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 44 & 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/df4 (@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 > !
30 86071s koj728CK05000206 V PDR l
. - -. - - - . - - - _ . - - _ _ -
= . ~. _ . . . - - - . .. _- -- .--- .
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 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 calculation Senior Reactor Operators demonstrated a lack of understanding of the potential problems associated with water hammer in the main feed line . 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 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 examination Individual weaknesses noted on the oral examinations had been previously discussed with the training departmen 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 i 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 The facility stated that they were very pleased with the way the orals were conducted and with the philosophy of " operationally oriented" question . 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: R0 Written Examination & Answer Key , SR0 Written Examination & Answer Key
- Facility Comments on R0 Written Examination & NRC Resolution Facility Comments on SR0 Written Examination & NRC Resolution ,
f
l
. _ . ._ - - . - _ . . . . . - _ - _ . , - -
~- -_
,
Athtch ment l JLa<t: of
.
a 6 b y &
.
U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR REQUALIFICATION EXAMINATION FACILITY: INDIAN POINT 3 REACTOR TYPE: PWR-WEC4 DATE ADMINISTERED: 86/06/05 EXAMINER: NORRIS, APPLICANT: Gbr - MF a#
,a INSTRUCTIONS TO CANDIDATE:
Read the attached instruction page carefull This examination replaces the current cycle facility administered requalification examinatio 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 start % of Category % of Candidate's Category Total Score Value Category Value 15.00 25.00 Principles of Nuclear Power Plant Operation, Thermodynamics, Heat Transfer and Fluid Flow 15.00 25.00 Plant Design Including Safety and Emergency Systems 15.00 25.00 Instruments and Control 15.00 25.00 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 ai CANDIDATE'S SIGNATURE
.
ES-201-2 .
* .
- NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penaltie . 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 cheatin . Use black ink or dark pencil only to facilitate legible reproduction . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each section of the answer shee . 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 shee . Number each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . 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 require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no . Partial credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION l AND 00 NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of i the examiner onl j 1 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 complete Examiner Standards 12 of 18
.. __ _ ._. _. . _ . .
.
ES-201-2
.
. 18. Wnen you complete your examination, you shall: Assemble your examination as follows:
(1) Exam questions on to (2) Exam aids - figures, tables, et (3) Answer pages including figures which are a part of the answe Turn in your copy of the examination and all pages used to answer the examination question Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the examination area, as defined by the examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke ( (
Examiner Standards 13 of 18
_ _ __ . . _ _ _ __ . _ .-_. _ _ PAGE 2
-
1.- PRINCIPLES OF BUCLr. Alt PO'"J11 PLAP2 OPER.ATIO * 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 xeno Initial conditions: equilibrium xenon, rods in manual, CBD at 220 steps, i boron concentration at 1200 pp 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 tri i
QUESTION 1.03 (1.50) l Explain how and why Differential Boron Worth will change with an increase j in moderator temperatur !
, QUESTION 1.04 (2.50) i List two physical requirements for natural circulation flo (0.50) , During natural circulation, explain how it is possible to form a bubble in the reactor vessel head when indications show that (1.00) the RCS is subcooled? ! 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 I (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****) l .
- - _ _ _ _ . _ . _ . _ . _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ . . . _ _ __
__ . - .
.
PRINCIPLES OF NUCLEAR POWE" PLANT OPERATION, PAGE 3
' 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 positio JUSTIFY YOUR ANSWE The startup is delayed until 8 hours after the tri (0.75) The steam dump pressure setpoint is increased to a value just below the Steam Generator PORV setpoin (0.75) Condenser vacuum is reduced by 4 inches of Mercur (0.75) All Steam Generator levels are rapidly raised as criticality is approache (0.75) QUESTION 1.06 (1.50) A motor operated centrifugal pump is operating at rated flow when the discharge valve is throttled in the shut directio State how the below parameters will change (increase, decrease, constant): Flow Discharge pressure Motor amps Net Positive Suction Head c Fle" dacr^a--e, dirck=";^ prerrura incr02rer, meter 1rpr incresce, tETH decrcccc Flce decr:2002, diccharge prercure increar^r, meter impe d-cr"?"e, NPO!! increase (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
... _ . - _ . . _ _ - . . - _ - -. . . _ _ __ . _ _ . _ - - - .
PAGE 4 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 Coolant Pumps (RCP) when subcooled margin drops below 32 F? (1.00) Describe why subcooling is used to determine RCP trip criteria instead of Reactor Coolant System (RCS) pressure or Secondary dependent RCS pressur (1.50)
(***** END OF CATEGORY 01 *****)
l
- - _ - - - - - - - _ _ _ - _ _ - - _ _ - - _ _ _ __ _ _ . _ _ _ _ _ _ _ _ __ . ._ , _ _ . , _ _ ._. _ _ _ _ __ . _ . ._ _ _ . . _ _ _ _
2 PAGE 5 2 PLANT DESIGN INCLUDING SAFrai AND EMERGENCY SYSTENS 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 Flowpath QUESTION 2.03 (3.00) If the Instrument Air (IA) pressure starts to decrease, what automatic actions should occur to maintain the pressure? (1.00) If pressure continues to drop, at what pressure must the plant be , ' tripped in accordance with ONOP-IA-17 (0.50) i On a complete loss of IA, how will the following valves fail: (1.50) Excess letdown hand control valve (HCV-123) Diesel generator service water flow control valves (FCV-1176/1176A) Main feedwater regulators (FCV-417/427/437/447) Atmospheric dump valves (PCV-1134/1135/1136/1137)
- Liquid waste release valve (RCV-018)
QUESTION 2.04 (1.50) At what pressure should the spray valves begin to open during power operations? (0.25) List two purposes for the bypass line around the spray valve (0.50) What is the basis for the combined capacity of the spray valves? (0.75) QUESTION 2.05 (2.40) List the conditions that will cause the Motor Driven Auxiliary Boiler Feedwater pumps to automatically star (1.60) List the conditions that will cause the Turbine Driven Auxiliary Boiler Feedwater pump to automatically star (0.80) i i
(***** CATEGORY 02 CONTINUED ON NEXT PAGE *****)
f ! ! t _ . . . - - -
- ._ - - - _ - -_ - _- .-_ - - _ _ - - _
- -.
.
PAGE 6
.
2 PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
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 of recirculation fans and containment spray pumps will maintain the containment temperature and pressure within limits. What are those three combinations? (1.50) 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 of each of the breakers for a normal at-power lineu (1.95) List eight different loads powered from Bus 5 (0.80)
(NOTE: distribution panels and duplicate components are not acceptable] ,
(***** END OF CATEGORY 02 *****) ._ ._ _ _ _ _ _ _
_. . _ . ._
- .- . - .- _ _ __
.
PAGE 7 3 INSTRUMENTS AND CONTROLS e . QUESTION 3.01 (2.25) What would be the significance of one Intermediate Range channel being undercompensated during a reactor startup? (1.00) 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 instrument prior to a reactor startup? (0.75) 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 Explain, in detail, HOW and detector for #31 S/G stic;(s at the 25% valu WHY this will affect #31 steam generator leve Assume no operator actio QUESTION 3.03 (1.50) When a Safety Injection signal is received, six automatic actions occur in addition to the illumination of the appropriate annunciator List 5 of the QUESTION 3.04 (2.50) What are three reasons for having Rod Insertion Limits? [0.75] With respect to the Rod Insertion Limits, "...the steamline break accident imposes the highest shutdown margin requirement."
Explain why this is a true statemen [1.00) Considering each of the following sets of conditions separately, 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 (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
-_ _
.
., '
3 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) Steam Generator Blowdown Monitor (R-19) (1.00) 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 Syste a. Load is reduced to 50% fast enough to cause a Tavg/ Tref deviation of i 15 F (0.70) b. A turbine trip occur (0.75) QUESTION 3.07 (3.00) Provide the setpoint and basis for each of the following reactor trips:
- High Pressurizer Pressure (2.00) Low Pressurizer Pressure Low Low Steam Generator Level l High Flux, Power Range (low) What would be the effect (increase, decrease, no effect) on the Overtemperature Delta T setpoint if Pressurizer pressure was 2200 psig?
l i WHY? (1.00)
i
(***** END OF CATEGORY 03 *****) . _ . . _ . _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ . . _ . . _ . _ _ _ _ _ _ . _ _ _ . _ _ _ . . _ . . _ __
-- .
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 9
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 steps BELOW the Estimated Critical Rod Position calculation? (1.00) What if the rods are 100 steps ABOVE the Estimated Critical Rod Position and the reactor is not yet critical? (1.00) , QUESTION 4.02 (2.00) l 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 Exchanger must not exceed 145 (0.50) 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 15 psi (0.50) Pressurizer spray shall not be used if the difference between the pressurizer and the spray fluid is greater than 350 (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 *****)
. . _ _ _ . - - _ . - .... . . . _ . - _ - - _ _ _ _ - _ _ , . _ _ - -- - - - - _ _ . _ - - .
_
,
, '
^
4 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 10
*
RADIOLOGICAL CONTROL "' 4 -
,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 neutro 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 limit? Show all wor ,. ;, (1.25) During a declared emergency, this individual volunteers to enter a high radiation area and perform work necessary to prevent further effluent releas In accordance with IP-1027, Emergency Personnel Exposure, what is his maximum allowed.whole body exposure? (0.75)
- '
(0.75)
~ Whose authorization is needed in part' QUESTION 4.05 (1.55)
Answer the following in accordance with IP3 Teclinical Specifications: Define HOT SHUTDOW (0.60)
~ Which THREE parameters must you observe in order to ve'ify r that Reactor Core Safety Limits are being adhered to? (0.75) Provide the following temperature limitation value . Pressurizer heatup rat . Pressurizer cooldown rat (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 steam generator with a tube ruptur (1.20) State 5 actions that must be performed to isolate a steam generator with a tube ruptur (1.50)
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
-_-________-_______ ___________________ _ _____________________________ __ _ .
4 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 11
'
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 failure Assume a power level of 100%. Power Range channel A upper detector fails high 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
-
o BORATION NOMOGRAPH FOR HOT 580 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-
- * - 300 1000 -
d[ 900 - _ co - ,, To - 800 -
~
~
'00
, 2000 - - 200 600 -
500 - 200 - - 150 i ' o- 400 -
'~ -
Soo - 300 - - 100
'
1500 - - 90 200 - . 2 - 80 200 - - 70 300 - to - 2000 , - 60
- 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 / w
.
:-
600- ;_
-
-.---
: m
-
-;
-
.
:
590_--- ,,
:..
.=:,."
r .
^V 580 - .:
-
:
-
u "
:
"
T .--
:
...
-: .-.
7' -- 570_ .g';'
:
*
.- .
-
,
le , 1 - - _
,- ,
.: + ,
-
-
( F)
-
1 4 - -
: , . /
_ : -. . - - - . . 560 : e .
-
: ,- -.;
-
,
--
, . _
.x w
,
, .
'
: -- .
p'- nn .L
:1 ,I; .m .,n m -= 4-2_ .- --,-
' k Ig i
'
i ,z ' ',_:-' .
--
-_ :
-:--
= 4_. _ .. -
-,:
. _
-/ ,- ...
m- - ~ .
- r-.
. . . .
- , . ... _ . -
.
_M L _ 5a0 -
- - -
~r -.
m
._:
_
'.-_ ___'
_- ; T. -(- _
-+- f ,:L 1
, .- _ .-- _-- _. = :{'p, -- __
__
,
~~--
,
,-i:.w.;-_... . .
-
-
530 ad 10 ,. _ ob ad 6b O - Reactor Power ( "o )
._ ..___
v -
.
e - Ap c e I. y
.
U 7 : ..*.- ; n:.. .
...r_
'
: 2: .. . n_ . = . *~
T . - /.:;=. - ~..1--* * l
. . .; t- . _..;:::: .: ~T- .~~.:* = t- -
_ . . . . _ . . .
.*t--- _ _ _ . . _ .
-
' _. .._:. . . . . . . . .
.:=- - =- - -=.
u _5=-- - ._1=--_ _ . . . _ . . , _ _ .,::-- - -- - - _
- T . . _ _
__ ==. . . lE -..- - - - - - - O s-- -- -- -
. . . _
1__ = : f=~._2,
=
._=_ =:==: . ._; -- ::::_ ._. ;- . .__
=. 2.:2= .=r.:c:
:=-: = c- -
. , _-
.4:
.. _ . . _ _ . .- ,_
_n_: - M h . .o g ._ . . .. . . . . _g --- j:. E- .:p- r -=_nt-. ___ . i_-l' g - g, ...5t :7
.
~-g= .=,. ;;. :._ J. e . ., - [ . ; -
:n- t
-: . r :_ = " . .
:
l~
~
m
.' . u t. ::. [- . :
-
-
%
--
_t:.- - - -
:
-200 -- r . I ---
. . = _ ..: '.~="'.' :=t
; _ :_;. . =r : =_ : =
- .
-
=
4=:2_ :::._: .:;- :=_ . . .=: -+ _ :[. :-r r r: - _ _ . . . _ . v4=_.:n..u_ :
-
. . : =:-
--
: :=yu: u._ f = = = =__ ;.=. . . ::_:=_=_ _1=.. .__
.
- . . .
- .. M. s,..z= . = =- =-- 3,: .
_ _ . . _ =:_
.
.
-
. _ . . .=..C__-
.
. _ . _ . . _ . - . .
-
1t .. . _ =:_)'- V _T.=_..._..... =. _.: :=. .== . . .
.. - .
.. 1=I.= r'O.. ; :L -
- g . X - ._.: {, = -- *+ :-= =-i:=. ' 2=" :=
-400
.; _O -
-- -x W = w=* - _ - -
-
_ _ _
. _ - _ _ __-- ~'
1 .-
+D '* ! ~
^
_
- i'g - .
.- _
wm 5 . . _.;
- - . -;-. = = - . %W ._._ r.-
gr _
.
- _ . . g _ __ __
3+ -- "_- r==
-
- ___-.
U -600 -"_u 3 ._..r :rt :(-g .. . p: "
. :=- _- _ _ = _ .t
. .....:.
*- -t- .:.tn Ug_..y_3 ._v._ _ i ---+ n z_ _
~
- -;. _ . ._ = . . - ._ , . _
. . _ . . _ _= =
.
= m_ %_,x .
- r=_.&._
_ s ==..= .
._ . . . _ . . . -
. . .;. . -$
. .r. .:.- 'I. :
.-
_
"
9~ .g. .
.. -
0 .
. _ . . . ==. . . . + -' -r. .r. . : . r. .:. ._:.{ . .
-~ ..
.
~. . .
DJ .
--=
g, D3 - _ . . -_' - " '* * "' 'g.... *~"~2
. . . . .. .x :
*; ~ W._ # : N:.\;4* {-
c_
"'~ T-
;
{--*/'"=
a -800 7 == Mii=e.i:irtri m"'iA w w !Ni;=h > '. '= . '65! . s + g.=gcl3.p;c r=g s m N w .:i c.:t=-pg g
. m p de m s it- % t e s =tr X = 4 s%W viv."
