IR 05000286/1986012
| ML20203E724 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/16/1986 |
| From: | Dudley N, Keller R, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20203E709 | List: |
| References | |
| 50-286-86-12, NUDOCS 8607240230 | |
| Download: ML20203E724 (90) | |
Text
{{#Wiki_filter:. e
e
f U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING REQUALIFICATION PROGRAM EVALUATION REPORT Requalification Program Evaluation Report No: 86-12 (OL) Facility Docket No: 50-286 License: Power Authority of the State of New York P.O. Box 215 Buchanan, New York 10511 Facility: Indian Point Unit 3 Examination Oates: June 3-5, 1986 Chief Examiner: ketd
& 7-6 ~ [I6
Noel F. Dudley / Date
' Lead Reactor E neer (Examiner) Reviewed by: ) N/[/f6 . Robert M. Keller, Chief Date
Pro ect Section 1C j Approved by: 79[/4/ 4 df (@ry B. Kister, Chief Date ,m ?/ojects Branch No. 1 , l Summary: Three licensed Senior Reactor Operators (SRO) and two licensed Reactor Operators (RO) were examined by the NRC as part of the facility annual requalification examination. All individuals passed the examinations resulting in an overall program evaluation of satisfactory.
i i > !
koj728CK05000206 30 86071s V PDR
-. . _ .- - -. - - -. - - - . - - _ _ - .
= . ~. _ ... - - -. .. _- --.--- . o.
O Report Details Examination Results: R0 SR0 Total Evaluation l Pass / Fail Pass / Fail Pass / Fail (S, M or U) Written Examination 2/0 3/0 5/0 S Oral Examination 2/0 3/0 5/0 S Overall Program Evaluation: Satisfactory Chief Examiner at Site: N. F. Dudley, USNRC Other Examiners: B. S. Norris, USNRC 1.
Summary of generic deficiencies noted on oral exams: Reactor Operators were unfamiliar with the procedure for performing an Estimated Critical Position as shown by their inability to use the correct curves and perform the required calculations.
Senior Reactor Operators demonstrated a lack of understanding of the potential problems associated with water hammer in the main feed lines.
2.
Personnel Present at Exit Interview: NRC Personnel: N. F. Dudley, Lead Reactor Engineer (Examiner) 8. S. Norris, Reactor Engineer (Examiner) Facility Personnel W. A. Josiger, Resident Manager R. R. Tansky, Training Superintendent B. J. Ray, Training Coordinator S. J. Bridges, Operations Training Supervisor R. E. Robenstein, Operations Trainer 3.
Summary of Comments Made at exit interview: The Chief Examiner summarized the examinations which had been administered and presented the generic weaknesses noted on the oral examinations.
Individual weaknesses noted on the oral examinations had been previously discussed with the training department.
The Chief Examiner noted that the training material is not keeping pace with the plant modifications; the facility acknowledged this situation and stated that plans were in progress to correct the proble * ' < . o
i The examiners expressed their appreciation to the training department for coordinating the visit with the plant; additionally, the control room operators and the health physics personnel were very supportive during the evaluation process.
The facility expressed a concern over the administration of the SR0
written examination; in that, Sections 5, 6, & 7 were collected (after ' three hours) before Section 8 (with a handout) was distributed. The SR0s stated afterwards that the examiners should have allowed the individuals ' to pace themselves with the restriction that they hand in Sections 5-7 before starting Section 8.
The facility stated that they were very pleased with the way the orals were conducted and with the philosophy of " operationally oriented" questions.
4.
Examination Review: J The facility comments on the written examinations were discussed at the examination review held June 5, 1986.
(See Attachments 3 & 4) Attachments: 1.
R0 Written Examination & Answer Key 2.
SR0 Written Examination & Answer Key , 3.
Facility Comments on R0 Written Examination & NRC Resolution
4.
Facility Comments on SR0 Written Examination & NRC Resolution , f
l .. _ - _. -. . _. ._ - -. - _.. .. -. -.. ... - - - . - -. ... - _ - _ ., - -
~- -_ , Athtch ment l JLa<t: of . 6 b y & a . U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: INDIAN POINT 3 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 86/06/05 EXAMINER: NORRIS, B.
S.
APPLICANT: Gbr MF a# ,a - INSTRUCTIONS TO CANDIDATE: Read the attached instruction page carefully.
This examination replaces the current cycle facility administered requalification examination.
Retraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff.
Points for each question are indicated in parentheses after the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination starts.
% of Category % of Candidate's Category Value Total Score Value Category 15.00 25.00 1.
Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow 15.00 25.00 2.
Plant Design Including Safety and Emergency Systems 15.00 25.00 3.
Instruments and Control 15.00 25.00 4.
Procedures - Normal, Abnormal, Emergency and Radiological Control 60.00 100.00 TOTALS FINAL GRADE % All work done on this examination is my own, I have neither given nor received aid.
CANDIDATE'S SIGNATURE
. ES-201-2 .
. NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS - During the administration of this examination the following rules apply: 1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
2.
RestrMs trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3.
Use black ink or dark pencil only to facilitate legible reproductions.
4.
Print your name in the blank provided on the cover sheet of the examination.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Use only the paper provided for answers.
7.
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
8.
Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only one side of the paper, and write "Last Page" on the last answer sheet.
9.
Number each answer as to category and number, for example, 1.4, 6.3.
10.
Skip at least three lines between each answer.
11.
Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
12.
Use abbreviations only if they are commonly used in facility literature.
13.
The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
14.
Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
15.
Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION l AND 00 NOT LEAVE ANY ANSWER BLANK.
16.
If parts of the examination are not clear as to intent, ask questions of i the examiner only.
j 17.
You must sign the statement on the cover sheet that indicates that the j work is your own and you have not received or been given assistance in ' completing the examination.
This must be done after the examination has been completed.
Examiner Standards 12 of 18 .. __ _ ._. _.. _. . . _. - - - .
. ES-201-2 . . 18. Wnen you complete your examination, you shall: Assemble your examination as follows: a.
(1) Exam questions on top.
(2) Exam aids - figures, tables, etc.
-- (3) Answer pages including figures which are a part of the answer.
Turn in your copy of the examination and all pages used to answer b.
the examination questions.
Turn in all scrap paper and the balance of the paper that you did c.
not use for answering the questions.
Leave the examination area, as defined by the examiner.
If after d.
leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
( ( 13 of 18 Examiner Standards
_ _ __ .. _ _ _ __ ._.
_.-_. _ _ PAGE
- 1.- PRINCIPLES OF BUCLr. Alt PO'"J11 PLAP2 OPER.ATION.
THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
e
, I f ' QUESTION 1.01 (2.50) Calculate the required boration/ dilution to maintain Tavg on program for a power increase from 50% to 100% with no rod motion and equilibrium xenon.
Initial conditions: equilibrium xenon, rods in manual, CBD at 220 steps, i boron concentration at 1200 ppm.
Use Figures 1.1 through 1.8 (attached).
State any assumptions and show all work.
'
4 QUESTION 1.02 (1.50) l Calculate, and explain the basis for, the stable negative Start-Up Rate ' immediately following a reactor trip.
i
QUESTION 1.03 (1.50) l Explain how and why Differential Boron Worth will change with an increase j in moderator temperature.
!
QUESTION 1.04 (2.50) , List two physical requirements for natural circulation flow.
(0.50) i a.
, b.
During natural circulation, explain how it is possible to form a bubble in the reactor vessel head when indications show that the RCS is subcooled? (1.00) ! c.
How will pressurizer level respond, (INCREASE, DECREASE, or REMAIN THE SAME) if the backup heaters are energized with a bubble in the ! reactor vessel head? Assume normal pressurizer level and briefly , (1.00) EXPLAIN your answer.
I .! l
l ! i (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) I l . - - _ _ _ _. . . . . . ...
__ . -. .
PRINCIPLES OF NUCLEAR POWE" PLANT OPERATION, PAGE
THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ' e . QUESTION 1.05 (3.00) An Estimated Critical Position (ECP) is calculated for a startup to be performed 4 hours after a trip from 100% power.
Compare the CALCULATED to the ACTUAL critical control rod position if the following events / conditions occurred.
Consider each independently.
Answer whether the ACTUAL control rod position is HIGHER than, LOWER than, or the SAME as the CALCULATED control rod position.
JUSTIFY YOUR ANSWER.
The startup is delayed until 8 hours after the trip.
(0.75) a.
b.
The steam dump pressure setpoint is increased to a value just below the Steam Generator PORV setpoint.
(0.75) Condenser vacuum is reduced by 4 inches of Mercury.
(0.75) c.
d.
All Steam Generator levels are rapidly raised as criticality is (0.75) approached.
QUESTION 1.06 (1.50) A motor operated centrifugal pump is operating at rated flow when the discharge valve is throttled in the shut direction.
State how the below parameters will change (increase, decrease, constant): a.
Flow b.
Discharge pressure c.
Motor amps d.
Net Positive Suction Head c Fle" dacr^a--e, dirck=";^ prerrura incr02rer, meter 1rpr incresce, tETH decrccccc.
d.
Flce decr:2002, diccharge prercure increar^r, meter impe d-cr"?"e, NPO!! increasee.
(***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) ... _. - _. . _ _ -.. - _ - -. _.
. . _ _ __ . _ _. _ - - -.
PAGE
1 PRINCIPLES OF NUCLEAR FOWER PLANT Ol'URATIOM, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW , e . QUESTION 1.07 (2.50) What condition is prevented from occurring by tripping Reactor a.
Coolant Pumps (RCP) when subcooled margin drops below 32 F? (1.00) b.
Describe why subcooling is used to determine RCP trip criteria instead of Reactor Coolant System (RCS) pressure or Secondary (1.50) dependent RCS pressure.
(***** END OF CATEGORY 01 *****) l - - _ - - - - - - - _ _ _ - _ _ - - _ _ - - _ _ _ __ _ _. _ _ _ _ _ _ _ _ __ .._ , _ _. , _ _._.
_ _ _ _ __ . _. ._ _ _.. _ _ _ _
PLANT DESIGN INCLUDING SAFrai AND EMERGENCY SYSTENS PAGE
2 d-
QUESTION 2.01 (1.50) List three conditions that require Emergency Boration.
QUESTION 2.02 (1.10) Using the attached drawing, Figure 2.1, highlight and identify the NORMAL and ALTERNATE Emergency Boration Flowpaths.
QUESTION 2.03 (3.00) a.
If the Instrument Air (IA) pressure starts to decrease, what automatic actions should occur to maintain the pressure? (1.00) b.
If pressure continues to drop, at what pressure must the plant be tripped in accordance with ONOP-IA-17 (0.50) , ' On a complete loss of IA, how will the following valves fail: (1.50) i c.
1.
Excess letdown hand control valve (HCV-123) 2.
Diesel generator service water flow control valves (FCV-1176/1176A) 3.
Main feedwater regulators (FCV-417/427/437/447) 4.
Atmospheric dump valves (PCV-1134/1135/1136/1137)
5.
Liquid waste release valve (RCV-018) QUESTION 2.04 (1.50) At what pressure should the spray valves begin to open during power a.
(0.25) operations? b.
List two purposes for the bypass line around the spray valves.
(0.50) What is the basis for the combined capacity of the spray valves? (0.75) c.
QUESTION 2.05 (2.40) List the conditions that will cause the Motor Driven Auxiliary Boiler a.
(1.60) Feedwater pumps to automatically start.
b.
List the conditions that will cause the Turbine Driven Auxiliary Boiler (0.80) Feedwater pump to automatically start.
i i f (***** CATEGORY 02 CONTINUED ON NEXT PAGE *****) ! ! t _ ... - - - -. - - - - - - -.- - - - . - _ - -.
. .
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
4 QUESTION 2.06 (1.00) If Component Cooling water is lost to the RCP's while the RCP'S are operating, when (time) are you required to stop the RCP's? QUESTION 2.07 (1.75) In the event of Loss-of-Coolant Accident, any one of three combinations a.
of recirculation fans and containment spray pumps will maintain the containment temperature and pressure within limits.
What are those(1.50) three combinations? b.
What is the purpose of the NaOH in the Containment Spray System? (0.25) QUESTION 2.08 (2.75) On the attached drawing, Figure 2.2, designate the correct position a.
of each of the breakers for a normal at-power lineup.
(1.95) List eight different loads powered from Bus 5A.
(0.80) b.
(NOTE: distribution panels and duplicate components are not acceptable] ,
(***** END OF CATEGORY 02 *****) ._.__.
_ _ _ _ _ _ _.. _. ._ - .-. - .- _ _ __
. PAGE
3 INSTRUMENTS AND CONTROLS e . QUESTION 3.01 (2.25) What would be the significance of one Intermediate Range channel being a.
undercompensated during a reactor startup? (1.00) b.
If one IR channel fails high during a reactor shutdown, how can the Reactor Operator continue to shutdown? (0.50) How, as a Control Room Operator, can you tell if power is lost to an IR c.
(0.75) instrument prior to a reactor startup? QUESTION 3.02 (2.30) The reactor is operating at a steady state 25% power, all control systems are in automatic.
Turbine load is increased to 100% and the steam pressure detector for #31 S/G stic;(s at the 25% value.
Explain, in detail, HOW and WHY this will affect #31 steam generator level.
Assume no operator action.
QUESTION 3.03 (1.50) When a Safety Injection signal is received, six automatic actions occur in addition to the illumination of the appropriate annunciators.
List 5 of the 6.
QUESTION 3.04 (2.50) What are three reasons for having Rod Insertion Limits? [0.75] a.
b.
With respect to the Rod Insertion Limits, "...the steamline break accident imposes the highest shutdown margin requirement."
[1.00) Explain why this is a true statement.
Considering each of the following sets of conditions separately, c.
[0.75) which condition will make the Steamline Break accident worse? BOL or EOL Reactor shutdown or at 100% power Tavg at 350 F or at 547 F (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
-_ _ ., .
INSTRUMENTS AND CONTROLS PAGE O ' , > e . QUESTION 3.05 (2.00) For the below Process Radiation Monitoring Systems, list: purpose protection on alarm, if any
type of detector used (Geiger-Mueller, Scintillation, Ion Chamber) a.
Steam Generator Blowdown Monitor (R-19) (1.00) b.
Containment Radiogas Monitor (R-12) (1.00) , i QUESTION 3.06 (1.45) The plant is operating at 80% power with all control systems in the automatic mode of operation. Explain the effect that each of the folloWing will have on the Steam Dump System.
a. Load is reduced to 50% fast enough to cause a Tavg/ Tref deviation of i (0.70) 15 F b. A turbine trip occurs.
(0.75) QUESTION 3.07 (3.00) Provide the setpoint and basis for each of the following reactor trips: a.
1.
High Pressurizer Pressure (2.00) 2.
Low Pressurizer Pressure 3.
Low Low Steam Generator Level l 4.
High Flux, Power Range (low) b.
What would be the effect (increase, decrease, no effect) on the Overtemperature Delta T setpoint if Pressurizer pressure was 2200 psig? l (1.00) WHY? i
i
(***** END OF CATEGORY 03 *****) . _.. _ . _. _ _. _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _. _ _. . .. . . . .. ..
-- .
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
RADIOLOGICAL CONTROL . QUESTION 4.01 (2.00) In accordance with POP-1.2, Reactor Startup: What operator actions are required if criticality is achieved 100 a.
steps BELOW the Estimated Critical Rod Position calculation? (1.00) b.
What if the rods are 100 steps ABOVE the Estimated Critical Rod Position and the reactor is not yet critical? (1.00) , l QUESTION 4.02 (2.00) The following precautions come from SOP-CVCS-2 " Charging, Seal Water and > Letdown Control," provide the reason for each: The temperature of the fluid downstream of the Non-Regenerative Heat a.
(0.50) Exchanger must not exceed 145 F.
b.
Letdown flow must be maintained less than 120 gpm. (2 reasons) (0.50) Charging pumps should not be operated if VCT pressure is less than c.
(0.50) 15 psig.
d.
Pressurizer spray shall not be used if the difference between the pressurizer and the spray fluid is greater than 350 F.
(0.50) QUESTION 4.03 (1.00) In accordance with the Emergency Operating Procedures, what is the difference between a FAULTED Steam Generator and a RUPTURED Steam Generator? , i (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****) . . _ _ _. - - _. - ....... . - _ - - _ _ _ _ - _ _,. _ _ - -- - - - - _ _. _ - -. _
, , ^ '
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
- RADIOLOGICAL CONTROL
"'
- ,a s- ,, . , ., QUESTION 4.04 (2.75) In order to maintain the plant at'100% power, work'must beiperformed inside the containment in a radiation field of 850 mrem /hr-gamms ands 30 mrad /hr thermal and fast neutron.
The maintenance man selected is 28 years old and has a lifetime exposure through last quarter of 48 rem on~his NRC Form 4; additionally, he has accumulated 1.0 rem so far,this quarter, How long may the man work in this area without exceeding his 10CFR a.
limit? Show all work.
- ,
(1.25) ,. b.
During a declared emergency, this individual volunteers to enter a high radiation area and perform work necessary to prevent further effluent release.
In accordance with IP-1027, Emergency Personnel Exposure, what is his maximum allowed.whole body exposure? (0.75) c.
Whose authorization is needed in part'b.
- ' (0.75) ~ QUESTION 4.05 (1.55) Answer the following in accordance with IP3 Teclinical Specifications: a.
Define HOT SHUTDOWN.
(0.60) b.
Which THREE parameters must you observe in order to ve'ify that ~ r Reactor Core Safety Limits are being adhered to? (0.75) c.
Provide the following temperature limitation values.
1.
Pressurizer heatup rate.
2.
Pressurizer cooldown rate.
(0.20) QUESTION 4.06 (2.70) Answer the following in accordance with E-3 " Steam Generator Tube Rupture"; State 4 parameters that should be monOtored to aid in identifying a a.
(1.20) steam generator with a tube rupture.
b.
State 5 actions that must be performed to isolate a steam generator(1.50) with a tube rupture.
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
-_-________-_______ ___________________ _ _____________________________ __ _ .
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
' RADIOLOGICAL CONTROL a QUESTION 4.07 (3.00) What operator actions, if any, are required to stabalize the reactor plant for each of the following instrument failures.
Assume a power level of 100%. c.
Power Range channel A upper detector fails high b.
