR REQUALIFICATION EXAMINATION 1.01 A. Acceptable B. This is a valid _ question, however, should also accept the following answer with the proper assumption.
Assumption: Define spent _ fuel as fuel that has been-completely depleted, with no fissionable material remaining. Under this assumption, removal of the spent fuel would cause no change in core reactivity,.as it has no fissionable . material remaining and is no longer contributing to the reactivity of the core. Could in fact consider this as an increase in core reactivity as poison is removed.
C. Acceptable D. This. is a valid question, however, should also accept the following answer with the proper assumptions.
Assumption: Depleted is defined as the source ~has decayed to the point that it is producing virtually no neutrons.
Under this assumption, removal of the source would ha,a little or no effect on core reactivity, as it is produci..;
no neutrons.
1.02. Acceptable 1.03 Acceptable 1.04 . Acceptable 1.05 Acceptable 1.06 -A. Acceptable B, This is a valid question, however, should also accept enhances -flow stability.
Reference:
HTGR Technology Course 1.07 Due to the numerous ways that this question may be answered utilizing the assumptions listed below, this is an invalid question. The intent of the question is valid and has in fact been utilized at Fort St. Vrain in-the past. Since there are better questions. to determine an individuals knowledge of Xenon, we at Fort St. Vrain no longer include this question in our training. Should also accept the following answers:
Assumption: Assume power reductions can be treated as step
-changes for purposes of fission product poison transient analysis.
.g.
General: Differences between the two scenarios will be.
primarily due to changes in~ Xenon-135 concentration (and therefore reactivity) with time following the downpower maneuver. Following a downpower, the Xenon-concentration will vary.with time as is shown on the following graph:
. N-a9 s Y,# ss.*v +;**'.
%v.
~.
' !! l f
+._)
f I a
i
- f-6 % y,-fr/ w 6%
The maximum Xenon concentration occurs at approximately 5-6 hours following the power transient; therefore, this. is the time at which the largest negative reactivity is inserted due to the Xenon. After this time, the Xenon concentration decreases to an equilibrium value at about 40-50 hours following the transient.
Note: As long as the candidate exhibits knowledge.of the above, a number of solutions are correct, depending upon the assumptions made.
CASE 1 Explanation: In the slow downpower, more time is allowed over which Xenon will be inserting negative reactivity.
Therefore less negative reactivity must be inserted via the control rods. Therefore, the rod height to achieve 50% power will be higher for the slow downpower. After equilibrium is reached, this will result in a higher final power for the slow maneuver.
Answers:
A. Fast will require most. rod insertion B. Slow will have higher final, steady state power level C. Xenon will not reach equilibrium until 40-50 hours following this maneuver (due to the 6.6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> half-life of the Iodine and the 9.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> half-life of the Xenon-135). It will therefore take 40-50 hours for power to stabilize following the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> maneuver.
CASE 2 Explanation: Assuming a step decrease in power, for purposes of analyzing changes in Xenon-135 concentration, and Xenon peak occurs at time =5 hours.
f
-~---n y-t stu WS e.- - ,.
L '
- re y I
1
For the rapid downpower, Xenon is peaking, inserting negative reactivity. At tine =2 hours, Xenon reactivity (negative) will be at a higher value than -at time =10 hours. The faster downpower will, therefore, require less negative reactivity due to control rods to achieve the 50% power level. As rod height
'will be higher in this case, final reactor power will be higher. It will require 40-50 hours for Xenon to reach
-equilibrium value for 50% power.
Answers:
A .. Slow will require most rod insertion B. Fast will have. higher final steady state power C. Same~as (C) above.
CASE 3 Assumption: Assume the downpower is not a step change, but a ramped change (see graph below).
N.$p
- n. .
l N% ov%
With a step change in power, the Xenon concentration will peak at a given value in 5-6 hours, then decrease to a new equilibrium in 40-50 hours.
With a ramp change, the Xenon transient is less easily predicted.
With a rapid change (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />), the Xenon burnout will drop at the same rate as the flux drops (dominant means of loss), the I-135 to Xenon-135 decay will occur with a constant 6.6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> half _-life (dominant means of production). Therefore,-the Xenon peak will be lower, and will occur later (time) than with a step change.
