IR 05000423/1987028
| ML20148B536 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/16/1988 |
| From: | Eselgroth P, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20148B533 | List: |
| References | |
| 50-423-87-28OL, NUDOCS 8803220015 | |
| Download: ML20148B536 (213) | |
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- V.S. NUCLEAR REGULATORY. COMMISSION REGION I
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OPERATOR: LICENSING EXAMINATION. REPORT
. EXAMINATION REPORT N :87-28(0L)'
FACILITY DOCKET N .50-423-FACILITY LICENSE N0c NPF-49 LICENSEE: Northeast' Nuclear Energy Company P.O. Box 270 Hartford, Connecti_ cut 06141-0270
. FACILITY: Millstone Unit 3 EXAMINATION DATES: December 14-18, 1987 CHIEF EXAMINER: faeb hq- /dd 1I[" N '
Barry S. Norris
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/ Date Senior Operations Engineer APPROVED BY:
Pet'er WTEsel oth,'Ch'ief PWR Section 3 '/['N Date Operationr, B nch, Division of Reactor Safety SUMMARY: Written and operating examinations were administered to four Senior Reactor Operator (SR0) candidates and three Reactor Operator (RO) candidate Three SR0 candidates and two R0 candidates received their licenses. One SRO
. candidate failed both the written and operating examinations, and one R0 candidate failed the operating examination.
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L 8803220015 880316 PDR ADOCK 05000423 DCD )
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.4 REPORT DETAILS TYPE OFLEXAMINATIONS: . Replacement EXAMINATION RESULTS:
1 R0 l .SR0 l l Pass / Fail l Pass / Fail l'
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CHIEF EXAMINER AT SITE: B. S. Norris (USNRC)
OTHER EXAMINERS: E. Yachimiak-(USNRC)
... R. M. Keller (USNRC)
L. E. Briggs (USNRC) '
P. H. Bissett (USNRC)
N. C. Jensen (EG&G)
~P.-T. Isaksen (EG&G)
1.0 Summary of Generic Strengths and Deficiencies on the Operating dxams The following is a summary of generic strengths and deficiencies noted during the operating exams. This information is being provided to' aid the licensee in upgrading their license and requalification training programs. No licensee response is require .1 Strengths Communications between the members in one of the groups of candidates that were examined at the simult. tor were clear and precise. Orders were clear and direct and responses by the operators were of equal clarit Supervisory skills, as demonstrated by one group of candidates during the simulator portion of the examination, were effec-tively used when directing the operators during abnormal and emergency olant conditions. Time w&s taken to summarize the plant's status so that each operating crew member understood his responsibilities during tha ensuing recovery effort . -. , . _ , - . - . . -
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. emergency plant conditions. Time was'tak'en to summarize'the
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. plant's status so-that each operating crew member understood his responsibilities during the ensuing recovery effort _
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1.2 Deficiencies In contrast to paragraph 1.1.b,. communications between the memoers in another group of candidates on the simulator were poor. Plant conditions and parameters were often described without. adequate clarificatio Requests for information wer often non-specific and responses to these requests equally vague, The candidates were unfamiliar with the expecte'd plant response in the simulator while implementing =section 5.4 of OP 3204,
"Reduced Temperature Return to Power." Som' SR0 candidates had difficulty verifying, via the control roo. logs, that scheduled surveillance. tests were complete Some fK) candidates had difficulty performing a plant calorimetric by han .0 -Sumc.ary of-Generic Strengths and Deficiencies on the SRO Written Exams The following is a summary of generic strengths and deficiencies noted from the grading of the SR0 written examinations. This information is
~being provided to aid the licensee in upgrading their license and requalification training programs. No licensee response is require .1 Strengths Overall knowledge of plant' systems design, control, and instrumentation, with the exception of paragraphs 2.2.c and 2.2.d below, Overall knowledge of_ procedures - normal, abnormal, emergency, and radiological contro .2 Deficiencies The effects of xenor oscillations on primary plant condition , The effects of a dropped rod on primary and secondary plant c conditions.
I The basis for WHY the auto start signals are different for the auxiliary feedwater pumps, HOW the arming of the cold overpressure protection system (COPS) affects the PORV block valves.
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3.0 L Summary of Generic Strengths and Deficiencies on the R0 Written Exams -
The following is a summary'of generic strengths and deficiencies. noted-
i from- the grading of the R0 written' examinations. This information is being provided to aid the licensee in upgrading their license and requalification' training programs. No' licensee response is require .1 -Strength Overall knowledge of plant system features in both safety and emergency system .2 Deficiencies
'~ The effects of core age on the Doppler Only Power coefficient, HOW to locally start the diesel using the manual start lever
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on the air start valves.
L HOW the arming of COPS effects the pressurizer block valves and power operated relief valves (PORV) and PORV block valve Radiological exposure control procedure .0 JSummary of Simulator Discrepencies During the conduct of the simulator portion of the operating exams, the following human factors discrepancies were observed:
- The Critical Safety Function Status Tree computer displays for-Subtriticality and Heat Sink do not always identify the cor, rect path to the operator's. For Subcriticality, a red path is'continousl displayed when at power. For Heat Sink, the path displayed is not in agreement with the procedurally derived pat Black and White tape is in use on the control room benchboards to identify electrical bus configuration This has not been done at the simulator, White masking tape has been placed on the handles of the switches for buses 328 and 32N (power supplies for the rod drive MG sets) in the simulator. The tape has been removed in the control roo Barrel switch guards are in use around various pushbuttons in the control room. This has not been accomplished in the simulato . _= . .
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- Personnel Present at the' Exit Meeting 5.1 .NRC-Personnel-
- 8. S .Norris- Chief Ex'aminer 5.2 Facility Personnel-J. M, Black -. Director,' NTO C. H. Clement - Superintendent, MP3
'J ' S, Ha'rris - Operations Supervisor, MP3-
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R. F.' Martin .ATS, Simulator Training M. J.'Moehlman-- ATS, Operator Training-R. G. Stotts Supervisor, Operator Training 6.0 Summary of Comments Made at the Exit Meeting
~6.'l The NRC discussed'the generic deficiencies noted on the operating examinations,,see paragraph 1.0 for details.
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-6.2 :The NRC noted the discrepancies between the simulator and-the-
_ control room as discussed in paragraph' _
6.3 The NRC noted that the posted telephone numbers for contacting' the NRC are~not consistent with those listed in EPIP-411 ~
j The facility stated that they would determine which telephone numbers were correct and would ensure that the procedure and the-posting were consisten .0 Review of Exam-The written examinations were reviewed by the utility and discussed withL the examiners after all. candidates h'ad completed the examination on December 14, 1987. The facility's comments (Attachment 3) and the NRC resolution (Attachment 4) are enclose Attachments:
' R0 Written Examination and Answer Key 2 .' SR0 Written Examination and Answer Key Facility Comments on Written Examinations NRC Response to Facility Comments
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ATTACHMENT 4 NRC RESPONSE TO FACILITY. COMMENTS
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The:following: statements-address the NRC's resolution of comments on the' ,
written' examinations submitted by the' facility-(see Attachment 3):and changes made'to the answer: key during the grading proces /
REACTOR OPERATOR-EXAMINATION
.1.0 ' Comment accepte'd, answer key modifie .0 ' Comment accepted, answer key modifie .0 Comment accepted, answer-key modifie .0 Comment accepted, answer key modified to accept "cold leg temperature decreases" as an alternate answe .09(2) Comment not accepted. .The question was intended to test the knowledge of-the magnitude of the change of equilibrium Xenon levels. The candidates' responses will be evaluated on a case-by-case basi '
2.01(3) Comment not accepted. It was not agreed that either TRUE or FALSE
< was an acceptable answer. Rather, it was determined to-delete the
. question. Question point value was reduced by 0.50 point .0 Comment accepted, answer key modified to accept "Containment Instrument Air Compressors" as an alternate answe .0 Answer key changed to include an additional acceptable answer during the grading of the examination .07 ~ Comment noted, answer key not change Consideration will be given to candidates' responses which are appropriately justifie .0 Comment note The answer key and point values were not changed because the level of design basis knowledge required to answer the question was considered appropriate for the R .0 Comment accepted, answer key changed to reflect "RCS overpressurization" as the correct answe .0 Comment accepted, answer key modified to accept "Diesel has lost control power" as an alternate answe .0 Comment accepted, the reference material provided for exam preparation was in erro The answer key was modified to delete the word HIGHEST.
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Attachment 4 2 3.0 Comment noted. Consideration will be given to any properly explained response which assumes the steam dumps are in a Mode'which is normal for the stated plant condition .0 The answer key was revised during the grading process to allow another correct respons .0 An;wer key corrected during the grading proces .0 Comment accepted, answer key modifie .0 Comment noted, answer key modified and points redistribute .0 Comment accepted, answer key modifie .11 Comment accepted, answer key modifie ,
4.0 Comment not accepted, nor was there an agreement at the examination review. Departmental Instruction GPS-3.07 pages 3 and 4 "Handwheel Closure of Motor Operated Valves" stresses the requirement that Cheater Bars not be use .0 The answer key was revised and points were redistributed during gradin .0 The answer key was revised and points were redistributed to include adverse containment values that were not included in originally supplied plant reference materia .0 Comment accepted, answer key modifie The reference material provided for examination preparation was in erro .0 Comment not accepted, nor was there an agreement at the examination review. Subsequent information supplied by the facility states that the 233 gpm flow limit is ". . to ensure adequate NPSH to the charging pum .
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The answer key was revised to indicate this reaso .10 The ar, wer key revised to delete "at S 350 F" as a required part of the answ SENIOR REACTOR OPERATOR EXAMINATION 5.0 See the response for question 1.06.b.
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5.04 Comment noted. The answer key was modified to incorporate the changes made to the r:ierence data during the administration of the exa The change to che reference data, however, did not make it necessary for the candidates to have a Samarium curve. The candidates were asked for the reference value at 100% equilibrium power, not the time dependent value.
