IR 05000412/1987042
| ML20235J323 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/02/1987 |
| From: | Barber G, Collins S, Keller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20235J304 | List: |
| References | |
| 50-412-87-42OL, NUDOCS 8707150496 | |
| Download: ML20235J323 (102) | |
Text
{{#Wiki_filter:,
. . U. S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT { i l EXAMINATION REPORT NO.
50-412/87-42 (OL)
l ) FACILITY DOCKET NO.
50-412 l l LICENSEE: Duquesne Light Company ) P. O. Box 4 { Shippingport, Pennsylvania 15077 , i I FACILITY: Beaver Valley Unit 2 ~ EXAMINATION DATES: May 18-22, 1987
l CHIEF EXAMINER: brM2.7% /;- 7-2 - B 7 G. S. Barber, Rd ctor Engineer (Examiner) Date i [!'l REVIEWED BY: [ / 7/1 N 7 l R. M. Keller, Chief, Projects Section 1C ' Date APPROVE 0 BY: /hlk/(flly/M 9fff8~[ 5. Collins,' Deputy Director, DRP Date l
l ' ! SUMMARY: Operating and written examinations were administered to eight reactor operator (RO) candidates and 14 senior reactor operator (SRO) candidates.
Of these candidates, four RO candidates and eight SRO candidates passed all por-tions of their examination and will be issued licenses.
l Knowledge and use of normal and abnormal procedures was a generic weakness.
Further details are provided in the report.
l l \\ ! fh?6070797 K 050004 V
PD _ -. _ _ _ _ _ - _ _ _ _ _ _ - _ _ _
--_.
. . REPORT DETAILS TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS: ) l RO l SRO l l Pass / Fail l Pass / Fail l l l
l l l l l l l Written l 5/2 l 11 / 2 l , I l l l l l l l .I l Operating l 6/2 l 9/4 l l l l l ) I I I I l l0verall l 4/4 l 8/6 l { l l l l l l l l l l CHIEF EXAMINER AT SITE: G. S. Barber, NRC l OTHER EXAMINERS: B. S. Norris, NRC D. M. Silk, NRC .l K. Parkinson, Sonalyst ' G. Weale, Sonalyst i I.
l . - _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - -
- - .,
'.
1.
Summary of generic deficiencies noted from grading of written examinations.
This information is being provided to document areas of weakness which should aid the licensee in upgrading initial and requalification training programs.
No reply is required.
Reactor Operator Candidates Question No.
1.06 Proper use of heat transfer equation associated with i heat exchangers (Q = UA delta T) j l 2.0lb Conditions that could cause the Gaseous Waste Disposal ' Surge Tank rupture disc to rupture 2.02b Different methods and initiating conditions for intro-I ducing NaOH to containment i 2.05b Identification of symptoms that would indicate a leaky incore thimble guide tube l 2.07 Design features that prevent draining the spent fuel pool below the top of the fuel racks l 2.10 Effects of a malfunctioning Component Cooling Water Pump Discharge Pressure Control Valve l 3.01 Effects of a VCT level channel failure l - , l 3.05b Conditions when emergency bus UV lockout schemes are l in effect 3.05c Major pumps that are not started on an ESF actuation signal 4.01a Frequency of recording radioactive liquid flow rate during a release 4.04 Knowledge of major RCS precautions and limitations 4.06 Knowledge of the requirements of the load follow pro-cedure l l .
, ! .
. Senior Reactor Operator Candidates Question No.
5.03b The effects of changes in moderator density on the magnitude of MTC for various boron concentrations 5.05b How an actual stuck rod on a Reactor Trip affects calculated SDM 5.06d How different placements of the source relative to fixed detector locations.affects an initial fuel load 1/M plot 6.07c Pow the SR NI's are affected when P-10 is satisfied j
6.09a The reasons for a low-low S/G level reactor trip { 7.03b Knowledge of the requirements of the load follow pro-cedure 7.05c Knowledge of the applicable cooldown rate during emergency depressurization of the steam generators during ECA-0.0 7.08 Knowledge of major RCS precautions and limitations
7.09 Automatic actions that occur on a loss of 125V DC j switchboards 7.10 Knowledg,e of transient and accident analysis for a major secondary steam system rupture 8.01 Requirements for facility staffing per Technical Specifications ! 8.06a Use of Technical Specifications associated with con-tainment integrity 8.08 Logkeeping and tagging requirements for -defeating RMS interlocks , l Four of the five candidates who were licensed as R0s on Beaver Valley Unit 1 in August 1986 were unable to pass the SRO written examination 'for Unit 2, after completion of the facility Cross Training Program, t I l , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _.
I _
I l l l J
,
2.
Summary of generic strengths and deficiencies noted from the operating examinations: i This information is being provided to document areas of weakness which -{ should aid the licensee in upgrading initial and requalification training
programs.
No reply is required.
Strength j SR0 candidates were knowledgeable of fuel building equipment and proced-ures.
l Weaknesses i a.
Some R0 And 6n0 candidates did not recognize that the minimum accept-able steam generator (S/G) level was increased when adverse contain-ment conditions existed.
b.
Most SRO candidates were unaware of the requirements of the Sustained Partial Power operations.
(2.52.4.J) c.
Some SRO candidates were not aware of the reasons for tripping the reactor at 85 psig decreasing air pressure.
I d.
Most SRO candidates did not monitor status trees when they left E-0 l and did not use the foldout pages in any of the emergency procedures.
l e.
Some SR0 candidates improperly classified a LOCA with one hundred times normal activity and extremely high containment hydrogen con-centration as a site area emergency, f.
Several SRO candidates could not list the inputs and. outputs of the uninterruptable power supply. Additionally, these candidates did not recognize a rectifier failure as a Technical Specification Limiting Condition for Operation.
I g.
Some SR0 candidates could not explain the relative sensitivities of the air ejector and steam line radiation monitors to a S/G tube rupture.
h.
Several SRO candidates were reluctant to deenergize an emergency bus due to a fire.
This situation was exacerbated since procedures do not exist for it.
.
' ,
3.
Summary of plant deficiencies.
Three fire doors (T30-6, T30-8 and C35-4) were found open with no. fire watch being posted.
There were air hoses passing through each of the three doors and only two of the hoses were guarded.
4.
Personnel Present at Exit. Interview: NRC Personnel l ' G. S. Barber, Reactor Engineer (Examiner) B. S. Norris, Reactor Engineer , ' D. M. Silk, Reactor Engineer J. E. Beall, Senior Resident Inspector S. M. Pindale, Resident Inspector K. L. Parkinson, Sonalyst, Examiner G. D. Weale, Sonalyst, Examiner Facility Personnel W. 5. Lacey, Plant Manager, BV1 and BV2 T. P. Noonan, Assistant Plant Manager A. J. Morabito, Manager, Nuclear Training T. W. Burns, Director, Operations Training T. E. Kuhar, Nuclear Operations Instructor l R. J. Brooks, Nuclear Operations Instructor F. J. Lipchick, Senior Licensing Supervisor 5.
Summary of NRC comments made at exit interview: The chief examiner reviewed the number and type of examinations conducted over the previous week and presented generic weaknesses observed during the oral examinations.
A discussion was conducted regarding the appropriate knowledge level of normal and abnormal procedures. The facility had stated orally and in the Operator Written Examination Comments, dated May 22, 1987, that operators l are not required to reproduce actions required in normal or abnormal pro-cedures from memory. However, the facility stated that if a given opera-tor is familiar with the procedure, he may, at his discretion, per. form the actions without reference to the procedure.
In addition, the facility requires only immediate action steps required by Operating Manual Chapter 48 to be reproduced from memory.
l I _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _
p i a i - y 7~ l I i
- -)
- The NRC had questioned the candidates on the requirements regarding the:
' use of normal and abnormal operating procedures. Some-stated the facility
position as outlined above. However, many stated that they' should know k the -immediate actions from abnormal procedures from memory.
It.is clear _ that the candidates are not aware of' the ? acility requirements on proced- . f .ure usage.
The facility' stated that they train their operators on:the content,' inter-pretation and proper use of procedures. This statement is not - supported by the examination results. The overall - average of. candidates' scores on { . Sections 4 and 7 of ' the ' written examinations. was approximately. 9% below j 'the. other sections, indicating a. generic weakness in these areas.
In ' fact,. candidates performed' poorly-on' most of the questions. that specif-ically asked about the' content of. normal and abnormal procedures.
NUREG-1021, " Operating Licensing Examiner Standards" Chapter ES-202 and j ES-402 state that each candidate must: demonstrate complete knowledge - and W understanding of symptoms, automatic actions and immediate ' action steps specified'in abnormal. and emergency procedures. Additionally, candidates should be. able - to explain reasons, cautions and - limitations of normal operating procedures.
The. NRC. will continue to ask questions :in - these areas on future R0. and SRO. examinations.. Questions in these areas will consider -the knowledge and ability. rating of each question 'in accordance with NUREG-1122, '" Knowledge and Abilities Catalog for Nuclear Power ~ Plant
Operators" and will consider explicit facility enabling-objectives.
6.
Examination Review: A review of the written examination was conducted immediately following the examination.
Facility comments were discussed on a line item basis, i A number of comments were resolved during the examination review.
The ^ unresolved comments are' listed in Attachment 3 and. Attachment 4 which detail the significant changes' to the examination.
Attachments: 1.
Written Examination and Answer Key (RO) 2.
Written Examination and Answer Key (SRO) 3.
Facility Comments on Written Examinations made after Examination Review 4.
NRC Resolution of Facility Comments ' t k ! .
--__ _- krrnchmenf / . , U.
S.
NUCLEAR REGULATORY COMMISSION < REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _pEAyER_yALLEY_2_________ l l REACTOR TYPE: _PWR-WEC3________________ DATE ADMINISTERED: _87/9pfl9________________ ' l EXAMINER: _ SILK1_9.________________ j CANDIDATE: __ .#J[rg__.__h_)(;e!(_______ INSTRUCTIONS TO CANDIDATE: i l Use separate paper for the answers.
Write answers on one side only.
j Staple question sheet on top of the answer sheets.
Points for each l question are indicated in parentheses after the question.
The passing l grade requires at least 70% in each category and a final grade of at ] least 80%. Examination papers will be picked up six (6) hours after the examination starts.
! l l
% OF CATEGORY % OF CANDIDATE'S CATEGORY .._V_A_LUE-- _ T_ O_ T A_ L__ - _ S_ C_ O_ R_ E_ _ _ _ _V_A_L_U_E____ _ _ _ _ _ _ _ _ _ _ _ _ _ C_ A_ T_ E_ G_ O_ R_ Y_ _ _ _ _ _ _ - 1.
PRINCIPLES OF NUCLEAR POWER _29399__ _29199 PLANT OPERATION, THERMODYNAMICS, ________ _ _ _ _ _ _ _ _ _ _ _, HEAT TRANSFER AND FLUID FLOW _.25399__ _29 99 ________ 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS ___________ ek V.50 3.
INSTRUMENTS AND CONTROLS S M.-_ _2?i99 l _ _. _ _ _. _ _ _ __..________ A y. 50 4.
PROCEDURES - NORMAL. ABNORMAL, i _ ?@r9M. _ _2?.09 ' ________ EMERGENCY AND RADIOLOGICAL ___________ CONTROL 199199_._ ________% Totals _____ _____ Final Grade All work-done on this examination is my own.
I have neither given nor received aid.
____-___________..____________
Candidate's Signature
s J
_ _ - -_ _ _ __ @ 1., ' PRINCIPLES OF NUCLEAR POWER' PLANT OPERATION PAGE
2 IUEggggyN9dlCS _bE91_Ig8NSEE6_9Np_E(UJp_{6gW 3 L,
.
QUESTION 1.01 (2.00) j c a.
The plant is operating at 85% power with all systems in automatic.
ic The operator inadver tent l y aligns charging pump suction to the RWST.
l
How is shutdown margin affected by this action? Briefly explain C1.4] why, b.
If a control rod was stuck completely out of the core on a reactor trip, how, if at all, would the calculated SDM differ from the case CO.6] shcae 90 rods are inserted? No explanation is necessary.
l }T QUESTION 1.02 (2.25) l Ii A centrifugal charging pump is running with the discharge flow control fa valve in mid position.
Indicate how (Increase, Decrease, or Remain the fs Same) each parameter will shift if the discharge valve is fully opened.
a a.
Discharge flow b.
Pump discharge pressure upstream of the discharge valve l l c.
Motor amps d.
Available NPSH to pump ,b e.
Seal injection flow (Assume seal injection flow control valve l is in manual) QUESTION 1.03 (2.00) BT The following statements concern fission product poisons.
Complete the statements with the values given in the list at the right.
Place answers rh on your answer sheet.
Answers may be used more than once.
a tu a.
It takes about _____ hours to reach maximum xenon 1) O concentration after a reactor trip from 100% power.
2) 5 3) 10 b.
The decay half-life of xenon 135 to cesium 135 is 4) 20 5) 50 ST appr ox i ma t el y _ _ _ _ _., hours.
i c.
It takes about _____ hours to reach equilibrium xenon av concentration after a step increase from 0% to 50% power.
Jo - d.
The decay half-life of Promethium 149 to Samari um 149 is approx i mat el y _____ hours.
(***** CATEGORY 01 CONTINUED ON NEXT PAGE
- )
- - - - - - - - - - - - -. - - - _ - - _a
- _ _ - _ _ - _ _ _ _ _ - _ _ _ __ PAGE
l 1 __EBJNCJELEg_OE_ NUCLE 96_EgWES_[LgNI_gfESSI]QN 1 IdEggggYNgD]gS _bs9I,;IB9Ng[gg_gNp_[LUlp_[LgW '.
. QUESTION 1.04 (2.25) .] How do each of the following parameters change (Increase, Decrease, or No change) if one main steam isolation valve closes with the plant at i l 25% load.
Assume all controls are in automatic and that no trip occurs.
i a.
Affected loop steam generator level (initial change only) b.
Affected loop cold leg temperature l c.
Unaffected loop steam generator level (initial change only) d.
Unaffected loop steam generator pressure e.
Unaffected loop cold leg temperature QUESTION 1.05 (2.20) i Unit I has just restarted following a refueling outage while Unit 2 is near EOL.
Answer the following regarding the differences in plant f response between the two units.
Explain your answers.
f i ) a.
At a steady power level of 10EE(-8) amps during a startup, equal j reactivity additions are made (approximately 100 pcm).
Which Unit will have the LOWER steady state startup rate? (1.0) b.
At 50% power, a control rod (100 pcm) drops.
Assuming NO RUNBACK or OPERATOR ACTION, which Unit will have the HIGHER steady state Tavg? , (1.2) i QUESTION 1.06 (2.00) The reactor is at 70% power and Tave is 568 F.
A governor valve failure raises load 15%. Using Figure 1, calculate the new Tave if r'e d s are in automatic.
Show all work and state all assumptions.
QUESTION 1.07 (2.40) List the four factors that cause the Doppler Power Coefficient to change over core life and indicate whether each of these factors make the Doppler Power Coefficient more or less negative.
1 l l (***** CATEGORY 01 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ ._ _ _. - _ _ _ - _ _ -
_ - _ _ _ _ - PAGE
lt__[glygl[(gg_QE_Ugg(g@g_EQMgB_f(@@T_QEE6@llg@t T_H_E_R_M_O_D_Y_N_A_M__IC_S__,_H_E_A_T__T_R_ A_N_S_F_E_R_ _A_N_ D_ _F_L_U_ _I D_ _F_L_O_W_ , . QUESTION 1.08 (2.00) How does each of the following parameter changes affect the DNBR (Increase, Decrease or Remain the Same)? Briefly explain your answers.
a.
Pressurizer Temperature Increases 5 degrees b.
Mass flow rate in the core increases 10% c.
AFD increases to +10% QUESTION 1.09 (2.40) l a.
Of the coefficients that contribute to the power defect, which' coefficient contributes, most to the change of power defect over l core life? What causes the change in the coefficient you chose? b.
Of the coefficients that contribute to power defect. which coefficient acts first to affect reactivity on a sudden power change due to rod movement? Explain why the coefficient you chose j reacts before the others.
i QUESTION 1.10 (2.50) l ' a.
Describe how and why core Delta T will respond to a loss of natural circulation flow (caused by the steam dump valves failing closed) l f oll owing a reactor trip from 100% power.
(0.75) b.
Describe how and why the relationship between Tcold wide range and steam generator pressure will respond to a loss of natural circulat-ion flow (caused by s loss of feed flow) following a reactor trip from 100% power? (0.75) c.
How would the operator change the following parameters (Increase, l ' l Decrease, or No Change) in order to aid or maintain natural circulat-ion.
Consider each separately.
(1.0) l 1.
Pressurizer level at 5% 2.
RCS cooldown rate at 35 F/hr l 3.
Steam generator level at 30% WR 4.
RCS pressure at 1900 psig (***** CATEGORY 01 CONTINUED ON NEXT PAGE
- )
_ -_._ -______ _
_ _ _ _ _ _ _ _ ' PAGE
- 1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, 1UESO99YN901Cg1_bE91_IggN@[E6_9ND- [LU]p_[LOh' , , . l QUESTION 1.11 (3.00) t Consider the following plant conditions: MODE 3.
BOL Boron concentration is 900 ppm All shutdown banks withdrawn ~ l Actual reactivity present in the core is minus 4% delta-K/K Source range indication of 100 CPS-Differential boron worth is 10 pcm/ ppm l A boron dilution to 750 ppm increases the source range indication to l 132 CPS.
Dur i ng. true di l ut i on, Xenon concentration has changed.
What was Xenon's reactivity contribution during this time? l i l l i
l (***** END OF CAfEGORY 01 $$***)
!
' PAGE
2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS . . QUESTION 2.01 (2.50) Answer the following questions regarding the Gaseous Waste Disposal System.
Explain the effect, if any, that the inoperability of the heat trac-a.
ing up stream of the air ejector vent charcoal. delay beds would have on offsite doses in the event of a steam generator tube rupture?(0.9)
b.
What are four valve failures that would cause the rupture disc to rupture on the surge tank (2GWS-TK21).
Assume a Unit 2 waste storage g tank is in the process of being filled and that there are no cross- ' connections between the Unit I and Unit 2 gaseous waste systems.(1.6) QUESTION 2.02 (2.00) a.
When automatically actuated, the B Chemical Injection Pump fails.to start and the Quench Spray Chemical Addition Tank Discharge Valve to the A Chemical Injection Pump fails to open.
Explain how, if poss-ible, NaOH can be injected to containment vi a quench spray? l b.
Besides through the containment spray headers, how can NaOH be intro-duced to containment and under what circumstances will it occur?
QUESTION 2.03 (2.50) a.
The MSIV's are closed on a main steam line break to isolate the break and prevent blow down of the other steam generators through the break.
