IR 05000289/1986007
| ML20197H481 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/12/1986 |
| From: | Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20197H459 | List: |
| References | |
| 50-289-86-07, 50-289-86-7, NUDOCS 8605190176 | |
| Download: ML20197H481 (129) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT EXAMINATION REPORT NO. 86-07 (OL) FACILITY DOCKET NO. 50-289 FACILITY LICENSE NO. DPR-50 LICENSEE: GPU Nuclear Corporation P.O. Box 480 Middletown, PA 17057 FACILITY: Three Mile Island Nuclear Station Unit 1 EXAMINATION DATES: March 3 - 10, 1986 March 17 - 20, 1986 CHIEF EXAMINER: ,f M 45 P P'f6 N. Dudley, Le6d R.. tor Examiner date REVIEWED BY: NTM R. Keller, Chief,/ Projects Section 1C date APPROVED BY: _ / [[ H./KTtfer,4 ief, Projects Branch No. I d/te [ / SUMMARY: Examinations were administered to five Senior Reactor Operator (SR0) and five Reactor Operator (RO) candidates. All candidates passed all portions of the examinations and were issued licenses.
w 8605190176 860512 PDR ADOCK O g9 V- , . - - - - - - - - - - - .- - - - - - - -.- - -- - - -
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. ! f REPORT DETAILS , t TYFE ('F EXAMS: Replacement X ] EXAM RESULTS: 'f I RO l SRO l l l Pass / Fail l Pass / Fail l ! I I I i l I I I i l Written Exam I 5/0 l 5/0 l I I I I , i l i I I
I Oral Exam l 5/0 l 5/0 l l l l l i l l I I I Simulator Examl 5/0 l 5/0 l I I I I ' I I I I l Overall l 5/0
5/0 l l l l l 1.
CHIEF EXAMINER AT SITE: B. Gore, PNL , 2.
OTHER EXAMINERS: J. Huenefeld, PNL ' 3.
Personnel Present at Exit Interview: NRC Contractor Personnel B. Gore, PNL ! Facility Personnel e M.J. Ross, Jr., Ops-I Director l B. Leonard, Operator Training Manager i j.
R. Maag, ' Supervisor, License Operator Training ) L. Ritter, Administrative Operations 4.
Summary of NRC Comments made at exit interview: ' The examiner reviewed the examinations which had been administered and provided the names of nine candidates who had clearly passed the simulator and oral portion of the examination.
The examiner presented the following minor deficiencies noted during the simulator and oral portions of the examination.
i $ _, ,,,,,,m , -., . -.,,,, - .r--. ,- ~_ ,, _ _. ,,, ,, ,. , -, _ , - -., - - - -,,. - c..-,, -m , -
2' confusion in use of the SPOS P-T plot concerning loss of coupling
between primary / secondary (SG P vs T )" sat c Lack of guidance for use of RCS level detectors.
- Need for a better index to MOD COMP computer points as evidenced by
candidate difficulties calling up data.
General lack of understanding why NI counts /sec take longer to
stabilize as criticality is approached (NOT #n's).
Lack of knowledge that RM setpoints can be checked using colored
butttons on panel face.
Lack of knowledge that fristfers (RM-14) use GM tubes for sensitivity
to S-T.
Weak understanding of why a centrifugal pump shut-off head is higher
than when flow is allowed.
Error in coatrol room controlled procedure file discovered by
candidate and brought to SS attention for correction. TCN for " Plant Cooldown" procedure had been filed correctly. Other copies had been filed with the " Plant Heatup" procedure and notations made in the procedure referring to_the TCN.
5.
Changes made to written examination: Changes made to the examinations as a result of comments made during the examination review are detailed in Attachment 3.
Attachments: 1.
Written Examination and Answer Key (RO) 2.
Written Examination and Answer Key (SRO) 3.
Facility Comments on Written Examinations
m .
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ y '- 0o v /t f.
/ /a.> 7b,.- ATTAtNmen$ l . . . U.S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION ' Facility: TMI-1
Reactor Type: Babcock & Wilcox Date Administered: _ March 18. 1986 Examiner: Gore. Huenefeld, Schreiber. Dudley Candidate: Answer Key INSTRUCTIONS TO CANDIDATE: Print your name on the line above marked " Candidate." The grade points available for each question are indicated within parentheses after each ques-tion. The passing grade is 70% in each of the four (4) categories and is 80% for the total grade. Use separate paper for your answers and write on only one (1) side of the paper, unless a specific question instructs you otherwise.
Staple this question package to your answer sheets.
The examination questions and answers will be picked up six (6) hours after the examination was started.
Read the statement at the bottom of this page. When you have finished this examination, affirm the statement by signing your name.
Category % of Candidate's % of Value Total Score Cat. Value Category
25 1.
Principles of Nuclear Power Plant Operation, Thermodynamics Heat Transfer and Fluid Flow
25 2.
Plant Design Including Safety and Emergency -- Systems
25 3.
Instruments and Controls
_25_ 4.
Procedures - Normal, Abnormal, Emergency and Radiological Control 100 TOTALS Final Grade % All work done on this examination is my own.
I have neither given nor received aid.
. Candidate's Signature j < - - - - -
. . . . _ Page 1 TMI March 18, 1986 Points Available 1.0 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION. THERMODYNAMICS. HEAT TRANSFER AND FLUID FLOW (25.0) 00ESTION 1.01 The purpose of rod bank overlap is to: (0.75) (a.) linearize the curve of integral rod worth versus bank position.
(b.) provide adequate shutdown margin during reactor trip.
(c.) provide shielding against excessive neutron leakage to the excore detectors.
(d.
.rovide axial flux chaping to protect against DNB.
ANSWER 1_ u.
(a.)
[+0.75] Reference (s) 1.01 1.
iMI Reactor Theory, p. 294.
-Section.1.0 Continued on Next Page- { >
i . . .
. . Page 2 TMI March 18, 1986 Points AYlllattle OUESTION 1.02 On a reactor trip from 100% power and equilibrium Xe conditions, peak Xe will be reached in approximately hours.
(0.75) (a.) 4 to 7 (b.) 8 to 12 (c.) 13 to 18 (d.) 19 to 25 ANSWER 1.02 . (b.)
[+0.75] - - .. Reference (s) 1.02 . 1.
TMI Reactor Theory, p. 297.
-Section 1.0 Continued on Next Page-
_ -__ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . . . Page 3 TMI March 18,1986 Points Available OUESTION 1.03 Select the CORRECT statement concerning pump cavitation.
(0.75) (a.) Vapor bubbles are formed when the enthalpy difference between the pump discharge and pump suction exceeds the latent heat of vaporization.
(b.) When the vapor bubbles enter a higher pressure region, the bubbles collapse which produces high pressure pulses or shock waves.
(c.) Vapor cavities (bubbles) are produced when the localized pressure exceeds the vapor pressure at the existing temperature.
(d.) As the vapor bubbles are discharged from the pump they 1h,mpinge on downstream piping and valves causing water ammer.
ANSWER 1.03 , (b.)
[+0.75] Reference (s) 1.03 1.
TMI Heat and Fluid Power, p. 38 talks about NPSH, but not cavitation.
. -Section.1.0 Continued on Next Page-
. % o . . - Page 4 TMI March 18, 1986 Points available QUESTION 1.04 After the main generator is synchronized with the grid, excitation current is proportional to: (Selectone.)
(0.75) (a.) reactive load (MVAR) (b.) real load (MW) (c.) output voltage (KV) (d.) generator speed (RPM) ANSWER 1.04 (a.)
[+0.75] "
.,_ Reference (s) 1.04 1.
TMI Fundamentals.
-. -Section 1.0 Continued on Next Page-
. > . , . . l Page 5 TMI March 18, 1986 Points available QUESTION 1.05 Indicate whether each of the following will INCREASE or DAMPEN a Xe oscillation.
1.
Doppler effect (0.5) 2.
Negative MTC (0.5) 3.
Power or flux level in:reases during an oscillation (0.5) ANSWER 1.05 1.
DAMPEN [+0.5] 2.
DAMPEN [+ 0. 5] - 3.
INCREA;i: [+0.5] (Loth frequency and magnitude) [[c ference (s) I mQh 1.
TMI Reactor Theory, p.166.
-Section.1.0 Continued on Next Page- ,
. % . . , . Page 6 TMI March 18, 1986 Points Available OUESTION 1.06 a.
.Exolain why delayed neutrons are important to safe reactor operation.
(1.0) b.
How does the effective fraction of delayed neutrons, p 7,OL. (1.0) , change over core life? Give typical values at BOL an8 L ANSWER 1.06 a.
The delayed neutrons give a slow enough SUR or period, for given reactivity changes, to make reactor control practical, i.e., the reactor is stable.
[+1.0] b.
Decrease [+0.5] BOL 0:007 [+0.25] ^' "' E0L 0.005 [+0.25] ,c, ' '- Re F'rencris)_LDfi 1.
TMI Reactor Theory, p. 95.
QUESTION 1.DZ "' What two (2) factors make up the power defect? (1.0) aMSWER 1.07 1.
Doppler [+0.5] 2.
Moderator temperature [+0.5] Reference (s) 1.07 1.
TMI Reactor Theory, p.156.
-Section.1.0 Continued on Next Page-
. . . . . _ Page 7 TMI March 18, 1986 Points Available QUESTION 1.08 RCS boron concengration ig 500 ppm B.
RCS average temperature changes from 490 F to 310 F.
Using the following figures, calculate the resulting change in reactivity. Show your work.
(3.0) ANSWER 1.08 At 490 F, the relative reactivity due to temperature is +0.95% AK/K. The relative reactivity of the boron is -(0.0106) 500 = -5.3% AK/K.
[+1.0] At 310 F, the relative reactivity due to temperature is +4.35% AK/K. The relative reactivity of the boron is -(0.01245) 500 = -6.225% AK/K.
[+1.0] The change in reactivity is: = 4.35 - 0.95 + (-6.225 + 5.3) -. = 4.35 - 0.95 - 0.925 = 2.475% AK/K.
The reactivity increases (becomes less negative) by 2.475% AK/K. [+1.0] Reference (s) 1.08 1.
TMI OP 1103-15A, Reactivity Balance.
-Section.1.0 Continued on Next Page- - - - - - -
.. _- _-. _ _ _ _ _, _ _ _ _ __ __ _ _ -- .E' ..
. . . . . Page 8 TMI . j. March 18, 1986 i Points Available 110 3-15 A , Revision I QUESTION 1.08 (continued) e c6200 rigure 11 i e i i - .R f . / a - , e i i > I j / _9 $ + . i . ! -/ e,:
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._ .. _. . i
, . . Page 9 TMI March 18, 1986 .
Points Available !
'. 1103-15 A n.mi.n i i P006300 OUESTION 1.08 (continued) rigure 10 ' i e
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-Section 1.0 Continued on Next Page- , i t . -
- _ __ . . . . . Page 10 TMI March 18, 1986 Points Available QUESTI0tl 1.08 (continued) Figure 3 no 3 -is.
Integral Boron Worth $1Tei' 0-1000 ppmb rw. 3 Page 1cf 2 - 12
- l f*l 3 l l l ! l ' 280trPG l fl
- -
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- 1 !! ji! l ifE'i
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~ _5~1 !! t'li h M//l !l @ l ' ' , @ l l ! I h%,T//i i ! N JN j ' $ ~' j l . //_D,Y// l ! i AV i i l ; - ~h ~, ~. Iil I' M //iiILY I.I!
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- j, g7i lll l6 l Cycle 5. HZP l
' l l l '/[I l ll lll ! Legend ! I I //l ' ! !III
- S'S
' ., fi l i i j l eme-. -/l;I I I -- fi i I I l - . _ !/l. i i ' o ido 26o 350 450 550 650 750 abo 960 1000 Boron Concentration guno,..ioenmol 17.0-Section.1.0 Continued on Next Page- . - - - - -
. . . . . Page 11 TMI March 18, 1986 Points Available QUESTION 1.08 (continued) Figure 3 p,o t';*, , Integral Boron Worth ec asoi 1000-2000 ppmb gy;,2,, , ? ~#' ' I il i I ll t i !I I , - $ I l l I I lI I l l I l I I i:3c upo
i.
~ 'l l l l l 1 l I I ll l l 1 ' I ! !
- /dm/J
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" ' ' l ! l 7J[/i (i(1) i i l l 169; J l l WI I
l ' ' ' ' ~ . l ; j / @,,( l l l l l l Cycle 5. HZP[] , /,/,i lI l i ' ~7 ! -12 ; J' gj' 9. ; g j Legend
. riorreo a /\\/,/ ' l l l _,, ; . no veo L/ jf _, I l l l l ontt.. ' = /.' i l I I ,,, ; /,
I I I ' n l
I i ! - ~' 12' 0 12'0 0 14 0' 0 15' 0 16 o' 0 1700 is'oo 19'0 0 2000 icoo stoo
0 Boron concentration g o, s o,.. io,,,,,o 1 18.C-Section 1.0 Continued on Next Page- , ,
. . . . _ Page 12 TMI March 18, 1986 Points ayallable OUESTION 1.09 a.
During core loading or fuel shuffling, what is the main, purpose of keeping an inverse multiplication plot as fuel is added or moved? (1.0) b.
Why is it necessary to have a neutron source in the core during fuel loading or movement? (1.0) ANSWER 1.09 a.
To be assured that the reactor remains well away from cri ticali ty.
[+1.0] Alt: to'Dredict criticality b.
To be certain the count rate is on the scale of the source range nuclear instrumentation.
[+1.0] ' - ~~ w.
Reference (s) 1.09 1.
TMI Reactor Theory, p. 124 and 113.
-Section.1.0 Continued on Next Page- _
, . , . Page 13 TMI March 18, 1986 Points Available - 00ESTION 1.10 The reactor is shut down by 5% AK/K with a neutron count, rate of 50 cps. Rods are withdrawn inserting 2% AK/K reactivity.
What will be the final countrate? Show calculation.
(1.5) MSWER_ldD = -0.05, K; = 0.952
= -0.05 + 0.02 = -0.03, K2 = 0.971
,
- 50 (1 - 0.952) = 83 CR 1 - 0.971)
[+1.5] Rderence(s) 1.10 1.
TMI Reactor Theory, p. 120.
-Section.1.0 Continued on Next Page- %
. . . . . Page 14 TMI March 18, 1986 Points Ay dlable QUESTION 1.11-8 The reactor is critical at 10 amps.
Regulating rods are bumped in for a few seconds.
Reactor power will decrease.
Descrihe how far down it will go.
(No calculation is required.)
(1.5) ANSWER _L L1 Reactor power will decrease to the subcritical multiplication level corresponding with the amount of reactivity in the core.
[+1.5] Reference (s) 1 l1 1.
TMI Rx Theory.
QUESIl0!LL12 If RV voiding occurs, how should it be collapsed prior to continuing a natural circulation cooldown? Assume that an RCP cannot be bumped.
(1.5) ANSMER_L12 RCS pressure should be held constant at, or S110btly higher than, the pressure at which the void formed to allow the void to condense.
[+1.5] ReferencelsLL12 1.
TMI OP 1102-16, p. 6.0.
-Section.1.0 Continued on Next Page-p .,
. . . . , Page 15 TMI March 18, 1986 Points (Wallable OUESTION 1.13 Spraying emergency feedwater into an OTSG has a dramatic effect on RCS cooldown rate for two (2) major rhasons.
Stain these two (2) major reasons.
(2.0) ANSWER 1.13 1.
The AFW is sprayed high in the OTSG therefore increasing the effective surface area for heat transfer.
[+1.0] 2.
The spraying of cold AFW into the steam space of the OTSG causes a depressurization similar to that occurring during pressurizer spray.
This lowers the saturation temperature in the OTSG.
[+1.0] l Reference (s) 1.13 1.
B&W Plant Operations Manual.
. ' l-Section.1.0 Continued on Next Page- - - -
- _ -. __ _ _ _ _ _ __ _ _.._ _ _ _ _ _ _ _.. _ ___ _ , - ! . , . . , i
Page 16 TMI j March 18, 1986 Points AYallable t.
j OUESTION 1.14 ' ! j Box does water collecting in a steam line lead to water hammer? (1.5) i ANSWER 1.14 Water can provide an extended surface for condensation creating i j a low pressure region resulting from void collapse.