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4-Attachment 4 ~3 5.05 Comments note The answer key for part a.2 was changed to allow a candidate to provide a written response of power increasing and then
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stabilizing at a new, higher valu The answer key for part b.3 was changed to C. instead~of B. The answer key for part b.2 was changed to G. instead of H. In addition, the following additional -tuswers u were changed: Parts a.1 and a.4 were changed to add.F. as an alternate acceptable answer due to similarities between the two choices. Parts c.1 and c.2 were changed to "H. ~ or D." for the same reaso .0 Comment not accepted. A condenser circulating water pump-does-display the characteristics of a centrifugal pump when startin If tho discharge valve were to be open during the pump start, the starting current would be higher because of the low resistance to flow within the discharge pipin This can be-shown to be true by referencing the circulating pump start procedure and the pump's head versas flow curv ;
5.0 Comment accepted, answer key modifie .0 See the response for question 2.0 .0 See the response for question 3.0 .0 Comment accepted, answer key modifie .10 See the response for question 3.1 .0 Comment not accepte The caution is applicable throughout the entire procedure and should be understood prior to performing any procedural action .0 Comment not accepte The reference material supported the answer key respons .0 See the response for question 4.0 .0 See the response for question 4.09.b.
I 7.0 Comment accepted, answer key changed.
- 7.0 Comment not accepte The facility reference material supported the answer key respons .0 Comment accepte The answer key was modified to accept "if l
equipment is deemed inoperable" as an alternate answe .0 Comment accepted, answer key modifie i 8.0 Comment accepted. Any superintendent will be accepted as an alternate response for duty officer.
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Attachment 4 4 8.07 ' Comments noted. The answer key responses were. modified to allow reasonable: candidate responses, as long as justification was
.provided. In addition, higher classificationsLwere deemed acceptabl .
.with appropriate candidate. justification, 8.0 Comment not. accepted, based on the assumptions stated within the-questio .0 Comment accepted, answer key changed.
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8.0 Comment accepted, answer key change .09 Comments note The answer key for 8.09.b was changed, the answer key for 8.09.c was not changed because both parts of the answer are needed to fully explain why the limit exist ,
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U. S. NUCLEAR REGULATORY COMMISSION REACTOR OPERATOR LICENSE EXAMINATION FACILITY: _ M_ _I L_ L_ S_ _T O____________ _ N_ E _3_ _
REACTOR TYPE: _PWR-WEg4________________
DATE ADMINISTERED: _8Zflgflg________________
EXAMINER: _BRIGGSfBISSETT_________
CANDIDATE: _ d ________________
-1NS16UCIlgNS_IQ_g@NQ199IE:
U2e separate paper for the answer Write answers on one si de onl Staple question sheet on top!of the answer sheet Points for each question are indicated in par'entheses after the questio The. passing grada requires at least 70% i n each category and a final grade of at lacst 80%. Examination papers will be picked up six (6) hours after th@ examination start % OF ATEGORY- % OF CANDIDATE'S CATEGORY
._y@LUE_ _IQI@L ___SgQRE___ _y@6UE__ ______________g@lEGQRY_____________
.22:99__ _29199 ___________ ________ PRINCIPLES OF NUCLEAR POWER PLANT OPERATION,-THERMODYNAMICS,
, HEAT TRANSFER AND FLUID FLOW
.55:5S__ _2@ 99 ______..____ _______ PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS
_29199_- _25199 ___________ ________ INSTRUMENTS AND CONTROLS
.25199__ _25199 ___________ ________ PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 97.50 i22:2E__ ___________ ________% Totals Final Grade
.All work done on this examination is my nw I have neither given nor received ai ___-_________--_-___-___---_--_____
Candidate's Signature
- Q & 201 pJ3 M - c.sp frd
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NRC RULES AND GUIDELINES FOR LICENSE EX'AMINATIONS
'Juring the administration of this examination the f ollowing rules apply:
1.- Cheating on'the examination means an automatic denial of your application
.gnd_could result in more severe penal ti e .' Restroom ' trips are to be limited and only one candidate at a time may leav You must avoid al'1 contacts with.anyone outside the examination
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room to avoid even the appearance or possibility of cheatin ~
2 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, wri te gnl y gn gne si de 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 answer.
- ll. Saparate answer sheets fecm pad and place finished answer sheets face down on your desk or tabl ". 2 . Use abbreviations only if they are commonly used in facility literature.
- 13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer require . Show all calculations, methods, or assumptions used to obtain an answer to mathematical problems whether indicated in the question or no .f Partial credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questions of the examiner only.
,1 You_must sign the statement on the cover sheet that indicates that the
- work i s your own and you have not received or been given assistance in ( completing the examinatio This must be done after the examination has been complete ,
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'18' J When E you compl et e 'your;-ex ami nat i on ', you shall's
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c'. . Assemble your examination as follow; 11)' ; Exam: questions on to '(2) . Exam: aids- ' figures,; tables, et ~
.(3) Answer-pages including figures which are 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
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not use for_. answering the question Leave the examination area, as defined by~the examine If after l eavi ng , you are-found in this area while.the examination is s t i'l l in progress, your. license may be denied or revoke ,
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- 1 - PRINC'IPLES OF NUCLEAR POWER PLANT OPERATION t PAGE 2 IdE6DgpYN@DICS1 _UE@l_lB@NSEEB_@Np_ELUlp_Elgd
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QUESTION 'l.01 - ( 2. 50) ~
' : State whether the parameters listed below would INCREASE, DECREASE or, STAY THE SAME as,a result of a normal
. power change from 75% load to 85% load. . Consider each parameter separatel y and assume the control rod t -system is in AUTOMATIC. Assume no1 operator. action with the exception.of increasing turbine loa . Tavg RCS Delta T Reactor Power 4 Fuel Temperature
- Shutdown Margin State.whether tne parameters listed below would INCREASE, DECREASE or STAY THE SAME as a result of a normal power change from 75% load to.85% load. Consider each parameter separatel y 'and assume the control rod system is in MANUAL. Assume no operator action with the exception of the increase in turbine loa . Tavg RCS Del ta T Reactor Power
. Fuel Temperature Shutdown Margin (***** CATEGORY 01 CONTINUED ON NEXT PAGE *****)
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GUEST. ION' ~1.02 (2.00)
iAttachment-1.1 shows' characteristic-curves for two: centrifugal pumps. Each
- pump;is equippedc with a check valve on its discharge. Using, Attachment datermine the system. pressure and flow rate fort a. .Two pumpsfoperating in paralle b '. Two' pumps operating.in serie <
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.. 1[ ~ PRINCIPLES OF NdCLEAR P'OWER PLANTiOPERATIONI 'PAGE l4 1UE@dQQyN@glCSt _dE@I_IG@NSEE@_@NQ_FLUlp_[LgW c ;<
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DUESTION 1.03 . ( 2. 00) .
< What< is .'f.he subcooling margin of the plant if ' the f ollowing condi tions ~
exist SHOW ALL: WORK (1.50)
. T h'o t = 617 F' Tcold = 557 F Pp z r. ' = 2235 psig- Psg = 990 psig b.: If power;is lowered from.100% to 50%, how will the subcooling margin change (increase, decrease, or remain the sama)?' (0.50)
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il - PRINCIPLES: UF NOCLEAR: POWER PLANT OPERATION1-
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4- ' THERMODYNAMICSi; HEAT _TRANSE[U_@ND_F(UlD_ELOW m
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- QUESTION!t1.04- ( 1 ~. SO )
'Antwer;the-following,.TRUE or FALSE:
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a ~.'! A. neutron population at equilibrium always means-thattthe
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~ fDelayed neutrons..are less likely to escape, resonance- capture 'than
, prompt neutron 'ci- ' Delayed Neutrons:have'a greater effect on. reactor. period after La negative reactivity addition _than'after a positive ' reactivity
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T - :- PRINCIPLES OF NUCLEAR POWER PLANT' OPERATION t PAGE 6'
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THERMODYNAMICS 3 HEAT-TRANSFER AND FLUID FLO =
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1- GUESTION - 1.05 (2.75)
HOW:L(Increase,cDecrease,.No Change) and WHY wil1 an. INCREASE:in-eachLof'the f ol l owi ng' ~ af f ec t RCCA.(differential) worth? Include effects and results on ntiutrons. and : material Consi der.' each case separatel y and ' state any-
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Jassumptions.mad :Moderatorf Dbnsi ty ' (1.00)-
b' . . Boron Concent' ration (0.75) ~ Core. Age ( 1.'00 )'
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1[ PRINCIPLES OF NUCLEAR POWER PLANT DPERATION t PAGE 7 ISE6dggyN901CS _UE91_I66NSEE6_@NQ_ELUlQ_ELQW t
d QUESTION 1.06 (2.00)
HOW (More Negative, Less Negative, No Change) does the Doppler Only Power Co2fficient change if the below parameters change as follows. JUSTIFY WH Reactor power Increases from 50% to 100% powe (0.75) Core age Increases from BOL to EO (1.25)
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! 'DUESTION 1.07 ( 1.' 50)
.With all. systems in manual and-no operator action,_WHAT EFFECT ,(i ncrease, dscrease, no. change) and:WHY will decreasing the circulating water temperature have INITIALLY on the following7 Condensate temperature
~ Steam < generator: pressure- Reactor power
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QUESTION- 1.08 ,( 3.00)
t :How'doesiDNBR change (increase, decrease, no. change)'as each'ofLthe:
following'is. increased? (Consider 'each separatel y) .(2.00)
' RCS pressure 1, : ~ RCS - f l ow Reactor power Core inlet temperature
. What causes Beta bar to change over core life? (I.00)
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LQUESTION1 1.'09 '(3. 25) -
Af tzr L operat i on at ,50% f or .FOUR . (4): days, power is inereased to 100% using-control . rods onl y' (i . e. , boron : concentration . i s not changed).From the beginning of.the transient until steady' state conditions.are reached, ox pl ai n ' HOW and WHY.. Xenor. concentration will- change.'in terms-of production end. removal mechanisms. Include approximate: times and relative magnitudes
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- (50%: power vs 100% power).