List two additional reasons for closing the MSIV's on a steam Itne(1.5) rupture.
b.
Which mode (HSB, HZP, HFP) and which time in cycle (BOL, MOL, EOL) will cause a main steam line break accident to be most severe.
(1.0) Explain each separately.
(***** CATEGORY O2 CONTINUED ON NEXT PAGE
- )
i i - - _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - -
PAGE 7-2.__PL@NI_DEg1GN_1NCLUDING_gg[Ely_ gyp _EdEggENCy_gy@lEgg . i QUESTION 2.04 (2.00) The plant is at 100% power when a seismic event causes a small break LOCA and ruptures one of the auxiliary feedwater headers.
Offsite power is lost.
Train A Si actuates but Train B fails.
Answer the following questions assuming no operator action is taken and that all other systems, components and controls are not affected by the seismic event.
l a.
Explain how flow'from the turbine driven AFW pump may not be feeding (0.5) the steam generators.
b.
With the Train B SI failing to actuate, what signals generated dur-ing the transient would cause the 8 Motor Driven AFW pump to auto-matically start? Assume the turbine driven AFW pump is not operat-
( 1. 5) ing.
QUESTION 2.05 (2.00) a.
How would personnel in containment be warned that the incore movable (0.5) detectors at e in operation? b.
Besides alarms, what symptom may be encountered while performing a flux map that wouid be indicative of a leaking incore thimble guide (0.'5) tube? c.
After identifying a leaking thimble guide tube. how would it be (1.0) isolated? QUESTION 2.06 (4.00) While at 100% power a double ended shear occurs on the Loop C Hot Leq.
a.
What eight automatic system alignment changes (valve and pump oper-ations) occur when ECCS changes from the injection phase to the re-(3.0) circulation phase? b.
When it is time to go to hot leg recirculation, explain why the failure of a single section of piping could eliminate all flow to (1.0) the core from the low pressure pumps.
, (***** CATEGORY O2 CONTINUED ON NEXT PAGE
- )
_ _ _ _ _ - _ - _. - _ _ _,
1
PAGE 8 j t__PL901,gESl@y_[ygLUQlg@_@@[Ely_@yp_EMEgggggy_gy@ TEM @
C . A QUESTION 2.07 (2.00) a.
What are two sources of Borated water available for the Spent (0.9) Fuel Pool? b.
What design feature of the spent fuel racks ensure criticality does (0.5) not occur in the Spent Fuel Pool? c.
What two design features prevent draining of the Spent Fuel Pool below the top of'the fuel stored in the spent fuel racks? (0.6) ! QUESTION 2.08 (2.50) a.
What are three reasons for having Rod Insertion Limits? (0.75) b.
The 'A' reactor trip breaker is opened for RPS testing during Mode 1.
If the 'B' bypass breaker is closed prior to resetting the 'A' reactor (1.0) trip breaker, what actions will occur? c.
How does an URGENT alarm affect the lift, stationary, and movable(0.75) gripper coils? l l I QUESTION 2.09 (3.00)
a.
The seal water heat exchanger cools fluid from what three sources? b.
What are two specific instances when the operator may initiate flow through the RHR Heat Exchanger Outlet Flow Control Valve, 2CHS*HCV-142? c.
Explain the effect, if any, on Seal flow if the Seal Water Return isolation Valves close? l l (***** CATEGORY O2 CONTINUED ON NFXT PAGE
- )
PAGE-
2.__PL9NI_DggjgS_JNgLUp]Ng_g@ggIX_9dP_ggggggNgX_@X91ggy . . QUESTION 2.10 (2.50) IF the Component Cooling Water Pump Discharge Pressure Control Valve' Con-troller setpoint is significantly decreased, indicate how the'following parameters or valve positions will change (Increase, Decrease, Open, Close, or Remain the same).
a.
Thermal barrier flow b.
Neutron shield tank temperature c.
TCV-2CC-LOO, CCW Hx Bypass Valve d.
Surge tank level e.
PCV-2CH-145, Low Pressure Letdown Valve , l l l ! ( (***** END OF CATEGORY O2
- )
.. l
PAGE 10 1 . 3_ _.. _ _I N_S_ T_ R_U_ M_ E_ N_ T_S_ A_N_ D_ _C_O_N_ T_R_ O_ L_S_ . . QUESTION 3.01 (2.40) With the plant at 75% power and all control systems are in automatic, ex-plain'the plant response to the VCT level control channel failing low.
Continue your explanation until stable conditions are reached or until
" a reactor trip occurs.
If the reactor will eventually trip, state the the cause of the trip.
Assume no operator action is taken.
QUESTION 3.02 (2.50) a. For EACH of the following two cases, state YES or NO as to whether the reactor will trip in response to a simultaneous failure low of both l Intermediate Range channels. Justify each answer.
1) Reactor startup in progress and at 5% power (0.75) ! (0.75) < 2) The reactor is at 20% steady state power b. Assume the reactor is at 100% power when one Intermediate Range channel ' fails high, followed immediately by a reactor trip (from other causes).
What additional action Will have to be taken during emergency proced-ures to ensure proper operation of the Nuclear Instrumentation System? j l (1.0) I )
QUESTION 3,03 (2.50) What automatic actions, if any, are associated with the following radiat-ion monitors when their setpoint is reached.
Do not include annunciator alarms.
a.
2CCP-RQ1100 CCW l b.
2RMS-RQ13Ol Leak collection ventilation i c.
2RMC-RQ2Ol Control room area l d.
2RMS-ROI303 Containment airborne l e.
2 ARC-ROlOO Air ejector discharge l (***** CATEGORY 03 CONTINUED ON NEXT PAGE
- )
- - - - _ _- _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ -
-_ __
. PAGE
3:_ _ IggTSUgEglg _@yg _C,gyIgggg , . QUESTION '3.04 (2.75) a. Indicate whether the following. situations will ARM ONLY, ARM AND ACTUATE (1.0) or HAVE NO EFFECT on the steam dump system.
1.
50% power, 18% step load increase, Tavg is 6F less than Tref, steam dumps are in the Tavg mode of operation 2.
80% power, 7. 5'/./ mi n ramp decrease in turbine load for 10 minutes, Tavg is 7 F greater than Tref, steam dumps are in the Tavg mode of operation 3.
Hot Zero Power, Tavg=549 F, steam dumps are in the STM PRESS mode i ' with 985 psig set into the steam pressure controller 4.
Reactor trip, Tavg=549 degrees, steam dumps in Tavg mode ! b.
What three condi.tions would cause the first and second bank of dump valves to be blacked while in the STEAM PRESSURE mode? (1.0) ' c.
While at 100% pawer the turbine first stage. pressure channel 447A fails low.
Five minutes later the loop 3 RTD That fai.ls high.
What actions,
if any, need t o be taken to prevent the steam dump valves from opening? (0.75) i QUESTION 3.05 (2.25) a.
The Start Mode Selector Switch at the Diesel Generator Local Panel is in the LOCAL position and the diesel is running.
What trips, if any, are presently defeated? b.
When, if at all, are the emergency bus undervoltage schemes locked out? c.
What pumps, if any, are not automatically energized by the diesel generators in the event of a engineered safety features system act-f uation si gnal ? l l r ] (***** CATEGORY 03 CONTINUED ON NEXT PAGE
- )
_ _ - _ _ _ _ - _ _ _ _. _ __
- PAGE
. 3.
INSTRUMENTS AND CONTROLS
-------
. l = QUESTION 3.10 (2.50) Answer the following questions TRUE or FALSE a. Automatic initiation of SI is blocked when the reactor trip breakers are open with the SI signal reset.
b. The low steamline pressure SI signal may be reset if both the hot and cold loop stop valves in the associated primary loop are shut.
the low pressurizer pressure SI and MSLI. signal is blocked, '3)gggj () When the MSLI signal on steamline pressure rate decrease is enabled.
l d. 2/3 pressurizer pressure channels above 2000 psig defeats manual blocks on the SI signal (P-11 blocked).
l e.
If an Si signal causes a reactor trip the SI signal may be reset within 10 seconds if the reactor trip breakers are closed immediately.
l l l I l l l l l l (***** END OF CATEGORY 03 *****/
PAGE 14-Si__P60gggUSEQ_ _UgSO@(u_@@ygggg(t_ggggggggy_ANg _ 609196991G06_G9NI6g6 . . l l QUESTION 4.01 (2.50) a.
How frequently is the flow rate of liquid radioactive waste recorded (0.5) during a release? b.
An approved RWDA-L for a release is signed on 5/4/87 at 0830.
Due to various delays, a discharge can not be i ni ti ated until 5/7/87 at 1230.
Explain what action, if any, should be taken to begin the release? I (1.0)
c.
As soon as a liquid radioactive discharge through the cooling tower blow down is secured, the dilution flow is secured? Explain whether
or not this is permissible? (1,0) l l l l OUESTION 4.02 (2.00) Answer the following questions regarding AOP 2.6.1, Malfunction of Press-urizer pressure control.
Consider each separately.
a.
Pressurizer pressure is rapidly increasing to the PORV lift setpoint.
Is it permissible to open two PORV Isolation Valves to ensure that a PORV is available to reduce pressure? (0.4) l b.
What will give the following simultaneous symptoms? (0.6) Increasing pressurizer level Decreasing pressurizer pressure c.
One pressurizer pressure protection channel fails high.
Five minutes l later a second pressure protection channel fails low.
What action, ' if any, should be taken? (1.0)
1 . l l (***** CATEGORY 04 CONTINUED ON NEXT PAGE
- )
. 4.__PRgCEDURES_ _NgRMAL, _ABNgRMAL, _ EMERGENCY _AND PAGE
" 509196991C06_C9Nlgg( -. . QUESTION 4.03 (3.00) Answer the following questions concerning E-0 Reactor Trip or l Safety Injection.
a.
List three actions, in order, that may be taken if the turbine , (1.5) I is NOT tripped.
! b.
List two of the three conditions that would require steamline (1.0) isolation. (SLI) c.
What specific operator action is necessary after the RSS pumps (0.5) start? DUESTION 4.04 (2.50) Answer the following questions concerning RCS precautions and limitations.
a.
What is the maximum allowable RCS temperature and pressure with RHR in service? (1.0) b. What action should be taken if RCP vibration reaches 20 mils.
(0.5) c.
List two reasons for maintaining a nitrogen overpressure of 0.5 to 3.0 psig on the PRT.
(1.0) QUESTION 4.05 (.50) l When, if at all, can a faulted steam generator that is isolated be un-isolated? l l (***** CATEGORY 04 CONTINUED ON NEXT PAGE
- )
I ~3 __PgggggUggg_ _NggD9b2_gpNgBD961_EDE6ggdgy_9Ng PAGE; 16' BegIgggg]C86_C9NIS96 .. . QUESTION 4.06 (3.00) Answer.the following questions concerning General Operating. Instructions, .; OM S2.
' a.
What are the requirements in this.OM regarding the. completion of.
, procedure steps in. sequence.
, ' .i b.
What is the maximuni allowable value of Tave-Tref mismatch and turbine loading rate permissible during load follow operations, c.
During load follow operations, what must be done if thermal power changes 15% in one hour or less.
g QUESTION 4.07 (.50) When, if,at all, is it permissible to est'ablish f eed flow to a ruptured-steam generator that is also f aulted? QUESTION 4.08 (.75) a What three criteria are used to verify that. adverse containment.condit- , ions exists?
.i QUESTION 4.09 (1.00) i Answer the following questions regarding the E-O f old-out page.
a.
What conditions require tripping all the RCP's?- b.
What conditions require actuating SI? (***** CATEGORY 04 CONTINUED ON NEXT PAGE
- )
l l
- .' PAGE
SL__Pgggqqyggg_ _GQSQ@(t_@@yggd@6t_gdggggggy_AND 869[9h99[EOh_E99199h
QUESTION 4.10 (2.50) Answer the following questions concerning Radiological Con trol s.
a. What is the maximum allowable quarterly WB dose that a newly hired (0.5) 18 year old operator may recieve.
b. Under what circumstances, if any, would it be permissible for a worker to recieve an acute dose of 50 rem.
(1.0) c. What is an NRC Form-4 and how does it affect an individual's maximum allowable dose rate?~ Be specific.
(1.0) l QUESTION 4.
(1.25) Answer the following questions regarding the Red Path Summary on the Fold-out pages.
l ' a.
What are the Red Path criteria for Core Cooling? (0.75) b.
What are the Red Path criteria for Integrity? (0.5) l . QUESTION 4.12 (.50) Given the following information: identified Leakage Controlled Leakage I = C = Pressure Boundary Leakage U = Unidentified Leakage P = S = Steam Generator Leakage Which, if any, of the following is TRUE? i A.
I =C + P P B.
U = I + C C.
U = S D.
I = E.
I =C + S
i I { i ! \\ (***** CATEGORY 04 CONTINUED ON NEXT PAGE
- )
_ _ _ - _ _
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ __ _-_ PAGE
3:__P60ggDUSg@_ _N9BD962_9@N96d961_EdgB9ENgy_@ND RADIOLO.GICAL CONTROL
, . ! QUESTION 4.13 (1.00) a.
Which of the following describes a temporary change which alters the INTENT of a procedure? A.
A change that corrects an incorrect valve lineup.
B.
A change that modifies the criteria by which a system's . l operability is determined.
l , l C.
A change that allows partial use of a procedure to test a I l subtrain without affecting remaining equipment in that train.
D.
A change that allows you to change incorrectly specified instruments for data taking.
l)6g[o (.) What is the maximum period of time for which a Temporary Operating Procedure can be used? i I l A.
7 Days B.
14 Days C.
30 Days D.
90 Days QUESTION 4.14 (1.50) Answer the following questions TRUE or FALSE regarding control room area rules.
a.
The Control Room shall be maintained clean, orderly, and free of unauthorized material on control boards and panel s.
b. The oncoming RO may silence control board al arms if the offgoing RO is busy with a difficult evolution.
c. Storage of combustible l i qui ds in the control room is only permitted if the area is properly posted and roped off.
l (***** CATEGORY 04 CONTINUED ON NEXT PAGE
- )
' PAGE
S:__PBggggUSgS_;_NgBD961,@gNggggby,gDggggNgy_gNg S9919699199L_CgNJgg( - . i l GUESTION 4.15 (.50) Match the class of fires listed below (A - D) with the materials , involved (1 - 4).
CLASS OF FIRE MATERIALS INVOLVED 1.
flammable liquids, gases, or ______A.
Alpha greases j i I -- ---B.
Bravo 2.
combustible metals ______C.
Charlie 3.
ordinary combustibles (paper, wood, etc.)
______D.
Delta 4.
energized electrical equipment
I l l l ' l
QUESTION 4.16 (2.00) Answer the following question in accordance with AOP 2.6.2, Excessive Pri-l mary Plant Leakage.
Match the TYPE of LEAK with the PARAMETER or METHOD used to detect the l l type of leakage.
Multiple responses may be required, i PARAMETER or METHOD TYPE of LEAK 1.
Air Particulate Monitor a.
FW or Steam leak l 2.
CNMT Humidity b.
Aux Cooling Water Leak j 3.
CNMT Sump Flow Rate c.
CCP Leak l 4.
CNMT Sump Chemistry Analysis d.
RCS Leak , S.
RCS Inventory Balance l
!
l
] i , l l l l f (***** END OF CATEGORY 04
- )
(************* END OF EXAMINATION
- )
l l l !
.g ...
1 ,. i e- . j . .l
. e l
-l J q j i ( . , . ,I I i I
- 170 - - l i , n.
i ' H \\ ~ W 'l i3 - l i l ~ ! o . I i , l t I i ' O .
~} Pt b -- i i i ee r l
't H ! . >
T59 - y . I ! l I I -, - , i ' ' '
! . cr { i i j i l-i '
o $ SEC -
~
g i j , ' , i-w
. i a: .
i , n.
!
i ! t . i , I
7B5 - l ' t } { ' ' < . l .l
, , wr
i , , - , m O
20
40
60
80
(00 NSSS POWER - % RATED POWER ,
- _ - _ - _ - _ - _ _ _ _ PAGE 2.0 li__C61dElEhEE_9E_d9Eh568 89 DES _ChOdl_9CE86119dt IUEgdgD yg@01C@ t _dE@l_166NSEE6_@@D _F Ly [D _ELQU ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
- ANSWER 1.01 (2.00)
a. It increases (0.6) since RCS Cb concentration is increased (0.8) l
b. No change (actual 3 tuck rod worth is added to the TS limit) (0.6) REFERENCE BV2 LP-RT-9 pg 4,6,7 EO 2,5 001/010 K5.35 3.3/3.6 004/000 K5.19 3.5/3.9 OO4000K519 OO1010K535 ...(KA'S) ANSWER 1.02 (2.25) a.
Increase b.
Decrease c.
Increase d.
Decrease e.
Decrease (0.45 pts each) REFERENCE BVPS Thermo Manual Chapter 4, pgs 21,32c,33 Components 191004 Pumps 1.05 2.3 1.06 3.2 1.07 2.9 LP-TMO-4 EO-8,14 191004K107 191004K106 191004K105 ...(KA'S) ANSWER 1.03 (2.00) a.
b.
c.
d.
(0.5 pts each) REFERENCE BVPS Rx Th Chapter 7, pqs 2-16,20 EO-2,8 3.1 001 000 K 5.13 I 1.__E6[GC[E6E@_QE_yggLE@@_@QH@@_E(@Ml_QCE6@llgyt PAGE.2l ISEGyggY@@d[gSt_dE@I_IB@NSEE6_@NQ,ELylg_ELQW q ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
- y
001000K513 ...(KA'S) f ANSWER 1.04 (2.25)
a.
Decrease j b.
Increase .j c.
Increase j d.
Decrease j e.
Decrease (0.45 pts each) REFERENCE BVPS Thermo Manual, chapter 7, pgs 26-27 chapter 6, pg 37 3.2 002 000 K 5.01 3.1 5.09 3.7 5.11 4.0 LP-TMO-7 EO-18 002000K511 002000K509 002000K501 ...(KA'S) f I l
ANSWER 1.05 (2.20) a a.
Unit 1 (0,5) due to a higher Beta coefficient at BOL (0.5) b.
Unit 2 (0.5) due to MTC being more negative, so Tavg will decrease less to add same positive reactivity (0.5) REFERENCE ! BVPS Rx Th Chapter 5, pgs 17-23, EO-3,4 Chapter 6, pgs 16-18, EO-11 l t' 3.1 001 000 K 5.47 2.9 K 5.49 3.4 00lOOOK549 OO1000K547 ...(KA'S) l l ! l l u i . 'l l \\
1:__E01993EbEE_9E_U9EbE90_E9dE0_Eb691 9EE0011991 PAGE 22 ] IDEgggpYN99]QS _UggI_I699pFg6_90D_E6Ulp_[ggy
. ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
I i I ANSWER 1.06 (2.00) a.
