ML20196C070
| ML20196C070 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 02/05/1988 |
| From: | Burdick T, Mark Daniels, Miller R, Sullivan M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20196C032 | List: |
| References | |
| 50-341-OL-87-01, 50-341-OL-87-1, NUDOCS 8802120232 | |
| Download: ML20196C070 (117) | |
Text
{{#Wiki_filter:_ _ _ _ , t U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-341/0 L-87-01 Docket No. 50-341 License No. NPF-43 Licensee: The Detroit Edison Company 6400 North Dixie Highway Newport, MI 48166 Facility Name: Fermi 2 Nuclear Plant Examination Administered At: Fermi 2 Nuclear Plant, Newport, Michigan Examination Conducted: December 15-18, 1987 Examiners: R. Miller # # Ph
/ Date M. Sullivan '
2[fd8 M. Daniels
/
U f N8 Date Approved By: T. M. Burdick, Chief Operator Licensing Section Date ffl88
/
Examination Summary Examination administered on December 15-18, 1987-(Report No. 50-341/0L-87-01). Written and oral examinations were administered to one Senior Reactor Operator (SRO) candidate and five Reactor Operator (RO) candidates. Results: The SR0 candidate passed the written examination, however, he failed to pass the simulator portion of the operating test. Four of the five R0 candidates passed the written examination; and all five R0 candidates l passed the operating test. I 8802120232 800200 , PDR ADOCK 05000341 ; V PDR 1 i
REPORT DETAILS
- 1. Examiners R. Miller, Chief Examiner M. Sullivan M. Daniels-
- 2. Exit Meeting r
At the conclusion of the site visit, the examiners met with facility representatives. The following personnel. attended this exit meeting: Facility Representatives B. R. Sylvia, Group Vice President W. S. Orser, Vice President Nuclear Operations T. Randazzo, Director Regulatory Affairs G. R. Overbeck, Director Nuclear Training R. W. Bovinet, Work Leader, Operator Training Programs NRC Representatives G. M. Nejfelt, Principal Examiner, NRC R. Miller, Chief Examiner, Sonalysts, Inc. M. Sullivan, Examiner, Sonalysts, Inc. M. Daniels, Examiner, Sonalysts, Inc. The following items were discussed during the exit meeting:
- a. No generic training weaknesses or strengths were observed during the operating examinations. (This comment was further substantiated upon review of examination results in NRC Regional Offices).
- b. Security and radiological accesses for examiners to the plant did not result in any undue delays, except for the first examiner to go through security each day with approximately a 20 minute delay.
- c. Status of the suspension of NRC Requalification Examinations was )
discussed,
- d. Active versus inactive license status in accordance with 10 CFR 55 l as it applies to a Senior Reactor Operator Limited to Fuel Handling License was discussed.
- 3. Examination Review Responses to licensee's comments, concerning the written SRO and R0 examinations are provided in Attachment 1 ,nd Attachment 2, respectively.
Other modification or clarification of these examinations is presented in Attachment 3. i 2 l l I
ATTACHMENT 1 FERMI 2 NUCLEAR PLANT-FACILITY COMMENTS AND NRC RESOLUTIONS SENIOR REACTOR OPERATOR EXAMINATION DECEMBER 15, 1987
- 5. 01. a Facility Comment: Also accept the change in reactivity caused by a change in void fraction OR mathematically as delta k/k/% voids.
Reference:
Fermi Reactor Theory, Section 8.2.1, Void Coefficiant of Reactivity. NRC Resolution: Comment accepted. The answer key was revised to include for full credit, "delta k/k/% voids." 5.02 Facility Comment: Answer should be rephrased to state that this amount of reactivity is equal to that contributed by delayed neutrons, removing dependence on delayed neutrons to maintain criticality.
Reference:
Reactor Theory, Section 10.6.6., Prompt Critical NRC Resolution: Comment accepted. Alternate wording is acceptable. No change to answer key was warranted. i 5.03.b Facility Comment: The question asks why the final speed for 90% power is greater than the initial speed for 90% power. If the statement is made that "The final equilibrium xenon _ concentration is greater than the initial xenon concentration, therefore a higher flow rate is necessary to produce 90% power," full credit should be given. As asked, the question does not require any further discussion of the changes in xenon concentration and the partial point values assigned in the answer key are inappropriate.
References:
Fermi Reactor Theory, Section.9.2.5, Maneuvering Xenon Fermi Reactor Theory, Figure 9-4, Up-Power Maneuver e e .- -, - ,. , - e- -. , ,.
J NRC Resolution: Comment accepted. The answer key was abbreviated to read:
~
"The 90% equilibrium xenon concentration adds more negative reactivity than the 60% equilibrium xenon
- oncentration. (1.00)"
6.02.a Facility Comment: "Maintain negative pressure within.the secondary
. containment," or words to this effect~should be given full credit. Candidate may respond from the point of view of maintaining the negative pressure in the secondary containment (following containment isolation and Reactor Building trip i due to LOCA signals) rather than provide the basis.
Reference:
Fermi Student Handout on Standby Gas Treatment System, pp 14-15. NRC Resolution: Comment accepted. Answer key was revised to gi/e full credit for alternate answer to maintain negative pressure within the secondary
. containment.
6.02.b Facility Comment: Reactor vessel low water level also acceptable as more specifically Level 2 and High radiation , level on the refuel floor also acceptable as more specifically Fuel Pool High Radiation. ,
Reference:
Fermi student Handout on Standby Gas
. Treatment System, p. 8.
NRC Resolution: Comment accepted. Also added to answer key were two items from Fermi Lesson Plan, 03-15-66, HVAC SYSTEMS, Revision 4, Sections F.3.b and l F.3.c, pages 9 and 10. The answer key was revised ; to read:
"b. -
high drywell pressure reactor vessel low water level (Level 2) high radiation level in the reactor building ventilation exhaust high radiation level on the refuel floor (i.e., fuel pool high ; radiation) ' loss of offsite power 2
- reactor building pressure +/- 2 inches water of atmospheric pressure
[Any 4 of 6 with 0.50 point for each answer]." 6.03 Facility Comment: Also acceptable are words to the effect that "The second shutdown cooling loop provides a backup means to ensure there is a sufficient alternate method of coolant mixing provided.
Reference:
Fermi Technical Specification (TS) Bases 3/4.4.9, Residual Heat Removal NRC Resolution: Comment accepted. Equivalent wording, such as, "backup means" to connote single failure considerations is acceptable. No change to the answer key was warranted. 6.06 Facility Comment: Also acceptable is 117 seconds as time delay. This is the allowable value.
Reference:
Fermi TS Table 3.3.3-2. NRC Resolution: Comment accepted. The answer key was revised to provide a tolerance range for the time delay and to read:
"The ADS [ Automatic Depressurization System]
valves will CLOSE (0.50) FOR 105 +/- 12 SECONDS (0.50); AND THEN WILL RE0 PEN (0.50) (if the low water level signal is still present)." I: 6.08.c Facility Comment: HPCI flowrate = 5000 to 5200 gpm RCIC flowrate = 600 to 640 gpm
References:
Fermi POM 23.202, HPCI, pp. 8 and 11
- Fermi POM 23.206, RCIC, pp. 3, 8, and 12.
NRC Resolution: Comment accepted. The answer key was revised to provide tolerance ranges for HPCI and RCIC flow rates. The answer key was revised to read:
"c. HPCI flow rate = 5,100 +/- 100 gpm (0.50)
RCIC flow rate = 620 +/- 20 gpm (0.50)" 3 4
, , , . . .. _ . . _ . - , - c-. ..p,, , , . , .m-. . - o
6.09.b Facility Comment: Turbine Control Valve Fast Closure is bypassed at less than or equal to 154 psig turbine first stage pressure which is equivalent to 30% rated thermal power. Full credit should be given for.
"less than or equal to 154 psig turbine first stage pressure OR 30% power."
Reference:
Fermi TS Table 3.3.1-1. NRC Resolution: Comment accepted. The ansner key was revised to read:
"b. No response (0.50). Scram is bypassed when reactor power is less than 30% OR when turbine first stage pressure is less than or equal to 154 psig (0.50)."
Consideration should be given to incorporate reference to TS Table 3.3.1-1 into Section H, "Technical Specifications," of either Lesson Plan 03-15-29, MAIN TURBINE SYSTEMS, or Lesson Plan 03-15-30, MAIN TUR8INE AUXILIARIES. 7.02.a Facility Comment: HPCI flowrate = 5000 to 5200 gpm ,
Reference:
Fermi P0M 23.202, HPCI, p. 8. NRC Resolution: Comment not accepted. Greater than or equal to 5,200 gpm flow rate in automatic in needed to ensure sufficient flow with potential instrument and indicator errors, as stated in the note of Section 4.1.2.1.j of P0M 23.202, Revision 24. The answer key was not changed. i 7.02.b l Facility Comment: HPCI will not auto start. Allowable value is ' 103.8 inches and therefore will not start if l 1evel decreases to only 110 inches. Candidate may explain that the allowable value is greater than or equal to 103.8 and/or the setpoint is greater than or equal to 110.8 inches however. NRC Resolution: Comment accepted. The answer key was revised to read:
"b. HPCI will not auto initiate (restart) (0.50)."
l 4
Also, the answer key reference was changed from page 16 to page 19 (Section F.4.d of Lesson Plan No. 03-15-39, HPCI System, Revision 4). 7.03 Facility Comment: NO OPERATOR ACTION should have been stated in the question. Because it was not, candidate may take corrective action IAW A0P 20.109.02 REACTOR PRESSURE CONTROLLER FAILURE and as a result arrive at conditions other than those stated in'the answer key. With operator action the MSIVs may remain open and the reactor would not have scrammed. Candidate should be given full credit if however he discusses the core power changes as a result of the depressurization (if correct response is given).
Reference:
Fermi POM 20.109.02, REACTOR PRESSURE CONTROLLER FAILURE NRC Resolution: Comment not accepted. Candidate was told during the examination that he was to assume no operator action. In the future, this question will include a statement that no operator action is taken. The answer key was not changed. 7.13.b Facility Comment: The way the question is written leads the candidate to believe that there are automatic actions at 100 psig. Instead the operator is required to trip the GSW [ general service water] Pumps if all available GSW Pumps are operating and the system header pressure cannot be maintained above 100 psig by isolating leaks or ruptures in the system. Therefore, no auto actions occur at 100 psig. However, if the candidates provides the stated answers, credit should be given.
Reference:
Fermi P0M 20.131.01, LOSS OF GENERAL SERVICE WATER, p. 1. NRC Resolution: Comment not accepted. The immediate action of the procedure requires the operator to verify the automatic start of the fire pumps prior to decreasing to 100 psig GSW header pressure. The operator should also be aware that no GSW system automatic actions will occur. Also, the candidate was told during the examination that he was to state the automatic actions which would occur as GSW pressure was decreasing to 100 psig. The answer key was not changed. 5
r 8.08' Facility Comment: Request question be removed from examination. This Abnormal Operating Procedure [A0P].is one that does not require immediate action memorization by licensed operators.
Reference:
Fermi Internal Memo Op-85-139, "Required A.0.P.s for Memorization." NRC Resolution: Comment accepted. The 1.50 points and Question 8.08 were deleted from the examination. The candidate will not be penalized, because P0M 20.000.18 is not required to be memorized by the Op-85-139 memorandum. However, "Operator Licensing Examiner Standards," NUREG-1021, Section ES-402.A.3, Revision 4, each states:
"In general, a candidate must demonstrate .
complete knowledge and understanding of the symptoms, automatic actions, and immediate actions steps specified by off normal, or emergency operating procedures." 4 If the immediate actions in the abnormal operating procedures are indeed not immediate, consideration should be given to remove this terminology to be consistent with NUREG-1021. i 6
ATTACHMENT 2 FERMI 2 NUCLEAR PLANT FACILITY COMMENTS'AND NRC RESOLUTION REACTOR OPERATOR EXAMINATION DECEMBER 15, 1987 1.01 Facility Comment: Correct answer is b OR c. Utilizing the reference indicated: Text 8.2.3: Fuel Temperature Coefficient provides no specific explanation for the control rod. density
~
effect on doppler coefficient and Table 8-4: Reactivity Coefficient vs Reactor Parameter Variations indicates that rod density has no effect on the doppler coefficient making Answer a not correct. Answer b is supported by Text 8.2.3.2: Doppler Coefficient vs Temperature, Figure 8-12: Void and Fuel Temperature Effect on Doppler Coefficient, Text 8.2.3.3: Summary, and Table 8-4: Reactivity Coefficient vs Reactor Parameter Variations. Answer c is supported by Text 8.2.3.2: Doppler Coefficient vs Temperature, Figure 8-13: Core l Age Effect on Doppler Coefficient, Text 8.2.3.3: Summary, and Table 8-4: Reactivity Coefficient vs Reactor Parameter Variations. Text 8.2.3.2: Doppler Coefficient vs Temperature, Figure 8-12: Void and Fuel Temperature Effect on Doppler Coefficient, Text 8.2.3.3: Summary, and Table 8-4: Reactivity Coefficient vs Reactor Parameter Variations all support that Answer d is not correct. Fermi Reactor Theory Section 8.2.3: Fuel Temperature Coefficient ; Fermi Reactor Theory Section 8.2.3.2: Doppler ! Coefficient vs Temperature l Fermi Reactor Theory Section 8.2.3.3: Summary i Fermi Reactor Theory Figure 8-12: Void and Fuel I Temperature Effect on Doppler Coefficient ! Fermi Reactor Theory Table 8-4: Reactivity Coefficient vs Reactor Parameter Variations i I l
NRC Resolution: Comment accepted. Due to an error in the question stem, the answer key was modified to accept either answer b or c. 1.12 Facility Comment: Add Recirc (suction)-temperature as an acceptable answer. An explanation of cavitation and NPSH. usually includes general parameters which contribute to AVAILABLE NPSH. As such the specific parameter added is available to the control room operator and should be an acceptable answer. Fermi Functional Operating Sketch 6M721-5702-1 Reactor Recirculation System / Nuclear Boiler System NRC Resolution: Comment accepted. The recirculation suction temperature may be used to determine the saturation pressure at the eye of the pump in the NPSH equation. Answer key was modified to include this additional answer. 2.01.a Facility Comment: Also acceptable 9 feet. Fermi P0M 23.202 High Pressure Coolant Injection System, p. 7 Fermi POM 23.206 Reactor Coolant Isolation ' Cooling System, p. 7 Fermi Technical Specifications 3/4.5.2 ECCS - SHUTOOWN Fermi Technical Specifications 3/4.5.3 i SUPPRESSION CHAMBER Fermi Student Handout on Condensate Transfer & Storage, pp. 3 and 4 j NRC Resolution: Comment accepted. An equivalent level indicator (9 feet) is certainly acceptable. Answer key was modified to read "a. 150,000 gallons OR 9 +/- 1 feet" 2.03.c Facility Comment: Also accept groups that isolate at reactor low water level Level 3. No part of the question indicated that only Level 2 isolations should be detailed. Groups that isolate at Level 3 include: I l 2
. , - , - - - - + , - , m .- , .
r---- - r - -- - -, . - ---- - -
GROUP 4: RHR GROUP 13: D/W Sumps GROUP 15: TIP Fermi Technical Specification Table 3.6.3-1 NRC Resolution: Comment accepted. Answer key was modified to include the Level 3 isolations provided above as items numbers 8, 9, and 10 respectively in Part c. 2.07 Facility Comment: 1. SDV level high alarm, 2 level switch, 32 gal. (+/- 2 gal.)
- 2. Rod Block, 2 level switch, 70 gal.
(+/- 7 gal.) OR 591 ft. (+/- 2 ft.)
- 3. Discharge Volume High Level channel (also accept: SCRAM) 4 level switches, 120 gal. (+/- 10 gals.)
4 level switches, 120 gal. (+/- 10 gals.) (also accept: 8 level switches, 100 OR 120 gal. (+/- 10 gals.) (also accept: 8 level switches, 596 ft. (+/- 4 ft.) (3 required at 0.75 ea., 0.25 per signal, 0.25 per no. level switches, 0.25 per setpoint) Fermi Functional Operating Sketch 6M-721-5703-2 Control Rod Drive Scram Discharge System Fermi Technical Specification Table 2.2.1-1 Fermi Technical Specification Table 3.3.6.2 l Control Rod Block Instrumentation Fermi ARP 302 SCRAM DISCH VOLUME LEVEL HIGH l Fermi ARP 3094 DISCH WATER VOL HI LEVEL CHANNEL l TRIP l Fermi Master Instrument List, pp. 1073-6 i i NRC Resolution: Comment partially accepted. The answer key was modified to accept: l
- 1. 32 gal. (+/- 3 gal.) as the SDV level high alarm setpoint,
- 2. 120 gal. (+0/-20 gal.) for the SDV high level channel trip,
- 3. 591 feet and 596 feet of elevation
(+/- 2 ft.) as given in Technical Specifications for the rod block and channel trip setpoints, respectively, and 3
- 4. -The increased number of level switches since the answer key addressed the number.of ' level.
switches per scram discharge' instrument-
-volume.
However, it is strongly recommended that the operator training handout on CRD be revised.-'The candidates. answers clearly indicate' confusion in the following areas:
- 1. The setpoint for the SDV level high'. alarm,-
- 2. The setpoint for the SDV channel . trip level switches and level transmitters, and
- 3. The number.of level switches / transmitters per function. (Definitively stating that there are two SDVs and that the number of level switches / transmitters = listed are for one SDV would significantly clarify the ,
training text.) l 1 2.09.a Facility Comment: Accept Trips / Isolates Reactor Building Vent System as two (2) of the four (4) required answers. ' Fermi Student Handout on Heating Ven'tilation and Air Conditioning pgs. 9 and 10. NRC Resolution: Comment accepted with restrictions. The answer key for Part a was revised to read for Item 3:
"Isolates Reactor Building Vent system" l
and:
"Trip Reactor Building Vent fans (supply and exhaust)" was added to Item 5. l 3.05.b.2 Facility Comment: Correct answer is NO ACTION. Control Valve scram input comes off of dump circuit (fast closure) not valve position.