With a slow change (10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />), the Xenon burnout will again drop at the same rate as the flux drops-(slower, in this case) and the I-135 to Xenon-135 production will occur with the constant 6.6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> half-life. The Xenon peak will be lower still, and later (time) than in either a step change or a rapid ramp change.
Therefore, the slo er downpower (10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />) will have the least amount of Xenon contributing negative reactivity.
Therefore, more negative reactivity must be inserted with' the-control rods (i.e. rod height will be lower), and therefore final reactor power will be lower.
Answers:
A. Slow will require most rod insertion B. Fast will have higher steady state power level C. 40-50 hours 1.08 Acceptable 1.09 This is an acceptable question, however, should also accept that steam temperature decreases, lowering cycle efficiencies.
2.01 Acceptable 2.02 A. Acceptable B. .This is a valid question, however, should also accept the following impurities:
CH4, Kr, Ar, Xe, CO, (LTA is designed to remove everything except Helium and Hydrogen, with Hydrogen being removed in the Hydrogen Getter.)
Reference:
E0-065.00 pp. 11, 13-17.
2.03^ A.
. This is a valid question, however, should accept PCRV Auxiliary cooling loop 1 or loop 2 as both loops are 100%
capacity and each should be considered as a single source of cooling.
Reference:
FH C41.00.01.05.1 B. This is a valid question, however, should also accept the out of service 46 system auxiliary loop as this is considered as a backup supply.
Reference:
FH 041.00.01.05.1 2.04 Acceptable 2.05 This is a valid question, however, should also accept the maximum scram insertion time of 152 seconds as stated in the Technical Specifications.
2.06 Acceptabl.e 2.07 Acceptable 2.08 Although a Reactor Operator should be able to answer this question due to his prior qualification as an Equipment Operator, we feel this question is invalid as it has no direct impact on his job performance in the control room and should not be used on any future license examinations.
2.09 A. This is a valid question, however, should also accept loss of the three room complex (as defined per Technical Specifications) with a LOFC.
B. This is a valid-question, however, the following answers should also be accepted: Fire Protection System (System 45), Service Water System (System 42), Helium Purification System (System 23), Liquid Nitrogen System (System 25),
Purification Cooling Water System (System 47), Circulating Water. Makeup System (System 41), Reserve Shutdown System (System 12), Reactor Plant Ventilation System (System 73),
and Selected Plant Lighting.
Reference:
EO 087.00, pg 14.
3.01 A. Acceptable B. This is a valid question, however, the question should be reworded to ask the setpoint of the high pressure scram.
The setpoint is less than or equal to 53 psi above rated, programmed with load. Upper programmed limit set to produce trip at less than or equal. to 775 psia.
Reference:
Technical Specifications, Section 3.3. Due to the fact that the master setpoint. list and the design.
setpoint list may differ (this is true for all setpoints), ,
training teaches the high pressure scram setpoint as 50 psi above normal. This answer should also be accepted.
The answer of 840# is incorrect'and should be removed from your answer key.
3.02 This is a valid question, however, should also accept two-loop trouble scram initiated by 4 circulator trip as this is the PPS signal that initiates an immediate turbine trip.
3.03 Acceptable 3.04 Acceptable
^
3.05. This is a valid question, however, the point distrioution should not be limited to verbatim answers as given in the answer key. Due to the complexity of the steady state control system, the answers may be longer and more in-depth than the answer key. Therefore, the answer should be valued for the t
overall concept versus verbatim answers.
3.06 A. This is not a valid question. Although this was taught in class, further research showed that the statement is false.
This information was not relayed in time to the trainees and NRC and this question should be thrown out. All other questions on 3.06 are valid.
3.07 This is a valid question, however, the locations are not asked in the question and should not be required in the answer.
3.08 A. Acceptable B. This is a valid question, however, should also accept mitigation of a large air leak at the air dryer.
3.09 Acceptable 4.01 Acceptable
4.02 Acceptable 4.03 Acceptable 4.04 . Acceptable 4.05 .A. Acceptable B. This is: a valid question, however, should also accept adjust orifice valves to maintain. equal core outlet temperatures or minimize mismatches.in the core regions.
Reference:
50P 12-04, Issue 12 4 OE Acceptable 4.07 Acceptable 4.08 Acceptable 4.09 This is a valid question, however, credit should be given if the individual shows understanding of the concept stated in the answer key instead of requiring verbatim wording of an Administrative Procedure.
c . _ _ _ _ _ _
c ATTACHMENT 2 REVIEW OF SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION 5.01 Same comment as 1.01 5.02 Acceptable 5~.03 'A. Acceptable B. This is a valid question, however, should also accept reducing the irradiation of the core barrel and liner.