O=UA (Tave - Tstm) (0.2) ! l 70% = U A (568 - 521.3) and 85% = U A (Tave - 518.7) (0.2) ) ' 85% / (Tave - 518.7) (0.4) l 70% / (568 - 521.3) = UA = l (521.3 and 518.7 are from the steam tables for their corresponding j ' pressures in Figure 3) (0.6) j { Solve for Tave: Tave = 575.4 F (0.6) l REFERENCE BVPS Thermo Manual Chapter 7, pgs.
1-4 3.5 039 000 K 5.08 3.6 ) A 2.05 3.3 l '
1 LP-TMO-3 EO-7 039000K508 039000A205 ...(KA'S) I ^ l ANSWER 1.07 (2.40) 1.
Pu-240 buildup--More Negative 2.
Acc u.nul at i on of Fission Product gases--bess Negative i 3.
Fuel Densification--Les$ Negative l y
- '
4.
Clad Creep--done Negative (0.3 pts for each response) l Le o i REFERENCE BVPS Rx Th Chapter 6, pgs 40-43: EO-5 3.1 001 000 K 5.49 3.4 OOlOOOK549 ...(KA'S) ' - - - _ _. __- - - - - _ _ _ - -
I I .1_ - _ESlNC [[LES _OE _NU,C(E @@ _EQW E6_[(@N I _OEE S@l[ON PAGE 23 t THER.MODYNAMICS, HEAT TRANSFER AND FLUID FLOW , --- -- --_---
-
ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
- ANSWER 1.08 (2.00)
a.
Increases (0.2).
As PZR temp rises, so does Pressure, hence the
margin to saturation increases (0.46).
) b.
Increases (0.2).
The Delta i across the core will be lower to pro-l duce the same power, so Th will decrease and the margin to saturation l increases (0.46).
i
c.
Decreases (0.2).
Since more power is being produced in the top half l of the core and since head loss increases with core height the margin to saturation decreases (0.46).
! l l l ' REFERENCE J ' BVPS Thermo Manual Chapter 7, ogs 17,18 ! 3.4 003 000 K 5.01 3.1 j i
LP-TMO-7 EO-11 OO3OOOK501 ...(KA'S) I q l ANSWER 1.09 (2.40) a.
Moderator Temperature Coefficient (MTC) (0.6) due to an increase (more negative) in MTC as baron concentration is reduced over core life (0.6).
b.
Doppler (FTC) (0.6).
Fuel temperature changes before the other l parameters change (0.6).
REFERENCE BVPS Rx Th Chapter 6, pgs 45-53; EO-10,11 3.1 001 000 k 5.49 3.4 OO1000K549 ...(KA'S) l l l _ _ _ _ _ - _ _ - _ _ _ - _ _ _ _ _ _ -
, ( lt__E81dE1EhEE_9E_UWEhEOO_C9dEO_EbOdl 9EE001190L PAGE Z,Lp j ISESOQQYU@digSt_SE@l_lB@dSEEg_@dQ_E(y[Q_E(QB ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
- i ANSWER 1.10 (2.50)
a.
Delta T increases (.25) as That increases (as boiling occurs in core) and Tcold remains relatively constant (0.5) b.
Tcold will not follow Psteam (.25).
Psteam will decrease (as boiloff occurs in S/G) while Tcold remains relatively constant (0.5) c.
1.
Increase l 2.
Decrease ! 3.
Increase 4.
No Change (0.25 pts each) REFERENCE j BVPS Thermo Manual Chapter 7, pgs 7,23,25,26
l 3.4 000 015 EK 1.01 4.4 LP-TMO-7 EO-16 q OOOO15K101 ...(KA'S) j l l ANSWER 1.lt (3.00) l 0.9615 (0.5) 1/((1-(-0.04)) Keffi = = 132(1 - Keff2) Keff2 = 0.9709 (0.5) 100(1 -.9615) = , -0.03 (0.5) (0.9709 -1)/O.9709 rho 2 = = 1000 pcm (0.5) 0.01-0.03 -(-0.04) rho 2 - rhol del ta rho = = = = 1500 pcm (0.5) 150 ppm x 10 pcm/ ppm Boron delta rho = = -500 pcm (0.5) IOOOpcm - 1500 pcm Xenon delta rho = = REFERENCE Rx Th Ch 4 pg.
EO-7 Ch 6 pgs. 45, 47 EO-13 3.1 001 000 K 5.28 3.8 l OO1000K528 ...(KA'S)
- 2 __PL@dI_QE@[QU_{MGLyg[Ng_S@FEIY_@@Q_EUERQENg1_@YSIEd@ PAGE 25 j t ANSWERS -- BEAVER VALLEY.2-87/05/19-SILK, D.
+ ,
ANSWER 2.01 (2.50) j ! a.
Without the heat tracers dehumidifying the gas stream, the charcoal i filters become less efficient (0.4) and thus offsite doses would be l higher than if the heat tracers were operable (0.5) ] b.
Surge tank pressure control valve closes (2GWS-PCV116) Gaseous waste storage tank inlet valve closes (2GWS-AOV108) l Gaseous waste storage tank inlet heaoer isolation valve closes l (2GWS-AOV104) j Gaseous waste storage tank inlet isolation valve closes..(2GWS-SOV125) ) (0.4 pts each) j I REFERENCE I BVPS OM 2.19.1 pgs 12,
2.19.4 AAB pg 1 of 4 l l i 3.11 071 000 K 4.04 3.4 K 4.05 3.0 l 2LP-SOS-19.1 EO 2,
l 071000K405 071000K404 ...(KA*S) l
l l l ANSWER 2.02 (2.00) i a.
NaOH can be injected (0.5) because the chemical injection pumps suctions have cross-connect lines (0.5) b.
Chemical injection pump discharge valve to containment sump will open l (0.5) during a CIB signal (0.25) with a low-low level in the RWST (0.25) i l l REFERENCE BVPS OM 2.13.1 pg 19; Figure 13-2 of system prints 3.6 026 000 K 4.02 3.6 2LP-SOS-13.1 EO-3,4,14,16 026000K402 ...(KA'S) - _ _ _ - _ _ - -
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -- - i . 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
I
ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
'
ANSWER 2.03 (2.50)
a.
1.
Minimize positive reactivity effects of RCS cooldown associated t with the' blowdown (.75) i 2.
Limit pressure rise within containment during a steam break in containment (.75) j Had b andby (0.2) because of the greatest mass in the SG results b.
in the largest RCS cooldown (0.3) l EOL (0.2) because MTC is at its maximum negative value (0.3) I i REFERENCE '
T/S B 3/4 7-3 y k 3.5 000 040 EK 3.01 4.5
i j l EK 2.01 2.5 EK 1.05 4.4 3.5 039 000 K 4.05 3.7 l 2LP-SOS-21.1 EO-4,14 2LP-ATA-4.1 pg 11, LO-4 BVPS Rx Th Chapter 6.
EO-2 OOOO40K105 . ANSWER 2.04 (2.00) a.
If the rupture occurs on the header to which the TDAFW pump is aligned, then it will not be able to feed the steam generators (0.5) l l b.
SG low-low level l Low TDAFW pump discharge pressure Both MFW pumps trip (0.5 pts each) REFERENCE BVPS OM 2.24.1 pgs 3,26.27 3.5 061 000 K 1.02 3.7 l K 2.01 2.2* l K 4.02 4.6 l - K 3.02 4.4 2LP-SOS-24.1 EO-2,3,7 l 061000K102 061000K302 061000K402 ...(KA*S) l l l l _. _ _ _ _. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- L 2;__g6@yI_pgg]@y_]Ng699]y@_p@[@Iy_@yp_gD@$ggygy_pypIgD)
PAGE-27 ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK', D.
l '. ' ' l
, ANSWER 2.05 (2.00) i , a.
Radiation W&rning System (Seven red. lights'in containment) (0.'5) , l 'b.
Dif ficult' insertion of detector (0.5) -l c.
Ensure detector is in storage position-(0.3);and manually'close the - appropriate isolation valve (0.7) REFERENCE-j .BVPS OM'2.3.1 pgs 7,8 ' 2.3.4 E 3.2 002 000 K 1.12 3.5 .I 4.05 3.8 2LP-SQS-3.1 EO-2,8,10f OO2OOOK112 OO2OOOK405 ...(KA'S)
ANSWER 2.06 (4.00) a. LHSI pump crossover isolation valves close (2 SIS *MOV 8887A, B) (0. 4 )'
RSS pump discharge to LHSI discharge header'open (2 SIS *MOV-LHSI pumps stop-(2SISP21A,B) (0.3) . 8811 A, B) (0. 4 ) LHSI pump suction valves close (2 SIS *MOV OBO9A,B) (0.4) , , RSS spray header isolation valves close (2RSS*MOV 156C,D) (0.4) l HHSI pump suction isolation valves'from LHSI pump discharge.
header open (2 SIS *MOV 863A,B)' (0.4)
HHSI pump suction valves f rom RWST close (2CHS*LCV 115B,D) (0. 4 )' l Al ternate mini f l ow i sol ati on val ves cl ose ' (2CHS*MOV380, A, B; 383A, B) (0. 3) L b.
With the loop 3 hot leg failed, a failure of the LHSI-piping to the loop 2 hot leg would eliminate the remaining flow path available,to the core from the low pressure pumps (1.0).
] ee b;hte oi PYt' M O W bc1 w n DT9.e.J ~huyl sf tis }u y 4o io (s b.nd ] } i l REFERENCE I BVPS OM 2.11.1 pgs 22,23 I 3.2 006 000 K 1.03 4.3 l K 3.01 4.2 L 3.4 000 074 EK 2.05 4.1
2LP-SQS-11.1 EO-4,5,17 OOOO74K205 OO6000K103 OO6000K301 ...(KA'S)' I
l q , - - _ - - _ _ _ _ - _ _ _. - - -. _ - - _ _ _ - - - - - - - - -. - - - - -. _ - - - - - _ - - - - - -- - - - ^ - ~ ^ ~
2.__PLegI_pggigy_1gglyp1Ng_ggFEIy_@dp_EDEB9 Edgy _@y@I@D@ PAGE
ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
, ANSWER 2.07 (2.00) a.
RWST l Boric acid tanks (0.45 pts each) I b.
The center-to-center distance ensures <.95 Keff for spent fuel (even if unborated water is used) (0. 5) or &v f(h3 in Al ruks l c.
Fuel transfer gates do not extend below the top of the spent fuel racks l All piping and piping penetrations of the SFP terminate no lower than 10 feet above the top of the active fuel stored in the racks (0.3 each) ,
l
REFERENCE l BVPS OM 2.20.1 pgs 3,4
2.20.4 L pgs 1 of 3 ! 3.11 033 000 K 4.05 3.1 l K 4.01 2.9 l K 1.05 2.7 K 1.06 2.2 , 2LP-SOS-20.1 EO-1,2 033OOOK105 033OOOK106 033OOOK401 033OOOK405 ...(KA'S)
l l l - - _ _ _ _ - _ _ _ _ _ _ _ _ _ -
2.__PLgyJ_QggJgN_JygLypJyg_S$ggly_9NQ_EDgBQEdgy_gy@IEDS PAGE
' ANSWERS -- BEAVER VALLEY 2-87/05/19-51LK, D.
, . ANSWER 2.08 (2.50) a.
To ensure adequate trip reactivity.
(minimum SDM) To limit the potential effects of rod misalignment.
d*/ NNd To assure power distribution limits are met.
(0.25 pts each) y, mtatmiH fke effe6 of an 4cchid m.l b.
Both bypass breakers will open resulting in a reactor trip (1.0) c.
De-energizes lift coils , l Energizes stationary and movable gripper coils (at reduced currents) (0.25 pts each)
l REFERENCE TS pg B 3/4 1-3 BVPS OM 2.1.1 pgs 3,49 3.1 001 000 K 1.05 4.5 K 2.02 3.6 K 4.01 3.5 K 6.03 3.7 i System generic 6 2.9 2LP-SQS-1.3 EO-5,14,17 OO1000K105 l l l l l l l l .
? 2t__PL@gI_DEgigN_lygLyDigg_g@FE11_@gD_EMERQEUgl g1gIEM@ PAGE
', ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
ANSWER 2.09 (3.00) a.
Seal water leak off Excess letdown Charging pump mini flow (0.33 pts each) b.
To purify coolant when on RHR cooling.
Provide additional letdown during heatup or bubble formation.
RCS solid plant pressure control.
(Any two, 0.5 pts each) c.
Continued flow is assured by a relief valve which directs l flow to the VCTE3nd PRT.
(1.0) REFERENCE BVPS OM 2.7.1 pgs 20,41,44,588, AB3.7 2.6.4 P pg 1 CVCS Fig 7-3 3.1 004 000 K 1.02 3.5 3.2 002 000 K 1.06 3.7 3.3 010 000 K 1.06 2.9 2LP-SOS-7.1 EO-3,5,7,8 OO2OOOK106 OO4000K102 010000K106 ...(KA*S) ANSWER 2.10 (2.50) i a.
Decrease b.
Increase c.
-Open~ C L630 d.
Remain the same e.
Remain the same (0.5 pts each) REFERENCE , l BVPS OM 2.15.1 pgs 31,32,33.35,36 3.10 008 000 K 1.02 3.3 ! l 2LP-SQS-15.1 EO-9 OOBOOOK102 ...(KA'S) l
3_.o__ld@l@U@dI@_Od9_E981696@ PAGE
ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
. ANSWER 3.01 (2.40) C ging pump suction switches to the R Incr boron concentration causes rods to withdraw Tave starts to decrE .,sc-ds are fully withdrawn l Steam header ure starts to dec Governor ves open to try to maintain lo R or will trip from low pressurizer pressure a 'nventory shrinks t' h' Quk) mt yeaQ Q1 LT. ( I 'r
NO I e) kil dwcef 'lo VCT (.2) REFERENCE 3) Afo mke af Shrds (Ld BVPS OM 2.7.1 pg 10 3; p jg gay 2.
6.1 pgs 63,64 4) * JI O '*M 3.1 001 000 K 4.03 3.5 &<se TL L T-Il L gj p g g f, g l 3.9 016 000 K 3.11 2.2 2) I f le d I i hm h o w e d W h I 5 V 2LP-SQS-1.3 EO-11 l AI ""W Cu((bu d nay vsm WT (b) l A 7.2 EO-7 ' 3) Q l y [/ k bl bMc'o 26.2 EO-7 OO1000K403 % h IMI cH rr-ide L.( <~ I re d k'i h N '0 f ANSWER 3.02 (2.50) a.
1) YES (0.25). P-6 drops out ( b ec aus'e IR < 10 E-10 amps) (.25) and SR NI reenergizes causing a level trip signal (.25)
1 2) NO (0.25). P-10 is in effect (.25) which will prevent the SR from reenergizing (.25) (even though P-6 has dropped out) b.
Manually reset SR trip / block switches for both trains to reactivate the SR high voltage and thus get Source Range indication (1.0).
REFERENCE BVPS OM 2.2.1 pgs 15-17 3.9 015 000 K1.01 4.1 K3.01 3.9 K4.01 3.1 K4.07 3.7 A2.02 3.1 ,
2LP-SQS-2.2 EO-4,11
015000A202 015000K104 015000K301 015000K401 015000K407
i _ _ _ _ _ A
--__ _ _ _ _ - _ _ _ _. t 31__ldE109UEdlE_9dE_ CONTROL @ PAGE 32.
ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
. . ANSWER 3.03 (2.50) a.
None b.
Diverts ventilation through filter banks c.
Actuate control room pressurization d.
Annunciated CNMT evacuation alarm e.
None (0.5 pts each) l REFERENCE 2LP-SOS-43.1 pgs 12,13,22,25,39 EO-4 3.9 072 000 K 1.01-3.1 K 1.03 3.6 K 1.04 3.3 072OOOK101 072OOOK103 072OOOK104 ...(KA'S) ANSWER 3.04 (2.75) a.
1.
No effect 2.
Arm and actuate 3.
Arm and actuate 4.
Arm ec+y-enc / o c}m}e ( 0. 25 p t s e ac h ) b.
No condenser vacuum No cooling tower pumps running i Lo-Lo Tavg (0.33 pts each) H c.
Take the control mode selector switch to RESET after Pimp failed low T.k' N<6m h-f coon l S& eke's & OF-F (0.75) l sc REFERENCE BVPS OM 2.21.1 pgs 21-24, Fig 21-7d OMCN 87-3 pgs 5-8 3.5 041 020 K 4.11 2.8 K 4.14 2.5 K 4.17 3.7 K 1.05 3.5 K 4.09 3.0 2LP-SGS-21.1 EO-4 041020K105 l
_ _ _ _ _ _ _ _ _ _ _ _ __- ' 3 __ldElgggEgIg_ggg_ggylggLS PAGE
', ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
ANSWER 3.05 (2.25) a.
Low oil pressure High oil temperature High jacket water temperature (0.25 pts each) 6.
During isochronous operation when the diesel is supplying the emergency bus (0.75) pumps (.37)
c.
RHR (. 3 78) Standby service water pumps-CCW-pumps W26--r t c-2 chi - o t; No yvmf.s w LL o%f, E bl,, w,\\ \\ s%1 m EW Lot wll ne1 )s a d UNh n REFERENCE ,a.swd c a ve l hue is /a o a c o o ns BVPS OM 2.36.1 pgs 41,42,53,54 U 3.7 064 000 K 4.01 5.8 K 4.02 3.9 k 4.11 3.5 2LP-SOS-36.1 EO-12 36.2 EO-6,9 064000K401 064000K402 064000K411 ...(KA'S) ANSWER 3.06 (3.00) a.
Raises the limit (0.25) because high dT indicates a higher power (0.5) b.
Increases (0.?5) to raise pressurizer level to 1 0 0*/. program, because of the higher Tave (0.5) c.
Rods move in (0.25) because of the Auct. Tave/ Tref mismatch (0.5) d.
No effect(0.25) the demand signal is present (Tave/ Tref) but there is no arming signal (0.5) REFERENCE BVPS OM 2.1.1, pgs 12,20 2.6.1 pg 63 2.21.1 pgs 21-24 3.9 016 000 K 3.02 3.4 K 3.03 3. 0 K 3.01 3.4 2LP-SOS-6.2 EO-8 2LP-SOS-21.1 EO-4 1.3 EO-10 . - - _ - _ _ _ _.
3i__1dElgydEyl@_@NQ_ggyl@Q6S PAGE
ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
, Ol6000K302 ' ANSWER 3.07 (2.00) I a.
Close b.
Close c.
Open ' d.
Open , e.
.Close f.
Close (0.33 pts each) REFERENCE BVPS AOP 2.34.1, Loss of Instrument Air 3.8 078 000 K 3.02 3.4 R 2LP-SQS-34.1 EO-8 I 078000K302 ...(KA'S) ANSWER 3.08 (2.60) a.