This sudden ] void collapse causes a hydraulic shock.. or " hammer".
[+1.5] l a i Reference (s) 1.14 i ]) 1.
THI Heat and Fluid Power, p. 21.
.
i l 00ESTION 1.15
j Exolain why DNBR = 1.0 is acceptable in the operation of the 0TSG, but not acceptable in operation of the reactor.
(1.5) ! ! ANSWER 1.15 , The maximum metal temperature in the OTSG is limited to T l from the RCS, [+0.7] but the fuel cladding temperature caN D ,
increase to destruction because the heat being generated in i the fuel can only be released by heat transfer across the ' cladding.
[+0.8] '
.
i ! ! Reference (s) 1.15 j_ I 1.
TMI Heat and Fluid Power, pp.190 and 200.
! i i
,
J i ! -Section 1.0 Continued on Next Page-
l
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. . . . _ Page 17 TMI March 18, 1986 Points avatlable OUESTION 1.16 Matchthepressureandtemperatureeffects(ah)withtheir corresponding cause (1-3): (Each choice should be used only once.)
(1.5) (a.) Reduction in pressure with no reduction in temperat. ce.
. (b.) Reduction in both pressure and temperature.
(c.) Increase in temperature and pressure.
_________________________________________________________________ 1.
Excessive primary to secondary heat removal.
- -. 2.
Lack of primary to secondary heat removal.
3.
Loss of RCS inventory.
- ANSWER 1.16 (a.)
[+ 0.5] (b.)
[+ 0.5] (c.) 2 [+0.5] ~- Reference (s) 1.15 1.
ATOG, Part 2.
-Section 1.0 Continued on Next Page-r: - - - - - - .. - .. . - - .
- _ _ - _ _ _ _ _ _ _ _. . I - - . , Page 18 TMI March 18, 1986 Points anttlable QUESTION 1.17 a.
After operating at 100% power for three months, power is suddenly lost to all of the reactor coolant pumps.
Below are three (3) things that can be done to enhance natural circulation. Why is each done? (0.75) 1.
Maintain pressurizer level 2.
Maintain subcooling in RCS 3.
Maintain steam generator level b.
Briefly explain how the following parameters will be trending if natural circulation is LOST: (0.75) 1.
RCS differential temperature (Incore - T ) c 2.
Steam generator steam pressure 3.
RCS T - 0TSG T c sat ,. - AHSWER 1.17 a.
1.
To ensure that no vapor pockets form in the loops 2.
To prevent steam pocket formation 3.
To help thermal driving head [+0.25] for each b.
1.
Will exceed 100% full power value 2.
Pressure will decrease 3.
Delta T will increase [+0.25] for each Referencelsl_1.11 1.
TMI OP 1210-1-10.
-End of Section 1.0-
- - - -
_ _ _ _ _ - . . , Page 19 TMI March 18, 1986 Points Avatlable 2.0 PLANT DESIGfLIHCLEll{G_ SAFETY AND BERGMC_Y_SISIms (25.0) QUESTION 2.01 Loss of which one of the following combinations of 480 V buses will result in the dropping of control rod groups 1-7? (0.5) (a.) 1G and IL (b.) IF and 1H (c.) 1G and IJ (d.) IF and IG ANSWER 2.Q1 (a.)
[+0.5]~* - Referencels) 2.01 1.
TMI Electrical Schematic IE-710-11-003.
-Section.2.0 Continued on Next Page- - - - - - - -
. . . . , Page 20 TMI March 18, 1986 Points AYdilable 1. OVESTION 2.02 a.
Answer TRUE or FALSE.
The emergency boration flowpath from the Boric Acid Mix Tank to the Makeup Tank is through batch controller (MU12-FT).
(0.5) b.
Explain why, when terminating feed from the boric acid addition pumps CA-PIA /B, each pump must be stopped before its discharge valve is closed.
(1.5) ANSWER 2m02 .- a.
FALSE (bypasses it) [+0.5] b.
Pumps are positive displacement [+1.0]. Damage to pumps or other components may occur due to resulting high ' pressures if valves are closed first.
[+0.5] . , Reference (s) 2.02 1.
T OP 1103-4, Section 3.10, 2.
TMI Station Drawing C-302-670.
-Section.2.0 Continued on Next Page- - - - - . - . - . - - -
. . . . . Page 21 TMI March 18,1986 Points Ani.lable OUESTION 2.03 When reestablishing a pressurizer bubble after HPI cooling and - solid operations: a.
approximately how long will it take for PZR level to come onto scale if letdown exceeds makeup by the recommended 25 gpm? (1.0) b.
what should be monitored as an indication of steam bubble formation in the PZR? (1.0) , ANSWER 2.03 ~' a.
about half an hour (25 - 30 min) [+1.0] - b.
stable RCS pressure * [+1.0] Reference (s) 2.03 1.
TMI ATP 1210-9, Rev. 5, p. 3.0.
, . . -Section,2.0 Continued on Next Page- . . - - - - - - - .
_ _ _.
_ _ -_.. .- _ __ - l
r > .
Page 22 TMI i March 18, 1986 . I ' Points
Available t i I OVESTION 2.04 i Describe the " piggy bask" flowpath lineup and when it is used.
(2.5)
ANSWER 2.04 ! l l Used to supply water to HPI when the BWST level drops to LO-LO ' alarm point (36 inches) [+0.5] If pressure has not dropped enough to establish LPI flow.
[+ 0.5] Lineup by opening the LPI suction to the RB sump (DH-V6) [+0.5],
closing the flowpath from the BWST to the LPI suction (DH-V5) ' [+0.5] and opening valves connecting the LPI discharge to the ,' ' HPI suction (DH-V7) [+0.5]. ! . l Reference (s). 2.04 i
1.
TMI ATP 1210-6, Rev.,4, p. 3.0.
-' .., ! ) 00ESTION 2.05 " ' ) , If the Nuclear Services Closed Cooling Water system is in its
normal electrical lineup, how must this lineup,be changed.to j remove NS-PIC for maintenance? (2.0) . ,
- ... , d
, aMSh'ER_2.05 ' i NS-PIB must be removed from service and its breaker to 480 V j ES Bus IP racked out [+0.5]. Then using the.," kirk key" its l breaker to Bus IS is racked in [+0.5]. It is then selected I for ES operation [+0.5] and restarted before NS-PIC is removed j from service [+0.5]. )! ReferencrisL2E ! j 1.
TMI OTM NSCCW lesson, p. 16.
f-Section.2.0 Continued on Next Page-t i
- - . , I
.-. - .-. - -. . . -.. _ -. _.
.- -. -- . -.. _... -. .. -. - ._ _ - - - _ _ _ _ _
i
i i Page 23 TMI j March 18, 1986 j Points . i '
Available
3 i i OVESTION 2.06
The plant is operating at 85% power, in full ICS automatic,
when one MFW pump trips off.. During the brief period before ') the subsequent ICS runback changes demand values, how will
generated megawatts change? Exolain the two (2) factors causing i this change.
(1.5) } j ANSWER 2.06 MWe increases [+0.5] due to increased steam available from the
] tripped MFWP [+0.5] and reduced aspirating steam needed for j MFW heating [+0.5].
i Reference (s) 2.06 1.
TMI OTM Vol. V, RCS Lesson, p. 33.
I
! l _- i l i i ! l !
l i i ] -Section 2.0 Continued on Next Page-i
. ,
1 . . .... . . . . . a
-.. - . - - . _. _ -. - ... - . - _ - _. -. . -. _ -- .
, I t
. , i e I Page 24 ' TMI ) March 18, 1986 $ ' . Points
hallable ! I ' i l' QUESTION 2 R j,N ! Draw a-one-line diagram showing the 4160 V inputs to both ES ! buses. Include the diesel generators and bienti.fy supply . transformers. Show circuit breakers and indicate whether
normally open or closed. You do not need to show electrical . loads.
(2.0) q . . ANSWER 2.07 [3Ln N1" ELL =d 17 i L-p t b (*tz1is uj 1.ji.)
- i TN]J' viin':L . J'o Swofcit VAI'd fa %TestyAf D . l . ! 3d l(Y .I A b U.$e ll. O ht)f.
230 }{Y < ,
., n%us.
- -Tf{nus, "" {, mm mm mm mm i O!(* II'! ~ 6.*1 l( V $1jf/ '/.l(.}[t/ . ._ - ' . , . .. - . -. , . . ._.
-, . . - y ' H H H h} , . Components and connections [+1.0] . iU ES. Vl(V $ E' l'. s.
///(tl-l- [ -] l > - Breaker positions [+1.0] ' E'd d - , Referer1ce(s) 2.07 - . , 1.
TMI OTM, Ch. 20, Electrical Distribution, p. 60.
. [,( j. a j o cu.
pacirt * -Section.2.0 Continued on Next Page- ! ' - . , -\\ e g ---,,-r - n ,e ,e .,. , ,n v,, ,,,-,,e-,.------,,-~-- -,-n,v,,-- -,.
. Page 25 TMI March 18, 1986 Points Anti.1able QUESTION 2.08 E3 plain two types of damage which could result due to failure of check valves FW-V9B (at MFW pump discharge) and FW-V128 (between MFW valves and 0TSG) after tripping of the MFW pumps.
(2.0) ANSWER 2.08 [ L j' f.cc,, g,- (. ,.,,, . <,,,y, g- ,, , i.
- - V Vi g*, Water hammer could be produced by steam-water interactions in the MFW piping.
[+1.01 Overpressurization could cupture components upstream of the MFW pumps.
[+1.0] f1 {.<.<. < c.c c, }/,- eL, sn., c. La.,; L,,,, /;.,,,,. 4cje , .
,{ ,m ui-u i n,cc u ns, l, 5 ci+<u .-u n... GL n, <(u.
ts ',ia t. c(.m.g ' C[ A i F-V- t A p3 < < f pu...y* 'c < c f a o.u-Reference (s) 2.08 f gL.~ Wr yjq ( 1.
San Onofre Incident, Nov. 21,.1985.
2.
TMI Plant drawing C-302-081.
.- . -Section.2.0 Continued on Next Page- - . , e
.. - - _ - -.. ..- - _ .. ... - _ -. _ -- _ - _.. . J, ' l, Page 26 TMI i March 18, 1986 i Points ayallable
I r QUESTION 2.09
i a.
Describe the two (2) methods by which control rod position i is indicated.
(1.5) $ b.
What switches and displays are fed by each detection method? (1.0) , j c.
Which method is used to determine group average position? (0.5) ANSWER 2.09
a.
1.
Absolute position indication: a magnet attached to the rod drive mechanism closes reed switches mounted
l along the motor tube when it is near each of them, j indicating actual rod position. [+0.75] 2.
Relative position indication: a stepping motor is , driven by the electrical phase changes which drive
l the CRDMs producing an electrical signal corresponding -- ! to where the rods would be driven if they are not l stuck, tripped or dropped. [+0.75] _ '" b.
Absolute: 1.
In-limit and 0% switches 2.
Out-limit and 100% switches 3.
Five zone reference switches 4.
Individual rod position on PI panel 7, %yn~ <e s -a ue
Relative: 6#9 '*'"' I" C # '" ' 1.
Individual rod position on PI panel ,
2, s q u<. a.- A u n-s~ ! [+0.2] each 4"<1 a../c-fi. t j wti .S h 1 Nf'
c.
API [+0.5] ReferenceJsl 2.09 1.
TMI OTM CRDM Lesson, pp. 27-30.
-Section.2.0 Continued on Next Page- . - , t .
_ _ _ _ _--- -- _ __ ___ ..... ...- . _. - - -. _ _. __ . Page 27 TMI March 18, 1986
! j Points ! Available t l
I OUESTION 2.10 . .. -. i ' Briefly exclain what must be done, and in what order, to provide ' , adequate RC pump lubrication prior to hand rotation.
(2.0) ! < j ANSWER 2.10 i { Both backstop and a lift oil pump must be started [+1.0] with
the backstop pump started first to allow air to bleed out properly from the oil lines [+1.0].
, l ! Reference (s) 2.10
1.
TMI OP 1103-6, Rev. 31, p. 25.0.
I Qut; UON 2.11 ' Lzplain what the spectacle flange in the Core Flood System near CF-V11 is used for and-how it is used.
(1.5) , _ l ANSWER 2.11 It is used to blank off or allow flow from the MU pumps to increase the CFT level [+0.8]. -The flange must be reversed from its normal blanked position to allow flow [+0.7]. '
Reference (s) 2.11 1.
TMI OP 1104, Rev. 11, p. 16.0.
. -Section.2.0 Continued on Next Page- , = '
. ' . w .e-. --, --, - -,, -
e,
- - - - +,,., - ,,n--enr-,y,-,p,,, ..-v.- ., ,n-,..-w-,-., ,. ..g,.y-e-a, ., ,---neg.-,-e-,ag .,--~m--rv,. . w s p+m--+,,.,9~,-, , +
. Page 28 TMI March 18, 1986 Points &Y111able OVESTION 2.12 If Condensate Storage Tanks low-low level alarms occur when they are supplying EFW, you are directed to depress the Emergency Alignment control pushbutton located on the control room console.
a.
List the three (3) valves that this opens and state what this accomplishes.
(2.0) b.
What is accomplished by closure of the valves that this closes? (1.0) ANSWER 2.12 3f, j , a.
CO-V-8, 42;-13- [+1.0] permit EFW pump suction directly from condenser hotwell [+1.0] -- b.
prevents air from entering pump suction line [+1.0] (CO-V-6, 7-not required) Reference (s}_2.12 1.
TMI ATP 1210-10, Revision 7, p. 8.0.
-Section 2.0 Continued on Next Page- . . ' . ,
. - . Page 29 TMI March 18, 1986 Points Available 00ESTION 2.13 . Exclain why the No. I seal bypass valve should not be opened if seal injection is lost to an RC pump.
(1.0) ANSWER 2.13 The thermal barrier heat exchange capacity may be exceeded.
[+1.0] Reference (s) 2.11 1.
TMI AB 1203-15, Rev. 9, p. 2.0.
- -End of Section 2.0- . . a , .
_.
-_.. . Page 30 TMI March 18, 1986 Points available 3.0 INSTRUMENTS AND CONTROLS (25.0) ' QUESTION 3.01 Answer the following TRUE or FALSE.
a.
Atmospheric Monitor interlocks are actuated by the " Alert Alarm" on the gaseous channel of the respective monitor.
(0.5) b.
All of the area gamma radiation monitors (designated RM-Gf) are powered from distribution panels VBA, VBB, VBC, and VBD.
(0.5) Illumination of the green " FAIL" light of the area gamma c.
monitors indicates that power is on.
(0.5) d.
During normal operation of RM-L-12, the " RED" pump power indicating light automatically illuminates when either IWTS or 1WFS discharge is initiated.
(0.5) _ .. ANSWER 3.01 a.
FALSE [+0.5] "High Alarm" actuates b.
TRUE [+0.5] i c.
TRUE [+0.5] . , d.
TRUE [+0.5] I Reference (s) 3.01 1.
TMI OP 1105-8, Revision 28: a) p. 26.0, b) p. 34.0, c) '
p. 8, d) pp. 16.0, 17.0.
i l i-Section 3.0 Continued on Next Page- - . , .. i -
_ __.
, , _ _.,,. - - _., - -,. -. . _.. ,, _ , _., _. - -, _. _.. _ _ -. _ _......,.,, _ _. _, -.,,,..
. -. _ . . - _ - ~ _ _. - _ _ __ __ i . Page 31 TMI March 18, 1986 Points Available ! OVESTION 3.02,. Unx will the following equipment respond to an ES (1600 psig)
signal? (3.0) ' , a.
EF-P-2A with coincident loss of main feedwater.
b.
EDG able to develop 4 psig lube oil pressure during starting.
c.
Letdown valve MU-V-3.
l d.
Makeup valve MU-V-18.
s s.
. Non-ES selected running MVP (offsite power maintained).
e.
- ku ANSWER 3.02 Starts 20 sec after ES signal (5 sec after block 4 loading).
a.
b.
Starts (6 psig start shutdown is blocked on ES).
., _ _ c.
Remains as is (closes on Rx trip - may be reopened after , 10 sec. However, MU-V-2A,B do close, isolating letdown).
d.
Closes.
e.
Continues running.