Fermi ARP 3089 Turbine Control Valve Fast Closure i Channel Trip ; NRC Resolution: Comment partially accepted. The question for i Part b.2 could be better stated as "Fast closure of turbine control valves 1 and 3." Since the 4 l
p candidates may'have assumed that a fast-closure (an oil trip failure) occurred or that a valve mechanical failure occurred the answer key.was modified to' accept either "half scram" or "no. action." 3.08 Facility Comment: Also accept the following:
- 9. ANY APRM inop (0.25) Module unplugged Switch out of operate Too few inputs (0.25)
- 10. Any APRM (0.25) S 14% of RPT (0.25) upscale, setdown
- 11. Scram (0.25) 591'ft. (+/- 2 ft.) OR 120 (+/- 10 ft.) Discharge Volume Lvl Fermi Technical Specifications Table 3.3.6-1 Fermi Technical Specifications Table 3.3.6-2 NRC Resolution: Comment partially accepted. The "120 (+/-10 ft.)"
for the scram discharge volume level'in Item No. 11 was not accepted. Control Rod Drive Hydraulic System Handout, PIS No. C-11-50. 03-15-10 System, Revision 4, Section D.6.f, stated that a level switch actuation at 70 gallons accumulation causes a rod withdrawal block. The following items were added to the answer key:
"9. Any APRM inop (0.25); Module unplugged OR Switch outl f operate OR Toofewin%ts(0.25)
- 10. Any APRM upscale, setdown (0.25); greater than or less than 14% of RPT (0.25)
- 11. Scram (0.25); 591 ft. (+/- 2 ft.)
PD 70 gal. (+f 10 gal.) discha)ge volume (0.25)" 3.09 Facility Comment: Also require the following for full credit: or when eitter RhR pump in loop A is running (also accept: RHR loop pressure greater than or equal to 115 psig +/- 10 psig) 5
r y ; Fermi Student Handout ADS Table 1. NRC Resolution: Comment accepted. Answer key for.Part d was modified to read:
"d. When either Core Spray pump in loop A is running
-OR Core Spray Toop pressure is greater than or equal to 125 psig;+/- 15 psig OR-When either RHR pump in loop A is running OR-RHR loop pressure is greater than or equal to 115 psig +/- 10 psig (0.50)"
4.02.b Facility Comment: Bases for the caution regard.1g injecting with Core Spray could not be.founc in the reference material stated. An answer could, however, be-found in Appendix B which for this set of E0Ps was not approved by the BWRs Owners Group. We, therefore, request this part of the question to be removed from the examination. Not applicable. NRC Resolution: Comment accepted. Question was deleted, because the training material was not adequate to clearly state the bases for the caution statement requested. NOTES: (1). POM 29.000.08, REACTIVITY CONTROL, Section 3.7.5, Revision 2, which was provided for the examination preparation, stated the following caution:
"00 NOT USE THE CS SYSTEM DURING BORON INJECTION UNLESS NO OTHER INJECTION SUBSYSTEMS ARE AVAILABLE."
(2). Training Lesson Guide for Operating Characteristics and Procedure, File No. 08-02-05-03, Revision 3, lesson objective no. 3, stated that the student is responsible for the reason of each caution in E0P 29.000.08 (i.e., P0M 29.000.C8). 6
4
-:e j
4.05.b Facility Comment: The.way the question is written leads the candidate to believe that there are automatic actions at 100 psig. Instead the' operator is required to trip the GSW [ General. Service Water] Pumps if all available GSW Pumps are operating and the system header pressure cannot be maintained above 100 psig by isolating leaks or ruptures in the system. Therefore, no auto actions occur at 100 psig. Fermi P0M Procedure 20.131.01 Loss of General Service Water, pp.1. NRC Resolution: Comment not accepted. The immediate actions of the procedure require the operator to verify the automatic start of the fire pumps prior to decreasing to 100 psig GSW header pressure. The operator should also be aware that no GSW system automatic actions will occur. Answer key was not modified. f 1 7
ATTACHMENT 3 EXPANSION OR CLARIFICATION OF FERMI 2 REACTOR OPERATOR EXAMINATION DECEMBER 15, 1987 Question No. Answer Key Modification 3.07 Alternate answer and clarification added:
"[Also accept: CST suction valve F004 (0.25). Closes if HPCI suppression pool suction valves (F041 and F042) are open.]"
4.04.A Add valve, P50-F403, as an additional example of an non-interruptible control air isolation valve.
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NRC RULES AND GUIDCLINES FOR LICENCC EXAMINRTIONS l 1 A Cusir.g the ad:ainictrat icr. of thic cxarainst icn the folicwing rulac apply: I e
- 1. Chcatir.g c.n the exarainat ion r.ieanc a r. aut oraat ic denial of year applicaticr.
cnd could recult in racrc covere pencitiec.
- 2. Rectroor tripc are to be liraited and only one ecndidate at a t i ra_ :.. a j 1ccve. You rauct c. . :. i d a l l c :.r,t act c wi th anyor.c cut cide the exanination rccr tc avcid cven thc appearar.cc or poccibility of thcating.
- 2. U:.c b 1 c.c h ink cr dc.rh pencil inly to f ac i l i t c.t c Icgibic re prod u c t : :.nc.
- 4. Print your narac in t h t- blar.h provided en the covcr chect of the e x a ra i r.a t i on. ,
C. Fill in the date en the ccver chaet of the e x crai nat'i cn (i f necccccry) . C. U .c c.nly thc papcr prcvided for ancwcrc.
- 7. Print your narac ir the upper right-har.d cornce :.f the firct page c.f tini cccticn of the an:.wcr chect C. Concc cut i vel y r.uraber each ar.caer sheet, write "End of Category __" as appecpr;att, ct c.r t cact categ:ry on a ngd pagc, write ELly Gn gnE nidt of t he p c. p c e , and write "Lact Page" or, the I c.ct answer chect.
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- 9. Number cach ar.cace ac to cctescry cr.d n ura b e r , for exarapie, 1. 4, G. 2,
- 10. Chip at i c e. c t ibrcs lir.ct. bctween cach antwcr.
- 11. Scp:rctc a ncv.c r chtctc f e c: . pa d ar.d placc finir.hcd ar.cwcr chectc fac.:
d e,.s n cr. your desk or t abic.
- 12. Ucc abbrevic.tienc cnly if they are ccrarasnly uctd in facility litecniarg.
- 12. The point valuc fc r cat . qucction in indicated in parenthecos aftcr thc quecticn a r.d can bc uc :d ar a guide for the depth of answcr required.
- 14. C h c <. all c a l c u l a t i o ".c, ra c t h c.d e, or accurapt ionc used te obtain an anc e.c r t o ract heraat ical p rob i c:a c whcther indicated in the quect ic.n or not.
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a ._ m. n .,K . 1C. If parte cf the c ,. c.:a i n:.t i c r. arc r. : t cicar a :. to intent, arh qucctice- : the taginct only. IT Y_. a .. c t c i g r. t he st at ernent or. the covcr chett that indicates that the v.crh ic ycur c ..n and you have n :.t rcceived ce been givcn accintar.cc it. c arapict ing the e > c rc. i nc t i cr.. Thic rauct be denu af t e r the exarainc t ion har b e c c. c e ra p i c t c d .
/
d
- 10. Whcr you corapict e your examinatier., you chall:
4
- s. Acccubic y c.u r c x c:a i nst i c,r. an followe:
(1) Exam quention c r. top. C C x c.m cid. - figuccL, tsLic:, e t c. (3) A r.Lwe r p c.g c c i r.c l u d i r.g figures which c7 part of the a n;..c r . L. Turr, ir. your copy c.f t' .e excrc.inatier. and a:1 pagoc uced te a r. ..e: thc c u c.':i r.at i cr, q u c et i or.c.
- c. Turt. i r, cil cerop pcper and the balance of the paper that you did r.st unc fcr ent..cring tht q u:. t i c r.: .
- d. Lc:.c tFc t >. ;:.: : r.:. t i c '. 2r c s, c. dcrince by th: c x ar.:i n c e. If aftc4 I c av i r.L . pu c; c f c ur.d i r. thic art -x v.hile thc e xcrc i ne.t i on i; ;till
.c pecgrc;;, y s :- l i c c r. :. c rac y bc cfc nicd or re .okcd.
I i I 1 1 l l l 1 i l I
^
- r. --
gs___p.---y _ _usk__L__u urumm..m Laub p . ,, t . . --'O wn .x _ u a _ _ _ - .. _ _ _ u b 2 1 _ pa c a _p u a A _ N_ L _ F L_ U_ _I " " t _ A_ N_ D_ _ ue -- " , auua_susue_suu t
. . .~ .... - ~ . . ,-
L ..Cs n) T'. c. ; c. crc thrc: r.:c j e r react ivit y e sof ficicrit e which offcet corc c pc rat ic..;,
- c. c f thc;c in the soid cecfficicrt of resetavity.
- c. E c f i r.c tha void coefficier.t of reactivity. ( 1. C )
6
- w. .m. 4. j. .r.
s.. t
..,_ ..%. . .. e. 4. s. . u,. \. v...w
.i c, v. Cr . -r . . .C .,. a., v f r c %. _v4.. N.1 *.y 3.e . ( A. . e-s -+ s
. ) _.. ),. 10_e _ e <- w
.. y . ..
m, .. . . . . v :.
,a _ .
e. J .e
*v.
w a i., _.. v. e_ ? C.._-.._.,.
- m. .
. 3, - . . . O r.s ,.
If the effc:t;vc value of beta in 0.007 arid lanbda
- C . 1, how mich rcectivity mutt bc addcd to c. c r i t i c e.1 reactor to cause the reactc-
#_ m_
w _. . . , c .. ,R _. . w. .,., , T m n r. ,T .m A. ..., b,h >, ., (.. . ns i, um_-,.._,.,.
. C. .- , . , .
s-. .., The r c. c.: t cr v. : . cperated at CC'; pc.wcr for c pcricd of 1 6.cc:.. Thc RO hac ,juct ir.:rccccd ecc. tcr pchcr f r crc C O*: t c ? ?** Li ir. rc. ir.; r c c l .* c a l a t i c r. pa:c.p cpced up t o CC:: of rc.t e d cpced. Duririg the ric x t fcar (4) to cix ( C, ) hcurc th; cpc stcr will d e c r o s :.c rc irculat:cn pur.p cpc.cd to nsir.tain pc..c r st 90%. After 40 bcurc the rceirculaticr. p ure p cpcod w 11 be geccter t h c r. G "*' i f thc r c c '. c :- p . . cc r 12 rc.a i n t a ; n; d et n.,..,. v J. . ..j dLC: thC cperd.Or# ir.itia11 f h l .'C t e d C r C. C. : t' khC recirC p ur
- p ( 1. C )
q . . . 9%
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= c _ _-. .- ., q y n-c uu
_ __ uu_q p. __=aaa -r- n ps.-pg. ..cJten_a_y m.. u a t_p,_u 9_ _7 3_ et_n__e_ . png- n
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..:- cau__.,_~=p._va.=
v e, aJu g g.
.:._au m _:aus=a -- .. .- -._. . , . . . ...s s,
D ar i r.; a rccctcr ctcetup with the plant belo,. thc psint of Eddirig
! .c c.t , t ' .c r ..ct.c 1: :cp cc.riticeI w .d . . . e C' rccer.d p ait:.c p c r i .; d .
If the reactor operator dcc c r.ot toach thc c c r.t re i c , t he re ac',or wi! ! cyc nt u;.11 3 bc ,;; t c r i t i c e.1 couenherc in the hostir.g range. The pc i r.t c f c ' i i i . ;, '. c s t ic CO on IRM range 8 z.nd the tempercture coe f f i c i e r.t .: f e c -. *. . .' '. ,- '-
. v. ..~ .
.
- W !. , * . . . * . . . . . ' " - C . O n- ."., . . . . ' '. - .". . ad. 1' e_ C. *. .
c H:.a much tiac docc it take to incrocce power from 30 on IRM rcr.gc 4 t ._.- ,. s. v.... .. A. i.....u
. . , c -
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r e a c ,. c 4 1 c, ,j a ,, cc.
. 1ce,. 1 ,t..c
. 5.c c.,. ;r.g r er.g u .,
w a . . n v.
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Scicci the ctatement below which defincc pump cavitc. tion. ( 1. 0 )
- c. Thc lack of c u f f i c i c e.t cyc t orci bachprcccurc o r, the diccharge sido
.. c , ..u.
- v. , , . , , .., .. .
- b. Preccurc : . c i l i e t ; c r.c c.t the dicchargc of the puup due to excectivc i r . . _. t. r r. _. a.c
- c. Fcruction c c.d cubcequent collapce of vapor bubbloc which caunc c r 1: c i c e. : f p u .ip pcet c.
- d. Cr c ' i ri; cf the pump impcilor cauced bj cold watcr hittir.; a hot i t. ;. c ! ! c r .
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- . c..
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. -s. _
would bc I c :. t ! . o r, the c c .. '. a r.t fion t h e s a.,5. _ icu p . .. c r be.dic c. _ r . . . _ r. .... <i.__.__-_o_ _ __ . .
- c. the t.. p r.c u. " I c. .. f r i c t . c r. nultiplice decreoccc.
u.
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_ . .m... . - . c .,. f. ...00) - t i [ Carir.; a plce.t Ch ut dowr., rtacter pecccure decrucccc frora 885 p:1g tc l 400 p;.i; i r. : r c-h :. i f h :.ur. Ha thc :p;ect c.. n:.ir.t air.cd the rcact or cc:.idown rate within the Ferni
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1 aswm8 de cNb?rd4 4cned /s nexcp 7e eUMdE' c.we Doidal b975.
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t'u l t i p i c Choica Hcat trcr. fcerad frc:- thc fuc cladding to thc cutecaled recetor w at c .- is pri::arily t rar.c fcered by:
)
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- L i :.t f: w.' (4) cf the fivc (C) ps it ive rccet ivity effectc which rauct Lc c.cr cc: : tj the Ctcr.dbj Liquid Systera when borcn inject ic.n beconc-c necenscry. ,
i I
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3 ( 1. ,s.m. ) , i N:c.-c or.d e n c i b l e gs:c: crc pred-ccd i r, the rr.cetor. What would happcc. to t arbine c f riciency if the nsr.-ec.idcncitic Ectt; were not r c :a :. .w d 'r c r :
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At a ecrtcin spe e d, the t ur b i ric drivcn fced pump chcracterictico cro .c r .. .. .. .
- r. _ s . . . . a. u_ ,. f..._w , w.c,.
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e..... develcpcd hrc.? = 000 paid l' the tpccd cf thc fecd pumpc ic doubled, what will be the final valucc
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e .e, are pec.:pt . .c at rcnc. L. Lc t t h c r. 40% of all rie u t ror.: produced fror.1 thc fi ccic r. o f U-22" m.-- -r ,. .m_ .. ,.._ ., .. r. -v , . , 4,..w. . i..._
- c. Thc pecductice. rate of prcr.;pt neutronc depend: cn the t o .'.c c r.t e c t i : r.
ar d Ec!flifc of the f i c t. i c r. d r.u g h t c r pr.ductc.
- d. h c c v e r a;;c c r.c r g y cf p crpt r.c a t e c r. . ic Iccc than the average c r.cr ay c f dc l aycd r.t u t . c r. L .
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Duri r.g r.:rt:a! :,.crci i e r. et 100:' p ..c r wher. a cercra occurc, the icv:1 cor.t e: ! r.::.d c :. c i c c t c..i t ch in i r. RUN" snd the rccctor fccd purapc arc b i r.; ccr.tro11cd r c ut o:act i c . ir,the r.c x t rairaut e of operat iori, what
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- b. The reactc.r feed purap H.O. arid M.D. diccharge '. c '. v c :
- c. .. u. c cter,.up Icve.. cor.. rc . vs.ve m.
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J . .. m-. .e . e, . . .s (-,.. ) The C i c : . _* b , G;;. Trent rcc r.t cyct era hoc thc capability of filt erir.g exhc .:ct f e c:e thc rcceter baildir.g, the dryucil, s u p pre .,c i or. pool, or the p e r c :ce.r.:.1
- c. i r lock. Thc CO3T cycter. will aut oraat ical ly ir i t i at e or, a ' COE c i gr.al.
- :,. ( n. . ,. r.. .s
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m ._ m- .. ~ .: 3r..,, .
- b. What crc the four (4) C' T cy ct c:. i r.i t a c t i c r. c i gr c i c (0.005
' c i p .. i r. t . r. : t r.c c c :. c a r ,) -..-n,e.,.
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The bcccc cc ct i cr. o f Tc::'. Specc regardir.; Reciduci Hcat Rc ra:.va l ctstc "A c:e.gic ch u t d: 6.r. c::1 Irig racdc icop provides. :,u f f i c i e r.t htat r c ra c'. c i cap;.bility for r c r.;:.. v i r. ; ccre dccay heat..." 1'y d:cc Tc:5 Opcc C. 4. 9.1 rc r, u i rc t u:. (O' ch ut dcur. e:i:.l i r.; ta:.d c lo:pc wr- 1.c. ., N. C n, c ,.
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C u r i r.;, c ct c.r t u p ee. .d h c c.t u p , the Reacter tl:.tcr Cleanup Synter. in rcjcetIr.g w tcr t .- the Mcin Co.dcr.ccc to control Icvcl.
- c. tl' .a t c.. t orc.s t i c c et ; st. c:curc i f the Elowdcur. Flow Control Vciv:
("CCC: i ;. r.c.d . eet c r.11y cl oced, whilc the rc t urr. line valve (F042)
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ANCWERS -- FERM! 2 -07/12/15-SULLIVAN, M. l i
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4 4 ; 4 ANCW~R C. 01 (C. 00)
- c. The cht.rige in teactivity cauccd by a 1% change ir. the void fraction i else eccept A b/ ( 1. C } :
4 v.;/> i
- b. "O" (O. C) :
i R r-cn . _-.
.. . E j FERMI REACTCR THEORY FUNDAMENTALC pp. S. 2 & G.11 022004M110 . . . (M A' C ) .