The controlling steam flow indication channel fails high l l l
l l l t (***** END OF CATEGORY 04 *****) (************* END OF EXAMINATION ***************) _
- - ~ a- . p, 4,,,.,_ i, f Ar a r e-f-Z ~ - BORATION NOMOGRAPH FOR HOT 580 o DILUTION NOMOGRAPH FOR HOT RCS 580 RCS 5000 - 4000 - 3000 - - 1000 3000 - - 900 - 800-700 'O~ 2000 - - 600 to - - 500 E 500 ~ 20 - 20 - - 400 M-d[
1000 - - 300 - 900 - _ co - ,, To - 800 - ~ '00 ~ - 200 , 2000 - 600 - 500 - 200 - - 150 i ' o-400 - '~ - Soo - 300 - - 100 1500 - - 90 200 - . '
- 80 - 70 200 - 300 - - 60 to - 2000, - 50
- ~
~ 1000 - ,g9, - 40 ' ' ~ - 30 io.ooo - , ; l 20 Doo - 500 - - 20 2000 - SW - 50.000 -- 200o- ,oo ooo -
sooo-200o - ' PPM BORON PPM BORON DILUTION WATER _,a IN COOLANT DILUTION IN GALLONS , PPM BORON BORIC ACID PPM IN COOLANT VOLUME BORON
IN GALLONS ADDITION .
. . . e figu<e / 3 . w . 600- -.---
- -
- _
- A.
m -;
- - . 590_--- ,,
- ..
.=:,." r. ^V 580 -
- .:
- -
u .-- T " "
....-. -: 7' 570_ .g';' --
.- . - , le ,
- - ,- _ .: + , - ,
( F) -
- - -
/ , .
. - - -.. 560 _
e . -. -. -
,-
, .x -- ,. _ w - , , . '
-- nn. .
- 1 p'-
,I;.m.,n m -= 4-L 2_ .- --,- ' k Ig ' iM.
i 550- ,z ' ',_:-' -- -:-- . -_ = 4_. _.. - _
-/,- -,: . ... - r-. m- - .... . ~. -,.. _. - .. - _ L _M_.
5a0 - ~r ._: - - - -. T. -(- '.-_ m _ ___' _ _- ; f,:L
-+- , .- _ g.
-.--4.
_-- _. = :{'p, -- __ __ - 530 ~~-- ,-i:.w.;-_..... , , - _ ob ad 6b ad 10,. O - Reactor Power ( "o ) ._ _.
..___
v . - e Ap c e I. y - . U
- ~
T. 7 :..*.- ; n:.. . l ...r_ ' - /.:;=. -
. : 2:... n_. =. .~~.:* ~..1--* = t- - ~T- .*t--- ..; t- . _..;::::.:
==... lE -..-' _ _ l.. _ _ _.. _ . _. ... _... ... :. u _5=-- -._1=--_ .,::-- .:= = =. - ........ - - _ _... _.., _ _ - T_.. .. _ _ __ - - - - - - - - - - - - -- - O -- - ... _ =. 2.:2=.=r.:c: =:==: ::::_ ;-. :=-: = c- = ._=_t._.
s-- --
- f=~._2,
- = .._; --._..__ 1__ .4: ., _- ,_ .- _n_: - .. _.. _ _. h..o M ___. i_-l g - g,... . ._.... .=,. ;;. :._ J. e.., - [. ; --- j:. E-.:p-r -=_nt-. g .... _g 5t :7 ~-g= -
- n-t
.i.
-- - -- r :_ = ".. .. u t. ::. [-. : l~ - '.~="'.' :=t -: - ~ % . _t:.- - ' m ' - - - -- I ---
-200 -- r
- _
- _;.. w._
.. = _..: ...=: -+ _ :[. :-r
. r r: - =r : =_ : = - v =_.:n..u_:._:.:;- :=_ =
4=:2_ :: .. : =:- - -... -.. M. s,..z= =-- 3,: -- =yu: f = = = =__ ;.=... ::_:=_=_ _1=...__ . . _.. _ _. .. _. . .
- e.
. _ _.._ = = =-
- u._
. _T.=_..._..... =. _.: :=..== t.. 1. . ...=..C__- - _ =:_) - _..
- _
. . _. _. . _. -.. .. -. V 1=I.= r'O.. ; J.
.. =-i:=. ' '-
- L
.; _O - - g. X -._.: {, = -- *+ - 2="
- =
W = w=* -
- -=
-400 -- -x - _ - - ^ _ _ - - ~' +D '* ! ~ _ _ _ . _ - _ _ _ 1.- .- -_.
i'g - . wm _.
_ - . _.a 4.
. _.; - %W -;-. = = -. . _.- - _ _. r . gr 3+ _.. _.
-- "_- - - ___-. g _ __ __ U-600 -"_u :rt :(-g.. r== . :=- _- _ _ = _ . p: " .t _.
3._..r . ._v._ _ i ---+ n .....:.
- - -t-.:.tn Ug_..y_3 c.
z_ _ _.. _ _.
._._ ._,. _ . ~ - r=_.&._ ._ _= = - -;. .__.
9~.g.. =.. - _... - ...;.. -$ %_,x _ . .. _.. _ = m_ s
=..
. -... ~... .. ..r..:.-r. 'I. : .. _ " -
.- . . =... + - -' r..r.. :.r..:.._:.{.. . _... =. . -~ DJ --= {--*/ = .__.. : N:.\\;4* {- T-c_
g, Mii=e.i:irtri m"'iA w w !Ni;=h > '. '=. '65! ... ... .x
W # "'~ '" " '* * "' 'g.... *~"~2
- ~
D3 - _.. _ a-800 - ' - 7== . g + g.=gcl3.p;c r=g s m N w.:i c.:t=-pg s . m p de m s it- % t e s =tr X = 4 s%W viv."
. " d
==Ft TE==tMt-~.!! =!i sfM! \\@i== R R =-- j5'+ : . g p,e p : i. 1 g m =pi=.jx x i x x x i -i> ; _1000 g r.
p i: - t . t- : p !.. i \\ \\ - Nix: N t ! i i ! \\:\\ \\\\ \\ ' ' - \\\\ NN N . .
i t 1.
i
_1,00 \\ \\. \\ 1500 PPM
. - 11 i i r > t l. ' l
- -
!' i k i\\ N 1200 PPM i l'. g-I-d.
}: _.:.........n_....:j:.;p. j.. p g \\\\.g p.
. ji~_t." E-F - l~ :y= - g_pl.j} -.ii '. l:a.:[.7:4 l \\N 3 900 PPM ., . a- . - \\ j\\ -
- .. I. = a y:.
l.
\\ -1400 \\ t .- .i y-=: r-- '-. ' - - lifi--Q.l : ~l - i ; j'", idE h '. j.
\\l \\ ! .r =::
- :
" i Ni.\\ 300 PPM ..[!; [- f-f - l - - , [- u[.
I'
' I ' I - }. t
. t- . I- = i: -
- =
- 9--- h.E {..
[. - [ i. y:. l ! l i\\ ' -1600 -
0 PPtt - . _. I I . i-i ._.
. , i , ' l"_.P ic
FE.1 F:* t r' t
t. n _. ;. - :-.- i -)-- t- . . . $. _ IL.. , , -* .g
.{. l' .. j t.
(_
- .._.i. J :.
. g- - v- -
, -1800,... :_ . 3.: -
- _u[
- ... t . , . . ,
20
60
100 , , Power (Percent of Full Power)
. - . . . 'AVAILABLE CONTROL BANK WORTH AS A FUNCTION OF BANK POSITION - . . . - Squ er /. 5 v . _ -.. .- +--- , . - -. - s' - . ._ __ _ -3500 -- - -- ~ z=% -t - -__ ._ s _. - _ _ -y . - -. _ .._...x E.b_ ; Ir-c.: _..- . - L -
__ ,. - . w_ -:=_y__ _ _ -. \\.; . _.r._ i- ._;.__ __ g .. _ _ _. _ .A - + - - ___ ~ _ - - + - -
~ 2--~ -+- - - - __ _"; _, -- -3000 ~ - O .._ __?"c_-
- -
'._.
t- , 611 g C.
. _. - _. -
- - - ' ~ F.- ~~_ m t-
- ---F-
%, _ . _
- =: __ - p_.%___.-. --- - pY_,,._q. _--. ; , e -. . a: - Z~- t t' = - '- - - - NY i .' - - -- - t O r---,--
- --
, 4-\\' -- - ; 4- - p.
\\ .. ~. +~"-- t b . ._.s._5_.._ \\ i--- >4-t----*-. . y ~- . _j_.__._ =c. - + 2-- - - g g._ l> _. -*'- \\- -. _ t..~ . _ _. _. IT_E --"L.
- D I~"~2=~ ^ - L.__..__- - - -. _- .\\ i .__ r ^
- -*--{
. g5 g . __.
... +=N'C -*='- Y~ . ._ R - r- , "D - D"'*** ^ - -2500-I i. : \\==t =i- .. : : r T .:1, - t e--- ,- - t :.p:t._.;_.,, an h...::n:::r= t:=" V* --.L_ - .. _ -* _; --
"
l -' ' t.
-.f. : +t --* +E- ;-- ; r 1 ~..' :: : {.. * :- -r. ..-.. te u .t. = - +-- -t _4-----* _ -=
- - -- _ - ~ - _ .. .-l- .. . -_....... + .L..;. I f...:.L. : s. h......!. - ._ - " *-'. : t.. -.. .e.; !. J.. ~ -* . _.. _ - ~ _ _ - _ -,-,,_=,_.t__;._.
-, . - - . . .... .
- : _ y
~E=- =2..v. _ l. 2.: r*==_.:- - - r.== E-b==t:-y .. (2::2- ' -- ' a _..
-.=
==. :E - . - - - . = _ -= - -- - W --.. ._ -~*--1 2. :C.: ;r L _..
- __~.:- ' '
N c= --:-
- t _-- -
,._ ._-- t : t.u r. -._ .. - . - Ls l ' q.
4.. _ h,.:.. _- _.. - -- ;
- - t = :=_ ;-
g.- _ ; l __._- p___._..._._ 2_.
- _;
+ ... _- .- " i!= T i EE~2t-5'.N-_ . _. i _ ~~~ if.s9.iff E:d51!E.I'~E.- - * - - -. -- -. - - -,
- --=..=_..r..~._.
. . = =_. =_ E. =. i =... - ... - - . _.... _ _ - _. . -.. _..._ _ - .- = - _ _... =_. u_ _--=.__~._-t-______t -. - . . _ . -.., -.. - ._ . ;-__ - y-.--. _,. -. -. - _.
_..- - -- L. 22: - -- l -
- -
= l
- --- - _.i._ Ef. :t--; : =..E--
.... - _:. ...:.; . - C- .r t; . _ ;:_:..:_ m.,,- - _.. _ ; y -..{, ..-. l
- --.; t - ;- -- +_
- !. r.
. 7. . ' - -. _. _. _ _ _.. ...Z: _ -2000~ -2 !- :- {- 1._ ...---t - -. -e-- l , .... ._ _ _ t_-._ _n= ji. ;i-y..? i_ -.j. -j=. i.-E. =- d'.
- -iE-F - b--! n I. ME _- i:. E 2_......
-- -- __.
... _ .. . -
i.
r-i .. s r.. E. - E:. l.
- =. > = = -=1.1.. . =
- t -.. .. - =t==.; = 1c_ - - [ r ' ' ' ' D BANK 220 200 180 160 140 120 100
60
20
228 208 188 168 148 128 C BANK
i
DIFFERENTIAL BORON WORTH
__ .
- . q u, c_.
l.6 BOL-14.
- _ _ _. _ _.. _ _ ,_ __.,...-;._._....__.4 .. _ r . _ _ . _.___.
- " - - - - : n*; = 4_.
. -. -
..,. ___.5_
- -
, , .. , _.. . ....+ _.,_.
._.
- - - - _i . -13
a- > x __
.... _. _... - - _.
.._ ... _.. . ~ f-I.~~~.~_~.Y ^ i[E. 5E,.-.'_-.5._'Eihi23Ni: ~ ~ ~
- ... r_ _._.. _ - _
_ _
. . . .... _.. _ -.;. t7 : - +-.. [.... . t: =..':;:::. _. +. _ - - . _. _ _, h- - - 4 _.
- :-1 -..
_. t: : :- :- - '- -- -12 =- F : N . ' .. -- - m r- - p. _. _..... _, _
- - - +--+ -- n --2
- ..
-1: r T _.* 2 r --!.m - F_....__.. _4 -. r--- -% - _.
- _-
.-t..._ q-- ___5._.. ..._u_ _: --. -+ - ....g , = _.5_... _ _ _. _ __ :_. __. _, _ _.~ -.... _ ._ _ _ ~ ._ _ _.,. ... - ._.
.. g
,_._ _ ~.....=._.,2_._._.
g- . _N . a a -+ - r-uu =,_ : " N-10- __ '_..._. _ _.. s --+- - , - , _ _ . ,__ _____ _.- +__- g_.
, _.: . -9 -- ~ = , ._ ___ , -8 , i . , , 300 400 500 550 Core Average Temp. ( F) 6 are f. 7
-16 EOL _.. _. _ ___ _._._, . _.. _ _ _ _.. _. _ _ . _ _ _ _. ..... . _.___ r.. ,_ .. _... _2.. ___. _.. _..... _.......__... .. _ _.. _. _.
.. ,_.g._.
.._... _ _ _ _, _ , ,_.h u- .W--4 r: ' __._..__.7.__.:.___.._.... ,_ _ _ _ _ _.
. _.
. _ _.... _. _. ...... - - -. . _.. _... _ _ _ .. .. _., .. _. .. ..t=
- 7= ~ -
. ,-.t'.: = :--~ _: _}5_ ___ _.T.._ :.._---__._._.
. _ _ -. _. - , _. _ _ _. - _. _. _ _...._._..t_._...__.,_..p=.__,...r_-,___:_.
._ ... - _ . .. _. -
- --
-.t........ .. _. _.. _.
_ __= : _ _ _, _ _ _ . - _ ... _ _. _ _ .. _ __.
_... p_ _. n m_ m__-*_--1 _.-- +g.--- *. p=-t: = = _ ru-- - - g _...... :.,c. 7.:._ g .. . _ _, _ _ _.. _ _. _,.....____.__.
-.. . n - - - - - - - -- - - - - - - - - - - - - - -- "- - -14 - _ _ _ - { j - ...,.,. T-
- { - l _... !. _, _.
_. .-- ' -- - ;- {' I' I-13l 'l . .:.. . , , i
r- "
- - , i .
- ;.
- . - '
! - - i e e .._... f--- l I ' ' , ..., D E . . - 12 )' _:;- I _ ; r_ - - - - - . . ! t ' ' _.;_
- _rt- =m;
'-' :... -. p.
. '{
. R---.-V-.-** ... - - - t
- _
. . -, _ _.
.. _.._.,. .. _,..-.... _. _.,._..._.w.
..... _.. ._11 --- . . _ _ _, _ __ _ _ _ . _ _.u g.. ~ ::,.. . ' . .... . . -- '_ _-.. --'; - J !,. { ' - - . _ ". _.. ... , . __ p -t--'-+-=t... __:- ...'.:--._ -
- - I -
.. _ -. . . .... .. t.. ..__.,_-t~.-'..._6... .., .. , _ ...... .. .. ..T_ ':~ ". - * ' - ' ' ' ~. ~ f -'~. - -~ ! ;. _.
, l. _; '- _:1--' -, .. _.. ...g.
, ,- -,. ... U. ~ - , . . , ,, - 30'O 4b0 500 55'O Core Averac}e Temp.
( F) .
. ' - - REACTIVITY DUE TO XENON AFTER STARTUP
. . . F~9 ace /Y _ ....
- __-:= --.u.. c r_m-::n: =-=:. : = _: n. _:- - -
n. - - r - - - -- - - r :=- Percent Power ' - - --&:n _a_==1 . _..... ....
- .u_n
_.:.. =._..r: -- .g.
_ 4___.
. . - " *: 10(,) % --
- - x : =:=_ : = 2-r n u.r. EM - 4- - i T =E "i _ __.
' =1 80 % -3000 fi"-d"-E'535_T5-=-%f;TT y: ~ ;W " -" M= Ek.=ti;=edEMPE T_T-3E=1 E J,6 ._,.p. 4..... =_.=_ E-l= i - ._...._.__.___.t 60 % =7,_.__; F.-f.
__ _ _ _.. _ _..,, - ~ 1 -- - -- --- -. u.-.
- t. =
u.. t-t.= r h-y:_.w = - n- . = = = * : a -- e:"!t. =......_t : C -- = = :t ="u u = - =t -
T.Cf *._ ; - -- - "._ :7- : .- . 7.. _=._+_:_ =r p-a.-
- 2L r-s 3,=.E=
.... - _. 4 _=y _ -- -? . - - _... . . _ =. - =::---}. : _.. - ....,.......... -+- -- . -:_.
- =
.- ' -- - J - _+. 21__, & _ __ _- ,- 40 % ._.
- .. t -
- - - - - - - - ........ r-. f'f' : f.:- - c-3p.2 _ A..;,. g.._ __.t..__i_ 3_.._;_._ c- - - - -- -- -
- j_g; ;_.
. ,_ -i =: rnd. = :...: t. =:-- :=: __j -- n -- - -.. r:.:
- c--- r. : i
=m ur ___. =n=t-
n =F ' e - /f_M nirr h-. r:..['. :*h. r .:=n. h;=;"a===.r + -"-
" -r- "I# ~~ l:-- : r,1-fn r /
- t:_-
- r
=n-mn t --- . .. _ =:- c:tu t // ff=;/
- t - d -. : :t nt= j :__E... l-.. # _ _ ! :..i.....
.. t =: e II. 7 -/- ut:..
- ._......_ _.....___.== :-= - =
-- --'- r
-2000 _=: : _ L: - ...a.= =:;;.. :: := : =:t:._ t_:::Lu.. .u = :t=r.::::. ri=' - = 2== - !~C - :: : int:n =t u!-- -=-l = n . u- -- . r- -- -m---- =- -: 2- = ;. -.j c.2 :: : = _. _:.4 nn - r..t= =. ~h- = t :t: ; !
- 1-a
., - u --:::- ....: n= : P . - -:t.-
- .
t
o ;g :: 2iiij9.f ff f_..[.Ii ~ T:[I{i[iif, ~.:~ji~-II -F d22'-t- =2 5 20 % . --h.I:.h fibchu : _.:. !'liN!!I5U5I fi~[W~. : f >+ ' ' $ El NEhM-M -Ei=iE::==- UI=lij=F tiMisisE5l '. --.t.=ra < r.. _: c.. .t u: _d: ' c - : :-+h .-;- - - + - - -
- 1...
.* !.