.
" ==Ft TE==tMt-~.!! =!i sfM! \@i== R R =-- j5'+ : .
d _1000 g g p,e p : i. 1 g m =pi= .jx x ir. x x x i -i> ; p i: - t . t- : p !. . i \ \ - Nix: N t
'
!
' -
i i
!
\:\ \\ \
\\ NN N 1500 PPM
. .
: i : i
_1,00 t .
-
11 i i
> r \ \. \
i
}: t l. ' l :- !' i k i\ N 1200 PPM ., l'p.. g-I- _.:.........n ..:j: .;p. j.. p .
g \\.g
\N 3 900 PPM .
ji~_t." E- F - l~ :y= - g_pl.j} -.ii '. l:a.:[.7:4 l-
;
-1400 :. . I . ='-. a-
-
a y: .
. \\ j\\ t y-=: .r =::
r-- .- : .i : ' -
-
lifi--Q.l : ~l
-
i ; j'", idE h '. ; \l \ !
: l
- -
..[!; [- f-f -
"
i , Ni.\ 300 PPM
-
[- u[ . t :: t- .
'
I
}. :
.
'
I - I- = i:
'
I'
-1600
-
l ! l i\
. ;=: 9--- h.E { . . [. - [ i. y:.
. i- i
-
3 0 PPtt
.
, i , I I
. ic 1 F:* t r'
F _ . ;. - :- .- i , ,
'; l"_ .P t. n
$. _ IL . .
t :
-*
-)-- t- .
. .
(_
v- .. j . , g-
:
:: .._.g.i . J ::. .{.
-
-
. 3.:
-
;_u[
.. . t . .
l' ,
-1800 ,... :_
-
,
.
,
,
60 80 100 0 20 40 Power (Percent of Full Power)
-
.
. . .
.
'AVAILABLE CONTROL BANK WORTH AS A FUNCTION OF BANK POSITION
-
. .
- Squ er /. 5 v
. _ - . .
.-
+---
,
.
-
-. -
s'--- .
--
-
._
__ _
-3500 ~
z=% s ._ -t - -__ _ . - _ _
. - - .
-y
_
.._...x E.b_ ; Ir
- : -
_..-
.
L __
;
-
,.
- . w_
-:=_y__ _ _ -.
. _ . i- \.;
._;.__ __ g
_ _ _ . ..
.A
_
- + - -
___ ~ _ - - + - 1
~
~ 2--~ -+- -
-
::-
-3000 - - - __ _"; _ , --
,
O t- . ._ __?"c_- 611 '. . _ . - _ . - g F.- ~~_ m :---F- %,
' ~ .
* - - - t- _ _
-
=: __ p_.%___.-. , _--. ;
:::
-
--- - pY_,,._q .
e . -. a: O
- - --
-
Z~- t t' = - '- - - - NY i r---,--
-
t
; --
.'
, 4- \' -- - ;
t \ . . ~ . +~"-- b -t----*-.
.
. ._.s._5_.._ \ i---
>4 l> _ . -*'- = .
2-- - - g y
~-
. _j_ ._ + \-
t..~ . _ _ . _ .
^
-
IT_E --" D I~"~2=~ _ L.__..__- - - - .* -*--{ _- .\ i g .__ r .
^
_ .
. .. . g5
._ R - r- ,
-2500 +=N'C -*='- Y~ .. : "D
^
.:1,
-
D"'*** -
-I e--- ,- - t :.p:t._.;_.,,
. . _ an h...::n:::r= t:=" 2
: r T i. :V*\==t --.L_ =i-
- - t
-*
_;
-- ----- "
l -' ' _4-----* _
-. : +t-= --* +E- :;-- ; r 1 ~ . .' :: : { . . *.:-.- -r .. . -
te u
..
.t. = - +-- -t -
. -_ . . . . . . . + - _
.L...;.-..I f . . .: .L. : s. .e.; .-l- -- _ - ~ -
. _ . . _ . .
~ !. J. . -,
-
-*
~ _ _ - _ - ,-,,_=,_.t__;. ._ - " *-' . : . . . . . . h. . . . . .!.
.
. - -
..
--
'
.-- _
-=
a _. . : : _ -.=
y ~E=- =2.. v. _ l .== - 2.: .r*:E ==_ - .:- - (2::2-
- r . ==' E-b==t:-y . = ._
2. :C .: ;r L
- -- - W --..
,._
-~*--1
._-- t : t .u r . - ._ --:- :::t__~.:- _-- - ' ' N c=
' .. - .
l : - t = :=_ ;- - Lsg.- _; l __._- p___._ +
. _ . . .. . . . 2 _-.. :;_; _ h,.:.. _- _.. - -- ; .-
~~~ if.s9.iff E:d51!E.I'~E.- - * - - -i!= . .- T i EE~2t-5'.N-_
"
i_ . _ . . . . _ _ - _ .
-
_ _ . . .
. - . . _ . .._ _ -
. . . - -
-- - .
= =_ . =_ E. -. =. i =.. . - =
---, :--=..=_..r..~._. =_. u_ _--=.__~._-t-______t
- .
.
. _ .
. - . . , - . . - ._
. ;-__
-
y-.--. _ , . -. - . - _ . l - *-
:--- - _.i._ Ef. :t--; : =..E-- :
= : _..- - --
L. 22: -
--
l
. _ ;:_: 7.:_.. m.,,-
-
. . . . . .-.
- _: . ...:.; .- C- .r t;
.{,
_ . . . . l ' - -. _ . _ . _ _ _ . . _ .. .Z: _;y-.
- - . -e--
,
;-- .; t - ;- -- +_ : ! . r .
..---t
.
l -- -- . . . .
-2000~ -2 !- :- {- ._ _ _ t_-._ _n= ji. ;i- y..? i_ - .j. -j=. i.-E. =- d' . #-iE- . . .
- ---- F - b--! n I. ME _- i: . E 2_ . . . . . .
i. r- = . _ . . . _
= = -=1.1. . .= >
- . . .. :.. srr. . E. - E: . t -
=t== .; = 1c_ - - [ '
i -
-
'
D BANK ' ' 160 140 120 100 80 60 40 20 0 220 200 180 228 208 188 168 148 128 C BANK
i
* DIFFERENTIAL BORON WORTH
__ .
-
.
q u , c BOL-1 r - _ _ _ . _ _ .. _
. _ _
_
. _ .__ ,_ __ . , . . .-;._._....__ .4 .. _
.., . ___.5_ 1 - : n*; = 4 . -. - - " - - -
, _ . . . ....+ _., . ;-
.. - - - -
, ,
-13 ; x
_ . _ . .. _i -
.
- >
.._ . . . _ . .
__ a- 1 . . .. . 3Ni:
~ ~
~
~_~.Y ^ i[E. 5E, .- .'_-.5._'Eihi2 2
: . . . r_ _ ._ . . _ - _
~
_ .f-I.~~~. _
. _
_ 1 . . . . . . .
- -
. _ . _ _,
h- - 4 _. - .; . t7 : - +- . . [ . . . . . t: = . .':;::: ._.+._ '- --
:: :-1 - ..
-
-12 =- F : N
-
. _ . t: : :- :-
'
.. -- - m
:- - +--+ -- n --2 :..
r- - p . _ . _ .... .
-1: r T _.* 2 r --!.m - F_...._ _ ,
_4 -. _ ___5. . .._u_ _: .-t..._ q-- r--- -%
-+
- :_- ....g --.
,
. . .
- ._ _ _ ~ ._ _ _ . , .
= _.5 . . _ _ _ . _ __ :_ . __ . _ , _ _ .~ - . ... . . _
~ . ....=._.,2_. g-g 4 .
_N
. ,_._ _
a a -+ - r- uu =,_ : "
--+- - N-10- -
, _ _ __ , '_... _ . _ _ . . s
.
,__ _____ _.-
_.: +__-
. g ,
~
-9 --
= ,
._
___ ,
-8 ,
,
, i .
400 500 550 300 Core Average Temp. ( F) 6 are 7 f. 7-16 EOL
. _ _ _ _ .
..__.. .... .
. _.___ .._. . . _ _ _ _ , _
: _._._,
,_
. _ _.. . ._ ___ _.. .__ .___
r: __
..
_... _2 . . __ .. _..,_.g._. _ ..... ... . .__... '
, ,_.h u- .W--4
._.._...___ . _ _... . ... _. . __ .. . . .... . . - - - . ,_
. . _ . ,
_ _ _ _}5_ _ . ,-.t'.: = :--~ _: __._..__.7.__.:.___.._....
..t= :7= ~ -
_.T.._ :.._---__. ___ .
-
-
._ ... - _ . - . _ . . _ _
, _ . _ *-- _ _ _ _ , _ _ _
. - _
_ __= : . . . _ _ . _ _
. . _ . -
. . _ _ _ .-.t........
_ . _ _ . ..._._..t_._...__.,_..p=.__,...r_-,___: .. _ . _ . . .. . _ , _ _ _ . . _ _ . _ , . . . . .____._ . n- _ __... p_ _. n m_ m__-*_-- -"-.. _
-14 _- - - - - - - - 1 _ .-- +g.--- * . p=-t: = = _ ru-- - - g _ . . . ... : . ,c . 7.:._
-- - - - - - - - - - - - - - --
-
- g
' -- - ;- . .. , . , . T- .-- { j
: { - l _. .. ! . _ , _ .
_ .
'l,
.:.. {' . , ,
I'
.
I-13l i 1 r- " - -
: ;.
:.-' !
-
'
i
-
i
. . . , .
I ' f---
,
e e .._... l D E . .
. .
' ' - 12 )' _:;-R---.-V-.-** t
- - -
- !
.
- I _ ; r_ - ...-- - . .
'{ : :
_ .;_ : _rt- =m; '-' :... ;_ . . t
. . _ . ._ . ,. .. ... _.,._... _ . .
g .......
- , _ _ , . .-.
~ :: ,. . .
. . ... .
.
. _ _ .u
' --
---
._11 _ _ _ , _ __ _ _ _
. .
. . _ - . ..__.,_-t~.-'..._6...
__ p -t--'-+-=t......'.:--._ . ;_- .J. !, . { ' - -
- :- I - .
_
..
. . . . __:- '_. _-
. . . . . .
. ., _ . ". --' . . .
.. ,
,
.
.
. . t. .
..
. . . U. ~ ':~
. .T_
. . _" . ..
- * ' - ' '
' ~. ~ f -'~. - -~ ! ; . ,
-
l . _;
.
'-
... _:1--' -, ,
,
,
,- - , . .
,,
-
30'O 4b0 500 55'O Core Averac}e Tem ( F)
.
.
'
- -
REACTIVITY DUE TO XENON AFTER STARTUP
* .
.
.
F~9 ace /Y _ . . . . n. - - r - - - -- - - r :=- Percent Power
:__-:= -- .u . . c r_m-::n: =-=: . : = _: n . _:- - -
'
: .u_n --
- - --&:n _a_==1
- - x : =:=_ : = 2-r n u.r . . - " *: 10(,) %
.g. _ .:. . =._ . .r: --
*
_ 4__ .
. _ . . . . . . . . .
_ _ -
- i T =E "i EM 4-fi"-d"-E'535_T5-=-%f;TT y: ~ ;W " -3000 -" ' =1 80 %
E J ,6 M= Ek.=ti;=edEMPE T_T-3E=1 60 %
=_.=_
__ _ _ _ . . _ E-l= _..,, i -
=7,_ .__; -F.- ._,.p. 4. .. ..-._...._.__.__ . u .- . :t. =
~ 1 -- - -- ---
u . . t -t .=
= = = * : a -- 1 -r n-
: C -- h- y:_.w =
.
= = *:t._="u = - =t
=......_t
; - -- u
-
T.Cf - "._ :7- : .- e:"!t .
._+_:_
. - - _ . . .
=::---}. .-: .
: _. .
._=.-
-
:= #2L r-s 3,=.E=
. . . .
=r7..p- a.-
.
.-
_= -+- --
--
-?
,-
-
... ., ... . ...... _. 4 _=y _ __
' -- - J - _+. 21__, & _
_-
._ .
; .. t -
- - - - - - - -
40 %
- - - -- --
.2 _ A ..; ,. g .._
-
__.t..__i_ 3_ .._;_._ c-
. f'f' : f.:- - c- 3p
,_
. .. . .. ;_
:j_g; . . r-.
.
--
n --
- - .. r: .: : c--- r. : i -i =: ::: rnd. =m = : ur . . ___
.: t. .=:-- :=: __j
=n=t- : n =F * "
-r- ' -"-
~~
l:-- : r,1-e
"I# .:=n . h;=;"a===.r
=n-mn --- +
- /f_M nirr / h- . r:. .[' . :*h. r
. . _
: t:_- :r
.
t
=:- fn r e . . t =:
II. 7 -/-
: t - d - .:._.... : :t nt= j .._ _.l-.. ...# _.__ _ ! :..i. .==
c:tu t //
-- --'-
ff=;/ r : ut: ..
:
:__E...
=:t:._ t_:::L .u = :t=r.::::. ri='
. . . :-= - =
-
...a.= =:;; .. :: := u!-- -=-l =
- :: : int:n =t n
2- -2000 _=:u-: --_ L: -
. r- -- = 2== - !~C nn = ;. -.j. m---- =- -:
, - :: u :--:::-
.
= t :t: ; -
! :1- a r..t= =. ~h- = _. _:.4 . ...: n= :
P ::. t : o ;g :: - -:t.-
. .
T:[I{i[iif, ~.:~ji~-II -F d22'-t- =2 5 20 % 2iiij9.f ff f_..[ .Ii ~
>+ '
!'liN!!I5U5I fi~[W~. : f
--h.I:.h fibchu : _.:.
'
El NEhM-M -Ei=iE::==- UI=lij=F tiMisisE5l
$
o gr ..=_:_:. !. c ..
:
{ 2:-
, .t u:
.-;- -
_d: ' c - : :-+h
-
- + - - -
'.
1 --.t.=ra :1... .*
< . . .
5: E hi[5i .d5N:=-E=j- i'd:EiE.EF_MTd -l. -9=f:li'~'i ~~ 3 S! . t =: r p . . . u - tl .t
-
-
:: :.4,. . .:: at
.
v- . _ ;. .4 .
- :;:.::..-L". .- t---
. . .
--- :- =-. . .-1 : =u:
. .
; 10 % . .
u .,...j- _.: .Et . ._ . . p ' W
.
. . . _ . . .
. . -- -- -1
:Eii Jft]=ii ft rd - . - - . -
' '
-1000 mp r 7 . i i 11 .
l-
.
-
i t I[!
,
_i
. . '
! i
! i
. . . k/i=[i
.
_. ..
-
!
, .
;
,
! -
.
!.
.