, [+0.6] each - Reference (s) 3.02 1.
TMI ATP 12-10, Rev. 7, p. 6.0.
2.
TMI OTM EDG Lesson, p. 25.
3.- TMI OP 1105-3, Rev. 18, pp. 14.0, 20.0.
4.
TMI OTM MVP Lesson, pp. 15, 22.
i-Section.3.0 Continued on Next Page-
- . , e . . - - . - . . - - . -.. - . -- -.. . .- . - m .
. .. . .. .-. ' , . Page 32 TMI March 18, 1986 Points Available < OVESTION 3.03 l When preparing to switch the Bailey Reactor Demand station to ' I " Auto". I error should be zero. Whh1 reading indicates this condition {' (1.0) , ANSWER 3.03 i J 50 percent on the Rx Demand station [+0.5] with MV-Pos switch in MV [+0.5]. . Reference (s) 3.03 .. 1.
TMI OP 1105-4.
OVESTION 3.04 ,
If ICS/NNI power to the selected pressurizer level transmitter is lost, exolain how and ahy this will affect the makeup valve - ' ~ MU-V17 if it is in AUTO.
~~ (1.5) ~ ' ' " '
ANSWER 3.04 MU-V17 will close [+0.7] because the pressurizer level indication will fail high (320 inches) [+0.8]. Reference (s) 3.04 1.
TMI EP 1202-43, Rev. O, p. 1.0.. ! . -Section 3.0 Continued on Next Page- - . . l - _ . - . _ _ _ _ _ . - _ _ _,. _. _. _ _ , _._._. _. _..... Page 32 TMI March 18, 1986 Points Available OUESTION 3.03 When preparing to switch the Bailey Reactor Demand station to " Auto". T error should be zero. What reading indicates this '" condition? (1.0) ANSWER 3.03 50 percent on the Rx Demand station [+0.5] with MV-Pos switch in MV [+0.5]. . Reference (s) 3.03 , _ - 1.
TMI OP 1105-4.
OVESTION 3.04 If ICS/NNI power to the selected pressurizer level transmitter is lost, exclain how and why this will affect the makeup valve -- ~ MU-V17 if it is in AUTO.
-- (1.5) ". ~ ANSWER 3.04 MU-V17 will close [+0.7] because the pressurizer level indication will fail high (320 inches) [+0.8]. Re_frence(s) 3.M 1.
TMI EP 1202-43, Rev. O, p. 1.0.
. Cd on 3.0 Continued on Next Page- .
. . i . J
. Page 33 TMI March 18, 1986 Points allilable OVESTION 3.05 List the four (4) plant parameters used to calculate the BTUs available to the Steam Generators.
Indicate hoy each parameter must change to reduce the amount of superheat supplied by the Steam Generator.
(2.0) ANSWER 3.05 1.
Thot 2.
RCS flow 3.
FW temperature , 4.
OTSG pressure ' [+0.25] each thermal h8ker[+0.25] or RCS flow [+0.25] (reduces available Reduce T to the OTSG).
.e, ~. - Reduce FW temperature (increases the thermal power required to provide superheat).
[+0.25] Increase OTSG pressure (increases Tsat, yielding lower superheat for a given steam temperature).
[+0.25] Reference (s) 3.05 1.
TMI OTM Vol. 6, ICS Lesson, p. IV-6.
-Section 3.0 Continued on Next Page- - . , .
_- ._.
_- - -. ._... - . - -. - -.. _.. i ,: i- . Page 34 TMI March 18, 1986 Points , ' Available OUESTION 3.06 , Describe the effect that failure of the feedwater RID (high) would have on the: plant when operating at 100% power in full ICS Auto. Assume no operator intervention.
(2.5) ' ANSWER 3.06
FW demand calculator would increase FW demand.
[+0.5] T,,,would decrease.
[+0.5] Rx demand increases.
[+0.5] Rx demand high limit would prevent plant, trip on high flux.
, [+0.5] Plant would trip on low pressure or variable temperature-I pressure.
[+0.5] - (Btu limit has no effect.)
y - t < ~.. t c Ju is /% - ms .:.-i%/s O g % cy <-;c ? c HQ Reference (s) 3.06 /5II' 264 3fg g , j 1.
TMI OTM Vol. 6, ICS System Description.
i - .l . - !
i ! a-Section.3.0 Continued on Next Page- . . , I - . .. -. . _ _ - _ _.... _ _ _.. _ _. -. _ _, _.
.. _. _. _,, _ _ _ _.
. Page 35 TMI March 18, 1986 Points Available OUESTION 3.QZ - During operation at power, will pressurizer level read higher or lower than' actual (and exolain why). If-(2.5) a.
Temperature compensation is lost, b.
dp cell connection to tank top ruptures.
c.
RCS rapidly depressurizes to 600 psig.
ANSWER 3.07 a.
Reads low [+0.4] - PZR water density is reduced so level is higher than at lower temp. -[+0.5] ~ b.
Reads high [+0.4] - less pressure from top indicates more water weight than actual. [+0.4] ' ~~ Reads high [+0.4] - reference leg boiling or outgassing c.
reduces pressure there, indicating more water weight than actual. [+0.4] , Reference (s) 3.07 1.
TMI OTM Vol. I, Appendix, p.14.
, 2.
TMI ATP 1210-10, Rev. 7, p. 10.
-Section 3.0 Continued on Next Page- - . , .
-. _ _. - .. ___ l . e , Page 36 TMI March 18, 1986 Points Available OVESTION 3.08 List, in sequence, the four (4) major automatic actions that ' occur in the Reactor Building Emergency Cooling System following i an ES signal without loss of off-site power.
(2.5) ANSWER 3.08 1.
The two (2) fans operating will trip (on a block one loading signal).
[+0.6] 2.
All three (3) fans will start automatically and operate , j at their slow speed (on block two loading signal).
[+0.6] 3.
The Emergency Cooling System will go into its emergency ""' j mode of operation, openi6g'The necessary valves automatically and starting the river water pumps (RR-PIA /B) i to establish flow through the emergency cooling coils.
[+0.7] 4.
The normal cooling coil penetration isolation valves (RB-V2.
and,RB-V7) will close.
[+0.6]
- -'
__.
.i Reference (s) 3.08 l 1.
TMI OTM RB Emergency Cooling Lesson, p. 16.
! i
i i
! !, -Section 3.0 Continued on Next Page- , O .-.. . - - . - - - . . - -.. - - -.. -.
- t . Page 37 TMI March 18, 1986 Points Arallat21e OVESTION 3.09 , When the " Trip Reset" button at the Diamond Rod Control panel --
- is depressed, what indication is observable in the RPS cabinets'?
(1.0) ANSWER 3.09 Breaker trip lamps of subassemblies A, 8, C, and D go dim.
[+1.0] ' ' Reference (s) 3.09 - 1.
_TMI OP 1105-2, Revision 18, p. 14.0.
_ -. ~ = ~ - . - - ., % -- -Section 3.0 Continued on Next Page- - . , e
. Page 38 TMI March 18, 1986 Points available QUESTION 3.10 a.
List the three (3) ICS signals that can be selected from either RPS-A or 8 by toggle switches in Cabinet A.
(1.0) b.
State which RPS channel is normally selected and exclain why.
(1.5) ANSWER 3.10 a.
1.
flux [+0.25] 2.
RC flow (loop A and B) [+ 0. 5] 3.
RC pressure [+0.25] 40tt'~ ..;, b.
Channel A [+0.5], because on loss of RPS-A power they automatically switch to Channel B.
Automatic transfer _ _, _. _ from 8 to A does not occur.
[+1.0] - Reference (s) 3.10 ~ . 1.
TMI OP 1105-2, Rev. 17, p. 15.0.
- i-Section 3.0 Continued on Next Page- - . , .
... _.. -. . _.
. _ _ _.
_ _ _ _ _. _ _ _ _ _ _ . _ _. _ - . \\ . i - . . . Page 39 TMI March 18, 1986 Points available ! l QUESTION 3.11 . If both the Diamond Rod Control and the Reactor Demand stations are in Manual and the Diamond Rod Control is to be placed into Auto, exclain how a large mismatch between reactor control demand and neutron power is avoided.
(1.0)
... ANSWER 3.11
) j When it is in Manual, the Reactor Demand station automatically ~ follows actual neutron power and maintains zero neutron error. [+1.0] F Reference (s) 3.11 , 1.
TMI OTM Vol. 6, ICS Lesson, p. V-7.
. OVESTION 3.12 ! With regard to the Movable Atmospheric Monitor RM-A13: , ' a.
What three (3) types of monitors does it utilize? (1,0) i i b.
Exclain how flow is controlled during 1) normal operation and 2) as a backup monitor for RM-A-5.
(1.0) , i ANSWER 3.12 (Or /% Tot.cla h" ) fo r 1, *'rn) i i a.
fixed filter [+0.33], charcoal [+0.33] and gaseous [+0.34] i b.
normal: sel f-regulating af ter initial adjustment [+0.5] t , RM-A-5 backup: manually throttled [+0.5] i } stIto ws % eu ,.s..<a [a r G %nm C f a uen<-eY k-u 'hrI<% i rf rhw ju.14 di,a <.; fr7 ,-c u.
-J o.J McL.f ep wl4>, I Reference (s) 3.12 Ahs. 9% A a, jg a. jn.q,/ f _ c.
' 1.
TMI OP 1105-8, Revision 28, a) p. 18.0, b) p. 21.0.
! I i-Section 3.0 Continued on Next Page-( - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - - - ^ ^ ^ - ^ ^ ^ ^ ^ ^ ^ ' ^ ^ ^ ~ ^ ^ ' ^ ^ ' ^ ^ ^ ^ ' ^ ^ ~
. . ' . Page 40 TMI March 18, 1986 Points AvailabJs OVESTION 3.13 After a reactor trip, one (1) Intermediate Range NI reading decreases faster than -1/3 DPM.
Exolain what this tells you about detector compensation and why.
(1.5) eRSWER_1J1 The detector is overcompensated. [+0.5] Because gammas decay more slowly than the delayed neutrons, the subtracted compensation current increases with respect to the neutron current, reducing this reading more rapidly. [+1.0] Reference (s) 3.11 1.
TMI OTM Vol. 2, p. 269.
-End of Section 3.0- , . l l J
. _ _ _ _ _ . ' ' . Page 41 TMI March 18, 1986 Points AYallablf 4.0 PROCEDURES: NORMAL. ABNORMAL. EMERGENCY. AND RADIOLQGICAL CONTROL (25.0) QQE1110N 4.01
If at any time you discover that RCS temperature is already below 500 F with four (4) reactor coolant pumps running, you should: (Select one.)
(0.75) (a.) leave them all running until temperature exceeds 500 F.
(b.) secure the RCP supplying PZR spray flow.
(c.) immediately secure one (1) of the four (4) RCPs.
(d.) leave them all runnin~g, but reduce RCS pressure to the 50 F subcooling margin.
- -- r, . ANSWER 4.01 (c.)
[+0.75] Reference (s) 4.01 1.
TMI OP 1102-1, p. 3.
l-Section 4.0 Continued on Next Page- __-
. - - . . Page 42 TMI March 18,1986 Points available QUESTION 4.02 If RCS pressure is at 2155 and the RCP radial bearing exceeds its high temperature limit of 225 F, the reactor operator must (select one) (0.75) (a.) stop the affected RCP.
.. (b.) open the No. I seal leakoff valve for the affected pump only.
(c.) open the No. 1 seal leakoff valve for all running RCPs.
. (d.) stop the affected RCP and open its flo 1 seal leakoff valve.
~ ANSWER 4.02 (a.)
[+0.75] ~ Reference (s) 4.02 1.
TMI OP 1102-1, p. 3.0.
.. _ -Section 4.0 Continued on Next Page-
. . . . Page 43 TMI March 18, 1986 Points Available OUESTION 4.03 With feedwater valves in automatic, which of the two (2) actions listed below would tend to prevent the Main Feedwater block valve from cycling after they have opened? Explain.
(1.5) (a.) increasing Main Feedwater pump speed (b.) decreasing Main Feedwater pump speed ANSWER 4.03 (b.) decreasing Main Feedwater pump speed.
[+ 0.5] -- ss. - ,_ Decreasing speed causes feedwater demand to open the startup feedwater valve, holding it further from the block valve cycling setpoint.
[+1.0] Reference (s) 4.03 ~ ' ~ ~ ~ 1.
TMI OP 1102-2 and observation of operations.
-Section 4.0 Continued on Next Page-
. - - . . Page 44 TMI March 18, 1986 Points itVAilable OVESTION 4.04 According to Emergency Plan Im'limenting Procedure 1004.10 p (Onsite/Offsite Radiological Monitoring), above what airborne radioactivity level should respiratory protection be used? (0.75) a.
IE-9 Ci/cc b.
1E+9 pCi/cc c.
IE-9 pCf/cc , d.
1E+9 p Ci/cc AMSWER 4.04 c. - other values are ridiculously high [+0.75] Reference (s) 4.04 IMI EPIP-1004.10, p. 1.
- -Section 4.0 Continued on Next Page-
. , . . Page 45 TMI March 18, 1986 Points Available OUESTION 4.05 Given one (1) RAD of radiation exposure, which of the following sources of radiation would cause the most biological damage? (Select one).
(0.75) (a.) Beta radiation (b.) Thermal neutron radiation (c.) Gamma radiation (d.) X-rays _- ANSWER 4.03 (b.) [+0.75] .. - ' .. . Reference (s) 4.05 1.
TMI Radiation Protection Training Manual.
QUESTION 4.06 Answer TRUE or FALSE.
The CRA safety groups must always be at their upper limits prior to boron dilution.
(0.5) ANSWER 4.06 \\
TRUE [+0.5] Reference (s) 4.06 1.
TMI OP 1103-4, p. 6.0.
' -Section 4.0 Continued on Next Page-
. . ' . . Page 46 TMI March 18, 1986 Points Available OUESTION 4.07 Answer TRUE or FALSE.
-8 To assist in leveling Rx power at 10 amps, the Approach to Criticality procedure, OP 1103-8, allows using the more finely controllable axial power shaping rods (APSRs).
(0.5) ANSWER ?.07 FALSE [+ 0.5] Reference (s) 4.07 1.
TMI OP 1103-8, p. 4.0.
--- OUESTION 4.08 Answer TRUE or FALSE.
At temperatures above 300 F, maintaining a 25 F subcooling margin ensures adequate NPSH for the RCPs.
(0.5) ANSWER 4 JD1 FALSE [+0.5] . Reference (s) 4.08 1.
TMI OP 1210-10, p. 13, Figure 1.
. -Section 4.0 Continued on Next Page-
_ _ _ _ _ _ _ _ _ _ _ _ _ . . - , Page 47 TMI March 18, 1986 Points AYAllable QEESTION 4.09 Answer TRUE or FALSE.
The NPSH limit does not apply for RCP bumps'. (0.5) ANSWER 4.09 ' TRUE [+0.5] Refer.cnce(s) 4.09 , 1.
TMI OP 1210-10, p. 11.0, _ _ _ - % . .
- e, --
- . -Section 4.0 Continued on Next Page- _ - _
-- .--- ' . . . , Page 48 TMI March 18,1986 Points Available , OUESTION 4.10 A shutdown margfn calculation is performed during a cooldown in accordance with the Shutdown Margin and Reactivity Balance i procedure, OP 1103-15A. Is this calculation more conservative i with control rod groups 1-4 fully inserted or 100% WD?
Exclain.
(1.5) ANSWER 4.10 Control rods fully inserted. [+0.5] ... The shutdown margin calculation assumes all (with the exception of Groep 8 and the most reactive rod) rod, are fully inserted.
, [+1.0] i i Reference.(s) 4.10 1.
TMI OP 1103-15A, p. 11.0.
EQIE: The reactivity calculated for the SDM is based on CRG 1-7-at 0% WD minus any stuck rods. This is a SDM and not a reactivity balance. Actual core subcriticality at nominal . rod positions (CRG 1-4 at 100% WD with no stuck rod) is , less negative by approximately 2% Ak/k.
, ! i
I
!
-Section 4.0 Continued on Next Page- , - .. -. , -. - -. -, - , -. .. - -. -. -.... --. , .-. - -..,,
. _ _ _.... _.
_ __ .,. _ _ _. _.