C. This is a valid question, however, should also accept "backscattering" in lieu of "in-leakage".
5.04 This is a valid question, however, we feel that the understanding of the concepts involved with bypass flow are more important than the key words orfphrases that are listed in the answer key. Therefore,- credit. should be given if the individual shows understanding of the concept.
5.05 This' is a valid question, however, we feel that the understanding of the concepts involved are more important than the key words or phrases that are listed in the answer key.
Therefore, credit should be given if the individual shows understanding of the concept.
5.06 This is a valid question, however, should also accept that NTC will become smaller in magnitude or NTC will have a lessening effect.
5.07 Acceptable 5.08 This is an acceptable question, however, should also accept the following answers:
- 10. High power production at hot spot
- 11. Low helium flow at hot spot
- 12. High heat flux
- 13. Unequal coolant flow distribution within a region caused by uneven power production within a region.
Reference:
- FSAR 3.5-14 and 3.6-5 5.09 A. This is a valid question, however, should also accept a closed discharge valve allows pump pressure to increase to operating pressure rapidly to prevent damage to the pump.
Reference:
R0 118.00, pg 16 of 34 B. Acceptable 6.01 Same comments as 2.02.
.: a. ..
6.02 Acceptable 6.03 Same comments as 2.03 6.04 Same comments as N.09 6.05 Same comments as 3.05 6.06 Same comments as 3.06 6.07 Same comments as 3.01 6.08 Same comments as 3.02 6.09 Acceptable 7.01 A. Acceptable B. This is an invalid question, as there.are a multitude of places that non-operations personnel ' report which are delineated in Attachment G-5A pages 11 and 12 of 12. The correct answer to' this question .is any one of the accountability stations. ' Re ferer.ce : G-5, pg 3 of 12 (4.3.1).
C. This is a valid question, however, the understanding of the concept and not memorization of the . numerical values is important, therefore, the correct answer should be: 1.
When not able to card out of the reactor building (concept). 2 When. contaminationfis found at the exit monitor (concept). 3. When high background is present at the exit monitor (concept).
D. This is a valid question, however, should also accept determine habitability.
Reference:
GE 020.00 pg. 2 and G-5'pg. 6 step 4.5.
7.02 Acceptable 7.03 'AcceptableL 7.04 This is a valid question, however, should also accept any unexplained reactivity change deemed unsafe by the operator.
Reference:
EP E follow-up action 3.6 ,
! 7.05 Acceptable
, 7.06 -Acceptable
'7.07 -Same. comments as 4.05 7.08 This is an acceptable question, however, we would like to have the. reference.
8.01 Acceptable l
l l
8.02 'This is a valid question, however, should also accept the following two answers.
Reference:
APM P3, pg 5, Issue 12, step 4.5.3
- 2. Category III workers as described in 5.2 references are allowed to enter RWP areas. Other personnel and visitors are allowed entry only after approval of . Radiation Protection Manager or his delegate. HP must be notified prior to entry into any'RWP area.
Reference:
SUSMAP 5, pg2, Issue 1, steps 3.5.1-3.5.3 8.03 Acceptable 8.04 Acceptable 8.05 This is a valid question, however, the LSO is not~ required ts report (he would report as fire brigade member), the Technical Advisor is not required to report (would report on call out),.
and the Senior HP Technician is also required to report to the control room.
Reference:
APM G-5, pg 6, step 4.4.1 8.06 A. Acceptable B. This.is a valid question, however, should also accept that the person the key was issued to will retain possession of the key until he has returned the key to the Shift
. Supervisor.
Reference:
SMAP 12, pg ' 2, Issue 2, step 4.1.2 8.07 Same comments as 4.09 8.08 Acceptable 8.09 A. This is a valid question, however, the following answers should also be accepted:
- 1. Assure the safety of personnel working on or servicing plant equipment.
- 2. To notify operating personnel when equipment is not available.
- 3. To indicate what steps are necessary to restore the system to normal.
(Concept for all parts)
Reference:
APM P-2,-pg 2, Issue 13, step 3.2.1
ATTACHMENT 3'.