'
! ! .
ll.9 xL:- . l : .
.- N-355< I
: :. [: 1 I .f.~
.i
!
.
>
}.. j ,
,
.. . .j:.- .g:. p..... .
) %:. lL. , .
.
.
f ^ . - ,c_;, . . :t u. . . 3
:
.J [',;[",_i:l41
.
l .
[ ._ r
-
[p/ : l .
.
j .; c f . .
[ j L -I ' . ub _ ~ - l
[[:[i [ l
'
Iit _
. A!
'
- -
. !
I : I _
- i f i- ;. !-
.f l
-
- c 0 i 20 40 60 80 100
TI!4E AFTER STARTUP (HRS.)
l l
.. -
'
$ O BASIC CHEMICAL AND VOLUME CONTROL SYSTEM fma re 2./
'
.e $ 4 uPt E STSites BSIDOWN
* IUNI 4EIDOWN Val %E SO'lefitOL'v at yg 04 eCf 9
*
"I* "O LE100Wes eBOt a luwe - l l - (=)--
8 . .
-, -m#1
. .e. .. . c SI "M n w . .8.e.......
. .
seO88 Af Of M Mu 9 CeleDN-lll-C
' 1-. COio tee aoOP s or eOnarmer
seOmunt CMamomeG R OOP 3 e MA)- lO t 1 y(e nE ACf 080 COOL ANS f.Tre
: ..esPi. .. . ...
Cen s iee I Il _11 attisese4Tf CMannesG LOOP 39 *-( )
,,g o, , gy
,
g,, 0 's'eu*r* Q T> R esof afG CouPosef NI WE es t 3 m , ausee
*
g scs as / OOe see ME ADE A J AU3 SPAAV 10 Penf S$LNetTIN d 'f- SS 100 Wee ME ~( MgAND* * ek .-
- F I WCW *** 8'8 h a. .c.e, .-.-- y>- .
E I;'
--- .e r<,er []-
.
. . . .
. C.,.,
. . o.e . . 1-O'",,"','",",W.i.. .. l<- >1>
--
O ' 7 s
-.
s,.s (. s .",. toi R+
.e
'T-g. -4
'
- "
,e : a e -
=:: e.e.n.. .,~. ..i n--
.,
~~-
(,, _ ,,, (x )
e...
^
9.. Is e{ f' ,
.o -- -.
p ,p . eg ,> x_ .re .-
- -
-tb Cone e.see. es ,
*" "m,
,,0, -:e i.r,. '*ir>--
. - -
_ Weannee omose
e O
\
d l . N ' cl
.
N w t e
.'% 2 t-
1 OD
.= ,, e% MO - M 4
'4? ;
-
, C i st
** k
. O NA g, _ w
- ,Q a u it h $ %
S 't 4 1 'e
%n % L * %
Q 9
3 ,. t ' h C-7e e 36 ' k %% l 3 s% v i
&
at 3 .V '
> %'n ? ~
m> n&A-og
< ;
u 6 ha
~s } i m
kE e*u h* 9 a N E9 k I * e n'
- ,
w kw c,
+ '
R sm n - Sk
- < ---C 3t kS NN % % s %sa k %
s w - n f 4, 't * q
%
C o ,F s
ya: h sc _ nbs pQt
,
am b 4,
-
kE
- ' s *
5 w ws QD $ e4w ,%
,A '*
gs , o
"
i
f .
'e ,k 't .- ,* %C b D 4 f$ k '
%e xe s qt u % *
u O
,
u 3t
- -
="-
Sh nh 3 w wa _-- -_
.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 12 , THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW t ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. S.
. ANSWER 1.01 (2.50) Power defect: -1290 - (.650) = -640 pcm
- (fig 1.4) (0.50)
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) approximate 15,000 gallons (0.50) 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 _____________________________________________________________________ K&A 004-000-K5.20 / IF 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) T = 55 sec 79.36 sec (0.50) ______ = 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 __ . - _ _ . .-- -.
. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 13
, 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 _____________________________________________________________________ K&A 004-000-K5.06 / IF 3.0(RO), 3.3(SRO) ANSWER 1.04 (2.50) Difference in density (pressure) (0.25) Heat source lower than heat sink (0.25) 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 saturatio (0.33) The temperature indicators would not reflect this local saturated conditio (0.33) 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 K5.17 / IF A2.03 / IF _ -- _ - - - - .- _ . _ _ - _ - -
.
PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 14
' THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW L ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. S.
. ANSWER 1.05 (3.00) ACP higher than ECP (0.25) Xenon will increase adding negative reactivity (0.50) 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) Same (0.25) Condenser vacuum will have no effect on RCS reactivity (0.50) 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 A4.03 / IF ANSWER 1.06 (1.50) decrease (0.375 each) increase decrease increase REFERENCE Thermodynamics Text, Chapter 6, pgs 27-32 _____________________________________________________________________ K&A Components: Centrifugal Pumps / IF ~ , I
!
,
, - , - - - . . - - - - , , - - - - , . - - - - - - - - , - - . -
- - - - - , - -
, - - - - . - - - -
-
1 PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 15
THERMODYNAMICS, HEAT TRANSFER AND FLUID FLOW
'.
ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. S.
. ANSWER 1.07 (2.50) Prevent catuation conditiene in U tube (1.00) RCS pressure may result in tripping RCPs during SG tube rupture. (0.75) Sec. dependent RCS pressure is too hard to calculat (0.75)
'
REFERENCE REQ-OPC-5, pgs 9, 11, 15 REQ-OPC-5, obj 5.4 & _____________________________________________________________________ K&A 000-011- EK3.14 / IF .
\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.)
>
. . PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 16 ' * ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. .
ANSWER 2.01 (1.50) Two or more rods not fully inserted after a plant shutdown Uncontrolled reactor cooldown below 540F with one rod stuck out Uncontrolled reactor cooldown below 500F 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 EA1.16 / IF K6.09 / IF ANSWER 2.03 (3.00) Standby Instrument Air Compressor starts (95 psig) (0.50) Service Air System valve opens (90 psig) (0.50) psig (0.50) . Fail closed (0.30 each) Fail open Fail closed Fail closed Fail closed REFERENCE ONOP-IA-1, pgs 1-3 _____________________________________________________________________ K&A 000-065-EA2.06 / IF K3.02 / IF 3.4 i t l l l
-- .. . _ . ._. _ - . - - . . - _ -.
. . - - - _ _ - . .
- -.
.
-
. PLANT DESIGN INCL 3JDING SAFETY AND EMERGENCY SYSTEMS PAGE 17
'
b ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. S.
. ANSWER 2.04 (1.50) psig (+/- 5 psig acceptable) (0.25) Minimize thermal stresses (on the spray line & surge line) (0.25) Help to equalize boron concentrations (0.25) 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. _____________________________________________________________________ K&A 010-000-K6.03 / IF 3.2(RO), 3.6(SRO) ANSWER 2.05 (2.40) MDAFWPs: loss of voltage to 480vac bus 3A or 6A without SI lo-lo level any 1/4 steam generators auto trip of BO9H- MFPs safety injection t e', M r TDAFWP: lo-lo level any 2/4 steam generators 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 l ANSWER 2.06 (1.00) Within 2 minutes from the time CC water is los (1.00) l
REFERENCE ONOP-CC-1, pg 2 _____________________________________________________________________ K&A 003-000-K1.12 / IF K3.01 / IF . _ - - _ . - -- . . _ _ - _ . . - . .. - - - _ _ , . -__ . ~
. . PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 18 L ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. .
ANSWER 2.07 (1.75) . all containment recirculation fans operating (0.50) both containment spray pumps operating (0.50) three fans and one CS pump operating (0.50) 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 K4.04 / IF ANSWER 2.08 (2.75) See attached drawing (1.95) 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 K4.06 / IF 2.9 =
-svw-, --- ,- w-, -- w w y w
_ . INSTRUMENTS AND CONTROL S PAGE 19
- ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. ,
l . ANSWER 3.01 (2.25) 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~ &~& Simultaneous operation of both "IR Permissive Defeat" pushbuttons to reactivate the SR (0.50) " 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 trickle curren (0.45) REFERENCE System Description No. 13, pg 38 ONOP-NI-1, pg 4 _____________________________________________________________________ K&A 015-000-K4.04 / IF EA2.11 / IF ANSWER 3.02 (2.30) As power increases, steam pressure decreases (0.35) 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 higher than actual steam flow (0.40)
The summing network for flow will send a signal to the total controller to (0.40) open the feed regulating valv 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(0.40) flow 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 _____________________________________________________________________ K&A 035-010-A2.03 / IF _ _ . . _ - _ _ __- . . - . _ _ _ .
.
.-. _ _ _ - - . _ .
PAGE 20 3 INSTRUMENTS AND CONTROLS
.
b ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. . ANSWER 3.03 (1.50) Reactor trip (any 5 at 0.30 each) . Feedwater isolation Turbine trip Phase A isolation Control room ventilation isolation Safeguards sequence REFERENCE System Description No. 10.0, pg 16 _____________________________________________________________________ K&A 013-000-K4.xx / IF ~4.0 , ANSWER 3.04 (2.50) 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 me (0.25) Due to the large value of positive reactivity inserted by MTC during the resulting uncontrolled RCS cooldow (1.00) EOL (0.25) Shutdown (0.25) 547 F (0.25) REFERENCE Technical Specifications, pg 3.10-15
*** CAF ***
_____________________________________________________________________ K&A 001-000-K5.08 / IF K5.04 / IF 4.3
- - . , - . - - _ . . . - _ - - _ - . _ _ _ _ . . _ . - . _ . . . . _ _ - - _ . -. _.__. - _ . - .,m. _ , _ _ _ . _ . _ _ . _ _.. _ _ _ _ _ _ ._ . . - - - .
.
PAGE 21
.
3 INSTRUMENTS AND CONTROLS k ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. ANSWER 3.05 (2.00) purpose - primary to secondary leak detection (0.40) 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) purpose - detection of a failure of an integrity boundary (0.40) protection - isolation of containment ventilation (0.40) detector - G-M tube (0.20) REFERENCE System Description No. 12.0, pgs 16, 22, 29, 31, 32 ____________________________-______-______-__________________________ K&A 068-000-A4.04 / IF K4.01 / IF EK3.17 / IF ANSWER 3.06 (1.45) hi setpoint valves blow open (0.35) 6 hi-hi valves modulated open (0.35) all 12 steam dumps open (0.35) to bring Tavg to No-Load (547F) (0.40) REFERENCE System Description No. 18.1, pgs 8-9 REQ-OPC-3, obj __-_-_-_-----_--_-_-___--_-_---_--_-_---_-_----___-_-_-_-__-_-_--__-_ K&A 041-020-K4.18 / IF l l l
__ _. __ __ __ , _ _ , __
.
PAGE 22 INSTRUMENTS AND CONTROLS .
* ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. S.
. ANSWER 3.07 (3.00) . 2385 psig(T:A s .23A5psy /.e/***/) (0.50) Protection against overpressure (0.50) psig(%4.) o r /120 /ty fu 43 (0.50) Void formation and excessive QNB (0.50) % NR (7: 4.) ee /f"% N8 (uA O (0.50) Loss of heat s hk with a small Wstm/Wfeed mismatch (0.50) % (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 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 _____________________________________________________________________ K&A 012-000-K4.02 / IF . PAGE 23 PROCEDUDER - NORMAL. ABNORMAL. EMERGENCY AND
*
RADIOLOGICAL CONTROL
=
ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. . ANSWER 4.01 (2.00) . Insert the rods 100 steps (0.25) Recalculate the ECP (0.25) If a mathematical error is discovered, borate as necessary to ,
'
insure rods will be above RIL, reinstitute rod withdrawal (0.25) If the ECP is correct, insert rods an additional 230 steps (0.25) . Insert the rods back to the ECP (0.25) Recalculate the ECP (0.25) If a math error is discovered, reinstitute rod withdrawal (0.25) 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) . prevent channeling of the demineralizers (0.25) design flow of the NRHX (0.25) NPSH of the charging pumps (0.50) thermal shock of the pressurizer (0.50) ! l REFERENCE l SOP-CVCS-2, pgs 1-2 _____________________________________________________________________ K&A 004-000-K4.03 / IF K5.09 / IF _ _ _ _ _ _ _ _ _ _ _
.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 24
~
RADIOLOGICAL CONTROL
, -86/06/05-NORRIS, B. ANSWERS -- INDIAN POINT 3 .
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 ANSWER 4.04 (2.75) (N-18) = 50 rem (0.25) Total lifetime to date = 48 + 1 = 49 rem (0.25) Total lifetime available = 50 - 49 = 1 rem (0.25) Total this quarter available = 3 - 1 = 2 rem 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 =if52 (0.50) min factor for neutron not used] quality rem whole body one time exposure (0.75) Emergency Director (0.75) ' REFERENCE 10 CFR 20 IP-1027, pg 1 _____________________________________________________________________ K&A Plant Wide Generic #15 / IF i l
!
l i 't l
- _ , .__,- -.
__ _ _ _ _ _ _ __
.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 25 4-
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) 200 F < Tavg <= 555 F (0.30) Rx (thermal) power (0.25) RCS pressure (0.25) RCS temperature (0.25) . 100 F/Hr (0.10) F/Hr (0.10) REFERENCE Technical Specifications, pgs 1-1, 2.1-1 & 3.1-4 _____________________________________________________________________ K&A 002-000-K5.18 / IF SG#5 / IF ANSWER 4.06 (2.70) . S/G Narrow range level (increasing in an uncontrolled manner) Blowdown radiation monitor (abnormal levels)C A/f] Secondary radiation (abnormal levels)ffggt] Condenser air ejector radiation monitor (abnormal levels)LA/()
(0.30 each) . Adjust atmospheric setpoint (to 1040 psig) Close MSIV Close MSIV bypass valve Close ASDV ump Isolate Isolatesteam ticcacdn to AFW k l.wp/m n 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) _ _ .__ _ _. .
.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 26 RADIOLOGICAL CONTROL s ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. . ANSWER 4.07 (3.00) Deenergize load limit motors (a. 75' cac4) (0.40) Switch rods to manual to restore Tave (0.70) P.eret rtear durpr '0.40) 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 _____________________________________________________________________ K&A 015-000-K4.08 / IF K3.12 / IF 3.4 t
--- , _ . _ _ _ _
.
, o fg a e e- /%
R y u r f. / 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 -
~
1000 - - 300
- $2 eo - 900 - ,
70 - 800 - 2000 - - 200 500 - 200 - ,
'00 - 400 - '~ -
Soo - 300 - - 100
'
1500 - - 90 200 - - 2 - 80 200 - - 70 soo - - 60 to - 2000 -
~
5000 - ./ 4
/76 5/f ) 100 -
- 30
\
7 /_ N [i - 20 000 - _/ j - 500- - 20
/ i 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 5-55.E715i - 'I : r-5EE='_!~iiE;..d '~~- . : 5E--NSi- _ . . ._.,__ _ _ , _ . . . . . . . . . _ _ _ _ . . , .