, e.
o g =_:. { 2:- - E hi[5i.d5N:=-E=j-i'd:EiE.EF_MTd-l. -9=f:li'~'i ~~ 3 ... S! 5: . :; :: L".
t =: r p... u - tl.t
- ...-
.
- :.4,...: a
. . _ ;..4 .- t--- ... - - ..-1
- =u: : t v -
- 10 %
- --- :- = -. . i.
.. . . ... _... _...._.. p ' W ._.
u.,...j-
- Eii Jft]=ii ft rd -
4-4. -- -- -1 Et
. - -. - ' ' mp r 7. i i
l- - i-1000 t . ... k/i=[i I [ ! ! ! , . _i ! i . . ' i - . .
! ! . . , ' !. . _... , ! . .f.~ ! ll.9 xL:-. l -
I
- . [: 1 I N-355 l.
.i .- ) %:. lL. f.. }.. j , , .-.g:. p..... . .j: > < ... f . . , .
- t u..
,c_; . - ^ . ,.. .J [',;[",_i:l41 . l t.
[ ._ r
.
. [ j f . . j.; c l - [p/
. . [[:[i [ l L -I _ '. ub _ ~ - l ! . i.
t.
Iit _ ' ' 7A! I
I - - . l i f i-
- .
!-
. f - - c - i
20
60
100 TI!4E AFTER STARTUP (HRS.)
.. - ' $ O BASIC CHEMICAL AND VOLUME CONTROL SYSTEM fma re 2./ ' .ee.
$ 4 uPt E STSites SO'lefitOL'v at yg
IUNI BSIDOWN 4EIDOWN Val %E 04 eCf 9 "I* "O
LE100Wes eBOt a luwe - l l - (=)-- -m#1 c SI "M w 8.e....... 8.. .e.
. e.. -, n .. .... seO88 Af Of M Mu 9 CeleDN lO-lll-C 1-. COio tee aoOP 3.
s or eOnarmer ' t
y(e nE ACf 080 COOL ANS f.Tre
- ..esPi.......
seOmunt CMamomeG R OOP 3 e MA)- Cen s iee I Il
_11
's'eu*r* Q T> R attisese4Tf CMannesG LOOP 39 *-( ) , ,,g o,, gy g,, esof afG CouPosef NI WE es t
m , ausee g scs as / OOe see ME ADE A J
ek AU3 SPAAV 10 Penf S$LNetTIN d 'f-SS 100 Wee ME ~( MgAND*
.- I h WCW
8'8 - F a.r.e 8 30.c.e, --- . y>- . .-.-- .... . o.e. E I;' r<,e _.e []- 1 .e C.,., r - -- O'",,"','",",W.i.... O ' 7 . .. -- - >1> l<- g.
-. s s,.s (. s.,. toi .e 'T R+ - " ' ,e : a e - -g.
-4 " (,, _,,, (x =:: e.e.n...,~.e.
~~- n ) -- ..i ., e... 9.. Is e{ f' , ^ ,p .o .g.
-- -. eg,> p .re.- b x_ -:ee.
-i.r, '*ir>-- _
- " "m,
- - -t ,,0, - .. - - Cone e.see. es, Weannee omose
e O \\ d l N ' . . cl N t e w.' 254 t- % 1 OD .= ,, i.
1 e MO
M - ? % - C st '4 ; , i
k O . g, N A w.
,Q w - _ a u it $ h S 't
1 'e % %n L
% % Q
9 h C-3,. t ' e e l
s% 7 k 3 6 ' %% %'n & i v
.V > at ? n&A ' ~ m> -og <
ha } i u ~s m kE e* h*
u aN E9 k I
k c, - , e n' w w + ' R sm Sk n - - ---C < 3t kS NN % % %s k % sf s a n w - 4, 't
- q C
% o ,F s
ya: h sc _ nbs , b Qt am 4, p kE - - ' s
w w s QD $ e4w ,% ,A gs '* o , " i9 'e ,k 't .- ,* f. f$ k ' %C b D
%e
xe s qt u 2.
%
, - = " - - u O u 3t Sh nh 3w wa _-- -_
. 1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW , t ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 1.01 (2.50) (.650) = -640 pcm (fig 1.4) (0.50) Power defect: -1290 - - Boron worth: -10 pcm/ ppm (fig 1.6) (0.50) ~ Equilbrium Xenon: -3060 - (-2550) = -510 pcm (fig 1.8) (0.50) Required change in boron concentration: [(-640 pcm) + (-510) pcm]/(-10 pcm/ ppm) = 115 ppm (0.50) From Dilution Nomograph (fig 1.1) (0.50) approximate 15,000 gallons 7, 000 [If the candidate adds in factors for rod reactivity or a separate temperature reactivity, deduct 0.50 for each] REFERENCE System Description No. 3, Figures 3-13 & 3-15 Graph Book, Curves RV-1, RV-3B, RV-6, RV-7A & RCS-8 REQ-OAC-2, obj 2.7 _____________________________________________________________________ K&A 004-000-K5.20 / IF 3.6 ANSWER 1.02 (1.50) The SUR immediately following a reactor trip is based on the longest lived delayed neutron precursor (which has a half-life ~55 sec.). (0.50) (0.50) T = 55 sec 79.36 sec ______ = 0.693 SUR = -26.06-26.06-0.328 dpm (0.50) ______ = __________ = T 79.36 see REFERENCE Reactor Theory Manual, Chapter 4, pgs 10 & 29 _____________________________________________________________________ K&A 000-007-EK1.04 / IF 3.6 . - _ _ . .-- -. --
. 1.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 1.03 (1.50) Differential boron worth will decrease (become 'Edde negative) (0.50) because as moderator temperature increases, density decreases (0.50) decreasing the number of boron atoms available to absorb neutrons (0.50) REFERENCE Reactor Theory Manual, Chapter 7, pg 43 REQ-OPC-2, obj 2.5 _____________________________________________________________________ K&A 004-000-K5.06 / IF 3.0(RO), 3.3(SRO) ANSWER 1.04 (2.50) a.
Difference in density (pressure) (0.25) Heat source lower than heat sink (0.25) b.
Subcooling is based on core exit T/C or hot leg RTD readings (0.34) During natural circulation the mass of metal in the head can retain heat and keep local temperatures above saturation.
(0.33) The temperature indicators would not reflect this local saturated condition.
(0.33) c.
Pressurizer level decreases (0.33) because as Prcs > Psat, the bubble in the vessel will collapse (0.33) and cause water flow out of the pressurizer (0.34) REFERENCE Thermodynamics Text, Chapter 9, pgs 42-46 ES-0.3, pgs 10-11 _____________________________________________________________________ K&A 002-000-K4.02 / IF 3.5 002-000-K5.17 / IF 3.8 002-000-A2.03 / IF 4.1 -_ _ _ -- _ - - - -.- - -. . _ ._.
_ _ - _ - -
.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW ' L ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 1.05 (3.00) c.
ACP higher than ECP (0.25) Xenon will increase adding negative reactivity (0.50) b.
ACP higher than ECP (0.25) Steam generator will be at a higher pressure / temperature causing RCS temperature to be increased adding negative reactivity (0.50) (0.25) c.
Same Condenser vacuum will have no effect on RCS reactivity (0.50) d.
ACP lower than ECP (0.25) Cold water is being added to the SG which is cooling off the RCS adding positive reactivity (0.50) REFERENCE Graphs Book _____________________________________________________________________ K&A 001-010-A2.07 / IF 3.6 001-010-A4.03 / IF 3.5 ANSWER 1.06 (1.50) a.
decrease (0.375 each) b.
increase c.
decrease d.
increase REFERENCE Thermodynamics Text, Chapter 6, pgs 27-32 _____________________________________________________________________ K&A Components: Centrifugal Pumps / IF ~2.8 , I , , -, - - -. . - - - - ,, - - - -,. - - - - - - - -, - -. - - - - - -, - - , - - - -. - - - -
-
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE
- THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
'. ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 1.07 (2.50) n.
Prevent catuation conditiene in U tubes.
(1.00) b.
RCS pressure may result in tripping RCPs during SG tube rupture. (0.75) Sec. dependent RCS pressure is too hard to calculate.
(0.75) ' REFERENCE REQ-OPC-5, pgs 9, 11, 15 REQ-OPC-5, obj 5.4 & 5.6 _____________________________________________________________________ K&A 000-011-EK3.14 / IF 4.2 . \\s . /.ph. & Gtp w a Sy,ucJ d y w arl & k & W.A 24-7:Je) (o.sd
- NM&
M A S & E '-' k M fo,s.)
>
. . 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
'* ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 2.01 (1.50) 1.
Two or more rods not fully inserted after a plant shutdown 2.
Uncontrolled reactor cooldown below 540F with one rod stuck out 3.
Uncontrolled reactor cooldown below 500F 4.
Control bank position below the insertion limits (any three at 0.50 each) REFERENCE System Description No. 3.0, pg 54 _____________________________________________________________________ K&A 000-024-EK3.01 / IF 4.1(RO), 4.4(SRO) ANSWER 2.02 (1.10) See attached drawing REFERENCE SOP-CVCS-3, pgs 8-9 _____________________________________________________________________ K&A 000-024-EA1.04 / IF 3.6 000-024-EA1.16 / IF 3.9 004-010-K6.09 / IF 4.4 ANSWER 2.03 (3.00) a.
Standby Instrument Air Compressor starts (95 psig) (0.50) Service Air System valve opens (90 psig) (0.50) b.
60 psig (0.50) c.
1.
Fail closed (0.30 each) 2.
Fail open 3.
Fail closed 4.
Fail closed 5.
Fail closed REFERENCE ONOP-IA-1, pgs 1-3 _____________________________________________________________________ K&A 000-065-EA2.06 / IF 3.6 078-000-K3.02 / IF 3.4 i t l l l -- .. . _. ._. _ -. - -. . - _ -. . _.
. - - - _ _ -..
. - -. - 2.
PLANT DESIGN INCL 3JDING SAFETY AND EMERGENCY SYSTEMS PAGE
. 'b ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 2.04 (1.50) n.
2260 psig (+/- 5 psig acceptable) (0.25) b.
Minimize thermal stresses (on the spray line & surge line) (0.25) Help to equalize boron concentrations (0.25) c.
Prevent RCS pressure from reaching the PORV setpoint (0.25) following a step reduction of 10% (0.25) assuming automatic rod control (0.25) REFERENCE System Description No. 1.4, pgs 13 & 14 REQ-OPC-4, obj 4.1.b _____________________________________________________________________ K&A 010-000-K6.03 / IF 3.2(RO), 3.6(SRO) ANSWER 2.05 (2.40) c.
MDAFWPs: 1.
loss of voltage to 480vac bus 3A or 6A without SI 2.
lo-lo level any 1/4 steam generators 3.
auto trip of BO9H-MFPs 4.
safety injection t e', M r b.
TDAFWP: 1.
lo-lo level any 2/4 steam generators 2.
loss of normal power to 480vac bus 3A or 6A without SI (0.40 each) REFERENCE System Description No. 21, pgs 31-32, 34 _____________________________________________________________________ K&A 061-000-K4.02 / IF 4.2 ANSWER 2.06 (1.00) Within 2 minutes from the time CC water is lost.
(1.00) l REFERENCE ONOP-CC-1, pg 2 _____________________________________________________________________ K&A 003-000-K1.12 / IF 3.0 008-000-K3.01 / IF 3.4 -- . _ - - _. - -- .. _ _ - _.. -... - - - _ _ , . - . ~
. 2.
PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE
. L ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 2.07 (1.75) a.
1.
all containment recirculation fans operating (0.50) 2.
both containment spray pumps operating (0.50) 3.
three fans and one CS pump operating (0.50) b.
to aid in the removal of iodine (0.25) REFERENCE System Description No. 10.2, pgs 2-3, 8 _____________________________________________________________________ K&A 026-000-K4.02 / IF 3.1 026-000-K4.04 / IF 3.7 ANSWER 2.08 (2.75) c.
See attached drawing (1.95) b.
Containment Spray Pump (31) Component Cooling Pump (31) Containment Recirc Fans (31 & 35) Recirculation Pump (31) Safety Injection Pump (31) Service Air Compressor Pressurizer Heater Backup Group (33) Charging Pump (31) Service Water Pumps (31, 34, & 37) (eight required at 0.10 each) REFERENCE System Description No. 27.1, pgs 34-69 ________________________________________________ ______________-_----- K&A 062-000-K2.01 / IF 3.3 062-000-K4.06 / IF 2.9 = -svw-, --- ,- w-, -- w w y w
_ _.
. 3.
INSTRUMENTS AND CONTROL S PAGE
ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
, - l . ANSWER 3.01 (2.25) c.
Detector output is higher than actual neutron level (0.50) e~,.mm n.mme mm,, a .,,*m_ammmm.m4,. ..., " (0.50) l-I5 uA5'so 5 sk]~$5I~ &~& b.
Simultaneous operation of both "IR Permissive Defeat" pushbuttons to reactivate the SR (0.50) c.
" Loss of Compensating Voltage" alarm (0.15) " Loss of High Voltage" alarm (0.15) The respective IR channel will be pegged low due to loss of the (0.45) trickle current.
REFERENCE System Description No. 13, pg 38 ONOP-NI-1, pg 4 _____________________________________________________________________ K&A 015-000-K4.04 / IF 3.1 000-033-EA2.11 / IF 3.1 ANSWER 3.02 (2.30) (0.35) As power increases, steam pressure decreases As power increases, steam flow detector Delta P increases (0.35) m-stm = K(P-stm)(Delta P[E1/2])
==>since the steam pressure component stays constant (it should go down) while the Delta P increases, indicated steam flow will be (0.40) higher than actual steam flow The summing network for flow will send a signal to the total controller to (0.40) open the feed regulating valve.
As level starts to increase, the level error will signal for the FRV to (0.40) close Eventually, th" flev error "ill bc Ocncelled out by the level error, and th-FF" "ill be peritioned such that etcim fice c~ucic fccd flow (0.40) at rema higher in"el. y,Q g p,. YW w (W'/ab REFERENCE System Description No. 21.1, pgs 6-8 REQ-OPC-3, obj 3.0 _____________________________________________________________________ K&A 035-010-A2.03 / IF 3.4 . . _ - _ _ _.
__- .. -_.
. _ _ _. .
.-. _ _ _ - -. _ PAGE
.
INSTRUMENTS AND CONTROLS . b ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 3.03 (1.50) 1.
Reactor trip (any 5 at 0.30 each) 2.
Feedwater isolation 3.
Turbine trip 4.
Phase A isolation 5.
Control room ventilation isolation 6.
Safeguards sequence REFERENCE System Description No. 10.0, pg 16 _____________________________________________________________________ K&A 013-000-K4.xx / IF ~4.0 ANSWER 3.04 (2.50) , a.
To ensure adequate trip reactivity (0.25) To minimize the reactivity effect of a rod ejection accident (0.25) To assure power distribution limits are met.
(0.25) b.
Due to the large value of positive reactivity inserted by MTC during the resulting uncontrolled RCS cooldown.
(1.00) (0.25) c.
EOL (0.25) Shutdown (0.25) 547 F REFERENCE Technical Specifications, pg 3.10-15
- CAF ***
_____________________________________________________________________ K&A 001-000-K5.08 / IF 3.9 001-000-K5.04 / IF 4.3
- -., -. - - _. .. - _ - - _ -. _ _ _ _.. _. -. _... . _ _ - - _. -. . . - . - .,m. _, _ _ _. _. _ _. _ _.. _ _ _ _ _ _.__.
--.. - - -.
. PAGE
3 INSTRUMENTS AND CONTROLS . k ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
ANSWER 3.05 (2.00) purpose - primary to secondary leak detection (0.40) a.
protection - all B/D isolation and sample valves will close (0.20) spray valve to B/D tank will close (0.20) detector - scintillation (0.20) b.
purpose - detection of a failure of an integrity boundary (0.40) protection - isolation of containment ventilation (0.40) (0.20) detector - G-M tube REFERENCE System Description No. 12.0, pgs 16, 22, 29, 31, 32 ____________________________-______-______-__________________________ K&A 068-000-A4.04 / IF 3.8 073-000-K4.01 / IF 4.0 000-009-EK3.17 / IF 4.0 ANSWER 3.06 (1.45) (0.35) a.
6 hi setpoint valves blow open (0.35) 6 hi-hi valves modulated open (0.35) b.
all 12 steam dumps open (0.40) to bring Tavg to No-Load (547F) REFERENCE System Description No. 18.1, pgs 8-9 REQ-OPC-3, obj 3.0 __-_-_-_-----_--_-_-___--_-_---_--_-_---_-_----___-_-_-_-__-_-_--__-_ K&A 041-020-K4.18 / IF 3.4 l l l
--' --- -- __ _.
__ __ __, _ _, __
PAGE
. 3.
INSTRUMENTS AND CONTROLS . ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 3.07 (3.00) a.
1.
2385 psig(T:A s.23A5psy /.e/***/) (0.50) (0.50) Protection against overpressure 2.
1800 psig(%4.) o r /120 /ty fu 43 (0.50) Void formation and excessive QNB (0.50) 3.
5% NR (7: 4.) ee /f"% N8 (uA O (0.50) Loss of heat s hk with a small Wstm/Wfeed mismatch (0.50) 4.
25% (7.'I.('ae A t) (0.50) Protection against a power excursion low in power (0.50) C M v d d e 0. 5, T.sf. cr L & A b.
Decrease (0.50), puts you closer to DNB conditions (0.50) FNF -
- ka ea*pcint fer part 2.3 abe're ir net corrirtert brtcer-the Tech Speer and the Sycter Deccription TS, pg 2.3-4 gi'?er retpoint as 5%
SD No-2, pg 17 gi'fer cetpcint cc 15% THIS !?EEDS TC EE RECOEVED D"RI!?C THE EE.'_'" ETJ!r" ! REFERENCE Technical Specification, pgs 2.3-1 to 2.3-6 System Description No. 28.0, pgs 6-8, 11-12, 17 REQ-OPC-4, obj 4.0 _____________________________________________________________________ K&A 012-000-K4.02 / IF 3.9 -
4.
PROCEDUDER - NORMAL. ABNORMAL. EMERGENCY AND PAGE
. RADIOLOGICAL CONTROL
= ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 4.01 (2.00) n.
1.
Insert the rods 100 steps (0.25) 2.
Recalculate the ECP (0.25) 3.
If a mathematical error is discovered, borate as necessary to , ' insure rods will be above RIL, reinstitute rod withdrawal (0.25) 4.
If the ECP is correct, insert rods an additional 230 steps (0.25) b.
1.
Insert the rods back to the ECP (0.25) (0.25) 2.