ANEt;ER 5.00 (1.00)
- a. )= 0.OCT dk/h (O.50) [
l also accept >= betc j
- b. The reactor would be critical on prompt neutrons alor.c, with no t control due to the Dets fraction. (0.00) 4 1
R-_r ER ..--.. - FERMI REACTOR THEORY FUNDAMENTALC p 10.1C 23OOO3M10T ...(MA'C) i e 6
! ANDWER 5.03 'O. 00) i [
- a. cfter a power inercace, XENON DURNUP IC GREATER THAN XENON PRODU': TION !
t fcr a period of c:.vce.:.1 %ourt. (1.O) ,
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- 50;. COUILIDRIUM XENON CONCENTRATION 40D0 MORE NEGATIV" REACTIVITY j THAN THE COM EQUILIDRIUM
- XENON CCNCENTRAT!ON 'f ~] r- ..s. c
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- b. T= 'Sc t c-rho) / (1crabda* rho) (O. C) th: ( 1 +T* 1 ct:bd c ) r k c t c rh - hctc/(14T*1cukdal rho = 0.00G/(1+50*0.1)= 1 X 10E-OO (0.25) delte temp = rhc/c1phe t ertip -
(1 X 10C-03)/(1 X 10C-04) (0.00) deltc tcup r 10 degrcc; I (O. CC) r.-. e. C R. . .- ...-r. FCRM: FCACTOR THCC"Y PUNDAMENTALS TEXT p 10.9-10.12 !. 8.12-8.17 29000SM108 . . . (M A' G) ANCt4CR 5.05 (1.00)
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n i _..u Re...-- FCRMI THERMAL SCIENCES TEXT p 17-20
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-u--u Awu_uuu_gno__aAxwny ANCWERS -- FCRMI C -07/10/15-GULLIVAN, M.
ANCWCR 5.07 (2.00)
- 1. Cor. vert prec ares to psia: (0.5)
CCC r '.."r 90^ p ,1 c. c.r.d 400 4 14. 7 e 500 pcia
- 2. Obt air. correcponding t eraperat ures f ror.1 ct e a r.1 tables: (0.5)
"X p ::. : e -) CO2 des F COO p;ia -> 4C7 deg F O. O c i a r .c. i r.; t e raperat .e: char.g : (0.5) 531 den F - 4C7 dca F = CC dcg F change in 1/2 h:ur
= 130 dc5 F change in one hour
- 4. NC, thc cocidowr. l i r..i t et i or. (50 dc; F/hr.) has boon (0.5) c >:c ce d c d.
--..rR -
n_. t_- _ FCRMI THCRMAL SOICNCE TEXT CHAPTER 3 L c_ , . m,. .. . C ,.-e C _. ,. t.C N. O . m. 1... . u. P v" ". "'__ " . 0 0 0. O '., . , . e ,,. _ ,.- ,. _
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,AN3WCRC -- FCRMI O -87/10/15-SULLIVAN, M.
ANCWCR 5.05 (0.00)
- 1. Coc!down frca hot to cr. icnt conditior.c O. Decay of rated Pencr. cor.c c nt ret i or.
- 2. Climinctior, of etcon v0ide
- 4. F.c d u n d ..c s et i vc rccctivity duc tc- dcppler C. Occccerad Ccr.teci red w;rth ac the usdccctor coolc
( 4 required C 0.5 occh ' REFERENCC FCRMI LCECON PLAN 03-10-14-01 STANDBY LIQUID CONTROL p. 11 0?CoiSX100 2CC01CHiO3 . . . (MA' S) ANCWER C.10 (1.50) Turbir.c cfficicr.cy hsaid DCCREACC (0.5) because CONDENSCR VACUUM UCULD DECRCACC (0.C), no the au s u r.t of wcrk removcd from the ctos:. an it went through the t ur b i r.c w:.uld decreacc.(0.5) F.-rCe..-...- FCRM: LCSCCN PLAN 03-15-0.5-01 CCNCCNSCR VACUUM AND OFFGAC CYGTEM p. 4 CD100CM110 . . . (K A' S )
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;AN3MCRC -- FC"M: 2 -87/12/15-SULLIVAN, M.
ANCUCR 5.11 (1.50)
- a. Speed in pecportional to flou O (1) /O (2) - F (12 /F (2) (0.25)
C (1) / (2< 0 (1) ) - f C. G X 10C+0C) / F(2) F(2) = 7. O X 10C+0G (O.20)
- b. Spacd cutcd is proportice.a1 to work (5 (1) /s (2) ) ^3 = W (1) /W (2) (O.25)
(C (1) / (2* S (1) ? ^3 = (20kW)/W(2) U(2) = 160 l&' (0.25)
- c. Cpccd equored is proport f or.a1 to head (E (1) /S (2) ) ^2 = P (1) /P (2) (O.25)
(C (1) / (2*S (1) ) ^2 = (2OOpcid)/P(0) P (2) - C00 pcid (0.25) n_ n _, n _ f 6. e. \ ..L-- NUCLCAn POUCC PLANT THERMAL SCIENCC p 17-24 and p 17-20 201004M100 . . . (MA' C) ANOWER 5.12 (1.00)
"c" (1.O)
-nu F L R_;_.... r_
FCPMI RCACTOR THEORY TEXT p 3.7 252OO1M102 ...(MA*C) A .~. -., R e.<...,. s ( ,. . s.se ) A flow i r. rc ccc t rans i ent (0.75) c a u ce d by r.10 t c r g e!r /. c rat or cpced cor. trol fstlurc (O. C) 4
u _ N
" t _._T H_"w a _P Y _QF_ _N_U_ C L_C_ n _" P_O_ WE_ R _ P_'m(_' N_T__O ?_ C_ _R A_T_ _! C_ N_ n _F_L_U_ _T P_ C_ n_O_N_
FACCD 04 7 e _ -o .,- v a . - v , - r uauase_auasue ONOWCP.C -- F"PMI C -87/10/15-SULLIVAN, M. I ~-.r -" P. ~ ' .' .m TCCHNICAL CPCCIFICATICN DA3CC C/4 0-4 00COOOMICT ...(MA'C) ANSWCR 5.14 (1.00) T: L M!~ CCNTT'CL RCC UCRTH (O. C) below a pec ct p o.a c e Ic '1, which i r.t ur e that the CNTHALPY OF THE FU~L DOCC NOT EXCCCD DCCICN LIMI(C (0,5)
.,--n.-..--
- c. : w r -. . u
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~ ... ,d ,. A . -,- s .. , . . R
- n. ..r e.
.e (4.aO) c
- c. 1) the rcc tor can bc ras d e cub:ritical frota all operating (0. 5 )
cor.dition:
- 2) the reactivity tra.. for.t: at:cciated with po t ulated (O. C) accidcr.t ec.nditions are cont ro11 cbi c within ac=cpt ab!c l irai t C) the reactcr will be ncintained cufficiently tuberitical to (0.5) pecclude i n a d . c r t c r.t criticality in the ch ut d wr, c.:c r.d i t i on
- b. f u c. ; depictice (0.5) poicer. burnup (0.5)
Rr.r
- _ e P .. . -
-r-
.. L. ... , C n- ._ e a,,C - u.
,r I ,w s T ,. u.s.. .s D ,,s. s . . ca .,
~ / .,. 1-1 CCiOOIC0CC 00COCCM114 ...(MA'C) I 1
1 l l l l l l l
"u _. __T_H_E_O_ _R _
Y_Q_ F_N_ U_ CLC_ A_ _R _P_+QW"= _ _R _P_L_ A_NT_ _O_P_E. E A_T_igN_ u_F_WlDR_ u _ A_ N_ D_ PAGC 25
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. b. .
AN,,a.,.--.n e.1
- C s . 7.-a,s
- c. Corc ficw decroccec to net ural circulstic. (O.05)
- 5. CHC clocc.s the turbino cor,teci valvcc to contesi preccuro ecutcd by a decreace in total ct a cta gencrction rate (0.25). C t c ara flow then etcbili:cc at a value equivalent to the st eara generation rate f reactor power for natural circulction (0.05).
- c. 1. Levc1 w 11c in the d : w n: ct. c r due to the i r.c e c ut e in two-phacc fisw recictance (cauced by i r.cr e o t e d voiding) cnd the lo:: cf the rceirc d e :'. i n g ri si. (0.0"'. F c e d ..:.t c r icvci centrcl cenccc the incrcc;cd Icvel in thc dowr.corac e and reduccc RFPT cp;cd (O.CC).
- 2. Ros: tor pee.cr decreate cauccc a reduced stcara genc e r t ic.n r -t e (0. CC) reducing the st c ara flow cenced by feedwate.' icvel contes! .n thret c1cucr* than rcducing RIPT cpced (0.25).
p,_ en. _ .-. C FCRMI LCSSON PLAN CN RCACTOR RCCIR"ULATION SYSTEM Le u
. .. C ., ,- --...u h. . e, .
FCRM: LCCCCN PLAN CN M:TIGATING CCRC DAMAGC PG 120. e m., -en r .r ii
., w. . a , , Ce., g ,i,
- e. .
r n. ... e
.. e.
.L i.,
t , w e . \ , u ew n. 4nm F. e, .e.#, 4. w.. L t P'* u c.'s ,.I
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,IN.
4iIebb (9*
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, 9 f'tj Augf hv y.=yp" $ eI. p. to7v 8g 7.J b? v A e.
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=.*'.
mwhs v *., ... t ud a
G __ELENI_GrtIgbg_D;E196 _GQbIECL _002_1GGIBU5ENIBIIQU PAGC .cc ANC.tRS -- FCRMI 2 -87/12/10-SULLIVAN, M. L 9 b 1 ANCU"T. C.01 (C.00)
- c. Icvel cetpcint recalvec on 10" cctdown cignal (0.75) ;
- b. RFP H. O. and M'O. diccharge valvec eccoive a cloce sigv.a1 (0.7C)
- e. CULCV will transfer to AUTC (0.75)
- d. RFP r.tsxit.iuta spec d = C300 RPM (CSM) (0.75) l RCFCRCNCC t
' FCRM1 LCCCON PLAN 00-10-46-01 RCACTOR VCCCCL LCVCL CONTROL SYSTEM p. 11. : LCCCCN ODJECTIVC C 295002A101 ...(MR'C) l 1 ANCWCR 6.00 (2.75)
- n. To PRCVCNT LCAMACC (0.05) of pctent ially RACIDACTIVC MATCRI AL (0.00) 1 tc the CFF-SITC (O.05) environtcent i ) deiafe *n A g.6ie' t i. f f% Wo w[Ydik sec /.7 senI.een m.*I"I7f) ;
., (4 8
- a a c sf
- b. High drywell pecccurc (0.50) !
Rec:tcr vescci low water Icvel Qvgl h (0.50) j High radiction icvel in the rec: tor building vent.*1ation exhaust ! (0.50) i Icvel en the refuel floor (0.50) Hi(rh rcdict icnL R.L+in sdu nCrCRCNCC kIPeeIH.5 ') w 1 og.si.c g t.am FCRMI LCCSON PLAN 00-15-20-01 STAND 3Y GAC TRCATMCNT SYGTCM 14 _ OC1000M401 ...(MA'S) & 6t.b4 /Va3 */- t d /*- M N0 *
- G:tm , wg.,a fcy p. fwa Ob K 46. IhMr-. $157cm, k 4, %k ~. F. B h ! f- L L, ANSWER E. OC (1.00)
C:NCLC FAILURC CCNCIDERATIONC ( 1. 0 ) regaire that two loops be op ratic. I r.CFCRCN : i TCCH C7:00 DACCC C/4.4.? ! 0000000000 . . . (M A' C ) i 7 I i l 4 d
r A _ _ __ _P_'m_N_T_SY_STC_M_S__MES__I m_ GN_ _ m_C_ON_T__R _ L_ L_A_N_D_'_ _T M_S_T_RU_M_FN__TA_T,IO_N _ a _ . PAGE 27 I t .. e ,y
- ANSWERS --' FERMI 2 _G7 /12/15-SULLN VAN, M.
r s
. . (
ANSWCR G. 04 (3.00) ,
/ <
4
- a. the pump:. will trip (0.5) on LOW FLOW ' (150)
~
- b. Rccetcr low water icvcl (0. 2) Level 2 (0. 2)
~. .
~
- High c
- cita flow (0. 2) E3. 4 g pra fer EO cceende (0.2)
High cibient t eraperct urc ' (0. 2) 182 dcg F-(0.2) . High diffcrentici tcupercture (O. 2) 50 den F ,(O.2) Non rescn heat c;: changer outlot temp high (0. 2} 140 dcg F (C.2) Standby Liquid Control initiation (0.4) ~ 1 (5 of C rcquired tot O.4 cc) i REFCRCNCE FERMI LESSON PLAN 03-15-08-01 p. 14 & p. 18-19 204000M404 . . . (MA' S) ANSWER E. 05 (2.50) 'i
- a. Red Block = 0.GCU + 45Y. (0.5)
Ccrsn e O.GGW + 54Y. (0,5)
- b. RPC - A (0,5)
- c. to provide a SIGNAL which is REPRESENTATIVE OF RCACTOR THCRMAL POWER (0.75) during a TRANSIENT (0.25)
REFERCNCE FERMI LESSON PLAN 03-15-24-01 POWER RAN E MONITOR pp. 11 & 25 LESSON OD.'CCTIVES 8,9 212OOOM101 215005M202 215005K505 ... (MA' C) AN3MCR 6. OC (1.50) g undr [ The ADS valvec will CLOEE ( 0. 5 ) FOR 105 tECONDS-(0.5) AND THEN W:LL RCOPCN (O. C)j if the low wcter lovci cignal it still peccent. REFERENCE FC T'M I LCCCON PLAN 03-15-42-01 AUTOMATIC DEPRESSURIZATION SYSTEM Fig. 2 L L.n4.e n ~, As
., m.a s s w, Lu- sA n,- v, , s.
,.- 1 J-n.
PACC 2E 5:.__ELBUI enIGME_EEG10da._GONIEL._SUD_INEIBUMGUIGI190 ANEMCF,C - . FERMI 2 -87/12/15-SULLIVAN, M. C'COOOKC01 . . . (MA' S) ANSWER G. 07 (1.50)
- a. 457 (O. 5)
- b. Spried lir.. iter #1 would DECREACE RECIRC FLOW (0.00) TO 20% (0. 5)
REFERCNCE FERMI LESCCN PLAN 02-15-47-01 RECIRC FLCW CONTROL SYSTEM pp. 7 & 12 LCSECN OBJECTIVE t'3 202OO2KGO4 . . . (MA' C) P.NSWER C. OS (2.50)
- c. Low inict etcco prcccuro icolation (0.5) will trip the HPCI and RCIC turbince
- b. Hi;h i drywc11 preccure (O.25) 1.CC pcig (O.25)
Icu rec.ctor ostcr Ic'-1 (0.25) Icvel 2 (0.05) T' Ic o * /. in Y bi~
- c. HPCI flowrcte =
Kj^gpm (0.5) M - %66s/ID [O - 6 k ' /- h - g-/C % RCIC flowrate e gG gpm (0.5) M (00 m g/ REFERENCE FERMI LESECM PLAN 02-15-39-01 HIGH PRESSURE COOLANT INJECTION SYSTEM p 5 LESSCN OCJECTIVE #4 FERMI LESSON PLAN 03-15-42-01 REACTOR CORE ISOLATION CCOLING p 5. 20COOOK401 20COOOM407 20COOOM403 217000K502 217000K500
. . . (KA' S) i l
l c
E_ _. __P_'mA_.N_T_S_Y _e_ " TE_M_3__D_E_G_4'.G_ N_ s._C_O N_T_[lO L_. s.'_ A_N_ _D __I ?_!_C T _P U._ M E_N_T_ A_T_ _I O_N_ PACE 20 AN3N~RS -- FERMI 2. -87/12/15-SULLIVAN, M. 4 ANC'. CR C. 00 (2.70)
- c. Load Reject (0.25) ,
.le
- b. No rec;:cnce (0.50). .: c re ic b acsed when reactor power'locs ha f whLA tarLlst (!rbi h c ff*L>$ M &
- c. (1) clocce (O.00) is le, thu .c eful /, iW ,gf, C R W ) y (C) c1cccd (0.50)
- d. Open (0.50)
REFEREt:CE FERMI 2 LESCON PLAN MAI! TUR3INE SYSTEM (NCO) PG 11, 59, CO, CD AND n c .,- a ... 212OOOM:12 ...(MA*C) ANONER G.10 (2.00)
- 1. NO RPS ACTION
- 2. FULL SCRAM
- 3. HALF SCRAM
- 4. ND FiPC ACTION (0.50 each)
REFERENCE FERMI 2 LESSC:: PLAN RPC (C71) PG 19. ANSWER G.11 ( 1. 00) d.
. REFERENCE FCRMI CTUCEN~ LECCON PLAN CN ME!V LCS P3 C.
LESSCN OBJECTIVC NO. 4 AND C.
- 3. 5 ...K/A VALUE 229002COC7 . . . (Kn' 3' l
l l l i
' g ,;, , , , _ , , _ , _ _ , , , , , ,
e - - r- , -.,r-,-n -,r,-- , - ,, ._n, - , , - , -n_. __n_ ._ _.,_ , _ ,
C___P_L_ AN_T_C_YC_T_E_M_S _ __ _ _ _ D_E_S_ _I G_N_L_C_O_N_T_R_O _ _ L_ L _ A_N_D _ _ __T_ NS_T__R U_ME_N_T A_T__I C_N_ PACC 20 ANSWERS -- FCRMI 2 -87/12/15-OULLIVAN, M. ANSWCR C.12 (1.50)
- a. 1. Turbine trip C. Fecd.; ster hecter high water Icvc1 (2 rcquired, 0.50 ca.)