-
.. . _ .
- - . _ - - ==
__ . _ . .
:
= ;; ==. . . E. . . _ . . . -=. _ g=---- :t=_-
_ ,
, ,,
__ _ , _ . _
- e-- .._ -
- --- - -_- - + - - -
_..__ =.; . = ~- . ===. :: 0-e-
-
_ .,- :- -
- -
-
- --
_-- t,,-- t. 2= .
-
- -
..___;
. _-__
-
= __._ ::- :_=. .
_ 4 , _ _ - _ __g_ _ _ 6 r_ . _ : n .--=
._ _ g _=: f _2 = -:r r -- - :- : =: ===: -r2w- = : .2=. .
6 :t - .
- -
:-_c: ;t . r t -- . :- -
..
r"1~i-: + 5. .II:EZ
'
.'. %_ - I: 7
--2. !r -
c -- 2Ein ~-! = 1- -
-200--; _- - - - m
-- -+
=__ N =_4.;._:__E_. _.. .i . 2 .: r. -- l. _f, . .c.i. =.r _l.-_ i . ..___n_=.?.. .: :.E. .-E_E..T. __ r .
.. ..
.. r .
.,_ _ _ . .
. _ . _
,
, , . .
:-.:.
,
...,.... - . , _ . . . : : _ .: : =_ . .
_. ; y __ _- -s- ;~ =e :.:_ . _ . :
==:r . :. ;-
-- ..
--- . _ _
_.:t =w_m .:t_:c::n.__ . .a r.t. =:!= . = : ==:t .r= == :;; - 2ng__ _ __ .
=t rs .. . _ a
----
-
g- --
.;:
L-2- 1- w: - K. N__r+=~ --
-
e_-
-400 -'
-
.
'-'
w 7*-;
._ '.g%_. . j_r ~
.--
.,_-
_ .
----YEW', .,_ ., . .__1 -: " i --
kNN'% . _ .
+- - :r -
.
_ ___
--
g - _._ __ _ . .._._,___ .. '3 -~
-600 _-___--
-
:;g',~[\.. ,-- *
.j__. . . _ . _ _ . ._ -* --
. m =_= r =.._:_= g__
q. - ~ , U . . . ,
> .- -(3p .. --
t =_=-.t. n.~ -w_ w -
- -.. _ ,.____ ,__~ .
-
._. _: _: __
.; :;._..; . -- _3 :,Nge ,g--,-+ -
2tr g - :_- ' - E* =_=.;._ : .
{ I..r.. .- ..;...:.
._ . ._]
. . _ _
.:
U . . . -
===
_ .
:. . . .t.:_ __p_ :
. .
Q_ .b_ . _.... _... _p.. . . . . .. .._.._..._; .
...
.
W g
=. _ . . + - -=_ -t. ;- . .
,_ ; , ..
.
;; .7
_ _ _ . . . . _.__._- g .. __ "~ ~~ ~ y ~T = "; 2" # ~ C" a -800 . ' [1: i-fd
?:55: r5!i;U.r=l #I [js-f:i.EEliE2 N5MLM! E +iEtE=i;:. :i:"iff'#HEEs M:ii'NN!N9 i i:: 'i=-55 ci -
k"
=g siga; = :s.== i..aei:= agggN.N j .; ! ;i .:i j _1000 -=_ . imE :====!=Miirgs!-w=2:RW iau=.:-
j 7 p . : _=m:g g p.x x x i -ri $ g i . p .p- j- ;_ . ;-- jn:y ,- l \}. :y i p
! . !
' -
i i N:\ \\ N : _u00 : ! I i i
!
\\ \ \ N, 1500 PPM
,
i I i
,
- -
.
i \\ N. N .~ ~
: .
: l - I
-
.
t- \\ \ \,: /1200 PPM '-
-/JPC f- ~'
, = . . . {: !Eil)'2-il;: - :E'.$;f!! . =j . {-
_
-
l \\-(^ 900 PPM f r_;[:' :E -i: _ i=- ;j_j; i}-2121 .u:ll l % ~ \\ j
.
_ i-1400 --t ..
. ::
e n3.. . . ! p * - . :Lu
:L- ::): =
' ' . . s
' .
- . :
~
- -[ - : .{Ij' iE --p - 2: : ei \b
,
N-300 PPM
- -
.
*
:: .
.
! \
' -'
i
- 1600 l: l k
[. ...u:
=rj:_l.. l. - :
[:_ -Zi , 'l l
: .O PPM
:_.- r i! i. ! tj_,- , j t
;. :3. _
. . - -
: .
; :- *
_- -
-
- , , , _ .
'
;: - l '. . I; . I f i f. '
~
4- i
,
= ; *~' ..-- . . - .p.. . j .
j ;
--r ..p _
.;__l'- .
:
'.
-1800 7- ,
,
60 80 10) 0 20 40 , r,7-o o Power (Percent of Full Power) _. . __
. ' - -
REACTIVITY DUE TO XENON AFTER STARTUP
. .
.
.
/ W /-r / f
_ ..
.= r:::::== :_. ..: : =:- --- :=r -
- -- - -- - - - - Percent Power
:_ . _ ; 2-
=: =:=q: =t . . : 2 :_= _ ::m r. 2 = r_ _ . ___.__- - ~ ~
100 % _gg 7- :. : =.t. .
' ";4-3000
- ' - - - '
-
' = ~ ~ ; H - - ~ ' ~ = = '~2 =1
-". _: .=y"E=fg f ;._;.4=__- -:i;: :t t
-
_ = = r 7- t: ..t "=1- -- 80 %
.. .. . . _ __ .
_ . .
=-.t -
=;=- - --,=
=
=:: : T :.;=z .. ..= .=.:;=A+ ; ' =r.= ,e- 4- .- : :. .._=_ i=...==- : . _3.._. = __ __..==
=y - $u:~-.q:-.t=- = 2:-.=- .z = = = ;- _:=== 60 %
a= r
. . -
:=---..
:.a... x =1.= =R
-
-
-- -- .
&- 5 =*.-~= -?:Wf,_ ' ...
1EEI-~$~'.~.. a_ . , . _ _.,-hfEQ .. . , . _ . . -. . . . ......n..... .. w _ _ 79 7, _ _ __...._..._..y,. . g__u.......__ . . . . _ . , _ _ _ - . .
-=-:-- - p=:
-
== a t. - __c -+ . . a__ .. . _ . _ . .
- =-g::y-: ==:: .:..-= =
. ._. .
-
==:= .:= .= ..
40 % zij.2.[~c -[M[i%liiR-Mr - _
.a :-1- :-:---d==i-fi- :4
.**
-
-
9.~=4=i/,/Mii ,. .., a ... _ p . 7 '. .
-Wni"=..Esms?".. ._ .
. . . _ . . . . _-
== -:, r -+ -~ .
,
..
-.
_: i=_In == - /f_ fu ,t: f :ti_m Ei: HE1.E E- r 2 . . _ x_
._ .....,. ..,.
. . .7...-
1_; "
-
,
=c= = t=2 = :.:- t= =.
- --: . }......... _=' : 2 :.._a-~-- - - - - - - - - - - - -._r--
=:- :. ---
. . . . ' . _j '
-
-2000 : -
= = t= .. .=-: =ul=; =:==- : . = r;=
:_:c.l.///,.f..=
-
-
a- - - -- =_u;
= =; .
. .::
= I=
= =. a:: . ==== =n =-t _-:
_..n-
- --
--s ~ ~ - --
3 .g
-
- ~~-
u :
.-
- :y ln; c ;f
-
. r.j --- ~ m- =;}=;:1= :- - 5. - l, :=g :. g c, .-
l 4':* _-b 225 20 %
:. dye..! // /_./ .i[' :E)~%i if iy_l=id =i" - -- .
>.
.
. f[ ~i~
5 . !-f2;b;;=.d f: I i fb .
$ E=:Ei T/MFP=6- .jf f. / 1 ; /. . ..
s#-' -MW!Eir
.
j~ . ;- t- -- ' -' t;T NEMisiEl
*
-*- - t :. L = Q
' : 3. . ; :.;
U . =. ;._ ,. f, J. f. . ! .. ri /.! ^. : 'J:*
-
i .' - g .
=;n ;: : J.=. : =: _;
.:L .:: E f. fc . ::/:=
'
M / g: ::--
(% =n- ff:f; fi:: -!.. : .. . . . .d. I: C. = :: .= f" .c. ; .- - - -
..
. . , . . . . . . _ -~.~..._~-.-'..-_{.
. . .
...
-i'.L- kg f . . h-s. i'_=$. . . 2i!!: . i k.: 2 !:- 'l . _L 'ii'i '.Pfi: _.- ' t:dI2-[ 2!!2. .
-
_
-
.4 < 10 %
:: v er: . e. :. n - :- - z .
w
:. . .
. a_ . _ -;
=: } ft l=: ft=t-- - = - := '
....;.. I I]
'
~'
.
! l-
-
-1000 If- :.i. ;
Lx_ f'. /i'.- I
. i . '. . ..e - . . . -
I ;. }. t ,
;_
'
'
_ h ,
. ',
., .
.
'
]/[y/=../
,, '
I !
;
.
-
l
'
! -
! .
' REEM I ; i: .t -!. ! d
.
=
p/gt= j
-
j :- -!i. = t :=l y i. [ :
-g :=l: ;;
9 /39 A:
. .
' .
ggg= h : j i= !
. .
!.
; .
i . ; .. a-.p _ 4 .. . p/A' I: I :
-
l i l~ - l'-i'-
/
i
'
i
.
I- i-
-
t+
-
:
-
!-
-
0 - 0 2b 40 60 80 100 , 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 i o ,.,.,a.,,,.
c . . .. _ r.-
].._...... .=.
' r.f.,=,=,,
.
/
'
~ ,l ~t I r(V -*a='''
-
-.
.o ua ca.aa ([, .c:o. coo..= ,a I co o u..% .
_ . n-.= c.y. ,o , oo, =Tn 3%f .. ,,,, _,,,,,,,,_0 ** g
=>
'
_ _ _ , L 2 l .. n , . n. J3 ) ./,L'J'. _ c@_ {""'.'."". J - = :: = g
, ,,
.=>
,
e r , g .
...
- . ,-T "
. i = [ l -.,
.v.".".."'.".;"~
-
lC E... . . , , ., a
)(1 9j "
u. ..
'_ _w .a susuu
===.} b gj , ,
,
y I .o g . m
_ m.a*
:.".: / - +>o,, g I .,_ n~3 ",", (t>M --
.. . i W, .y ( ,
D(>f
.. .
r l c4 . l
;,;
--
W ..
.
,
I d - 0,, "3.rf. ,!," . 2 i
'" ,
::- -
ylr..irr-
- . . .
y _ . _ . n s l w/fu,c 4===
% b b
% 4 s' k
'
-
a ,t c a OD e,
. '
n ,, ~ D h. Xh g
* M
\
ye W 3e a[
'-
se g1 e og
'is, R M C i
y s%n a
.
L As* h s 4 9
%
p,1j
, -
g k
;s t %
y 4wx &s N dt
." '
> Ns
*> NC A
*nk '(
s t . O S 4
%
qk u "1s 4 de , e 4 49 $ s v N 4 4
+k S
,__ a la > 4 u,e _A ~
'
v S NN
%; 4 y
kS qS LA N s s ,
q,3 a n w s e se W +
= , ut W g
, ,,e t
4, a= N
, '
s , ,. 4 $ 5h.' 3_4 ,. @
,
=
-.:-*=
%
'e ' b
.t, ga s
,e w 11}
At k i
,'8 5 g *
7di M 8h (h
- F-U 8t n cc
*
**
wh 3 sa % __
.
PAGE 1
* TEST CROSS REFERENCE
. 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, APPLICANT: M nbfY - FF
.- g INSTRUCTIONS TO CANDIDATE:
Read the attached instruction page carefull This examination replaces the current cycle facility administered requalification examinatio 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 start % of Category % of Candidate's Category Total Score Value Category Value 15.00 25.00 Theory of Nuclear Power Plant Operation, Fluids, and Thermodynamics 15.00 25.00 Plant Systems Design, Control, and Instrumentation 25.00 Procedures - Normal, 15.00 Abnormal, Emergency, and Radiological Control 15.00 25.00 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 ai CANDIDATE'S SIGNATURE
. - - _ . _ -_ . - _ _ _
_ - _ _ _ _ _ - . _ - - . - _ . _ - - - - - _ _ _ - . . - -
, ES-201-2
,
NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply: Cheating on the examination means an automatic denial of your application and could result in more severe penalties, cc 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 cheatin . Use black ink or dark pencil only to f acilitate legible reproduction . Print your name in the blank provided on the cover sheet of the examinatio . Fill in the date on the cover sheet of the examination (if necessary). Use only the paper provided for answer . Print your name in the upper right-hand corner of the first page of each section of the answer shee . 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 shee . Number each answer as to category and number, for example, 1.4, . Skip at least three lines between each answe . Separate answer sheets from pad and place finished answer sheets face down on your desk or tabl . Use abbreviations only if they are commonly used in facility literatur . 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 require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no ! 1 Partial credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of , the examiner onl l 1 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 complete l I Examiner Standards 12 of 18
- . _ _ _ .
.
{, ES-201-2
,
e 18. When you complete your examination, you shall: Assemble your examination as follows:
(1) Exam questions on to '
N2)-Examaids-figures,' tables,et (3) Answer pages including figures which are a part of the answe Turn in your copy of the examination and all pages used to answer the examination question Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the examination area, as defined by the examine If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoke (
(
Examiner Standards 13 of 18
~
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 2 ' 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 xeno Initial conditions: equilibrium xenon, rods in manual, CBD at 220 steps, boron concentration at 1200 pp Use Figures 5.1 through 5.8 (attached).
State any assumptions and show all wor 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 ANSWE Total loss of coolant flow at power (1.00) Rod withdrawal accident from low in the Source Range prior to any significant reactor coolant temperature increas (1.00) Loss of load from 100% to 50% (1.00) QUESTION 5.03 (2.50) The plant is operating at 33% power when the 31 S/G Main Steam Isolation Valve fails shu Using the below initial conditions, calculate the new steady state values for the listed parameter Assume no operator action, rod control system in manual, all other control systems in automatic, and no reactor trip and no SI actuatio State all assumptions and show all wor Initial conditions: Tavg = 554 F Tstm = 539 F Core Delta T = 18 F Turbine power Tavg (loop 31) Tavg (loop 34) S/G pressure (loop 31) S/G pressure (loop 34) l (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) _ - _. -- _
* 'T4EORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 3 ERMODYNAMICS 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 step 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 stops? (1.80) 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 temperatur QUESTION 5.06 (3.10) What condition is prevented from occurring by tripping Reactor Coolant Pumps (RCP) when subcooled margin drops below 32 F? (0.70) Describe why subcooling is used to determine RCP trip criteria instead of Reactor Coolant System (RCS) pressure or Secondary dependent RCS pressur (1.20) State FOUR advantages of continued RCP operation during a Steam Generator tube ruptur (1.20) I (***** END OF CATEGORY 05 *****)
- ._ - . _ _ - _ _ _ _ _ .. . . - . . . _ . - _ _
__. - _ - -
~
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 4
.