The steam pressure compensation failing low causes the steam flow signal to decrease which causes FRV closure (0.5) As level decreases, the level error will cancel the flow error and level will stabilize when the FRV opens (0.5) b.
The FRV will open due to low level indication Actual SG level will increase to 75% FRV will close on 2/3 high-high level turbine will trip on high SG level which will cause a reactor trip (0.4 pts each) REFERENCE BVPS OM 2.24.1 pgs 16-19 2.1.5 pg 4 ' i l 3.5 059 000 K 1.04 3.4 l K 4.19 3.2 l 3.9 016 000 K 1.12 3.S ! K 3.12 3.4 l 2LP-SQS-24.1 EO-7 016000K112 016000K312 059000K104 059000K419 ...(KA'S) - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ _ _ - _ _ _ _ - _.. _ _ - _ _ _ - -
, f 3.__]Ng]SgDENig_gNg_CgN189ES PAGE 35' ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
I . . ' ANSWER 3.09 (2.50) PZR heaters trip off Letdown line isolation valves close Letdown orifice isolation valves close Charging flow increases RCS inventory increase causing the reactor to trip on high PZR level if above P-7 (or P-10) (0.5 pts each) l REFERENCE
1 BVPS OM 2.6.1 pg 63 3.2 011 000 K~1.01-3.6 K 1.04 3.8 K 4.01 3.3 K 6.04 3.1 ) 2LP-SQS-6.2 EO-8 011000K101 011000K104 011000K401 011000K604 ...(KA'S).
J ANSWER 3.10 '2.50F 1 D a.
True b.
False W.. Delekch d.
True e.
False (0.5 ea) REFERENCE s BV2 LP-SOS-11.1 pg 3 EO
l 013/000 K4.01 3.9/4.3 - ; 013/000 K4.12 3.7/3.9 l [ 013OOOK401 013OOOK412 ...(KA'S) t i
__ _ _ - _ _ _ s/t Cycle efficiency = (Networx ' f. m a' v = out)/(Energy in)- ") .
s = V t + 1/2 at , -. og o { = mc A = A e.At - gg = 1/2 mv a = (Vf - V )/t A = AN g
PE = mgn s/t i= tn2/t1/2 = 0.693/t1/2-y =y - 3: 4 = 8## " E(*1 9)(t )3 'A =v2 _ t b 1/2 [(t1/2) * (*b)) l-i e 13 1 = . ; _ 'E * l ,. =-t . l . . Q = c.: ..a I=Ie (j. uA :,: g l I = I, 10' */ pwr = DL = 1.3/u P = P 10 ""!*) HVL = -0.593/r
o.
P = P e'7' . o $UR = 25.06/T SCR = S/(1 - K,ff) CR = S/(1 - Keffx) x SUR = 25c/t' + (s - o)T CR )( 1 - Kgff)) = CR (I ~ k eff2) [
T = ( t*/c ) + [(a - o )/ o] M = 1/(1 - Xgff) = CR)/CR g T = L/ ( o - 3 ) M = (1 - Kefg)/(I - Kefn) T = (3 - o)/(la) SDM = (1 - Keff)/Keff ,
/K t* = 10~' seconds a = (K eff )/Keff * #Keff eff ~I T = 0.1 seconds o = [(L*/(T Keff)3 + [ieff (I * T)] / Id I d) = P = (reV)/(3 x 1010) I-)d) 2 =2 2 l Id22
t = aN R/hr = (0.5 CE)/d (meters) R/h'r = 6 CE/d2-(feet) ' dater Parameters Miscellaneous Conversions 1 gal. = 8.345.lem.
1 curie =~3.7 x 1010dps 1 ga. = 3.78 liters 1 kg = 2.21 lem
if = 7.48 gal.
I hp = 2.54 x 10 8tu/hr ' Density = 62.4 lbm/ft3 1 on = 3.41 x 106 Btu /hr
lin = 2.54'cm Oensity = 1 gm/c::r Heat of vaporization = 970 Stu/lom F = 9/5*C - 32 Heat of fusion = 144 S tu/ lbm
- C = 5/9 ("F-32)
1 A t:a = 14. 7 p s i = 29. 9 i n. Hg.
I BTU = 778 f t. lbf-I ft. H 0 = 0.4335 lbf/in.2
_ _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _. _ _ _ __ _ _ _ _ _ _ j _ __
_ _ _ _ _._ - . . PAGE
Si__PggCgggggp___gggggby_9999999g3,ggggggggy_ggg _R A _D _I O _L O G_ _I C_ _A _L _ C O _N _T _R O L _ _ _ __ __ , ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
ANSWER 4.01 (2.50) a.
Every 15 minutes (0.5) b.
A confirmatory sample should be analyzed to extend the effective per-iod of authorization since its 72 hour limit was exceeded (1.0) c.
No (0.5) because dilution flow shoud continue for 30 minutes after any-discharge (0.5).
REFERENCE RCM pgs 47-49 BVPS OM 2.17.2 pg 1 3.11 068 000 K 4.01 3.4 068 System generic 1 2.7 2LP-SOS-17.1 EO-9 068000G1 068000K401 ...(KA*S) ANSWER 4.02 (2.00) a.
Yes (0.4) b.
PORV or Safety Valve is open or PZR vapor space leak (0.6) c.
Prevent ILC from tripping the bistables from first channel failure (0.7) and be in hot standby in one hour (0.3) fitabe n eg e n digs p.10 Ab5v m pY id. 000 SUA Wniffin C]AHa C pen ng e,,) d6 REFERENCE
I BVPS AOP 2.6.1 pgs 5,6 3.3 010 system generic 1 3.5 3.3 000 008 EA 2.12 3.4 r 2LP-SOS-6.2 EO-8,9,10 0000084212 010000G1 ...(KA'S)
-_ _ _ _ _ _ _ _ _ _ - - - - PAGE-37 S2_ _ PBggggyBg@_;_ygSD961_9pygBD8by_ ggggggygy, ANp 599196991996_999I596 . . BEAVER VALLEY 2-87/05/19-51LK, D.
ANSWERS -- ANSWER 4.03 (3.00) a.
1.
Manually or locally trip the turbine 2.
Runback the turbine 3.
Close the MS trip and bypass valves (0.4 each, 0.3 for sequence) b.
Intermediate high cntmt pressure.(3.0 psig) l [, s.Mi-9h s t m line pres (525-psi.gL 4 8"* P3 4 l Stm line high rate of change (100 psig in 50 secs) (Any two 0.5 each) c.
Monitor RSS pumps for cavitat,on (0,5) i REFERENCE BVPS EOP, E-O pgs 3,7,8
3.1 000 007 EK 3.01 4.0 SYS GEN
4.4 OOOOO7K301 OOOOO7G11 ...(KA'S) l l ANSWER 4.04 (2.50) l l a.
350 F (0.5) 425 psig (0.5) b.
Shutdown the pump (0,5) l %.n:Wiwiss C inno s t oiv l c.
Exclude air (0.5) and to prevent the formation of an explosive hydrogen / oxygen mixture (0.5) REFERENCE BVPS OM 2.6.2, pgs 1, 5,
3.3-010 000 G 1 3.5
3.3 3.4 003 000 G 15 3.8 2LP-SOS-6.2 EO-10,11 003000G15 010000G10 010000G1 ...(KA'S) I ! ! l ,
.. ... .. .. .. .. .. . . . . . . PAGE
31__E09EE990ES__~_U99UOb1_ bed 99UOb1_ggggggggy_Agp RADIOLOGICAL CONTROL
. ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
- l l
l I ANSWER 4.05 (.50) ' l If it is needed for RCS cooldown '( 0. 5 ) l l REFERENCE i BVPS EOP.E-2, pg 2 3.6 000 040 EK 3.04 4.5 i
LP-LRT-VII-65 LO-B 3,4
, OOOO40K304 ...(KA'S) l I I )
4 l ANSWER 4.06 (3.00) I oat of at d onfiren af WhC N'% l gq a.
Steps must be performed i-n-sequence ( 0,5) -uni. ass expr-essl y st at ed-- otherwise. (0.5)
l b.
2F (0.5) 5'/. p er minute (0.5) A c.
Chemistry must sample (0.5) for iodine. (0.5) \\ l REFERENCE BVPS OM 2.52.4 B pgs 1,2 3.5 045 000 G
2.6
2LP-SOS-50.51.52.1 EO-2 045000G1 ...(KA'S) l l ANSWER 4.07 (.50) If it is needed for RCS cooldown (0,5) REFERENCE BVPS EOP, E-3 og 6 3.6 000 040 EK 3.04 4.5 3.3 000 037 EK 3.07 4.2
LP-LRT-VII-67 EO-B4 OOOO40K304 OOOO37K307 ...(KA'S)
_ _ _ _ _ _ - _ _ _ _ _ _ PAGE
t__PggCgggSE@_;_ygSU@6t_@@ygSO9(t_gd@SQEdgy_@ND
66919L991G6'_G99IB9' .
ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
I ANSWER 4.08 (.75) /,f ! CNMT pressure > SrO psig I.3 78} I Rad' levels > 10E5 R/hr (. 3 75) I nt egr-a t ed -rad dos e-->- 1 OE 6. Rads _._ l0..-25-pt s-eac h )- l Ce n*N sunl> s e of a 1h nsd ny sweg a m cLbd. d, c'le s. c o rn m enb f REFERENCE i LP-LRT-VII-65 pg 7 l 3.3 000 011 EK 3.12 4.4 LP-LRT-VII-65 LO-A2 l OOOO11K312 ...(KA'S) l l ANSWER 4.09 (1.00) a.
At least one HHSI/ charging pump running RCS/ steam line differential pressure < 145 psid (0.25 pts each) b.
Less than required subcooling PZR level < 4 % (0.25 pts each) REFERENCE BVPS EOP E-O fold-out page 3.1 000 022 EK 3.02 3.5 l LP-LRT-VII-61 EO-B 4,5 OOOO22K302 ...(KA'S) i __ _ - - _ _ _ _ _ _ _ _ _ _
S L _ _P6Qgggg6{@ _ _ _GQ@[@b t _@@UQBU@6 t _([[6@{GQX _ AN D PAGE
5691969GICeg_CgNIgg(
ANSWERS -- BEAVER VALLEY 2-87/05/19-SILK, D.
l l l \\ q ANSWER 4.10 (2.50) a.
1.25 Rem /qtr (0.5) l _ f,p fby sn w -!)CN6nS ' b.
To search for or remove injure personnel (0.5) or prevent conditions that would probably injure numbers of people.
(0.5).
c.
Occupational exposure history (0.4) If provided it allows an increase in the quarterly WB exposure limit from 1.25 Rem /qtr to 3.0 Rem /qtr.
(0.6) REFERENCE BV2 RCM pg 6,9 PLT GEN
3.4/3.9 PLT GEN
3.4/3.7 OOOO22K302 OOOO74K311 ... (-KA'S) ANSWER 4.11 (1.25) a.
Core exit TC > 1200 F (0.25) or Core exit TC > 729 F and RVLIS full range < 40*/. with no RCP's running (0.5) 6.
Cold leg temperature decreasing > 100F/hr and RCS cold leg temperature < 242F (0.25 pts each) REFERENCE BVPS EOP E-1 fold-out page 3.1 000 022 EK 3.02 3.5 3.4 000 074 EK 3.11 4.0 LP-LRT-VII-62 EO-83
LO-85 OOOO22K302 OOOO74K311 ...(KA*S) - _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _
d.___6@gCEgQQg@_;_ygSO@(t_@@ygBy@(t_ggggggggy_AND PAGE
- 5091969GIC66_C991596
.
ANSWERS -- BEAVER VALLEY 2-87/05/19-51LK, D.
ANSWER 4.12 (.50) D (0.5) REFERENCE TS pg 1-3 3.2 002 020 Sys Gen 11 3.3 l
3.8 l 2LP-SQS-6.2 EO-13 OO2020G13 OO2020G11 ...(KA'S) l I (o,d ANSWER 4.13 L1 rOO)~ , l a.
B (0.5) h- - - M O {)e le k k s REFERENCE BVPS OM 1/2.48.2 B pgs 5,7 l Plant Wide Generic 194001 A 1.01 3.3 l 2LP-SOS-48.1 EO-12,15 (?) 194001A101 ...(KA'S) l ANSWER 4.14 (1.50) a.
True b.
Fal se c.
False (0.5 pts each) l REFERENCE BVPS OM 1/2.48.1 8 pgs 7,8 Plant Wide Generic 194001 A 1.03 2.5 2LP-SOS-48.1 (?) 194001A103 ...(KA'S) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .. _ _ _ _ _ _ _ _ _ _ _ j
31__E599E990EE_!_U98U96L OEU98U@ht,gdgggggg1_AND PAGE
6691969Glce6_cggIggh ANSWERS -- BEAVER' VALLEY 2-87/05/19-SILK, D.
- ANSWER 4.15 (.50)
A.
B.
C.
D.
-(0.12 $p ts each ) ] l REFERENCE BVPS OM 2.56 B.3 pg i Plant Wide Generic 194001 K 1.16 3.5 2LP-SOS-33.1 EO-10 194001K116 ...(KA'S) l t l ' ANSWER 4.16 (2.00) 1.
d 2.
a,d 3.
a,b,c,d 4.
c,d ! l S.
d (0.2 pts each) l REFERENCE BVPS AOP 2.6.2 pg 4 . 3.2 002 O20 Sys Gen 11 3.3
3.8 i 2LP-SOS-6.2 EO-10,12 OO2020G13 OO2020G11 ...(KA'S) i , l ' l i - _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ - _ _ _ _ _ _ _
- -. " "### N [& U.
S.
NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION . , FACILITY:. _B_E_A_V_ER__V_A_L_L_E_Y__2__________ , - REACTOR TYPE: _PWR-WEC3________________ i DATE ADMINISTERED _ @ 7 / 9 9f t 9_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I EXAMINER: _ _B _A _R B E _R _ _S _. _ _ _ _ _ _ _ _ _ _ _ _ _ _
g_ j[._hiY_ _ i l CANDIDATE: ___ _ _____________ IN@IBUgIJgNg_IQ_C@Npip61El i Use separate paper f or the answers.
Write answers on one side only.
I Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question. 'The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF ! CATEGORY % OF CANDIDATE'S CATEGORY __V66VE_ _19186 ___SCQBE___ _V8(yE__ ______________QQIEQQ6Y_____________ _2E 99__ _2Et99 ________ 5.
THEDRY OF NUCLEAR POWER PLANT ___________ OPERATION, FLUIDS, AND THERMODYNAMICS , 7/f.523 l _2E_22__ _3E:99 ________ 6.
PLANT SYSTEMS DESIGN, CONTROL, ___________ AND INSTRUMENTATION _3E199__ 2E 99 ________ 7.
PROCEDURES - NORMAL, ABNORMAL, ___________ EMERGENCY AND RADIOLOGICAL SL4',5R) _9fIft__ _29199 ________ 8.
ADMINISTRATIVE PROCEDURES, ___________ CONDITIONS, AND LIMITATIONS 199 99__ ________x Totals ___________ Final Grade All work done on this examination is my own.
I have neither given nor received aid.
___________________________________ Candidate's Signature _ _ _ _ _ _ _ _ - _ _ _ _ - - _
__ - _ _ _ _ _ _ _ _ _ _ _ _____ _
- $
s' 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 gely to f acilitate legible reproductions.
4.
Print your name in the blank provided on the cover sheet of the examination.
S.
Fill in the date on the cover sheet of the examination (if necessary).
l 6.
Use only the paper provided for answers.
~ l '
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
8.
Consecutively number each answer sheet, write "End of Category __" as appropriate, start each category on a new page, write gnly gn gne side - of the paper, and write "Last Page" on the last answer sheet.
9.
Number each answer as to category and number, f or example, 1.4, 6.3.
10. Skip at least three lines between each answer.
11. Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
12. Use abbreviations only if they are commonly used in facility LLtetatute.
13. The point value f or each question is indicated in parentheses after the question and can be used as a guide f or 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 examiner 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 I completing the examination.
This must be done after the examination has been completed.
I _ _ _ _ _ _ _. - _. _. _ _ _ _ _ _
__. _.
_.
_ !. b 10. When you complete your examination, you shall: a ' a.
Assemble your examination as follows: . ' (1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
(3) Answer pages including figures which are part of the answer.
j 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 l not use for answering the questions.
l i d.
Leave the examination area, as defined by the examiner.
If after leaving, you are found in-this area while the examination is still in progress, your license may be denied or revoked.
< . Y ) . ! l i I
) _ _ _ _ _ _ _ _ _ _ _ _. _
""~~iN_$$$h_6f_sh__5$65_""""~"~~~"~~~^~~~~~~~~~~"~"~"""""""~~ ~~ ~ ..., , _ _
- '
. , ' QUESTION 5.01 (2.50) ANSWER the f ollowing TRUE or FALSE.
a.
Equilibrium samarium concentration is a function of power.
i b.
Equilibrium xenon reactivity is dependent upon core burn up.
c.
Xenon concentration initially increases after a reactor trip.
d.
Equilibrium samarium concentration after a trip is a function of the previous power level.- e.
Equilibrium xenon concentration after a trip is a function of the previous power level.
l ' ! QUESTION 5.02 (3.00) ! I The operator has brought the reactor critical at BOL and is increas-ing power to 10-8 amps.
a.
If the critical data was recorded with Bank D at 120 steps, Tave at , l 547 F, and a critical boron concentration of 1000 ppm what would be the expected SUR if Bank D was raised to 152 steps? Assume Bank D differential rod worth is 6 PCM/ step and l ambda i s 0.1/sec.
Show all work and state all assumptions.
(2.0) b.
At BOL, reactor power is raised to 50*/ power at which point a control rod drops into the core.
Briefly explain how and why Tave would differ if this event occured at EOL.
No calculations are necessary.
(1.0) ! l QUESTION 5.03 (2.50)
Answer the f ollowing questions concerning coefficients of reactivity.
.l l a.
How and why does the value of MTC change as temperature is increased in an undermoderated core? (1.0)
b.
Which initial temperature, 300 F or.547 F, will give the largest change in the magnitude of MTC as boron concentration is lowered from 1000 to 500 ppm? Briefly explain why.
(1.0) c.
Why does power defect become more negative as the core ages? (0,5)
l (***** CATEGORY 05 CONTINUED ON NEXT PAGE
- )
l l l !
L--_______-.__-__-___..__ ~~$b5$$b6555b[$$ "" ~ " " ,.. , l
, - . QUESTION 5.04 (3.00) During a startup the reactor is subcritical at 3000 CPS on the Source Range Instruments when a steam dump valve f ails open.
a.
Explain the response of reactor power and Tave during the transient.
Continue your explanation until stable conditions are reached.