REVIEW 0F SENIOR REACTOR OPERATOR UPGRADE EXAMINATION 5.01 Same comments as 1.01 5.02 Acceptable 5.03 Same comments ~as SRO Requal 5.03 5.04 Acceptable 5.05 Same comments as SR0 Requal 5.04 5.06 Same comments as SRO Requal 5.05 5.07 Same comments as SRO Requal 5.06 5.08 Acceptable 5.09 Same comments as SR0 Requal 5.08 5.10 Same comments as SR0 Requal 5.09 5.11 A. This is a valid question, however, should also accept that due to the bi-metallic weld between EES and Superheat II is sensitive to thermal shock.
Reference:
R0 129.00, pg 17 Parts B and C are acceptable.
5.12 -The discussion presented in 1.07 also applies to this question.
The answers associated with each assumption stated in.part B of 1.07 are the correct answers.for this question.
6.01 Acceptable 6.02 Same comments ~as 2.02 6.03 Acceptable 6.04 Same comments as 2.03 6.05 Same comments as N.09 6,06 Same comments as 3.05 6.07 Same comments as 3.06 6.08 Same comments as SR0 Requal 5.05 a6.09 Same comments as 3.01 6.10 Same comments as 3.02
.c .* .
6.11 Acceptable 6.12 Acceptable 7.01 Same comments as SR0 Requal 7.01
~
- 7. 02 Acceptable 7.03 Acceptable 7.04 Same comments as SRO Requal 7.04 7.05 Acceptable 7.06 Acceptable 7.07 Same~ comments as 4.05 7.08 Acceptable 7.09 Acceptable 7.10 Acceptable 7.11 Acceptable 8.01 Acceptable 8.02 Same comments as SRO Requal 8.02 8.03 Acceptable 8.04 Acceptable 8.05 Same comments as SRO Requal 8.05 8.06 Same comments as SRO Requal18.06 8.07 Same comments as 4.09 8.08 Acceptable 8.09 Same comments as SR0 Requal 8.09 8.10 Acceptable 8.11 This is an invalid question as rote memorization of the-Technical Specifications is'not a requirement of the Senior Reactor Operator. However, the recognition and interpretation of Technical Specifications is a requirement of the Senior Reactor Operator. Therefore, future questions. regarding Technical Specifications should be on . recognition and
-interpretation and the Technical Specification should be available for reference.
8.12 Same comments as 8.11.
, < e .
ATTACHMENT 4 REVIEW 0F SPECIAL SENIOR LICENSED OPERATOR (FUEL HANDLER) EXAMINATION Evidently there.is a discrepancy in the category values between what is stated in the PSC TPAM and the values on this examination.
Our values are:
Category M - 20% 5%
Category N - 20% 1 5%
Category 0 - 30% 1 5%
Category P - 15% i 5%
Category Q - 15% 5%
REVIEW OF QUESTIONS AND ANSWERS Category M M.01 Acceptable M.02 Acceptable, however, reference probably should be FH 039.00, pages 2-4 (same comments as 1.01, R0 Requalification).
M.03 Same comments as 5.02, SR0 Requalification M.04 Acceptable M.05 Same comments as SRO 5.05)
M.06 Acceptable, however, answer contains a typographical error which should read: c,a,b,[ orth-232,U-235, U-233] (Note:
U-235 was listed twice)
M.07 Acceptable M.08_ Acceptable Category N N.01 Acceptable - Reference probably should be FH 049.00, pages 11-13 instead of past _ examination question FH 049.00.01.05.5.
This would allow using both objective FH 049.00.01.05 and FH 049.00.01.06 as references for answers. This question utilizes both objectives.
N.02 Acceptable
O < D ^ s=
~
N.03 Question and answer as stated are incorrect. However, the intent.is valid. Question wording asks for information which is partially variable. Question should ask for:
- 1) Maximum capacity in fuel elements (4 outer columns X 14 fuel elements per column = 56 fuel elements maximum).
Fuel may only be stored in outer columns. Fuel is only full' length.
- 2) Maximum equivalent capacity in reflector elements (all 5 columns X equivalent of 14 full length elements = 70 equivalent full length reflector elements, assuming FSW only held reflector and no fuel). Reflector may be stored in all 5 columns (4 outer plus center), and reflector could be full,-half, or three-fourths length elements.