. QUESTION 6.01 (1.00) What would be the significance of one Intermediate Range channel being undercompensated during a reactor startup? (1.00) QUESTION 6.02 (1.50) List three conditions that require Emergency Boratio QUESTION 6.03 (2.00) What is the operative force for the Pressurizer Spray Valves? How do they fail on loss of this operative force? (0.50) At what pressure should the spray valves begin to open during power operations? (0.25) List two purposes for the bypass line around the spray valve (0.50) 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 lineu QUESTION 6.05 (2.40) List the conditions that will cause the Motor Driven Auxiliary Boiler Feedwater pumps to automatically star (1.60) List the conditions that will cause the Turbine Driven Auxiliary Boiler Feedwater pump to automatically star (0.80)
(***** CATEGORY 06 CONTINUED ON NEXT PAGE *****) . - . - -_
. ~ PAGE 5 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
. t . QUESTION 6.06 (2.50) What are three reasons for having Rod Insertion Limits? [0.75] With respect to the Rod Insertion Limits, "...the steamline break accident imposes the highest shutdown margin requirement."
Explain why this is a true statemen [1.00] Considering each of the following sets of conditions separately, 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 occu CONSIDER EACH CHANGE INDEPENDENTL JUSTIFY YOUR ANSWER Pressurizer pressure decreases 100 psi The N-41 lower detector fails lo 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 take Steam dump system (0.40) Rod drive control system (0.40) Steam Generator level control system (0.40) Pressurizer level and pressure control system (0.40) Plant response to the point where parameters are stable or the reactor trip (0.70)
(***** END OF CATEGORY 06 *****)
__
'
PAGE 6 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND
'
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 (1.00) steps BELOW the Estimated Critical Rod Position calculation? 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: Containment - Red Core Cooling - Red Heat Sink - Yellow Integrity - Orange Inventory - Green Subcriticality - Orange QUESTION 7.03 (2.25) In accordance with ECA-0.0, what are the immediate actions for a Loss of All A/C Power? (1.50) What is the basis for the following quotation from ECA-0.07
" NOTE: CSF Status Trees should be monitored for information onl FRP's should not be implemented." (0.75)
l
.
(***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
. _ _ . .-. __ - - -
- .- -
-_.- - . - -
.
PAGE 7 PROCEDUDRM - NORMAL, ABNORMAL, EMERGENCY AND
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 33 or 34 RCP should be left running? (0.75) 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 (1.20) a steam generator with a tube ruptur State 5 actions that must be performed to isolate a steam generator with a tube ruptur (1.50) 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, 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 List 5 immediate operator actions for a loss of level in the Refueling Cavit (2.00) (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
__ _ _ - _ _ - - - _ .
_
'
PAGE 8 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND
*
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%. Power Range channel A upper detector fails high (1.30) The controlling steam flow indication channel fails high (1.20)
(***** END OF CATEGORY 07 *****) - - * - , , _ ,w-m, ----+,-,---,,-,,,--,,,.-,,mw, - -
ay, y w,--,, - -me, ,----,-,_.-n,., ,-w----mw-- --een m, --qw,,
-w -w-w -,----r, ,,-,w, ,v,,,,
'
PAGE 9 ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS
. $ .
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: Define HOT SHUTDOW (1.00) Which THREE parameters must you observe in order to verify that Reactor Core Safety Limits are being adhered to? (0.75) Provide the following temperature limitation value . Pressurizer heatup rat . Pressurizer cooldown rat (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": What is the meaning of a RED lock on a valve? What is the meaning of a YELLOW lock on a valve? What is the meaning of a GREEN lock on an electrical breaker? 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) 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 full scale? (0.60)
. (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) . _ _ _ _ _ - - - _ - - . . _ _ _ _ _ _ _ _ . _ . __ _ _ .
.
PAGE 10 8 ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS , t . QUESTION 8.05 (1.50) Answer the following in accordance with AP-3 " Procedure Preparation, Review and Approval": Choose the correct answer to complete the following sentence: (0.50) A temporary change to a procedure is authorized to Modify a test that cannot be completed as require . Provide guidance in a situation not within the scope of the procedur . Correct typographical errors, Who must approve a temporary change to a procedure? (1.00) QUESTION 8.06 (3.00) The plant is operating at 100% power, all control systems Using are in automatic, Section 3.0 of the except as stated below all equipment is operabl 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 separatel #33 AFW pump failed its latest surveillanc #31 SI pump circuit breaker is racked out for replacemen #32 Charging pump motor is being replace #31 Emergency Diesel Generator fuel transfer pump has seized bearing Assume that all four of the above situations occur consecutivel (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
-. - .-- .- . - -- - . _ - . _ _ . _ _ - ,
. - ---
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 11 ,
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) 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 shift? (0.30) Whom, if any one, may authorize exceeding the overtime quidelines?
(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: a. Equipment which is out of servic The length of time the facility has been in any Technical Specification action statement Trends on the volume control tank leve The names of the licensed operators who are meeting the Technical Specification staffing requirement The value of Dose equivalent I-131 in the primary coolan The present values of the Technical Specification power distribution limit (***** END OF CATEGORY 08 *****)
(************* END OF EXAMINATION ***************)
_..-__ _ .- _ - . . _ _ . . ._ . _ _ . - __
-
, so fi q u e ~/ Ar- a c e- S~. 2
!
DILUTION NOMOGRAPH FOR HOT RCS 580 BORATION NOMOGRAPH FOR HOT 580 RCS 5000 -
.l 4000 - ,
3000 - - 1000
' 3000 - - 900
- 800 30 - - 700 to _
2000 - - 600
~
- 500 2o - yo _ 2500 -
'
-400 30 - } ~
' 40 - so - 1000 - -300 Q-
'
900 - , so - _ 800 - I 2000 - - 200 _ g ,
: 200 - 500 -
voo- -150 400 -
'~
< soo - 1500 - 300 - - 0 i 200 - i000 - ,
~
j -
- 80 l 300 - - 200 - - 70 'O 2000 - - 60 : soo _ - 50 5000 -
1000 -
- 40 . ,a ; 30.000 - 100 - _ ~ -
_ 20.000 - 500 - - 20 i N~ N~
$0.000
-
,
too 000 -
' ~
PPM BORON PPM BORON DILUTION WATER 10 - -10 IN COOLANT DILUTION IN GALLONS
,
PPM BORON BORIC ACID PPM i
'- IN COOLANT
VOLUME BORON
~
IN GALLONS ADDITION I
.
. _ _ _ _ _ _
.
.
-
t . hea<e - es:_3 I 600_ . _ _
--
__
.
- -
J
, -
.
r
~
'
~~; -
.
590_~
-:/
.:.
I 1 JE I A E V 580 _#. f r'
,
. .
.
-:
.= ,.:
_
-
570_ = ,/9I
. . : ,,
-
,- .. ,
, -
,
_ - .M ! 7' .-
..-
(Orr )
-.
- -
_ ,
.: - --
/
.
360 y -
.-
,
-
- 1
.. ,
p- - r .+ K= I
/
l f y_ ,
.
^
L 5 l'~
/
,f ,,an.,E 4::
,,
<
y .
: - " # =- - + -
550 / _ . . .
-- '
__ _ . __
-
_
. -
-_ ._ ; _--t - -
:.
.
. .
... ,
. .
.,_
,
-w u .
4 .
- -_ E.. _- -
540 -
'
76m._P E:
-,A:-:-p.==Tr %-%
_
-e- ;_ ---- - . - - -
--- r i _ .
..._ . -
.w -~
=
g _ ,,,-r e ::=_ -
._
_:
.- -:. _ - - - ' -.+-- .,,,,.+-- ,
_ _ _ _ P=.88_ 1__
--
. _ .
- -
. . . e_
t_- - .
-
--
. _ _
-.
t u - - t -
~
c> 3 o_ .
.
ad 103 o 2b ad 6b Reactor Power (%)
. -
.
.
' S farE d. f . I .: == +
-
..
. :::.. 2_:n ;_: m
. . , _ _ .. . . . . . _..r-2.r . . -
.r . - :..t---
. :+==r. .- I
,_ _ m. .;.
.
_-
=r: 1r r- . - . , _ -
,= == * - ._ _ _. ..~ ===
. . . . .
=.g; ~- .* -=, =_ =h== = .;..
_ _
. = ,._ _ -
--
= . , r_ :. ._ . _ ..__7:3_ r= gj.g.. :_. . .y
.
O's- + - - =-
-
. .__. ^ ~ - = _4,_ _
. _ _ . - -
4 .. . - -
==1 _ r. _ . . _ . . . . . -
g .~~._ .- .. _I.._.*...*j....-.-. ! ' '--. .*i :1
* "
r_". . C. '~f '~_~U..~. ...--
...3" ."" -.I "~ ~ " . ~ _ .~ { =. .I '.I.:. : . .
. . .
_ . . ._ 7 '_ ( '
..;.
--
-
r- .p rf
:- l~: ,;~.;#. .
_ 2 7.:.;' ~
~~-~*---* ' --_$; -~~ ' . -!:; .g'. ^^ .
g -
": :n:- -. : - - -
- 200 --.--:' - . : . : . :g...:
-
. .- .I -- ;
. _ = _ = = .n,
-
_
= 1m ........s ..e _ t :... : . ..g.w. x. .:. ,
.
=.t._ g. ..n. . . $ =. . . .
.
*= _- rrn nyr..-[:.rr .: .- -: :-
__
- - + . = ;W =: : -- :.. ~~ n Tr:-:
rc r :: ;_ .:-- : - :: : _ /.
%\ ---g;..n'_ - - -r : - . -
f ..IL. ._..J-~ ;,,.. .:' =t ." { ' . ~ " '
~*-'-%(Q . . p ;r;t- :,' :-r-i :r::: +-.:- nr2 _ -. .
- __t r gwwv 1 -
:
'
..-
- -
-cr _
.: :3 d.: n .,; .._ .-:- _
.' .3 = '-t- .-_.=-
_ _ .. s-400 -- g;,N~._.- , ;-~ . . _ _ . _
-
'
.
~~"'
~-* %N k MC:! -'
~
.-
.
-
_ w_.w. ,s .
-
_ _-
._ m -h--
-
_ r. ._ - -- ._ :
--- L..=:= - - : .
.
_r
.e . Ae .. mM
. _
-
_ _ x "..
-
- '
..,__-t_.___
U -600- .. .
--- [g-by ..ww _-4._.--
_ :NA g , -+ -- ;. - 7g. : . ---;.__ . a - 4- -
.
-.
-
=:-..:__
..~t".' 7 p'1;~~l-sr
.r . . - -
_y,w\
:73%t l
. " ~C .T. : '.~..." ...__,._.;=-= . - 6 2.~.*! =
b _ { ..:-: . .. .:.r. . '...?. k..... . - [. . . "C. . ~3
.
_g...
.
U . _ -
--a_=- _- ar.t .f : . :.--t. . ... _ . . . _ .
-- .
.. ...
Cd ~ . .. ~ g -
. la ':R!
'
Q -800 e ZiEdi: ==!!=b=i=. tin-i=.0gai~=%!=%%h E
.a-gs ag :.p=p -!=mg rg.Thg.NNig:.: i: t=--iss - [" . .. WEMalAiW ; :!!r imih=lMMa%N \!
Fi : . "- Y55!515EN'dYNNk _ . . . .- p; g ; m g i .n q "! :-! g . pg . l .
. p i:
.
i t :- .=n t.. c i N y NiN: N i
!
' : i i - : \:\ \\ \ :
i
\\ \\
.
I I I 1500 PPM
!
\\ \. \ (.
.
-l'00 -
.
t
!
I I i . bi b i \ .\ k N 1200 PPM
- l' ; :- \ .p x--
*
.[.
~~~'
. h 1.. . l. :=i . [:
.
. .. l N\ PPM
.-- .-
;\ N ~3 900 i - -i : j- g.j l =.QJi .ui[Fel L
;
(=_p_gE ...-= > .-
>
-1400 ... _
,
: . c . . wr
.... . .- t N\I
.
:
._.._r..-.
-
rr, " . i: ja -T- r4" !. [ ;
[.' -C - : I ; {\:\ 300 PPM
- ;-Q _
- : ( .}!
. i x-'
'
;
.
' !
r .
* " * -'
r 8:
-1600 :'-
' i. , -i ; j l l !\
....,._: 1 -t9_ .
; ; 3 .0 PPM g- f r_-
. . . . . , . . t
_ _ . .: ==_ :-: .. : ... .
,
;
...
,
. 3
,
.
. .
-
. .
.. :.
. .
.
. t ..-- .
r. . . .
- .
j 1. --
.
p
;- :::jr
,
-- r ..F . p :. '
"
7 ,
,
-1800 7 ,
,
60 80 100 0 20 40 Power (Percent of Full Power)
.
. .
.
, '- AVAILABLE CONTROL BANtC WORTH AS A FUNCTION OF BANK POSITION
-
y .
- .
Squ w v
--.
, , rm_
. - -- .
_ .
- _ _ _
-
_- .__.-
--*--
__
- -3500 ".y . -_7 _"; _ _.-
N-- _ _ . _ _
- -
_
.____,_ _ _
- --
. ._ .__. -
r -; #, .
-. .
".
-
._ J .
_3__
. _ __
. _ .
.__ F - .X-_- .
- . - _ -b
._=_ : =_. _ _g__.&q__: - _
- .E. -
'
.
. _
.
-
, :.
- .-;
- - -==
~.__=g--
--+- - i;.
..
.--r ...+. _
,
g .,_1_g. _,_ ___
._
-3000 _ __ ,__ _
'*-
__
'
_
-
-t o
a, g....
.- ,- . _
. _ .
--+
- --- r El- _ ' --- -- r -t- : -t: _ __.'-i
,
_ _ _ . -
- e__+.-...--- n;_ * -
,,,,
-
._
- - - :
.,_
_ _-- -T -- s_- r--- - u.g{L.,+- . -.. -:__
*
o
~
; _ +~ -
--t : t-- - rDh -~ L 4
_ _ _ _
*- ~t-N
-
IL_ ,_ _ _-4=. r_ g. -.*._.-t-- _ 3 -4 ; ~ *- _
-1 - __ _
x ;___,.-- -
> .--
i __ _ &__ . L_ _ _ . __ ~\
------- [ = - t---f: .-t _._ _
r -+-g -- - ., _
--
\ I ._ '~- -
>
s _ _ . . -
- - , - _ .
,._ _ i _ _ . _. t ____
.
-
:r- :- ~~ ~ -.