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' PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 11 THERMODYNAMICS t _ HEAT TRANSFEC AND FLUID FLOW
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l DUESTION 1.10 (1.50)
-9 A rcactor'at BOL is critical at 10 amps. Rods are withdrawn at 30 steps par minute for 10 seconds in bank sequenc What is the SUR IMMEDIATELY AFTER the rod motion stops? Assume differential rod worth is 20 pcm per step, effective delayed neutron fraction is 0.006 and the effective precursor decay constant is 0.1 sec-1.
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j'[-QUESTION ~ 1.11 (3.00)-
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Indicate.-whether the;value of the f ollowing reactivity parameters will-become MORE NEGATIVE, LESS NEGATIVE, or REMAIN THE SAME (no significant chenge) . for their respective condition changes below. Consider each case esperat el y. : Briefly explain your answe .a.- .MTC Beginning of 1ife to end of 1if Doppler only power coef f ici ent: 1 */. t o 100'/. p ower .
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r 6 4 :UES. 3N 2.01 '2.00:
O (Indicate 'whether the f ollowing statements, which pertain to the plant nir system, are TRUE or FALS (2.00)
l' . . The cold shutdown air compressors use TPCCW for cooling water supply?-
2.- IThe instrument air compressors use TPCCW .for cooling water supply?
f "r cent 2!- r-t i ct 2 r-t 2!- cc ;cercr r -a c e c o C C'r' r-
- alin; -: 2 t e- c u p p ! '/' The containment instrument air compressors normally supply air to the containment header ring?
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QUESTION ~-2.02- (2.75)
Tho reactor plant component cooling water -(RPCCW) is comprised of three
.esparate'subheaders, two-of which-are safety-related. Answer the f oll owi ng questions in regard: to-these two subheaders, Given below is a list of' heat-loads. State whether each is supplied by RPCCW: Train,A, RPCCW-Train'B,-both trains,-or neither train.. (1.75)
1.L Reactor _ cool' ant pump thermal barrier 2.. Letdown heat' exchanger (HX)
3. Diesel generator-lube oil cooler
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4.-Residual Heat. Removal (RHR) HX Service air compressor Seal water HX- Safety injection pumps cooling surge tank What'TWO RPCCW loads would be cooled in the event of a1 station blackout or CIA condition? (1.00)
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.OUESTION
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2.03 (2.00)
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.c., List'FOUR.-(4)Lsignals that will automatically trip the. Motor driven
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main feedwater pum (1.60)
- 1b . Why is moisture separator reheat steam not;use'd to drive-the Turbine
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- driven; main ~feedwater-pumps during-startup?' (0.40)
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.' QUESTION 2.04 ~( 1. 50 )
. What is the' purpose of_the crossover line from the-sur. tion of the
. safety injection. pump 'A' to the suction of;the centrifugal charging
- . pump (1.00)
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-b.- !Evolain the purpose of:the "power' lockout" feature associated wit valve MV 8813'(SI4 pumps common miniflow header isolation. valve)?
(0.50)
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-QUESTION 2.05- (2.75) .Ex p l a'i n thel Technical 1 Specification-Bases for the f oll owing :
requirements. f or the SI: Accumulator Tanks when.at 100%. powe (2.00)
' l '. - . Power zi s removed from the accumulator' tank i sol at i on.-val v . Minimum water volum . -- ; Maximum water volum . Maximum nitrogen-pressure, b.- List.3 occurrences ~ that could cause accumulator' tank pressure to ris (0.75)
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PAGE- 18; 2___EbeN1_DE@lGNilNCLUDING_S@ Eely _9ND_EMSBGENCy_Sy@lEMS
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L; ' QUESTION
. 2.06 L(2.OO)
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- Anewer -the f ollowing questi~ons-concerning the steam generator outlet ~
-nozzle What are the.3 reasons why it.is desirable to liniit steam line break flow rate by the use of.the S/G outlet nozzle _
- ( 1. 50 ) -
- What other basic ~ function, besides those referenced in a. .above, . i s-provided for-by the design of the steam generator outl'et nozzle?(0.50)
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'GUESTION. 2.07
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(1.50)
A11 erge break' LOCA ' concurrent - wi th a loss of off. site power.has occurred. The' emergency diesel generator has started on the loss of-pow 3r.and a containment depressurization actuation si gnal _ has . ini ti~ate Approximately 60 : seconds , elapse bef ore the Quench Spray pumps deliver wate Epray to containment. State'THREE reasons'why.there.is.a time delay bef ore tho-Quench Spray l pumps are energized and deliver water-spray to containment.
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~ QUESTION 2.OB- (3.00) The turbine auxiliary feedwater (TDAFW) pump has THREE'(3) main- h '
steamline supply-lines. TWO (2) are required:to meet gle f ailure crieria-considerations. WHY is the third supply line equired? (0.50) WHAT are.the THREE '(3)' sources-of water for-th FW system in their ORDER OF. PREFERRED USAGE? ( 1. 00)- WHAT are'the.FOUR (4) signals which ca utomatically start the moto ' driven AFW pumps? -( 1. 00) WHY are the automatic start si is of the TDAFW pump different from the MDAFW pumps?- (0.50)
ANSWER Because one RCS loop c .be i sol at ed. t ]
' Demineralized water orage tank. CO.25]
Condensate-stora tan [0.253 Service water ong Island Sound) CO.25]
(Listed in right order) CO.253 SIS [ ]
LOP .25]
CDA CO.253-Lo S/G. level LO.253 Reduce the possibility of S/G overfill' [0.503 hb OL 4 Qa?md /
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_ QUESTION
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'.01 '2.00?
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-a. For a large break.LOCA, WHAT'are-the minimum number of emergency core cooling system pumps required to cover exposed fuel and limit possible core damage?
{f2C}~iG.7Di b. Following SI reset, WHAT operator-action (s) must be performed in order to reinstate automatic re-initiation of SI? +0-5&P (C t ( )
c. If TWO (2) charging pump are OPERABLE ~in MODE 4, WHAT RCS system safety limit can'be violated if BOTH are operated? Include TWO (2) significant parameter ,40.70)
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QUESTIONL'2.09-
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. ~WHY would increasing battery charger output voltage above 143 volts be a. concern when. charging a discharged battery?
tL;. WHAT prevents standby battery charger 301A-3'from being used to feed more than one 125'VDC bus? If'the plant.is at 100% power and experiences.a, loss of'125 VDC bus 301A-1, WHAT component DIRECTLY prevents emergency diesel generator."A-from starting, iffrequired, from the control room? ,Will a loss of any ONE (1) class 1E<125 VDC bus'cause a DIRECT reactor'
trip? If so, briefly. explain HOW? Assume the plant i s.at 100% power.-
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GUESTION 2.10 (2.50) Besides LIQUID monitors, there are THREE (3) basic types of process radiation monitor sampling channels at Millstone 3. WHAT ARE THEY? (1.00) List FIVE (5) of the li qui d process monitoring points. Also, state any automatic actions associated with them when high activity levels are detecte (1.50)
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OUESTION 2.11 (2.00)
- Ancwer.the following. questions concerning-charging pump recirculation flo J
- o. - What is the primary reason f or_ having' chargingf pump recirculation flow? (0.00)
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~ Where is recircul ation f low directed to-during normal operation? ,
(0.60) Where is recirculation. flow directed to during a small break'LOCA with RCS pressure at 2300 psia? (0.60)
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2[__P6@NI_DESigy_ lng (UplN@_S9 Eely _@yp_EUESgEUGy_Sy@lEDS PAGE 24
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QUESTION 2.12 (1.00)
U3ing Attachment 2.1, STATE the purpose of valve AOV14 EXPLAIN WHY this volve does not tap directly into the turbine building ring heade (1.00)
(***** END OF CATEGORY O2 *****)
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QUESTION 3.01 (2.20)
The reactor is at 100% with all control systems in automati The controlling l evel instrument for number one steam generator fails hig WHAT happens to the actual level in the affected steam generator (increase, dacrease or no change). WH EXPLAIN the transient to the first automatic protective actio Assume no operator ac t i o (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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c.,- _WHY 'i s' pressuri z er , l evel . manual l y controll ed during . a pl ant ~
'cooldow (1.00)
Ib'. :WHY.is11evel controlled.at 50 to~.60%-.during a-cooldow ( 0. 50) . J HOW is pressurizer l evel program maintained- during a : power increase-from.no-load to full' loa (1,20)
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QUESTION 3.03 (2.00)
The Reactor Vessel Level Monitoring System (RVLMS) consists of two safety relcted instrument channels with eight level detectors per channel, WHAT type detectors are used and HOW do they detect leve (1.25) What three (3) parameters are displayed on the control room CRT for the RVLMS SYSTE (0.75)
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3[__ INS 16UDEBjlS_@ND_ CONI 6065 PAGE 28
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QUESTION 3.04 ( .50)
TRUE or FALSE Wh:;n the last (No. 8) indicator on the RVLMS does not indicate any level in the reactor vessel, the core is definitely uncovere (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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'OUESTION'- 3.05 (3.00)
WHAT.'is steam dump response / action during the fo41owing plant hvolution ~
Idantify the ' measured and ref erence parameters in each example.' -Steam i dumps are - aligned normall y .f or plant condi tion Include.setpoants where icpplicabl Consider each _ case _ separatel y. Assume no operator a,- t i on .