- b. 1. Prevente turbir.c overspoed (in conditier.c cuch as a turbine trip)
O. Prcvent; ficoding cf the turbine (cico eccept: p cvents water i rap i ngc- .:cr t cr. turbine blading) (1 requircd, C. 50 cc.) REFERENCE FERMI STU0ENT LESGCN PLAN CN MAIN TURBINE SYSTEM P3 48, 49. LECCON CBJECT!VE NJ. 11 AND 1C
- 3. 0 ...K/A VALUE C4COCOM405 . . . (MA' S)
L i 7__. __P__R__ OC _ _ _N__O __ E_r U__RE_C__' _R M AL__ u_ AB_N_O _ _ _RM_ AL_ n' __E_M_C_ __ _R G E_N_ CY_ A_N_D_ PAGE 31 _p- O " "a7 bF'i a c 3_ _7 m n ,' C_ u= _ C__c eux=A
,AN3WERC -- FERMI 2 -87/12/15-GULLIVAN,. M.
.ANGUCR 7.01 (1.00)
OVERFILLING THE VESSEL by the RFP's (0. 5)- due t o locs-of. Level Setdown Lcgic (O. C) REFER 2NCC POM 20.300.12 2C2OOOK201 262OOCGOOG . . . CKA* S) ANSWER ?. 02 (3.50)
- a. 1. Ctcam inlet valvc (FOO1) openc.
- 2. Barometric condenter vacuum pump ctarts.
C. Outboard isolation valvo (FOO3) opent. 4 Condencate pump dischargc to CRW (outboard) isolation valve (F025) closes.
- 5. Condencate pump diccharDe to CRW (inboard) isolation valve (F02C) cloccc.
C. Stcom cupply lino drain pot (inboard) isolation valve (F020) cloccc. '
- 7. Stcam cupply linc drain pst (cutboard) isolation valve (F020) clostc.
C. Lube oil cooling water inict valva (F059) opens.
- 9. Au>:iliary oil pump starts (0.125), then auto stopc when attached oil pump diccharge precoure is sufficient (0.125).
- 10. Turbine ctop valve (FOC7) openc.
- 11. Turbine control vcive throttles open.
- 12. :r.jccticn valvc (FOOC) openc
- 13. The minimum flow valve (F012) opens and cioccc wher. flow in greatcr_than 1200 gpm.
- 14. HPCI develops >- 5200 gpm flow i n aut omat i e d'*^- 7',1p
- 10. Earcuctric condenter vacuum pump icolation valve opens 1C. 'E43-FOO4 Condensate Storage to HPCI Pump valve open l
- 17. E41-FOO7 HPCI Pump diccharge outboard isolation valve open
- 10. E41-FOOE HPCI Test Line out bcard icolation valvo clocce
'19. E41-F011 HPCI Pump tect return to CGT downstream valve closed
- 20. Stsndby Gac Trcatment Systou ctarte (Any 12 at 0.25 cach)
Ad$
- b. HPC! will auto initiate (rectart) (0.5)
A RCFERCNCC 03&d FERMI E LESCCN PLAN HPCI (PIS E41)j^PC l'. / . FCRM PCM 22.202 p. iC
,-. - - . . - - - , , , . - _ . _ , - - - - - .-- . v. .- -
- a---n.--c et4P D ~=u'"u _Y_ A_M_"z PAG" 'e A L__' p n _
w akewu m e'___N_Q _R
- u^ L_uL_ A_B_N_ O__R M_ A_'m L _m a n us' - --
__R 42 I OL C 3 ! C A',_C QN_T__"OL_ ANSWERS'-- FERM? 2 -87/12/25-SULLTVA'!, M. em 0Cm,r. w , -. C . . . ( . o.un. .-s ANC'<'E R ?. 02 (2.00) Turbinc ' Control Valvec oper. raorc, Eypas: valves open, MCIV' c cic c cr.'1cw reacter pressure The Rc--*-- CFRAMS. , 'O.5 ca)
-..-_.e-,%s,-6 4 'e m 7a eMa FERMI 2 A00 20.1C7.02 (RCACTCR PRES 3URE CCNTRCLLER: FAILURE) 245000V303 . ..(MA'C)
AN2WE". 7.04 (2.00) +
- c. Manually cercra the plant and exit the procedure and perforra the c rata procedurc ADP 20.000.21 (0.5)
I
- b. Stcrt GDFW and/or ROIC (0.25) to RESTORE AND MAINTAIN reactor d
water LEVEL (O.25)
- c. 1. Rc rac. i n i n g, RFP restores and rasintain: Irvel between level 4 and Icvti 7 (O. C)
- 2. Rccirculati in puraps run back to 4Gi: speed ( .~ 25 ) if low level alarm occurs. (O.25)
REFERENCE FERMI 2 LESSC PLAN RPV LEVEL CCNTRCL (N2:) PG 10 FERMI 2 AOP 20.107.01 PG 3 29500?CoiO . . . ( VA ' C ) b l l l l 4 I i
m au=_sg - z,,__u _: _..'__a, pm --n, i n - p. py e. . . . m e, v - . P a.o :. ws
,,,,,,r u.u__ - a. u_
_ _:=._.,: ..
,.1=,L_n_:.. edu um a n_gue u uy ps,9_ . Leess wC E Azu=_C_C_21eO, _
r . . ...:
.~.. v. . -- r a. s ..a.
s.
- 8,i / 1 , /:.1,a c ,w.n w L 1 i.,a,, .s , ,v. .
C+'."..,'..'~". _. 7 . ^v "w ( ."., . 0 0 )
- a. Rccctor ..ctcr Itvel ler; thar. Icvc1 3 (+17C") (0.5)
Rocctor pecccurc greatcr than 1088 pcig (0.5) A condition which requirce an MCIV icolation (0.5)
- b. Icwcring rce.ctcr water icvc1 would decrca:c rcccter power (0. 5 )
d t.c to incroaced voiding in the core (0.5)
- c. if t h e re c i rc u l c.t i .or. pur.;pc art r ur.r. i n g . (O. C) .
r .-.r-u--...-n- .. w CCF C9.000.01 - o . ' - o, 'o - ^ ~ A ' .. ' C. '. P r^.~. C '., ~. H O J ' c. C R n ". . pw o C w"r" eJ e' .
t.n"',c.'t'.'~.
i w 'v.' 'A LCCCON CBJECTIVC tt 4
~ , . -
- c. ;s w o. .. G v.. n.. ... . , h, A , S )
ANG'WE R 7.OC (1.CO)
- a. The MSIV will cloce (0.5) if the backup r.1anual scrar: pusht ut t ons are pushed.
- b. I nj e c t i r.; with the Corc Cpray Cyctern will r.o t aid in circulatir.g the boron int o the corc (0.5) (and rnay even cicu or dcter the circulaticn of the boron into thc core) since Ctar.dby Liquid Cor. trol injects below the core p l c.t c and Core Spray injcct c abo.c thc Top of the A=tive Fucl. (0. 5) rh"I"~ c' w " aw.
P .' ~w~ FCRMI CCP C9.000.00 REACTIVITY CONTRCL p. E
. . . ( K ho , Ss
- e. n .- , w w...n.mn- .
ANC'JC" 7.07 (C.00)
- a. P l c. c the r.odc cwitch i r, chutdown ( 0. 5) ruch bot h r.;anual t e r c r.. p:.thbuttonc (0. 5)
Arra ar.d dcprca: Main Turbinc Trip Puchbuttonc (0.5)
- b. (- 90 deg. F pce hcur (O.C)
IT. .' r w.s-o ~'6 .' ~..wr~ pw ..n. .g e. oi 4.v..,. D C t ..' F o. . "w .Y. p. w7
.v.
" I ". ~_ C " ',.. P. ww r. ~.'.
..
- v.
ws 3 . s .. w. C 'v' ~. -n w m ,,ws... c .w w w-v.r.,.
~.,m.
w _ w .. . .e s s . .aw.s. r , .. , . . ... ( . .
- n. , ae )
*"^'
__Ln_ R _ =C="*-' c _'T n ur _ " _ _ _u = uut.:= s._ A"""' s._ C"' _ uR m "_ r'N"%' 'r r* "- '- " O"= "'
.t.r ~
_ ea u _2 = = = _ =___a _R_ A D_ I.O_ L_ O_ _? _I C_ _P_.L_ _ _ _C_O N_ T .R.C L_
, A .a ,.e., e- R o- -- FCR.w.I .:., -8.,,,,,,,<r...
, . - , . ,r...,
- i , ,,, . .v. .
A ..n t.,- r , ,.C- ( . 003, The MCTC, . i r.d i rig : could CVERMCAT (0.5) at a result of the r.1 ster dra6.ic.; CTr.RT!NC C'JRRENT (1crgc i r. i t i c.1 c ur r e .'.t curgcs tc required to start t!.c ract c r ) (O.5) c.cen! t i r.12 : i r. a chcrt t i t.ic per of with 1ittIc or r c coc. l i r.g e f f e c t f orn t.;:.t or rot at icr.
,--v.,..-
u c . FERM 2 PCM 23.120.01 PG 3.
.__n.-..,n. a .- -
...(,,.,.-, r v.
ANC'<!C R 7.09 (1.00)
- a. 50 dcg F (O.CO)
- s. t.,. .: m ....m t ch ( n- . em n ,s
-. . . , ,O ., .
es. r r r,, t m.,e, r. rr.. w% m P w ".. -- *'.*'..r.'*
. . F... r r^.~_ ~. O ., R-r.r,.' '. r", mJ'._ n' T O '. ,' S Y.e,-.T "". ,.. E n. r . . . ,. , Ca.-w.
A . c ,-.. - , F.w, A , ",na_,.u. m.
- - ,. r_. ,. ,f...
. 4 . f*
m2.
.es ,J n, es v..e. n, m- ...
- u.nr . . e )
r, A..
.-..i ..- , .... . .
( ,.. O C, ) r
- u. u- es..
<- ( . c.. .,., + e, .?. )
. r. n . i
- b. APRM:, (0. 5)
R er Er ,. u t,.. . - FERM! 2 PCM 22. COO.17, PC C. c .._ n, J mv~ c ,, . mv.n01G01,
.e a . . . ( M A, )
\
PAGE 35
' ZI__dbbb,h2MEk.C0..h-U28506t_GEURE506t_EbEBGEdGZ_002 on
. _PueAG.aQ-eA =_CCua.--uw=
ANSWERC -- FERM '2 - 87/12/15-SULLIVAN,'M. I l ANOWCK 7.11 ( 1. 50) l l
- 1. ptrform ACP 20.007.01 EMCRCCNCY DIESEL GCNCRATCR FAILURC
- 2. initiatc start sequence on CTG II Unit I C. not ify the nucicar chif t cupervicor of ~the event 6 (0.5 ca) ar--s-,
. n ACP 20.300.01 LCSC OF CFFCITE AND ONSITE POWER 29:00:0010 . . . ( K A' C ) ,
ANSWCR 7.10 (2.00)
- 1. Monitor the gercral ctate of the plant, if entry conditionc occur cnter ECDs. Exit the ECP when the condition r.o longer exicts and enter appropriate procedures ac directed by the NSC.
- 2. Monitor the reactor water icvcl/proccurc and containnent pecccurec/temperaturen from multiple indications. ;
r I
- 3. If a cafety fur.ction initiates automatically, assume that a true initiating event has occurred unless otherwice verified.
- 4. Wher.cver LPCI han initiated , cctablich RHR host exchanger coolir.g ard inject through the heat exchangerc ac coon as icvel control permite.
- 5. The defeat of any trip, isolation, or accident cignal muct be performed in accordanec with the applicable Mai ret er.ance Inchruction.
C. Ac:ure that the NCC in informcd of ar.y change in the plantLctatue 4 and that it may affcet thc cmergency classification. (4 required, 0.50 ec.) , RC."ERENCC FERMI CTUCCNT LECCOM PLAN CN CCEP EMCRCENCY PROCC"URE GUIDELINEC. 4 LECGON CCJCCT!VC NC. C. PCM C1.000.13 CNCLCOURE 1. [ C. 9 ...M/A VALUC d b y . - . . . , -- -, ,.,--e, _w,-- .m , , - . + - , . , , , -!.---my -,.yy, .- e.m... ,.-er. - . - , - -
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- c. . 1. TOCCU heat c >,chc.nga r o ut l et t erapc rat ur c ) 115 deg. F C. F*c r. Turbine thruct t:c ar i r.;; oil drain teraporat ure grec.tcr t h a r.
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C. Ar.y Ma i n T ur b i r'.c bci -i r.;; rac t e l t er.1perat ur e > 170 deg. F ( c.- cc inrcd, A e . c-, ,, pa r cor.. 2 l oc., n ,- p or r c ,. p :. r.,. . + / -- vA . -s .
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- b. 1. The c c:tcic 'irc p utt p auto e t cr t :;
- 2. The diccci fire p urc p c.u ts - starts (C required, O.25 ca.)
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- 8. ADMINTETRATIVE PROCEDURES
---------------------------- ,.------ --- CO'?DITIONG s------------ AND LTMITATi gNS --
PAGE OT
. AN WER3 -- FERMI 2 -07/12/15-SULLIVAN, M.
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- c. a partici red te; clesrance r.cy be a ut hori::cd by a PROTECTION Le - ., .- P., r, .., , e, ,
- d. Red tags are audited ct Iccct once every 31 dcyc (0.5)
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- b. 1. The NGC is aware of cr.d will enforce the radiation prctcction requi rcracnt e ct i p lat ed by Hecith Phycicc.
- 2. The NCC in a;. arc of p l cr.t cnd cy ct ere statue in the affected avec C. T '. c NCC chall crsure that c pe rct i:r.cl and other rccint enance f ur.c t i er.c which could advercly cffcct the radiclogical e n v i r cnr. e nt addec ccced by the P.WP arc provented.
(2 of 3 requircd G O.5 cach)
- c. 1. To cr.tcr posted radiaticr. crcac
- 2. To enter post ed ccr.t arai nat ic.n arcac
- 3. To enter poct ed high radiation areac
- 4. To ent e r ponted Airborne radioactivity crcac
- 5. To cr.tcr p:icted neutrcr. radiction arcac C. To enter arcs pacted "Spccifi RWP Required for E r.t ry "
- 7. Ojcicm beccch on cont ami nct cd /p .t ent i al l y cent er.:i nat ed cyct er.ic C. Ceswlir.g, c l i r.- b i n g , or " h a n d c-o r. " work without Hccith Phycict c thorization
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_ _ w _ PAGE ' 38 A
- - ANSWERC -- FC" 2 -87/12/10-SULL2 VAN, M.
w ANC'dE R 8. OC (1.CO) In the-cacc of a design bacic accident the inspcrable Jet purap (1) incrccccc the blowdown'arca ar.d (0. 50) ' (2) reducc: the espc.Sility 'cr refloodir.g thc eccc. (O.CO) REFERENCE FERMI C TECH SPEC DASEC P3 3/4-4-1 FERMI' .2 LE3GON PLAN REACTOR RECIF.C 'CYSTEM l(331) n . , ,
-. 00.n00u-.v . . . ( 1,.,4 ..
ANGWER C. 04 (3.CO)
- a. 1. Rcview Ter.ip:irary Mc di ficat ionc Log 'Inden Suramary Shoct for channec cince lact cr.-duty period -
- 2. Review Chorai c a l Action Levcic on LCO D:.crd
- 2. Discucs with H? the RWPs ir, uco
- 4. Ravicw thc Alcria Scquence ' Recorder C. Revica the 2ccurity Mcy Log E. Ecvicu thc LO~ Ctatus Bccrdsto cncure it ic-accurate and curecnt.
'"ivc :C required at O.5 ccch)
- t. the NACC raust t. : in the "At Ccv.trcit." c r c :. (O. 5) and the CRNGO rc.uct be in the Control Roc.ra (O.5) r-
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FERM: 2 PCM 01.000.01 PC 17 c.nd At t c.chraent 4 294001A1C3 . ..(MG'C) r ANSWER S.05 (1.00) EVENTS that arc !N PRC3RE32 CR HAVC CCCURRCO which involve ACTUAL CR~
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_ acT_ A_T__I O_N_S_ F T- " 4 '- [AN;lC"C--FET'M: ;_ -87/12/15-SULLIVAN, M. A tm.- v. . .-- m.
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- s. I r. i t i a t : cci:c. .. i t h i r, 15 ra i r.ut c c to rectacc. LHOR tc within cpcc, within 2 hours (0.5)
- b. The LHCR lir:it prevente any fuel rod fror.: execcdirig itc decign LHGT' c yc.. i f fuci pclict dc. . .,i fi cat i on in pcstulatcd. IOR prcvur.ts f u c '.
c i cd c i r.6 f c ; 1,.r t (c;c. chir @ ty c r.c ur i r.g t!.s t i t'- picctic ctrain c.r. thc c l ..d d i r..; ic r.s t cxeccded) (1.0) r ...-C.-..,,.
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- a. Whcc. THREC concecutive t er.;per at ure readings of ( 5 deg. F ch a rig c (C . C5) over a 20 r.1i nut e period. (O.2C1 (ar.d desired p l c r.t ccnditior.; arc reachtd)
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V- , PAGE 42 C _. __A_D_* i_! N_ _! T_T _R _nT__I V_E_ _ _ _ _ _ . . ._P__RC_C_ED'. f RE_ S u_C_O_N_D__I T__I O_N_ S_ m_A_N_D _L_.I.M_I T A_T__I C_N_S o
-87/12/15-SULLIVAN, M.
- i. ANSWERS -- TERM: 2 t
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- a. '1000 raReta) / (800 rarer.1/hr) (0.25) 1.05 hourn (0.25)
- b. I(1) d(1)^2 = : (2) d(2)^2 (0.05)
- O ' :' ::.'k 0 +-(E : '; ' e c' 51 ratt > (4 ;~t } 'd 10.15) dc._.c . c '. c = 200 rcT'c: 'br 'O. I S)
(1000 raRcra) / (200 mRcra/hr) (0.05) 5 hcurc (0.25) R~FERENCE Stcr.dcrd dccc rctc cciculation frcra 10CFR2O w.r-oe n'i vn v i .a'n --w a
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s U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _FE801_2_________________ gpc: 2 7 .j Lt.. t - - cu REACTOR TYPE: _pW8-Gg4_________________ r 'l, F , i.[ DATE ADMINISTERED _gZfigflg________________ ue . - EXAMINER: _MILLgR2 _R.______________ CANDIDATE: _________________________ INDIBUCIJgND_IQ_CBNDJDSIg], Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parenthuses after the question. The passing grade requires at least 70% in each category and a final grade of at least 90%. Examination papers will be picked up six (6) hours after the examination starts.