' ,
- . , Page 49
._ TMI ' March 18, 1986
Points AM LlAble , '
i , j OVESTION 4.11 ! During a plant heatup in accordance with OP 1102-1, when RCS i temperature is equal to or greater than 525'F, boron concentration may be reduced below the cold shutdown value but ! must be maintained at least at the con-centration until OTSG levels are lowered per the startup
procedure.
(0.5) ANSWER 4.11 l flooded nozzle [+0.5]
Reference (s) 4.11 , , '
1.
TMI OP 1102-1, p. 30.0.
27 TMIOP1102-2,p.1350.
' ~ ~ ~ ~ ~ '
j OVESTION 4.12 At what reactivity limit must the reactor be maintained if any
condition occurs which physically or administrative 1y delays criticality? (1.0) . j ANSWER 4.12 At least 1 %Ak/k subcritical [+1.0] ) -
l Reference (s) 4.12
l 1.
TMI OP 1103-8, p. 2.0, i i-Section 4.0 Continued on Next Page- , [ __ l l . - -
-. _ . . - _ _ __ _ _ _ -- - . , ' . r Page 50 TMI ! March 18, 1986 Points Availahle OVESTION 4.13 According to OP 1210-1, how soon after a reactor trip should RCS temperature and pressure approach post trip values? (1.0) ANSWER 4.13 within 2 to 5 minutes [+1.0] Reference (s) 4.13 'l 1.
TMI OP 1210-1, p. 3.0.
> . ' OUESTION 4.14 I ! The RCS natural circulation cooling procedure gives four (4) ) indications to be used~ for verifyin~ ' the existance of natural ' - - - g circulation. State three (3) of these indications.
(1.5) ANSWER 4.14 1.
RCS AT increases to approximately 30*F to 50 F (depende'nt on Decay Heat) and stabilizes and TH is ( 600'F.
2.
Incore thermocouple temperatures stabilize and are tracking T-H 3.
Cold leg temperatures approach saturation temperature for - secondary side pressure (normally within 5 minutes).
4.
Verify heat removal from OTSGs.
a.
Steam flow indication.
i ' b.
Feed flow indication.
'
- r.
Any three (3) [+0.5] each . j Reference (s) 4.14
1.
TMI OP 1106-16, p. 6.
-Section 4.0 Continued on Next Page-
_ _, _ _ - -. -.,. . - - - - -. - - - - - - - - - - ~ - - - - - - - - - -
. . . .. . _ .. - -. c . . - ..r '
. >- , j ~ Page 51 TMI .- March 18, 1986 Points AY.ailattle QUESTION 4.15 - , , According to the emergency procedure,1210-5, ahen may RCPs be red 0ced to one per loop dur_ing a steam generator tube rupture? (1.0) . ANSWER 4.15 Whea additional spray flow is no longer required to control, succooling margin.
[+1.0] i Refer ~ence(s) 4.15
] 1.
TMI OP 1210-5, p. 3.0.
QUESTION 4.16 . State the four (4) HPI throttl4ng criteria.
(2.5)
! ANSWER 4.16 1.
Prevent pump runout.
[+0.6] 2.
Prevent violation of BFPL and PTS limitations. [+0.6] 3.
If.LPI flow > 1000 gpm in each train and stable for 20 minutes.
[+0.6] ... 4.
25'F subcooling margin exists and PZR level is > 0 inches.
[+0.7] ' j Reference (s) 4.16 1.
THI OP 1210-10, p. 4.0.
I , -Section 4.0 Continued on Next Page-J ' '- '- _.,. ,
. e e Page 52 Tlil liarch 18, 1986 Points avdlahls 00ESTION 4.17 What constitutes a dry OTSG? (1.0) ANSWER 4.17 Less than 18 inches on the SU range.
[+1.0] Reference (s) 4.17 1.
Tlil OP 1210-10, p. 11.0.
... - - -Section 4.0 Continued on Next Page- . - -
. -. . . _ -. - -. -. _.
- , '
- i s ' < . Page 53 TMI + March 18, 1986 <
Points , availabl.e if i j QUESTION 4.18 What immediate action should be taken for each of the following t
! situations? ' a.
A main steam isolation valve is inadvertently closed.
(0.75) , . j b.
During a stgam generttor tube leak / rupture, cooldown rate exceeds 100 F/hr with three HPI pumps running.
(0.75) c.
Subcooling margin is 15 F following a Rx trip.
(1.5) , { d.
Feedwater flow is not decreasing after a Rx trip.
(1.0) i ~ -~ _ ' ANSWER 4.18 a.
Trip the reactor. [+0.75] b.
Secure the non-ES selected MU pump. [+0.741,, c.
Trip all RCPs , i Initiate HPI
Initiate EFW + raise OTSG level to 90-95% Implement the loss of SCM procedure (ATP 1210-2) [+1.5] ,
d.
Take hand control of the MFW regulating valves and run MFW back.
If this is not effective, then trip the MFW ! pumps. [+1.0] ,
I . Reference (s) 4.18 1.
TMI OP 1203-42, p. 1.0.
! 2.
TMI OP 1210-5, p. 5.0.
3.
TMI OP 1210-1, p. 3.0.
,
, ' 4.
TMI OP 1210-1, p. 2.0.
l ! ! -Section 4.0 Continued on Next Page- , i i i !,
. . . , Page 54 TMI March 18, 1986 Points AYdilable OUESTION 4.19 Why does Operating Procedure 1102-la (Fill and Drain of Fuel Transfer Canal) prohibit filling the fuel transfer canal through the reactor vessel? (1.5) aMSWER 4.19 It causes a CRUD burst which causes high refueling radiation levels.
[+1.5] Reference (s) 4.19
1.
TMI OP 1102-15, p. 3.
. :. ~ QUESTION 4.2Q Following shutdown of the last RCP during plant cooldown, RCS pressure is controlled using the auxiliary PZR spray throttle valve. Unw and why is the auxiliary spray throttle valve adjusted to proper flow during cooldown.
(2.0) ANSWER 4.2D The valve is throttled open until PZR surge line temperature begins to increase, then is throttled sh'ut untiT PZR surge line temperature returns to its previous value.
This ensures that hot PZR water does not cause voiding in the top of the hot legs.
[+2.0] Reference (s) 4.20 1.
TMI OP 1102-11.
-Section 4.0 Continued on Next Page- ~ - - - - - - - - - - -
.
9 Page 55 TMI March 18, 1986 Points AYdilable QUESTION 4.21 Thete.are three (3) general principles that always apply to minimizing radiation exposure. One of these is use of shielding.
Slate the other two (2).
(1.0) ANSWER 4.21 1.
Minimize time of exposure.
2.
Maximize distance from the source.
[+0.5] each Reference (s) 4.21 1.
TMI Radiation Protection Training Manual.
,... m, -End of Section 4.0- -End of Exam- ~~ % . m x.. . .. .
. . . ____._---.____--______-_-----__-----____---- ___ ___-_----______-_--_.. __ EQUATION SHEET .___....--__--___-___--__--_--___---_---_.--------____---------_--____-__- . . Where my = m2 ( densi ty ) 1 ( vel oc i ty ) 1 ( a rea )1 = ( den s i ty ) 2 ( vel oci ty ) 2 ( a rea ) 2 -_..----_--__--_-___---___--______--________-_-_-__-__-_-__----_____----_-
PE +KE +P V where-Ved specific 1 i = PE +KE +P Y22 KE = mv PE = mgh
2 i l ,, li vol ume P = Pressure - - - - -.. - _ _ _ - _ _ - - _ _ - _ - _ - - _ _ _ - - - - _ _ _ _ - _ _ _ _ - - _ - - - _ - _ _ _ _ _ - - - _ _ - - _ - _ _ - - - - - - Q = sc (Tou t-Tin) Q = UA (T-Tstm) Q = m(h -h ) p ave i 2 --__--_--_---_-__-__--___--__---__-------_--_--__-----__--_--_---__----_-- p $= p 10(SUR)(t) P = P e /T SUR = 26.06 T = (B-p)t t
o I p _ - _ - _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - - - _ - _ _ _ - _ - - - _ _ - - - - - - - _ _ delta K = (Keff-1) CR Il-Keff1) = CR (1-Keff2) CR = S/(1-Keff)
2 - - - ~ - M = (1-Keff1) SDM = (1-Keff) x 100% (1-Keff2) K eff . __--_----___.________-_--______-_____-__--__-------_-_-___-__.-______--___ 1 = A e-(decay constant)x(t) In (2) 0.693 A decay constant = = g t t 1/2 1/2 -______-___-_-----__--___--__-------_-_-_______-_-___________-____-_______ Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 1010 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft3 = 7.48 gallons 1 hp = 2.54 x 10 Btu /hr
Density = 62.4 lbm/ft 1 MW = 3.41 x 10 Btu /hr
6 Density = 1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters
1 Atm = 14.7 psia = 29.9 in Hg g = 32.174 f t-lbm/lbf-sec ___-_-__--___-___-______------___-__---____________________-______________ e h
bioYn:aL/l(h?c,- hTTRl$inen E.
, . U.S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION , Facility: TMI-1 Reactor Type: _Eabcock & Wilcox Date Administered: March 18. 1986 ' Examiner: Gore, Huenefeld. Schreiber, Dudley Candidate: Answer Kev , INSTRUCTIONS TO CANDIDAIE1 Use separate paper for the answers. Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question ' are indicated in 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.
Category % of Candidate's % of Value Total Score Cat. Value Category
25 5.
Theory of Nuclear Power Plant Operation, Fluids and Thermodynamics i
25 6.
Plant System Design, ControlandInstrumentation
25 7.
Procedures - Normal, i Abnormal, Emergency, and Radiological Control
_ZL 8.
Administrative Procedures, Conditions, and Limitations 100 TOTALS' , Final Grade % t.
All work done on this examination is my own; I have neither given nor received aid.
I Candidate's Signature
. I .. - .. . . .. . . - . .. . .
. . Page 1 TMI March 18, 1986 Points Ara 11able 5.0 IHEORY OF NECLEAR POWER PLANT OPERATION d VIDS E D IBERM0 DYNAMICS (25.0) OVESTION 5.01 Indicate whether each of the following will INCREASE or DAMPEN a Xe oscillation.
1.
Doppler effect (0.5) 2.
Negative MTC (0.5) 3.
Power or flux level increases during an oscillation (0.5) ANSWER 5.01 1.
DAMPEN [+ 0. 5] 2.
DAMPEN [+0.5] . 3.
INCREASE [+0.5] (both frequency and magnitude) Reference (s) 5.01 1.
TMI Reactor Theory, p. 166.
. -Section*5.0 Continued on Next Page-. ._ . . . . ' . Page 2 . TMI , ! March 18,1986
l Points Available . QUESTION 5.02 The feedwater loop demand stations, the reactor demand station, and the S/G/Rx master are in " hand" with reactor power stable at 15% power. The operator commences a power escalation by l bumping rods out and T,,, increases. Which of the following describes the required operator course of action to bring T,,, back to its pre-rod bump level? (Selectone.)
(1.0) (a.) The operator must increase feed flow, restoring OTSG level, and lower the steam header setpoint slightly.
(b.) The operator must insert rods slightly, but not as far as
they were withdrawn. He must request the I&C technicians
to adjust the low level limits.
t (c.) The operator does not need to take any action. Doppler ,! a, feedback will return T,, to normal.
' (d.) The operator must over-feed the OTSG slightly, increasing OTSG inventory, then stabilize at a higher feed flow and
j a higher OTSG level, f ANSWER 5.02
(d.)
[+1.0] Reference (s) 5.02 . 1.
ICS Training Material.
, .
-Section 5.0 Continued on Next Page-
- - . - - - .- -.... - _-. .. -. . -, . - - - -.. -
-- ._ . - _ - _ __ < . i - i Page 3 TMI March 18,1986 Points Available , j OVESTION 5.03 i The reactor is shutdown with all rods on the bottom. An RCS { dilution occurs lowering RCS boron concentration from 800 ppmb
to 700 ppmb. As a result of this dilution, source range counts ' were observed to increase from approximately 3. counts per second ., to approximately 5 counts per second. Assuming equilibrium xenon conditions and no change in RCS temperature, eitlmatt the current value of reactivity in the reactor. The attached figure should be used to make this estimate. Assume an EFPD
I of 150.
You may make simplifying assumptions. Show your work j and state your assumptions.
(2.5) J f ANSWER 5.03 The reactivity change due to boron (from the attached figure) is i p2 - #1 = -0.076 - (-0.0865) = 0.0105 . i ] K-1 g"K-1 g(K2 - I) + 1
1 K j F1 * K CR K2-1 1" CR i
1 K-I
5
K1" 3 23 K i F2 " K2 Assume pi = Ki-1 and p2 = K2-I
p2 - F1 = K2-Ki=K2 - 5/3 K2 + 2/3 0.0105 = -2/3 K2 + 2/3
, 2/3 - 0.0105, y _ (0.0105)3 l K2" = 0.984 = 0.0163 = 1.63% shutdown - p2 "
!
-Section 6.0 Continued on Next Page-i - - - - - - - -.. - - - - - - - - - - - . . . . -. - . =. - - - - - - - - -
. . Page 4 TMI March 18, 1986 Points Available Alternate: ' P2 - #1 " - " - (fK - ) K-1 (K - I) K2-1
2
5 K K K - 2
y
3 2
E - K2+ - +
2 " 5 2_2 g y 3 2 3 2 - 2 2+2 K
3 0.0105 = 5. K2 - 2 K 3 2 3 2 (0.0105) (E K2_ g)+ =0
2-0.0175 K2,2 g(1-0.0105)-f=
0.0175 K2 + 0.65967 K2 - 0.66667 = 0-0.65967 * 1(0 d596712 + (4)(0.0175)(0.6667) _ 2(0.0175) -0.65967 * 0.69414, 0.03447 K
0.98486 ~ 0.985 2
2(0.0175) 0.0350 = -0.0154 = 1.54% shutdown p2 " 0 985 [+2.5] -Section 6.0 Continued on Next Page- - - . - - - - - - - -
. . Page 5 TMI March 18,1986 Points Availahle QUESTION 5.03 (continued) Figure 3 pg,;sf, Integral Boron Worth .roosic' 0-1000 ppmb
- 5;;,1,
, - - 12 f I l I l f I! ! l ! s ! ' I i f > !:so trPo ' e i !l l IJl 1 i i : I ! ' ' > i o-it - l l ll l !ll ! l l ll l
f ' l =$ , I l l ! l l l l l l !l ! l I I I .!0[rPo - ' - -
, ,,.. ,s v.: l ,l - ,,;e I t I ' /) _
, a j'l'!I l bh[/ l ' ' ! l '
,, n\\ l!l l ! ! ! l l / I I ! ! RD I i l l l A !Xk.k'I l l l l I ; : '[f,Dii!l lM k/f l i i ! l s . i ! % I i ! I l@4 f.
IIJI, j ~ I i : l i i ! I I h f./ II I $1' E ii!! I i l bW// i i I N d. ll i I
! I l l I l f l., b i l l l N )Z l i !LYIill I . _I 1 l : c FM ! I rtN ~! i
.,; i i evp' I ; w! '
i l! !'l lIl l llC 'l , I: i !,F i i I t i i I ycle 5. H Pl
.,; I l l ! /! lll l l l Legend ' t j g,]# g gggggg 'e i reo rreo-2.
,p ' 'sotreo
[i ll l ll l l " ?.'f M.. fi i l 'i i l ' .,. /i i i i l - l[l l l I I 0: . 200 300 400 500 600 700 too 900 1000 O too , . , , , . . , QUEST 10N 5.01 Boron Concentrotion k* g..., o,.. o,,,,,,,, j 17.0-Section.5.0 Continued on Next Page- - -
!
i - i ! ' ' Page 6 TMI March 18, 1986 Points atallable Reference (s) 5.03 1.
TMI OP 1103-15A, Operator Training - Reactor Theory, p.120.
QUESTION 5.04 If RV voiding occurs, how should it be collapsed prior to continuing a natural circulation cooldown? Assume that an RCP cannot be bumped.
(1.0) ANSWER 5.04 RCS pressure should be held constant at, or slightly higher than, the pressure at which the void formed to allow the void to condense.
[+1.0] Reference (s) 5.01 1.