Recalculate the ECP 3.
If a math error is discovered, reinstitute rod withdrawal (0.25) 4.
If the ECP is correct, insert the rods additional 230 steps (0.25) REFERENCE POP-1.2, pg 8 _____________________________________________________________________ K&A 001-010-A2.07 / IF 3.6(RO), 4.2 (SRO) ANSWER 4.02 (2.00) prevent damage to the demineralizer resins (0.50) c.
b.
1.
prevent channeling of the demineralizers (0.25) 2.
design flow of the NRHX (0.25) c.
NPSH of the charging pumps (0.50) d.
thermal shock of the pressurizer (0.50) ! l REFERENCE l SOP-CVCS-2, pgs 1-2 _____________________________________________________________________ K&A 004-000-K4.03 / IF 2.8 004-000-K5.09 / IF 3.7 - _ _ _ _ _ _ _ _ _ _ _
.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
RADIOLOGICAL CONTROL ~ , ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 4.03 (1.00) Faulted - a break in the secondary pressure boundary (0.50) Ruptured - a break in the primary pressure boundary (specifically the (0.50) steam generator tubes) REFERENCE WOG-Executive Volume, Writer's Guide section, pgs 48 & 61 _____________________________________________________________________ K&A 035-010-A2.01 / IF 4.5 ANSWER 4.04 (2.75) (0.25) n.
5(N-18) = 50 rem Total lifetime to date = 48 + 1 = 49 rem Total lifetime available = 50 - 49 = 1 rem (0.25) Total this quarter available = 3 - 1 = 2 rem (0.25) Lifetime is more restrictive than quarterly limit 0.85 rem /hr gamma + (.03 rad /hr)(10 QF) neutron =1.15 rem /hr dose rate 1.0 rem /1.15 rem /hr = 0.87 hrs = 52 min (0.50) [-0.2 if quality factor for neutron not used] (0.75) b.
25 rem whole body one time exposure (0.75) ' c.
Emergency Director REFERENCE 10 CFR 20 IP-1027, pg 1 _____________________________________________________________________ K&A Plant Wide Generic #15 / IF 3.4 i l i 't -- - _ _ _, . _ , .__,- -.
__ __ _ _ _ _ _ _ 4-PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
. RADIOLOGICAL CONTROL
s ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 4.05 (1.55) Rx subcritical with adequate SDM (IAW Figure 3.10-1) (0.30) c.
(0.30) 200 F < Tavg <= 555 F (0.25) b.
Rx (thermal) power (0.25) RCS pressure (0.25) RCS temperature (0.10) c.
1.
100 F/Hr (0.10) 2.
200 F/Hr REFERENCE Technical Specifications, pgs 1-1, 2.1-1 & 3.1-4 _____________________________________________________________________ K&A 002-000-K5.18 / IF 3.3 002-020-SG#5 / IF 2.9 ANSWER 4.06 (2.70) S/G Narrow range level (increasing in an uncontrolled manner) a.
1.
Blowdown radiation monitor (abnormal levels)C A/f] 2.
Secondary radiation (abnormal levels)ffggt] 3.
Condenser air ejector radiation monitor (abnormal levels)LA/() 4.
(0.30 each) b.
1.
Adjust atmospheric setpoint (to 1040 psig) 2.
Close MSIV 3.
Close MSIV bypass valve 4.
Close ASDV Isolate steam to AFW p/m n ump 5.
Isolate ticcacdn k l.w 6.
7.
Isolate upstream steam traps (any 5 at 0.30 each) REFERENCE E-3, pgs 1, 4-5 _____________________________________________________________________ K&A 000-038-EA1.32 / IF 4.6(RO), 4.7(SRO) 000-038-EA2.02 / IF 4.5(RO), 4.8(SRO) _ .__ __.
_..
4.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
. - RADIOLOGICAL CONTROL s ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 4.07 (3.00) c.
Deenergize load limit motors (a. 75' cac4) (0.40) Switch rods to manual to restore Tave (0.70) '0.40) P.eret rtear durpr b.
Transfer to alternate control channel '0.50) Tranrfer er check bciler feed pu=; in manu;1-( 0. 5 0 )- Transfer FWRV to manual (p,7 f ,4 ) (0.50) REFERENCE REQ-OPC-4, pgs 22, 23, 27 REQ-OPC-4, obj 4.0 _____________________________________________________________________ K&A 015-000-K4.08 / IF 3.7 016-000-K3.12 / IF 3.4 t --- ' --- . _ _ _ _ _ _ _ _ _ _ _ _ , _. _ _ _ _
. , o R y u r e.
f. / fg a e e- /% BORATION NOMOGRAPH FOR HOT 580 DILUTION NOMOGRAPH FOR HOT RCS 580 RCS 5000 - 4000 - 3000 - _sooo 3000 - - 900 - 80C - 700 ~ 2000 - - 800 to - - - 500 2500 - 20 - 20 - - 400 30 - ~ $2 1000 - - 300 900 - - eo - , 70 - 800 - 2000 - - 200 500 - 200 - , '00 - 400 - '~ - Soo - 300 - - 100 1500 - - 90 200 - - '
- 80 - 70 200 - soo - - 60 to - 2000 - 5000 - ./ ~
/76 5/f ) 100 - - 30 [i - 20 000 - j - \\ 7 /_ N / i _/ 500- - 20 2000 - 'N " 50.000 - " 2000 goo con - _ PPM BORON PPM BORON DILUTION WATER ~ o_ _,g IN COOLANT DILUTION IN GALLONS PPM BORON BORIC ACID PPM IN COOLANT VOLUME BORON IN GALLONS ADDITION .
. - . . Ayuce 1. y - . D-5EE='_!~iiE;..d '~~-. 5E--NSi-5-55.E715i - 'I
- r
_ _ _ _..,. .. . _. __. _..
... E...r. _... -=. _ g=---- :t=_- - -_- - -. _ -
......... - _ _, _ - - - + - - - _ _.. . _., _ _ _. , __ _, _. _ = ;; ,,, - e-- .._ - - --- - - _ - - - - _..__ =.;. 0-e- - - . _-__ _- t -- -,, __._ ::- :_ .===. :: =..t. 2=. = ~- - ., :- - ..___; -- - = _
__.
- , _ _ - __g__.
_
6 = -:r r -- :t -. - :- : =: .. _ : n.--= _ r_ - . r t -- . :- -===: - w- = :._ _ g _=: f _2 r2 .2=._.
.. -
- -_c: ;t r.
- - r"1 : + 5.
.II:EZ ~i- - I: 7 2Ein ~-! ' = 1- -- -+ --2. !r c . '.%_ - - -- -200--; ...___n_ ?..: =.._. : E..-E_E..T. __2.
. _- - - - m .. N =_4.;._:__E_. _...i. 2.: r. -- l. _f,..c.i. =.r _l.-_ i r. =__ . .. .. _. ; y . ...,.... -., _... _.. .,_ _ _ . . . _. _ , ,,.. r ,
- -.:.
- ~ =e
- .:_. _. : --: : _.: : =_. u.
__ _- -s- ...w..:t_:c::n.__2.._. :==:t.r=== : - 2ng__ _ -- w ---. _ _
==:r. :. ;- ___.. . ..a r.t. =:!= = _.:t =w_m .;:
- =t rs... _ a g-
-- - L-2-1- w: - K. N__r+=~ -- e_-
- -400 -' - . w 7*-; .-- '-' ._ '.g%_.. j_r ~ ., _ -
YEW',
. _ . .,_., _.. kNN'%_._ . _. _ ___ .__1 -: " i -- +- - :r - -- .. '3 -
- g',~[\\..g.y
. -~ g - _._ __ _. .. _. _, _ _ _ ,--
_ - _ _ _ - - .. _. _ _ .._ U-600 -- t =_=-.t.
n.~ -w_ .j__.
- _= g__ -* -- q.
- ~,.- . m =_= r =.._: ..., > w-(3p ..
- ,Nge,g--,-+
- -.. _,.____,__~ . - .; :;._..; . -- _3 - ._. _: _: __ 2tr g - :_- Q_.b_. _. p....... { I.....;...:.. .r. -._.._] ' -
. .: ... E* =_=.;._ _ . .. _ _ U =. _.. + - -=_ -t. ;-
- ....t.:_ __p_ :
. .. _. _.. . ... - . W
=
... . ._.._..._; . . .. _. _ _. _ - g.. __ ,_ ;,..
.7 g a-800 ~T = "; 2" # ~ C" "~ ~~ ~ _ _ _. . y ci ?:55: r5!i;U.r=l #I [js-f:i.EEliE2 N5MLM! E . ' [1: i-fd k +iEtE=i;:.
- i:"iff'#HEEs M:ii'NN!N9 i i:: 'i=-55
=g siga; = :s.== i..aei:= agggN.N j .; ! ;i.: - i " -=_. imE :====!=Miirgs!-w=2:RW iau=.:- j g j 7 p. i
- _=m:g
. g p.x x x i -ri $ _1000 p p .p-j-
- _. ;-- jn
- y
,- l \\}.
- y i
i i N:\\ \\\\ N
! ! ' - _u00 : ! I i i ! \\\\ \\ \\ N, 1500 PPM . , - - i \\\\ N. N . ,
i I i .~ ~ . . \\\\ \\ \\,: /1200 PPM '- l I t- - -/JPC f-
- _.
- , =... {: !Eil)'2-il;: - :E'.$;f!!. =j. {- l \\\\-( ~' - _ ^ f r_;[:' :E -i: i=- ;j_j; i}-2121.u:ll l.
l % ~ N.
900 PPM _ . i \\ j-1400 _ . e n3.... . :Lu
! \\ --t p
- L- ::):
..
- = ' ~ -. : ' ' . . s .{Ij' iE --p - 2: : ei \\b 300 PPM . - -[ - : , N- ! \\
. . - - . ' - 1600 l: '..u:=rj:
i -'
[..' _l.. l. - [:_ -Z, 'l l l k
i .O PPM
- .
- 3. _ :_.- r i i. !
j.
tj_,- j t , ._.
. ! - -
.
- -
f. ' ~ -, '
- l '.. I;. I f i
- , , _. _- - j
, --r ..p _ .;__l'- = ;..-- .. -.p... j 4-i . .
- ~'
'.
-1800 7-
20
60
10) , , , r,7-o o Power (Percent of Full Power) _.. __
. ' - - REACTIVITY DUE TO XENON AFTER STARTUP . . . . / W /-r / f _ .. - -- - -- - - - - Percent Power 2- .= r. r:::::== :_.
..: : =:- ---
- =r -
=: =:=q: =t..
- _. _ ;
- =.t..
- 2 :_=
_ ::m r. 2 = r_ _ . ___.__- - ~ ~ 100 % _gg 7- :. ' ";4 ~ ; H - - ~ ' ~ = = '~2 =1 - ' - - - ' - ' = ~ -". _:.=y"E=fg f ;._;.4=__- -:i;: _ J. r 7- __ -3000 80 % = = t:..t "=1- -- t -
- t --
_.. . .. .. .. _ =-.t -
;=- - --,
: T :.;=..... ;=A+ ' =r.= -4-.- : _..._ _ i=. :. _3.._.
=: : z = =.: ; ,e - - -:. = ..==- __ _ _.. = = = 2:-.=-.z = = = ;- .. - _:=== 60 %
y - $u:~ q:- a
- =---..
=R -. .t=- r - -- --. -
- .a... x =1.=
1EEI-~$~'.~..W..,-hfEQ&- 55.Q =*.-~= -?:Wf,_ ' ... 79 7, a_ .,. _ _...,. _.. -.... ......n..... .. w _ _ _ __...._..._..y,. . g__u.......__ .... _., _ _ _ -.. _ _.
- = t - -+ . ._.. . - - p=: =-g::y-:==::.:===.:=.=. =-:-- - - ..- = := = a_. __c.. a__... _. _. .. 40 % zij.2.[~c -[M[i%liiR-Mr - .a :-1- :-:---d==i-fi- :4 - 9.~=4=i/,/Mii-Wni"=..Esms?"...** - _ ... _.... _- , .. a... _ p. 7 '.. ._. HE1.E E-F.
== -:, r -+ -~. .. _ ,..., -. _In - /f_ fu,t: _ i=== f :ti_m Ei: r 2 ._.
7... 1_; "
x_ ._r-- = :.:- t= =. - , ..,. . b.
-. - =c= = t=2 }......... _=' : 2 :.._a ._.....,. =:- - -~-- - - - - - - - - - - - -
- .
- --:. --- .... '. _ 'j-2000 : - .=-:
- . = r;=
- _:c.l.///,.f..= =_u; =;..:: I= =. a::. 2.
= = t=.. =n ul=; =:==- = - a- - = . = =
==
=-t _-: -
-- .g .- - :y ln; c. r. --- ~ m- =;}=;:1= :- - 5. - l, :=g :. _..n- - ~~- .- - - -- --s ~ ~ - -- - - u
l
- f j g
c, 4':* _-b 225 20 %
- . dye..! // /_./.i[' :E)~%i if iy_l=id =i" -
. f[ ~i~ . --. >. 5.b.
!-f2;b;;=.d f: I i fb . -MW!Eir NEMisiEl $ E=:Ei T/MFP=6-Z.. s#-'
- - t- --
' -' t;T j~ . -*- - t :. L = Q
.jf f. / 1
- /..
.. . - ' : 3.. ; :.; . =. ;._,. f, J. f.. !.. ri /.! ^. : 'J:* U . i .' - g . . ,...... _ -~.~..._~-.-'..-_{.
- J.=. : =: _;
= ::.= f".c. ;.- - - -
- /:= g: ::--
=;n ;: / ' =n-ff:f; fi:: -!..
- ......d.
I C.
.:L.:: E f. fc. M
(% .. . . . i'_=$.. k.: 2 !:- 'l. _L 'ii'i '.Pfi: _.- ' t:dI2-[ 2!!2.5.. -i'.L-kg f.. h-s... ... 2i!!: i < 10 % - - . _ .4 . . v er:. e. :. n -
- - -
z.
- .
- } ft l=: ft=t-- - = - :=
w ....;.. s.
. a_. _ -; =: I] ! I l ' ' If-.i f.
~' Lx_ f'.. i. '.. . - -
- .
/i'.- I
- .
} ..e - I-1000 ... . t , -
- _
' h ' ,, ., . , . ', ]/[y/=../ I !
- l _ ! . ! . - ' ' . ' . REEM l.
I
i:.t -!. ! '
- -
-!i. = - t :=l d y p/gt= j j = i. [ -g
- =l: ;;
9 /39 A: . . ' j i= ! . . . ggg= h
!.
i .
a-.p _ l'-i'-
p/A' ... . .. l i l~ I: I -
' - I i-t+ - !-
/ i i . - - - - -
2b
60
100
, i TIME AFTER STARTUP (HRS.)
l l l l
- - . , BASIC CHEMICAL AND VOLUME CONTROL SYSTEM fiqa re 2./ -, - - .... ,[h *"" .= ...... . = = . = =. . .c .., -,-.. sl,-e7>-
- _~-Q /
- ._.. e ,:,2 ,, , o ].._...... -" -**>i' ". ~a o ' r.f.,=,=,,.=. o ,.,.,a.,,,. ,li.c 4 ~ i c.... _ r.- . t I r(V ' / ~ -*a=''' - -. . n-.= c.y.,o, oo, =Tn 3 _ ([, .c:o. coo..= ,av.. .o ua ca.aa .%s.
. _,,,,,,,,_0 I co o u.
L
** g => %f .. ,,,, ' _ _ _, l .. n,. n. J3 ) ./,L'J'.i.
_ c@_ {""'.'."". J
::
g - ,f.2 g . ... , , ,, .,-T _.
e.
.=> es. r - [ l., E...)(1 " - . it.
'_ _.v.".".."'.".;"~ lC10= " -
===.} ..,,, u... a susuu , w .a n.
9j gj,, . b .o . m y g _ m.
I a*
- .".: /
- +>o,, g I .,_u._ n~3 ",",o.f - - - - - - (t>M ( , D(>f - -- ... n.
i W, .y .. . c4. l W.. l , d - 0,,J.
"3.
,!,"4.
r --
- ,;
. I rf.. i '"d.t.
ylr..irr-
- -
- , -... y _. _. s n l w/fu,c 4=== % b % b s' k -
4 ' a,t a c OD e, ' n,, ~ . D h. Xh \\ g a[ M
ye 3e W '-
se g1e og 'i R M C i s, As s% a . s
n L h
y
9 - % p,1j g k ,
- s t d.
4w &s % x N y ." dt > N ' s
- >
NC A '(
- nk s
t . O S
"1 % 45.
qk u s de , u.
e
49 $ +kS s
4 v N
la > 4 ' _A ,__ a u,e ~ v S NN 4 kS %; y qS LA
N s
s w s W , + q, a n e se t W =a.
ut g,,e , a= , 4, , N ' s , ,.
$ 5h.' @ 3_4,. , = % -.:-*= 'e ' b .t, s ga ,e w 11} (h ,'8 i
7di
At k g
M U n cc
8h - F-8t wh
sa % __
TEST CROSS REFERENCE PAGE
.
. QUESTION VALUE REFERENCE __________ ________ ______ ' 01.01 2.50 BSN0000152-01.02 l'.50 BSN0000155 01.03 1.50 BSN0000187 01.04 2.50 BSN0000189 01.05 3.00 BSN0000190 01.06 1.50 BSN0000198 01.07 2.50 BSN0000207- _, 15.00 02.01 1.50 BSN0000150/ 02.02 1.10 BSN0000160' 02.03 3.00 BSN0000166 02.04 1.50 BSN0000169 02.05 2.40 BSN0000170' 02.06 1.00 BSN0000175 02.07 1.75 BSN0000179' 02.08 2.75 BSN0000159' ______ 15.00 03.01 2.25 BSN0000148' 03.02 2.30 BSN0000162' 03.03 11.50 BSN0000171 03.04 2.50 BSN0000173 ,,9 03.05 2.00 BSN0000174 _ 03.06 1.45 BSN0000176' 03.07-3.00 BSN0000177 ______ 15.00 04.01 2.00 BSN0000161 04.02 2.00 BSN0000181~ 04.03 1.00 BSN0000182/ 04.04 2.75 BSN0000183 04.05 1.55 BSN0000186 04.06 2.70 BSN0000199-04.07 3.00 BSN0000208- ______ 15.00 ______ ______ 60.00 ,
- - - - - - _ _ _ -- % s4: esc . U.
S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: INDIAN POINT 3 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 86/06/05 EXAMINER: NORRIS, B.
S.