Y '-~ v-- -e P
~
N=-t -~ ~==1 4 U ._ m ntE ;.. _.. __ri 2 _ E- _E:_ r=--! .m
< -
_-_p
.
_.___...-i----.-;I---__;_ _4 - _ .___ -
-
, ' .-
t ';l M - - :
.
g _. - M'
-
-1___ , __ .-..-_.5........ --7
_ _; __ __p_
---+_=.=-1_.._-t_-.-.._ .
:
.c = . -
_r .
.=_--t ., ; _ _ .
.
--
-- --
- -
-
-
.. q'
:;
-2500 *
__w_-. .- ._- .t= ... : c . r_ [_ - t- - -+ t :. _..j _ a._y 4._:= rnxl=...: nz r - .-.-- ,_;
.-
- . -
F- _
[ b- _ t -- ;_ _._5_ = . -_- . -- - .-
r. h_ :,2 :. .:. ';-- - y_ .- r. - ;- _;..-..
=
--
F' - T - -ttr - t' r '
:: -d ;' .;;z
: ^n ,_X-+ _ ,__
.~~ 1 _
.. ,
__-_--. _ _ .q _ m _ k_=: r I-~ {l
- - + - -- . _ _ _ _,
_-_:--Ej' =. t :_.{-i E.T=1E=ii ij 1:j?;i c h _
--
h. EOE- . .. . _ _ ,_ \_-E B _& _..._ . _ " . , _ _ _ _ . . . =_:t= -. -
':._ _ - .-.dii= i = .Z~~Mi .i!-EE T=iE~lbi
-_u c = =-tn-t'i-E?r?M _._.- . . - _: -
.. -
_.-.._ ;
-- . -
_ 3__ _L__ _- r z. r. -:- _t.=; -- c - - t--+---
--1
__
. .
-
5:-- t
. :.:_ =:= p A *:11-f =. == _.__ ===----h _.__.} - = :9: .. En_.-I' L f=-C,__in _r- -n:- 1 - " ;
: . n- .T -- .,--e--.
__
-
;._{.r=.. - --_.{. _.;_:h
-- . ..t- -
-
-+-- . _ .4._;:;n- -. {2 2:=le_ n:[.:_ - .a _
-
,
=
--
. _ . ._r_ . _ ~- _ _ _ ___..i ... ..._ . . . _r ;.;"E - - I"-
-
.-_ :- x r r; _,- .__:_ ,__t . -
:
-- j.=_- . . =-
r_ ._: _ . -
-e- - 4 - p_ t__
-
__
. ..
. _ _ - . --- - - " ;. n .
.--
.7
~;-
; .- {
.'
.
!-+:i 21--
,
'
t :--. i 1 :h. ~-*i 3-j[ -_[_. __ =. -. *dH: . ..- t- - t: L . * = t- ! .[ - -i-- - ! -_ -r.--l * ' - * *
. _ , _ _ .
nu t- ;.
.
.
. ..
..L I - . - ' -;
.
.
,
i
- - : - -- t -! rr " r :'I - - '
-
L-. t "-t =1
.
F ~" F F.. ::
--
0 _, . : _-*.n-_ ___ . [.;ii-
- -
j -{ = ; = = : = x.E~
. . -- -200
_ :. _.._. . .__ i. n. . . 'p !~ _ _ __ , . , _ . .
~!
h5 .
.. ~
==i = L + r :'l- i' ! i i
;
-
l
:
[i ; i -1 100 80 60 40 20 0 DBm 220
'
200 180 160 140 120 208 188 168 148 128 C BANK 228 _ _ _ .
- - - _ - - DIFFERENTIAL BORON WORTH
__ . _
< % .
. fff u r C bb BOL -
-
,
- 1. 4. . - _
_1 . . _ __ , .._., ___-
-_ _ _ _ _ ,_ -- ;
. , . . . ,_ _ _ . _ ._ . _ .__..f..-_____.:__-..
_ . , _ _ . .- _ . _ . _ . .
. . . . .
.._.._ ... . . . . ___ _ _ . ._ w_
,
. . '
_,_ . .. _ . , _ _ . ..'. _., ._ r-- 3_
'_ _w __ t _ .._- - .. _._..a. _ _ . . _._=
.. ..
.
_... . . . _ .. .
._.. -.
. . . _ . . .._.......
-** - - -
. -_ . ~*, _ _ . .- _ - -
_
,_ -_. ._ ., _-"_ . .... * ._. .e**. ~ _ ", , _
r,. .
-_."..;*~*[... .. . . . _ _
. , . -. ..- l__ . ....u.__. ~ _ . . _ _
:_
. .n i . : -- :;-" T_ _ h- u__ . - _ : t :: -t- - ...... _ -. ~- *- . _
- -
a
- t . . . t - _ t. . -- -~ . ..t... . tr. : -- - -12 ..-.- F. .-_N, : . ---- .
_ _ _ _ . . . . ._
._- ._. . . .._.___. .
r, __ w.__T_...__....._._.r..._.-... - .., _. .. . _ _...,. _ . ._ _ .
. _ ___;: .._ ...._, ... _ _ _ _ .
u ... . ._ _ _ _ . _ . _ ..._t _ .. .... . __ __
....%.._.%_
.L
__. . _ _ r w _ _4_... . .._ u C --- N-11 - - - -
. . . ._
. _ . _ __. __.____- . . . _ " . . . . -- -- r-----
-
'
- -
--
r - --
.u::._x. . _.__ _- ; :-_
o a
~ . _ _ - __t. - __ _ .: __ -
_. - ,
.- _
't
~
C i r :uun:p=:
-10 _ _- ' - "-_ ._ ' _ ' , _ ._.- . " , _ _ .
_ .
"__. -- X _ .
x -
. _ _
. _ _ _ _
- _ -
. _
+- :_: +- . :
-
_g _ _ _ . _ _ r_ . _
-
,
-8 ,
,
, .
400 500 550 300 Core Average Tem (UF) 6 7ace 57-16 EOL ___... . _ . , _
._t--. ,_.._ _ . _ _ . . _ . . _ __ _ _ _ _ _ ._._._._..._......r_...._.__.... ., . . , _ . . _ _ _ - . . . . , _ . . .__ .._._ . . _ .
_
:
.
. _..... ._ . .. . .. .._.. -_ _
.
.
.
: - . . . .
._ --. _ ..._. _t._. ... . . .
_ . . . . . .
.- -_ . - . _ . . . _ _ . + _ _ . _ ...
_ . ..- - _
..
__.a___. ..t-..___-.....w.t.__.. ..
+
.
--
-__.___.__.._.:-__._..-.. .
. . . _ .
-.1_-._-.-- . . _ . - - - - --
.
__1 )_ -_.-..r-._-.-.-:. _ . _ _ _ _ . ,_..._- ..._--- _ _ _ _ _ _ . ____;
..
_ _ _ _ . , _ _ _ . . _ _ _ .
. . _ . . . . _ . __. __ _ _ , _ . t __ _ __ _ . . . . ___ ._
_ . _ __ _ ...
- _..__.. .. . - _ _ .. . __1._..... . _.... __.._....__ _ . . _ ._ _ . _ _ , . _ . _ - _ _
__
.-
_ _ . _ . _
. . . .. . . , . . _ . ......
_ _._.. _ ....
. _ . .
.._-t.._
-
.
-
. _ _ _ _
.__t._.... .
. _ . . . . . ...
.
. . . . . .__.____:_.t.____._. _ . . . . . _ . _ . . _ . .. .._._. .. ....
+.. --- -
. . ._.. __ _ . . . _ . ..
. .
-
.
.. ..
- - . '-. .
-14 -
_-
.
_ .- _l--._. ..r__ .l - -- . - .
-
. _ _ -
. . _. .
..
.__
.
.
.. ._..t._.._..t...
.
.
. . .
..
. .I .
. .
. . .
. .
-- ... . -
. .
. ., .
..
I -. , . - [ [ .
> -
-13 i ....
.
-
. . . . .
-
.
,
. . . .. . . , ,
i . c .- . - F.-- , . l l O E ' l
-
-
- c. I
- 12 - - - -
..___t'_._..'..
.. . _ . -..__t___.. .
. . .
_ ,
.. ._. . .
. . . . , .. . _ . .
...
_ .. .
. - _ . . .
.
. .._
. ._ . . i
._.___.{._..r._.,-
_ . .
. _ _ , _ _ . _ .._. ..___ .. . . _ , _ . .
.. _- ... _ _ . . . . . ._
.
- - + -r"
--
- .
: + - 72 g . :- -.
-11 r
-
-+ -- -
... _
_ ._r ,
. _- ______ .. . . _ _ . . _... . t ...
.
_ ..._ . . _ . .
. _ . . . _ _ ....
.._.+_.,
,._
. _ _ _.. ._ .. _
._. ..
,. w .
. _ . .
. ._
.
..
..._... . . __ . _ _ . .t__. . _ _ m. .. . .. .
,.
.. .. _,
._ . . . . . . _ . _ _ . .
... . . ._
_ . . -. . _ .
. . _ .. _. .. ,_ .
._
,. .,
.
..___. . . ..__
._ ..
_ . .. . _ . .
._ . . . .
._ . ,
_10 . . .. .. . .
.. .
30'O 4b0 50 55'O Core Averacje Tem (OF)
.
. ' - -
REACTIVITY DUE TO XENON AFTER STARTUP f w .
.
ft 9 a re d~. [
~
_ . . .
.
Percent Power
=: _ : r n ._; =r
-
---v =-- . --
_ . _..t
.___. _ c t = _t- +._; :r[=. - _n n u := I 12= rr u t- --- "-=t : r- ,--+- - - . J.0 0 %
_ . _ . .a .._= t ....... . . r -- - - '--- _ _ _ . _ . _ _ _ . _ . b ~" 4 ~ - " = = '#
-3000 M-
"
, -: =1 80 %
g= =EL=:E ij ; M g 5 M ii i -- " + ~!= t-- + - --- 4 --
-
=:: N.D Ei:iF,$hr:M- F= = -$~~'
- = :- <- -- --
;xr= 2 _q - - --
Y d55E'3 Z.'._' $ ~5[
-- -
r
- %
.a. .. .u =u .= =F:g, ==: =. .p
-
. .
. :t a-r -- -
; '- '
'
* ==:=_.,._..___" 4 2
. ; =C._ =E2 .3._E. :~ . . ..;t. r. :. ::. ._:ct - _r.. _ . .
. . . .
_
. .
_
.
t =-{=- ==---
~-
- :=;
2=teerr
- - . .
xr ;.:..u 7---}= ,=j_._.__a _n. : ..__-t-- - :
-- ----
===_. = =. =- , =. =. . _.=.. y_.._:=. . =. =, _ . ; - .
. - . . .
_ %
. ..
f:. . ~ . .
.
- .-
. = 9 - r-:fr = him- -""
-
'i-iE
. . . __
.
.,..:.. #[ h../..i' .I...... r Ei 3 .. ..._ ..: - ,,L - t ' : -
"
5~i i
!95 //h[!!E NN-Fi5E.E._NsiS57N9 :a
-
-
: _;=__ }: //;e- = ==:---+-z._.. .._ u,_ .
e 8 f..n . . t--A = y r:te-1:rrun rx a-- :.:=+!n = r.n:h:2:= r= __::.=
- ;-, . _ :{ _2.g.- n- - g--la ,c=m.2::: = = = :_ .a t --n
'
. _ _.. .....
.
.
..
- r :; . : =~...... : _c - - - - - - -
-
- - -
>- --
-2000 _ -
_---+--
; : nn:' ; =t;. 1. nt .; c= ;,= ;.= t:::n=
e ...... . EL1;_'.i Il l.{(.n fr.- fff.; f.; ::'.:n J n=:. :;: . - Un .. ::t nn :c '
-
=!u . 4- .~.*- M
. ---
ll2" :_
: . u.~.t , . .. :-*1 =..;.; . -. .j . ., =.,. . m._-t--., g ._._...y -- - ' ,
-
=.,- , :.n. [g: :t- II;[I . :, .=, = ,
,.
.
*-
,, _ _; . 7
"
-
" #! ;i=-F 20 %
p
- I
:ffh= j .
~
i [[Ed N.i -5~-} N Ei!5![/ f!-[il 2.5.c[u.:.'Mi- Ir lf t!.u" 5E5I nf Lnun _ -r . c r.=,
> . ; -.- :
f in-f -f ---
*- ..:=, :.:
: -f".:: t= Ei:r : tunn=t =:=r lt-f--}. . .. h- t/
-
H == ff..-.. :: : r
/. t~ - t. : 2tm.=n ~J -
T. l 'Jr . ..
-:.gc,
".:: = - : t. . :.$
f . l.. ? A ,[:.: .-
*
< ..___:- ,
~~- r f
-
i kb b : -
: b :
db: nr
'
t =.:--
.
- - - t=:=g:...;=
,:==
.-- j p]=... j./e t. .. p=.: . q= .d2q:-l..;...f.,p-=--,
_ . . . ,
--t=, .
.. . .. .
i 10 % , . ,.l'R /ti.B - - .::i-li-t . . . _ . . p -W , s . _ _ . ' la; . .. . . t.. . _. . . x
'
-1000 f. E F F f r t r I!! t- I
- -
= -
; //iE A i f. i _i'i i
'
I ! i
'
I 'llM /-a: ] - l t ! !!
' *
l
-
},
L::
.
: . /. -
.
lf.,y=-:;t= '.
'
r ! l- I- y} =f: :. ] -
, +- =ip.:lf- f := k -l p g; .
.j !. [; :
:pj [ .3 3
-
[./j:/ : : j j c[ { .
[
W- !. ' i t:
:
i
'
.
:
++P
.:.
.
[
.
[.
-
.J= a .
.+ : .i
;
//.. .
.
_
.- .
y . j . r r r
.
20 40 60 80 100
TH1E AFTER STARTUP (HRS.)
dD e d ht ,
:
w s c0
( Q%\
Y E4 a Ub 4, i, .. NS .
! 15 3* O la%
* J
??
\1
"A -- as - 9 O,a
- " n 3 * 14 +
, ka e
n* n _) t
hi- > S V Q
#e c %
V uk wx ! a 4 u a h x 9
.9 * 3 e> N6%
u u <r-- N Wb
- a w
r at E D, k h'C O
,
=
D M N k 4 n
$
a nE wa 4 kk w +
-
w q .f h:,
\
Q '
---C )[ a~ , <
s as sa s s s ha b
*
*n
%
< -
^ g%
q{, h a
' a w .
S 47 g
-
p, wk: 2 s
% N 60 w hbw 4 Qg q, aw
#'
R s ka
$b \ N'2
,%
"
^dh "" '
O S
*
1 - S ,," % ,
!. b S h lI 4% %
qtz y
- % "w * 4 y
kD 1 7T 1 e
.
u .
.,
g g
wh f
% %; - - "w - - . .