TMI OP 1102-16, p. 6.0.
- i-Section 5.0 Continued on Next Page- . _ _ -. .
. . . Page 7 THI March 18, 1986 Points available OUESTION 5.05 a.
During core loading or fuel shuffling, what is the main purpose of keeping an inv6rse multiplication plot as fuel is added or moved? (1.0) b.
Why is it necessary to have a neutron source in the core during fuel loading or movement? (0.5) ANSWER 5.05 a.
To be assured that the reactor remains well away from criticality.
[+1.0] Alt: to predict criticality b.
To be certain the count rate is on the scale of the source range nuclear instrumentation.
[+0.5] Reference (s) 5.05 1.
TMI Reactor Theory, p. 124 and 113.
QUESTION 5.06 How does MTC change over core life? (1.0) ANSWER 5.06 MTC becomes more negative (at a given moderator temperature) as boron concentration is decreased.
[+1.0] Reference (s) 5.06 1.
TMI Reactor Theory, p. 152.
-Section 5.0 Continued on Next Page-
.__ . Page 8 TMI March 18, 1986 Points Anilable < QUESTION 5.07 . Ve,;t yg W W f %t " f opa to h h Asp h e r e, , ... v:= +. .......:=-., _
A
30'f ' ) j'80 j L f M ' The simple system shown above consists of two similar tanks , (Labeled A and B) and a pump that pumps through a throttle valve from tank A to tank B.
The pump is located 10 ft below
both tanks.
Below is a head vs. flow. curve for the pump as well as a system curve with tank B empty and the throttle valve full open. Use all of this information to answer the following questions about the thermodynamics / fluid mechanical behavior of the above system.
' a.
Assume that the vent valve on tank A is shut and the tank contains only water and water vapor (no air) at 70*F.
Further, assume that the vent is open on tank'B which is also at 70 F.
Both tanks are at a level corresponding to 30 ft above the pump suction.
The pump is running. When equilibrium is achieved, what will be the levels in tank A and B? (Atmospheric pressure = 32 ft of water at 70'.) (1.0) < b.
Assuming the tanks have the same cross-sectional area, } explain what would happen if the vent in tank A were
opened.
(1.0) By making a simple sketch, show how the system curve changes c.
with b.o.th 1) the level in tank B and 2) the position of the discharge throttle valve.
(2.0) -Section 5.0 Continued on Next Page-i ! - _..... _ _ _ _. - _ _ , _. _.. _. _ _
. Page 9 TMI March 18, 1986 Points AYailable
00ESTION 5.07 (continued) .
3L
[ set oh Ntad AC 1, 7Wf I i System Co rv e, so
, V
ANSWER 5.07 a.
The tank levels would remain at almost equal levels of 30 ft each.
[+1.0] b.
Tank A would lower by 16 ft, tank B would increase by 16 ft.
[+1.0] -Section 5.0 Continued on Next Page-
._.
. _ _. _ _
- j Page 10 TMI March 18, 1986 Points i available A, M B S:sts c.
, i [+ 1.0]
4 , l
1 __ _ A., v&u i<, MCt.d. l l I P i . ' [+1.0] J .., ~~ Reference (s) 5J)Z 1.
TMI Fluids Training Material.
-Section 5.0 Continued on Next Page- .
. Page 11 TitI March 18, 1986 Points ayailable QUESTION 5.08 The existence of a negative transient startup rate does not necessarily indicate subcriticality. Explain why this is so.
(1.5) ^NSWER 5.08 , Because the reactor can be prompt subcritical yet delayed supercritical.
[+1.5] NOTE: There are numerous correct (and incorrect) answers to this question, but the answer must address the effects of prompt and delayed neutrons.
-rence(s) 5.rg t.
TMI RN ar Theory Manual.
-~ l . -Section 5.0 Continued on Next Page- - - - - - . . - - - - -
_ _ _ _ _ _ - .. _
. Page 12 TMI March 18, 1986 Points Available 00ESTION 5.09 . . . . . . Xt ,- C.c.
... . - . . i . i I
' ' . . ,_ - _ . - -. - - - - -... - - , I , , , . A '8 C % e.
The graph above depicts the behavior of xenon resulting from successive instantaneous power changes.
Initial xenon concentration is at the 100% equilibrium value. An instantaneous power change takes place at times "A", "B",' and "C".
Using this graph, answer the following questions regarding xenon cause and effects.
a.
Was the xenon concentration just prior to time B at its equilibrium value? (0.5) d b.
Estimate the amount of time between time B and the time of minimum xenon concentration in interval B-C.
(0.5) What are the relative magnitudes of the power changes c.
that take place at time A and time B? (0.5) d.
Which is longer, the time to reach peak xenon after time A at af ter time C7 (0.5) The power af ter time C is what fraction of the initial e.
power (100%)? Select one.
(0.5) (1.) 0.0 (2.) 0.1 3.) 0.4 4.) 0.7 . -Section 5.0 Continued on Next Page- _ _ _ _ -____- _ _ _ _ _ _ - - -
. Page 13 TMI March 18, 1986 Points available ANSWER 5.09 a.
No b.
About 4 hours (*1) c.
The power increase at B is equal and opposite to A d.
The time to reach the peak after C e.
(2.)
[+0.5] each Reference (s) 5.09 1.
TMI Reactor Theory Manual.
-Section 5.0 Continued on Next Page- _ _ - - .1
- - . - . -.-. - _ -- . . . . - - . - . . , . f . Page 14 TMI March 18, 1986-i Points Available . QUESTION 5.10 , j C@N i W Eg , s <
% ' , ililE The graph above depicts the response of neutron power vs. time I to two (2) situations. Curve A is a response to an instantaneous positive insertion of reactivity. Curve B is a response to an
instantaneous negative insertion of reactivity of equal
magnitude. Answer the following questions regarding this i behavior.
' a.
Both curves show neutron power approaching a stable SUR.
- ] are the SURs for both situations equal in magnitude? (0.5) ~ b.
Both curves start out steeply, then rapidly the rate of ,
change of neutron power decreases toward a stable value.
Why is this? (1.0) In the situation depicted, the magnitude of reactivity c.
' inserted was much less than Beta.
If it had been much greater than Beta, What two (2) maior differences in response would you predict for the case of negative . reactivity insertion as compared to the response shown in ' curve B.
(2.0) . < i i ) ! Section 6.0 Continued on Next Page- -
i i w ,e ,,, - ,-+w~ w --,,,--,,c- , ,,y,.n, r,r,,--n,, e.- - a m --n-we-p.
-,,.,- w-n-,,-- .As- -- gv-n , - -4--e- - - -
. _ _ _. __ ._ _ _ _ _.
_.. .__ ._ . _. _.. _. .__ __ ) ' , , Page 15 TMI j March 18, 1986 i-Points available
ANSWER 5.10 a.
No [+0.5] ,
b.
Because of the effect of prompt neutrons.
[+1.0] !
c.
1.
The stable negative SUR would be more negative (i.e., j steeper curve).
[+1.0] i 2.
The magnitude of the prompt drop would be much greater.
[+1.0] , l ! NOTE: Other answers given for this part will be j weighed on technical merit; however, only these"two j answers will result in full credit.
l Reference (s) 5.10 1.
TM1 Reactor Theory Manual.
! QuESIl0N 5.11 ! Explain why control rod groups 5, 6, and 7 are overlapped, but ] groups 1, 2, 3, and 4 are not.
(1.0)
ANSWER Sd l
! Groups 1 through 4 need not be overlapped because they are not used for fine control.
[+1.0] i i ti l Reference (s) 5.11 . ' 1.
TMI Reactor Theory, p. 293 and 294, i ! ! < .! -Section 5.0 Continued on Next Page-
1 . . .. . . .... . . . . . .
, Page 16 IMI March 18, 1986 Points available @ESTION 5.12 Spraying emergency feedwater into an OTSG has a dramatic ef fect on RCS cooldown rate for two (2) major reasons.
State these ~ two (2) major reasons.
(2.0) ANSWER _5_d2 1.
The AFW is sprayed high in the OTSG therefore increasing the effective surface area for heat transfer.
[+1.0] 2.
The spraying of cold AFW into the steam space of the OTSG causes a depressurization similar to that occurring during pressurizer spray.
This lowers the saturation temperature in the OTSG.
[+1.0] Reference (s) Ll2 1.
B&W Plant Operations Manual.
-Section.5.0 Continued on Next Page-
. Page 17 TMI March 18, 1986 Points available OUESTION 5.13 a.
Why is the injection of cold SI water stressful to the RV? (1.0) b.
State two (2) factors that are necessary for RV failure? (1.0) ANSWER 5.11 a.
The cold SI water cools the inside wall of the RV, inducing tensile thermal stress, which adds to the existing pressure stress.
[+1.0] ~ b.
1.
Large flaw or crack (defect).
~ 2.
Low fracture toughness, due to irradiation embrittlement or vessel temperature below NDTT.
3.
High pressure / thermal stress.
Any two (2) [+0.5] each.
Reference (s) 5.13 1.
TMI Heat and Fluid Power, pp.176 through 182.
-End of Section 5.0- .
.. _.
- . - _ - -.. - - - - . .. _ _ _ _. - _ . Page 18 TMI March 18, 1986 i j Points . Available ) ., ' ! i 6.0 PLANT SYSTEM DESIGN. CONTROL AND INSTRUtiENTATION (25.0) ! OUESTION 6.01 ' i ' a.
Why must seal injection flow be limited during RCP restart i after recovery from loss of Intermediate Cooling and Seal Injection? (0.5) i b.
tion can pump restart be accomplished if total seal flow must be controlled below the 22 gpm seal injection flow - interlock of the RCP start circuit? (1.0) J ANSWER 6.01 a.
To limit RCP bearing cooldown rate. [+0.5]
i b.
Reduce the setpoint monitor low pot [+0.5] in the NNI I cabinet to zero. [+0.5]
pare r nte - GO w&ty f o s) k x C E 4'e{di Ghk.f(f o G ) ", [r(. ley 1/i3/gg { Reference (s) 6.01 '
1.
TMI AB 1203-16, Rev. 18, p. 6.0.
4 i i d i ! ! .
i , ! i i i i ) ? -Section.6.0 Continued on Next Page-i f
. Page 19 TMI March 18,1986 Points AYAllable OUESTION 6.02 a.
Why must safety rods be withdrawn using the auxiliary power supply while regulating rods can be withdrawn without using the auxiliary power supply.
(1.5) b.
Why is the relative rod position indication used instead of absolute rod position indication for monitoring sequence faults? (1.5) at1SWER 6.02 a.
Normal power to the safety rods is the hold bus which is two phase DC which cannot rotate the drive mechanism.
[+0.75] Normal power to regulating rods is six phase which can rotate the drive mechanism. [+0.75] b.
Relative position does not respond to a dropped rod. [+0.75] Absolute indication responds to a dropped rod and would reset the rods to manual and prevent automatic runback.
[+0.75] Reference (sl 6.02 1.
TMI OTM CRDM Lesson, pp. 12,30.
I-Section 6.0 Continued on Next Page-
. -.- . - - - - . -. . - - - - - -... . Page 20 ~ TMI l March 18, 1986 Points aya11able . QUESTION 6.03 - Draw a one-line diagram showing the 4160 V inputs to both ES- ~ buses.
Include the diesel generators and identify supply transformers. Show circuit breakers and indicate whether
normally open or closed. You do not need to show electrical loads.
(2.0) . l ^ ANSWER 6.03 N \\ [3Lhtdi~ ELECl?lOl-Di (*tti20~l~1.*U.)
T JVl X U N I T :l.
I f 1'u , f fo LaenVMo sworces vas:a ! I i 230IN .1 A AOL L il hux.
230IN . "# ft%tJ5.
- ~ TRi\\llS.
! mm mm mm mm } _ '/./G 1( V 6.clIW 6:1tw 't. IC /W i ~ , i
, i
' -
- - - ~ ~ -. .. .. _ _
. .,
- .
- . f f
. ' E'd E'3 E'3 ['d , l i U E S. ' liv _ ._ ,_ _ ' LE*G.s.
4lw . I i Components and connections [+1.0] '
Breaker positions [+1.0] ['o] [mj
- i ! Reference (s) 6.03 b' hl ' ' 1.
TMI OTM, Ch. 20, Electrical Distribution, p. 60.
' !' ',f-Section 6.0 Continued on Next Page-k ' . - _
. Page 21 TMI March 18, 1986 Points arallab.Le QUESTION 6.Q4 Describe the effect that failure of the feedwater RID (high) would have on the ' plant when operating at 100% power in full ICS Auto. assume no operator intervention.
(2.5) AMS' DER 6.04 FW demand calculator would increase FW demand.
[+ 0.5] T,,,would decrease.
[+0.5] Rx demand increases.
[+0.5] Rx demand high limit would prevent plant trip on high flux.
[+ 0. 5] Plant would trip on low pressure or variable temperature-pressure.
[+ 0.5] (Btu limit has no effect.)
p t rs (di (W th a vef w,.;q <;' <-ac 4 s (S t 64.( ,, _ Reference (s) 6.04 1.
TMI OTM Vol. 6, ICS System Description.
-Section 6.0 Continued on Next Page- , ~-~3 - - --
- - - .--s
. - _.. . -- . _ -. .-.- - -. , . (
, . !! l Page 22 TMI i Marcn 18, 1986 i Points j Available ' 'l ' QUESTION 6.05 , Exclain two types of damage which could result due to failure of check valves FW-V9B (at MFW pump discharge) and FW-V128 (between MFW valves and 0TSG) after tripping of the MFW pumps.
(2.0)
. ] ANSWER-6.05 , g ,{, . j. g c,, g. c c, j.'Z j j ; pg.,. , , Water hammer could be produced by steam-water-interactions in
- /"
the MFW piping.
[+1.0] 'Overpressurization could rupture co onents upstream of the MFW pumps.
[+1.0] 46,gauEg c(Luc,_, c in., g,g e gt,.,2 (y,zute c f , cif y # h a t c ~ n a w -, g.y y d h < d.7 a.m f/ c4,4 4 a u -Q c em g
Reference (s) 6.05 ff o lf ' "' ' A# " /""~"P 'N'"~N*'Y /V$<*a 3/z ajgiL l i ] 1.
San Onofre Incident, Nov. 21, 1985.
] 2.
TMI Plant drawing C-302-081.
, OUESTION 6.06 If ICS/NNI power to the selected pressurizer level' transmitter , i is lost, exclain ha arid why this will affect the Makeup Valve
j MU-V17 if it is in AUTO.
' ' (1.5) - .. ANSWER 6.06 MU-V17 will close [+0.7] because the pressurizer level indication will fail high (320 inches) [+0.8]. Reference (s) 6.Qfi
, ' 1.
TMI EP 1202-43, Rev'.' 0, p. 1.0.
. s , , j / ' ' , , _ -. ~ -Section 6.0 Continued on Next Page- . , . r t .. -... ._ _, _ _ - _. -, - _ _.,.. -,.,,. , _.,. -. ' . _, _.., _ _ _, - -. - .. _,. y
_ .__ ._ . - - __ _ _ _ __ _ . _- _ t . Page 23 TMI March 18, 1986 Points avatlabic . . QUESTION 6.QZ If the Nuclear Services Closed Cooling Water system is in its normal electrical lineup, how must this lineup be changed to remove NS-PIC for maintenance? (2.0) J ANSWER 6.07 NS-PIB must be removed from service and its breaker to 480 V ES Bus IP racked out [+0.5]. Then using the " kirk key" its breaker to Bus IS is racked in [+0.5]. It is then selected for ES operation [+0.5] and restarted before NS-PIC is removed ] from service [+0.5]. ! j Reference (s) 6.07 1.
TMI OTM NSCCW lesson, p. 16.
OUESTION 6.08 ' After a reactor trip, one (1) Intermediate Range NI reading decreases faster than -1/3 DPM.
Explain what this tells you about detector compensation and why.
(1.5) ANSWER 6.08 The detector is overcompensated. [+0.5] Because gammas decay
more slowly than the delayed neutrons, the subtracted compensation current increases with respect to the neutron current, reducing this reading more rapidly. [+1.0] Reference (s) 6.08 1.
- TMI OTM Vol. 2, p. 269.