Assume no operator action is taken at BOL conditions and no reactor trip occurs.
Calculations are not required.
b.
How and why would SUR and final reactor power level differ if the transient occured at EOL as compared to BOL7 Calculations are not j required.
j l QUESTION 5.05 (2.50) I ! l a.
The plant is operating at 85% power with all systems in automatic.. l The operator inadvertently aligns charging pump suction to the RWST.
l How is shutdown margin affected by this action? Briefly explain why.
(1.0) ' b.
If a control rod was stuck completely out of the core on a reactor - trip, how, if at all, would the CALCULATED SDM differ from the case where all rods are inserted on a trip? Briefly explain why.
(1.5) l l l l QUESTION 5.06 (2.00) ' Listed below are conditions might would af f ect an initial fuel load 1/N plot. For each condition listed, INDICATE if criticality + sill be under or over predicted and STATE a brief reason for your prediction.
a. A fuel assembly is loaded near the detector.
(0.5) b.
The detector is too far from the newly installed fuel.
(0.5) c.
The detector is too close to the source.
(0.5) l d.
Thu detector is too far from the source.
(0.5) l l l (***** CATEGORY 05 CONTINUED ON NEXT PAGE
- )
- _ - - _ - _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ .__ -
~~IbkkbhIbbbIbh " ~ ~ ~ ~ "~ "" ""~"~~ . .
. . QUESTION 5.07 (3.00) There are THREE primary parameters that af f ect DNB and can be controlled by the reactor operator other than core flow or flux distribution.
Briefly explain how an INCREASE in each of these parameters affects the DNBR.
Assume the other parameters remain constant.
QUESTION 5.08 (2.00) a.
During natural circulation, Explain how it is possible to f orm a bubble in the reactor vessel head when indications show that 'the RCS is , subcool ed? Include any indications used.
j b.
How and why will pressurizer level respond (INCREASE, DECREASE, or STAY THE SAME) if the backup heaters are energized with a bubble in the vessel head? Assume pressurizer level is in the normal band.
) QUESTION 5.09 (2.50) a.
During operation, indication f or charging flow rate is lost due to a transmitter failure.
Explain how the operator can approximately estimate or calculate the charging flow rate using other control room indications.
(1.0) b.
Explain how the f ollowing occurrences would af f ect Net Positive Suction Head available to the Reactor Coolant Pumps.
Assume that no operator action occurs and consider each occurrence separately and independently.
1.
Grid f requency decreases to 59.6 HZ.
(0.5) 2.
Pressurizer temperature increases.
(0.5) 3.
Turbine power increases slightly with rods in manual.
(0.5) (***** CATEGORY 05 CONTINUED ON NEXT PAGE
- )
_ - - _ ____-_- - - . J
= - :.ues= =- = ==== w- - = u = - - a a s s - u = - - a u - - w a u = = s u a - - - - ISE60QQyN@dlCS , ,
. QUESTION 5.10 (2.00) The secondary heat balance (calorimetric) is used to verif y instrumentation accuracy.
a.
How much of an error would a 20 psi deviation in Pstm cause in the heat balance.
Briefly explain your answer.
j b. How, if at all, is RCP heat accounted for in the heat balance? . f (***** END OF CATEGORY 05
- )
. . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____ ___ ____.__ ____ _ __._______1J
mm___m_me m_e mee_maseeee_meweeesu__a=_mweewuww2_u_xwu e -mo m
- ..
- QUESTION 6.01 (3.25)
l . a.
List the 5 signals that will start the motor driven auxillary feedpumps and the 2 signals that will start the turbine driven auxillary feedwater pump.
Setpoints not required.
(1.75) b.
What automatic action takes place if a low flow condition exists in an auxillary feedwater line.
(0.5)j ! c.
A steam break occurs on a S/G that is being fed by AFW.
How and why will the AFW system respond? (1,0) a QUESTION 6.02 (2.75) i ) a.
What positions of the " Makeup Mode Selector Switch" will NOT l result in the delivery of a BLENDED makeup flow? (1.0) < b.
During boration, what control or instrument serves to control the amount of boron added.
(0.5) c.
State how automatic makeup is initiated and explain the automatic action that occurs upon initiation.
No specific setpoints or values are required.
(1.5) i QUESTION 6.03 (3.00) a.
The ACB-42A breaker is closed and supplying the A 4160V bus.
What action is necessary to allow transf er to the ACB-42C breaker.
(0.5) b.
While attempting to supply the A 4160V bus, a fault occurs on the bus.
How are both supply breakers af f ected by the fault? (0.5) c.
What action must be taken prior to reclosing a given A 4160V supply breaker if a fault still exists on the bus? (1.0) d.
Under what 2 circumstances will the A 4160V auto transfer to the alternate supply? Setpoints not required.
(1.0)
! ! (***** CATEGORY 06 CONTINUED ON NEXT PAGE
- )
' . _ _ _ - - _ -
wa- -www= waaaawa-wasaawo-ae---naa-wan-----~n-uw waaaa ---
.. !
QUESTION 6.04 (2.50) . , a.
List the three major inputs to the pressurizer OPS system.
(1.0) ' , b.
During shutdown conditions, a wide range Tc fails' low.. How, if.at l all, will the pressurizer OPS system be affected? Briefly explain why.
(1.0) J c.
If during shutdown conditions, a wide range Tc had failed high, how,
if at all, would plant response differ? No explanation is necessary.
I d i.^! H QUESTION 6.05 (2.50) Answer the following questions TRUE or FALSE a.
Automatic initiation of SI is blocked when the reactor trip breakers are open with the SI signal reset, b.
The low steamline pressure SI signal may be reset if both the hot and kWTE cold loop stop valves in the associated primary loop are shut.
c. When the low pressurizer pressure SI and MSLI signal is blocked, the MSLI signal on steamline pressure rate _ decrease is enabled.
d.
2/3 pressurizer pressure channels above 2000 psig def eats manual H blocks on the SI signal (P-11 blocked).
e.
If an SI signal causes a reactor trip the SI signal. may be reset within 10 seconds if the reactor trip breakers are closed immediately.
I
QUESTION 6.06 (2.50) a.
Under what condition would it be necessary to use the RSS pumps to supply the HHSI pumps.
(0.5) q b.
Wh.at would be the two probable consequences if the chemical addition system failed to inject its solution into the quench spray pump suction on a valid CIB signal.
(1.0) c.
If the control switch for a quench spray pump is taken to stop will the pump always stop? Briefly explain your answer.
'O.75) - C.O i (***** CATEGORY 06 CONTINUED ON NEXT PAGE
- )
l l u __.__ _ ____ _ 1 _____ _ _ _. _. _. .J
esemawwasmemesememeeeeeuemeeemmeeemueeceumeeeuwu_w;=uu - - - - w, l T.
QUESTION 6.07 (3.00) , l e a.
What is the purpose of the high positive and negative rate reactor trips? b.
What reactor trips are automatically reinstated below P-10? l c. How are the SRNI's af f ected when P-10 is sati fied? QUESTION 6.08 (2.00) Describe the automatic actions of each listed radiation monitor when its countrate increases to above the high radiation alarm setpoint.
Do not i include alarms.
a.
Waste gas storage vault (2RMG-RQI303) (0.75) ' , Containment purge exhaust (2HVR-RQ104A) (0.5) b.
c.
Control room area (2RMC-RQ201) (0.75) QUESTION 6.09 (3.50) List the setpoints and the reasons for the f ollowing reactor trips.
, a.
Low-Low S/G 1evel (1.5) , b.
Safety injection (2.0) ! i (***** END OF CATEGORY 06 *****)
l _ _ _. _... _ _ _ _ _ _ _ _ _ -
~5bb$bbhb$h5(2Nhb!hhh . ,
, QUESTION 7.01 (2.50) l ' l Answer the following questions concerning refueling either TRUE or FALSE l a.
Inching can ONLY be accomplished when the. key is set in the "Run" position and the inching _ permissive light is illuminated.
b. The Emergency Pullout Cable system can only'be used if the conveyor motor is manually disengaged f rom the transf er system.
c.
If the operator notices a large unexplained change in -load on the i Dillon readout, he should immediately reverse directions.
J d.
Slack cable-hoist will not lower if the Dillon Load Coll < 450 lbs.
l e.
Before fuel handling operations in the f uel building are commenced l the f uel b1dg vent system shall be in service and discharging Through at least one train of SLCRS HEPA filters and charcoal adsorbers.
l l l
QUESTION 7.02 (2.50) Answer the following questions concerning Radiological Controls, a. What is the maximum allowable quarterly whole body dose that a newly I hired 1B year old operator may recieve per the Radeon Manual.
(0.5) j l b.
Under what circumstances, if any, would it be permissible for a l worker to recieve an acute dose of 50 rem.
(1.0) i l c. What is an NRC Form-4 and how does it affect an individual's (1.0) maximum allowable dose rate? Be specific.
QUESTION 7.03 (3.00) Answer the following questions concerning General Operating Instructions, OM 52.
a.
What are the requirements in this OM regarding the completion of procedure steps in sequence.
b.
What is the maximum allowable value of Tave-Tref mismatch and turbine loading rate permissible during load follow operations.
c.
During 1 cad follow operations, what must be done if thermal power changes 15% in one hour or less.
(***** CATEGORY 07 CONTINUED ON NEXT PAGE
- )
_ - _ _ _ _ - - -
Zz__PgggEDUggg_ _NOSD8L _89$9BD8L-2_gDESGEB9Y_8@p PAGE
1 88DlDLD9100L_CQNJBQL i .
. QUESTION 7.04 (2.00) Answer the following questions concerning Continuous Insertion of RCCA Control Bank, AOP-2.1.3.
a.
What anticipated operational transient could cause a continuous bank insertion of the controlling bank? (0.5) b. If a malf unction causes a bank insertion and it terminates at less than the Low-Low insertion limit, what immediate operator action is required.
(0.5) c. If rod control is transferred to manual and a continuous insertion condition is still present, list two operator actions that should be performed.
(1.0) QUESTION 7.05 (2.50) What is the preferred core cooling method during a loss of normal (1.0) a.
and emergency AC power? Include the components / systems used.
b. The actions of ECA-0.0 LOSS OF ALL AC POWER require letdown to be isolated.
What is the purpose of this action? (0,5) c. If the S/Gs are required to be depressurized when using ECA-0.0, what, if any, cooldown rate limit applies? Briefly explain your answer.
(1.0) QUESTION 7.06 (3.00) Answer the f ollowing questions concerning E-0, Reactor Trip or Safety Injection.
a.
List three actions, in order, that may be taken if the turbine (1.5) is NOT tripped.
b.
List two of the three conditions that would require steamline (1.0) isolation. (SLI) c. What specific operator action is necessary after the RSS pumps (0.5) start? (***** CATEGORY 07 CONTINUED ON NEXT PAGE
- )
__ _ _ _ _ _ _ _ _ _ _ _
"'IRhhfhhhhfhh(_hhhfhhL l ~ "" " ~" . t l .
, ' QUESTION 7.07 (3.50) Answer the following questions concerning E-3, Steam Generator Tube Rupture (SGTR).
l a.
List 3 of the 4 indications that are used to determine the ( 1. 5)' l ruptured S/G.
b.
List the 2 conditions that require tripping RCPs during a SGTR.
( 1. 0 ) ' c. When, if at all, is it permissible to establish FW flow to a ruptured S/G that is also f aulted? (1.0) , QUESTION 7.08 (2.50) , , Answer the following questions concerning RCS precautions and limitations.
a.
What is the maximum allowable RCS temperature and pressure with (1.0) ' RHR in service 7 b. What action should be taken if RCP vibration reaches 20 mils.
(0.5) c. List two reasons for maintaining a nitrogen overpressure of (1.0) l 0.5 to 3.0 psig on the PRT.
! QUESTION 7.09 (1.50) List three automatic actions that occur on a loss of 125V DC Switchboard DC 2-1.
l QUESTION 7,10 (2.00) i Answer the following questions concerning a major secondary steam system rupture.
Assume 3 loop operation at EOL with all ECCS and offsite power systems available.
I a.
What is the initiating condition for the reactor trip? (0.5) ' b.
Does the plant return to criticality if a rod sticks'out (0.5) during the reactor trip? c.
How does MSIV closure lessen the consequences of the event.
(1.0) (2 reasons) (***** END OF CATEGORY 07
- )
l l _ _ _ - _ _ -
=x - ww wu ga wa w w-a a a - a w a n a - a - - n - - - - a n - - u - - - - - a n - n - - -....
. t
QUESTION 8.01 (2.00) . , Answer the f ollowing questions concerning f acility staf fing per Technical Specifications ONLY. Assume plant power is 100% unless otherwise specified j
a.
Choose the minimum number of Radiological Controls technician (s) that are necessary to relieve the offgoing shift for present plant conditions.
A.
O B.
C.
) D.
i l b.
Choose the minimum number of fire brigade members required on shift.
I A.
B.
)
C.
D.
c. Choose the minimum number of licensed operators required on shift for safe shutdown.
l A.
O j B.
g ': / . ' d.
Per Tech Specs, choose the one set of crew manning that best represents the MINIMUM requirement for reactor startup after a reactor trip.
l An STA is on shift in each case. Select the best answer.
A.
2 SROs, 1 RO in the control room, 2 AO i l B.
2 SROs, 2 ROs in the control room, 3 AOs l C.
1 SRO, 2 ROs in the control room, 3 AOs i D.
1 SRO, i RO in the control room, 2 ads l l l , (***** CATEGORY 08 CONTINUED ON NEXT PAGE
- )
J
me._eememememm-eemmmeeommmmmemmmmemeeeeeeumusemwtumuuusmau --mm ami .
QUESTION 8.02 (2.50) , , The following questions pertain to job responsibilities of various plant personnel.
Use the appropriate title to answer the questions.
a.
Who is required to notify offsite agencies of any situation which may affect the safety or integrity of the reactor plant? b.
Who assures that equipment clearances are properly executed? c. Who can issue Special Operating Orders?. d.
Who is responsible f or initiation of the Emergency Preparedness Plan (EPP)? e.
Who will ultimately assume the responsibility of the Emergency Director? QUESTION 8.03 (2.50) a.
Following a trip that resulted in a Reportable Event, whose approval is needed to initiate action to start up the unit? (0.5) b.
Under what circumstances is it permissible to exceed a Limiting Condition of Operation and who must be notified? (10 CFR 50.54) (2.0) QUESTION 8.04 (1.50)
Diesel Generator 21's operability load test, which is required every 31 days, is scheduled for today.
The last three tests were completed 36, 68, and 102 days ago respectively.
The plant is at 100% power.
Are Technical Specifications being met? Explain why or why not.
i (***** CATEGORY 08 CONTINUED ON NEXT PAGE
- )
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
s_-_ws_a_aaauu aaa a-saeua-aan----aaaaa-au---a
==wa_asee-a - - - - -- ?. r l I QUESTION 8.05 (3.00) ,
Classify each of the following occurances using the Event Classification l sheets provided.
Identify what factor was used to determine the final classification. If an event would not be classified under any of the four I emergency classes, explain why? a.
A small plane crashes on the river bank across from the plant.
The radioactive medical isotopes the plane was carrying cannot be l located.
' b.
One diesel generator is inoperable and a loss of offsite power ) occurs. The operable diesel generator fails to start. Convex reports that a lighting strike disabled the switchyard and power j won't be restored for at least one hour.
c.
An accident in the containment results in an injury to a worker.
The worker is in contaminated anti-C clothing and has broken his l 1eg.
Due to the accident the worker receives 2 Rem of radiation l Previously he had accumulated 500 mrom f or the quarter and year.
i i d.
Following operations at 100% power for six months, a loss of coolant accident occurs inside containment. Due to a RSS and QSS malfunctions l containment pressure reaches 55 psig.
Only one diesel generator started and System predicts a loss of f site power within 15 minutes.
l QUESTION 8.06 (3.00) Using the attached Technical Specifications, list all the applicable actions statements by number, if any, f or the f ollowing equipment failures.
Consider each f ailure independently.
Reactor coolant letdown valve 2CHS-ADV2OOA is open and a.
cannot be closed.
A reactor startup is in progress (mode 2).
b. RHS Heat Exchanger outlet thermocculples, TE606A and B, are found to be inoperable, c.
Control room bottled air system pressure is found to be at 1500 psig.
(***** CATEGORY 08 CONTINUED ON NEXT PAGE
- )
- - - _ _ - - _ _ _ _ _ _ _ _ _ _ _ . _ _. _ ,
uneenaaw-aasa - - - - wau ww=waauwwav-wwa-aawsawana-e - - - - f, e
.. og the Event Classification erating Procedures (TOP), what is the maximum cd to determine the final h they can.be used and who reviews and' officd under any of the'four are for safety-related procedures? (1.0) operating procedures that have become unwork-ecte from the plant.
ed what three conditions are met? (1.0)
wco carrying cannot be assuring that all personal on shift become red reading material? (0.5) 300 of offsite power a to start. Convex ' 9 cwitchyard and power an injury to a worker.
l ing cnd has broken his 'ssion has been given to def eat an interlock ' /oc 2 Rem of radiation sent purge exhaust monitor.
What actions tho quarter and year.
to tagging and log keeping? (2.0)' months, a loss of coolant c RSS and QSS malfunctions i ono diesel'qenerator power within 15 minutes.
- ions TRUE or FALSE regarding control room area-be maintained clean, orderly, and free of an control boards and panels.
tot all the applicable following equipment tence control board alarms if the offgoing j 'a icul t evolution.
1 10 open and ligulds in the control room is only permitted progress y posted and roped of f.
E606A and B, are ) .) found to be ifications, list ALL the actions statements (1.5) be considered if both centrifugal charging j a low head saf ety injection pump in train l noperable? t differ if, instead of the "A" train charging (1.0) esel were inoperable? l . l AEXT PAGE
- )
ORY 08 CONTINUED ON NEXT PAGE
- )
1' I__--_-__-
ADMINISTRATIVE PROCEDURES _CgNpITIgNp3_ANQ_LIMIYATIgN} PAGE
B.
- o
..
QUESTION 8.11 (2.00) . The reactor is in mode 6 with the head bolts removed, the vessel head lifted, but not yet removed. An electrical malfunction occurs which renders the Train "A" DC buses and the "A" RHR pump inoperable. Would it be necessary, per the tech specs, to restore the headbolts and return the reactor to mode 5? Justify your answer by referencing any applicable sections by number.
(***** END OF CATEGORY 08
- )
(************* END OF EXAMINATION ***************)
. - -.- - .^.- -; . n. - - - .- -. - ..: :. ..... . ........ - . . -- .... ..
.
- .
r-
-
. I T - . ":. c.