~
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE _VALUE__ ______________ CATEGORY _____________
?'
25.00 25. 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW li ________ 2. PLANT DESIGN INCLUDING SAFETY l _2E 99__ _2E:_%_ ___________ AND EMERGENCY SYSTEMS I 1< _2E 99__ _2Erf9p___________ ________ 3. INSTRUMENTS AND CONTROLS ab(,0) 24.1 $ _ h .1:." _3@rf9 L ___________ _____..__ 4. PROCEDURES - NORMAL, ABNORMAL, r EMERGENCY AND RADIOLOGICAL g CONTROL 122_20_S. ___.._______ ________% Totals V Final Grade All work done on this examination is my own. I have neither given nor received aid. l 1 Candidate's Signature 8
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 only to facilitate legible reproductions.
- 4. Print your name in the blank provided on the cover sheet of the axamination.
- 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-huad corner of the first page of each section of the answer sheet.
B. Consecutively number each answer sheet, write "End of Category __" as ! appropriate, start each category on a agw page, write ggly gg 993 gidg 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 thrgg lines between each answer.
- 11. Separate answer sheets f rom pad and place finished answer sheets f ace down on your desk or table.
- 12. Use abbreviations only if they are commonly used in facility litetatute.
- 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 examinet 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.
L -. . - . . - .
1
- 18. When you complete your examination, you shall:
- a. Assemble your examination as follows: ;
i (1) Exam questions on top. (2) Exam aids - figures, tables, etc. (3) Answer pages including figures which are part of the answer.
- b. Turn in your copy of the examination and all pages used to answer the examination questions.
- c. Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
- d. Leave the examination are.a, 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
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1_ _ _ E8] NCJE6gg_ gE_ byCL E98_ EgMEB_ E69BI_ gEg89IJ gN 2 PAGE 7 ISEBD9PXN9MJCg3_Sg81_IB9NSEEB_9Np,E(yJg_E6gy QUESTION 1.01 (1.00) MULTIPLE CHOICE Which ONE of the following conditions would cause the MAGNITUDE of the temperature (Doppler) coefficient of reactivity to become MORE NEGATIVE.
- a. Inserting control rods from 50% rod density to 75% rod density
?
- b. Fuel temperature decreases from 1500 degrees F to 1200 degrees F ,
- c. The core age increases
- d. Moderator temperature decreases from 500 degrees F to 450 degrees F QUESTION 1.02 (1.00)
MULTIPLE CHOICE During a reactor startup, the IRM readings go from 30% to 65% on the same range in 2 minutes with NO OPERATOR ACTION. What is the Reactor Period 7
- a. 120 seconds ,
l
- b. 155 seconds l
- c. 173 seconds j 1
- d. 357 seconds l
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1:__EBINQJELEg_QE_NUghg83_Egyg8_E(8NI_gEgRSIJgN 2 PAGE 3 IHE8dggyNSdJgg3_HE81_IB8NgEgB_QNQ_Ebulg_E699 QUCSTION 1.03 (1.00) MULTIPLE CHOICE Choose the statement which best describes APLHGR (Average Planar Linear Heat Generation Rate).
- a. APLHGR is the sum total of the average LHGR of each fuel pin divided by the total number of fuel pins in the core.
- b. MFLPD (Maximum Fraction Limiting Power Density) is maintained greatur than or equal tw one in order to prevent exceeding the maximum limiting APLHGR allowed in the core.
- c. APLHGR is maintained below the maximum limiting APLHGR in order to prevent the onset of transition boiling in over 99% of the core fuel bundles.
- d. In the ore, the decay heat as well as the stored heat following a LOCA is determined by the APLHGR value at which the core was operating prior to the accident.
QUESTION 1.04 (1.00) MULTIPLE CHOICE Select the statement below which defines pump cavitation.
- a. The lack of sufficient system backpressure on the discharge side of the pump.
- b. Pressure oscillations at the discharge of the pump due to excessive inlet pressure.
- c. The formation and the subsequent collapse of vapor bubbles which cause erosion of the pump. parts. ,
- d. Cracking of the pump impeller caused by cold water hitting a hot impeller.
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1 1 1:__EBJNg1ELEg_gE_NQgbE98_EgygB_Eb8NI_QEgBBIlgN 2 PAGE 4 ISEBd99YNBdJgg2_bg8I_IBBNjEg8_8ND_Ebg]D_Ebg8 QUESTION 1.05 (1.00) MULTIPLE CHOICE Without core orificing, the coolant flow through a high power bundle would be less than the coolant flow through a low power bundle as power increases because
- a. the two phase flow f riction multiplier decreases.
- b. the coolant quality in the channel increases.
- c. the bypass flow increases.
- d. the fuel rods expand into the channel.
QUESTION 1.06 (1.00) Answer the following question TRUE or FALSE 2 EXPLAIN your choice. One of the factors which determines control rod worth is the thermal diffusion length (L) of the neutrons in the core. QUESTION 1.07 (1.00) l In a subtritical reactor, Keff is increased by control rod withdrawal from .S80 to .965. Which of the following is the amount of reactivity that was added to the core?
- a. O.100 delta k/k i
l
- b. 0.085 delta k/k l l
- c. O.125 delta k/k I i
- d. O.136 delta k/k
/
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1___EBJNCIEkg@_gE_ NUCLE 88_EgyEB_E6SNI_QEgB8I]gN2 PAGE 5
- IbEBDggyN8DJCg2_SE3]_IB3N@EgB_8Np_E6Ulp_E699 QUESTION 1.OS (1.50)
STATE the predominate mode of heat transfer (conduction, convection, or radiation) for the followings (ASSUME NORMAL OPERATION UNLESS OTHERWISE STATED)
- a. Center of the fuel pellet out to the outer edge W
- b. Clad surface to the center of the coolant channel
- c. Clad surface to coolant under the film boiling conditions QUESTION 1.09 (2.00)
' A significant amount of excess reactivity must be loaded into the core at BOL so that 100% power can be attained at the end of a fuel cycle. LIST FOUR (4) negative reactivity inputs (OTHER THAN FUEL BURNOUT), l during power operation, which must be overcome by the excess reactivity loaded. QUESTION 1.10 (1.50) Complete the following; (Blanks may require more than one word) Xenon 135 has two (2) methods of production. About 95% of the Xenon is produced by ___(a) ___ and the remaining 5% is produced by___(b) ___. Xenon also has two (2) removal methods, ___ (c) ___ and ___(d) ___. Samarium 149 is produced only by ___(e) ___ and is removed only by ___ ( f) ___- (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1:__EBJNCJE6Eg_gE_N9C(E88_EgWEB_EL8NI_gEEBBIJgN2 PAGE 6 IBEBdgDyNedJg!2_bEBI_IBBNgEEB_8ND_Ekg]D_E6gW QUESTION 1.11 (2.00) Consider a TURBINE TRIP for UNIT TWO from approximately 20% power. EXPLAIN what would be expected to occur to the following plant parameters or components during the next 15 minutes with NO OPERATOR ACTION. (PROVIDE REASONS FOR ALL THE CHANGES.)
- a. Bypass valves (0.50)
- b. Feedwater temperature (0.50)
- c. Reactor power (0.50)
- d. Reactor pressure (0.50)
QUESTION 1.12 (3.00)
- a. List THREE (3) parameters which contribute to AVAILABLE NPSH (Net Posiitive Suction Head) for a recirculation pump. Limit your answer to those parameters which are DIRECTLY indicated in the ,
CONTROL ROOM. (1.50) l l
- b. Consider the follow'.ng TWO Reactor Plant conditions:
Low Power and Low Flow (<10%) OR High Power and High Flow (>B5%).
- 1. During which condition is the REQUIRED NPSH for a recirculation pump greater? (0.50)
- 2. During which condition in AVAILABLE NPSH for a recirculation pump greater and WHY is it greater? (1.00)
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
1___EBJNCJELES_gE_NggbE63_EQWEB_EL9NI_gEgBSIJgN 2 PAGE 7 ISEBD9DyN9d]Cg3_yggI_IBBNjEEB_3ND_E(gJD_E6gM QUESTION 1.13 (2.00) For a DUAL RECIRCULATION PUMP TRIP transient from power, EXPLAIN the recorder traces on Attached Figures # 2A and 2B.
- a. Why does core flow DECREASE f rom point ONE (1) and then l stabilize at approximately 30%7 (0.25) ;
l
- b. Why does total steam flow decrease and then stabilize between point TWO (2) and point THREE (3)? (0.50) )
1 I
- c. Why does total Feedwater Flow decrease at point FOUR (4)? '
ETWO (2) REASONS REQUIRED, BE SPECIFIC 3 (1.00) i 1
- d. Why does reactor power DECREASE from point FIVE (5) to point SIX (6)? (0.25)
QUESTION 1.14 (2.00) Consider DIFFERENTIAL CONTROL ROD WORTH for the following situations.
- a. Is differential control rod worth GREATER at a moderator temperature of 150 deg F OR a moderator temperature of )
500 deg F. EXPLAIN WHY. (1.00)
- b. Is differential control rod worth GREATER for a rod at position 08 or a rod at position 40 of a core operating at 100% power.
EXPLAIN WHY. (1.00) QUESTION 1.15 (1.00) HOW does the MAGNITUDE of the Doppler coefficient change for a DECREASE of the VOID FRACTION in the core. (Increases, Decreases, OR Remains the Same). EXPLAIN WHY. l l J (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
l 1:__EBJNg]ELEg_gE_Nyg(g88_EQWEB_EkBNI_QEEBBIJgN2 PAGE 8 ISEBdgDIN9dJgg2_SggI_IB9NgEgB_ByD_E(g]Q_E6gW QUESTION 1.16 (1.00) MULTIPLE CHOICE SELECT the correct description of the ONSET OF TRANSITION BOILING.
- a. The area on a heat transf er curve where the moist energy is added to the coolant.
- b. The condition where the fuel cladding becomes continuously blanketed with a vapor film causing the heat transfer coefficient of convection to drastically decrease.
- c. The condition which causes the fuel cladding temperature to increase as the heat transfer coefficient of convection increasen.
- d. The condition which causes the fuel cladding temperature to fluctuate as the clad is alternately blanketed with steam and then rewetted with subcooled coolant.
QUESTION 1.17 (2.00) During a plant Shutdown, reactor pressure decreases from 885 psig to 485 psig in one-half hour. Has the operator maintained the reactor Cooldown Rate within the Fermi Unit 2 administrative limits. (YES or NO) EXPLAIN YOUR ANSWER AND SHOW ALL WORK. ASJHr't [ NO dPCj?4721f_ Qf)& /J 74M/fAl 7's c#,9N$6~ CCOL DoLJN 1297 6, l 1 1 (***** END OF CATEGORY 01 *****)
, 2___EkeNI_ DESIGN _lNC(UDING_SQEEIY_QND_EMEBGENCY_SYSIEd@ PAGE 9 QUESTION 2.01 (1.50)
A minimum water level is required to be maintained in the Condensate Storage Tanks (CSTs).
- a. STATE the MINIMUM LEVEL required in the Unit 2 CST. (0.50)
- b. STATE WHY the minimum level is required. (0.50)
- c. STATE the DESIGN FEATURE which ensures this minimum level is MAINTAINED. (0.50)
QUESTION 2.02 (1.00) The Main Steam Lines are provided with radiation monitors for monitoring the radiation level of the steam lines. CHOOSE the ONE statemrent which correctly describes the Main Steam Line Radiation Monitors.
- a. There are four (4) radiation monitoring channels in an RFS division, any two of these channels in the tripped condition will provide a half scram. ,
1
- b. The two (2) channel select switches for the main steam line ,
radiation monitors allow the operator to select which radiation l monitor in each division will provide an RPS trip signal. I
- c. There is one radiation detector assigned to reach steam 5ine so that it only monitors ti'.e radiation of that one main steam line.
- d. The main steam line radiation detectors are geometrically located in the steam tunnel so that each detector monitors the combined radiation of all the main steam lines.
l l (***** CATEGORY O2 CONTINUED ON NEXT PAGE *****)
I 2.__gl6NI_DESJgy_JNCLUDJNG.SSEEIy_gNp_EdgBgENCy_gySIEbg PAGE 10 i QUESTION 2.03 (2.50) Following a reactor scram, vessel level DECREASED to 82 inches but is now 219 inches (Level 8) and increasing.
- a. LIST FOUR (4) of the five systems / equipment components which receive TRIP SIGNALS at reactor vessel LEVEL 8. (1.00)
- b. STATE ONE (1) of the two reasons f or the Levn1 8 trips. (0.50)
- c. LIST FOUR (4) of the seven systems / equipment components (Or group isolations) which received an ISOLATION SIGNAL due to reaching a reactor water level of 82 inthen. (1.00)
QUESTION 2.04 (1.00) SELECT the ONE correct statement which correctly describes the operation of the MSIV LCS (Main Steam Isolation Valve Leakage Control System).
- a. Division II of MSIV LCS injects and pressurizes the steam lines between the inboard and outboard MSIVs.
- b. Division I of MSIV LCS injects and pressurizes the steam lines between the third MSIVs and the turbine stop valves to prevent steam leakage to the turbine building. .
l
- c. The Division I injecticn valve opens after the isolation. valves open and the main steam piping pressure decreased to 2 psig and close when pressure increases to 6 psig,
- d. The Division II MSIV LCS will isolate if the steam line to reactor differential pressure is less than 1.0 paid for 5 minutes.
QUESTION 2.05 (3.00) STATE SIX (6) of the seven ISOLATION SIGNALS which will cause the ! MSIVs to automatically CLOSE. (INCLUDE SETPOINTS) l l l (.**** CATEGORY O2 CONTINUED ON NEXT PAGE **'4**)
32__eLeNI_pggJgN_ jug 6Up]Ng_ggEgIy_ gyp _gMgBggNQY_gYgIEMS PAGE 11 QUESTION 2.06 ( .75) The major breakers on Bus 69J (Breakers J2, J3, and J4) are provided with interlocks to ensure propor alignment of the bus. Refer to the attached figure # 1 to answer the following question. LIST THREE (3) of the four CONDITIONS that must be met for breaker J3 to AUTOMATICALLY CLOSE. QUESTION 2.07 (2.25) The Scram Discharge Volume (SDV) is protected against filling with rea: tor coolant during power operation (non-scram conditions). STATE the THREE (3) ALARMS and/or TRIPS that the operator will observe if the SDV is slowly filling with reactor coolant. (INCLUDE SETPOINTS AND THE NUMBER OF LEVEL SWITCHES PER ALARM OR TRIP FUNCTION) QUESTION 2.0S (1.50) Each train of the Off-Gas System has a SAND FILTER and an ABSOLUTE FILTER.
- a. STATE ONE (1) of the two PURPOSES served by the SAND FILTER.
(0.50)
- b. SELECT the type of filter used in the ABSOLUTE FILTER.
(1.00)
- 1. Sand
- 2. Activated charcoal bed
- 3. Non-activated charcoal filter
- 4. HEPA filter QUESTION 2.09 (3.00)
The Reactor Building Ventilation Exhaust Radiation detectors monitor the exhaust f rom the Reactor Building at the inlet to the Reactor Building exhtust fan plenum.
- c. LIST the FOUR (4) AUTOMATIC ACTIONS initiated by a trip of the i Reactor Duilding Ventilation Radiation Monitoring system. (2.00)
- b. STATE the TWO (2) TRIP CONDITIONS of the Reactor Building Ventilation Exhaust Radiation Monitoring System which will initiate AUTOMATIC protective actions. (1.00)
(***** CATEGORY O2 CONTINUED CN NEXT PAGE *****)
l 12
. Et__Ek6MI_DESl@d_lMGkMillM@_S6EEll_6ND_EMEE@ENgy_@ySI@M@ PAGE QUESTION 2.10 (1.50)
Balanced swing check valves and motor operated isolation valves ar e placed in the extraction steam lines leading from the main turbine to the feedwater heaters.
- a. LIST the TWO (2) CONDITIONS which will cause an AUTOMATIC CLOSURE of these valves. (SETPOINTS NOT REQUIRED) (1.00)
- b. STATE ONE (1) of the two PROTECTIVE FUNCTIONS served by these valves. (0.50)
QUESTION 2.11 (3.00) The Emergency Equipment Cooling Water (EECW) provides cooling to various auxiliary equipment including Battery Room Space Coolers Control Center Air Conditioning Second and third floor Switchgear Cooling
- a. LIST EIGHT (8) of the remaining thirteen major compnnents cooled by EECW. (2.00)
- 6. LIST the TWO (2) SIGNALS which will AUTOMATICALLY START the EESW (Emergency Equipment Service Water) pumps.
(SETPOINTS NOT REQUIRED) (1.00) i l I l (***** CATEGORY O2 CONTINUED ON NEXT PAGE *****) I I I
.Ea__E68dI_DEg]GU_JU96UDJ$9_g8EEIy_8SD_EDE89EU9Y_EXEIEDS PAGE 13 QUESTION 2.12 (2.00) Reactor Core Isolation Cooling System (RCIC) is an Engineering Safeguards Feature.
- a. Which ONE (1) cf the following is the only normally CLOSED valve when the RCIC steam supply flow path is in the STANDBY LINEUP 7 (1.00)
- 1. Steam Supply Valve (F045)
- 2. Outboard Steam Isolation Valve (FOOB)
- 3. Trip Throttle Valve
- 4. Governor Valve
- b. For each of the situations listed below, STATE whether final RCIC injection into the reactor would: CONTINUE AUTOMATICALLY (no system isolation), REINITIATE AUTOMATICALLY, require CONTROL ROOM Operator action, OR require LOCAL Operator action.
(ASSUME that RCIC had automatically initiated PRIOR to each of the following situations.)