-Section 6.0 Continued on Next Page- , , -, - - - _ < ~ _ m-,- ..., _.m., .. .. -, - _. - - - - - , -. -.. .
. . Page 24 TMI March 18, 1986 Points AYallable QUESTION 6.09 List, in sequence, the four (4) major automatic actions that ' occur in the Reactor Building Emergency Cooling System following an ES signal without loss of off-site power.
(2.0) ANSWER 6.09 1.
The two (2) fans operating will trip on a block one loading signal.
[+0.5] 2.
All three (3) fans will start automatically and operate at their slow speed on block two loading signal.
[+ 0.5] i 3.
The Emergency cooling System will go into its emergency mode of operation, opening the necessary valves automatically and starting the river water pumps (RR-PIA /B) to establish flow through the emergency cooling coils.
[+0.5] 4.
The normal cooling coil penetration isolation valves (RB-V2 and RB-V7) will close.
[+0.5] Reference (s) 6.09 1.
TMI OTM RB Emergency Cooling Lesson, p. 16.
, '
-Section 6.0 Continued on Next Page-
_ _ __ _ _ _ _ - _ _.
. _ _.
_ ._ i + .
Page 25 TMI March 18, 1986
Points Available OUESTION 6.10 a.
List the three (3) ICS signals that can be selected from
either RPS-A or 8 by toggle switches in Cabinet A.
(1.0) b.
State which RPS channel is normally selected and exclain
why.
(1.5) , ANSWER 6.10 a.
1.
flux [+0.25] 2.
RC flow (loop A and B) [+0.5] .I l 3.
RC pressure [+0.25] b.
Channel A [+0.5], because on loss of RPS-A power they automatically switch to Channel B.
Automatic transfer from B to A does not occur.
[+1.0] Reference (s) 6.10 ' 1.
TMI OP 1105-2, Rev. 17, p. 15.0.,, ' ,
, .5 , -Section 6.0 Continued on Next Page-i .... _, - - - _. - _- .. _ _. _.. - _ _ . _. _., _.. _ - _. . . .
. _ _ _.
.. . _ _.. _. . _ _. _ _ _. _ _ -. . . ! Page 26 TM1
March 18, 1986 l '. Points ! Available
i i +- - OVESTION 6.11 i If Condensate Storage Tanks low-low level alarms occur when they are supplying EFW, you are directed to depress the Emergency .) Alignment control pushbutton located on the control room console.
t a.
List the three (3) valves that this opens and staic Ehat this accomplishes.
(2.0) b.
What is accomplished by closure of the valves that this closes? (1.0) . ANSWER 6.11 sj 0 *t 3/z-s/w 6 a.
CO-V-8, 4ti=47 [+1.0] , permit EFW pump suction directly from condenser hotwell [+1.0] b.
prevents air from entering pump suction line [+1.0] (C0-V-6, , ! 7-not required)
Reference (s) 6.11 1.
TMI ATP 1210-10, Revision 7, p. 8.0.
t i
-Section 6.0 Continued on Next Page- , . ! -- _ _ _.. _ _ _, . _ _. _. -.. . . .. -. .--..,,. _ _ _,.. - _ _
. Page 27 TMI March 18, 1986 Points available . QUESTION 6.12 a.
AnSher TRUE or FALSE. The emergency boration flowpath from the Boric Acid Mix Tank to the Makeup Tank is through batch controller (MU12-FT).
(0.5) b.
Explain why, when terminating feed from the boric acid addition pumps CA-PIA /B, each pump must be stopped before its discharge valve is closed.
(1.0) ANSWER 6.12 a.
FALSE (bypasses it) [40.5] b.
Pumps are positive displacement.
Damage to pumps or other components may occur due to resulting high pressures if valves are closed first.
[+1.0] Reference (s) 6.12 , 1.
TMI OP 1103-4, Section 3.10, 2.
Station Drawing C-302-670.
-End of Section 6.0- .
. _. -.- .. _.
- __ .- . _. . . ! I !
Page 28 TMI March 18, 1986 Points , 4 - Available 7.0 PROCEDURES - NORMAL. ABNORMAL, EMERGENCY, AND_RADIOLQGICAL CONTROL (25.0) QUESTION 7.01 Power has been reduced to allow some mechanical repair work.
i i Time of completion cannot be easily estimated so the decision i is made to follow the " unplanned power return at nominal rates" i strategy of 0P 1102-4 " Power 0peration". Basically this strategy l consists of: (Select one.)
(0.75) ) (a.) maintaining regulating rods within the " steady-state" band.
j (b.) maintaining regulating rods within the " transient" band.
(c.) allowing rods to drift out with xenon.
(d.) ensuring that the shutdown margin requirements are not . exceeded.
ANSWER 7.01
I (b.)
[+0.75] i Reference (s) 7.01 1.
TMI OP 1102-4, p. 18.0.
! ' I i j l
-Section.7.0 Continued on Next Page- ! , ,,. -. . ,. -.. - - -.. . -.. -.-- ,.. -., .. - - - , - -
. . Page 29 TMI March 18, 1986 Points Aya110hlr 00ESTION 7.02 Given one (1) RAD of radiation exposure, which of the following sources of radiation would cause the most biological damage? (Select one).
(0.75) (a.) Beta radiation (b.) Thermal neutron radiation (c.) Gamma radiation (d.) X-rays ANSWER 7.02 (b.)
[+ 0.75] Reference (s) 7.02 1.
TMI Radiation Protection Training Manual.
-Section.7.0 Continued on Next Page-
. Page 30 TMI March 18, 1986 Points Ayallable OUESTION 7.03 According to Emergency Plan Implementing Procedure 1004.10 (Onsite/Offsite Radiological Monitoring), above hbat airborne radioactivity level should respiratory protection be used? (Select one.)
(0.75) (a.) 1E-9 Ci/cc (b.) 1E+9 C1/cc (c.) 1E-9 pCi/cc (d.) 1E+9 gpCi/cc ANSWER 7.03 (c.) - other values are ridiculously high [+0.75] Reference (s) 7.03 TMI EPIP-1004.10, p. 1.
. -Section 7.0 Continued on Next Page-
. -. - . .. - - - _ .. . . - . _ . . Page 31 TMI March 18, 1986 Points Available . ' OVESTION 7.04 " ! With feedwater valves in automatic, which of the two (2) actions listed below would tend to prevent the Main Feedwater block , valves from cycling after they have opened? Exclain.
(1.5)
(a.) increasing Main Feedwater pump speed
(b.) decreasing Main Feedwater pump speed . ANSWER 7.04 (b.) decreasing Main Feedwater pump speed.
[+0.5]
Decreasing speed causes feedwater demand to open the startup feedwater valve, holding it further from the block valve cycling l setpoint.
[+1.0] , t Reference (s) 7.04 1.
TMI OP 1102-2 and observation of operations.
!
i i a ! . ! ! -Section 7.0 Continued on Next Page- . (
, - _ _ _. _ _ _ _ __ . ' Page 32 TMI March 18, 1986 Points Available - OUESTION 7.05 i A shutdown margin calculation is performed during a cooldown in accordance with the Shutdown Margin and Reactivity Balance ' procedure, OP 1103-15A. Is this calculation more conservative with control rod groups 1-4 fully ~ inserted or 100% WD? Why? (1.5) ANSWER 7.05 Control rods fully inserted. [+0.5] The shutdown margin calculation assumes all (with the exception
of Group 8 and the most reactive rod)'~ rods are fully inserted.
[+1.0] --- - ' ~ ,, J Reference (s) 7.05 1.
TMI OP 1103-15A, p. 11.0.
- -- Male: The reactivity calculated for the SDM is based on CRG 1-7 at 0% WD minus any stuck rods. This is a SDM and not a , reactivity balance. Actual core subcriticality at nominal rod positions (CRG 1-4 at 100% WD with no stuck rod) is less negative by approximately 2% Ak/k.
, , ! -Section J.0 Continued on Next-Page-i
I r-e , _., ,-----s ny, y - r , s.-.----m, - m .. -
- ..m
.~ --,-
pr
-, , ,v- -
.. . . - -- _= . j Page 33 TMI j March 18,1986 Points > available QUESTION 7.06 At what reactivity limit must the reactor be maintained if any condition occurs which physically or administratively delays criticality? (0.75)
ANSWER 7.06 At least 1 %Ak/k subcritical [+0.75] . Reference (s) 7.06 1.
TMI OP 1103-8, p. 2.0.
_, _ _ QUESTION 7.07 a.
During a power escalation, da NIs tend to read HIGH or LOW? (0.5) b.
What is done to remedy this effect? (1.0)
ANSWER 7.07 a.
NIs tend to read low.
[+0.5] b.
Heat balance checks (and NI adjustments when necessary) are performed at frequent intervals during the power escalation.
[+1.0] Reference (s) 7.07 1.
TMI OP 1102-2, p. 6.0.
-Section.7.0 Continued on Next Page- ) i , - - - - - - - - -
. _. _ -_ ._. I Page 34 TMI March 18, 1986 .i l Points ' Available OVESTION 7.08 -
When the reactor is at power, how is available shutdown, margin ' ensured? (1.0) ! ANSWER 7.08 i The minimum shutdown margin exists provided that the rod inser- - tion limits are not violated per Technical Specifications.
, j [+1.0] i l Reference (s) 7.08 ] 1.
TMI OP 1103-15A, p. 3.0.
>-- OVESTION 7.09 i State two (2) major hazards regarding opening of the RCS prior to degassification.
(1.0) ANSWER 7.09 1.
Explosion [+0.5] 2.
Personnel radiological exposure [+0.5] . ' Reference (s) 7.09 1.
TMI OP 1102-12, p. 15.0.
, i-Section 7.0 Continued on Next Page- , , r ... -. , _ p v - - , .,-_.m , .- .--.---. -y - . - -. ---r -,, , - ,,
,. - . .. _ - - _ _ _ _ _ _ _ - - - i . Page 35 THI March 18, 1986 Points
Available OVESTION 7.10 Analyze the attached cooldown curve inaccordance with the cooldown rate limitations given in OP 1102-11. State any , ' departures from that guidance.
(Note: the scale on the attached graph has been adjusted for ease in plotting five-minuteintervals.)
(2.5) ANSWER 7.10 The slowing of cooldown rate that occurs during the first hour of cooldown was handled improperly. A new reference line should have been drawn rather than " catching up" to the old reference line. [+1.25] Starting in the second hour, the cooldown rate was increased with new reference lines drawn. According to the - guidance, a hold should have been established to bring temperature back in line with the original reference line.
' [+1.25] .~- Reference (s) 7.10 1.
TMI OP 1102-11, p. 32 (ENCL I).
_ . , . i . . i l-Section 7.0 Continued on Next Page- .. . . _ - . - _
. . Page 36 THI March 18, 1986 Points available QUESTION 7.10 (continued) .
$UPPLEMENTAL DATA $,aCET !!C2.}] 6% - - * * - - -PLANT MEAPJP/t00agwg _ FIGeet 5 8evitten 54 CATA $HE[t - - .m_ - , \\ (. - , 500 ~'_ ^ ' n .e . -. _ - - - .
- , ' - - . _ '. ' g ' ' ' ' s t . ' ,
.-
a.
.u," ,.
. . . , _-- -.. l,,, - . ._- . __
- '
a.
. - -.. , L , . _
- -,
-- - 2,.
- "
, __- ($ ' O,' ' ' .- , us
, II l t' I
- =
-.. - p$ 300 _. . , ' '
- .','.
t ,- 1. .. .: I: .' !}
- _s
= . s
, '
= ,
,' ' ? , h 200 = , .. ' 1,, - . I
1 I I I 100
- L - h.n,[ pu, 3fy - b - - IsaA small iewa atet egne f A.,g,4, -Section 7.0 Continued on Next Page- ,
.. - - ...-. - . J . + Page 37 TMI March 18, 1986 Points Available
OVESTION 7.11 , , The main fuel handling bridge is near the deep end of the transfer canal with a fuel element loaded when fuel transfer canal level is observed to be decreasing:at a rapid rate warranting immediate action (i.e., level decrease of > 6 inches
per minute).
State three (3) actions that should be taken immediately.
(1.5) i ANSWER 7.11 1.
Evacuate all unnecessary personnel from the RB.
[+0.5] 2.
Lower the fuel element to the bottom of the pool.
[+0.5] 3.
Close FH-V-1A and FH-V-1B.
[+0.5] . Reference (s) 7.11 .. 1.
TMI OP 1203-43, p. 2.0.
1 ,
-Section.7.0 Continued on Next Page- .. -, _ _ . - . - ._ _ _ _ _ _ _. - - -. -__ ._. -, -
. . Page 38 TMI March 18, 1986 Points Available QUESTION 7.12 The RCS natural circulation cooling procedure gives four (4) indications to.be used for verifying the existance of natural circulation. State four (4) of these indications.
(2.0) ANSWER 7.12 1.
RCS AT increases to approximately 30'F to 50'F (dependent on Decay Heat) and stabilizes and TH is ( 600*F.
2.
Incore thermocouple temperatures stabilize and are tracking T-H 3.
Cold leg temperatures approach saturation temperature for sec65dary side pressure (normally within 5 minutes).
4.
Verify heat removal from OTSGs.
.. .- a.
Steam flow indication.
b.
Feed flow indication.
[+0.5] each ~ Reference (s) 7.12 1.
TMI OP 1106-16, p. 6.
. -Section 7.0 Continued on Next Page-
_ _ . _. _ . . Page 39 TMI March 18, 1986 Points available QUESTION 7.11 ,
I The OTSG tube leak / rupture procedure,1210-5, states criteria which should be ccasidered regardihg isolation of OTSG's.
This procedure considers all combinations of the following five (5) factors: RCPs on or off
Condenser available or NOT available a One OTSG leaking
Both OTSGs leaking at greater than 9/1 ratio
Both OTSGs leaking at less than a 9/1 ratio i
_. _,, , Under Ehich two (2) combinations of these five (5) factors j should isolation be most strongly considered.
(2.0) . J f ^ ANSWER 7.13 TM. ' ' ~ ' v 1.
RCPs on, condenser NOT available, one OTSG leaking i 2.
RCPs on, condenser NOT available,.both OTSGs leaking ) 9/1 [+1.0] each ~ ' ~~ Reference (s) 7.11 1.
TMI OP 1210-5, p. 13.
I
Section 7.0 Continued on Next Page- - i , ,m ,,=,:- - - -, - -,+1-
+-me , e- ,, ay+ . , - -,,n-- - + -,,
-. .. . .- .
Page 40 THI i March 18, 1986 j Points Available QUESTION 7.14 What immediate action should be taken for each of the following situations? a.
A main steam isolation valve is inadvertently closed.
(0.75) b.
During a stgam generator tube leak / rupture, cooldown rate exceeds 100 F/hr with three HPI pumps running.
(0.75) , c.
Subcooling margin is 15 F following a Rx trip.
(1.5) d.
Feedwater flow is not decreasing after a Rx trip.
(1.0) . !
ANSWER 7.14 a.
Trip the reactor. [+0.75] b.
Secure the non-ES selected MU pump. [+0.75] c.
Trip all RCPs Initiate HPI Initiate EFW + raise OTSG level to 90-95% Implement the loss of SCM procedure (ATP 1210-2) [+1.5] d.
Take hand control of the MFW regulating valves and run MFW back.
If this is not effective, then trip the MFW pumps. [+1.0] , Reference (s) 7.14 1.
TMI OP 1203-42, p. 1.0.
2.
TMI OP 1210-5, p. 5.0.
3.
TMI OP 1210-1, p. 3.0.
4.
TMI OP 1210-1, p. 2.0.
' -Section 7.0 Continued on Next Page-
- , .- ., . . . -- . , - - '
__ -.. . _ _ _ - _.
-. _ _ __ _ , - . Page 41 TMI March 18, 1986 Points Available OUESTION 7.15 ' There are three (3) general principles that always apply to , minimizing radiation exposu're. One of these is use of shielding.
, State the other two (2).
(0.5) l ANSWER 7.15 1.
Minimize time of exposure.
2.
Maximize distance from the source.
, [+0.25] each j Reference (s) 7.15 ' 1.
TMI Radiation Protection Training Manual.
i ! i . j .
i j . , -Section J.0 Continued on Next Page-1.
!
) ._.