. . N.
t s - ' - .. . T' i . 's s'~3. . '. s \\ ,
- t s.:
- . xP e32 c e.#. ca,ct:s . - - , cm -- -.
j 8t: 5 ar-e 54- 'S'sa2 8* . - f.-gi-. -327 2.jec-
n =1 gags---s:1 l
.: al.s.a,:e;. . ses g ! i.
= e 3 2.31 es ris - .g:sge"a .- - . < e . ae.18! m 3til!!! liissai ' 111
- -
. . i -
a - ' in J.g ! s ! - -
. 3 I,,33
I. gar - w s_,.:28 e e,3 g-sal is:- - - -2.: m , a - --
s33133 s = 3-
esgg!sta,,3
j!!r.32-- a s: I! tg 3. - - . ! .- y
. - - - I-j .
2-2*3:5:- a. t. e2 'nsa --.
2
a'n t . . em - . - a 12.
' k1s! . ,, = .k E sst s'. . 38:
.me8 . - 2 :s 328 I-.e . 5-351 8<en s p.& - a ' . - -- s.
a-Ils r81 =g .e.,ts.
- -- g -- ,: :=.
gg 1 .-gI*5 2lg :- - - - - per -, ]. ds.[:f
== flerge.se:-- e s-y = - -! --s.
- t sg
- 5-
. a n. >.. . : - r >; i. : : . : r.:.__ s. 1. !,.. _... .. e =n:. 3s-I..gI..s.. =.e..:n, - g3-:- :r.- - - - - . s a., e.
... gg a.
s .-. . . . . 'J s - . . -
- 4-Igge 3:
- e-e lig,t-
- 4 g4
- si.
n -
j , 2: r1:2 2- - 3:3-da.
' t I3 l:e.; '
.s - 8sssa. 2:= -.. . -
- f.:. :
53.:2 >s + , 5.
- o .s.
gg ,
- .
. ' 2,y 23.5 l . . . e6
- .S e 0"I C
.O.zs e m gu g
- .:
.; - <c - . . F
$ ! mers H gg= .,, _.
,3 E h .i ja!M g-] ^ - -
zu 2 :: !:s, . s.. .i.. t,.h.
8a-..
- - . . -. . . . . ? '
- * * ' ' * * * " ' ' * *.
. h t'**a F..v,.'.[
- ef., C, s'.fg.rf f yN'* * ' *, *'w* * i f *, '.,,.lt,;
- * *
I.
, ,,. t. s T.,.._._.._.......__....,.
... ... ~. --.---A__.___ __ _
. '
- y . . " . ' - - a I s .
. r . I , u / s. m s .a . c . . q c ct t e eec c I n . c cnl . n t rr.
O . ) I ot s uee t de y s eay - I i t re suv n nr db y Scs l , qe e e r . n y sr o ii r.
yeny.
u r ado odr, r _ . e tk.
t at a.
t sel n ecre en n eou t r t= ,M n i= s ue . lbmel tnot rwe. oer - n h i.
itis.
e eog= r eu ke l o a t t e. n e, , n tt tlr teusk C i.Ii na u tStit acsw id i t. eL n n sd alet cl qoe eW = eh4il i: r v e vt n l i e e aroe wom. egeLm t rs.
nt e e y.
e n.mhc ete dfEy tiR n . r A eetn r Is t i w f e s on yd .a v ec crir sol eef riabn l n r.ri ovr h hcewe aray ftor t aP >e - h l e ,
t tg tcI e e o ed-r uttt.. ,e,r. t N eee reon rset rtte.er 0, , to
i i
- y.eescilel, w W.) sue / etTe enra e ewn o
- re _ " - J j.
g euw tsl oi m t -
'. .a A rjl eehr sdtd sl s pli.
- i
.I a n i e.
ml s . . 7= el c c al ai srt . ;'.N l e. t n v iLT
- le rgt.
. og eaoo. e hcFr RFcrc L _ d .o cs ' i , i , . l ie mR r gt, Ap e l c4.terjq'.y ee~.e r - ..,, h,, .d **, -
- t
' - l ' ' t ',. _ , I e ' a* . ., _ mh erh q 'f ,,, + e H.
a s
5 _ _ . Alnesr , d _ _ - . ._ b y l . - t e l . l e - r.
e b _ _ , p i- _ e . s . . -
S.' . . $gi,3l' , l .* - . e ri , p a. r R t b s . t _ v.
- s .u ee _ rl i ll . oe - e i 1-h _ t d.l s Cs.
- ', m A a - _ w /wl e p O , Ir - t .~ .rry s
E r _ - l, e _ - e e e - 0 det _ - d ". t o . ku
a e i e
ree - .e f s G .e H o . gse-t n se > eoe _ rr s _ i DLS . r . , . k.
1_ e ,, . _ -' o .V.
y _ . y.
_ ( i .!, i .p r-t I t m ~ , . . '. i i t i.
v ,- '; -. e' l. -
g s-i i " . .,, l.l / t c.
. i iw ' hm 11,eM g , i.. A
i i _ pit! _ / ! - k i" / l . i.
- w
,: m 'M r a '
_ r ra.. s cI.*
g . - ie* N' H.
g s . ep
d e cg l g 'p e g e*i e . . s
e L se . = > s cS i e A> l r p l F iN . , s . ' ., d / r f o n . ' r e-r o.i l .t - . i e Oe
- k-I.
pt rIi . ' [ p Ie Lh . g . t Ct
- P 3, . - u
' p e
. e _y l sr . el e o .., t oss ,da
M lc.. c c e i i oley ep c_ o a t t v CAsd ee l W .e... . ir ya ce r i .. e . . terrl e xl s t c eeet E d .i.
d.
d.
d.
A ttns e e w n - kv e o eo .l . e . ei s, p ri l.. e s e.
s0ss al-c l - - cc o o r o-ee x e ut u,. r r . ILRHog Ly E D t daec ci ! - er . rs-ei . t = h s e g gaa ,e 3.4 .
6
B
i3 M t.
e e H nll s l o nd w c e id-s i , t e oi e t.
. t.
B B ndIs B B B i t s BI M l oB nB r e . g r u ,e T uiapey A e n oe e t 4n A A oe A A eA e A rA e ms, t l e n [/ v srr T yl T aT u .r T n eL e.
,. T T a eata T l e I do u .l, d.
tei-c ' t . s s rd - dt te o s c e pe i t-._ .'. t e t.
o erun et eV i t g ,- l e f e e . . . c tese lts e, s r . . s se cd ' al r e o a rs-i f t.
e c s kee a set ,l r e o es p / / ners lr ll - tg s iep eg sli s S sc.
n s - /o-
cee C it s e e oror ae * .c nace fD AAf
I l rc . m m ' t rer , t ERe -, :. g.
,i ., !; i a' . iI
- !l.;
-
- 'L
,'
- *
, n!j i .3h pp,':[.4 sby19 A' - i ' - . ji.
.ci . rJ I al;. i- .' ,- j
- i'
J };.I
ll Ilt1llllll ,( .lll ,!' Ii
..._.._.._........_....m- . 7_ ,- -. .,. _, ,, , ,,, , ,
- .
r .. _ .
- * - E :i a 3 J e ': b .2 2. 8 i x__ O I' 8 82-t -
E! . .1 33# -
- >.T8,.[.*h c 3,1*12 s ass g !. "s %, g. !
" a l * a 12 "' I ' i .. .e. $ a s.
. :3 2: s,m s . 2:1
3 j"a* 8 :;8.J. j ?! ::2:T*2 a,
e2 225 s.
iij~e i sI,:
- A.
> : as
, > . .,, , 8:32 2.3.2,. ::: g_- , r- ' e ss s _3.
a -:-. e . . g,32 . _a se re. e
.. . g y:ys,s= =1.
n
- ~g. aing s.mir:..
s.: : e.... .:.s ss- .m seS . t a== a-n:.==r:*--:328 $ 1 ?*l _= A S gn=== ::e$ 382:
== . se
- %.
- != -
liasia azak 335
-gg-
- 3 ma
.: 4 a .; .e - a y . - -, - .
- e.
s \\ - . l: ! a . - . - g
=; - 23-mg
- s<a 3sl
. . . ie . - - . =
- 2 4 a
t - is' 3l=. 2Ci glf t - ..ff te 1 .
. .- u me..:3 i
- -
- . a - ._{ -
- 5
. gsm-. g -
. v
5:3.s >
- .
-a a IS 335 3333 raa akae5
. g now a s y - - ~ s ,
.2 ~. i - 6 ..
t
- ,
2, zei e ' s' ,
2":28 t g 31,3 R " - r
.
8 a _3.g k.- -- e asa e - .___ a .o - . 2 gn > s a ms ..
- c <.
-
323= t$.
a t.*e .:.. .E;* 2:3i: t-i'2 ), "
"I' I. 2-
.sm... . c..i:.::
ra.
-
- . .-y _ .'.
J L J L '; L A - - . . . a
Eb ) { ar - 8:*3 w.
E:2 - .) l gi.I'k-d
- 2
{ j2 -.
m a r r
- .
. J.
,s ' I-I I CJ .: 2.g 'l j,$ y ' N, I~'t Ak' At 53i$ - $c.
P -: C v-N c5 e to a,s . v-e v- . S-5- ,- c , .- s:! ! m i e - =
re !m e m. I <e m 3.
m s .am
- ".5 ez
3 <
- 4r -r 1 2 : 4>
312a at = < a
_=!
- 1 zo
- .
3,. Es usi r !! r s . > . r . .. -- ,sf g__ ! is ' - .f ' _::
e .: .: .::3
- .
.m _.: . ,_ z
- b 3:22
- 2:
- .g.
- *
-
== r.j g
4-V ..
- !
-i
=E tu-g.. :$# e-33.g ' - .
2 2- $z ~- 2.:s.
K'
- 5
. . .. . , ' .,_:...,..._.;.....,..y..:.,.., ....:...... ....-...: . .,.. ..,, ~. . ....-......... s... . .... ...... ... . . . .. .
.. . ..,. - ....... . - - - .
- .
s . .. . .. .s .
.. = a.
. . . .
. . - 8 a._
um.
. . v.
. 8... 3 8 #. It --...- . v.2 .1 ? att. E . .' > . .. . >. e 3.
~.. ... . . sa.
. . ..=.
.,. .w . .. ..s u . -ea.
8.. u.
. -.a.- .u. 4 4.. 3.....e.. .,- .2.
. . .- -- . u- - - 8.
.. s2 .2 .- - . .s t , . .. . ... And s ., . . .. . . 8.3...3.
-..I.
. .. > .&.m.
. . - . ft., g~, 3".. .is
- .3 33.*I.1.
, < . > >.. . . . L Jd: .. I.. <m =.. 3.3.-78;
.c
" ... .-.3 ..... . - .. 3-, .- . - .... a.Esoz.I. ..- --. f. 3-t.
s.. ... ..., . . - .- . ... s.. . .. - . .-- .
, s
J.
. . .., .. s . . .: s .. , .. . - - . . 's i i E i.t i l : 1 1.: i t a
.c. - . . l g .. , . , I ' g-n .Ii y a s . 3:
. .- . e_.
- 3 Is:
. -..m...
_ m.
... % . 2<d...g s=
.
aj.g . . -.. . _ _ .;- .. .s , : . am si a = t.: . t-, . . m,.. .- .- . . . .. .: .- . ... ,f . . .- ... .. .s.
.. .
i.
j ., 3.
. a.. -- - . , -- . .a .e s
- , n.
1.
i .. , .. s.
. l . ,
. , _.
~ :.:..: , , - g . .. , . - - z.
. . - u . . . . . .. . . t
. =
==: - [ sa m . _3 [ g {.-. =h.a.
. < -- - .8.. =s, f ' - - - ., g.--...__ q E-3.g = .. . s. g.,,, , .
- 3 3.*x.
- 2 3.
b . . ^ .. E. >.d . < .. < A.
3.I... gg .
] .
.- D,..= .3 . .- .t
,, ,
. -r w~ s .. - - a, w' ad' &..W.. 5 ..
4 k 6, . - -
- ~;p: uEi '- -E--
- . u . . ,. .- .. .. . . _e .. .- . ..I .. . . .. u . -
.3 2g3 - .:ts E .S w tg
-
-
. l
.L
u . .. . .,z - -,
t
.
- .
to '8; - . Q 'a.
S -. -u- . t.
.:g... =. ... - - e g };g8 !.3 5**t t.-22
I e E.
.
- E2C 22:
'3]S: -
222 s
- -
fl:' 4.,".,, . 8.
v-CN ce ge to ':rs cc. a,- --C R --. a a a a w a . r2. - e i.
i. m i m. i m gm im e. J<.I.
.A du a: m m c:
e= <
< t . at : at.:j at.
,.1_ 2 gl* E2 3a H::
- . H a >c j H
H..H H H i- . -
.
. s. s.
- I
. , -..t.
$c
3.
. ., . .s.
, - . .. .. . . . .. .. - , .!- .-m .
.' :s . :s.
E.s,. 13 E.
e t - - . . - - .. . .- .- - . 5k?.M..-[-s~t.wm.m.,gn.,>..>. ;,pr.EA~,:.=.:p.?.,."n.. 3 ? Y W ?.: m.s - ~ ~ .. - .n. - m.a -.. . .:..215.y .g.':w,.,. -- e g. _ . . ,, r,
- - -...
.. . - . .- .. . .
- ,. 3.-~..-
.
. .2 .-.......v .. i ... .
- -+-.-am-e.
en.m4.
-4== h e g ww j
,. go ' - j 1JJ a, lnIl i< lIj.
. E- , . . .. * s - s
i-s r ' . m u i , a . . / 4, e m e c . C ot t . aet c- . . r C cnl . n t rrs O , r l ' ,. aus E uea t de y . coy E q.. o.
re suv n nr db y sCs l _ fls "f tn. ar-. n y sr-o- i s . at o yeeye u r adc o dfp r I ,.. mt soln ecre en n eou t ,M n., l e or tnot rwe. oe r - n l b p e i.
. u e s se o au k io a eogm it i r tto - n t namne u iStit scsw tl re ta usk C . i.ii sv ad toa t t aLn n sd al et ci s a ehAil l t wosms et oLf e vt b-t i e o oroni dfEy ti A n n,r - eys a n.Hhc ete m.Eetb f is t lw r e S on yd a se-iL Y ecrie crir lot eef ri abn l - b , vn 4.
ao nrevr h-hcewe Atey rtor e a P . ,,o ' ' i u Li t. s t tE go a e o ed es. reon rset rt tee f , to t e l l , e.w.,Wb- ! u s r e., otte onra e ew o r i , esfosl t t g eeu ts lo e . k' uuo osep . i g l . dtr ol m A 4'rlti seir sdld ptl s . r.
rieeife C C ail stte snle e. l - oeo e l \\ s ' mlo s . \\ _ r. th, - M8oa.t( L.Lefsr LoWE LCFf nf CTC L l ogvsd m O Osay. er4m eoee .a
- g
. L
.- ' {.
. tear ,~ r .- y ysl or -
i t . n e erh o '. . . . , . a I s ,- ,. -, s AlSoSf 1 3
- l I - .,- ~ - . - '
i.
- t' - . . e i , .t v.' t[n' ' .- e .t-syr Y .e.u es , > . tbt- +
F . ' . d.
k - - .
' . . . tt r pr - _ .
_ J E . o.
rre ' _ . d . au . tt ' s, h.ue h ca , l .,.. .rp , . . E ..,, CSl . rte . _ . ,
e.
. _ , ot - ... rf _ < ,; s i,- .ule t t .ea _ I S ps - , . - e - iey , . { ). . rtd t _
' 1(,, t.. Dt.
'L n ,.d r r. _ o as t - .. .page . 3g . iseSe . w.,.og t,e _ a D! r g t td nu g .leyot g . . t.
. .r eitte blie .
..: s ... rersar _ g . .n . irtatt afSeSs ' . _ e g t. g - n e eg . l s - i l i . e .' ' e tn relt s . . j-n ie etei - a L ,. .t: e-a l nup e C s . e ,. . s ect node p/ t.e .yl1 n bes - . oc8.l 8w r _ - s p l e F e o i aRn i .e pt . M e tde e q n.d ande rt r n t s r g . e e n.
t.C t l n Iem tant ei i o .. ert e r r l s f i .eer e suw od e en t .l.., eto pedr se o a / r _ . .f-ae t , a rt ie hcl oref e e ,.l r et s a' luF nuto te w t _ e .s .ip .e re se rr ejs ps .r e . t s - t ri t n er ttn rnno ui . . ot . v AD pA sSI tiIt Rl e P . a . o d. c . eirs ein
g g - - ese
7
8 sl
.g
2
2 .at . ..li _ icd m e _ . e - m g _ .de O B B B B .g B _ s . ts _ Tu - _ .e C U A A A A d . p . o. e i At e _ l e n p . I T T T T _ e y t t i g' . i.nc . r a l R
S . ,t i ut a n e l e r i pe e -
itg I . i - e m is s l r . ., n 'e a, Pt i , ~ . y e ree S ,e e s igm E , , a l' nl 8p - h i t t c' . . o g /oE 'o A n a r a oo - rc . l t i.
, W Cs I eer , I _ .. tR.e ' ,>: i
. . _ ' . i .. ,V } ', - h 4.a,.; J 'C7,I t4t ' 3.~- - ',, ',". cT 3 ,,.: '
- .
' - ' . J - . .
. - .j,.,- ,' 1i'
i ,-}i il:!} ,i* '.;.. A f(I - lt!llill t !
S __IdEggy_gE_NyC(E66_EgWE6_E(@NI_QEEE@IlgNt_F(ylgSt_@Ng PAGE
t
IugRdQQYN@dlCS " ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
. ANSWER 5.01 (2.50) a.
False b.
False (concentration changes with life but not reactivity) c. True d.
True e.
False; True with appropriate explanation (0.5) ea.
REFERENCE BV2 LP-RT-7 pg 3-9 EO 1,2,4,7,B,10 001/000 K5.33 3.2/3.5 001/000 K5.34 2.1/2.2 001/000 K5.35 2.1/2.3 OO1000K533 OO1000K534 OO1000K535 ...(KA*S) ANSWER 5.02 (3.00) a.
rho = (152 steps - 120 steps) X 6 pcm/ step CO.63 192 pcm CO.23 = SUR = 26 X Crho X lambda / (Beff - rho)] CO.63 = 26 X C192 pcm X O.1/sec / FW>b pcm - 192 pcm)3 CO.43 = ^ "i 3PM (g,C) CO.23 . l.07 b.
Tave would be higher CO.33 since MTC is larger at EOL. [0.73 REFERENCE BV2 LP-RT-5, pg B EO 6,7 001/000 K5.47 2.9/3.4 OO1000K547 ...(KA'S) i lL______-__-_ - _ _ _ _ - _ _.
m ___mmmmm_m _ memm_e____e___e_me_m m __me_m_emesemm_mem __ _- _ , o ISEBUQDYN@dlCS ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
- ANSWER 5.03 (2.50)
a.