- 1. The RCIC Gland Exhauster VACUUM PUMP FAILS (0.25)
- 2. A 125% Overspeed Trip is received due to low control oil pressure. Control oil pressure is then returned to normal.
(0.25)
- 3. After decreasing to 40 psig, RCIC Steam Line Pressure INCREASES to 150 psig. (0.25) j
- 4. After increasing to 22Y inches, Raatter Vessel Water Level DECREASES to 102 inches. (0.25)
QUESTION 2.13 (2.00) An operator hrs just started the Emergency Diesel Generator for testing folloUing maintenance on the fuel system. l
- a. STATE the MINIMUM LOAD and the MINIMUM TIME that the EDG should be run to reduce mechanical stress and wear. (1.00)
- b. STATE the CONTINUOUS LOAD RATING for an individual EDG. (0.50)
- c. STATE the ACTION that must be taken if EDG starting has been delayed 20 minutus after prelubing the engine. (0.50)
(***** END OF CATEGORY O2 *****) l l
Iz__INEIBUMENIg_@MQ_QQMIBQ(g PAGE 14 l QUESTION 3.01 (1.00) Reactor power is 20% and a plant Startup is in progress. Select the ONE CONDITION which will result in an INSERT BLOCK being applied to the selected control rod. , l
- a. The operator salmets (but does NOT move) a control rod which is not in the currently latched rod group. l
- b. A withdraw error exists and the operator selects a rod other-than the error rod.
- c. A control rod contained in a group lower than the currently latched group is withdrawn beyond its insert limit.
- d. The operator withdraws the selected control rod beyond its withdraw limit.
QUESTION 3.02 (1.00) The Rod Sequence Cor, trol System (RSCS) is designed to prevent excessive control rod worths. SELECT the ONE statement which correctly describes the operation of ; RSCS. ! a. The initialize pushbutton switch f or RSCS is only operable when l power is less than 30% of rated.
- b. The backlight function of RSCS will operate when the Sequence Mode Selector Switch (SMS) is in the NORMAL position and reactor power is less than 35%.
- c. After 50% of the control rods have been withdrawn, the Rod Sequence Selector Switch (RSS) must be switched to the NORMAL position in order to continue red withdrawal.
- d. RSCS uses the rod position reed switches for determining control
. rod positions during group notch control. ; 4 (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****) i ) i r
It__INSIBUMEMIS_AMD_QQMISQLE PAGE 15 QUESTION 3.03 (2.50) The Core Level Indicator (LI-R610) located on Control Room Panel H11-P601 has an indicating range from -150 to +50 inchas.
- a. WHAT is INSTRUMENT ZERO for this level sensor?
(Provide the core component located at Instrument Zero.) (0.50)
- b. Is this level sensor calibrated hot or cold? (0.50)
- c. MATCH the core conditions in Column 1 with the correct response of the core level indicator (LI-R610) in Column 2 .
(1.50) COLUMN 1 COLUMN 2
- 1. LPCI is the only system a. Full Scale injecting into the vessel
- b. Downscale
- 2. No recirculation flow exists, no systems are injecting to c. Actual Level the RPV, and the reactor is at atmospheric pressure d. 14 inches HIGHER than actual level
- 3. Both recirculation pumps are at 45% speed e. 14 inches LOWER than actual level 1 l
1 l l l 1 J (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****) i
3 s_ INSTRUMENTG AND CONTROLS PAGE 16 l l . l I QUESTION 3.04 (2.00) The Station Service and the Emergency Power Electrical Systems use interlocks between various breakers to ensure reliability of power supplies. REFER to the ATTACHED FIGURE # 1 to answer the following questions regarding these interlocks.
- a. SELECT the ONE set of Station Electrical breakers which can be simultaneously CLOSED. (1.00) l I
- 1. K4, K6, AND K11
- 2. H4, J2, AND J3
- 3. B4, B6, AND B12
- 4. C6, C9, AND C11
- b. LIST FOUR (4) of the six breakers which are tripped OPEN for an Undervoltage condition on Bus 64B. (1.00) i QUESTION 3.05 (2.00)
The Main Turbine is provided with a trip system to prevent damage to the turbine or the generator.
- a. STATE the TWO (2) SIGNALS (CONDITIONS) which will result in a 60 second time delayed turbine trip. (1.00)
- b. STATE the type of RPS action (FULL SCRAM, HALF SCRAM, NO ACTION) which will result from the following turbine valve positions.
l
- 1. Turbine stop valves number 1, 2, and 4 fail closed. (0.50)
- 2. Turbine control valves number 1 and 3 fait closed. (0.50) 1
(***** CATEGORY 03 CONTINUED ON NEXT PAGE *****) l 1
3___INSIggdENIS_$NQ_QQUISQ!_S PAGE 17 QUESTION 3.06 (2.50) The reactor is operating at 45% power with Recirculation pump A running and Recirculation pump B tripped (B loop idle) when a design basis LOCA occurs in recirculation loop B. During the LOCA, Recirculation pump A fails to trip on low level. Answer the f ollowing questions concerning the LPCI (Low Pressure Coolant Injection) LOOP SELECTION LOGIC.
- a. STATE the action initiated by the loop select logic PRIOR to proceeding with loop selection. (0.50)
- 6. LIST the signal which provides the LPCI LOOP SELECTION PERMISSIVE. (INCLUDE ANY SETPOINTS) (0.50)
- c. HOW does the loop select logic determine that loop B of the recirculation system has broken / ruptured.
(BE SPECIFIC, SETPOINT NOT REQUIRED) (1.00)
- d. LIST the PERMISSIVE SIGNAL for the LPCI Loop A injection valve to OPEN. (INCLUDE ANY SETPOINTS) (0.50)
QUESTION 3.07 (3.50) Answer the following questions associated with the valve interlocks for the HPCI (High Pressure Core Spray) system.
- a. LIST TWO (2) of the three val *;
Answer the following questions about radiation work permits (RWPs) in accordance with POM 12.000.013 Radiation Work Permit Request.
- a. LIST SIX (6) of the nine CONDITIONS when a General-RWP shall NOT be used. (1.50)
- b. LIST the TWO (2) TYPES of RWPs, in addition to the General RWP, AND EXPLAIN when each is used. (1.00)
QUESTION 4.08 (2.50) Answer the following questions on INDEPENDENT VERIFICATION in accordance with the Administrative Procedure on Verification of Correct Performance of Operating Activities POM 12.000.043.
- a. STATE THREE (3) of the five acceptable METHODS for Independent Verification of system alignment and component status. (1.50)
- 6. STATE the proper METHOD for Independently Verifying the position of the following:
- 1. Motor operated valves (0.50)
- 2. Throttle valves which are NOT sealed (0.50)
I QUESTION 4.09 (2.25) Technical Specifications establish four Safety Limits. LIST the THREE (3) SAFETY LIMITS which must be met in Operational Condition 1 (Power Operations). (2.25) t 1 (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) i 1
~
1 Sz _ _ EBgC EpgB E S_;;_ NgBdeb2_9 B Ng30962_ EdgBGE Ngy_9ND PAGE 23 BOD 196991996_99NIBgb QUESTION 4.10 (1.00) A Plant Startup is in progress. The reactor is critical and the operator is withdrawing control rods to increaue power to the POAH (Point of Adding Heat). Answer the following questions in accordance with the General Operating Procedure on Startup From Cold Shutdown to Rated Power POM 22.00.03.
- a. STATE the MINIMUM and the MAXIMUM Count Rate between which the SRMs (Source Range Monitors) are maintained during startup. (0.50)
- 6. Why are all the SRMs NOT withdrawn simultaneously when BELOW the point of adding heat. (0.50)
QUESTION 4.11 (1.00) During reactor plant cooldown the operator maintains the coolant and vessel metal temperatures within specified limits. Answer the following questions in accordance with Technical Specifications and the General Operating Procedure for Reactor Heatup, ! Cooldown and Temperature vs. Pressure Monitoring POM 22.000.12. i
- a. STATE the CONDITION under which the operator is allowed to STOP recording the vessel temperatures and the reactor pressure on the Temperature / Data Sheet of POM 22.00.12. (BE SPECIFIC)
(0.50)
- b. STATE the LIMITING reactor vessel COMPONENT and the MINIMUM temperature allowed for that component when the reactor vessel HEAD BOLTING STUDS are under TENSION. (0.50)
QUESTION 4.12 (1.75) 1 Following a Reactor Scram, the operator is controlling vessel level j with HPCI (High Pressure Coolant Injection) system. Answer the following questions in accordance with the System Operating Procedure for HPCI POM 23.202.
- a. STATE the MINIMUM RPM below which the operation of the HPCI turbine should be minimized and EXPLAIN WHY. (0.75)
- b. EXPLAIN WHY the HPCI Pump Test Return to Condensate Storage Isolation Valve (E41-F011) shall be closed and deenergized except during testing. (BE SPECIFIC) (1.00)
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
ic__EBQQEDUSES_ _UQBM@bt_@gNQEd@6t_EME8GENQX_@ND PAGE 24 BeDlQ6QGlG@(_QQUIBQ6 QU'IST I ON 4.13 (1.00) Answer the following question in accordance with the Immediate Operator actions for AOP 20.107.01 Loss of Feedwater or Feed Control. STATE the two (2) AUTOMATIC ACTIONS which the operator must immediately verify if ONLY ONE (1) of the two (2) RFPs in service trips. (1.00) QUESTION 4.14 (1.50) An operator must work two f eet f rom a small radi ation source. The gamma / beta dose rate two feet from the radiation source is 800 mram/hr. The operator is not allowed to receive more than 1 Rem on this job.
- a. How long (in hours) can the operator work on this job 7 (0.50)
- b. How long (in hours) can the operator work on this job if the work site is moved so that the operator is four feet from the radiation source? (1.00)
(***** END OF CATEGORY 04 *****) (************* END OF EXAMINATION 4**************)
, 7 f [' {; " * "' Q
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,,. 4 G~ .a ANSWER KEY FERMI 2 RO EXAM MILLER, R.
87/12/15 I l y w
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4
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1s__EBINQlE(gg_QE_NQQ(g@B_EQWEB_E(@NI_QE(8@IlgN i PAGE 25 T_H_ER_M_O_ D_Y_N_A_M_ _I C_g g_H_E_A_T__T_R_A_N_S_F_E_R__A_N_D__F_L_Q _I D_ _F_L_O_W_ .. , ANSWERS -- FERMI 2 -87/12/15-MILLER, R. L. , t a r. : '. i-a F '
,L ~
b ( L' L ANSWER 1.01 (1.00)
><- b e r e-REFERENCE FERMI STUDENT LESSON PLAN ON REACTOR THEORY SECTION S.2.3 LESSON OBJECTIVE NO. 1 2.5 ...K/A VALUE 292OO4K102 ...(KA*S)
ANSWER 1.02 (1.00) b REFERENCE FERMI STUDENT LESSON PLAN ON REACTOR THEORY SECTION 10.6 LESSON OBJECTIVE NO. 2. 3.7 ...K/A VALUE 292OO!K105 ...(KA*S) ANSWER 1.03 (1.00) d i REFERENCE FERMI STUDENT LESSON PLAN ON REACTOR THERMAL LIMITS PG 12-2 AND 12-4. LESSON OBJECTIVE NO. 1. 3.3 ...K/A VALUE 293OO9K110 ...(KA*S) ANSWE'R '1.04 (1.00) c REFERENCE FERMI STUDENT LESSON PLAN ON THERMAL SCIENCES PG 17-20. LESSON OBJECTIVE NO. 2. 2.8 .<.K/A VALUE 293OO6K109 ...(KA*S) i
- 1. PRINQlPLE@_QE_NQC(EAR _PQWER_ PLANI _QEdlgIlQN 2 PAGE 36 ,
ISEEdQQ1NedlGHz_SEel_1EGNgE[B_QNQ,E(Q1Q_E(QW , ANSWERS -- FERMI 2 -87/12/15-MILLER, R. 9 ANSWER 1.05 (1.00) b REFERENCE FERMI STUDENT LESSON PLAN ON THERMAL SCIENCES PG 9-16. LESSON OBJECTIVE NO. 1. 2.9 ...K/A VALUE 293OOOK131 ...(KA*S) ANSWER 1.06 (1.00) TRUE (0.50) Since control rods absorb thermal neutrons, as the thermal diffusion length j increases the rod worth increases because more neutrons interact with the rod.
-OR-Rod Worth is proportional tos (Ls**2 + Lt**2) (ploc/ pave)**2 REFERENCE FERMI LESSON PLAN ON REACTOR THEORY PG B.25.
LESSON OBJECTIVE NO. 1 2.7 ...K/A VALUE 201003K506 ...(KA'S) ANSWER 1.07 (1.00) a REFERENCE FERMI LESSON PLAN ON REACTOR THEORY PG 7.1. LESSON OBJECTIVE NO. 1. 3.3 ...K/A VALUE 201003K506 ...(KA*S) i j I i l
It__E81NQlg(gg_QE_NQQ(EQS_EQWEB_E($NI_Q&[8@IlQN s PAGE 27 ISEBdQDYNQd1QQs_h[gI_IB@NSEgB_gNQ_E(QLQ_E(OW ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ANSWER 1.08 (1.50)
- a. Conduction
- b. Convection (conduction also accepted if both are given)
- c. Radi ati on (0.50 ea.)
REFERENCE FERMI LESSON PLAN ON THERMAL SCIENCES CHAPTER 5. LESSON OBJECTIVE NO. 2. 3.2 ...K/A VALUE 293007K101 ...(KA'S) ANSWER 1.09 (2.00)
- a. Moderator temperature increase
- b. Void fraction increase
- c. Samarium buildup
- d. Xenon buildup
- e. Fuel temperature increase (4 required, 0.50 ea.)
REFERENCE FERMI LESSON PLAN ON REACTOR THEORY PG 7.4 TO 7.6 LESSON OBJECTIVE NO. 1. 2.4 ...K/A VALUE 292002K109 ...(KA*S) ANSWER 1.10 (1.50) 1 l
- a. Decay of Iodine (I3 eta decay) l
- b. Directly from fission '
- c. Neutron absorption (or burnout) I
- d. Radioactive decay (Beta decay) I
- e. Decay of fission products (Nd or Pm) (Beta decay)
- f. Neutron absorption, (or burnout) !
(6 required, 0.25 ea) REFERENCE FERMI LESSON PLAN ON REACTOR THEORY PG 9.1 TO 9.4 LESSON OBJECTIVE NO. 1 l 4
1 i it__ES1NQlELES_QE_NQQ(EQB_EQWEB_E(@NI_QEEB@IlgN s PAGE 23 ISEBdQQXNedlGSs_dEQI_IQQNSEE6_6NQ_E(QLQ,E(QW i ANSWERS -- FERMI 2 -87/12/15-MILLER, R. t 2.9 2.9 ...K/A VALUE 292006K103 292006K104 ...(KA'S) ANSWER 1.11 (2.00)
- a. Bypass valves open to pass the steam previously going to the turbine.
- b. Feedwater temperature will decrease due to the loss of extraction steam.
- c. Reactor power will increase due to the decrease in feedwater temperature. (Slight power increase caused by void collapse upon initial turbine stop valve closure.)
- d. Bypass valves will maintain pressure asproximately constant.
(Reactor pressure will try to increase due to the increase in reactor power.) (4 required, 0.50 ea.) REFERENCE FERMI LESSON PLAN ON REACTOR THEORY CHAPTER 12. LESSON OBJECTIVE NO. 2. FERMI LESSON PLAN ON MAIN TURBINE SYSTEM ; LESSON OBJECTIVE NO. 4. ! 3.9 3.9 3.3 3.7 ...K/A VALUE 245000K302 245000K303 245000K304 245000K308 ...(KA*S) ANSWER 1.12 (3.00) i
- a. Feedwater termperature 1 Feedwater flow i RPV pressure RPV water level Geeieculab k s u el-*.es be m f e.s-d u ec. l (0.50 ea., any 3)
- b. 1. High flow, High power (0.50)
- 2. High flow, High power 40.50), due to the increased inlet subcooling from the increased feedwater 4 low. (0.50)
REFERENCE GE BWR ACADEMIC SERIES ON HEAT TRANSFER AND FLUID FLOW FERMI LESSON PLAN ON THERMAL SCIENCES PG 17-20 LESSON OBJECTIVE NO. 2. r
,it__EBINQlE(Eg_QE_NQQ(EeB_EQWE8_E(8NI QEgB@IlQNs PAGE 29 IbEBdQQ1NQdlQSg_yggI_IBQNgE[B_QNQ_E(Q1Q_E(QW , ANSWERS -- FERMI 2 -87/12/15-MILLER, R.
3.3 3.4 2.7 ...K/A VALUE 202001K607 202001K609 293006K110 ...(KA's) ANSWER 1.13 (2.00)
- a. Core flow decreases to natural circulation (0.25)
- b. EHC closes the turbine control valves to control pressure caused by a decrease in total steam generation rate (0.25). Steam flow then stabilizes at a value equivalent to the steam generation rate of reactor power for natural circulation (0.25)
- c. 1. Level swells in the downcomer due to the increase in two phase flow resistance (caused by increased voiding) and the loss of the recire driving flow (0.25). Feedwater level control senses the increased level in the downcomer and reduces RFPT speed (0.25).
- 2. Reactor power decrease causes a reduced steam generation rate (0.25 reducing the steam flow sensed by feedwater level control in three element thus reducing RFPT speed. (0.25)
- d. Increased voiding in the core adds negative reactivity (0.25)
(EXACT WORDING NOT REQUIRED) REFERENCE FERMI LESSON PLAN ON REACTOR RECIRCULATION SYSTEM LESSON OBJECTIVE NO. 5. FERMI LESSON PLAN ON MITIGATING CORE DAMAGE PG 120. FERMI LESSON PLAN ON REACTOR THEORY PG 12.7 LESSON OBJECTIVE NO. 3. 3.9 3.3 3.3 ...K/A VALUE 202001K303 202001K507 202001K607 ...(KA*S) l i
It__EBINGLELES_QE_MQC(g@B_EQWEB_E(@MI_QEgg@IlQN z PAGE 30 ISEBdQQ1NedlCS,_ug@I_1gegSEgB_@NQ_E(Q1Q,E(QW
, ANSWERS -- FERMI 2 -87/12/15-MILLER, R.