' Reactor. trip..from.20% powe 'b . ' Turbine trip:with plant'at 45% powe ; Plant at 559F, zero powe (***** CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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PAGE- 30
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- QUESTION ~ 13.06 ( 1. 80)'
For.each' of'the below rod contr el interlocks state 1-11.--The setpoint
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~ .Whether rod withdrawal as prevented ~in auto, manual o r--. b o t h - -
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QUESTION 3.07 (3.40)
Give the BASIS for each of the following Reactor Proctection and Safeguards Actuation System protective action INDICATE which of the actions can be blocke Identify HOW and WHEN the block is accomplishe include SETPOINTS where appropriat a. Source range High Flux High pressurizer Pressure OP Delta T Pressurizer l evel High l
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' QUESTION 3.08 ( 2.' 80 )
. Ancwer'each o{ the f ollowing' concerning the Emergency. Diesel Generator :c. When the-Barring Device is installed can the diesel still be r o t a r t e d .-- Explain your answe (1.00)
b.: After an Emergency start whatLthree (3)' automatic protective oignals can stop the diesel generato (0.60) The solid state emergency generator load sequencer prevents overloading the diesel generator on a loss of power to the emergency-bu List automatic actions:and equipment affected~when thi's occur ~(1.20)
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3:__1N@l69MENIS_@ND,CQN1696@ 'PAGE' '33 '
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. QUESTION _-3. 09 (2.20)
c. Briefly explain HOW neutrons produce current in a Source Range (SR)- ,
Excore Nuclear Instrumentation (NI) system detector.. Include both nuclearJand electrical reactions wi thin the detecto ( 1. 00) -
b.- A reactor ~ shutdown'is.in progress with the SR detectors reading-about 10,000 cps and both Intermediate Range (IR) = detectors reading 1X10E-11 amp Tel.' minutes later the SR detectors read _about_1,000 cps but the .i
, IR detectors still read 1X10E-11 amp WHY does'the IR detector output remain the same? (0.60)
4 The plant is operating at 100% power with-N44 out-of-servic If an automatic reactor-trip occurs and N43 is f ailed as is, WHAT affect, if any, will this have on the NI-system's ability to monitor neutron flux
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as the plant is stabilized in Mode No action is take (0.60)
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QUESTION 3.10 '(2.40)
MATCH the ESF' Status' Panel. group description from-the right hand column with'its respective Group number from the left hand colum Only ONE (1)
doctription matches each Group numbe '
o.' Group I- 1. Consi sts of lights for those components _whose status is changed'during a CDA Group II 2. Consists of. lights covering the steam system
.c.~ Group III 3. Consi sts of lights that.only light during the injection phase Group IV 4 Most of these lights should always be off; however, some may illuminate during special or infrequent operation e. Group V 5. Consists of lights _for those components whose status only changes when in the cold leg.recirc phase f Group VI 6. Consists of lights that are normally off and will come on after an SIS 7. Consists of lights for those components whose status only changes for the hot. leg recirc phase B. Consists of lights for those compon2nts whose status is changed during the cold leg recirc phase and remains in the hot leg recirc phase ( * * '4 4 * CATEGORY 03 CONTINUED ON NEXT PAGE *****)
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- QUESTION. 3.11 (2.00)
HOW WILL the Cold. Overpressure Protection (COP)_ system respond if an operator._were.to arm both-Trains while hot l eg wi de-range RTD 'TE-413A i s
' failed LOW? Include in your_ answer WHY each Train i s -OR .i s not affected Assume
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'bacause'of the RTD failure, and WHAT automatic actions take plac the plantris shutdown at'3OO F and 700 psi i l
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, apply only to the first ste Unless otherwise specified,.a required task need not be f ully-completed before proceeding to the next instruction; it is enough to begin the task and have some assurance that it i progressing satisfactoril c.' Even after a transition to another procedure, the steps begun before the transition was made must still be complete d .- Once a Functional Response Procedure (FRP) is entered due to a RED or ORANGE condition, that FRP must be completed, unless prompted by a higher priority conditio i e
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s 4 PROCEDURES - NORMALg_ABNQRMAL1_EMERGENgY_AND PAGE 36 69919L99199L_G9NI@gL
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QUESTION 4.03 (2.50)
Lict the FIVE conditions that support or indicate Natural Circulation (NC)
Flow as stated in EDP 35 ES-0.1 Reactor Trip Response (step 9). Include pcrameters and trend (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
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QUESTION 4.04 (2.00)
Liot the six (6) Critical Safety Functions IN ORDER FROM HIGHEST TO LOWEST PRIORIT (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
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QUESTION 4.051 (2.50)-
Tho following' concern Departmenti instruttion'No.:3-OPS-3.07 on' valve
'op sr a t i on . -
!d.- What :are -the ' FOUR requi rements regarding manual sea t i ng -!( h and wh eel
~ closure) ~of motor operated valve (0.80)
b .c 'How are manual. valves. VERIFIED OPEN during. performance of..a valve lineu Include all required valve operation (0.90) lWHAT . action must: be perf ormad pr-i or to pl ant. cool down ' f or a '
backseated' valve? WHY i s this action necessary? (0.50)
d, < WHO-can. authorize.b'ackseating.a valv (0.30)
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'4 __E6QCEQUBES_;_Ng@d@(1,@@Ng60@6t_EDE6GENCy_@NQ PAGE 41-18091969GICB6_CQNI6g6
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OUESTION 4.06 (3.00)
LA condition: arises which requires entry into containment while. critical at 40% powe The operator entering will receive a whole body dose of 4 mes Data'is available on the f ollowing persons:
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Ccndidate 1: 2 3 4-Sax male male female male Ago 27 3 .Otr/ exposure 270 mrem 970 mrem 475 mrem 900 mrem Lifo exposure -
54730 mrem 5200 mrem 9770 mrem Rsmarks history -
4 months -
unavailable pregnant Each candidate is technically competent and physically capable of perform-ing the task. ' Emergency limits do not apply but time constraints do not permit obtaining authorization for an exposure limit increas For each psrson indi.cate if that person could or could not be selected to perform the task based on exposure requirements only and justify your
.rsspons Use Millstone exposure limit Include all requirements or limits that appl (***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
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. QUESTION' 4.07 (2.00) .
' State'the. ACTION 1 required by OP'3202-Reactor Startup, if f the f ollowing'
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Jconditions'are observed-during a Startup. . Include, times as appropriat .a. : Lowest"loop Tave-less than'551 F- (0.75)
b.- Unexpected' increase in' source range count rate (0.25) Reactor, critical below Rod' Insertion Limit
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(0.50)
d .- Reactor not c'itical r at MAXIMUM rod position per ECP .(0.50)
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'Be9196991966_G9NI696
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- . QUESTION- k.08
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.Ths plant has experienced a-reactor' trip and procedure EDP 35 E-0, REACTOR
[ TRIP - AND SAFETY INJECTION,- has: been entered.- 'Per.the EDP 35 E-O'
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FOLDOUT page answer the f ol l owi ng , include. appropriate setpoint numbers and-adverse containmen . State the. reactor coolant' pump trip criteria.- (1,00) WHAT-are the'SI actuation criteria *
(2.00)
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k ' PROCEDORES - NORMAL _ABNgRMAL t _tEMERGENCY _AND ~PAGE1 : 44 599196991C66_C9NI6g6
.. ,
'i y iOUESTION':4.09 . (3.00)
Ancwerithe:following questions concerning procedure,AOP-3566,' " Immedi a t ,
- Boration" 4
'
s.--l WHAT;. are the . F IVE 1( 5) entry conditions for-AOP-3566?. '(2.00)
b.:.WHY~is0Immediate Boration charging flow required =to be.< 233 gpm? (b.SO)
~
'
c.lWHY is'Immediate-Boration charging flow required to be > 33-gpm? (0.50) >
s e
(***** CATEGORY 04 CONTINUED ON NEXT PAGE *****)
- . , _ _ . . _ . _ _ - - . , . . _, _ _ . - , _ . _ . - . - , . .._
o , ,
%
14[ PRO'CEDUR'ES - NORMALt_ABNQRMAh__EMERgENgY_AND -PAGE 45 60919L991CeL_CgN16Q(
.. .
QUESTION 4.10' (2.50)
-A plant heatup'in preparation: for startup is in progress _ Plant tsmperature-is 325 F with a heatup' rate of 50 F/hr. When the operator ottGmpts.to open the "D" safety injection accumulator discharge valve
~
' it will' notEopen. 1The Maintenance: Supervisor informs the Shift Supervisor that'the valve is mechanically ~ damaged butLrepairs can be-
-compl eted wi thin 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> The Shift Supervisor declares the "D" accumulator inoperable and tells the Reactor Operator to continue the
-
haatu Expl ain -WHY the heatup SHOULD_or SHOULD NOT continue and
.
WHAT ACTION, i fEany, is.necessar (***** END OF CATEGORY 04 *****)
(************* END OF EXAMINATION ***************)
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o =,og 5 = Vo t + 1/2 a t2 E = ec 2 KE = 1/2 av 4 = (Vr - V,) / t A = AN A = A o ,-'t PE egn V f = V, + at * = e/t x = gn2/ t1/2 = 0.693/t1/2 y . y ap
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- i = 931 m
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pwr = w e I = I, 10-*/U L f
l i/L = 1.3/u p = P 10 sur(t) e;VL = -0.693/u P = P e'l .
l SUR = 26.06/T SCR S/(1 - K,7f)
'
CR x = S/(1 - K,ffx)
SUR = 26o/L' + (a - o)T G (1 - X,ffj) = G2 II -
eff 2)
T = ( t*/s ) + [(a - o )/ o ] M = 1/ ( 1 - X,ff ) = CR) /CR, T=1/(p - 8)
M = (1 - X,ffo)/(I - K,ffj)
T = (8 - o)/(lo) SDM = (1 - K,ff)/K,ff a = (K,ff-l) A,ff = Merf/K eff t' = 10 sgond T=0.1 seconds'j o = ((1*/(T K,ff)] + (E,ff/ (1 + T)]
Idlj=Id P = (I+V)/(3 x 1010) I)d) 2 .2 7d222 2 I = oN R/hr = (0.5 CE)/c (meters)
R/hr = 6 CE/d2 (feet)
Water Parameters _
Miscellaneous Conversions 1 gal. = 8.345 lb I curie = 3.7 x 1010 dps 1 gai. = 3.78 liters 1 kg = 2.21 lem 1 ft* = 7.48 ga I hp = 2.54 x 103 Stu/nr Oensity = 62.4 lbm/ft3 1 ,, . 3,41 x 106 Btu /hr Oensity = 1 gm/c:n3 lin = 2.54 cm Heat of vaporization = 970 Stu/lom *F = 9/5'C + 32 Heat of fusion = 144 Btu /lbm *C = 5/9 (*F-32)
1 Atm = 14.7 psi = 29.9 in. H BTU = 778 ft-lbf 1 f t. Hp0 = 0.4335 lbf/i .
, FRPCEDURC5 - NORMAL. ADNORMAL1 . EtjER(piijgf _ AljD F ABic 6~
86DIULOUICM _.C[WIF E
.