It becomes more negative (0.3) g)ghp = j Increasing temperature reduces b;ren density in the core. This reduces t h e-
b::r;t i aa and-edd= a n= i + 4 v= e=="+4"ity t: the c e.
(0.7) MM (A W 4 AfTC f) M q g g b.
547 F (0.3) The change in density at higher temperature is much greater than at lower temperature. So more boron atoms enter or leave the core at higher temperatures which causes a larger reactivity change f or a given temper-ature change. (0.7) c.
Lowering boron concentration over life makes MTC more negative which causes its contribution to power def ect to increase. Hence power, defect increases. (0.5) REFERENCE BV2 LP-RT-6, pg 6,13 EO 1,2,11 , 001/000 K5.15 3.4/3.7 001/000 K5.49 3.4/3.7 OO1000K515 OO1000K549 ...(KA'S) ANSWER 5.04 (3.00) a.
(The excess steam flow causes) Tave to decrease CO.253 which inserts posi tive reactivity CO.253, ower increases. CO.25] (At the POAH) increased power will increas perature which inserts negative reactivity via the FTC.
CO.5 Power will stabilize higher than POAH CO.253 and Tave will be lower than the no-load value (minus the number of degrees needed to overcome FTC).
CO.253 b.
SUR is higher at EOL CO.253 because of a smaller Beta-eff CO.53 Final power is the same CO.253 since the steam demand of one steam dump does not change over life. CO.53 F2 ; - " T C.- *- REFERENCE BV2 LP-RT-6 pg 6,8,13 EO 2,4,11 001/000 K5.29 3.7/3.9 l _ -___ - -
ws__ euw-meuew-me-eemwmeaamee-a-meseseu---e -- -
- .
ANSWERS -- BEAVER VALLEY 2-87/05/19-BAREER, S.
- OO1000K529
...(KA'S) . , ANSWER 5.05 (2.50) /
& NfA nJ D a.
It increases (0.3) since RCS boron concentration is increased (0.7) 6.
No change (0.5) the actual stuck rod worth is added to the TS limit to raise the minimum allowable SDM (1.0) REFERENCE BV2 LP-RT-9 pg 4,6,7 EO 2,5 001/010 K5.35 3.3/3.6 004/000 K5.19 3.5/3.9 OO1010K535 OO4000K519 ...(KA'S) l ANSWER 5.06 (2.00) a.
Loading a fuel assembly into the core close to a neutron detector increases the fraction of neutrons in the core reaching the detector.
The detector count' rate increases more than the core neutron population increases CO.253. Criticality is under predicted CO.253.
j b.
The detector will not see neutrons until there are a great number.
, CO.253 Criticality is over predicted. CO.253 l c.
The initial count rate is too high and the detector is insensitive to i core changes. [0.253 Criticality is over predicted. CO.253 j d.
The detector will not see neutrons until there are a greater number CO.253 Criticality is over predicted. CO 253 REFERENCE BV2 LP-RT-5, pg 15 EO 12 001/010 KS.16 2.9/3.5 ______ ___ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ -. _ _ ___ _ _____ _ ___ _ _ j
seem em=- _me-mem-eo_esuss_eeum_sasseus_uuu --- m.
!. e , ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
' ANSWER 5.07 (3.00)
1.
Reactor power (0.3).
Increasing reactor power results in increased heat flux and DNBR decreases. (0.7) 2.
Temperature (0.3).
If pressure is held constant and Tave is increased, subcooling will decrease.
Therefore the heat flux required to reach DNB will decrease and the DNBR will decrease. (0.7) 3.
Pressurizer pressure (0.3).
If Tave is held constant and pressure increased, subcooling increases and DNBR increases. (0.7) ] REFERENCE BV2 LP-TMO-7 pg 26 EO 11,12 Comp HX 3.2/3.5 ANSWER 5.08 (2.00) a.
Subcooling is based on core exit T/Cs or hot leg RTD readings CO.23 During natural circulation the mass of metal in the head can' retain and keep local temperatures above saturation Co.53 The temperature ' indicators would not reflect this local saturated condition CO.33 b.
Pressurizer. level decreases CO.43 because the pressurizer pressure increase will compress the vessel void and force water out of the pressurizer. [0.63 REFERENCE BV2 LP-TMO-7 pg 12, 29-34 EO
000/074 EA2.05 3.4/4.2 000/074 EA2.07 4.1/4.7 OOOO74A205 OOOO74A207 ...(KA'S) __._____ _-__ -
~~Ybhhbhh$bbb$hh , , ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
! . ANSWER 5.09 (2.50) a.
Perform a heat balance calculation across the regenerative heat exchanger by using delta T across both side of HX and letdown flow Flow = L/D F1qwg's.4) charging flow rgte.
OR Chg.
rate to determ Injectiodha% th Tavg. and Pzr. levolk?*2) + Seal Leakof Seal constant CS --* c' dr---=== a' VCT 1:v:1 "!'h -- rt;..t T v: er "" - - - r u-i - -' i=u=1 - - (Any single method 1.0 each) b.
1.
Increase (0.2) as the slower pump speed will decrease friction head (0.3) , 2.
Increase (0.2) as RCS pressure has increased. [0.33 3.
Increase (0.2) as pump inlet temp. has decreased. (0.3) REFERENCE , i BV2 LP-TMO-4 pg 6,7 EO 3,8
Comp pump-centr.
3.4/3.6 ANSWER 5.10 (2.00) a.
Very small error (0.3) the enthalpy change of steam at operating pressure for a 20 psi pressure change is insignificant. (0.7) b.
A correction factor is used to calculate RCP heat (27.3 x 10E6 BTU /hr correction factor) (1.0) REFERENCE BV2 LP-TMO-6 pg 18,19 EO
015/000 K5.03 3.2/2.6 015/000 K5.04 2.6/3.1 015000K503 015000K504 ...(KA'S) - _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ - _ - _ _.
wa.__ww=a-a-asawa-amae-won-n----nu-n-a-enn----=-enenma ' ' ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
. ' ' ~ i t
. ANSWER 6.01 (3.25) a.
Motor driven-Lo-lo level in 2 of 3 S/Gs Trip of all running MFW pumps.
SI bea4- ^t-6 Diesel loading quence (Blackout) TDAFW stm supply open for a time period with low discharge pressure 5 items (0.25) ea.
Turbine driven-Lo-lo level in any S/G's.
UV on 2/3 RCP busses.
2 items (0.25) ea.
, b.
The recirc valve opens.
(0.5) c.
Flow is limited to a preset value (310 gpm) (0.5) Cavitating venturi limits flow (0.5) REFERENCE BV2 OM 24, Sect. 2.24.1, pg 3,29 2LP-SGS-24.1 EO 4,7 061/000 K4.02 4.5/4.6 061/000 K4.04 3.1/3.4 i i ) I - ___ _ ____- ________ - _ - _ _ _ _.. - _ _ a
ws___wuu__semazeemeeeeeuecese_osesemcemeeemmemes weeem -- --, ' ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
l
- = *
l t l . ANSWER 6.02 (2.75) , a.
BORATE, DILUTION, and ALTERNATE DILUTION (0.33 ea) l (Accept MANUAL for no credit) j b.
Batch integrator (0.5) c.
1.
Initiated by VCT low level.
(0.25) l 2.
Auto Actions , o Boric acid transfer pump starts o Makeup water stop to chg pump suction opens (2CHS*FCV1138) j o PG water flow control valve opens (2CHS*FCV114A) l o BA flow control valve opens (2CHS*FCV113A) (0.25 ea) J REFERENCE BV2 OM 7 pg 7,8,70 2LP-SGS-7.1 EO B 004/000 K1.06 3.1/3.1 004/000 A3.01 3.5/3.7 l l I ANSWER 6.03 (3.00) a.
Select DN position for the live bus transfer switch (0.5) b.
Both supply breakers are locked out. (0.5) c.
Clear the fault (0.5) and reset the lockout relay (0.5) d.
Bus UV (0.5) Sustained bus UV (0.5) REFERENCE BV2 OM 36, Sect. 2.36.1, pg 53 2LP-SOS-36.1 EO 4,11,12 062/000 K4.01 2.6/3.2 062/000 A2.12 3.2/3.6 _. _ _ _ _ _
usmmme__somesseesmeeeeeeameeeemsesmsuemesemmeueuausume - ~ - m, - ... ' ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
' , ! ! ' l ANSWER 6.04 (2.50) a.
WR RCS Pressure (2-RCS-PT403 & 402) (0.5) WR RCS Hot (0.25) and Cold (0.25) Leg temperatures bd if W d5 M M b. Both40PS PORV M 455C & M will openg(0.4) [ (} Since auctioneered low Tc f ails low the calculated lif t setpo: t will drop to minimum (0.6) c.
No response (auctioneered low Tc is the input) (0.5) REFERENCE BV2 LP-SGS-6.2 pg 14 OM 6 fig 6.45 EO
010/000 K4.03 3.8/4.1 010/000 A2.03 4.1/4.2 010000A203 010000K402 ...(KA*S) ANSWER 6.05 (2.50) a.
True b.
False Cc. Fals @ h d.
True e.
False (0.5 ea) REFERENCE BV2 LP-SQS-11.1 pg 3 EO O 013/000 K4.01 3.9/4.3 013/000 K4.12 3.7/3.9 013OOOK401 013OOOK412 ...(KA'S) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ -.___J
w=- www-w x aus-weseawa-aaua-aaa-waa-awa--a-aaawaeew -- -- -
' ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
! ! ! ' i I ANSWER 6.06 ( 50) & K W , a.
During. LOCm when RCS pressure is above the shutoff head of the LHSI pu (^.3; - . dh 0 i b.
Insufficient iodine removal could cause offsite doses to exceed 10CFR100 limi ts. (0.5) ! Excessively low sump pH could cause excessive corrosion of entmt materials (0.25) which may cause excessive H2 generation. (0.25) {O*&'not {Cs1)4L .. 20,- if a CIB signal is present.
sv.C, c.
No I REFERENCE BV2 LP-SGS-13.1 pg 5,6,26,27,39 . , I EO 1,14,16 ! ! 000/011 EA1.11 4.2/4.2 ! ! 000/011 EK3.13 3.8/4.2 ) OOOO11A111 OOOO11K313 ...(KA'S) ! l l ANSWER 6.07 (3.00) l a.
Protect against a rod drop (0,5) or rod ejection accident. (0.5) i l l b.
PR low level reactor trip (0.5 and IR high level reactor trip (0.5) l I l c. Auto blocks the the high SR reactor trip (0,5) and prevents , l energizing SR high voltage. (0.5) l i REFERENCE l i BV2 2LP-SQS-2.2 pg 20 i ' I i ! EO 4,5 ! 015/000 K1.01 4.1/4.2 l' 015/000 K4.07 3.7/3.8 i l l . - _. __ _
wz__us== _usw;wu=_w=uswaw_sse _saw _sm_amemmem_eem - ---
ANSWERS -- BEAVER VALLEY 2 .~87/05/19-BARBER, S.
j
. ANSWER 6.08 (2.00) a.
Stops 2HVQ-FN214B (0.25) and starts 2HVQ-214A on low radiation. (0.25) Stops 2HVQ-214A on high radiation. (0.25) l b. Closes 2HVR-MOD 23A (0.25) and 2HVR-MOD 25A (0.25) l c.
Isolates tho' control room (0.25) and initiates control room air pressurization system (0.25) and starts thk 60 minute TD for the emergency supply fan. (0.25) j REFERENCE j BV2 OM 43 pg 76,81,95 I l J EO
j 073/000 K4.01 4.0/4.3 i ANSWER 6.09 (3.50) a.
15.5 7.
(O.4) 0.8) Protects against a loss of heat sink ( in the event of a ' . sustained Wf/Ws mismatch insufficient to activate the low level trip. "^"'-(,0J) I b.
Low RCS pressure 1845 psig (0.4) Low MS line pressure 500 psig (0.4) High cntet pressure 1.5 psig (0.4) Protects the core against a LOCA (0.8) REFERENCE BV2 OM 1 pg 8,9 EO
012/000 A3.06 3.7/3.7 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _l
eemm _ me-mme_memm_mommmmee_ mmememeemsemuse - - 880196001G06_QQN16Q( ' . <-+ ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
j --4
. l l l ANSWER 7.01 (2.50) a.
True b.
True i c. False i d.
False l e.
True REFERENCE l l BV2 2LP-FHP-1.0 pg 4,28,31,44,47 ' i EO 8,9,12 l 034/000 A1.01 2.4/3.2 034/000 A3.01 2.5/3.1 034/000 GEN 7 2.9/3.7 ANSWER 7.02 (2.50) a.
1.25 Rem /qtr (0.5) b.
To search for or remove injured personnel (0.5) or prevent conditions that would probably injure numbers ofL - .p l e. (0.5) peo ' jgQ et y4g , 6.0)' c. Occupational exposure history (0.4) N -' If provided it allows an increase in the quarterly WB ex sure limit from 1.25 Rem /qtr to 3.0 Rem /qtr. (0.6) REFERENCE BV2 RCM pg 6,9 PLT GEN
3.4/3.9 PLT GEN
3.4/3.7 l l l l l l
___
$$h[ $ $$$$CNNb!NNb < ,. , a ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
.' l ANSWER 7.03 (3.00) + . W &k Y & a.
Steps m+e44be perf ormed Msequence (O. 5) .1;_ eng,.. 1y oi i A N 65 P h-~ ir n (0.5) ^ l b.
2F (0.5) 5'/. per minute (0.5) c. Chemistry must sample (0.5) for iodine. (0.5) REFERENCE BV2 OM 52 pg 1, B1, B2 PLT GEN 7 3.5/4.0 PLT GEN 12 3.4/3.3 l . ANSWER 7.04 (2.00) a.
Turbine runback (OTdt or OPdt) (0.5) b. Emergency boration (0.5) M b0 M N s M l c.
Trip the reactor (0,5) and go to E-O (0.5) fj p REFERENCE /g ff, l BV2 OM 53C AOP-2.1.3 pg 1 OM 1 pg AAM1 001/000 A1.04 3.7/3.9 001/000 A3.02 3.7/3.6 ANSWER 7.05 (2.50) a.
Natural circulation (0.5) using the TDAFW pump to feed (0.25) and the Atmospherics to dump steam (0.25) b.
Minimize RCS inventory loss (0.5) c.
No CD rate applies (0.3) pressure is dropped rapidly to
minimize the inventory loss (0.7) REFERENCE BV2 Exam Bank Question 7-3 BV2 OMS 3B pg 102 _ _ _ _ _ - - _ _ - - - - - - --- ---- _ --- -_ - ------- -- - - - --
- $bh[h(hb$hhb_Nhb!!bb ,. s. ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
000/055 K3.02 4.3/4.6 . l ANSWER 7.06 (3.00) a.
1.
Manually'or locally trip the turbine 2.
Runback the turbine Close the MS trip,lapd bypass valvesG)?) 3 items (0.4) ea 3.
Wi / sequence (0.3) b.
Intermediate high cntmt pressure (3.0 psig) i Low stm line pres (500 psig) Stm line high rate of change (100 psig in 50 secs) Any 2 (0.5) es.
c. Monitor RSS pumps f or cavitation (0.5) REFERENCE i BV2 E-0, pg 3,7,8 000/007 EK3.01 4.0/4.6 SYS GEN
4.4/4.5 ANSWER 7.07 (3.50) a.
1. Unexpected increase in S/G NR level 2. High radiation from a S/G sample 3. High radiation f rom a steam line rad monitor 4. Hi gh ra,,di ati on f r om a S/G bl owdown moni tor Any 3 (0.5) ea.
b.
1 Chg/HHSI pump running (0.3) and RCS/Stm Line DP < 145 psid (0.3)
or Loss of CCP flow (0.4) ! c. When it is needed for RCS cooldown (1.0) REFERENCE BV2 E-3, pg 3,6 000/038 EA2.02 4.5/4.8 EA2.03 4.4/4.6 .
~5bhIbbbbIb5(_bbbI5hb ~~ ~"~ ~ .. .,, l ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
l l l ' . ANSWER 7.08 (2.50) , l a.
350 F (0.5) 425 psig (0.5)
(0.5) Shutdown the pump $ W b.
. & fft Exclude air 4 (0.5) and to prevent the formation of an explosive c.
hydrogen / oxygen mixture (0.5) l REFERENCE BV2 OM 6 Sect 2.6.2 pg 1, 5,
! 002/020 SYS GEN 7 3.7/4.3 ANSWER 7.09 (1.50) I Normal LD isolates Comp. cool. to Excess LD HX isolates i ' TDAFW pump starts (0.5 ea) I REFERENCE l BV2 OM 53C AOP-2.39.4 pg 1 l l 000/058 K3.02 4.0/4.2 l l ANSWER 7.10 (2.00) . '
a.
Low steamline pressure SI. (0.5) l b.
Yes (0.5) c. Cooldown rate s ws (0.5) and power rise slows (0.5) REFEREN
l) BV2 Accid. Trans. Analy. LP pg 11 j{ EO 5,6 i
000/040 K1.02 3.2/3.6 000/040 K1.05 4.1/4.4 000/040 K3.02 4.4/4.4 l l _ _ _ _ _. _ _ _ _ _ _.. _. _ _ _... _.. _. _. _. _. __
es--========uw u =-wasmewanemonaaaaa-aaaaw--un-n--n---aaua '" ANSWERS -- BEAVER _ VALLEY 2-87/05/19-BARBER,= S.
'* * "
.' ANSWER 8.01 (2.00) a.
A b.
B c.
D' . G. 8 LO.5 an d h &kC W ' ' REFERENCE SV2 TS pg 6-1, 6-5 PLT GEN 23 2.8/3.5 ANSWER 8.02 (2.50) a.
NSS (0.5) b.
NSOF (0.5) c.
NSDS (0.5) d.
NSS (0.5) e.
Plant Manager or his designated alternate (0.5) REFERENCE BV2 OM 48, Sect. 1/2.48.1, Procedure A, pg 4,5,12 BV2 EPP, pg 3-3 PLT GEN
2.8/3.5 ANSWER B.03 (2.50) a.
Plant Manager (0.5) b.
During an emergency (0.6) to protect public health and safety-(0.6) when no action consistent with TS is immediately apparent. (0.6) The NRC should be notified (0.2) REFERENCE BV2 OM 48 E pg
BV2 OM 48 F pgs 2-5 - BV2 TS 6.6a pg 6-13 PLT GEN
3.9 PLT GEN
3.8 2LP-SQS-48.1 EO 2,
- _
___ossususseeeeeee - - - e - eeeeeeee - cewe meweew_ _ - --
- "# ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER,.S.
- t^
,' ANSWER 8.04 (1.50) No to.53 (each test is within 25% of the required. time interval) the three consecutive combined test intervals. exceed 3.25 of the required interval C1.03.