. _ . . _ - . -- - . - ~ -- . .- -. ,
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 12
*
. THERMODYNAMICS
\
-86/06/05-NORRIS, B. ; ANSWERS -- INDIAN POINT 3 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)
000 (0.50) approximate Is 15, # gallons ,
[If the candidate adds in factors for rod reactivity or a separate temperature reactivity, deduct 0.40 for each]
' REFERENCE i System Description No. 3, Figures 3-13 & 3-15 Graph Book, Curves RV-1, RV-3B, RV-6, RV-7A & RCS-8 REQ-OPC-2, obj _------___-_--____-_--_-__-_-_-_-_---_-_-_-_-_ --_-_-_-_-_-_-_-_---__ K&A 004-000-K5.20 / IF 3.7
ANSWER 5.02 (3.00) i (0.20) l M is less negative and thus imparts less negative reactivity from
the coolant heatu > EOL (0.20) f DOPC is less negative and thus imparts less negative reactivity as , the fuel temperature begins to increas (0.80)
i BOL (0.20) , MTC is less negative and thus imparts less negative reactivity from l
- the res heatu (0.80)
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 1 --_-------------_------_-_-_-_-_---___-----____-_-_-_---_--------_--- ! K&A 002-000-K5.14 / IF EK1.06 / IF 4.2 i ! t I l _ , - . - _ - - . - - _ _ _ - - _ - - _ _ . - - _ - , - . - - . - _ _ _ _ _ _ _ . _ _ _ _ - . - - - .
.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS. AND PAGE 13 5.
i THERMODYNAMICS
\ -86/06/05-NORRIS, B. ANSWERS -- INDIAN POINT 3
. ANSWER 5.03 (2.50) Turbine power - stays constant at 33% power (0.50)
[ alternate acceptable answer: slightly reduced due to reduced Pstm] Tavg (loop 31)
due to no heat sink, goes to Th = 554 F + 18/2 = 563 F (0.50) Tavg (loop 34) 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) S/G Prensure (loop 31) (0.50)
saturation pressure for 563 F =1161 psia (or 1176 psig)
[also acceptable if assume that safeties will be lifting starting at 1065 psig) S/G Pressure (loop 34)
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 K&A 000-074-EA2.04 / IF K3.05 / IF ._ . .. .-. . - -
-
-
~
5 THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 14 ., THERMODYNAMICS I ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. S.
. ANSWER 5.04 (2.40) 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) (0.30)
= -90.74 SUR = 26.06/T (0.30)
= 26.06/(-90.74)
= -0.287 dpm (0.30)
SUR*t P = Po10 (0.30)
= 10E(-8)*10E({-0.287dpm}{1 min})
= 10E(-8)*(0.516)
= 5.16E(-9) amps (0.30)
REFERENCE Reactor Theory Manual, Chapter 4, pgs 8,18,25,30, & 33
-__-___-_____-__--__-_______-___- __-_______-__-______-__-______-____
K&A 001-000-A1.06 / IF 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 _.---__-__-___-__ ____-_--__-__-__-________-__-____--_______- _-_- __ K&A 004-000-K5.06 / IF 3.0(RO), 3.3(SRO)
- ___- _ _ _ _ _ __ ._ _ _ _ -
. _ - . .
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND PAGE 15
.
THERMODYNAMICS '\
-86/06/05-NORRIS, B. ANSWERS -- INDIAN POINT 3 ANSWER 5.06 (3.10) Pre 10nt 02tuati0n 00ndition; in " tubO (0.70) RCS pressure may result in tripping RCPs during SG tube rupture. (0.60)
Sec. dependent RCS pressure is too hard to calculat (0.60) Available spray (0.30) j Good core cooling (0.30) 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 & _____________________________________________________________________ K&A 000-011-EK3.14 / IF ) .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.. . .
. __ -. __ _ - - - - - --- ' PAGE 16 6 PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
.
-86/06/05-NORRIS, B. ANSWERS -- INDIAN POINT 3
.
ANSWER 6.01 (1.00) Detector output is higher than actual neutron level (0.50) Sourc; ner.;; aculd nutr-dernergize early (0.50) WG N SR % REFERENCE System Description No. 13, pg 38 ONOP-NI-1, pg 4 REQ-OPC-4, obj __---___ ----- __---_----_____--___------___--------------------- K&A 015-000-K4.04 / IF EA2.11 / IF ANSWER 6.02 (1.50) Two or more rods not fully inserted after a plant shutdown Uncontrolled reactor cooldown below 540F with one rod stuck out Uncontrolled reactor cooldown below 500F Control bank position below the insertion limits(any three at 0.50 each) REFERENCE System Description _ N .0, pg 54
--_.--_----__.-_-_-_-_____.-__-___---_---_--___-
_.--- _-____-_--_ K&A 000-024-EK3.01 / IF 4.1(RO), 4.4(SRO) l
. - . . _ - . . _ _ _ - _ - _ . - - . .. . _- ._ . - __ . _ _ _ _ . - - - -_ -. _ ..
o 17 PAGE . PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION-86/06/05-NORRIS, B. Y ANSWERS -- INDIAN POINT 3 . ANSWER 6.03 (2.00) Instrument air (0.25) Fail shut (0.25) psig (+/- 5 psig acceptable) (0.25) Minimize thermal stresses-(on the spray line & surge line) (0.25) Help to equalize boron concentrations (0.25) Prevent RCS pressure from reaching the PORV setpoit$t (0.25) following a step reduction of 10% ,
(0.25)
assuming automatic rod control (0.25) REFERENCE System Description No. 1.4, pgs 13 & 14 REQ-OPC-4, pbj 4. ___.---_---_---_-_--_____-__-_--_--_-_-____-_-_--___-_----- -----_-_- K&A 010-000-K6.03 / IF EA2.08 / IF ANSWER 6.04 (1.30) See attached drawing REFERENCE System Description No. 27.1, pgs 34-69 REQ-OPC-5, obj * _________--____--_-_ ------__ ___-_-_-__-_-____- _____.---_-___--_u-- K&A 062-000-K4.06 /'IF < . . . ____ -.
.. . .
e PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 18 6 .
-86/06/05-NORRIS, B. I' ANSWERS -- INDIAN POINT 3 .
ANSWER 6.05 (2.40) MDAFWPs: loss of voltage to 480Vac bus 3A or 6A without SI lo-lo level any 1/4 steam generators auto trip of .',OT:: MFPr safety injectionELelf$re TDAFWP: lo-lo level any 2/4 steam generators 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 ANSWER 6.06 (2.50) 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 me (0.25) Due to the large value of positive reactivity inserted by MTC during the resulting uncontrolled RCS cooldow (1.00) EOL (0.25) Shutdown (0.25) 547 F (0.25) REFERENCE Technical Specificacions, pg 3.10-15 o** CAF *** _____________________________________________________________________ K&A 001-000-K5.08 / IF K5.04 / IF 4.3
l' (
_ _ _ _ _ _
"
PLANT SYSTEMS DESIGN, CONTROL. AND INSTRUMENTATION PAGE 19 f.
.
-86/06/05-NORRIS, B. j ANSWERS -- INDIAN POINT 3 t
. ANSWER 6.07 (2.00) OT Delta-T: decrease (0.25) 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) OT Delta-T: decrease (0.25) Delta flux, a normally negative term, is subtracted from the setpoint (minux x minus = positive); if lower detector fails, Delta flux (0.25) becomes positive, which causes the setoint to decrease OP Delta-T: decrease (0.25) Discussion same as above (0.25) REFERENCE System Description No. 28.0, pgs 21-28 REQ-OPC- ____--___-_-____________--__-_-___-_-_--_-_______-____-___-__-____-__ K&A 012-000-A1.01 / IF ANSWER 6.08 (2.30) Dumps quick open (0.40) Rods drive in (0.40) FWRV open (0.40) c., PZR spray valve full opens ,Mf C ,f /9 /#t/ t decreas /4.ae c s,4) ( 0, ;0 ; Reactor trips on low SG water level,e A4 hys +'r/8 J/# Is, '. (0.70) REFERENCE REQ-OPC-3, pgs 7, 8 REQ-OPC-3, obj ._-----_-_-_--_---_-_----------_---_-_-_----__-__-_-_-_------_---_---_-_-_ K&A 010-000-A1.06 / IF K4.03 / IF . _ _ .
._ .-
___
.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 20
. % RADIOLOGICAL CONTROL-86/06/05-NORRIS, B. S.
- ANSWERS -- INDIAN POINT 3 ANSWER 7.01 (2.00) . Insert the rods 100 steps (0.25) Recalculate the ECP (0.25) If a mathematical error is discovered, borate as necessary to insure rods will be above RIL, reinstitute rod withdrawal (0.25) If the ECP is correct, insert rods an additional 230 steps (0.25) . Insert the rods back to the ECP (0.25) Recalculate the ECP (0.25) If a math error is discovered, reinstitute rod withdrawal (0.25) 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) Core Cooling - Red (0.25 each, proper sequence required) Containment - Red Suberiticality - Orange Integrity - Orange Heat Sink - Yellow Inventory - Green REFERENCE F-0, pg 3
--_----_------------_---_------------_-_---------------------_---_---
K&A 000-074-System Generic 10 / IF .-. - _ _ - _ - _ . .
' PAGE 21 7m PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND k RADIOLOGICAL CONTROL-86/06/05-NORRIS, B. ANSWERS -- INDIAN POINT 3 ANSWER 7.03 (2.25) . Verify reactor trip (0.30 each) Verify turbine trip Check if RCS is isolated Verify AFW flow greater than 415 gpm Secure any liquid radwaste release in progress FRP's are written on the premise that at least one 480 vac bus is (0.75)
energize REFERENCE ECA-0.0. pgs 2-3 Step Description for ECA-0.0, pg 1 _____________________________________________________________________ K&A 062-000-K3.01 / IF EK3.02 / IF ANSWER 7.04 (1.50) To provide normal pressurizer spray (0.75) Shift to cold leg recirculation mode (0.75) REFERENCE FR-H.1, pg 4, 11 REQ-OPC-5, obj _____________________________________________________________________ K&A 000-028-EK3.04 / IF EK3.15 / IF 4.3
, - -
.
PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 22 7-4 RADIOLOGICAL CONTROL , ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. ANSWER 7.05 (2.70) . S/G Narrow range level (increasing in an uncontrolled manner) Blowdown radiation monitor (abnormal levels)f AttJ Secondary radiation (abnormal levels)cg623 Condenser air ejector radiation monitor (abnormal levels)f4ZL7 (0.30 each) . Adjust atmospheric setpoint (to 1040 psig) Close MSIV Close MSIV bypass valve Close ASDV Isolate steam to AFW pump Isolate bleruen f /.v/w (any 5 at 0.30 each) Isolate upstream steam traps 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) (1) one second (assuming 50,000 R/Hr) (0.55) 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 SG#11 / IF . - - _ _ _ .-- . _ _ _
.
* PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE 23
{ RADIOLOGICAL CONTROL
, ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. ANSWER 7.07 (2.50) 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) Transfer to alternate control channel I# (0.40) 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 K&A 015-000-K4.08 / IF K3.12 / IF 3.6 l , _ -_ - _ _-
- - - - - -.
- - _ . - _ .
PAGE 24
- ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS-86/06/05-NORRIS, B. ANSWERS -- INDIAN POINT 3
. ANSWER 8.01 (1.60) All required non-automatic containment isolation valves are closed and blind flange er ErIuipment door [ase properly close . Both doors in personal air locks are properly close . All automatic containment isolation valves are operable or closed, or isolated by a closed manual valv (0.40 each) REFERENCE Technical Specifications, section 1.10 _____________________________________________________________________ K&A 103-000-K1.02 / IF ANSWER 8.02 (2.00) Rx subcritical with adequate SDM (IAW Figure 3.10-1) (0.50) 200 F < Tavg <= 555 F (0.50)
@ 0.25 m cQ;g,75)
Rx (thermal) power RCS pressure
'O.25)
(0.257 gCS gmperature . 100 F/Hr (0.125) F/Hr (0.125)
REFERENCE Technical Specifications, pgs 1-1, 2.1-1 & 3.1-4 _____________________________________________________________________ K&A 002-000-K5.18 / IF SG#5 / IF .
. - _ - . .- . _ _ . _ _ _ . - _ . . _ . . .__ _ _ -
.
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 25 /06/05-NORRIS, B. ANSWERS -- INDIAN POINT 3 . ANSWER 8.03 (2.00) Locked open (0.66 each) Locked throttled Locked open REFERENCE AP-10.1, pg 6 _____________________________________________________________________ K&A Plant Wide Generic #14 / IF ANSWER 8.04 (2.10) Radiation fields (ow 3 dp (0.30 each) Oxygen e .Nm (0.30 each) Beta-Gamma (7to) Neutron Leave containment (0.30 each) Rcchcrgc decimetcr
^4f.h HP REFERENCE SOP-CB-2, pgs 1-2
_____________________________________________________________________ K&A 103-000-A2.05 / IF ANSWER 8.05 (1.50)
(0.50) .
Two members of plant staff with knowledge of the affected are (0.50) One of the above must be licensed as an SRO at IP (0.50) REFERENCE AP-3, pg 6 __________________________________________________________-_-________ K&A - -
/ IF .
. '
ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 26 ANSWERS -- INDIAN POINT 3 -86/06/05-NORRIS, B. . ANSWER 8.06 (3.00) Pg 3.4-2, para 3.4.B ( hhours) (0.60 each) Pg 3.3-4, para 3.3.A.4.b (24 hours) Pg 3.2-1, para 3.2.B.1 (not an LCO) Pg 3.7-2, para 3.7.B.1 (72 hours) 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 ANSWER 8.07 (1.00) six days (0.30) Every other day (for six days) (0.30) Resident Manager or his deputy (0.40) REFERENCE TS Nmendment No. 64, pg 6-la REQ-TS-8 _____________________________________________________________________ K&A Plant Wide Generic #23 / IF ANSWER 8.08 (1.80)
* SRO log bookor 6' nr .M n 'N (0.30 each) * SS log, turnover sheet * ;;1;;r NRO log sheet, VCT level gra h * CRC icg, tu;.;v;; sh;;t-O g * * Chemistry logs Inrere computer read cut 32 4 Jpg mg gg *CAF REFERENCE REQ-AP-21.4, obj 1. _____________________________________________________________________
i
- - - -
- - ..
e PAGE 27
*
_ ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS-86/06/05-NORRIS, B. ANSWERS -- INDIAN POINT 3
.
K&A Plant-Wide Generic #26 / IF ,
- -..,., . - - - , - - . - - , . -, - - , . - ,--.
* *
, .
fiy u r e. cC/ f'f a ' ' S* A 0 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 -
-
40 - t 1000 - - 300 i _ Io 900 - _ l ro - 800 -
~ ' ~
2000 - 600 -
- 200 200 -
00 -
- 150 100 -
400 _
'~
soo - - 100
' ~
300-200- '000 * ' yo 3" ~ l vo .: 2ngg _ p '
- 60
- 50
'"~
1000 - sooo * v' ' ~ "O jgt* ll g
, "
A' {'
-
' ) ,00 _
, y to 000 - / - 30
~
'e N / 'N- 20 000 - '~*
~
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'
.