ANSWER 1.14 (2.00)
- a. At 500 deg F. (0.50), As moderator tomoerature increases, neutron thermal diffusion length increases, thus the control rod's area of influence has increased, thus increasing rod worth. (0.50)
-OR- :
Rod Worth is proportional to (Lu**2 + Lt**2) (pl oc/ pave) **2 I
- b. At 08 (0.50), The deep control rod withdrawal adds coupling to cells in ;
the core (substantiolly affecting radial flux) thus producing a large J reactivity worth. (or the rod at 08 is in the higher flux region of ' the core) therefore, drod/ dave is larger for the rod at 08.) (0.25) l Whereas, shallow rod withdrawal (position 40) has a small affect on ! reactivity addition due to the shadowing of nearby rods , thereby I reducing the radial effect. (or shallow rods are shaping rods not producing large overall core power changes) (0.25) REFERENCE GE BWR ACADEMIC SERIES ON REACTOR THEORY PG 5-12, -13, -21, -22, AND -25. FERMI STUDENT LESSON PLAN ON REACTOR THEORY PG B.26 AND B.27. LESSON OBJECTIVE NO. 2. 3.3 3.5 2.5 2.6 ...K/A VALUE 201003K507 292OO5K104 292OO5K109 292OO5K112 ...(KA*S) ANSWER 1.15 (1.00) DECREASES (0.50). As voids decrease, the amount of moderator in the core increases) therefore, the neutrons are thermalized faster (slowing down length is shorter) thus reducing susceptibility to resonance capture. l (0.50) i REFERENCE FERMI STUDENT LESSON PLAN ON REACTOR THEORY PG B.22 AND B.23. l LESSON OBJECTIVE NO. 2. 2.5 ...K/A VALUE 292OO4K111 ...(KA*S)
It__EB1MGIELEE_QE_WVGLEBB_EQWEB_EbeMI_QEEBBI1QNa PAGE 31 ISEBdQQ1Ned1GEi_UEBI_IBBNEEEB_eMQ_ELWLE_ELQW
, ANSWERS -- FERMI 2 -87/12/15-MILLER, R.
1 ANSWER 1.16 (1.00) i d. REFERENCE GE BWR ACADEMIC SERIES ON HTFF CHAPTER B. FERMI STUDENT LESSON PLAN ON THERMAL SCIENCES PG 9-14. LESSDN OBJECTIVE NO. 3. 3.0 ...K/A VALUE 29300BK109 ...(KA'S) ANSWER 1.17 (2.00)
- a. 1. Convert pressure to psian (0.50) 885 + 14.7 = 900 osia and 485 + 14.7 = 500 psia
- 2. Obtain corresponding temperatures from steam tables: (0.50) 900 psia -> 532 F and 500 psia -> 467 F ;
- 3. Determine temperature change (0.50) ,
532-467 = 65 F in one half hour (or 130 deg F/hr cooldown rate)
- 4. NO, the cooldown limitation (90 deg./hr.) has been exceeded. ( 0. '50 )
REFERENCE : SATURATED STEAM TABLES. POM 22.000.03 PG 5. FERMI STUDENT LESSON PLAN ON THERMAL SCIENCES CHAPTER 3. , LESSON OBJECTIVE NO. 3.1.1.2 ! 3.5 2.8 ...K/A VALUE l 29200BK114 293003K123 ...(KA*S) I i 1 l i 4
- - - . , - - -- + -
2___EkeNI_ DESIGN _{NQ(QQLNQ_SQEEIY_6NQ_EMEBGEUQY_SYElgdS PAGE 32 ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ANSWER 2.01 (1.50)D Y* l n r_ ,/,r e- % gal l onu^f , h
- a. 150.000 y 1. m sy4 i ' '
y
- b. 150.000 gallons is required as a reservoir for RCIC and HPCI.
- c. All systems taking a muction on the CSTs, except for RCIC and HPCI, are prevented from drawing the water level below 150,000 gallons by suction standpipes.
(0.50 ea.) REFERENCE FERMI STUDENT LESSON PLAN ON CONDENSATE TRANSFER & STORAGE SYSTEM PG 4 LESSON OBJECTIVE NO. 4. 3.5 3.5 3.2 3.5 3.6...K/A VALUE 206000A103 206000A209 217000A106 217000A216 256000K408
...(KA*S)
ANSWER 2.02 (1.00) d. REFERENCE FERMI STUDENT LESSON PLAN ON PROCESS RADIATION MONITORS PG 11. 20. LESSON OBJECTIVE NO. 5. 2.9 3.6 ...K/A VALUE 272000A401 272000K101 ...(KA*S)
=
k
2t__ELONI_QEglGM_lNQLQQlM@_G6 eel!_6MD_EMESQEUQY_%1RIEd@ PAGE 33 ANSWERS -- FERM1 2 -87/12/15-MILLER, R. ANSWER 2.03 (2.50)
- a. 1. Main Turbine
- 2. Reactor Feed Pump Turbines
- 3. Standby Feedwater isolation valve
- 4. HPCI Turbine
- 5. RCIC Turbine (4 required, 0.25 ea.)
- b. 1. Prevents turbine damage due to carryover
- 2. Prevents overflowing water into main steam lines during operation (which may cause hydraulic pressure surges)
(1 required, 0.50 ea.)
- c. 1. GROUP 2: REACTOR WATER SAMPLE VALVES 9. G Ret 4t' 41 d4 8E
- 2. GROUP 10, 11: RWCU '
- 3. GROUP 12: TWMS q . (g Rou P 13 '- D /kv Su m p 5
- 4. GROUP 14: D/W AND SUPPRESSION POOL VENTS 10 d db u r' I E *- TIF
- 5. GROUP 16: NITROGEN PRESSURE CONTROL
- 6. GROUP 17: REACTOR RECIRC PUMP SEAL PURGE
- 7. GROUP 18: D/W PNEUMATIC SUPPLY 3
(4 required, 0.25 ea., ACCEPT group or system name) REFERENCE FERMI STUDENT LESSON PLAN ON RPV PROCESS INSTRUMENTATION PG 8, 25, 26. LESSON OBJECTIVE NO. 2 AND 5. 3.4 3.8 3.4 3.0 2.9 3.3 3.6 3.7 ...K/A VALUE 216000K103 216000K113 216000K114 216000K116 216000K40S 216000K409 223OO1K402 223001K403 ...(KA'S) ANSWER 2.04 (1.00) d. REFERENCE FERMI STUDENT LESSON PLAN ON MSIV LCS PG 6. LESSON OBJECTIVE NO. 4 AND 5.
- 3.1 3.4 ...K/A VALUE 239003A101 239003G007 ...(KA'S) 1
2___P(QUI _DgSIGN_LUQ(UDINQ_SQ((IY_QNQ_Ed[RQEMQY_@Xflgd3 PAGE 34 ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ANSWER 2.05 (3.00)
- a. 1. MSL high radiation, 3.3 (+/- 0.3) x Normal Full Power
Background
- 2. Low reactor water level, Level 1 ( OR 28 inches +/- 5 inches)
- 3. High steam tunnel temperature, 200 deg. F +/- 20 deg.
- 4. Low steam line pressure in RUN, 745 psig +/- 25 psig
- 5. Low main condenser vacuum, 7.0 psia +/- 1 psia
- 6. Main steam line high flow, 138% of rated flow (+/-15%)
(also accept: 110 paid +/- 10 psid)
- 7. High turbine building steam tunnel area temperature, 200 deg.F ;
+/- 20 deg.
(6 required, 0.25 per signal, 0.25 per setpoint) REFERENCE FERMI STUDENT LESSON PLAN ON MAIN STEAM AND BYPASS SYSTEM PG 19, 20. TECHNICAL SPECIFICATION TABLE 3.3.2 LESSON OBJECTIVE NO. 4 3.8 ...K/A VALUE 239001K401 ...(KA*S) ANSWER 2.06 ( .75)
- 1. Dreaker control switch for J3 is in AUTO
- 2. U2 breaker is OPEN
- 3. Breakers to Circulation Water Pumps 1, 2, and 3 are OPEN
- 4. No fault exists on Bus 69J (3 required, 0.25 ea.)
REFERENCE FERMI STUDENT LESSON PLAN ON ELECTRICAL OVERVIEW LESSON OBJECTIVE NO. 2 PRINT 6SD721-25000-1 3.1 ...K/A VALUE 262OO1K403 ...(KA*S) 4
,2L__P(QUI _DEgl@d_lNQLUDING SAFETY AND EMER@gNQY_gYSTEMS PAGE 35 ANSWERS -- FERMI 2 -87/12/15-MILLER, R.
i ANSWER 2.07 (2.25) 2 32 yi. SDV level high alarm, J' level switchY 4.0 y-F. 3,0 ( +/- -0 r& g al . ) 1.
- 2. Rod Block, 2A' level switchY 70 gal. (+/-7 gal.)oR54/[/h/'2A9*s-,;
- 3. Discharge Volume High Level channel (al p accepts ,'
4tJflevel switches, gal. gal . )oR 594'/ 2'< 4,2' level switches, 120 gal. ( - g al . ) oR 594 /-2', (also accept g4' level swi tches , -100 e,- 120 gal. ( 2' gal.)oC 594 43 required at 0.75 ea., 0.25 per signal, 0.25 per no. level switches, 0.25 per setpoint) , REFERENCE FERMI STUDENT LESSON PLAN ON CRD PG 12, 18. LESSON OBJECTIVE NO. 3 3.6 ...K/A VALUE 201001K411 ...(KA*S) ANS4ER 2.08 (1.50)
- a. 1. Removes nongaseous decay daughters
- 2. Attenuates any transient pressure wave providing protection for Off-Gas System vessels downstream. *
(1 required, 0.50 ea.)
- b. 4. HEPA FILTER (1.00)
RIIFERENCE FERMI STUDENT LESSON PLAN ON CONDENSER VACUUM & OFF-GAS SYSTEM PG 12, 13. LESSON OBJECTIVE NO. 2 3.3 ...K/A VALUE 271000 GOO 7 ...(KA'S)
2___ELBNI_Dgstgg_1ggquq1gg_SeggIy_euD_gMggggggy_SySIgMg PAGE 36 ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ANSWER 2.09 (3.00)
- a. 1. Starts SBGT
- 2. Closes primary containment vent valven
- 3. '-ips/ Isolates Reactor Building Vent system
- 4. Isolates Control Center and initiates emergency recirculation (also accepts shifts Control Center Ventilation to emergency o
- 5. recirculatf.
Trig >s Che orn mode) Q \Ied ha s (ngplyam)almus)) b ald, (4 required, 0.50 ea.)
- 6. 1. 1 - HIGH HIGH alarm / trip
- 2. 2 - Downscale (Low) alarms / trips (2 required, 0.50 ea.)
REFERENCE FERMI STUDENT LESSON PLAN ON PROCESS RADIATION MONITORING PG 30. LESSON OBJECTIVE NO. 4 3.7 ...K/A VALUE l 272OOOK402 ...(KA*S) ANSWER 2.10 (1.50)
- a. 1. Turbine trio
- 2. Feedwater heater high water level (2 required, 0.50 ea.)
- 6. 1. Prevents turbine overspeed (in conditions such as a turbino trip)
- 2. Prevents flooding of the turbine (also accepts prevents water impingement on turbine blading)
(i required, 0.50 ea.) REFERENCE FERMI STUDENT LESSON PLAN ON HAIN TURBINE SYSTEM PG 48, 49. LESSON OBJECTIVE NO. 11 AND 16 1 2.9 ...K/A VALUE 245000K405 ...(KA'S) t
2___ELOWI_QE310N_INGLWQ1NQ_EGEEIY_eSQ_E5EB@EUGY_EYEIEd3 PAGE 37 ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ANSWER 2.11 (3.00)
- a. 1. SBGT space cooler /#, E6C/v fgau de,/re RHR space cooler 2.
- 3. Hydrogen control cooler /C g' } , , j ;), ,. ( ,* ,p, '/, p f3,,~3 fj, ;g/A/ / r ii #r /s A > / m i [c e // h ,,
- 4. Core Spray and RCIC room cooler ;
- 5. Core Spray motors -
- 6. RHR motors
- 7. Recire pump and motors B. D/W cooling units
- 9. CRD pumps
) 10. HPCI space cooler
- 11. Recombiner space coolers
- 12. Reactor Building equipment sump
- 13. D/W sump (B required, 0.25 ea.)
- b. 1. Loss of power to RBCCW pumps i
- 2. Low differential pressure between supply and return loops of essential RBCCW I (2 required, 0.50 ea.)
REFERENCE FERMI STUDENT LESSON PLAN ON RHRSW AND EESW PG 24 LESSON OBJECTIVE NO. 8 FERMI STUDENT LESSON PLAN ON RBCCW AND EECW. LESSON OBJECTIVE NO. 1 AND 4 EECW PRINTS M5729-1 AND M5729-2 2.8 3.1 3.1 2.9 ...K/A VALUE 201001K106 202001K107 203000K116 209001K112 ...(KA*S) ANSWER 2.12 (2.00) I
- a. 1. F045 (1.00)
- b. 1. Continue automatically
- 2. Local operator action
- 3. Control Room operator action
- 4. Reinitiate automatically (4 required, 0.25 ea.)
REFERENCE FERMI STUDENT LESSON PLAN ON RCIC PG 14 15, 16, 25. LESSON OBJECTIVE NO. 4
2 __ELBNI_DESIGU_lMQ(GDING_S@EEIY_@ND_(bERGENgy_SYSIEMS PAGE 38 ANSWERS -- FERMI 2 -87/12/15-MIt.LER, R. 3.5 3.6 3.6 3.3 ...K/A VALUE 217000A301 217000A302 217000A404 '17000K402 ...(KA'S) ANSWER 2.13 (2.00) s
- a. 1750 KW (+/- 200 KW) (0.50) for at Imast 2 hours (0.50)
- b. 2850 KW (+/- 200 KW) (0.50)
- c. Hand bar the engine over (0.50)
REFERENCE FERMI STUDENT LESSON PLAN ON EDG. LESSON OBJECTIVE NO. 2 AND 3. , POM 23.307 PG 7. 3.4 3.7 3.8 ...K/A VALUE 264000A203 264000 GOO 1 264000K101 ...(KA'S) 1 1 l l i l l
I 1 PAGE 39
.Es__lNSIBUMENI@_@NQ_QQNIBQL@
ANSWERS -- FERMI 2 -87/12/15-MILLER, R. l l ANSWER 3.01 (1.00) ! b. REFERENCE FERMI STUDENT LESSON PLAN ON RSCS PG 4, 5. LESSON OBJECTIVE NO. 2 I 3.4 ...K/A VALUE 201006K401 ...(KA*S) ANSWER 3.02 (1.00) c. REFERENCE FERMI STUDENT LESSON PLAN ON RSCS PG 5, 6, 7, 9. LESSON OBJECTIVE NO. 3. 3.9 3.1 3.2 ...K/A VALUE 201004GOJ7 201004K103 201004K405 ...(KA*S) ANSWER 3.03 (2.50)
- a. Too of active fuel (0.50)
- b. Hot (0.50)
- c. 1. d
- 2. c
- 3. a (0.50 ea.)
REFERENCE FERMI STUDENT LESSON PLAN ON RPV PROCESS INSTRUMENTATIONP 'G 6. LESSON OBJECTIVE NO. 3. 3.7 3.3 ...K/A VALUE 216000K105 216000K123 ...(KA*S) l
l 3___[NBIBUMENIS_QND_QONIB063 PAGE 40 ANSWERS -- FERMI 2 -87/12/15-MILLER, R. l ANSWER 3.04 (2.00)
- a. 3 (1.00)
- b. B4, B5, B6, 89, B10, B11 (4 required, 0.25 ea.)
REFERENCE FERMI STUDENT LESSON PLAN ON EDG PG 45 LESSON OBJECTIVE NO. 4 3.1 2.8 ...K/A VALUE 262OO1K403 262OO1K40i ...(KA*S) ANSWER 3.05 (2.00)
- a. 1. Rectifier cooling water low flow
- 2. Stator water cooling low flow (2 required, 0.50 ea.)
- b. 1. Full scram ^0j$ ,
- 2. Half scram -{' ' ' N o Med.th' '
(2 required, 0.50 ea.)
. b b REFERENCE FERMI STUDENT LESSON PLAN ON RPS PG 17, 18.
LESSON OBJECTIVE NO. 4 FERMI STUDENT LESSON PLAN ON MAIN TURBINE PG 116, 117, 118. LESSON OBJECTIVE NO. 11 3.7 3.6 ...K/A VALUE 241000K405 241000K406 ...(KA*S)
i I 3 __1NgIByMENIg_AND_CONIROL@ PAGE 41 ) i ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ' ANSWER 3.06 (2.50)
- a. Trips Recirc MG set A (Recirc pump A trip) (0.50)
- b. Low RPV pressure (0.25) 886 psig (+/- 50 psig) (0.25)
- c. Loop select logic monitors d/p between recirc riser A and B (0.50) and identifies the pressure in riser A is greater than the pressure in riser B (0.50).
- d. Low RPV pressure (0.25) 441 psig (+/- 50 psig) (0.25)
REFERENCE FERMI STUDENT LESSON PLAN ON RHR PG 29, 48. LESSON OBJECTIVE NO. 3 AND 4. 3.9 4.0 ...K/A VALUE 203OOOK410 203OOOK411 ...(KA'S) ANSWER 3.07 (3.50)
- a. 1. Throttle CST test return (FOOB) (0.25)
Closes if either HPCI suopression pool suction valve (F042 or F041) is OPEN. (0.50)
- 2. CST test return (F011) (0.25)
Closes if either HPCI suppression pool suction valve (F042 or F041) im OPEN (0.50)
- 3. Minimum flow valve (F012) (0.25)
Closes if the steam suoply valve (FOO1) is fully CLOSED or the turbine stoo valve (F067) is not fully OPEN (0.50) h?lto a ce.c f '. CST s u e fi<~, vabe El/0 (2 required, 0.75 ea.) ,. p ,g,
, f
- b. 1. F.OO6 CLOSED ferI sucliam v'alves ( fe t} l y! FC ?' 2.)