APPLICANT: M nbfY FF - .- g INSTRUCTIONS TO CANDIDATE: Read the attached instruction page carefully.
This examination replaces the current cycle facility administered requalification examination.
Retraining requirements for failure of this examination are the same as for failure of a requalification examination prepared and administered by your training staff.
Points for each question are indicated in parentheses after the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up four (4) hours after the examination starts.
% of Category % of Candidate's Category Value Total Score Value Category 15.00 25.00 5.
Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics 15.00 25.00 6.
Plant Systems Design, Control, and Instrumentation 15.00 25.00 7.
Procedures - Normal, Abnormal, Emergency, and Radiological Control 15.00 25.00 8.
Administrative Procedures,_ Conditions, and Limitations 60.00 100.00 TOTALS i , FINAL GRADE % All work done on this examination is my own, I have neither given nor received aid.
CANDIDATE'S SIGNATURE . - - _ ._.
_ -_ . - _ _ _ - -. - -. - . - - - - - _ _ _ -.. - - - - - -
ES-201-2 , , NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS
During the administration of this examination the following rules apply: 1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties, cc 2.
Restroom trips are to be limited and only one candidate at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearance or possibility of cheating.
3.
Use black ink or dark pencil only to f acilitate legible reproductions.
4.
Print your name in the blank provided on the cover sheet of the examination.
5.
Fill in the date on the cover sheet of the examination (if necessary).
6.
Use only the paper provided for answers.
7.
Print your name in the upper right-hand corner of the first page of each section of the answer sheet.
8.
Consecutively number each answer sheet, write "End of Category " as appropriate, start each category on a new page, write only one side of the paper, and write "Last Page" on the last answer sheet.
9.
Number each answer as to category and number, for example, 1.4, 6.3.
10.
Skip at least three lines between each answer.
11.
Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
12.
Use abbreviations only if they are commonly used in facility literature.
13.
The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
14.
Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or not.
! 15.
Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
16.
If parts of the examination are not clear as to intent, ask questions of , the examiner only.
l 17.
You must sign the statement on the cover sheet that indicates that the
work is your own and you have not received or been given assistance in i completing the examination.
This must be done after the examination has been completed.
l Examiner Standards 12 of 18 - . _ _ _ .
. {, ES-201-2 , e 18. When you complete your examination, you shall: Assemble your examination as follows: a.
(1) Exam questions on top.
' N2)-Examaids-figures,' tables,etc.
(3) Answer pages including figures which are a part of the answer.
b.
Turn in your copy of the examination and all pages used to answer the examination questions.
Turn in all scrap paper and the balance of the paper that you did c.
not use for answering the questions.
d.
Leave the examination area, as defined by the examiner.
If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
( ( Examiner Standards 13 of 18
5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE
~ THERMODYNAMICS ' s s QUESTION 5.01 (2.50) Calculate the required boration/ dilution to maintain Tavg on program for a power increase from 50% to 100% with no rod motion and equilibrium xenon.
Initial conditions: equilibrium xenon, rods in manual, CBD at 220 steps, boron concentration at 1200 ppm.
Use Figures 5.1 through 5.8 (attached).
State any assumptions and show all work.
QUESTION 5.02 (3.00) Indicate at which time in core life (BOL or EOL) the following accidents are more severe (i.e. results in a longer time spent at a higher power).
JUSTIFY YOUR ANSWER.
(1.00) a.
Total loss of coolant flow at power b.
Rod withdrawal accident from low in the Source Range prior to any significant reactor coolant temperature increase.
(1.00) (1.00) c.
Loss of load from 100% to 50% QUESTION 5.03 (2.50) The plant is operating at 33% power when the 31 S/G Main Steam Isolation Valve fails shut.
Using the below initial conditions, calculate the new steady state values for the listed parameters.
Assume no operator action, rod control system in manual, all other control systems in automatic, and no reactor trip and no SI actuation.
State all assumptions and show all work.
Initial conditions: Tavg = 554 F Tstm = 539 F Core Delta T = 18 F a.
Turbine power b.
Tavg (loop 31) c.
Tavg (loop 34) d.
S/G pressure (loop 31) e.
S/G pressure (loop 34) l (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) _ ._. - _. -- _
5.
'T4EORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE
- 74ERMODYNAMICS
- t o QUESTION 5.04 (2.40) You are in the process of starting up the plant with reactor power at 10E(-8) amps.
The reactor operator inadvertently moves the control rods IN for 20 steps.
Assume rod worth is 8 pcm/ inch, an average neutron precursor decay constant of 0.0767 sec-1, and a weighted average delayed neutron fraction of 0.00596; with no further operator action: What is the resulting Start-Up Rate immediately after rod motion a.
(1.80) stops? b.
What is the power 60 seconds after rod motion stops? (0.60) QUESTION 5.05 (1.50) Explain how and why Differential Boron Worth will change with an increase in moderator temperature.
QUESTION 5.06 (3.10) What condition is prevented from occurring by tripping Reactor a.
Coolant Pumps (RCP) when subcooled margin drops below 32 F? (0.70) b.
Describe why subcooling is used to determine RCP trip criteria instead of Reactor Coolant System (RCS) pressure or Secondary (1.20) dependent RCS pressure.
State FOUR advantages of continued RCP operation during a Steam c.
(1.20) Generator tube rupture.
I (***** END OF CATEGORY 05 *****) - ._ - . _ _ - _ _ _ _ _ .. .. -.. . _. - _ _ __. - _ - -
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE
~ .
. QUESTION 6.01 (1.00) What would be the significance of one Intermediate Range channel being(1.00) undercompensated during a reactor startup? QUESTION 6.02 (1.50) List three conditions that require Emergency Boration.
QUESTION 6.03 (2.00) What is the operative force for the Pressurizer Spray Valves? a.
How do they fail on loss of this operative force? (0.50) b.
At what pressure should the spray valves begin to open during power(0.25) operations? List two purposes for the bypass line around the spray valves.
(0.50) c.
d.
What is the basis for the combined capacity of the spray valves? (0.75) QUESTION 6.04 (1.30) on the attached drawing, Figure 6.1, designate the correct position of each of the breakers for a normal at-power lineup.
QUESTION 6.05 (2.40) List the conditions that will cause the Motor Driven Auxiliary Boiler a.
Feedwater pumps to automatically start.
(1.60) b.
List the conditions that will cause the Turbine Driven Auxiliary Boiler Feedwater pump to automatically start.
(0.80) (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) . -. - -_ - _.
.. -.. - - - - -.- .- . .- - -..
. 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE
~ . t . QUESTION 6.06 (2.50) What are three reasons for having Rod Insertion Limits? [0.75] a.
With respect to the Rod Insertion Limits, "...the steamline break b.
accident imposes the highest shutdown margin requirement."
[1.00] Explain why this is a true statement.
Considering each of the following sets of conditions separately, c.
which condition will make the Steamline Break accident worse? [0.75] BOL or EOL Reactor shutdown or at 100% power Tavg at 350 F or at 547 F QUESTION 6.07 (2.00) Indicate whether the OT Delta-T and the OP Delta-T setpoints will increase, decrease, or not change if the following changes occur.
CONSIDER EACH CHANGE INDEPENDENTLY.
JUSTIFY YOUR ANSWERS.
Pressurizer pressure decreases 100 psig.
a.
b.
The N-41 lower detector fails low.
QUESTION 6.08 (2.30) Describe the response of each of the following items to a 100% LOAD REJECTION which does not initially cause a turbine trip.
Assume all systems are in automatic and no operator action is taken.
(0.40) a.
Steam dump system (0.40) b.
Rod drive control system c.
Steam Generator level control system (0.40) d.
Pressurizer level and pressure control system (0.40) Plant response to the point where parameters are stable or the e.
(0.70) reactor trips.
(***** END OF CATEGORY 06 *****)
7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
' RADIOLOGICAL CONTROL ' i . QUESTION 7.01 (2.00) In accordance with POP-1.2, Reactor Startup: What operator actions are required if criticality is achieved 100 n.
steps BELOW the Estimated Critical Rod Position calculation? (1.00) b.
What if the rods are 100 steps ABOVE the Estimated Critical Rod Position and the reactor is not yet critical? (1.00) QUESTION 7.02 (1.50) Prioritize the below listed Critical Safety Function Status Trees from highest to lowest: 1.
Containment - Red 2.
Core Cooling - Red 3.
Heat Sink - Yellow 4.
Integrity - Orange 5.
Inventory - Green 6.
Subcriticality - Orange QUESTION 7.03 (2.25) In accordance with ECA-0.0, what are the immediate actions for a a.
(1.50) Loss of All A/C Power? b.
What is the basis for the following quotation from ECA-0.07 " NOTE: CSF Status Trees should be monitored for information only.(0.75) FRP's should not be implemented."
l . (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) - .- - -.- -. - - . _ _. .-. __ - - -
7.
PROCEDUDRM - NORMAL, ABNORMAL, EMERGENCY AND PAGE
. RADIOLOGICAL CONTROL
s . QUESTION 7.04 (1.50) Answer the following in accordance with FR-H.1 " Response to Loss of Secondary Heat Sink": When directed to stop all but one RCP, why does the NOTE state that a.
33 or 34 RCP should be left running? (0.75) b.
What action must be taken when the RWST level decreases to less (0.75) than 9.1 ft? QUESTION 7.05 (2.70) Answer the following in accordance with E-3 " Steam Generator Tube Rupture": State 4 parameters that should be monitored to aid in identifying a a.
(1.20) steam generator with a tube rupture.
b.
State 5 actions that must be performed to isolate a steam generator(1.50) with a tube rupture.
QUESTION 7.06 (2.55) Answer the following per ONOP-RP-3 " Loss of Refueling Cavity Water Level During Refueling": If an irradiated fuel assembly were to become exposed to air, O.
approximately now long would it be before you exceeded the quarterly 10CFR20 limit for whole body dose if you were 30 feet away? (0.55) (1) one second (2) one minute (3) one hour (4) one day b.
List 5 immediate operator actions for a loss of level in the Refueling (2.00) Cavity.
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****) __ _ _ - _ _ - - - _.
_ 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
' RADIOLOGICAL CONTROL
s . QUESTION 7.07 (2.50) What operator actions, if any, are required to stabalize the reactor plant for each of the following instrument failures.
Assume a power level of 100%. (1.30) Power Range channel A upper detector fails high n.
b.
The controlling steam flow indication channel fails high (1.20)
(***** END OF CATEGORY 07 *****) - - * - -w-w-w -,----r, , - -, -, ,,-,w, ,v,,,, ,, _,w-m,
+,-,---,,-,,,--,,,.-,,mw, ay, y
w,--,, - -me, ,----,-,_.-n,., ,-w----mw-- --een m, --qw,, - -
8.
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE
' . $ . QUESTION 8.01 (1.60) In accordance with the Technical Specifications, what conditions must exist for Containment Integrity to be satisfied? QUESTION 8.02 (2.00) Answer the following in accordance with IP3 Technical Specifications: c.
Define HOT SHUTDOWN.
(1.00) b.
Which THREE parameters must you observe in order to verify that Reactor Core Safety Limits are being adhered to? (0.75) c.
Provide the following temperature limitation values.
1.
Pressurizer heatup rate.
2.
Pressurizer cooldown rate.
(0.25) QUESTION 8.03 (2.00) Answer the following in accordance with AP-10.1 " Operating Orders and Control of Stop Tags, Do Not Operate Tags, Locks": n.
What is the meaning of a RED lock on a valve? b.
What is the meaning of a YELLOW lock on a valve? What is the meaning of a GREEN lock on an electrical breaker? c.
QUESTION 8.04 (2.10) Answer the following in accordance with SOP-CB-2 " Containment Entry and Egress": Prior to entry, what three surveys do chemistry and HP perform? (0.90)
c.
b.
List two types of dosimetry required when entering the containment while the reactor is critical? (0.60) What action must be taken if your dosimeter reads seven-eighths of c.
(0.60) full scale? . (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) . _ _ _ _ _ - - - _ - -.. _ _ . . __ _ _.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE
. , t . QUESTION 8.05 (1.50) Answer the following in accordance with AP-3 " Procedure Preparation, Review and Approval": (0.50) Choose the correct answer to complete the following sentence: a.
A temporary change to a procedure is authorized to Modify a test that cannot be completed as required.
1.
Provide guidance in a situation not within the scope of the 2.
procedure.
3.
Correct typographical errors, (1.00) b.
Who must approve a temporary change to a procedure? QUESTION 8.06 (3.00) The plant is operating at 100% power, all control systems are in automatic, except as stated below all equipment is operable.
Using Section 3.0 of the Technical Specifications provided, for each situation below, state what LCO is violated, if any (reference to the page number and paragraph number is sufficient); if the situation is not a violation of an LCO, justify by reference to page number and paragraph number.
Consider each situation separately.
- 33 AFW pump failed its latest surveillance.
a.
b.
- 31 SI pump circuit breaker is racked out for replacement.
- 32 Charging pump motor is being replaced.
c.
- 31 Emergency Diesel Generator fuel transfer pump has seized bearings.
d.
Assume that all four of the above situations occur consecutively.
e.
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) -. -.-- .- _.
- -. - -- - . _ -. _ _. _ _ -,
. - ---
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE
, n . QUESTION 8.07 (1.00) According to the Technical Specifications: How many consecutive days can an operator work 12 hours a day? (0.30) a.
b.
How soon after working a 16 hcur day can an operator work another 16 hour day if he continues to work his normal 8 hour (0.30) shift? Whom, if any one, may authorize exceeding the overtime quidelines? c.
(0.40) QUESTION 8.08 (1.80) What log book, log sheet, chart, computer data sheet, turnover sheet, or epecial log / report should an on coming Shift Supervisor use to determine: Equipment which is out of service.
a.
b.
The length of time the facility has been in any Technical Specification action statements.
Trends on the volume control tank level.
c.
d.
The names of the licensed operators who are meeting the Technical Specification staffing requirements.
The value of Dose equivalent I-131 in the primary coolant.
o.
f.
The present values of the Technical Specification power distribution limits.
(***** END OF CATEGORY 08 *****) (************* END OF EXAMINATION ***************)
_..-__ _ .- _ -.. _ _.. ._. _ _.
_. - __
- so , fi q u e e.
6~/ Ar a c e-S~. 2 - - !
DILUTION NOMOGRAPH FOR HOT RCS 580 BORATION NOMOGRAPH FOR HOT 580 .l RCS 5000 - 4000 - 3000 - - 1000 , 3000 - - 900 ' - 800 30 - - 700 2000 - - 600 to _ ~ - 500 2o - yo _ 2500 - -400 ' 30 - } ' ~ 40 - so - 1000 - -300 ' Q-900 - so - _ 800 - , I 2000 - - 200 _ g
200 - 500 - ,
-150 voo-400 - '~ < soo - 1500 - 300 - - 0 i 200 - i000 - , j - ~ - 80 l 300 - 200 - - 70 'O - 2000 - - 60 - 50
soo _ 1000 - 5000 - - 40 . ,a ; 30.000 - 100 - _ ~ _ 20.000 - - 500 - - 20 N~ N~ $0.000 i , too 000 - - ' ~ PPM BORON PPM BORON DILUTION WATER 10 - IN COOLANT DILUTION IN GALLONS-10 PPM BORON BORIC ACID PPM , i ' - IN COOLANT VOLUME BORON
I ~ IN GALLONS ADDITION
. .
. . t - hea<e es:_3 I . - 600_ . _ _ -- . J __ - - , - . r 590_~ - ~ ' ~~; . -:/ .:.
I 1 JE I A E V 580 _#. f r' , .. . _ -: .=,.: - 570_ =,/9I . .
,, - ,- , - _ -.M I.
.. , , .- 7' ! (Or ) -. - ..- r - .: / - -- , 360 _ y - , - . .-
-
.. , p- - r .+ / y_f.
K l = . , f I ^
l'~ ,f,,an.,E 4:: L /
-
y < . ,,
" ' =- - + - 550 / -- _ _... __ _. __
- _--t - -
- . - -_._
- .
. . . ... , . p.
. , .,_ -w E _- - . u .
.. - -_ 540 - 76m._P E: '
- -p.==Tr %-%
_ -e- -,A:-
- _
-. - - - --- r i a.
_ . ..._ . - = _ e ::=_ - -~ .w ._ _: .- -:. _ - - - g ,,,-r _ _ _ _ P=.88_ .,,,,. + - - , ' -.+-- ... e_ . __.
- - - . _ _ -- u - - t - t_- -. -- -. . 1__ c> 3 o_. t ~ ad 103 . 2b ad 6b o Reactor Power (%)
. - . . S arE d. f f ' . I + - ..
- . :+=..
. :::.. 2_:ne.
- _
- m.:m..
2.r.. -
== I . _. , _. _ - ..t--- =r - _..r- .r. - =r: 1r r-. .., _ _. _ -. -, _ = ...... _ m.;. _..~=== ..... ,=== * -._ _ =.g;
h=
.;.. =,._ _ -., _ - _ . _..__7:3_ r= gj.g.. :_...y ~ * = = - . ^ ~ - = _ =., _.. 4,__._ r : _ O's- + - - =- - ..__.
-- .
.. . - - . _ _ . - -
== _ r. _ .. _. r_".. C. '~f... - - .... -
'~_~U..~. . _I.._.*...*j....-.-. '--..*i :1 . ! '
" 6- .- .I ' I.: : .. . ~ ~. _ _. . T.
g ...3" ."" ._ 7 ( -.I "~ ~ ". ~ _.~ { =. . . .. -- - r-.p rf '_ _ --_$; -~~ '. -!:;.g'. 2 7.:.;' . ..;. _.. '
- - l~:,;~.;#.. ~ ~ - ~ * - - - *
~ ' ^^ - - g - 200 --.--:' _ ..-.I -- ; ":
- n:-
-. : - - - = _ = =.n, -
- . :..:
- . w. x..:.
-. :. __ g.
..n... $ =.... .. ..e _ t :... , . g.. _ 1m =.t.__.
......s . ..g.
= nyr..-[:.rr :- =: : -- :.. ~~ n Tr:-: *= _- rrn _ c.
.:.- -: /. - - +. = ;W%\\ ---g;..n rc r :: ;_.:-- : - :: : '_ : - . - - -r .:' =t." { '. ~ " ' - f ..IL.._..J-~
- ,,..
~*-'-%(Qg.. .. p ;r;t- :,' :-r-i :r:::L.O --+-.:- nr2 _ -..
- .: :3 d.: n.,;.._ - __t r gwwv
- - -cr _ .' .3 g;,N~._.-'-t- .. _.. ' , ;-~ - - -. - _. = - .. - 1.