.5k-i-
*
T y ~ - l _
:
'_9ihC bb . . _ _
.b~iiih :-- :I5 M- 5_ . . _ . . . _ . . _ _.......
: :: =~:= :--- _. .
. _ . . . . . . . . .
. _ . . .
=-- =-.
._a
-
, : .;-= := - __ . t. 3 ; _--.=- - -
-
-- 7 _ ::g_ g:j ,:1.=;=. g
-
.
_- .. ,;
-
O - + - - - - -,._u - x: - %___ _
. - . --i :r-- + -
-y
--%1-, 6. -
. . = :r :--:v_ :j-- . ..t. t =:=.-. . =n .r_-- -
::
- g =r.= .___1_ ;--=-=t__:l=
-r
-_ : -- =--u- :- :_: -:
_
: :... .{-*-
' " " .!=..=._t=d
~
..
-
-- -: . ... s. = I~. - :
-200 E--
- -:
=: Dg-.-_ur . .-=._.' J ---
-'.. . .. ...
u
- . .
== =.. : r. .=_=.. n. .n_ ,
_
- * -
. . . .
6_ .:
=... _ _ . t. =. . ,! r. . :.: ..w. n
:
_,... .t_.=_ .
. ,
-- - . _ . _ - - ... ; ._ _
. . _ . ..,._.....-
.___...___ ,r..._...:._': ::2_ . .,,_ .: n: _ g_ ___:__r_ c .o
.
____T_C
---
_ _ . . ,.--p_'
-
_: !. . . . _....u_-. .
.. _ _ ... T
. . . .
-
_ _ .
= = - ==c___. .- ;---w-w ;;:=w I;::_t= . . :., .i._=:::=_ .j.__ '_ - :t .-t , . ;-_
-
1-
. :t- - -
"p . 4 Mx' 'n=+--'-*- % ;.:-, - .-.- --
--
-- -
=_ _,__.r ; -s e-400- "
"- +
u-
-t h. m --w _t- 2:
--
-
--
. ;;.-
_ ___
;
_m
-- -
-~
-__
-.
-
__::- .
., . . . -
.-_ --. ,
= _ _ . . - - _ _-u=
,
__wMN . _u_ r -- N..t w__ : _ . _ _ . _ _
-- t ,-
-.
--
-__. ; :. _ - _ . . .. _ ...-
,..
--
-~
.*=~
._ -_"- -.
---# ^ :
- +,n:-=-- __.-_
--
g ,- == o -600 - :. t=y-v 1 m- = _ +== t. -. . .u &_ n-m -
-.
__ , _ _ _ . ;_ : __ p _...._- _ -
-
_ __:;;;.; -> , ~ *
,
-A. : = . . . _ . . --- - .::
_- .- ; . : .=. . . :'.%iN __ : : __.-_= _
..: n - mn!"n=: __-- ..
__. : = ._ t e '. 1. N:t ra =r : - - t= : :
:
j;j =__ =; =.- - -= --.. .. ..
, - =. .:t-=: u r =;
. . . .
':__ . . N
-
g =::=n =n-:- = p =--=_ . i = = t =a= : s ...:
=
.y- _=: -
_
.
=: -
ca a - 00
:- = --E=: - . .
Ei:E ' ;.N!'DL%ij;Ei
'
.:l2;6~ij Jij@ip p?Mi:si.i' fiJ.:
.
a: IU.i.- M -
- :i-EEEE'h ' Y!!ENE. Ef-N M -d D M i C- ;_ g gji_ ;
;E EJ-'i:198?!:.:.:fi-ii.7.= :+
E . g h M . N i ..; ; :.i~;j .
.r = a -"=:u - - - = r =- =. . . :q-> =\:=.. ='iYv A. % A:% c' fn.=.. ~v' '
j n..=n := r: = rna n :Ir:
-1000 = = - r=~
g e ' , .'. f FT 2:
~
i'_m si. jE.3.:g: : :i:-ii_ . Q !. \ N N i -iF
@
l -- i . .
.i: _ . ~ l \ \ - \iN \ l
-
[--
-
-
'
\.\ \\ \
\\ \ \ \ ,:
: t
.
i i
-
1500 PPM _ --n00 t .
' i -
i .; !
\\
_-
- I i .
i \ N '[1200 PPM _
-47 p p i . ' '
-
l
=. ._-i_k r..}' ..t.- 93_i_t n_:::ii i.n. ... I ^ 900
.
-
:\ N PPM
.
=.. . _ _ 'i- S. _i. .
.
:-! :MI:jii:tr_ ": u_ij!?el:
.
"' -l '
i _ifi;:{E ~i:- ~ k lk .
~ '- "
5:Y
" ~- -1400 - - :t .
l h5:.E!h -ud-
,
i = l "! ; ++= k L i .
~
i \i \
-
mi=1 ( :-t i t \[ .h : 300 PPM
%j. {' : ( P .l!. I - ( -[ : - ,
I \'
.: .
b-
.
i I
~-n:t- .
'
, ' ' ~
-
2: - - i f
.
2 .
-1600 7 }.,.c '_:!=:-r ' " j .. - [. . _
l
,
.O PP".
. -.... . i- : - ;- r__ .. l : _...-. . t : _..~t.._.. ==. t-
-
: 3
_- 7
-
- .- l- [_..;- . ::-
_.c : _' .
-
_ . !
::. .
.f -
-
n :::it.;: J,-r l !-j l t:..E- -E - Ei- u i 80 10) b 20 4d g 60 r Power (Percent of .ull Power)
.-- -
, .
- -
-
REACTIVITY DUE TO XENON AFTER STARTUP t
*
.
.
Fi q a re C. [
~
_ . . . Percent Power
-
--t-----4----
t n . . .{R .M_= 1 _ 2 . =_ I Cr ._r r '-'-*r._l_... f a a n:- - "--
1 00, %
- f(c,, C ---- rr t" -*-- _...k"=~*=-'T..- .
.
: :.:._ .....;: :: = :.r _:._n ;
_gnnn ==.:=.:_ nx:r: - :. .1 # -r- n c ._- . _ c _ - -- = t - 80 %
----
_ = :r: ==-_==-.u .r- g_= := = . : f.- . =:--=.-- l- t-- +
= -. :=- h;. --:-=:===22- ' - ~ _~_ ,~_ ~- ' =: :
-_ ~
> -::2 :-:=2'_ ._= . .r- .F,: _
:--e---! u nc . t .n::.-/.: --- -
: T . -:- =:=- 60 %
e- -- - --
'-p:- ;:r =r xrg-c-- =j. . . -._ m - 2=:-- _ r t :___. x . 2 _: - . .}I_._:/=E f_ _
.. y
,oc,gT h_5-Ef._ .._. _ .E 9 E M E..[ Y.._E;N
.
+ ._- S ~5 ~~}E~ E ~NE:i::A
._..___.__ ,p, g 4 . . ._, _ ,__ #
r._.__...,. .g.__..._...___..., r_ - - _.... ...p ,
.
'
12 2 ri;if_- :._na=2:$_:=_=.I'. 2;- -- . . ___ . i ._ _ __ : 40 %
-- , _ _ . . :---:=ftf c um . :n .. . . . . . . . _
r,':E - dWmr~=.::-.F==
...____...
. . . _ . . .= - zia __= = 4= =
..ia: . .E_.- .d[..
:
. .fi. n/ - ;---~--
.=_g=n_:. =..t: .. :===_ 4
-
r=_: I+ + --
:r:- : . rm- . _ . = .:- - _u:t- :/,fi.fn:c ==f.tv - - - -- - - - - - - - - - -
t-
- -
H:_'__.._ _: t: J =t2 / :ri= ..,E
...
7- t 2:!:r r- +--.!!=i:====-4 . __:
- .rt =
.:(: :==tr: j=;' . . _ . . _ . _
- - - -
. . .
n
= tn---mm...-_.__-.. x 1;, . - u t: {u-r2:. uta--t-- j
~
. }= .: ; - :- .:
: .. =-- t= =-O;L.- =--- -_ r :== :=y=J '. *' --
=
== _ : h.:g[p I f._5p p=..~_ :=- :.;!*.C12 --b=: . '=- =.
l .t .I =
:. c_-:!:2* .(-.
- - . -~
'
r, ff
.
% - _- n t--
-
E - - " n..n=.. ,:_~. . '.i;=_. .n=_;;
-
=. . .+[ __ _ _-.n __ n U tg : // ;[f: :[i, . - ~: . . ~. - .. _n._ -_.'
, ,
p. . . ,
- - 22~ 20 %
.c -
'
- ! _
22 - . p . 5 =:
~
: :
- 0*. .
.
L* Ct! ~; . . ;=
: :._;". . _;=p:Q: t= r - t= ==1.:
'
~~. U
> .=_ ; : :44- f3 f ' . ..:.' = {... /._+_---...=..-
f. Un r.; 4 .c y _
. . :- I: c- ... :;- -: ; t---; --t:- t. :n__ ~ ' . r : n t_
.=ra
-
:f 1- 3 '
,: m y c..- :-{. J. f: . .c: f.t = . _ :: r = 1 - =;~. C ' ' : !
-
I' :2 :ri.:U: : 4 p (.. _ 20 .. ...;. I ;; _:: 1
--. J fi T ,J r -! : -- t - --- -
-2 T 71 " ~ --b . _..' O Z4 -
. _......._ ' t- . . ..- :=
g _-t- . 2: ={-
;; :. , ' ,
g . . , . . . . . _ .=. ._.. .:_ g,:: .n.. .!, _. : . . g _h. .n. :. T. =. _ l: . .
.. ...:_ . -n.- _- I =. . . . . ,0 % - , .
_.._._ _
.. . . _
.
1 1 r . . .. .
. _ . .
. . .
n . .:__ ._...t I;i.E ; [.p:H= / .i '-- i~... . .iE '-i - W ' . . . _ ,
.: i : ic ;
.t
.. : E ..: 1 ir :.. l: *
.t . rc..:..' : 1 -
.- f- :: l l -l- ' - ^
, t* : .
. p. ., / m -t... . !: :.t
- -
.l
.
.
-1000 .
._.-y.r: ' .
_.;_: h_ , _
"
:
-
.
.
.-
-
, g - -l I g. . L (
- .
g. . . .=[.
.
. t ,
.
i, , t !: . fj [N/-li--/# ! ~! ! I - l r ; i ; i: =r i i IM_ tziA
.
-
..
. . . _. - - - [.
;-
. l-
-
.
(~
.
.- f. . .:::: c.[7
.. ..
. .. ,
[: . :rn {_; .: . ,
.
+
.
._v, n i c :t= e 1 v f.: fn./ ' i .
: .
. ..
'
..J..j, . _ - -
l' : . I'
. . .
t- j :'I -
.
i
.. 1
, --
!' -
-
;.r:.
, , .
,r;.f_..- .! . ,
. :I ': ' r
-
j , l' ".:. . g ..
'
I !
- : . i: .2 t
l~ f' l h
- _.;n_ .
..p"
.
. g-u --
r .
.
i i I ..
>
g g *- - 0 - .
.
100 40 60 80 0 20 TIME AFTER STARTUP (HRS.)
- _
, _, ._
A j \ g .
\ % +
-
\ ck 9 t e II sq
o tg,I s
.
s 4 kh 7b ac n e u'
<
x,
,a ku 5 EVK a
O n 'a s
p a% " o
.
L As h
* * -
4 t hi
.
e
* 4" t e i kk 4 w m
N b V % x E > p p([ m
, . :
w t( 2 n %: 1s Ih,' o, c y
]
jm ' t + s a$ N
;w
% uv gg <~ N.)
% b s% ; a s i * a N d s q% c s ds'di W - g
* y%d
+
C
> z
, N+A' w td '
.J
-
kw
,%
W U{W
,
{
.t, e3 M,O -
%
i I, n
*
w g a= y%%
-s w 3r8" Lk :
t o * Z' .Es qh ub 3t O
-
e q
%a E
. PAGE 1
. TEST CROSS REFERENCE 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 negativ Resolution: corrected answer ke .0 Comment: Tripping at 32 F doesn't prevent sat. It insures the
pumps are tripped before sat. reached in tubes (inc 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: accepte .0 Comment: you may block too early; no auto deenergiz Resolution: corrected answer ke ~ I 3.0 Comment: Should accept other answers if student assumes all power lost. I.e., Bis's tripping et , Resolution: accepte i l i
,--~vr- - ,,-,n,,w---,----, , , - . - ,, ---nw-,.-,,,-- , , - - - - , --e-me---m--n,,,me-- ,,---y ------.c-,------e,, ,, - . . . - , - - , .
- @
Attachment 3 2 Question Number Comment / Resolution 3.02 Comment: level will reset to 45% due to integral reset actio Resolution; corrected answer ke .07 Comment: accept T.S. or actual valves Resolution: corrected answer key, but the answers must be consisten .06 Comment: accept radiation monitoring designator or name (RIS, R19,R62).
Resolution: accepte .0 Comment: Resetting steam dumps a subsequent action not immediat Resolution: answer key corrected, points redistribute .0 Comment: MBFP always in manual so operator probably would chang 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-equilibriu .0 Comment: peak clad temperature concer Resolution: not incorporated, question was stated with respect to amount of time at power.
, 5.0 Comment: Beff is less, therefore, rate of increase is greate i Resolution: will be considered in gradin .04 Comment: ask question in terms of plant literature, i.e.,
- pcm/ ste !
Resolution: will be considered on future exams.
, 5.06 see R0 1.07 ) 6.01 see R0 3.0 .05 see R0 2.05.a(3) 6.0 Comment: PORV's open & charging pump speed decreases.
Resolution: answer key modifie .0 see R0 4.06 7.0 Comment: isolate MFW.
- Resolution: not incorporated; question was in reference to a specific procedure.
i i ) t
.v.- .-v -y- . _ _ , ,.. . - , _ _ - _ . - _ . _ , _ . . - . . . - .. . - - - . - - - - - _ . - - - - - - . ~ . - - -
- > - . .. _ . . . - - - . ~ -
. . d Attachment 4 2 Question Number Comment / Resolution 7.07 see R0 4.07 8.01 Comment: closed or blind flange; equipment door not door Resolution: answer key correcte .0 Comment: must assume flo Resolution: answer key modifie .0 Comment: add - V.C. air sampled for radiological concern Resolution: modified answer ke .0 Comment: accept TLD for beta gamm Resolution: accepte .0 Comment: change recharge dosimeter to notify H Resolution: accepte .0 Comment: add turnover sheet or status board c Comment: add log sheet Comment: add personnel schedule f Comment: Delta I log or Reactor Engineer in Report Resolution: accepted. }}