-4 NEWER 5 - MILLSTONE 3 -87 /12/1 S-PR J 6GS / is IE bE ! T Ai45WER 4.09 (3.00) control b an k- hei cin t below the low-low limit
- f a i l ur e o f %.vtvu -
or more control rods to fully insert following a reactor trip of chutdown
- uncontrolled cooldown of the RCG following a reactor trip of shutcr m
- uncontrolled or unexplained reactivity addition (i ndi cated by atanorm+
control bank insertion, increasing Tavg, or increasing nuclear power >
- ' failure of the reactor makeup control system E5 / O.40] > '
~'d .
' +,e-A!Pid m rb (0.503 (y P N.B Q czc02yat$t Th Chctry21,y (LLWfr r r evidr- a minimun rate of negative r eacti vi t y insertion (CAF) [ U . *- 0 ]
REFET;ENCE
M 3 1 1 r,t on e . Eun A66-02 -C-OO1,002,004 M111 steno 7 AOP-3566 pages K/A 00002.4 EK3.01 k/A 000024 Et:3.02 OOOO24K302 OOOO24k301 ...(KA'S)
AN St< tiR 4.10 (2.50)
A mede c h a r.o e cannot be made with reliance cn an LCO ACTION ETA?LMENT f1.00].
The plant wi11 enter MODE 3 at $50 F EO.50 The_heatup must be stoppedht - 350 F EO.bOS until tiie valve c at . te madr operebic EO.50 REF CREtJCE TS 3.5.1 pg. 3/4 5-1 TS 3.0.4 pg. 3/4 0-1 K/A 006 000 G5 3.5 AND Gil 3.6 SYSTEM GENERIC Enabling Objective TSG-01-C-OO2, 012 OO6000GS ...(KA'S)
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PRINCIPLES OFJNUCLEAR POWER' PLANT OPERATION t
~
PAGE: 4e
-
'. 1
'IbE6DQQYN@DICgt_UE91_169N@EE6_gNQ_[LUlp_ELQW
-.:,
' ANSWERS 1-- MILLSTONE-3 -87/12/15-BRIGGS /BISSETT ANSWER 1.01' (2.50)
-c.~ 1-INCREASE 2-INCREASE >
13-INCREASE- -E5 X O.25]
. .4-INCREASE 5-STAY.THE SAME
'
'b.= 1-DECREASE 2 INCREASE 3-INCREASE C5 X O.25]
,. 4-INCREASE 5-I NCRC ^,C-C l
Spy THE Shri- 2'y .
REFERENCE
- Mi'll stone 3 "Reacti vi ty Operati ons" Lesson Pl an ,
Millstone 3 EOs RTJ-01-C-OO6,73 RTF-01-C-OO7; RTE-01-C-OO6
.K/A 192OOOK121 K/A 192OO8K124 3. 5 -
J192OOOK121 192OOOK124 ...(KA'S)
~
ANSWER 1.02 (2.00)
~ Press = 58 psig [0.'50]
Flow- = 93'gpm [0.50]
b._ Press = 80 psig EO.503 Flow = 117 gem EO.503 REFERENCE
'HTFF Fundamentals Ch 12 "Fluid Flow Applications", pages 33-36 Millstone 3 EOs HFE-01-C-OOS,006 Millstone 3 "Fluid Movement" Lesson Plan K/A'OO4000A4.02 3.2 l K/A OO4000A4.03 K/A'OO4010A3.02 OO4000A402 004000A403 OO4010A304 ...(KA'S)
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< b l *. PRINCIPLES OFc NUCLEAR POWER ~PLANTsOPERATIONt- 'PAGE' g?r. ,
>
. THERMODYNAMICS t _ HEAT TRANSFER'AND FLUID FLOW '
b).:
'kNSWERS1-- MILL' STONE'3 ~87/12/15-BRIGGS /BISSETT'
,
'
,.
<
.
'ANSWERI : - ( 2. 00')
-
1, l-, .
.. ... .
e s, ,Tsat for-2250 psia (2235 psig) . [0.503
= 652.67 '
[0,503-
.SCM = Tsat - Thot = 652. 715" - 617 = 35. 715'. . [0. 50 3 ' .(.
L 47? .G7 -
,. . b.'- 'SCM will: increase [0.503 1 REFERENCE Steam Tables ,
Mi'lIstone!3 Text "RCS" pg-33 ."PZR'f, PRT" pg 16 HTFF: Fund, Ch'3'"Thermodynamics", pgs 43-51 Ch 13 "Natural Circulation", g:,g 4 Mill stone 13 EOs. HFE-010C-OO6 4K/A'191004K114 :OO1000A106 OO1000K503- 015000A102' .' . . ( K A ' S )
. ANSWER .1.04 (1.50) FALSE-[0,50)
" FALSE: [0. 50 ).
c .~ TRUE EO.50J
. REFERENCE ~
.tiIL.LS f GNE 3 EOsi, RTH-01-C-OO6; . RTG O1-C-OO)
MS 3 Delayed Neutrons Lesson, Plan, page 23
- MS 3 "Neutron Sour cesi and _ Subtri ti cal Multiplication" Lesson Plan, pages;11),13,22 -
-K/4 0101OK506- 'OO1010K508 ...(KA'S)
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J Fa .'m
IUEMOL4 JOLW LEM_1EJt"$EELONO.lL! LID _.B6.')h2-lA blii W E.h b - - Mll L61 Uld 3 --87 / I 2/15-l'R16th / htlESE TI ANSWER 1.05 (2.75)
9 .PCC4.we-th decreases (0.503; ot+ fusion l ength decr eas-ns (thuc neutron'
travel lems) 0,252 so are 1ess 1 i kel y to be absorbed in a control rod L O . 2 5.: . FCCA Werth decreases [0.50]; more cornpeti ti on betweeen bor on and RCCAe; E0.15 RCCA worth de e c ene5-m 'LO.503; fuel denletes over core cycle t x)
and baron concentration decreases at well ,J ]~~ 2 ; petg g p, [gft,g ,pgj,9 v
w.nw j REFERENCE h w ardy k (,d jNe
! MS 3 Neutron Persons Lesenn P1an. pages 11-16 (CeO7 MS 3 EOs RT I-01 -C- OO i ,
2. 9 fdp9 (h K Gtf f
K/A OO1000K507 [L -
K/A OO1010KSO4 ffdho,.y[d K/A 001OOOKS30 . O O 1 0 0 0 V.5 0 2 . OO1000K530 OU1010K504 .. (NA'El AllSWER 1.06 (2.00)
1.
I Less Negative CO.253 because '; n e fue' ten:perat ure coef 4 i c ) e nt ('TCi beccmes leus negative as fuer temperature (Rx pawnc) increenes f. v . 5 0 3 .
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REFERENCE l Mi l l s t one 3 "Reac ti vi t y Coefficients & Defects" Lecson Plan, pg 9 Millstone 3 Reactor Theory EO 85 (
K/A 192OO4K107 OO1000K549 ...(KA'S>
l Leoo up d a co.as] = & MQ4 l pse ome Gm G.aso c,ueo FTc +m Jeu-l m
'
Co.xT3 fck Wo leoup WbM
& ()MCJ28 fcs&A chtege frecenco h kus * fb wh, pen co u 3 we'$
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a- n a
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-* / PRTNCIPLI.E UF NULL EM;_F Oli ER_PLANLOr1.; ROT.10S, f *ee d ,
TH5':K'OYU901c s, _)jliOLlBGMtE B_O99_EL(IIl _ELOt1 dN9WLilS -- M 1 LLt 1 UN': 5 -ti? /12/ lir UF:ICGE /1 1 L t:E I T ANSWER 1.07 (1.50; Decreate LU.253; more heat is e:trccted LO.2S3 Decreccc LO.2S]: decreate in feedwater temperature EO.25) Increare LO.253; m:derator dtncity decreasco L O. I'5 3 REFERENCE
'}I M1]Irtone 3 "Pla t Cycle " Lesson Plan M211 stone 2 Text "Circulating Water" M111utone 3 EOc CUE-01-C-015,16 f./ A O O '.)O O ! f.l: 1 0 T !.G K/A OOOOOSEF.105 % 103 OOOOO5K105 .. 0;O'S)
(iN E le E R 1. OEs (3.00) . Increase LO.50] Increesa LO.50] Decreanc 00.50) Dec r ea s c- LO.50]
l Dcpleticn of U-235 [0.50]
DuiJduo of Plutonium (Fu 239 S 241) LU.50]
REF ERENCE Millstone 3 "Bailing P r oc oc s n e t; " Lescon Plan, page 24 Millstone 3 "Delayed Neutrons" Leeson Plan, page 9 M311ntone 3 EO'c Hrl-01-C-OO41,005 K/A OO1000KS2O 3.,
K/A OU100CK526 3. Er K/A OU1000K530 OO1000K518 OO1000K528 OO1000K530 ...(KA'E)
I
. - .