REFERENCE BV2-TS Sect. 4.0.2 , -l 064/050 SYS. GEN 8 3.4/4.4 ANSWER 8.05 (3.00) a.
No emergency classification (0.5) Aircraft does not crash on site (0.25) I b.
Site Area Emergency (0.5) Total loss of offsite power.and loss of all onsite power f or greater than 15 minutes (0.25) c. Unusual event (0.5) due to transport of contaminated individual from ' onsite to an offsite hospital (0.25) d.
General Emergency (0.5) LOCA greater than MU capacity subsequent failure of ECCS components and containment f ailure likely. (0.25) GRADER'S NOTE: GIVE HALF CREDIT IF EVENT.IS CLASSIFIED ONE LEVEL HIGHER AND APPROPRIATE JUSTIFICATION EXISTS FOR THE CLASSIFICATION REFERENCE CY, Emergency Action Level Classification Guide, pg 17-21 PWG36 2.9/4.7 ANSWER 8.06 (3.00) , a.
3.6.3.1.
(containment isolation valves actions), 3.0.4 (cannot continue startup since can' t change modes by rel ying on action statements) (0.5 ea) b.
3.3.3.5 (remote shutdown moni toring) (1.0) c.
3.7.7.1.b (control room habitability) (4.7.7.2.a specifies pressure requirement 1825 psig) (1.0) REFERENCE BV2 Technical Specifications
BV2 OM 2 pg 2.10.1 I l f L----_-_ _ - - - - - - _ _ _- _ - - _ - - _ m
8___0901NISIB011VE_P6QCEQyBEst_CQ@QlllgNS _@@Q_(ld11@IlgNS PAGE
t "hNSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
.
103/000 SYS GEN 8 3.5/4.2 . ANSWER 8.07 (2.50) a.diaximum 90 day perio Reviewed by usu 0.5-Approved by the Plant Manager (0 34-pts each) b.
The intent of the original procedure is not altered The change is approved by two members of the plant management staff, at least one of whom holds an SRO license on the affected unit The change is documented, reviewed by the OSC and approved.by the Plant Manager within 14 days of implementation (0.33 pts each) c. NSS or NSOS (0.5) REFERENCE BV2 OM 48 B pg 5 C pg 4 PLT GEN 23 3.5 2LP-SQS-48.1 EO 12, 15 ANSWER 8.08 (2.00) A caution tag shall be posted on the control switches of the containment ventilation system (0.5).
Posting of the caution tag shall be entered in the Caution Tag LOG (0.5), the ref ueling shif t supervisors daily log or status board (0.5) and on the NSS's log sheet or status board (0.5).
REFERENCE BV2.ON 48 8 pg 3 PLT GEN
3.8
4.0 2LP-SQS-48.1 EO 19
ww__uwuu2awawauuammmmmmmmmmmmummmmmmmemommmememmmmemmsemmo -- . I '* * '# * ANSWERS -- BEAVER VALLEY 2-87/05/19-BARBER, S.
- A
. ANSWER 8.09 (1.50) ' Va";e (w - & sisted uit% A eca Wss**~) c. False (0.5 ea) REFERENCE' 'BV2 OM 4BB pg 7,8 PLT GEN 23 2.8/3.5 ANSWER 8.10 (2.50) j I a.
Action of T.S. 3.0.3 b.
Action of T.S.
3.0.5 REFERENCE BV2 Technical Specifications 006/050 SYS GEN 8 3.6/4.4 ANSWER B.11 (2.00) NO, the only applicable tech spec is 3.9.8. 2 (4,4NL(requi res two loops of RHR in mode 6 when water level is less than 23 f eet above the flange) f or which the provisions of - l 3.0.3 are not applicable. t '.O! t.
DO) REFERENCE BV2 Technical Specifications 005/000 SYS GEN 8 3.3/4.2 i s I k
1 A7TACF]hg,qy g \\ , l Unit 2 Reactor Operator j , Written Examination C g. ants j i Administered 5/19/87 i
j QUESTION OJfEEtfI' ] 1.Olb Question is unclear, several interpretations are possible by candidate. Question could be asking to: (1) campare Sad calculated with actual SII4 (with one stuck rod); (2) campare SD4 with and without stuck red; or (3) know that if a rod is stuck you must increase the required SD4. The answer key should allow for these interpretation.
1.07 Answers 2, 3, 4 are incorrect. They should be, 2) more negative, 3) Inore negative, 4) less negative. Proof is in Chapter 6, Rx Theory Manual, page 42, see attached.
l l 2.02 NRC answer key is correct. Withdraw prior review comments.
2.03b This answer should be HZP. The Unit 1 requalification exam has the identical question (2.06.B) with the correct HZP answer.
i 2.05c The question does not state the detector is out of storage when the leak occurs. Therefore, there should be no points assigned for saying place det. in storage give entire 1 pt for saying manually close the isolation valve.
2.07b The answer key should also accept a e h correct answer: l Boron plating in the fuel racks. Attached FSAR 9.1-5 will verify this.
2.08a The answer key lists one of the reasons for having RIL as l " limit the potential effects of rod misalignment". The key I should also accept " minimize the effects of an ejected red" as a correct statement. Proof is in FSAR Accident Analysis.
(See attached pages FSAR 15.4-33, 34).
2.09b The answer key should also accept the answer "for temperature, pressure, boron concentration equalization on RHR system startup".
(See attached Chapter 10, Procedure A). l l
_ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ - l
3 Unit 2 Reactor Operator i Written Examination Cw aircs ' Mministered 5/19/87 (continued) CUESTION COMMEtTT l 2.09c The answer key states that the seal return relief valve goes to the PRI ard the VCT.
It actually goes to only the PRT.
(See attached system print 7-3A for verification). , i I 2.10c Answer key states that TCV-2CC-100 will open. It should state that it will close. The reason it will close is that the lowering of system pressure reduces flw rate through camponents and will result in the CCP system temperature trending up. The TCV would close in response to this, forcing j more CCP flw through the heat exchanger.
(See attached OM l Figum 15-1). ! ! 3.01 The answer given for this question only applies if both level transmitters 112 and 115 failed 1 m, because the logic to cause charging pump suction to swap to the RWST is 2/2 not 1/2. The correct answers are supplied on attachment if either LT-112 or 115 fails low. Icgics from CM-7 are also supplied.
3.04a A2 should be deleted from the test.
It is the same question which was deleted on a previous test (a 7.5%/ min. ramp down of turbine for 10 minutes will not arm the steam dumps). A4 on the answer key states the Steam Dumps would be armed. In , reality, they would be armed ard actuated twee the Reactor l Trip controller has a O' deadband.
(See attached ! documentation).
I l 3.04c Another solution that will prevent the steam dumps from opening is to take the Steam Dump control switches to OFF.
(See attached logic diagram).
3.05c Answer CCP is only applicable if the ESF actuation is a CIB.
The question is not specific as to what type of ESF signal is in, so the CCP pumps should not be a required answer.
An alternative answer to this question should be no pumps will start since the Diesel Generator starts on ESF signal (SI), but will not load unless an undervoltage also occurs. This s should be added to the answer key as an acceptable answer.
, ' Diesel Start and Output Bmaker Ingics are included.
l l .-
.o , Unit 2 Reactor Operator Written Examination Comments Administerai 5/19/87 ) (continued) OUESTION C m 4EtTT a 3.06 m e question never state whether the RID which fails is a orotection or a control channel.
If the student assumes a } protection channel has failed, there would be no change to any ] of the parameters. mis should be a valid answer if the student states his assumption that failure is to the protection channel. For future questions of this type, the question should state what has failed (i.e., control or protection).
3.07 h is question should be withdrawn because it is not required operator knowledge. The answer is found in AOP's Follow-Up Actions in three separate NOTES.
(Examples attached).
3.10c Tnis question should be deleted. Question deleted from the SRO exam.
4.02c h e answer key should also include the possible answer that the Rx is tripped and E-0 should be implemented. his could happen if the first failed channel's bistables were tripped within 5 minutes. mis situation would be possible if an I&C technician was in the cuulwl room when the first failure occurred, or if no I&C technician was available, this function would be performed by operations.
4.08 2e answer supplied to this question is correct for 1.
However, Unit 2's Adverse Cnmt is defined as 105 R/hr rad level or Cteff press > 1.5 psig.
(See attached documentation). he question asked for three (3) answers, and there are only two. W erefore, the students should not be penalized for adding a third answer. Answer key references a Unit 1 Lesson Plan.
4.11b he answer key should also accept the wording the Stations Integrity Status Tree uses, "All RCS Pressure - Cold Ing Temperature points to the left of Limit A line".
(See attached Status Tree). 4.13b his should be deleted from the test because no answer is correct. The answer is, "as long as is stated on the cover sheet". Question deleted from SRO exam.
- .
_ _ _ _ _ _ _ _ _ _ _ _. _ l
l
Unit 2 Senior Reactor Operator Written Examination Comments Mministered 5/19/87 l OUESTION COMMENT 5.02a Change the value of Beff to 660 pcm instead of 700 pcm. This will change calculated SUR to 1.069 DH4.
Reference: BVPS-2 Core Maysics Para:reter (Projected Values) VIII, attached.
5.03a change explanation to: " Greater density decrease per l'F increase at higher temperature, therefore greater loss of moderation aM MIC will be more negative."
Reference: Reactor Theory Text, Chapter 6, page 16 (attached).
5.04b Delete last line of answer, " larger MIC".
This is a typo.
l 5.05a Change explanation to "since control rods will be more with-drawn at the same power and Tave."
5.05b Question is unclear. Several interpretations are possible. Is the question asking the student to: 1.
Campare SD4 calculated with acblal SD4 (with one stuck red).
! 2.
Campare SI24 with aM without stuck rod.
l 3.
Know if a rcd is stuck you must increase the required SI24.
The answer key should accept other reasonable explanations.
5.06d If the detector is too far from the source, the answer key is correct unless the detector is close to the fuel being loaded. In this case, the answer to 5.06a is correct.
Therefore, the following answers should be acceptable: 1.
Under predict if the explanation given in 5.06a is used.
2.
Over predict if the explanation given in 5.06d is used.
_ _ - _.
- - - - - - _ _ - _ _ _ , .-
Unit 2 Senior Reactor Operator A Written Examination Cum d a - Mministered 5/19/87 y (continued) ' CUESTION 029 err .] 5.09a Delete the following fr a the answer key: 'M rate of decrease of VCr level with constant Tave or pressurizer level." 'Ihis method will not work.
. 6.01a For the motor-driven auxiliary feedwater pumps, the answer. . states, "SI train A", this will only start the A pump. The answer should be Safety Injection Signal.' l 6.04b Only ops PCRV 455C will be affected since auctioneered low 'Ib inputs to its lift setpoint.
ops ICRV 456 will not be affected since auctioneered low TH is the temperature input to its setpoint.
Also, 455C will not lift unless RCS pressure is above minimum setpoint pressure of approx. 450 psig.
(See attached figures).
6.05c Question is poorly worded. It could be interpreted as low pressurizer pressure SI is blocked and NSLI is blocked -(low s&a=1ine pressure SI and NSLI, since this is the only NSE that can be blocked) which would make the statement true.
Since a situation was presented in the questicrt that could not possibly exist, the question is invalid and should be deleted.
6.06a See attached page 39 of 2IP-SQS-13.1. Oceanents in r3ght column are Unit 1 differences. Column on left states during reciru11ation phase the IHSI pumps are stopped and the recirullation spray pumps supply the HHSI pungs.
6.06b.
See attached page 6.
Second part of answer states, "which may cause excessive H2 generation." Page 6 states NaOH will react with Al and Zn to increase H2 generation. If NaCH is not added, actual H2 generation will decrease. 'Ihe last part of the answer should be deleted.
. _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ - -
, " . Unit 2 Senior Reactor Operator {
Written Examination Comments Aininistered 5/19/87 (continued) a acESTroN OMERP l 6.08a Question only asks for automatic actions on a high radiation . alarm setpoint. Answer requires alert ard high actions for L full credit. Mark numbers should not be required for full credit. Filter exhaust fans for [21rQ-FN214A] ard containment surge supply and exhaust dampers for [2HVR-MOD 23A] and [2HVR- . MOD 25A] should be given credit. The first half of the answer f should be deleted since these are not actions initiated by a high alarm.
6.09a The answer key implies that the low-low SG level trip is a backup to the Stean/ Feed Flow Mismatch and Iow SG Isvel trip.
This is not the case. The Iow-Iow level trip is the primary protection for loss of heat sink. The misratch trip is redundant to this trip and is not a m maa to function in the accident analyses. See attachment from the BV-2 Tech Specs.
Full credit should be given for saying, " Protection against loss of heat sink."
7.01c CEP-2-75-57M (Site Receipt and Handling of New Fuel Asse:rbly and Their Shipping Containers) states that if the load cell reading exceeds 200 pounds when inserting a fuel assembly into a fixture reverse direction, lift the fuel assembly imtil it is clear of the fixture. This question should be deleted since there is no one correct answer.
7.02a This question asked for a special exception to the quarterly dose limits. This is not required to be known from memory by a Shift Supervisor. It is the Radeon Department's responsi-bility. That is why the limit is in the Radeon Manual. If an i 18 year old operator ever showed up for work in the Control Room and the Shift Supervisor needed to know his exposure limit, he could either ask Radcon or look it up. There would l be no urgency that would require him to know the limit from ' memory. This question should be deleted.
7.02b " Life-saving actions" should be an acceptable answer for full credit for this question. Both of the statements on the key , are life-saving actions. Refer to the attachment from EPP/IP ) 5.3, " Emergency Exposure Criteria and Control".
l i !
_ _ _ _ _ _ _ - - _ _ _ . l l l Unit 2 Senior Reactor Operator
Written Examination Cun wuls Administered 5/19/87 (continued) CUESTION OMWT 7.03a 'Ihe answer should be, " Steps may be performed out of sequence at the discretion of the Nuclear Shift Supervisor." The state-ment referenced in t.he k*y frun 01-52 is in error and paperwork will be subnitted to have it changed. Refer to the attachments frm CH-48, 50 and 51.
l 7.03b&c These question require that parts of procedures that are 7.04c required to be present and'followed when performing an 7.08a&b operation be lepE@M fra memory. Operators at Beaver Valley are not required to memorize these procedures. Relying on memory leads to mistakes. Since this is not required know-ledge, these questions should be deleted.
7.04a A load rejection would also cause a continuous bank insertion airl should be acceptable for full credit.
i 7.08c One reason for excluding air frm the PRT is to prevent corrosion. 'Ihis should be an accettable answer.
7.10c MSIV closure also limits the magnitude of the cooldown and power rise. 'Ihese should also be acceptable answers.
. a
8.01a Other answers should be accepted with sufficient justification relative to fire brigade manning.
l l l 8.01d Delete question frm exam since no correct answers were given as choices as per Page 6-5 of Unit 2 Tech Spec (attaclud).
l l 8.07a Maximum period of 90 days should be deleted frun key since the time period can be anythirg.
(Reference attached page 4, Chapter 48.2, Procedure B, Item B.2).
8.08 Accept placing jumpers / lifted lead tag and logging them as an acceptable answer since more details in question would be required. 'Ihis question appeared on the Unit 2 NRC SBO Exami-nation administered on 1/27/87 and this ccument was considered durity grading as per Examination Report No. 50-412/87-06 (OL). l .J
, .... .. .. . .......... .. . .... .. . ...,
Unit 2 Senior Reactor Operator
Written Examination Cwm.edw Administered 5/19/07 (continued) wESTION CCMNr 8.09b Answer could be true if pennission granted by RO to silence (as per attached Procedure B of CH-1/2.48.1, page 8). 8.10a&b Since the question asks for all action statements that should be considered, consideration should be given during grading for applicable action statements not listed on the answer key.
_ _ _ a_ _ - ..
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ _ _ . ' l l t ATTACHMENT 4 , NRC RESOLUTION OF FACILITY COMMENTS i 1.01b See Resolution for Question 5.05b.
1.07 Accept comment.
l
2.03b Accept comment.
2.05c Accept comment.
Manually close isolation valves for full credit.
2.07b Accept comment.
Boron plating in racks as alternate answer.
2.08a Accept comment.
I 2.09b Accept comment.
2.09c Accept comment.
2.10c Accept comment.
3.01 Accept comment.
3.04a.2 Do not accept comment.
Question was adequately modified based on previous exam review.
I 3.04a.4 Accept arm and actuate for answer.
i 3.04c Accept comment.
3.05c Accept comment.
Grade according to assumption.
3.06 Considered during grading.
3.07 Do not accept comment.
This question asks systems know-ledge: fail position of valves on a loss of instrument air.
I i I l I
l ! l
l
, _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ [. Attachment 4
! g
l 3.10c Accept comment.
4.02c Graded according to assumptions.
4.08 Accept comment.
! ! 4.11b Do not accept. comment.
Question asks for foldout page information not status tree information.
4.13b Accept comment.
l I 5.02a Accept comment.
! 5.03a Accept comment.
5.04b Accept comment.
5.05a Accept comment.
5.05b Do not accept comment.
Question requires a SDM comparison between a normal reactor trip (all rods inserted) and a trip where one rod sticks out of the core.
5.06d Accept comment only if proper explanation for detector response is included.
) 5.09a Accept comment.
i 6.01a Accept comment.
6.04b Accept comment.
' 6.05c Accept comment, question deleted, j t 6.06a Accept comment, question changed to read "during cold leg - recirc."
6.08a Do not accept comment.
Question stated that count rate increased to above the high alarm level and to do so it must pass through the alert level.
6.09a Do not accept comment.
Reference cited in key supports answer and differentiates this trip from the low-low level trip.
l J I !
l ls 3 - Attachment 4
I 7.01c Do not accept comment.
First action required by 2-75-57M is to stop movement of fuel assembly.
7.02a Do not accept comment.
Knowledge of facility Radcon Manual and exposure limits is important. The K/A for this question is 3.9.
7.02b Accept comment.
7.03a Accept comment.
7.03b&c Do not accept comments.
Common procedures used frequently 7.04c without direct reference to the procedure require actions 7.08a&b be committed to memory.
In addition, AOP automatic and manual actions should be taken without reference to proced-ures if required in a timely fashion in order to minimize the risk to public health and safety.
I 7.04a Do not accept comment.
Question specifically states per l APO-2.1.3.
! 7.08c Accept comment.
7.10c Accept comment.
8.01a Comment appears to be concerning 8.01b and reference pro-l vided supports the answer in the key.
' i 8.01d Accept comment.
8.07a Accept comment.
8.08 Accept answer if it is provided in addition to the specific actions in the key.
8.09b Accept comment only if the answer clearly states the action is done with the RO's permission, 8.10a&b Consider during grading.
i ? . _. _ }}