... =.. - - -. - - .,. -,.--.. - - .. - - -, - . - -
.. . _ _ _ - , , ~ . Page 42 TMI March 18, 1986
Points Available QUESTION 7.16 Following a LOCA, should HPI be throttled in each of the following separate situations? Justify your answer.
a.
Flow from HPI pumps A, B, and C read 510, 530, and 550 gpm respecgively. RCS pressure is 800 psig and RCS temperature is 450 F.
(1.5) b.
Flow from each HPI pump is 480 ggm, RCS pressure is 500 psig, RCS temperature is 350 F, and PZR level is 15" 30 minutes after a loss of coolant accident.
(1.5) ! ANSWER 7.16 ! a.
Yes [+0.6] to prevent pump runout (do not throttle below ' 500 gpm) [+0.9] b.
May be throttled [+0.6] since greater than 25 F subcooling and PZR level greater than 0" [+0.9] , Reference (s) 7.16 ! 1.
TMI OP 1210-10, p. 3.
-End of Section 7.0- , I i l . . -.,, . _ _ _ _,, __ , __,_ ., _ _ _ _ _... ., , . _,. ,
.. __. _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . s .
Page 43 TMI March 18, 1986 Points Available 8.0 ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS (25.0) QUESTION 8.01 ' Prior to exceeding 300 psig and 200'F in the reactor coolant system, OP 1102-1 specifies minimum shift operations manning.
State these minimum manning requirements.
(2.5) ANSWER 8.01 _ 1.
One (1) Shift Supervisor - SR0 qualified.
[+ 0.5] 2.
One (1) Shift Foreman - SR0 qualified.
[+ 0.5] 3.
Three (3) Control Room Operators - at least two (2) R0 qualified.
[+0.5] 4.
Five (5) Auxiliary Operators.
[+ 0.5] 5.
One (1) Shift Technical Advisor.
[+ 0.5] Reference (s) 8.01 1.
TMI OP 1102-1, p. 21.0.
00ESTION 8.02 If the deluge / sprinkler fire suppression system for one of the Diesel Generator rooms becomes inoperable, what must be done? (1.0) ANSWER 8.D2 Establish a continuous fire watch [+0.4] with backup fire suppression equipment [+0.3] within l' hour [+0.3]. Reference (s) 8.02 1.
TMI TS 3.18.3.
-Section 8.0 Continued on Next Page-t __
_~ _.. _ _ _ _ _ _ _ _. . . . Page 44 TMI March 18, 1986 Points Available OUESTION 8.03 The attached Figure 8.03 is a composite of two figures from your Technical Specifications.
Identify (name) both the outer and inner curves and state when operation _is allowed in Regions A, 8 and C.
(2.5) ANSWER 8.03 Outer curve - RPS trip max. allowable setpoints.
Inner curve - limiting condition for operation.
Region A - never operate.
Region B - operation for 4 hours if immediate corrective action is taken.
Region C - continuous operation.
[+0.5] each Reference (s) 8.Q1 1.
TMI TS 2.3.1 and 3.5.2.
. . -Section 8.0 Continued on Next Page- -
_
. . Page 45 TMI March 18, 1986 Points Available , inermal Power Level.
L 123 \\ , ( 17.103) 110 (103) (17,1,.) /, l 10.'C.'I .e S3:e - - ICQ l. l h =.l.0 Ng = 1,23 - ,32., ,, 10.0.92
, - 90 (25,50) (-35,25) .;;,30,, - 30. 10.0.30
-
- 9'#"
A Reps on D' ' (;g,gg,7) , , O G - 60 ( 35.57.7) , - . .%
' .. 50 r.0 - (35,25.1) (-3 5,3 0.1 ) "
- , , ' -.20 , $
, _ 10 .r , , , ,. , , t. . , , -53
30 20 .I0
10 20
,40 - 50 Reactor Power tscalance, 5 . ' FIGURE 8.03 (0uestion) -Section 8.0 Continued on Next Page-
- - - - - - - .- . . Page 46 TMI - March 18, 1986 Points ' Available i QUESTION 8.04 i Following refueling, the reactor is being brought from cold a
shutdown to hot shutdown. Under wha 1 conditions, if any, do i Tech Specs allow both doors of the personnel hatch to be open
for transport of equipment into the reactor building? (1.0) j ANSWER 8.04 When RCS P ( 300 psig (T > 200 F since above cold shutdown) (fuel is in core) (P may be as high as 485 psig dv'en at 2'00 F) l [+1.0] " ! i Reference (s) 8.04 1.
TMI TS 1.2.1, 1.2.2, 3.6.1.
! l OUESTION 8.05 During a response to an emergency, the Emergency Director decides to direct deviation from the Emergency Operating Procedures.
Who must concur with this decision and what additional consultation is imperative prior to implementing this decision? (1.5) ANSWH L6 d5 Duty SR0 must concur [+1.0]. Parsippany Tech Functions Center .should be consulted [+0.5]. . ,
Referertce(s) 8.05 ] ' i 1.
TMI EPIP 1004.2, Section 3.1.
! ! -Section 8.0 Continued on Next Page- , . $ +x-u ,. -., -.,,,,.,, -. ,,,, _.,, ,.,-,,,--,g,, ,,r., ,, ~., ~-..,.
-.. -. . . . _ _ - - -. . - -. - - - - - - .-- -. -. ' , Page 47 TMI March 18, 1986 Points Available i ~ QUESTION 8.06 ' For each of the following situations, indicate whal REQUIREMENT, if any, applies and whal ACTION, if any, should be taken.
Consider each situation separately.
i j a.
Diesel generator A's operability load test, which is required every 31 days was due seven days ago.
The last l three tests were completed 38, 70, and 102 days ago, j respectively. The plant is at 100% power.
(1.5)
b.
The plant is at 295 F and heating up at 1 F per minute, j when a decay heat removal pump is found inoperable.
(1.0) c The plant is at 100% power when it is determined that the discharge valves for two emergency feedwater pumps are
l failed shut.
(1.0) ANSWEE.1 % , Each test must be within 25% of required time [+0.35] and i s.
each three (3) consecutive tests must be within 3.25 of required time (not met) [+0.4]. Declare DG A inoperable [+ 0. 25]. Prove operability of DG B within I hour [+0.3]. Conduct load test on DG A [+0.2].
J ' Decay heat removal pumps are not required until Rx is ! critical. No action besides repair of pump is required.
[+1.0] . Three (3) independent EFW pumps and associated flowpaths c.
shall be operable. [+0.25] With more than one EFW pump-l i or flowpath inoperable, restore the inoperable pumps or i flowpaths to operable status [+0.25] or be subcritical i [+0.25] within one hour. [+0.25] i j Referenc.e(s) 8.06 1.
TMI TS, pp. 1-8, 3-25.
Question Bank 007914
i ) -Section 8.0 Continued on Next Page-I i ! i i 3%,.,, c _. __,., ..i_,m, .. <g._.
_-- _.m._.. _ .,_..,--,.r.-,-._m...,_.m.
,_, _,.,_,- -.-c- , . - - --.,.m . -, _. -. - - - - -
..,. - . - -. ..- . _ - _. - - ! < .
-
- .
, Page 48 TMI March 18, 1986 Points available QU QTION 8.07 A worker receives an acute radiation exposure _ estimated at 30 REM whole body dose. He is not contaminated during the incident. You may refer to EPIP 1004.16 which is provided.
! a.
Dnes this require activation of the Emergency Plan? (1.0) i i b.
Where should the person be taken for treatment, and walt ! form of transportation should be used? _ (1.0)
. t /J!?!ER 8.07 , a.
No [+1.0] i b.
Hershey Medical Center [+0.5] ! Conventional transportation is OK [+0.5] N ferenc~e(s)_S E f.
1.
TMI EPIP 1004.16.
., QUESTION 8.QS '
Under what condition may a deviation from plant Tech Specs be l proper? (1.0) l s Alt 5WER 8.08
- '
, ' In an emergency, when immediately needed to, protect public health and safety [+0.5] and no action consistent with license conditions and TS that can provide equivalent protection is ! immediately apparent [+0.5].
i . Reference (s) 8.08 1.
TMI AD 1044, Rev. 13, p. 18.0.
< J-Section 8.0 Continued on Next Page-t ,
o
- . - - ~ . - - - -,, ,, - - -.%., - - -, -, , --,+----,w y - -v
. . Page 49 TMI March 18, 1986 Points Available . QUESTION 8.09 For independent verification of manual valve position: a.
State the normal method of verifying proper position.
(1.0) b.
State the verification method for valves that are difficult to get to and Ehen this method is acceptable.
(1.0) ANSWER 8.09 a.
Each person physically turns the valve in the closed direction.
[+1.0] b.
One person operates the valve and the other observes [+0.5] -- acceptable only when the observer can certify that operation was sufficient to determine proper valve position [+ 0. 5]. Reference (s) 8.09 1.
TMI AD 1029, Rev. 18, p. 26.0.
. , -Section 8.0 Continued on Next Page- .
_.
., .g .... . -_ _ _.- $
, ' .,, ., . , .. . . . Page 50 TMI March 18, 1986 - i Points Available i
,
OUESTION 8.10 . During a plant transient, the Shift Technical Advisor gives
you, the Shif t Supervisor, seme advice that is contrary to your judgment. What is.your responsibility for following his advice? ' (1.0) ! , ANSWER 8.10 In any conflict the Shift' Supervisob is responsible.
He must follow his own judgment.
[+1.0] - d . ..
Reference (s) 8.10 - i .% ! 1.
TMI AD 1029, p. 33.
. ! i , i l ! ' l '
i + , , 't pd - ' /.. ,- . , ' - ., - _, , > - .,' ~ ,- L ', / / ] a p. ; -Section 8.0 Contin,ued bn Next Page- - ,
e p- %~ ~ * -.p p.
. c
- .
< .-.-_ - ..- . - - -... , , ?.-,. .. ,,.,. -. - ~. _,.,.. ., -. - - -.. -, -. ... - -,
_. - .. . . - . .._..- -. -. . -. -.. - s . Page 51 TM1 March 18, 1986 i Points Available , , l OUESTION 8.11 a.
What are the three (3) cases for which a procedure Temporary Change Notice (TCN) may be used? (2.0) b.
What is meant by a "Two Member of GPUN Management Staff" type TCN? (1.0) -
ANSWER 8.11 ! a.
1.
When existing procedures do not apply due to plant ' modifications, or plant performance not covered (short time only).
[+ 0.7] 2.
When a permanent revision is inappropriate due to temporary conditions.
[+0.7] 3.
When time or plant conditions do not permit use of a
Procedure Change Request.
[+0.6] b.
A TCN may be approved by two Responsible Technical Reviewers ' knowledgeable in the area affected by the procedure.[+0.4] For changes which may affect the operational st.atus of unit systems or equipment, one Reviewer must be a member of unit
management or supervision holding a SR0 license on the unit. [+0.3] The change must not alter the intent of the , original procedure. [+0~.3] < Reference (s) 8.11 l 1.
TMI AD 1001A, Rev. 9, p. 26.0.
2.
TMI AD 1001G, Rev. 9, p. 11.0.
-, . 3.
TMI AD 1001A, Rev. 9, p. 31.0.
l ,
-Section 8.0 Continued on Next Page-i . ,p -.,. -,vn,+.-n-~,yanww,,-*. .,-,.y.,,n,,, -,,,..w,- .-+.n--w,,.w.-y,e.,9-ne-,- ,, - -,. e m, -e r e- ,,,-w.pe, pvg,,,q-m, ye-,gp--v-m..----o,-een,.w--.m ,,
&kJ+.bmr4
- e%-
-. a m - w w--- - Ar.
e e a a - -- ' ., . i Page 52 TMI March 18, 1986 Points Available i ! . J OVESTION 8.12 Requirements in 10 CFR 50.72 establish categories of events and times requiring NRC notification using the " Red Phone" of - the Emergency Notification System.
a.
How soon after spurious ES actuation must notification be ! made? (0.5)
b.
If the " Red Phone" is inoperative, what must be done? (1.0) ANSWER 8.12 , .s a.
4 hours [+0.5] b.
Use commercial or dedicated telephone, or any other method , which will ensure reporting-as soon as practical.
[+1.0] ._ t I Reference (s) 8.12 1.
10 CFR 50.72 > 2.
TMI AD 1044, Rev. 14, Enclosure.1.
d OVESTION 8.13 i Chemicals to be used for chemical additions to the RCS must-l come from containers that are or ' , and (1.0) . ' ANSWER 8.13 Unopened [+0.4] or sealed [+0.3] and tagged [+0.3] Reference (s) 8.13 l 1.
TMI Ops Dept Memo 83-3.
. l-Section 8.0 Continued on Next Page-l
-. - - - _ _, _ -. _,, - - - ..-.-,.-_- ., -. . -, - -,., -....,_..., - - ,.,,.. -.. -,... -
, Page 53 TMI March 18,1986 Points Available QUESTI0ft8.14 Explain why a caution tag has been phaced on the toggle switch labelled MC/855 located on the Mod Comp computer.
(1.5) ANSWER 8.14 Due to errors in the Mod Comp which make it unusable for determining subcooled margin using the incore temperature from the 5 highest thermocouples when RC pumps are off.[+1.0] The purpose of the tag is to ensure updating of the plant status board (behind the switching and tagging CRO).[+0.5] Reference (s) 8.14 ~ ~ 1.
TMI Ops Dept Memo 85-4.
-End of Section 8.0- -End of Exam- __ h
. _ - - . . __________________________________________________________________________ , i EQUATION SHEET __________________._______________________________________________________ . . Where mi = m2 ( den s i ty ) 1( vel oc i ty)1 ( a rea )1 = ( densi ty) 2 ( vel oc i ty) 2 ( a rea ) 2 __________________________________________________________________________
1 i = PE +KE +P Y22 where V = specific KE = mv PE = mgh PE +KE +P V
2 i i ~l-volume P = Pressure __________________________________________________________________________ Q = mc (Tout-Tin) Q = UA (T-Tstm) Q = m(h -h ) p ave i 2 __________________________________________________________________________ P = P 10(SUR)(t) P = P e /T SUR = 26.06 T = (B-p)t t g T p __________________________________________________________________________ delta K = (Ke f f-1) CR (1-Keff1) = CR (1-Keff2) CR = S/(1-Keff) i
' , M = (1-Keff1) SDM = (1-Keff) x 100% II-heff2) Keff . - - -- ___________________________________________________________.______________ 1 = A e-(decay constant)x(t) In (2) 0.693 A decay constant = = g t t1/2 1/2 __________________________________________________________________________ Water Parameters Miscellaneous Conversions 1 gallon = 8.345 lbs 1 Curie = 3.7 x 1010 dps 1 gallon = 3.78 liters 1 kg = 2.21 lbs 1 ft3 = 7.48 gallons I hp = 2.54 x 10 Btu /hr
,
6 Density =62.4lbg/ft 1 MW = 3.41 x 10 Btu /hr Density = 1 gm/cm 1 Btu = 778 ft-lbf Heat of Vaporization = 970 Btu /lbm Degrees F = (1.8 x Degrees C) + 32 Heat of Fusion = 144 Btu /lbm 1 inch = 2.54 centimeters
1 Aun = 14.7 psia = 29.9 in Hg g = 32.174 f t-lbm/lbf-sec __________________________________________________________________________ , J l
, t
' ._ _ _.
. ~ _ ._ -
1004.16- " Revision 4 . . 09/05/84 , IMPORTANT TO SAFETY - NON-ENVIRONMENTAL IMPACT RELATED THREE MILE ISLAND NUCLEAR * STATION UNIT NO. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.16 ' CONTAMINATED INJURIES / RADIATION OVEREXPOSURE Table of Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0
2.0
3.0
4.0
5.0
6.0
7.0
8.0
9.0
, ~ '
' _ @ v , x' 9 9 /73 a c /L t c a v 7/s/se
r i M [/ Signature / Date j
Document ID: 0031H l , un ' g ' ,- / /- , .. _.