-
.
-
l h,,,_PRINCIPi,ES OF'NUCt. EAR POWER PLANT OPEPATION,3 F A lHERMODYNAljlGE;, _t%[q_TRANSEE B_AtjD_ELUlD_ELOW
.bH514ERS.-- MILLSTONE'3 -8//12/15-BRIGGS /BISGETT
.
ANSWER 1.09 (3.25)
.
After the power increase, xenon concentration ini ti all y decreases EO.503 since the removal.of Xenon by decay- [0.253 and burnout. CO.253 is-greater-than the production of Xenon f rom fissi on [0.253 and the decay of Iodine LO.253. After appro::imaterl y 5 (4-6) hours [0.253, the production rate te greater than the removt.1 rate and Xenon concentration increases [0.503 until equilibrium is reached after about 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (0.503. The new equi 1ibrl'um Xenon ic approximately 1.25 (1.15 - 1.35) times the criginal val ue (0.50)
REFER:E NCE l
'
h 11 stone 3 "Xenon & Samarium" Lesson Plan, pager 19 Millstone 3'EOs RTK-01-C-OO4,005, K/A OO1000KG33 K/A OO1000K535 OO1000K533 OO1000K535 ...(KA'S)
ANSWER 1.10 (1.50) In 10 tec, delta rho = (20pcm/ step) (30 stcpe,/ mini (1/6 min) eiOO pcm Co.503-1 SUR u 26(O.1 sec (O.001))/(6E-3 - E-3) E0,503
= 26 (IE-4)/5E-3
- = 0.02 DFM EO.5C3 l REFERENCE
!
Millstone 3 "Reactor Operations" Lesson Pl an Mi lletone 3 EOs RTG--01- C-OO6 h/A OO1000A106 K/A 015000A102 3. 5 OO1000A106 015000A102 ...(KA'S)
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' .J r.i._EBUSICLEE QE._UUCLEGB_COWEn_ PLOUL.OEERQTlgN, PAGE- Er IUEBdQQyN9(1106,, HE91.T66NSEE0; OUD,.ELy1D EL9W -
.. ..
ANSWEb;5 --' MILLS 10NE 3, -87 /12/15- BRICOS/B I SSETT
,
,
a; ,
ANSWER- 1 . 1-1 '(3. 00) MORE. NEGATIVE.[0.50]'There is less baron to lenva the core area
.per degree chance of coolant temper;atur CO.50]
'
, . LESS NEGATIVE CO.50]'Tiw cheng'es i n r esonant absorption by~ U23E
'
become less negative'as temperature increases. 00.50]
c. . MORE NEGATIVE [0.50] Baron c.oncent rat i on decreaten,,reculting in
- - .a more negative MTC. I.O.50]
w ,
F-REFERENCF *
'
Millstone 3 Reac t i v i t y Coefficiente L Defects p a g e r, 10-26
.
(, Mr11ctone 3 EQr R'f J-01-C-OO3,006; RT I --01 -C- 001 l ' K/A
'
UO1000KS15 K/A GO1000Kb!8
< 001OOOliS15 UO 1000K5301 ...(KA'S)
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3 . [1 AU ' .El?lf O_}!GL'='PME. iici [EJ Y._OUR El1EOGE;[f.'y. ' dis 1 fiM5 I~ r E
'
ANSWERS --- MI LL S'l ONE 3 --G7 /12/ I S- DR I COS / B I N.T T C/.Go]
Alt- WER ?.01 c:....- FALEE [0.5) '.
TRUE
"' '
LO.5]
- _2
k
[ FALSE C O. 51 REFERENCE r111Istone 3 EOt F' AS-01 -C-OO 3. 4, 5. '/
M111 s t one- 3 Text "Inutrument Air" peges ?-9 i /A 078000K104 e/n 07E,000K 0' } . / ,4 0791.01:401 U/ eOO% 1 e '. 07EnOOK104 e/YOOOK401 ...'NWS)
ANSWER 2.02 (2.75) s FO!H TRAlN 4
' NE]THER B0111 f9CITHER ea . T R A I r! B
'
. TR'M N A CO.25 each:t . Containment e:r recirculat~1on coolers (W
?. Netttr on shield tank coolern (( W MC)$O]
~ C&EctL&n2AE OS C Msy)Lm)
REFERENCF_
Millstone 3 Tent " RPCf'W " , paces 2-3 ili 11 stone 3 EOs CCP-OO5,015 K/A OOPOOOK401 K/A OO8n30A304 OOBOOOK401 OOB030A304 ...(KA*S)
f
L ._Ill O C U .P M .1 G E!.. 1 L"- L U P.I. U S ; g O F E ' _ OUD_fitjf; R(iEbjC y_t3iSIEL15 PME * J-N!5WERS - MJLLSTUNE 3 -87/12/15-BR]GGB/EsISSETT ANSWER 2.03 (2.00) . Low cuttien pressure CO.40]
2. Low lobe o)I prescure [0.40]
3.Susteined undervoltage on bus 34C CO.40] [ 6, if G 4.Feedwater i sol a t i on trip signal [0.40] 1 6. Ycb 0MNe,$ LAM (GW, L Y) O %) Pressure is not high enougli. 00.40] .
REFERENCE io 11st one 3 Text "Feedwater", pager '.6,15 Mt i1 stcr.e 3 FP s F Ld E ' ' l -C - 03.10 K/A 05V00 0'.416 3,1 M / (> 05900'#103 '.1 OO3OOOA20; ...(Kn'E)
PNSWER 2. O 'l ( 1,50i c. . Encurer that the 51Pc and the CCFr have a suction supply of water E0.50] de tr i ng th> cold log and hot leg recirculation modet of operat)on [U.'be]. Prevents apurious or anadvertent valve movement (due to contre)
circuit l >robl emt n- un i n t er' t l an a l operator action), f0.50 PEFERENW M1]15 tone 3 fen:t " E.C G " paget 15,34,41, Mi1. stone 3 ED+ L-01-ECC-OO5,032 P / A 0060005:406 ' .9 F' / / - 00 $000 A 40 ? eO5000):40', OObOOOKSO9 ...(MA'5)
.-
..
{
d[_..EL 6dl [6210N_ltiCLUC 1 NG.J.%F ETy _OL!If E MEBGEjl1 ShlEtjg F :. E 54 f}NSWERE -- MILL 310NE 3 -87/12/15-DRIGGS/DICEETT ANEWER 2.Ob (2.75) Unabic to meet single failure criterio.EO.50]
.2 Sufiicient inventory for core reflood. [0.50]
.3 Less volume for nitrogen gae LO.25], therefore suificient water injection may not occur 00.253.
( .4 Hich pressure gcis forces more water into the RCS before blowdown 1:
complete thus ]ess water is availab]e for core i 1 codi ng . 0 0. 50.!
g Accumul ator tank being filled. 00.25]
RCS in1eakage CO.25J Faalty praesure regulator. FO.25]
(t here may be o t h e r t, >
FEFERENCE Millstone 7 Tent "ECCS" pages 46-4D Millstone Z Technicel Spccificationn MI1] stone 3 EOc C-01-ECC-OOS, 015,040 K/A OO6000K'iO2 .?.8 K/A OO602OrLO3 h/A OO6020A107 .3 OO6000K502 OO602CA107 006020K603 .. WA'E)
ANSWER 2.OG (2.00) Minimizo reaction forces (reduce pipe whip). [0.501 Minimize mass flow rate that a main steem isolation val ve inust c l am against. [0.501 Reector coolant system cooldown rate is limited.[O.503 e a s ur e steam flow rat [0.50]
REFERENCE Millstone 3 Text "Steam Generator" pages 16,17 Mi11 stone 3 EO MSS-01-C-001 U/A OOOO40EK106 K/A OOOO40EK202 OOOO40K106 OOOO40K202 ...(KA'S)
l
- .- - - _ a
. _ _ _ -- . _ _ _ _ _ _ - _
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F ' "* 2 R [hNSWERS _b--1.MILLSTbNE 3 --87 /12/15-BR I GGS/ B I SSETT '
.
) :,
i t
F tiNSWER 2.07 -(I.50)L EDG/hasito come;up to: speed -(10 seconds). [O~503 .
-DSLpump. breaker timo: delay- . (;.5 seconds) [0.503 109: header:has to-beif111edL ;(45 seconds) [0.503
,
LREFERENCE . .
' MILLSTONE 3' TEXT "CLA" pages,2442b
.
- MILLSTONE ~3 TEXT'"QS"' page 8
~MILLSFONE-'3 EUs CDA-004,008,023, K/f) 026000K301' - }D A 026000K401 K301 026000K401 ...(KA'S)
'
' ' ONSWE .2.08 .(3.00)
/
({,CQ M( g G .
s
,.
REFERENCE Mi1!s3t' one 3 EOc RWA-02-C-DOO,001,004
'
-
WYO d4 DIM 4 tc . .
Mi11 stone 3 xt "AFW" pageu 9,12,1/
K/A'06100^s101.L {g l -K/AJO6 :OOK107'3.8-
.K/A i LOOOV402 OA'OOok101 061000K107 061000K402 ...(KA'S)
. ANSWER 2.09 (2.00) Significant hydrogen production occurs-(increased chance for
.
explosion) CO.503 . Kirk. Key interloc [0,503 c Air start solenoid valv CO.503 d.- No CO.503 REFERENCE
.Mi11 stone 3~EOs 125-02-C-OOO,003 iM111 stone 3 Text "125 VDC System" pages 3,4:"Diesel Generator and Support Systems" page 5 Millstone 3-ADP 3563 Attachments A,B,C,D page 1 K/A 063OOOK103 ?M/A-063OOOK301 .K/A 063OOOK302 'K/A 063OOOK502 ...(KA's)
l_063OOOK103 063OOOK301 063OOOK302 063OOOK502
,
!..