-.-:- _ _ = _ -400 -- s .. _ _. _ ' ~~"' . ~-* %N k MC:! -' . .- ~ w_.w.,. - _ - _ _- s _ - -- m ._ : ._ --- L..=:= - - :. -h-- - r.._ . .e... . _ _r - ' Ae mM - - - -- - ".. x _ _ _.
- ..,__-t_.___ -600- _
- NA g,
--- [g-by..ww _ -+ -- ;. - 7g.. ---;.__ . U ... a - 4- -
- 73%t
" ~C.T. : '.~ "...__,._.;=-= . -. . -4._.-- _y,w\\ l .... - 6 2.~.*! = - .r.. - p'1;~~l - =:-..:__ -sr . g.. {..:..r.... k.... - [... "C.. ~3 b ..~t".'
-...: ... _g... __.
. '. ?. . .
ar.t.f :. :.--t.....p.. . _ - .. U _- .. _... _ --a_=- -- Cd ~... ~ g - ZiEdi:==!!=b=i=. tin-i=.0gai~=%!=%%h E . la ':R! ' Q-800 [ .a-gs ag
- .p=p -!=mg rg.Thg.NNig:.: i: t=--iss e
. Fi f.
.. WEMalAiW ; :!!r imih=lMMa%N \\! - " "- Y55!515EN'dYNNk "!
- -!
_....- p; g ; m g i.n q - 10 00 - :. pg. l .m.
. g p i: i t :- .=n t.. c i N y NiN: N i . . i i -
\\:\\ \\\\ \\
' !
i ! I I I \\\\ \\\\ . 1500 PPM \\\\ \\. \\ (. -l'00 . . i I I - ! t - l' ; :- bi b \\.\\ k N 1200 PPM . i . - - . p x-- .- .[. . h 1... l. :=i. [: l N\\ \\j._ ~ ~ ~ '
- \\ N
~3 900 PPM . . .. i - -i : j-g.j l =.QJi.ui[Fel L-1400 (=_p_gE =.- r4" !. [
N\\I .... h..- >
wr. t c ... _ , . ._.._r..-. ... - > .
..
i: ja -T- " {\\:\\ 300 PPM - rr,p.
. .}! [.' -C -
I
-
- -Q
- : ( ! i x- _
. ' ' . ' r . " * -' ' i., -i ; j l l !\\
-1600
- '-
r 8: ....,._: 1 -t9_ .
.0 PPM ..... , g- _- f . . t r _ _..: =_. :... , . . = :-:. ,
, . .....--. . . . . t . . . - r.. .. :. . j 1. -- . . . -- r ..F . p :.
- -
-
- jr
-. p , ' " , ,
20
60
100-1800 7 , , (Percent of Full Power) Power
. . . . '- AVAILABLE CONTROL BANtC WORTH AS A FUNCTION OF BANK POSITION , - - Squ w 6.5 y . . v ,, --. rm_ . - -- . -3500 ".y .__.- - - * - - - - _ _ _ _ . _- _"; _ _.- __ - . -_7 N-- _ _. _ _ - - _ .____,_ _ _ - .._ .__. - -- r -; . . - -.
- ,".
._ J. _3__ . . _. _ _.. __ .__ F - .X-_- . -. - _ -b
- =_. _ _g__.&q__: -
._=_ _ -.E. - . _ ,A.
' .
- .
._.
- ~.__=g-- - - -== -.-; i;. --+- - .. .--r ... +. g _.
_ .,_1_g. _,_ ___ , _ -3000 _ __ ,__ __ ._ _ '*- ' - .- . -t o - --- r El- _' --- -- r -t- : -t _ __.'-i _ . _. - - + ,- a, , g.... _ _ _. - - e__+.-...--- - * - -T -- r--- - u {L. -. -:__ - .g.,+-. n;__.
s_-
._ - - - .,_ _--
_ ,,,, _.
--t
t-- - rDh + ~ -~ L
- - ~t
4 ~
- _
_-4=...*._.-t--
- _ _ _ _ _ - -N IL_,_ _ o-4 r_ g - ; ~ *- _ -1
- ___.
_ x
- ___,.--
- > [ = - t---f:.-t _._ _ i __ _ &__. L_ _ _. __~\\ .-- - - - - - - - . \\ I._ -- Y '-~ '~- - -- r -+-g -, _ - -, - _. . > ,._ _ i _ _. _. t ____ -
- r- :- ~~ ~
-. v-- -e s _ _.. - nt ;.. _.. __ri 2 _ E- _E:_ r=--! N=-t -~ ~==1
~ P E U - _.___...-i----.-;I---__;_ _.___ , ' ';l M - - .m < ._ m g _. - . _4 - - - t.-
_-_p . M' _r . . --. .-..-_.5........ - .c =. - =_ t, ; _ _. -- -- - - - --7 ---+_=.=-1_.._-t_-.-..__..
- -1___, __
. _ _; __ __p_ -- . r_ [_ - t- - -+ .. q' - . __w_-. t :. _..j _ a.
4._:= xl=...: .t= ... :
-2500
c .- ._- rn nz r -.-.-- -. - ,_; .- __-_--. _ _ -- - r. h_.: ';--. u.t - ;- _; = F' - T F- _ _y ttr :: -d ;'.;;z [ b- _ t -- ;_ _._5_ .~~ 1 = -- , ,_X-+ _,__ _ . -_-_._.
.-
- ,2 :.. y_.- r -.. -..
- - t' r '
- ^n
. .. - {l k_=: h..... _ _,_ \\_-E B _& _.q _ m _-_:--Ej' =. t :_.{-i E.T=1E=ii ij 1:j?;i c h I-~ r - + - -- _... _ _. _ -- ':.__._..dii= =.Z~~Mi.i!-EE T=iE~lbi -t'i-E?r?M . _ "., _ _ _ _... -. EOE- =_:t= - _ - . _ _ _ _, _ -.- i .. - c - - -_u c = =-tn _._.- .. - _: - _ _L__ _- r z. r. -:- _t.=; -- _. -.. _ _. t--+--- - -; __ .. 5:--. :.:_ =:= p A *:11 --1 --. - 3__ -f =. _.__ h _.__.} =.. En_.-I' L f=-C _r- -n:- - " _.. -
- {. =.. _. _.;_
- h..
t
=====---- -
- 9:
,__in 1 - t- - ._ r - -- {.. - __ -+--. _.4._;:;n- -. {2 2:=le_ n:[.:_ .T -- _ -
- . n-
.,--e--. - -- - .a . _. . _. _ _ _ _ ___..i ......_... _ ;.;"E - I"- , - -- _ :- x r r; _,-.__:_ _._ ,__t r_._: _. =_-.. =- - _. r - = ~- .- _r - -. -
' 3-j[ -_[_. __ =. -. *dH . ' t :--. i 1 !-+:i 21-- . --- - - " ;. n. .7 ;.- { -e- - 4 - p_ t__ - __ . .. -- j.
- - - - ! -_ r.--l
- h. ~-*i
, . . _ _ - .-- ~;- nu . . ..L I -. - . i - ! .[ i- . _, _ _. . ... .
...- t- - t: L. * = t- - * ' - *
0 _ t- ;. ,. : _-*.n-_ ___. _ :. _.._...__ i. n... 'p ! ~ ' -; , - - : - -- t -! rr " r :'I - ' "-t =1 _ __ .. [.;ii-j -{ = ; = = : = x.E~ F ~" F F.
L-. - - . . -- t - -200 . :: -- _ ,., _.. [i h5.
i ~ ~ ! -1
==i = L + r :' i' ! i
l - l-i
220 200 180 160 140 120 100
60
20
DBm ' 228 208 188 168 148 128 C BANK _ _ _.
- - - _ - DIFFERENTIAL BORON WORTH - __ . < _ % . . fff u r C_.
bb BOL - - - 1. 4.. - _ _1 _.
. _.
. _ __,.._., ___- -- ; _., _ _.. , .__..f..-_
- _ -.... _.. _ _..
. .... -_ _ _ _ _,_ .,...,_ _ _. _._. _ - _. _. _.. - .. '. _ _.._ w_ . ____. _. ' , ___a._ _,__.
....... 3_ _.,_.
.__.
--r-- '_ _.
._.
.. _., _ _. _ _ _.. _._= -- _w_.
-13 __ t _.._- ._..a.
.. .. . _... ... _ ... - .. . ~*, _ _..- _ - - ._.. -. .... _.
... _.. .._....... - - - - . -__.
_ _.. -"_ _ e**.,, _ . ~ _.. _ _ ,_ -. _, _ - *... ~ _ " . r,. -_."..;*~*[...,. -...- l__
- _
. .. ... _ _ . ....u.__.
-- :;-" T_ _ _.
. _ - t... t - _ t.. -- -~... tr. :..n i. : - - _ : t :: -t-...... h-u__. _. ~ *. _ - .t... -- -
a - - - - -12 ..-.- F.
.-_N,
. ._....._.___.. _.
_ _ _....._ _.
r, __ w.__T_...__....._._.r..._.-... -.., _.... _...,. _ . _ _. _ _.
._- . _ _ _.. ...._,... _ _ _ _.
___; . u.... __.._.. _ _ _. _. _ _.
..._t _...... ._ .._ ....%.._.%_ .L -_ _ r_.
-w __ __ _ _4_......_ u _.
r ... ._ . _. _ __. __.____-... _ ".... - - - - - - - -- C --- N-11 - - - - ' r----- o a . _ _ - __t. - __ _.: __ - .u::._x.. _.__ _ ; :-_ .- _ - -- ~ _. - , - C i C.
- -r :uun:p=: 't ~ - -10 _ _ ' - " _._ ' _ ', _.. _ -. ", _ _. "__. -- X _m.
- - . x - . _ _ _ . - _ - . _ . _ _ _ _ +-
- _:
. : +- - _g _ _ _. _ _ r_ . _ - -8 , , . , 300 400 500 550 , Core Average Temp.
(UF) 6 ace
7 EOL-16 _. _ _ .. _.. _ ___.
.., _.. _.. _., _ ___...._._.
._t--.,_..__.
. ._._._._..._......r_...._.__...._.
_ _ _ _ _ _ .
-_.-..r-._-.-.-:. .. ..t-..___-.....w.t.__.._.. . _......_..... - .,.., _.. _ _ _ -.. .... _. _ _ . ._ --. _..._. _t._.... -_ . _....... _. _ _.. _. . -... .
. . . .- ... . -- -__.___.__.._.:-__._..-.. -. _... _ _. + _ _. _ _ .. __.a___.
. ... _. . _...- - _ _ _ _. , _... _ -... _ - - - _ _.. -.1_-._-.-- .. _. - - - - -- + __1 )_ _ . .. _.... _.. _ _ _, _. t __ _ __. _. _.... ._.. _.... __.._....__ _ _.
_. _ __ _... _ _ _., _ _ _.. _ _ _ . _.... ___ _ __1._..... ._ .. - _..__.. ____; _.
_ _ _ _ _. _, .. ..,.. _ _.. _ __ _ _.. .. _ ... . _. _ - _ _ .- ... - _ _... _. _._.
. __ _ .._-t.._ . _.. _ _._.. _.... - .__.____:_.t.____._. _..... _. _.. _... _...... _ - .__t._...._....... . . - _- _l--._. r__.l - -- +.. . _..... _. _ _... _... ... . . ... -14 . _ _ _ _ . _.... . '-. . .. . ... . --- - - - - ._..t._.._..t... .. _.- - . . . -. ... .I. _ .t._ .. . .... ... . _ _ - . .__ . . . . . . . . ., -13 -.,. --.. - [ [ . .. . . . I . .. - - > - . - . i.
. . . .... . i i .... . - . .... , l c.- F.-- , , . _. -..___t'_._..'.. - l l , . - O E-a.
- - - - - ' - - I c. c.
- 12 - . _ ... . ...,.. . _. , ... .. _ _._.
. _. . ..... ..__t___.._.
._... i . - _... . .. _ ._ . . . ._.___.{._..r._.,- .. _- ... _ _......_ _.. . _ _, _ _.
_. _.._...___.. .. _, _.. -11 r -+ - - + -r" -- -
- + - 72 g. :-
-. . -- -. - ... _. ._r_.
,. _ ,. w. .._ ._... _.. _ _ _... _ _.. _..._ .. _.. . _ _ _... _ _. _ _ _ t__.
. . _- _ _ _. .. _. + _., . _... t... . _... _ .. _ , . _. _.. . _ _ m..... .. ... . ,. . _.. ... _... . _, ..._ .. _.. _. _. .. ,. ., .. ._ . ..___.... _. .__... _.. ._ ...... _. _ _.. ._ _.... _. ... ._ .. .... - . .., , _10 .. ._ . . .. .. . . . 30'O 4b0
55'O Core Averacje Temp.
(OF) .
. ' - REACTIVITY DUE TO XENON AFTER STARTUP - f w . . ft 9 a re d~. [ ~ _ ... . Percent Power =: _ : r n._; =r ---v =--. -- - _. _..t _t-r[=. - _n n u := I 12= rr u t- --- =t : r-,--+- - -. J.0 0 % _ _ _. _. _ _ _. _. _. _..a = t....... .. r -- - - .___. _ c t = +._; : "- ' - - - b ~" 4 ~ - " = = '# .._ M- " - g= =EL=:E ij ; M g 5 M i i -- " + ~!= t-- + - --- 4 -- , -: =1 80 % -3000 i F= = -$~~' d55E'3 Z.'._' $ ~5[ =:: N.
Ei:iF,$hr:M-Y D =F:g,==: =..p
- xr= 2 _q - - --
-- - r p.
60 % = :- <- -- -- - - .. . :t a-r -- - - .a....u =u.= '
2 . ; =C._ =E2
- '- '
.3._E. :~....;t. r. :. ::.._:ct - _r.
==:=_.,._..___" .... . _ .. . _.. _ ~- - -. . 7---}= _._.__a t =-{=-==--- --
===_. = =. _.
- =;eerr,=j _n. :
xr ;.:..u - 2=t ..__-t-- - : f:.. ~.. , =. =.. _.=.. y_ _:=.. =. =, _. ; - . -.. 1._.
_ -.- 40 % =- _.
. .. . . . .. ... __ :. # i' r Ei 3 - -"" 'i-iE.,... [ h../...I..........._..: -,,L - t ' : - . = 9 - r-:fr = him-5~i !95 //h[!!E NN-Fi5E.E._NsiS57N9 - . " i
- a
- te-1:rrun = r= __::.=
e 8 f..n t = y r rx a-- :.:=+!n r.n:h:2:= = - //;e-
==:---+-z._...._ u,__.
-
- _;=__ }:
.. --A
- _ t --n
_ _.
. ' .a - . - . .g.
.g.. g--la,c=m.2::: = = = _c,. _ :{ _2 - i...... ........ n- - - - - - - - - ;- =~.
- r :;.
- _ - - - + - - - - - - -2000 _ >- --
- nn:' ; =t;.
1. ntu...; c= ;,= ;.= t:::n= - ....... Il l.{(.n f.; ::'.:n :;: . fff.; fr.- J n=:. . - Un .. ::t nn :c =!u . 4-.~.*- M EL1;_'.ic.c ' - e ll2" =., :.n. :t-II;[I. :,.=, = :. u. t,...
- -*1 =..;.;. -.j.c._. =.,. m._-t--., g._._...y -- - '
---
- _
[g: , ,. .,. . ,,, _ _;. 7
~. . ,- -
- -
" 20 % " #!
- i=-F
- ffh=
j . - - I N Ei!5![/ f!-[il 2.5.c[u.:.'Mi-Ir lf 5E5I [[Ed N.i -5~-} i ~ p Lnun _ -r. c r.=, - t!.u" nf
== lt-f--}... h-t /
- : r : -f".:: t= Ei:r :
tunn=t =:=r ..:=,
- .:
. ; -.- : f in-f -f --- ff..-.. >
- -
H t.
- 2tm.=n ~J
".:: = , t~ - - T. l f.1 1.
. /. .. - : t..
- .$
< , 'Jr f. l.. ? A,[:.:
-:.gc .- ..___:- b 1.I f -
r ~~- db: i kb b -
t=:=g:...;= j ,:== nr p]=... j./e t... p=.:. q=.d2q:-l..;...f.,p-=--, - - t =.:-- --t=, . ' .-- . - ..... _.. p -W . i 10 % _... m.
, ..... s. _ _ , 4,.,.l'R /ti.B - - j.
. .. i.
.. t... _... x '
- i-li-t la;
' f. E F F f r t r I t- - - I-1000 - =
- //iE A i f. i i
I !! ! _i i ' l t ! !! 'i ' I 'llM /-a: ] - l - } '
. L::
- . /. -
. I-t.
, lf.,y=-:;t= '. ' r
! L.
l- . +- =ip.:lf-f := k-l ] y} =f: -
- .
, .j !. [;
- pj
[.3 3
p g;g.. . [ j j c[ { j.
- [./j:/ .
W-i t: i ++P . .J= a
. .
' . [. .+ :.i //.. !. I.
i.
.:. [ _ - ' . . .- j . y r r r . .
.
20
60
100 TH1E AFTER STARTUP (HRS.)
dD e d h
, tw s c0 Y Q%
( \\ E4 Ub a 4, i,.. NS . 3* O la% !
J
? ? \\19 O,a "A as -- - - " n
ka
+ e n
,
- n
_) t hi- > S V Q
% e c
- V uk
! a
wx a h u .9
x
N6%
e> u u <r-- N Wb a r - at h'C E D, k w O , =N D M
k n $ nE
kk a w a w + .f - q h:, w \\ Q )[ a~, ' ---C < sas sa s
- n
ha s b g% s ^
% < - q{, h ' a w . a S
g
p, - wk:
s hbw % N 60 w 4 Qg aw q,
- '
ka R s \\ N'2 b $ ^ h "" ,% d O ' " S*
- S ,, " % , !. % "w b S h
4 kD 7T lI % y 4% qt
. y
1 e u z - ., g g .
wh f % %; - - "w - -..