-- l
- .. ~ - '- 1004.16 Revision 3 ' .' THREE MILE ISLAND NUCLEAR STATION ' ' UNIT NO.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE 1004.16 CONTAMINATED INJURIES / RADIATION OVEREXPOSURE 1.0 PURPOSE To define the conditions where person (s) working at Three Mile Island and exposed to ionizing radiation greater than 25 REM (acute dose, or ill or injured and contaminated or potentially contaminated with a ive material will be removed from site to Milton S. Hershe c Center (HMC), Hershey, PA. To further define the steps in 1 noti fying HMC to allow time for pre aration of the Radiat' Eme ncy Area (REA) to receive the injur s). To provide for eral levels of treatment based o n s verity of the inju 9 and the degree of exposure /contami involved. The S i Supervisor / Emergency Director is responsi bor implementation of rocedure.
--
NOTE: All persons h injuries or.ill 'n a radio- -
logically tam'iJtated area or involvi adioactive
materia sh be considered co t in ed'until
proven er e.
--- -- ----------------- - --
=. . 2.0 ATTACHMENTS ' ,. 2.1 Attachmen I, W ological Contro Che kiist for Contaminated Injured n 3.0 IPPLEMENTATION CRITERI A . - 3.1 Person (s) are injured in a radiologically controlled area and have a contaminated (greater than 100 cpm above background) injury that can be treated on-site and released.
3.2 Person (s) are injured in a radiologically controlled area and must be transported off-site for medical observation / treatment before being surveyed for contamination.
' .. 1.0 .
,/ e /= - - - - - - - - - - - - - - - - - - . . - - - - - - - - - - - .. - -. - - - - - - . - -
1004.16 ' Revision 4 - . . . . - 3.3 Person (s) are injured or ill and h' ave, or have the potential for, radioactive contamination on their clothing or skin and must be transported offsite for medical observation / treatment before decontamination can occur.
3.4 Person (s) have received acute radiation dose in excess of 25 REM.
4.0 EMERGENCY ACTIONS 4.1 The Shift Supervisor / Emergency Director and'Gro g-Rg o ogical Controls Supervisor shall be notified immedist u n discovery of the injured personnel.
. _____________-____ _ ___________________ __ _ ______________________ NOTE: T .'. sing steps may erfo med concurrently.
- - 5) __ _______ -_ _ _ _ _ _ _ _ _ _ _ _. _____________ __ _ ________________ 4.1.1 he 'ift Superviscr/ m gen j Oirector, upon notifica-J tion of injured pe son e, shall: t " NotifySl(h cul Personnel at 450.
If Site a.
, Medic 1 P s nel are unavail he Shift Super- ~^ vi -/E gency Director sh h e"first aid in.2tered to the i ill personnel.
u.. _--__-__-_-__ _ __ _ ______________ ___ __ ______-__________________ NOTE: .f ossible the Shifs Su visor / Emergency Director nvuld provide the F c First Aid personnel with
. specific ingress /eg route for access and - e patient transfer.
The Shift Supervisor / Emergency . Director should consult with Radiological Controls
for this route if necessary.
. ______________________________________________________________________ i b.
Ensure that First Ald/ medical personnel evaluate the injury, to determine the need of medical treatment beyond that provided by on site personnel and that Radiological Controls evaluate the radiological condition of the victim (if injury involved radio- . 2.0 ,
we - - . . .m.
- m.. .. .. . - . .-.m -. . - - - . . -
_ _ _ - - _ _ _ _ _ _ _ _ 1004.16 - - Revision 4 active contamination) and both report their assess- ' ment back to him.
.-----
NOTE: Attachment I is a checklist for Radiological actions. : -_
c.
If offsite medical _ assistance is requi d, the Shift Supervisor / Emergency Director (or h acignee) will notify Dauphin Co. EOC by diali - 1 and repeat the following message: "THI , NAME/ TITLE MI NUCLEAR STATION.
'l REQ ST AN AMBULANCE AND- ~ 0 REPORT TO Ti. WIT PROCESSING CENTER.
WE , . i D 1A E (POTENTIALLY C0t INATED PERSONNEL WITH
FOLLOWING INJIRI BRIEF DESCRIPTION OF INJURIES) REQUIRING : I* SSISTANCE."
_, Call Se - ' Extension 8030 40 to inform , ,
.. . sec v f offsite medical ssista,ce arrival to can direct off i . d cal personnel to <a <. e injured person.
Tr.
o. t Supervisor /Emergcm:y irector shall a s 'i.' late the requirements of I EPIP 1004.19 "Emer : y Dosimetry / Security Badge Issuance" d.
If appropriate, declare an Unusual Event in accor-dance with EPIP 1004.1 and perform actions as required in Step 4.5 below.
4.1.2 The Shift Supervisor / Emergency Director shall direct personnel with minor injuries, not requiring more medical attention than site first aid, to the decon facility for . decontamination and treatment of the injury, per step 4.2.
3.0 , e ---.---y ,, - , - -, -. , , ~, - - , r y-
. - - - - _ _ _ -_ r.
. 1004.16 -. - Revision 4 , ..--.. ' 4.2 The Shift Supervisor / Emergency Director shall, with concurrence of , the available site medical and radiological controls personnel have the victim transported outside of the radiologically controlled area, if the injury and contamination levels will allow movement, for further treatment and surveys.
__------------------------------------------- ---- - --------
NOTE: To prevent the possible spread of c . mi a ion, the
Shift Supervisor / Emergency Directo i onsider - . ' . having the contaminated person's e ua i n route .
announced over the page.
------------ ----------- -- - ------------------
4.3 If the injury a Radiological Con o ersonnel shall assess w itionexposureandhh7?adioactivecontamination the degree r
prior to mov from site.
- ------------------- ----- _------------------------------ NO "- All injuries' - ur -i i n a radiologically contamin-
' ~ ' ated area sh e c.sidered.contar:nated until
monitored-ed.
.. __---_--___-_-_- _--___'__ _ ---__----_____-- __ ----__-----_---- - < 4.4 The Shift Supervi c-/Em rgency Director, w~ c urrence of the available sit .e Ica. staff, shall o. t injured pertop(s) offsite fo r e tensive medica ' ~ o at,a t.
< ---__-_--_-- _ -__-------_--_--_-- _ -_ -_ -----___---------_-_----- . NOTE-the injured person ontaminated, or potentially :
contaminated, a Radiological Controls Technician will : be dispatched to H.M.C. to provide Radiological
- Controls as needed.
NOTE: By agreement with the Milton 5. Hershey Medical .
Center (HMC), Hershey, PA, all contaminated persons-
with injuries too severe to be handled onsite shall -
be sent to H.M.C. for decontamination and treatment.
_-----------------------__------____-----------_----------
. _. 4.0 ,. ,, _.-_.
. - _. -,. .. _.. -, m -, ~ _.. ,_ _ .--
._.
~ - - - - '1004.16 . - e Revision 4 , . . . 4.5 The Shift Supervisor shall perform the following steps in the event _. -., an injured and contaminated or potentially contaminated person (s) is to be transported to HMC.
4.5.1 If an emergency classification is not already in effect, the Shift Supervisor shall assume the duties of the Emergency Director.
! 4.5.2 The Emergency Director shall implemen e uirements of Emergency Plan Implementing Proce e 04.1 "Emer-gency Classification", if not ea v eclared and requ lance service fro.
e auphin County Emer-ry. rations Center, q3ee.ed, for offsite ssi ance.
4.5.
Tne Emergency Dire tor is designee (Shift Foreman, . Communicator, h I call the Ch ge Nurse, Eccr- - e gency Room HM a 9-534-8333, and the followin; -' message 1er HMC of the arriva ~* injured victim: "TH _ n..E/ TITLE) AT TH :: I' SLAND ACTING AS , ( ) EMERGENCY DIRr eu I IS PREPARING TO . 1 ER A (POTENTIALL, C r -MINATED VICTIM WITH GURIES TO HERSHEY MEDICAL CENTER.
THE RADIATION EMERGENCY AREA SHOULD BE PREPARED TO RECEIVE THIS VICTIM.
PLEASE ACKNOWLEDGE AND VERIFY THIS MESSAGE BY CALLING 948-8069 (8070/8071) AND ASK FOR THE EMERGENCY DIRECTOR."
4.5.4 The Emergency Director, or his designee, shall then: '
- briefly describe the injury (s)
- give the name of the victim (s)
.. 5.0 , ! -. -., - . - -, ,- -..
-- - __ . 4:an: e .1004.16 ~' , . . - Revision 4 ' < a ,O.
- report levels of contamination, if known
- A.V
- request special equipment required
- estimate time of arrival at HMC i
- describe method of transportation P
- estimate expected dose rate nazard to HMC taff Person-nel based on dose rate taken 12 inches a ve 'ha victim D
,
- record the name and title of the pers6n\\ eceiving.the
.. N a notification call, and the time no i i
4.5.5 Perso decontaminated shal ceiv whole body > coun't .. accordance wl cP 16 2 and RCP 1628.
D 4.6 The Emerc ' rector shall req ire r nsportation of person (s) ' c ss of 25 REM whole body to with testgg4ation exposure i x HMC.
I this case,the vi ( an be transported in a conven- , ()) tional manner and will o . ire activation n he Emergency Plan.
, r RAC may reque't assi-ance in evalua-4.7 The Emergency Dire : d i _ tion of extreme a . n overexposure i.
'o EM or more) from
various Rad'o al Health Specialist-ter Consultants, v Radiatto TEnag..ent Corporatio, etc.)
4.8 The Em n, Director and Radiolcei 1 Assessment Coordinator shall restrict personnel who have received internal contamination I of greater than 50 Percent of the Derived Investigation level, as stated in RCP 1628.1, from further work in Airborne Radioactivity . Areas, until evaluation is made. Complete and direct the personnel for whole body counting, in accordance with RCP 1612, for~evalua- ! tion of Body Burdens.
l ] 6.0 , t ' _ _ _ _ _ _. .. .. . ., _,. _.._ _, _. _ _ ..... _. - _ - _.. _ -, _,. _
.' 1006.16 , Revision 4 ,. . . i.. Attachment-I (Cont'd) ,
Check 7.
If possible, have the ambulance crew standby in the ambulance until both are surveyed and released or with the Emergency Director's permission, have the ambulance return to TMI for decontamination as necessary. Any material that is above release limi s less than 0.5 mR/hR should be securely sealed in plastic, "Radioac-tive", and returned to the site.
Material gre r an 0.5 mR/hR should not be transported without consul .g a representative ! of the TMI Was i osal Group.
Info . e Control Room of the status of a.
ance.
8.
Rad Con hni an(s) at the ho p al ould coordinate the Radia-
l tio ty actions in the E er n Room with the attending l , ^7.s physic - . . l ' 9.
When possible, turn o er iation Safety.re ^^ < ' Th ties to the
- HospitaLgealth P sici Remain at the i i until the . '
-
- _n
' individual is e ttev or released.
_ ' 10.
Survey the
- h't veled by the a n
ersonnel and the indivi ua 11.
Before ing the hospital, ensure that all radioactive trash and used P.C.s have been collected and that a thorough survey of the I hospital emergency room and adjacent areas as applicable has been ccmpleted.
, 12.
Ensure that the Control Room is informed of the status.
- <
'w j 9.0 . $ a--.mo.
- - - . m.- ..m.. . . . . .
Attachment 3 l R0 EXAM COMMENTS Section 1 , 1.05 Question does not ask whether an increase or decrease in each of the reactivity effects is being considered.
(#1 & #2) 1.06 b.
Beff values are BOL.00583, E0L.00517.
Reference: Cycle 5 Reload Report 1.08 No tolerances given on key for enterpretation of graphs.
1.17 a.
1.
add: To ensure that bubble in RCS is located in the Pzr.
Section 2 ! 2.08 FW-V-1B (FW pump discharge valve) will auto close on pump i trip, preventing damage upstream of pumps.
Reference: OPM Section G-2, pg. 51 > 2.09 b.
Absolute - Sequence Enable Relative - Sequence Alarms Reference: OPM Section F-1 pgs. 48-50 . 2.11 Too specific a question. Too infrequenct an evolution.
( 2.12 This only opens C0-V-8.
The other two valves are verified ! open and do not work off P.B.
Reference: ATP 1210-10 Section 3 ! 3.02 a.
Question does not ask for time frame.
3.06 Note: X-limits would hold FW-Rx within 5% of each other.
Reference: LP 11.2.01.055 3.12 a.
RM-A-13 monitors " Particulate," " Iodine," and " Gas."
Also RM-A-13 is currently only using the gas channel.
Reference: OPM Section F-7 pg. 21.
Section 4 4.06 Can be " False'.' Deboration can take place as long as SDM is not i reduced below 1%. - Reference: T.S. 3.1.3.5 ! , - - - . - - - - - - . - - - . - - - - . - - - - - - - - - - - - - - - .
. . -- . L
SR0 EXAM COMMENTS Section 5 5.03 Question is mainly an exercise in algebra and assumption.
, It's relationship to the SR0's responsibility is unclear.
Recommend the question be deleted.
5.06 Question only asks for how it changes.
5.07 e.
Curve does not really isolate it to one answer.
5.10 b.
Decrease towari stable value is due to delayed neutrons.
Section 6 6.01 b.
Alt. answer: " Lift relay" if I.L.
b.
Reducing setpoint monitor should be adequate.
I&C reduces the setpoint.
6.04 Note: X-limits would hold RJ-Rx within 5% of each other.
Reference: LP 11.2.01.055 , ' 6.05 FW-V-1B (FW pump discharge valve) will aute close on pump trip, preventing damage upstream of pumps, , i Reference: OPM Section G-2, pg. 51
i 6.11 a.
This only opens C0-V-8.
The other two valves are verified i open and do not work off P.B.
i Reference: ATP 1210-10 i Section 7
None ! Section 8 8.05 ED need not consult if the ED is the duty SRO.
8.11 b.
Question did not ask for all items. A better question would be: What condition must be met for a TCN to be approved by.
I ! ! , i i l t
. .
. . TMI Exam Key Modifications and Responses to Facility Comments on Written Exam Questions Section 1 1.05 In #s 1 & 2 to speak of an increase or decrease has no meaning.
The coefficients themselves act to dampen the effect of an oscillation.
1.06 The new values were substituted into the answer key.
1.08 Reasonable tolerances would be allowed. All candidates come up with precisely the same value as the answer key.
1.17 This interpretation is one of many that would have been allowed for full credit.
Section 2 2.08 Accepted answers with discussion indicating knowledge of pressure concerns upstream of MFWPs, but dismissing them due to auto closure of MF-V-1A/B at pump discharge when MFWPs trip.
Accepted damage due to reverse rotation of MFWPs as an alternative to one of the two items listed in key.
2.09 b.
Accepted additional answers as alternatives (any 5 allow full credit): API - sequence enable - asymmetric rods RPI - sequence alarms 2.11 Disagree. CFT filling from MVP system is appropriate. Question i question.)(Only one candidate got less than full credit on this stands.
2.12 a.
Accepted. Valves C0-V-12,13 removed from key.
. . . . ..
. TMI Exam Key Modifications and Responses to Facility Comments on Written Exam Questions Section 3 3.02 a.
Disagree. Time delay of EFP start after MFP trip is the effect of coincident ES initiation.
.s 3.06 Discussion of the effects of X-limits is appropriate if included.
3.12 a.
Either " particulate" or " fixed filter" and " iodine" or " charcoal" are acceptable alternatives for monitor types.
b.
Alternative answer for 0.5 total credit is correct description of flow path lineup for normal and backup operation: Normal - particulate, todine, gas Backup - gas only Section 4 4.06 This answer was allowed, but only if technical specifications are referenced.
Section 5 5.03 Comment was not accepted.
5.06 True.
5.09 There is only one correct answer.
5.10 True. But that was not the question.
r . . TMI Exam Key Modifications and Responses to Facility Comments on Written Exam Questions Section 6 6.01 b.
Alternate acceptable answer: lift relay [+0.5] in XCR Relay Cabinet [+0.5]. em 6.04 Discussion of the effects of x-limits is appropriate if included.
6.05 Accepted answers with discussion indicating knowledge of pressure concerns upstream of MFWPs, but dismissing them due to auto closure of MF-V-1A/B at pump discharge when MFWPs trip.
Accepted damage due to reverse rotation of MFWPs as an alternative to one of the two items listed in key.
6.11 a.
Accepted. Valves CO-V-12,13 removed from key.
Section 8 8.05 Answer must recognize need for ED/ duty SR0 consultation when ED is not the duty SRO.
8.11 b.
Suggested wording change would be an improvement, but existing wording is adequate.
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