2. 3. F067 F600 CLCSED OPEN ] are e I> e n , '
- 4. F079 OPEN (0.50 ea.)
REFERENCE E Z-FERMI STUDENT LESSON PLAN ON HPCI 4PG 23, 24, 27. LESSON OBJECTIVE NO. 4 3.8 3.9 3.0 ...K/A VALUE 206000K401 206000K402 206000K508 ...(KA'S)
3:._.1N@lRWENIS_6ND_C MIBOb@ PAGE 42 1 ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ' ANSWER 3.08 (3.00)
- 1. SRM detector not fully inserted into the core (0.25) below the retract permit (100 cps +/-10) and any IRM less than range 3. (0.25)
S~ , 5' f ,
- 2. Any SRM upscale (0.25) 1.5 x 10EE,6' cps (+/ 72'x 10EFM (0.25)
- 3. Anv SRM downscale (0.25) 3 cps (+/- 1 cos) (0.25)
- 4. Any SRM inop (0.25) Module unplugged Switch out of operate High volts low (0.25)
- 5. Any IRM detector not fully inserted into the core (0.50)
- 6. Any IRM upscale (0.25) 110/125 (+/- 5/125) (0.25)
- 7. Any IRM downscale (0.25) 3/125 (+/ f2'/125) t (0.25)
- 8. Any IRM inop (0.25) Module unplugged Switch out of operate High volts low (0.25)
(6 required, 0.50 ea.) REFERENCE FERMI STUDENT LESSON PLAN ON RMCS PG 12, 13, 15. LESSON OBJECTIVE NO. 4 3.5 ...K/A VALUE 201002K402 ...(K4*S) 311ra'Hlf G, ll11Y Aff!/s1 j o te,) (O . 2 jj '# Sw ,?< ' W/e "f eye r< . , e 7ie eba pn!s
^
(c*,27,' so. A.< v A r'a m g,zr>f ay g e,/Jge,,,,',,,,,. (7 :l' te.zs-) ups c <3 c, c e r, d ns> , F it. Sera >n %)m e<,r (i . t r ' 5~9/ A (//- 2 ff' ac we Le,et ' og ,o ga !. o.i- ?gs '. ) cc. z r' l
2 __[NgIBUMgNIg_8MD_COMIB06@ PAGE 43 ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ANSWER 3.09 (2.50)
- a. No (0.50) Both Core Spray pumps in a loop must be running.
(Core Spray pumps A and C OR B and D) (0.50)
- b. Section 2 half of 130/260 VDC Battery A (0.50)
- c. BOTH ADS logic channels in each division (A and C OR B and D)
(0.50) M
- d. When either Core Spray pump in loop A is running Wh4MHIf" Core Spray loop pressure greater than or equal to
*1 '25 psig 15 psig) of D)kk ellls t r bid fu my 2f)h. /c cf // /S ,
r a n >r a >y ,,
- RH A Icej y)festu*'t 1. < er &;n u
( d,IO)Jrede r REFERENCE 4r il 5 P 5 i 9 M- / 0 Pd6 FERMI STUDE ESSON PLAN ON ADS FIGUR 2 AND PU 7, 8, 9. LESSON OBJECTIVE NO. 3 4.0 3.1 3.8 ...K/A VALUE 218000K102 218000K201 218000K403 ...(KA*S) ANSWER 3.10 (3.00) l
- a. 1. Post Scram Feedwater Logic light comes on ;
- 2. Post Scram Water Level Setdown light comes on
- 3. SCRAM TDR ACTUATED alarm comes in '
(2 required, 0.50 ea.)
- b. 10 inches (+/- 2 inches) (0.25) level setdown setpoint initiated (0.25)
- c. 1. Startup Level Control Valve (0.25) is transferred to AUTO (0.25) l
- 2. RFP motor operated discharge valve (0.25) receives a close signal (0.25)
- 3. RFP hydraulically operated discharge valve (0.25) receives a close signal (0.25)
(3 required) REFERENCE FERMI STUDENT LESSON PLAN ON REACTOR VESSEL LEVEL CONTROL PG 10, 11. LESSON OBJECTIVE NO. 3 3.6 2.9 ...K/A VALUE 259002K105 259002K404 ...(KA*S)
@c__lN@l6UbENI@_6MD_ CON 1606@ PAGE 44 )
. i ANSWERS -- FERMI 2 -87/12/15-MILLER, R. l 1 l d ANSWER 3.11 (2.00)
- a. Each pump goes to 45% speed (0.50)
- b. Recire pump A - TRIPPED (0.25) ,,
RecircpumpB-95%spbe 0 4](w, 25 ) (also !A+vtl [e e rec ice- (b run hoell if 34e t hecder d arcepY s'cks a reO'y)lec-l. hew
- c. Both check valves, in the number 5 heater drains to the flash tanks, are closed. (0.50)
- d. Recirc pump A - 95% speed (0.25)
Recire pump B - goes to maximum speed (approximately 102.5% speed) (0.25) REFERENCE FERMI STUDENT LESSON PLAN ON RECIRC FLOW CONTROL PG 11, 12, AND FIG 2. LESSON OBJECTIVE NO. 3, 3.2 ...K/A VALUE 202OO2K305 ...(KA'S)
4:__E80CEDUBE@_;_NOBd@Lg_@@NOBM@(2_EMEB@ENQY_QND PAGE 45 RADIOLOGICAL CONTROL j . 1 ANSWERS -- FERMI 2 -87/12/15-MILLER, R. I l ANSWER 4.01 (2.50)
- 1. Torus water level above &2 inches
- 2. Torus water level below -2 inches l
- 3. Torus water average temperature above 95 deg. F ,
- 4. Drywell atmosphere average temperature above 135 deg. F '
- 5. Drywell pressure above 1.88 psig (5 required, 0.50 ea.)
REFERENCE FERMI STUDENT LESSON PLAN ON OC&P EMERGENCY PROCEDURE GUICELINES l' LESSON OBJECTIVE NO. 2. POM 29.000.03 PG 1. 4.3 4.4 4.2 4.2 4.3...K/A VALUE 295024G011 295026G011 295028G011 295029G011 295030G011
...(KA*S)
ANSWER 4.02 (2.00)
- a. Below 110 osig RCIC (0.50) and HPCI will be isolated. (0.50)
(Therefore motor driven injection systems are required to maintain reactor water level.) ,
. (an>vo,
- b. Injecting with the Core S ay System not a circulating the baron into the core (an a y 'e slow or deter the circulation of the baron into corw) since SLC injects below the core plate and Core SprA inj s above TAF. (1.00)
REFERENCE FERMI STUDENT LESSON PLAN ON OC&P FOR ATWS PG 9. LESSON OBJECTIVE NO. 3. POM 29.000.05 PG 3. POM 29.00.0.08 PG 4. . 3.7 3.7 ...K/A VALUE 295031 GOO 7 295037 GOO 7 ...(KA'S)
4t__P80CEDy8ES_;_NO8M@(z_6ENO8d@61_EMEEGENQY_6NQ PAGE 46 l BB91969G1CB6_QQNI8QL j l , ANSWERS -- FERMI 2 -87/12/15-MILLER, R. l l AN3WER 4.03 (2.00)
- 1. Monitor the general state of the plant, if entry conditions occur enter EOPs. Exit the EOP when the condition no longer exists and enter appropriate procedures as directed by the NSS.
- 2. Monitor the reactor water level / pressure and containment pressures / temperatures f rom multiple indications.
- 3. If a safety function initiates automatically, assume that a true initiating event has occurred unless otherwise verified.
- 4. Whenever LPCI has initiated, establish RHR heat exchanger cooling and inject through the heat exchangers as soon as level control permits.
- 5. The defeat of any trip, isolation, or accident signal must be perf ormed in accordance with the applicable Maintenar.ce I n t,truc t i on .
- 6. Assure that the NSS is informed of any change in the plant status !
and that it may affect the emergency classification. (4 required, 0.50 ea.) REFERENCE FERMI STUDENT LESSON PLAN ON OCLP EMERGENC', PROCEDURE GUIDELINES. LESSON OBJECTIVE NO. 3. POM 21.000.13 ENCLOSURE 1. 3.7 ...K/A VALUE 295037G007 ...(KA*S) ; i
4c__PEOCEDUBES_n_NO80@(3,@BNOBd@(z_EMEEGENgy_@ND PAGE 47 BBD1Q60G1C66_QQNIBQ6 , ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ANSWER 4.04 (3.00)
- a. 1. Verify that the standby station air compressor starts at 95 psig station air pressure.
- 2. Verify that the station air isolation valve (P50-F401) closes at 85 psig station air pressure.
- 3. Verify that the North and South control air compressors start at 65 psig control air pressure.
- 4. Verify that the three non-interruptable control air isolation valves (P50-F402, -F440, -F441) close at 75 psig control air pressure. p g 9, (4 required, 0.25 per auto action, 0.25 per setpoint [+/- 5 psig])
- b. 1. SCRAM VALVE PILOT / AIR HEADER HIGH/ LOW annunciator AND
- 2. A CONTROL ROD DRIFT INDICATION IS RECEIVED ON MORE THAN "NE Control Rod.
(2 required, 0.50 ea.) REFERENCE FERMI STUDENT LESSON PLAN ON OCLP MISC ABNORMAL OPERATING PROCEDURES PG 21. LESSON OBJECTIVE NO. 18. POM 20.129.01 PG 1. 3.7 ...K/A VALUE 295019G010 ...(KA*S) i l
4:__BBOQEDQ8Eg_;_NO80@(z_@BMO80@(3_EdE8GENQY_ANQ PAGE 48 bed 1Q(QGlG@(_QQNIBOL ANSWERS -- FERMI 2 -87/12/15-MILLER, R. ANSWER 4.05 (1.50)
- a. 1. TBCCW heat exchanger outlet temperature > 115 deg. F
- 2. Main Turbine thrust bearing oil drain temperature greater than 170 deg. F
- 3. Any Main Turbine bearing metal temperature > 170 deg. F (2 required, 0.25 per condition, 0.25 per setpoint C+/- 10 deg. F3)
- b. 1. The electric fire pump auto starts
- 2. The diesel fire pump auto starts (2 required, 0.25 ea.)
REFERENCE FERMI STUDENT LESSON PLAN ON OC&P MISC ABNORMAL OPERATING PROCEDURES PG 23. LESSON OBJECTIVE NO. 20. POM 20.131.01 PG 1. 3.4 ...K/A VALUE 295018G010 ...(KA*S) ANSWER 4.06 ( .50) Operational Support Center (0.50) REFERENCE POM EP-110 PG 7 AND 11.
'.6 ...K/A VALUE 294001A110 ...(KA'S)
4:__P80GEDU8ES_ _MO8d@(z_8EMOBM@(z_EMESGENQY_AND PAGE 49
, 8@DIO(OGig@(_QOMIBOL ANSWERS -- FERMI 2 -87/12/15-MILLER, R.
ANSWER 4.07 (2.50)
- a. General RWP shall not be used:
l f
- 1. To enter posted radiation areas
- 2. To enter posted contaminated areas
- 3. To enter posted high radiation areas
- 4. To enter posted neutron radiation areas
- 5. To enter areas posted "SPECIFIC RWP REQUIRED FOR ENTRY"
- 6. System breach on contaminated /potentially contaminated systems
- 7. To enter posted airborne radioactivity areas
- 8. Crawling, climbing, or hands-on work without HP authorization
- 9. To perform radiography (6 required, 0.25 ea.)
l
- b. 1. Routine Specific RWP: used for routine duties in areas of the RCA where the radiological conditions are known.
- 2. Job Specific RWP: used for a specific task in a specified area.
(2 required, 0.25 per name, 0.25 per description) REFERENCE FERMI STUDENT LESSON PLAN ON PLANT ADMINISTRATIVE PROCEDURES. LESSON OBJECTIVE NO. 4. POM 12.000.013 PG 2 AND 3. 3.3 ...K/A VALUE 294001K103 ...(KA*S) j l 1
I 4:__PBQQEQUEEQ_ _MQ80@6z_@@MQBd@(1_EME8@ENQY_QNQ PAGE 50 l
- BBQ1969G1GB6_QQNIBQ6 ANSWERS -- FERMI 2 -87/12/15-MILLER, R.
1 ANSWER 4.08 (2.50)
- a. 1. Direct ohysical observation of correct component status
- 2. Observation of local or remote status indicating devices
- 3. Observation of a process parameter which indicates the system is in the proper configuration
- 4. Observation of a sealing device
- 5. Activities perf ormed locally are verified locally (3 required, 0.50 ea.)
- b. 1. Motor operated valves may be verified by the Control Room or Local Panel position indication (if the position indication is not suspect) (Also accept: Manual check of valve position by attempting to operate the valve in the closed direction. )
- 2. Throttle valves which are not sealed should be verified at the time of positioning. (This may be considered a transient phenomenon.)
(2 required, 0.50 ea.) REFERENCE FERMI STUDENT LESSON PLAN ON OCLP ON PLANT ADMINISTRATIVE PROCEDURES PG 3 AND 5 LESSON 1BJECTIVE NO. 17. POM 12.000.043 PG 6 AND ENCLOSURE 1. 3.7 3.9 ...K/A VALUE 294001K101 294001K102 ...(KA*S) ANSWER 4.09 (2.25)
- 1. Thermal power shall not exceed 25% rated (0.25) with steam dome pressure < 785 psig (0.25) or core flow < 10% ra.ted (0.25).
- 2. MCPR shall not be less than 1.06 (0.25) with steam dome pressure > 785 psig (0.25) and core flow > 10% rated (0.25).
- 3. RPV (cociant) pressure (0.25) shall not exceed 1325 psig (0.50).
REFERENCE FERMI STUDENT LESSON PLAN ON OC&P FOR PLANT ADMINISTRATIVE PROCEDURES PG 4. LESSON OBJECTIVE NO. 24. TECHNICAL SPECIFICATION 2.1. 3.3 ...K/A VALUE
4:__EBQQEQUBES_ _NQBd@65_QgNQSU@6z_EdEBGENCY ANQ PAGE 51
. B8Q1969GLCeg_CQN18Q6 ANSWERS -- FERMI 2 -87/12/15-MILLER, R.
290002 GOO 5 ...(KA*S) ANSWER 4.10 (1.00)
- a. 1x 10 EE2 to 1 x 10 EE5 (0.50)
- b. SRMs are not simultaneously withdrawn so as to allow continuous monitoring of reactor power during startup. (0.50)
REFERENCE FERMI STUDENT LESSON PLAN ON OC&P FOR NORMAL STARTUP AND SHUTDOWN PG 4. LESSON OBJECTIVE NO. 9. POM 22.00.03 PG 14. 3.2 ...K/A VALUE 215004G010 ...(KA*S) ANSWER 4.11 (1.00)
- a. When THREE consecutive temperature readings of < 5 deg. F change (0.25) over a 30 minute period exist (0.25) (and desired plant conditions are reached,)
- b. The reactor vessel / head flange (0.25) shall be greater than or equal to 71 dag. F (0.25).
REFERENCE FERMI STUDENT LESSON PLAN ON OC&P FOR NORMAL STARTUP AND SHUTDOWN PG 3. LESSON OBJECTIVE NO. 25 AND 26. TECHNICAL SPECIFICATION 3.4.6.1 POM 22.000.12 PG 1. 3.5 3.3 ...K/A VALUE 290002 GOO 1 292OO2 GOO 5 ...(KA'S) I I P 1
4___PBQQEDUSES_;_NQ8MQ(2_@BNQBdQ(t_EUEEGENQX_QND PAGE 52
, B8D1969 GIG 8(_QQNIBQL ANEMERS -- FERMI 2 -S7/12/15-MILLER, R.
ANSWER 4.12 (1.75)
- a. The HPCI turbine operaticn should be mintmized below 2150 rpm (4[- l TO f fr ,
(0.25) to ensure stability of operation (0.50).
- b. The HPCI Test Return Isolation valve (F011) will be closed and deenergized to prevent plant fires from causing a hot short, allowing the valve to open, bypassing the HPCI/RCIC flow from the vessel. (1.00)
REFERENCE FERMI STUDENT LESSON PLAN ON HPCI. LESSON OBJECTIVE NO. 3. POM 23.202 PG 5 AND 6. 3.2 ...K/A VALUE 209002G010 ...(KA*S) e
.if .; ANSWER 4.13 (1.00)
[k
- 1. Remaining RFP restores and maintains level between level 4 and level 7 (0.50)
- 2. Recirculation pumps run back to 45% speed (0.25) if low level alarm occurs. (0.25)
,o REFERENCE FERMI 2 LESSON PLAN RPV LEVEL CONTROL (N21) PG 10 ,
FERMI 2 AOP 20.107.01 PG 3 l 4.2 ...K/A VALUE l 295009G010 ...(KA'S) ' i i l ( l 1 f 1
e i
' 4:__EBQQEDUBEH_ _NQBd@62_@@NOBd@(z_gdERGEUg1_@NQ PAGE 53 RADIOLOGICAL CONTROL '
= ANSWERS -- FERMI 2 -87/12/15-MILLER, R.
ANSWER 4.14 (1.50)
- a. (1000 mrem) / (800 mrem /hr) (0.25)
= 1.25 hours (0.25)
- b. I(1) d (1) **2 = I (2) d(2)**2 (0.25)
(BOOmRem) * (2 ft)**2 = dose rate * (4 ft)**2 (0.25) dose rate = 200 mrem /hr (0.10) (1000 mrem) / (200 mrem /hr (0.25) 5 hours (0.25) i ,. REFERENCE STANDARD DOSE RATE CALCULATION FROM 10CFR2O 3.3 ...K/A VALUE 294001K103 ...(KA'S) l 1 I 1
-. __ _ _ , _ _ _ . .. __ .______ _ ___}}