. _. . _ -. -- -. - ~ -- . .- -.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE
,
. THERMODYNAMICS \\ ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
i ANSWER 5.01 (2.50) Power defect: -1290 - (-650) = -640 pcm (fig 5.4) (0.50) , ' Boron worth: -10 pcm/ ppm (fig 5.6) (0.50) ~ Equilbrium Xenon: -3060 - (-2550) = -510 pcm (fig 5.8) (0.50) Required change in boron concentration: (0.50) [(-640 pcm) + (-510) pcm]/(-10 pcm/ ppm) = 115 ppm
From Dilution Nomograph (fig 5.1) " (0.50) approximate 15, # gallons 000
Is [If the candidate adds in factors for rod reactivity or a separate , temperature reactivity, deduct 0.40 for each] ' REFERENCE System Description No. 3, Figures 3-13 & 3-15 i Graph Book, Curves RV-1, RV-3B, RV-6, RV-7A & RCS-8 REQ-OPC-2, obj 2.7 _------___-_--____-_--_-__-_-_-_-_---_-_-_-_-_ --_-_-_-_-_-_-_-_---__ K&A 004-000-K5.20 / IF 3.7
ANSWER 5.02 (3.00) i (0.20) M is less negative and thus imparts less negative reactivity from l
the coolant heatup.
> (0.20) f b.
EOL DOPC is less negative and thus imparts less negative reactivity as(0.80)
the fuel temperature begins to increase.
, i (0.20) c.
BOL l MTC is less negative and thus imparts less negative reactivity from , (0.80)
the res heatup.
i ! l REFERENCE Reactor Theory Manual, Chapter 5, pgs 34 & 54 l-FSAE, Chapter 14, pgs 14.1-8, 14.1-22, & 14.2-20 l SG-REQ-OPC, obj 3.3.e --_-------------_------_-_-_-_-_---___-----____-_-_-_---_--------_---
! K&A 002-000-K5.14 / IF 4.2 000-001-EK1.06 / IF 4.2 i ! t I l _, -. - _ - -. - - _ _ _ - - _ - - _ _. - - _ -, -. - - . - . -. - - -.
5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS. AND PAGE
. i THERMODYNAMICS \\ ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 5.03 (2.50) c.
Turbine power - stays constant at 33% power (0.50) [ alternate acceptable answer: slightly reduced due to reduced Pstm] b.
Tavg (loop 31) due to no heat sink, goes to Th = 554 F + 18/2 = 563 F (0.50) Tavg (loop 34) c.
total reactor power has not changed; however, the power that #34 S/G must produce has increased by a factor of 1/3 to compensate for 31 loop Qrx = m Cp (Th - Tc) ^1/3 ---> -> v initial Delta T was 18 F, increase by 1/3==> final Delta T = 24 F final Tavg = Th - Delta T/2 = 563 - 24/2 = 551 F (0.50) d.
S/G Prensure (loop 31) saturation pressure for 563 F =1161 psia (or 1176 psig) (0.50) [also acceptable if assume that safeties will be lifting starting at 1065 psig) S/G Pressure (loop 34) c.
as with part c above, the appropriate Delta T will increase by 1/3 Qsg = U A (Tavg - Tstm) ^1/3 --> ( 1/3 ) ~ initial Delta T = Tavg - Tstm = 554 - 539 = 15 F final Tstm = Tavg - Delta T/2 = 551 - 15(4/3) = 531 F final Pstm==> saturation for 531 F = 893 psia (or 908 psig] (0.50) REFERENCE Thermodynamics Text, Chapter 8, pgs 36 & 42 REQ-OPC-2, obj 2.7
K&A 000-074-EA2.04 / IF 4.2 039-000-K3.05 / IF 3.7 - ._ . .. .-. . - - - -
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE
~ THERMODYNAMICS ., I ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 5.04 (2.40) c.
one step = 5/8"==> 8 pcm/ inch==> 5 pcm/ step (0.15) Beta Bar Effective = 0.00596 (0.15) Lambda Effective = 0.0767 sec-1 (0.15) Rho = (5 pcm/ step)(-20 steps) = -100 pcm (0.15) T = (Beta - Rho)/(Rho)(Lambda) (0.30) = (0.00596 - {-0.001})/(-0.001)(0.0767) (0.00696)/(-0.0000767) = = -90.74 (0.30) SUR = 26.06/T (0.30) = 26.06/(-90.74) = -0.287 dpm (0.30) SUR*t b.
P = Po10 (0.30) = 10E(-8)*10E({-0.287dpm}{1 min}) = 10E(-8)*(0.516) (0.30) = 5.16E(-9) amps REFERENCE Reactor Theory Manual, Chapter 4, pgs 8,18,25,30, & 33 -__-___-_____-__--__-_______-___- __-_______-__-______-__-______-____ K&A 001-000-A1.06 / IF 4.4 ANSWER 5.05 (1.50) Differentialboronworthwilldecrease(becomeI$NMPnegative) (0.50) because as moderator temperature increases, density decreases (0.50) decreasing the number of baron atoms available to absorb neutrons (0.50) REFERENCE Reactor Theory Manual, Chapter 7, pg 43 REQ-OPC-2, obj 2.5 _.---__-__-___-__ ____-_--__-__-__-________-__-____--_______- _-_- __ K&A 004-000-K5.06 / IF 3.0(RO), 3.3(SRO) - ___- _ _ _ _ _ __ ._ _ _ _ -
. _ -.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE
. . THERMODYNAMICS
'\\ ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
ANSWER 5.06 (3.10) Pre 10nt 02tuati0n 00ndition; in " tubOO.
(0.70) a.
b.
RCS pressure may result in tripping RCPs during SG tube rupture. (0.60) Sec. dependent RCS pressure is too hard to calculate.
(0.60) (0.30) c.
Available spray j (0.30) Good core cooling Cool down easier on RCPs than natural circulation (0.30) { Prevents head voiding (0.30) REFERENCE REQ-OPC-5, pgs 9, 11, 15 REQ-OPC-5, obj 5.4 & 5.6 _____________________________________________________________________ K&A 000-011-EK3.14 / IF 4.2 ) .C o d. s_ ' YM w p a u & d & 1s & & a u x = '= a x-;;4 p.s.,-) ' * * U M d-4 k V m h d r_ Jt4.4 _- u c e (v..s.s , .. . __ -. __ _ - - - - - --- - --..
_.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE
' . ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
. ANSWER 6.01 (1.00) (0.50) Detector output is higher than actual neutron level (0.50) Sourc; ner.;; aculd nutr-dernergize early W N SR % G REFERENCE System Description No. 13, pg 38 ONOP-NI-1, pg 4 REQ-OPC-4, obj 4.0 --__---___ ----- __---_----_____--___------___---------------------_.
K&A 015-000-K4.04 / IF 3.3 000-033-EA2.11 / IF 3.4 ANSWER 6.02 (1.50) 1.
Two or more rods not fully inserted after a plant shutdown 2.
Uncontrolled reactor cooldown below 540F with one rod stuck out 3.
Uncontrolled reactor cooldown below 500F 4.
Control bank position below the insertion limits(any three at 0.50 each) REFERENCE System Description No. 3.0, pg 54 _.--- _-____-_--_ _ --_.--_----__.-_-_-_-_____.-__-___---_---_--___- K&A 000-024-EK3.01 / IF 4.1(RO), 4.4(SRO) l . -.. -.. - _ - . - -.... _-._ . - __ . _ _ _ _. - - - -_ -. _.. _
o 6.
PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
. Y ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 6.03 (2.00) n.
Instrument air (0.25) (0.25) Fail shut b.
2260 psig (+/- 5 psig acceptable) (0.25) Minimize thermal stresses-(on the spray line & surge line) (0.25) c.
Help to equalize boron concentrations (0.25) Prevent RCS pressure from reaching the PORV setpoit$t (0.25) d.
following a step reduction of 10% (0.25) , assuming automatic rod control (0.25) REFERENCE System Description No. 1.4, pgs 13 & 14 REQ-OPC-4, pbj 4.1.b ___.---_---_---_-_--_____-__-_--_--_-_-____-_-_--___-_----- -----_-_- K&A 010-000-K6.03 / IF 3.6 000-065-EA2.08 / IF 3.3 ANSWER 6.04 (1.30) See attached drawing REFERENCE System Description No. 27.1, pgs 34-69 REQ-OPC-5, obj 5.7
___-_-_-__-_-____- _____.---_-___--_u-- _________--____--_-_ ------__ K&A 062-000-K4.06 /'IF 3.3
<.. . ... ____ -. . 6 _.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE
e . I' ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 6.05 (2.40) n.
MDAFWPs: 1.
loss of voltage to 480Vac bus 3A or 6A without SI 2.
lo-lo level any 1/4 steam generators 3.
auto trip of.',OT:: MFPr 4.
safety injectionELelf$re b.
TDAFWP: 1.
lo-lo level any 2/4 steam generators 2.
loss of normal power to 480vac bus 3A or 6A without SI (0.40 each) REFERENCE System Description No. 21, pgs 31-22, 34 , _____________________________________________________________________ K&A 061-000-K4.02 / IF 4.2 ANSWER 6.06 (2.50) n.
To ensure adequate trip reactivity (0.25) To minimize the reactivity effect of a rod ejection accident (0.25) To assure power distribution limits are met.
(0.25) b.
Due to the large value of positive reactivity inserted by MTC during the resulting uncontrolled RCS cooldown.
(1.00) (0.25) c.
EOL (0.25) Shutdown (0.25) 547 F REFERENCE Technical Specificacions, pg 3.10-15 o** CAF *** _____________________________________________________________________ K&A 001-000-K5.08 / IF 3.9 001-000-K5.04 / IF 4.3
l' (
_ _ _ _ _ _ f.
PLANT SYSTEMS DESIGN, CONTROL. AND INSTRUMENTATION PAGE
" . j ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
t . ANSWER 6.07 (2.00) (0.25) a.
OT Delta-T: decrease Indicated pressurizer pressure will be b$gow the nominal pressure which will insert a negative term into the setpoint (0.25) OF Delta-T: no chango (0.25) Not affected by cha'nges in pressure (0.25) (0.25) OT Delta-T: decrease b.
Delta flux, a normally negative term, is subtracted from the setpoint (minux x minus = positive); if lower detector fails, Delta flux becomes positive, which causes the setoint to decrease (0.25) (0.25) OP Delta-T: decrease (0.25) Discussion same as above REFERENCE System Description No. 28.0, pgs 21-28 REQ-OPC-4.4 ____--___-_-____________--__-_-___-_-_--_-_______-____-___-__-____-__ K&A 012-000-A1.01 / IF 3.4 ANSWER 6.08 (2.30) (0.40) c.
Dumps quick open (0.40) b.
Rods drive in (0.40) PZR spray valve full opens f C,f /9 /#t/ decrease.s /4.ae c s,4) ( 0, ;0 ; FWRV open ,M t c., d.
Reactor trips on low SG water level,e A4 hys +'r/8 J/# Is, '. (0.70) c.
REFERENCE REQ-OPC-3, pgs 7, 8 REQ-OPC-3, obj 3.0 ._-----_-_-_--_---_-_----------_---_-_-_----__-__-_-_-_------_---_---_-_-_ K&A 010-000-A1.06 / IF 3.2 041-020-K4.03 / IF 2.6 . .. - . _ _. ._.-
___ . . 7.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
% RADIOLOGICAL CONTROL ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
- ANSWER 7.01 (2.00) (0.25) n.
1.
Insert the rods 100 steps (0.25) 2.
Recalculate the ECP 3.
If a mathematical error is discovered, borate as necessary to insure rods will be above RIL, reinstitute rod withdrawal (0.25) 4.
If the ECP is correct, insert rods an additional 230 steps (0.25) (0.25) b.
1.
Insert the rods back to the ECP (0.25) 2.
Recalculate the ECP 3.
If a math error is discovered, reinstitute rod withdrawal (0.25) 4.
If the ECP is correct, insert the rods additional 230 steps (0.25) REFERENCE POP-1.2, pg 8
__-__---_--_--_-___-__-_____-__--_-_--_-__-----_--___----_-_-_---
K&A 001-010-A2.07 / IF 3.6(RO), 4.2 (SRO) ANSWER 7.02 (1.50) 2.
Core Cooling - Red (0.25 each, proper sequence required) 1.
Containment - Red 6.
Suberiticality - Orange 4.
Integrity - Orange 3.
Heat Sink - Yellow 5.
Inventory - Green REFERENCE F-0, pg 3 --_----_------------_---_------------_-_---------------------_---_--- K&A 000-074-System Generic 10 / IF 4.7 - - - - - .-. - _ _ - _ - _ .. 7m PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
' k RADIOLOGICAL CONTROL ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
- ANSWER 7.03 (2.25) (0.30 each) a.
1.
Verify reactor trip 2.
Verify turbine trip 3.
Check if RCS is isolated 4.
Verify AFW flow greater than 415 gpm 5.
Secure any liquid radwaste release in progress FRP's are written on the premise that at least one 480 vac bus is b.
(0.75) energized.
REFERENCE ECA-0.0. pgs 2-3 Step Description for ECA-0.0, pg 1 _____________________________________________________________________ K&A 062-000-K3.01 / IF 3.9 000-055-EK3.02 / IF 4.6 ANSWER 7.04 (1.50) (0.75) a.
To provide normal pressurizer spray (0.75) b.
Shift to cold leg recirculation mode REFERENCE FR-H.1, pg 4, 11 REQ-OPC-5, obj 5.8 _____________________________________________________________________ K&A 000-028-EK3.04 / IF 4.2 000-011-EK3.15 / IF 4.3
, - -
. 7-PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE
- RADIOLOGICAL CONTROL ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B.
S.
, ANSWER 7.05 (2.70) a.
1.
S/G Narrow range level (increasing in an uncontrolled manner) 2.
Blowdown radiation monitor (abnormal levels)f AttJ Secondary radiation (abnormal levels)cg623 3.
Condenser air ejector radiation monitor (abnormal levels)f4ZL7 4.
(0.30 each) b.
1.
Adjust atmospheric setpoint (to 1040 psig) 2.
Close MSIV 3.
Close MSIV bypass valve 4.
Close ASDV 5.
Isolate steam to AFW pump 6.
Isolate bleruen f /.v/w 7.
Isolate upstream steam traps (any 5 at 0.30 each) REFERENCE E-3, pgs 1, 4-5 _____________________________________________________________________ K&A 000-038-EA1.32 / IF 4.6(RO), 4.7(SRO) 000-038-EA2.02 / IF 4.5(RO), 4.8(SRO) ANSWER 7.06 (2.55) a.
(1) one second (assuming 50,000 R/Hr) (0.55) b.
Verify automatic actions have occured (any 5 at 0.40 each) Initiate containment ventilation isolation Evacuate containment building and FSB Close spent fuel pool isolation gate and apply station air to gate seal close fuel transfer tube gate valve Instruct HP to monitor radiation levels Initiate make-up to the RCS (for small leaks) Start the recirculation pump (for large leaks) REFERENCE ONOP-RP-3, pgs 1 & 3 _____________________________________________________________________ K&A 000-036-EKl.01 / IF 4.1 000-036-SG#11 / IF 4.3 - . - - _ _ _ .-- . __.
_.
- -
- - _ _ . 7.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE
{ RADIOLOGICAL CONTROL ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
, ANSWER 7.07 (2.50) a.
Deenergize load limit motors ( * * ' I) (0.40) Switch rods to manual to restore Tave (0.65) (0.50) 2:20t stear dur;r (0 40) I# (0.40) b.
Transfer to alternate control channel Transfer or chcck bcil;; fccd pump in :::u:1-(0.40) Transfer FWRV to manual (d. 60 ) (0 40) REFERENCE REQ-OPC-4, p 22, 23, 27 REQ-OPC-4, obj 4.0
K&A 015-000-K4.08 / IF 3.7 016-000-K3.12 / IF 3.6 l , _ -_ - _ _- - - - - - -.
- - _ . - _ . 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE
- ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 8.01 (1.60) All required non-automatic containment isolation valves are closed 1.
and blind flanged.
er ErIuipment door [ase properly closed.
2.
3.
Both doors in personal air locks are properly closed.
All automatic containment isolation valves are operable or closed, or 4.
isolated by a closed manual valve.
(0.40 each) REFERENCE Technical Specifications, section 1.10 _____________________________________________________________________ K&A 103-000-K1.02 / IF 4.1 ANSWER 8.02 (2.00) Rx subcritical with adequate SDM (IAW Figure 3.10-1) (0.50) a.
(0.50) 200 F < Tavg <= 555 F @ 0.25 m cQ;g,75) b.
Rx (thermal) power 'O.25) RCS pressure (0.257 gCS gmperature (0.125) c.
1.
100 F/Hr (0.125) 2.
200 F/Hr REFERENCE Technical Specifications, pgs 1-1, 2.1-1 & 3.1-4 _____________________________________________________________________ K&A 002-000-K5.18 / IF 3.6 002-020-SG#5 / IF 4.1 . . - _ -..- . _ _. _ _ _. - _. . _. ._.
.__ _ _ -
. 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE
- ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 8.03 (2.00) (0.66 each) a.
Locked open b.
Locked throttled c.
Locked open REFERENCE AP-10.1, pg 6 _____________________________________________________________________ K&A Plant Wide Generic #14 / IF 4.0 ANSWER 8.04 (2.10) a.
Radiation fields (ow 3 dp (0.30 each) Oxygen .Nm e (0.30 each) b.
Beta-Gamma (7to) Neutron (0.30 each) c.
Leave containment Rcchcrgc decimetcr ^4f.h HP REFERENCE SOP-CB-2, pgs 1-2 _____________________________________________________________________ K&A 103-000-A2.05 / IF 3.9 ANSWER 8.05 (1.50) (0.50) a.
1.
Two members of plant staff with knowledge of the affected area.
(0.50) b.
One of the above must be licensed as an SRO at IP3.
(0.50) REFERENCE AP-3, pg 6 __________________________________________________________-_-________ K&A - - / IF _._ .
. 8.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE
' ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. ANSWER 8.06 (3.00) hhours) (0.60 each) c.
Pg 3.4-2, para 3.4.B ( b.
Pg 3.3-4, para 3.3.A.4.b (24 hours) Pg 3.2-1, para 3.2.B.1 (not an LCO) c.
d.
Pg 3.7-2, para 3.7.B.1 (72 hours) c.
Pg 3.4-2, para 3.4.B (12 hours) [ NOTE: pg 3.7-2, para 3.7.G leads to the above paragraph] REFERENCE TS, pgs as listed in answer _____________________________________________________________________ K&A Plant Wide Generic #7 / IF 4.0 ANSWER 8.07 (1.00) (0.30) n.
six days (0.30) b.
Every other day (for six days) c.
Resident Manager or his deputy (0.40) REFERENCE TS Nmendment No. 64, pg 6-la REQ-TS-86.2 _____________________________________________________________________ K&A Plant Wide Generic #23 / IF 3.5 ANSWER 8.08 (1.80)
- a.
SRO log bookor 6' nr.M n 'N (0.30 each)
- b.
SS log, turnover sheet
- c.