1 o, mi, eveveue n e e , r- u e- n , n n , m.in , ,- , m - .. . . m.,
zu___=_a__=a=_=_=_===_=uu_==u_u==t_su=_suesuxuuusu;twu -P AGE -- 4 9
ANSWERS -- MILLSTONE 3 -87/12/15-YACHIM1AK, l'Ta , i;. ')Tct
.
,2.C9 (9.cc)
ANSWER -6.01 '2.00) dU I charging pump 0 0. 25 3 EO.qb,] .
1 saf ety inj ection pump CO25](b.96)
1 residual heat removal pump M CC'*1 0 3
. cl ose the reactor trip breakers ?O. 55] G). b'C )
c.-RCS overpressurization COT 35: ot cduc;d CCS i m,,,p e r a t c c ; CO.352 r - m gb
-
REFERENCE 7/,[h _
Millstone 3 EO ECC-02-C-010; RPS-02-C-018 Millstone 3 Text "RFSAS" page 65 Millstone 3 Technical Specifications pages B 3/4 3-3,4-15,5-1 K/A 006000 K6.02 K/A 006000 K6.03 3.9
, K/A 006020 K4.06 4.2 l OO6000K602 OO6000K603 OO6020K406 ...(KA'S)
ANSWER ,
6.02 (2.40) , // [f . q: . C6 X O.,403 C . ,
./ . , .
l REFERENCE'
Mill stone 3 EO ECC-02-C-OO6 Millst'one 3 Text "ECCS" pages 86,87,120 K/4/ 013OOO A3.02 A302 ...(KA'S)
!
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3:$ .fLGlfl DES.I g tL, J tg.lypl W _g G EE l y .O!S!!_Kt}EiR(jhtE Y_Sy 5lgt!h FME %
. A,NSt0hES -- MILL 510NE 3 -87/12/15-ERIGGS/BISSETT A11SWER 2.30 (2.50) gas CO.333
/ particulate L O . J.3 3 3 lodine CO.33) S/G blowdown -p r oc e n e: stream 1s isolated 2 TB drains -process stream is diverted to LWS 3 Liqu2d war.te process stream ie isolated 4 Au::iliary condensate process stream is diverted to aerate:i drains 5 RPCCW -none 6 CVCS -isolates letdown 7 Containment recirc cooler serv 2cc water-none 5 X (0.30)=1.50 REFE fiENCE Millstone J. T ex t- "Radiation Monitoring" pages 2-4,14-1S,43-44 Mil 1 stone 3 EOs RMS 01-C-OO7 K/ A 0730 DON 1'il K/A 073OO3K201 1.
073OOOK101 073000K201 ...(KA*S)
ANSWER 2.I1 (2.00) Prevent charging pump from overheating during ocricar cf low f l ot operation.FO.eOJ Seal water heat e:: chang er . 0 0. 60 3 RWST.00.603 REFERENCE tiilletone 3 Text "CVCS" pages 13,14 Millstone 2 EOs C-01-CHS-022,023 K/A OO4010K606 OO4010K606 ...(KA'S)
. .. ~ .. . . . -. . -. - -.- . . . , - , . . . . - . .. . . . _.-, -
'
, VE ,
.
-
-
- b[ neti1LUE51EN_AUGLWD10G_.00EEIL889_EL1ESEENGi_.SYSICMM BASE '5e fd5WERG - MILLBTONE 5 - 87 /12/16-I.
- R I GBS /111 SEET ,
- ANSWER 2.112 (1.00)
,
Supplies -servi ce air duri ng 'a lonc or' decrease 'of. instrument air,' precsuit
-
> : EO.~ 503. Maintain the quality of f air by first directing service' ai r thorougg
,t.hc 'i rectrument : ai r dryer. C O. 503
,
' REFERENCE'-
t'i 11 stone 3- TextL "Instrument . Ai r" pg . 9
-
M111stono 3 EO PAS-01-C 005
'.- K/A 079000K401.2.9=
679000K401-
'
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.
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-87/12/15-BRIGGS /DISSET]
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ANSWER ':
f 3.ul; _( 2.20'
E
_ .Lt; vel (wi l l decrence:EO.50 Feedwater f } ow wi l l ' decrease. - C O. 30:! ' when a ~ -
- _
'
l arg^e ' l evel : err or . si gnal . i s generated E0.30 The reactor will t r :, p on fcu
.risam genorator level ~CO.503.because'fer?d-flow remaint Iact than
'
!. steam flow [Q.50 [REFEFiENCE f; .
.MP3 NSSS Vol'.5 IhC Failure Anclysic pas. 80 & 81.- .'
. t.'i A - 016000).112 3.'S t
- i F./ A 01oOOOK312 3.At SGC-01 - C-OO!! - 6 .004 ,
J O l 6 000!O 2 '. Ol6000r.212 ... (r.W O ,
r-
!
i l -ANEWER 3.02 (2.701 *
l-
'
,
- c!. Thc e.ut omati c' control l er uses a hot calibrated level instrument -[ 1. 00 3 -
.
b.: . Ensures ide:;uate watAr i n v en t or y ., - [0.503 l 6-
'
u f'r essur s .' er. '] ev el - i c. ' pr oc4r ammed to vary' based on auctioneereo hign
'
[
'
- loop Taye elgnal CO.40 Ac power increases .f rem nc 1c.2d the ' programed *
pi an.t- Tave increases which generater a 1evel error si gnal CO.40 Tho i level errer. signal willicontrol the charging pump flow control vElve tc
- i ncet.ase . l uvel ta the decired ve]ue E O . 4 0 ' .[
a Y
REFERENCE !
MS3 Cys. Descriptien. Vol.4, Pressurizer Presc. ' & Level pgr. 20-21 ,
~ K/A'011000K407 Dok401 ;
Pr eusor i z er ' Pres.t . b Level Control EO PPI-Gi-C-015, 026 b 027
.011000K407
'
011000K403 ...(KA"S) :
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?
IW' M AN5WERS -- MILLSTONE 3 -E7/12/15-E.RIGGE/1ISEEfT ANSWER 3.v3 (2.00) Heated junction thermocouples (HJTC)EO.25). The output of the HJI' f .e compared to the output of an unheated Reference lhermocoupie t t c ) [ O.1: v 2 If the output of the 1JTC is sigificantly higher than the reference ?-
the system considers the censor to be uncovered (0.50). Level in the vessel head E0.25 each]
Level in the upper plenum {
,m_r temper at ure of the unheated thermocoup)es REFERENCE lF 3 NES5 Vol.4, Incore Tc System an ci RVLHC. p a n . el - 1 EO ICC--01-C-013 AND 002 K/A OO2OOOK107 3.54 GO2OOOK402 s.bt OO2OOOK402 OU2OOOK107 ...(KA'5)
ANENER 3.04 t .50)
FALSE EO.503 REFERENCE MP3 NSSS Vol incore T c E v s t e m a n d P'.'L M.3 pgc 4-10 EO ICC-01- C--v12 and 002 K/A OO2OOOK107 3.54 OO2OOOK402 3.5$
OO2OOOK107 OO2OOOK402 ...(KA'S)
ANSWER 3.OS (3.00) Steam dumps will arm and actuate to reduce Tave to rio l oacJ Teve of 557F EO.75 Tave - Tno load (fixed signal when reactor trip is sensed) [0.253 Steam dumps will arm and actuate to reduce Tave to Tref (no load this example) EO.753 Tave - Tref (first stage pressure) EU.25] Steam cumps are armed in the steam pressure mode and will actuate to reduce pressure to 1092 puig EO.75 P pt 507 - P setpoint EO.25 REFERENCE MS3 NSSS Vol.3, Steam Dump, pg .
C-01-SD5-010L 015 K/A 041020K417 K41E .IUOT RUL%Uly._OND .CCNT SOLM ; 4 H A JEWERO -- MILLS i ONE 5 -87/12/15-FRIGG5/EISEFTT v41020K416 0 91 '>2u t .417 . . . OW 5 )
HNSWER 3.06 (1.60) percent power E O . ?.O each]
Auto and manuel Prevent nuclear overpowrr Intcr. Range percent bel ou OT-Del ta T varieble setpoint Auto and manual Eliminate cause of impending trip 15 percent powe hv Frrvent auto rou wi t hdr awal b ril ow 15 percent power cbi MWb
- " Y f(g3 h @/lke Y t OJ REFERENCE ,
ME3 NC.55 Vol. cf S a c3 $7 had Control System, pot. 57 anc Tablen EO C-01-ROD-OO9 K/A OO1000K407 3.7 001000K408 3.24 0010001:408 OO1000K407 ...(KA'S)
ANSWER 3.07 (3.401 F:ct i s Uncontrolled RCCA bank W)thdrawal ir om subcr i t i cal . [0.503 Black: Manuci LO.203 wher. W Int. Renge are above 100-10 Amps ( P - i- > LO,Jo]. / g Basi c: Fratect RCE and its components from ov er p r ei- sur e . E U . 5' '
-
Bloch Cannot be blocke [0.20]
Basis: Frot ect s against excess KW/FTQnd I. O . M O high -f uel tem Elock: Cannot be blocke [0.20] . Basis: Backup overpressure protection and to prevent water discharge through safety valve LO.50]
Block: Auto blocked (0.20) at less than 10% (P-7) [0.30]
REFERENCE MF3 N5SS Vol. 5 RPSAS pgs. 39-61 MP3 T.S. pgs. B2-506 EO RPS-01-C-020, 040 K/A 012OOOK402 3.9 012OOOK406 3.2 012OOOK604 OOOK604 012OOOk406 012OOOK402 ...(KA'5)
.
FmE o; A._ .INElSgt!fiMI5_ ONL_s;OSISOLE WsWERE -- MILLETONE - -87/12/1S-FRIG 65,'FISSETT ANSWER 3.98 (2.80)
a. Yes (0.20]. The diesel can be started by using the monual start lever on the Air Start Valves [0.00]
b. Overspeed f0.20]
Low lobe oil pressure EO.203 {l Generator differential current LO.2OJ (0 703 [o.L)
c. Strips all loads V encept (480 vol t) l oad center and (motor control center supply breakers) W the running charging pumps [0.$0].