ANSWER as stated is incorrect. Total well capacity is the equivalent of 70 full length elements, with a maximum of 56 fuel elements. Fuel is only full. length elements. Reflector length can be full, half, or three-fourths length.
A better reference is FH 041.00, page 7.
N.04 Question does not apply to fuel handler duties. An extra sheet (attachment 2) was enclosed with letter P-86318, which stated "FH 034.00 is given as information only, as helium circulator internals do not pertain to licensed fuel handlers. No test was given for this lesson plan." This lesson plan was presented at the option of the fuel handler candidates purely out of their interest in knowledge of the overall reactor system at Fort St. Vrain and will not be included in fuel handler training in the future.
N.05 Acceptable - same comments as 6.01. Also reference stated is incorrect. Reference should be FH 035.00, pages 4-9. Answer
.a.4. should be "...for PCRV penetration interspaces."
N.06 Acceptable N.07 Acceptable N.08 Same comments as 6.03, SR0 Requalification N.09 Acceptable. Reference should be FH 044.00.01.03.1 and FH 044.00.01.04.1. In addition, FH 043.00.01.03.1 shows that the HSF floor drains discharge through System 61 (decontamination system), and by valve alignment can be drained to a draining station, routed for recycle of system 61, or discharged to the liquid waste sump. Therefore, any of these answers is acceptable.
N.10 Acceptable
, s, .. ..
Category 0 0.01 Acceptable 0.02 Acceptable 0.03- Acceptable 0.04 Acceptable 0.05 Question as stated is incorrect. However, the intent is valid.
The -question should read "... Reactor isolation valve..."
Answer as referenced in FH 049.00, pages 10 and 11 was placed in the referenced sequence to aid clarity. The only two critical sequential steps are: RIV power supply cable must be connected before seal source helium hose for pneumatic seals.
The oth'er steps were listed only to identify the actions and need not be sequential.
0.06 Acceptable 0.07 Question as stated is incorrect. Should be "What are the four.
(4) steps required..."
0.~ 08 Acceptable. It is important to note that these ' steps are presented in detail in the Fuel Handling Procedure checklists
.and are in actuality not necessary to memorize since they are checked off. sequentially as performed when setting an RIV as per the FHP. For example: c and e could be performed at the same time, and g could be performed after h.
0.09 Acceptable Category P P.01 .Same comments as SR0 8.11 P.02~ Acceptable P.03 Acceptable P.04 Question acceptable. Answer c. should be "... advise or facility hazard. . ."
P.05 Acceptable
e
, < .a .
-4_
P.06 Question acceptable. However, answer.b. must be clarified for Servo error. A Servo error indicates that the difference is too great between commanded and actual machine position, or words to that effect. The circuit utilizes only analog signals and not digital in this instance. Therefore, the answer referenced by question FH 051.00.02.02.1 is correct except
"(analog.and digital positions do not agree)" and in the future will be corrected for that question. The information in the lesson is correct .and should be used for the reference.
~ Reference is FH 050.00, page 50.
P.07. Acceptable P.08 Acceptable P.09 Question as stated is incorrect. However, the intent is applicable. The question should read, "What two fuel handling related systems ..." in order to get the referenced answer. As written, the possible answers to this question could be any two of the following per Emergency Procedure H-3, Section 2.1.
a) System 63, Radioactive Gas Waste b) System 23, Helium Purification c) System 11, PCRV Auxiliary Piping d) System 13, Fuel Handling Purge e) System 14, Fuel Storage Building f) System 21, Helium Circulator Auxiliaries g) System 22, Secondary Coolant (SJAE and HRH)
P.10 Question acceptable. Answer as stated is incomplete. Answer per FH 035, Pages 23 and 24 is that HTFA is utilized to cool helium flowing through HTFA (during depressurization) by
-insertion of pipe spools to utilize System 46 PCRV cooling water to cool the helium. This in turn protects other helium purification system components from the high temperatures at a LOFC during depressurization. Normal helium purification and depressurization helium flowpath is through HTFA.
Category Q Q.01 Acceptable Q.02 Acceptable Q.03 Acceptable Q.04 Acceptable Q.05 Acceptable Q.06 Acceptable Q.07 Question acceptable. Answer 3. as stated is incorrect, and should be job cancelled. Job completed, which is redundant to
- 2. Reference should be FH 058.00, Page 15.
-- g g*43 b
, -s-Q.08 Acceptable Q.09 Acceptable 1
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