3;;1;;r NRO log sheet, VCT level gra h
- d.
CRC icg, tu;.;v;; sh;;t-O g
- e.
Chemistry logs
- f.
Inrere computer read cut 32 4 Jpg mg gg
- CAF REFERENCE REQ-AP-21.4, obj 1.1.2
_____________________________________________________________________ i - - - -
- - .. e 8.
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE
- _
ANSWERS -- INDIAN POINT 3-86/06/05-NORRIS, B. S.
. K&A Plant-Wide Generic #26 / IF 3.6 ,
. - -,. -, - -..,.,. - -,. - ,--. - - -, - -
. , fiy u r e. cC/ f'f a ' ' S* A BORATION NOMOGRAPH FOR HOT 580
DILUTION NOMOGRAPH FOR HOT RCS 580 RCS 5*0-4000 - 3000 - - 1000 3000 - - 900 - 800 - 700 'O~ 2000 - - 600 io - - - 500 20 - 20 - - 400 no - t - 40 - 1000 - - 300 i _ Io 900 - _ l ro - 800 - ~ ' ~ - 200 2000 - 600 - 00 - 200 - - 150 100 - 400 _ '~ soo - ' ~ 300- - 100 200- '000 * ' yo 3" ~ l vo.: p - 60 2ngg _ ' - 50 ' " ~ , v' ' {' 1000 - ~ "O sooo
ll g " A' jgt* g.
- ) ,00 _ ' to 000 - / - 30 y , ~ 20 000 - '~* ~ 'e N / 'N-500 - - 20 ' , 2000 - 1000-so u00 - 2000 ,00 0u0 - ~ _ PPM BORON PPM BORON DILUTION WATER ~ '~ ~'O IN COOLANT DILUTION IN GALLONS PPM BORON BORIC ACID PPM s IN COOLANT VOLUME BORON IN GALLONS ADDITION .
__ SFueC 5. y' < . . l _ '_9ihCbb .b~iiih :--
- I5 M-5_5..
.5k-i- _.. =-- =-.
T ~ - y . _. ........ . _...
_.......
- .;-= := - __. t. 3 ; _.=- : :: =~:= :---
.. _.. . _.. _ - .. _ _ - ,_.
7_.._a -- - - g -- x: - %___ _ ::g_ g:j :1.=;=. - - O -,. _ - _ ,. - - + - - - - u _-..,;
- r-- + -
--i . -. -y --% - g =r.=.___1_ ;--=-=t__:l= :r
- --:v_ :j--... t =:=.-.. =n.r_ c.M 6. -
1-, .. = - -- - -r _ -_
- --
=--u- .t
- _:
!=..=._t=d -: .{-*-:- ' " "... _
- :...
-- -:.... s. = I~. - : ~ Dg-.-_ur ...: . - - -: -=._.' - '.. -.. J --- -200 E-- =: ....
u
== =.. : r..=_=.. n..n_, ...... . 3.
6_ =... _ _. t. =..,! r.. :.: n ..w.
_,....t_.=__.
. . , - * - ,r..._...:._': t.
-- -. _. _ - -... ; ._ _ _ _.
. ..
- 2_..,,_.: n: _ g_ ___: c
__r_. o . _ _ _... _ _ _ _. _....u_-. . . ____T_C J.
,.--p_' !.. _ _.. ..,. _..... - . ... _: - - - -- - ..==c___._.. - _ _... T . ;---w-wM. I;::_t=.i._=:::=_.j.__ '_ - :t.-t = = - - _ _. - ;;:=w .. :., ,_.
1- "p. 4 . :t- - - . ;-_ - Mx' ' % ;.:-, -.-.- - - =_ _,__.r ; -- n=+--'-*- --
-~ -- - -s e-400- "- " -- + -t h. m --w _t-2: - ___
-- - _ _m u- . ;;.-
. __wMN N..t _ _.
. _ _. _ _ -. -__ - __::- ., ... - . , , r -- .-_ --.
_ _.. - - _ _-u
_u_ w__ : -. -__.n..
- ._._.
-- -. ... - t,- --
-~ ,.. ^ _ - _.... _ -- .*=~ ._ -_"- ---# =- __.-_
-- m - - +,n ,-== g-600 -
- . t=y-v 1
- -
- = _ o - u &_ a.
_.... _ - _ +== t.
-... __:;;;.; ->, n-m _ - , -. __, _ _ _. ;_ : _-.- ; _
- '.%iN
~ * -A. : = . --- -.:: __ p - ... _. __ : : .. . :.=... ..: n - _ _ - - a._ _ _. - _ = v.t mn!"n=: =r : - - : t= e '. w.t
__. : = _. 3....._ t 1.d.. N:t ra4.g j;j
__ =; =.- - -
--.. ...
- -=: ...: .y- - . , - =..:t u r =; _.. N= _=: _ =: - .
a
':_ =n-:- = p =--=_. i = = t s g =::=n = --E=: -. a - 00 . Ei:E ' ;.N!'DL%ij;Ei .:l2;6~ij ca
- -
' Jij@ip p?Mi:si.i' fiJ.: . a: ' Y!!ENE. Ef-N M -d D M i IU.i.- M -
- i-EEEE'hI.I.
- _ g gji_ ;E EJ-'i
- 198?!:.:.:fi-ii.7.= E. g h M. N i..; ; :.i~;j
-
A:% c' fn.=.. . C- =... :q-> =\\:=.. v. %
- +
~v' ' n..=n :=.r = a - =:u - - - = r n :Ir: ='iY A j-1000 = = - r=~ " r: = rna =- ',.'. f FT 2: i'_m si. jE.3.:g: : :i:-ii_. Q !. \\ N N i -iF g ~ @ _. ~ l \\ \\ - \\iN \\ l e .i: [- l -- i \\.\\ \\\\ \\ - . . -
t - ' - t 1.
i i - \\\\ \\ \\ \\,: . 1500 PPM _ n00 ' i - -- i.; ! . i.
_- \\\\ \\ N '[1200 PPM _.
- i _ i.
i _.. I i . -47 p p . ' ' - =... _ _ 'i-S. _i.i.i =.._-i_k r..}'.. 93_i_t _:::ii... n i.n. Ir.
l . ^ 900 PPM - t.- . i _ifi;:{E ~i:-
- -! :MI:jii:tr_ ": u_ij!?el:
-l
- \\ N
. . . " ~- ~ '- " ~ "' ' 5:Y l k lk. -1400 h5:.E!h -ud- - -
- t.
- mi=1 (
- -t i i = l "! ; ++= k L i.
i \\i \\ , ~ .h 300 PPM %j. {' : ( P .l!. I - ( -[ : - t \\[
, I \\ ~-n:t- . ' - . b-I . .: i ' , ' ' ~ i . -1600 7 '_:!=:-r ' " j.. j.
[.. f l 2: -
- . - _ .O PP".
}.,.c i- : - ;- r__ . l ,
.. r.
_... -. . -.....
==. t-t _..~t.._.. -
_ ' _. ! .
- . ::- - l- . l.
[_..;- _.c : _- 7 -.- l J,-.f - l !-j
- .
- r i.
i
- it.;:
t:..E- -E - Ei-u n 4d
80 10) b
g (Percent of.ull Power) r Power .-- -
, . REACTIVITY DUE TO XENON AFTER STARTUP - - - t
. . Fi q a re C. [ ~ _ ... Percent Power --t-----4---- t n...{R.M_= 1 _ 2. =_T.._r f a a n:- - "-- '-'-*r._l_... _...k"=~*=-'T..- -
00, % . I Cr r
1 - f(c,, C
rr t" -*--
- .
.1 #
- :.:._.....;: :: = :.r _:._n ;
. _gnnn
==.:=.:_ nx:r: - -r-n c._. _ c _ - -- = t 80 % _ = :r: u.r-g_= = d. : f.- 5. -- - l-t-- + - -
. =: =. - -_
==-_==-. :=. ._=..r-.F,:. :=- h;. --:- :===22- ' - ~ ~ ~ ~- ' =: ~
> -::2 :-:=2'_ r. = - = _ _ _, _
- --e---! u nc. t.n::.-/.: ---
- T. -:- =:= 60 % e- -- - -..}I_._:/=E f__.r.;:r xrg- =j....__. 2=:--
t :___. x. 2 _: _ '-p:- =r c-- - m - - -- _ r ,oc,gT h_5-E ..._, _,__ _.
f._.._. _.E 9 E M E [ Y E;N S ~5 ~~}E~ E ~NE:i::A y .. ,p, g .. .._ +._- . _.. _ _ _. _ _ . 4_.
r_ - -
r._.__...,._.
.g.__..._...___..., ...pp.
, . _...._..
- ._na=2:$_:=_=.I'. 2;- --.. ___. i._ _ __ :
.. 40 %
'
--
- ---:=ftf ri;if_-
d[...fi Tr,':E - d... _...= -
- n c um.
, _ _.. Wmr~=.::-.F== zia __= = 4= = n/._.
... _ _ _ _... ..ia:..E_.-.. ....... _
- ---~--
r=_: I+ + - .=_g=n_:. =..t: = - _u:t- :/,fi.fn:c==f.tv
- r:- :. rm-. _.
.. :==_ 4 - -- =.:- - - t- - ... -- - - - - - - - - __..__.h...,E =t2 / :ri= J 7- - - - 2:!:r r- +--.!!=i:====-4 . __: - H:_' _: t: t -.rt = .:(: :==tr: j=;'._.
_ ... . _.. _. {u-r2:. uta--t-- j. }=.: - u t: n.
- - - - n 1;,. x - :-.: ; = tn---mm...-_.__-..
- =y=J=
-2000 - t= = =--- -_ r :== '=- =..t :. c_ = -:!:2*.(-. -O;L.-
- '
== _ : h.:g[p f._5p p=..~_ =- :.;!*.C12 --b=:. ~
- .. =--
% -1.U _ - I '
-- '. l .I r, ff . - - " - n t-- - - -. -~ E p... t : // ;[f :[i. - ~:.. ~.n..n=..,:_~.. '.i;=_..n=_;; =...+[ __ _ _-.n _n._ -_.' - - 22~ 20 % __ n _.2 U g , ,, r.
- .. , .c - ! _ '
- - . p I.
. 5 =: ~
- :
- 0*. .
- .
' ~~. U L* Ct! ~;.. ;= _
- _;".. _;=p:Q:
t= r - t===1.
. = {... /._+_---...=..- ..:.' f.
Un r.;
- f3 f '.
> .=_ ; : 44- .c_.
-
- f 1-
- - I: c-
... :;- -: ; t---; --t:- t. :n__j.. = r a y . . _.
c..- :-{. J. f:. .c: f.t =. _
,: m t.
~ '. r : n t_ ' y - ' t-....- _-t-. 2: ={- I' :2 :ri.:U: : r = 1 - =;~. C ' ' : !
L.3
- _
- 1 p
(.. _ 20.....;. - 71 " ~ --b. _..' O Z4 - IT.
--. J fi T,J r -! : -- t - --- -2 T ... _u. n..!. :.. g - _h..n. :. T. =. _ l:. ...:. n. _ I =..... g
- =
. _....... _ _.=. _.: g,.., _
- .
, g ..... .., -
,0 % .. _ . t._ . .. _ - - - _.._.__.I.
, _. _ , ' .
1 _ .. r __.
... . _.. . ... . n ..:__._...t I;i.E ; [.p:H= /.i '-- i~.....iE '-i - W '... i
ic
, .t. rc..:..' .: .. : E..: 1 ir :.. l:
.t .- f- :: l l -l-t*
- ' - ^ ' . . .l , - - m.
. .
. -1000 _.;_: ., /m.... !: :. . p.
._.-y.r:p.
h_,
-t t . -l " g....=[. I g.. , . t, i, ( . _ - - g - . .- . L - , . !:. fj [N/-li--/ ! ~! ! I - l t
= r i r i IM_ tziA 1.
i
i: .. . l- . .- f...:::: c.[7 [:. :rn {_;.:., - - . t.
(~ . . .. , F.
... _. - - - [. . -
- -
. .... i
c
- t=
e +
_ n ._v, ' i f.: n./ f v . . ' i ... j :'I - . I' ... - - .! ;.r:.
. , l'
..J..j,. _ - -- !' t- ..
- . , , f_. f.
- j . , ,
- I ': '
r
. l' ".:.. g r;..- .. , I h ! -
- . i:.2
' l~ f' l . . u -- t _.;n_ . ..p" g- - i i u.
.. > r . . I g g -
- -
0 - . .
20
60
100 TIME AFTER STARTUP (HRS.)
- _ , _, ._
A \\ jg . \\ % \\ + ck -
t e II sq 3o,I tg s . s kh
7b ac n e u' < x, ,a a n 'a k
EVK O s As u a% o . -
L h
" p
- 4" t
e . hi k t
e i k w
m N b % V E p([c.
> x p , m t( .
n %:
w s Ih,' ] o, c y jm + ' t s a$
- w N
N.)
uv % % gg <~ b s% a s i * q% a c s
s d O.
N y%d d di g + -
C s' W > z N+A C.
' , w td ' .J kw - W U{W ,% {
, M,O 3e % .t, g a= y%% - n w i I, k
-s w t 3r L
o
Z' .Es ub e - 3t O 8" qh q %a E ._.
-
TEST CROSS REFERENCE PAGE
. QUESTION VALUE REFERENCE ______ __________ ,________ 05.01 2.50 BSN0000153 05.02 3.00 BSN0000154 05.03 2.50 BSN0000156 05.04 2.40 BSN0000157 05.05 1.50 BSN0000187 05.06 3.10 BSN0000209 ______ 15.00 06.01 1.00 BSN0000149 06.02 1.50 BSN0000150 06.03 2.00 BSN0000151 06.04 1.30 BSN0000158 06.05 2.40 BSN0000170 06.06 2.50 BSN0000173 06.07 2.00 BSN0000196 06.08 2.30 BSN0000210 ______ 15.00 07.01 2.00 BSN0000161 07.02 1.50 BSN0000163 07.03 2.25 BSN0000167 07.04 1.50 BSN0000172 07.05 2.70 BSN0000199 07.06 2.55 BSN0000204 07.07 2.50 BSN0000211 ______ 15.00 08.01 1.60 BSN0000165 08.02 2.00 BSN0000192 08.03 2.00 BSN0000201 08.04 2.10 BSN0000202 08.05 1.50 BSN0000203 08.06 3.00 BSN0000205 08.07 1.00 BSN0000212 08.08 1.80 BSN0000213 ______ 15.00 ______ ______ 60.00 . -... . _ _. . -. . - -. , - - - __
.. .. -. -- -. - --.-. --.- . - - - ~ _ . - -. -. -.- _ - - - } . g Attachment 3 Facility Comments on R0 Written Examination & NRC Resolution Question Number Comment / Resolution ' O 1.01 Comment: by nomograph, 115 ppm delection is = 7500 gallons; see , Curve.
' Resolution: corrected answer key.
j 1.03 Comment: less negative not more negative.
Resolution: corrected answer key.
1.07.a Comment: Tripping at 32 F doesn't prevent sat.
It insures the pumps are tripped before sat. reached in tubes (incl.
inst error) so as to prevent add. mass loss when break uncovers. Uncovery can't occur till U-tubes drain, , which won't occur till U-tubes at saturation. This prevents possible exceeding PCT's for the limiting , SBLOCA.
. Resolution: answer key modified.
I 2.05.a(3) Comment: Trip of either not both M8FP's.
i Resolution: corrected answer key.
! 2.07 Comment: Student must include Iodine, but credit shouldn't be lost if he mentions DH for corrosion.
Resolution: accepted.
3.01.a Comment: you may block too early; no auto deenergize.
Resolution: corrected answer key.
I ~ 3.01.c Comment: Should accept other answers if student assumes all power lost.
I.e., Bis's tripping etc.
Resolution: accepted.
, i l i ,--~vr- ,---,w--,,,,--n-,, ,, -- .,,-wr,,-ma ,,-,n,,w---,----,,, -. - ,, ---nw-,.-,,,-- ,, - - - -, --e-me---m--n,,,me-- ,,---y
.c-,------e,,
,, -... -, - -,. -
- @
Attachment 3
Question Number Comment / Resolution 3.02 Comment: level will reset to 45% due to integral reset action.
Resolution; corrected answer key.
3.07 Comment: accept T.S. or actual valves Resolution: corrected answer key, but the answers must be consistent.
4.06 Comment: accept radiation monitoring designator or name (RIS, R19,R62).
Resolution: accepted.
4.07.a Comment: Resetting steam dumps a subsequent action not immediate.
Resolution: answer key corrected, points redistributed.
4.07.b Comment: MBFP always in manual so operator probably would change.
- i Resolution: answer key corrected, points redistribute \\q . g Attachment 4 Facility Comments on SR0 Written Examination & NRC Resolution Question Number Comment / Resolution 5.01 Comment: Assumption could be made that rate of increase is sufficient to not allow time for Xenon affect.
' Resolution: not incorporated, question stated equilibrium-to-equilibrium.
5.02.a Comment: peak clad temperature concern.
Resolution: not incorporated, question was stated with respect to amount of time at power.
, 5.02.b Comment: Beff is less, therefore, rate of increase is greater.
Resolution: will be considered in grading.
i 5.04 Comment: ask question in terms of plant literature, i.e.,
pcm/ step.
! Resolution: will be considered on future exams.
5.06 see R0 1.07 , ) 6.01 see R0 3.01.a 6.05 see R0 2.05.a(3) 6.08.d Comment: PORV's open & charging pump speed decreases.
Resolution: answer key modified.
7.05.a see R0 4.06 7.05.b Comment: isolate MFW.
Resolution: not incorporated; question was in reference to a specific procedure.
i i ) t .v.- .-v-y- . _ _,,.. . -, _ _ - _. - _. _, _.. -... - ... - - -. - - - - - . - - - - - -. ~. - - - > -. .. ... - - -. ~ - -
. . d Attachment 4
Question Number Comment / Resolution 7.07 see R0 4.07 8.01 Comment: closed or blind flange; equipment door not doors.
Resolution: answer key corrected.
8.02.b Comment: must assume flow.
Resolution: answer key modified.
8.04.a Comment: add - V.C. air sampled for radiological concerns.
Resolution: modified answer key.
8.04.b Comment: accept TLD for beta gamma.
Resolution: accepted.
8.04.c Comment: change recharge dosimeter to notify HP.
Resolution: accepted.
8.08.a Comment: add turnover sheet or status board c Comment: add log sheet d.
Comment: add personnel schedule f Comment: Delta I log or Reactor Engineer in Report Resolution: accepted. }}