Sel ec t ed 1rade are started in c predetermined sequence EO.40 Generates a manual start block signel EO 40 REFERENCE MET FDP Vol. 1 E nrJ .
Eupport Systemr. pgs. 14 & 19 MS~'. BOP Vol . 1 Diesel G e n er a t.or Sequencer pgs. 1 &2 U/A 064000K105 3.4 06400K402 En EGF-01-C 007.002.005 En 4KV-01--C-013 OL4000K402 064000K105 ...(KA'5)
ANSWER 3.09 ( 2 . 2 0 's a neut*'on and a boron interact to yield an lentred (+) lithium nucleus and an ionized (+) alpha particle EO.50: these lors create additicnal ion pelt s E0.25) which migrate to the detector 's charged electrodes [0.253 e C)Q eGll!c +200
"
[ X 10E-- 11 amp si gne) is used as a referenceV4cr gamme compensation Ev.ea] Sh detectors willnot be energized EO.60]
REFERENCE Millstone 3 EOs NIS-01-C-700-OO9,011 & NIS-01-C-702-014 Millstone 3 Text " E:< c or e N.I." pages 6,16,20.26 h/A 015000 K4.01 K/A 015000 KD.01 K/A 015000 K6.02 ...(KA'S)
015000K602 015000K501 015000K401 i
'f: .-. l ltH @,*[1E tjT W ,_6 t!D ,XQN 160l_5 PAGF_ C e;15 WF K.E -- MILL 5 TONE 3 -87 /12 /15-b R I GG 5 / B I 55ET'l ANSWER 3.10 '2.40)
.
44 . .t . . L6 X O.403 . . .
REFERENCE M57 N553 Vol. 2 ECCS, pages 86,07.120 K/A 013000 A3.02 ED C-U1-ECL-vo7,v10.011,012,017 L 014 013OOOA302 ...(KA'S/
ANSWER 3.11 (2.00) g &^ .
wi11"open b '
1ra)n U bl cc i: ve1ve sMV 8000B1 PORV (PCV-456) wi11 not open [O.4v]
.dCGtAt' 0% g Train A bl or i: valve (MV 8000A) will V opendO.403 v PURV (F CV-955A) wi1i open EO.403 becaune train "A" 01 COP s v
.c s .
. ,
PAOL_ 63-4 &__EEDCEDUBE5_ _UQBdDLs_6bN08d8L t_Ed?SGENCX_ONQ'
8901RL961086;CONIBOLL i 6
! ANSWERS -- MILLSTONE 3: -87/12/15-BRISGS/B195ETT
- ANSWE .01 -(2.50)
=h. standby instrument-ai shutdown instrument air [3 X O.333 cervice-b. . air.. pressure decreasing rapidly LO.50]
.
loss of turbine /+eedwater control-LO.503-c. use; oi S/G atmospheric steam bypass valves CO.503-REFERENCE Millstona 3' EOs A62-01-C-OOO,001 Mi l l s t on t- 3 ADP 3562 page 3
~K/A 000065 EK3.08 3.7.-
- K/A 000065 EA2.06 3.6*
OOOO65K308 OOOO65A206 . . . -(KA' S )
ANSWER 4.02 (2.00)
a.- ~ FALSE [0,50 each3 TRUE TRUE TRUE REFERENCE MS3 EDP Format and Use poc. 2.4 L 6 Enabling Objective for EOP format and use No.2,3 & 5 KLA 194001A102 Plant-Wide Generic 4.1 A102 ...(KA*S)
,
-- . . , ,
.
,
,
+
4 I bOEhkk'BESi2_bQfh663._ADdOBINn3 3 Ef1EBOENCE SND-PAGe? 6s-
-
- - w I CONIBOL
,
- -,f L8sDJ.O' DR G86L
'ANSNERS'--' MILLSTONE 3 -87/12/15-BRIGGS /BISSET1 o
- ANSWER '4.03 (2.50)
f
' RCS Subcooling -') 3OF- EO.50 each]. Core Exit tempero6ures stable or decreasing
.3.'S/G Pressures stable or decreasing 4. RCS '(loop) . Het Lec Temperatures are stable or _ decreasin . . R C S. (loop) Cold Leo Temper atures are near seturation temperature-for S/G Pressur REFERENCE EDP 35 ES-0.-1 Reactor Trip Response Enabling Objective No. b KLA 193OOSK122 4.24 2193OO8K17 ...(KA'S)
ANSl6R- 4.04- (2.00)
5 - Subcrsticality C Core Cooling H - Heat Cink P- Integrity 7 - Containment I Inventory E6 at 0.3 cach, 0.20 +or correct order]
REFERENCE MS3 EOP Development poc. S-7 EOP Format and Use Enabling Objective No. 1 EOF Development Enabling Objective No. 6 K/A 000029 G012 4.19/4.24
EI '
,
,
>24v
. . .
PRQCEDUGES_ ;NOBM81;328BNOddAL,,_EDEilGENC'y1SND Pt46E Li&
4- RADIOLOGICDL.tCONTRO ! ANSWERS - MILLS TONE 3 '-87/12/16-BRIGGS /DISSETT
. ANSWER 4.05 .-( 2 . 5 0 s
. .' Shift Supervisor approva < 2. Notification of Operations-Supervisor / Duty Office . Identi f i cati on on Shift . Turnover Shee . Do not use cheater ber [4 at 0.20 each] OPEN - Partially clone' Ev.30] open to backseat LO.303 then cloce one-quarter turn. [0.302 .
Take valve of + its. backseat CO.253 to prevent undue stress to the valve.Ev.2S] Shift Supervisor E0.303 REFERENCE Department Inst. 3-OPS-3.07, pgs. 3,4 L 6 K/A 194001.K1.01'3.6/ lK101 ...(KA*5)
ANSWER 4.06 (3.00)
candidate M1: rejected (0.25) since he har no history on filo end will exceed 300 MREM /QTR whole body exposure (9.5)
candidate M2: rej ect ed (0.25) since he will exceed the quarterl y limat ni 1000 mrem whole body without Health Physics Supervisor' approval (0.5)
l-candidate #3: rejected (0.25) since she will exceed 500 mrem whole body during the term of her pregnancy (0.5)
candidate #4: accepted (0.25) since he will not exceed the aumin limit o+
1000 mrem /qtr (0.25) or the whole body limi t of 10000 meen lifetime exposure. (.25)
REFERENCE SHP 4902 pgs. 9,10 & HP Form 4902-1 HP Enabling Objectives 14 and 2 K/A 194001 K1.03 2.8/3.4 l 194001MIO3 ...(KA'S)
l
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,
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.
-
- 982iESCCCP.USE6ii.NQ6MCG ,ABNORMACdEtjhS@EUQy,0N '
- E. nt;E : d, p- _,
' ~ 4.....'5 68ILIDL0GIGAL CONTBQLf
,
-
,
_
. ,
~
--87/12/1b--PRlUSS/D1SSE1 f
-
+<AhS0) R9'--LMILLETONE J- ,;.
ll; '
,e; ns
-
~
- ANSWER ~J4. 07f - (2. 00):
~
Cc>.my s%Qk - [0
.
a.:
- Increase Tave above 551 F1:in 15 minutes CO.::5L or Hot.O...--..g_in- _
m
-
-1nexty15 minutes ; .dk ' - .m m . .J P:: c'- ' ;; ;r ^ I '
. i..._ ;
-b.' 'Stop1and.invettigate r, (O.35) son. Ed.253 oc . -
'
Termtnct'eLGU and insert control' rods LO.'253. Borate 00'25 .
,
-?d . . Insert' Control. Banks EO.253 Recalculate'ECP E0.253 .
? REFERENCE OP.3202 Reagtor Startup, pga. 6,7'& 10 DEnablingcObjective'GO2-01-C-OO7,008,013 and 019
'
'
'K/ATOO1010A101'3.7 .OO1010A207 OO'1010A191 .OO1010A207 ...(KA'S)
,
Y ANCWER 4.00 ( 3. '00 ) INH OG '
- RCS pressure less than,1435 psia, and ]f c. 33
.Ai1Ieast one chatgir.gfor SI pump running: LN at h each].
- RCS-subcooled less'than 30 F por core exit Tc
'
b '.
-- (less~than 90 F for adverse containment) O Cannot maintain PZR LEVEL > 7% ~
[4 at 0.50'ench3
--
(>.50%.for adverse containment)
REFERENCE Procedure EOP.35 E-O Fol dout p '
EOF 3S E-O Enabling obj. 43
'K/ A: 000011 EA1'.03 4.0 o -K/A 000011 EA2.11 'OOOO11A103 OOOO11A211 ...(KA'G)
.
Q 7*/)dH%"N 7 %
i C
U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION FACILIlY: _ M.I. _L
_ __ L S _T _O N. _E _ 3_ _ _ _ _ _ _ . _ _ _
.
REACTOR TYPE: _PWR_-WE_C4_______________-
___ __ _
DATE ADMINISTERED: _87figfiS_______________,
EXAMINER: _Y9CHIMI9f3_ CANDIDATE: _h [___ y1 , _
INSIBUCIJgNh_Jg_C9NDID9]El Use separate paper for the answer Write answers on one si de onl Staple question sheet on top of the answer sheet Points for each question are indicated in parentheses after the cuestio The passing grade requires at least 70% in each categcry and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination start % OF CATEGORY % OF CANDIDATE'S CATEGORY
__Y96UE_ _Igl@( ___SCO6E___ _y@(UE__ ______________C@lEQOSX_____________
_22199__ _29199 ___________ ________ THEORY OF NUCLEAR POWER FLANT OPERATION, FLUIDS, AND THERMODYNAMICS
_22:99__ 29199 ______--___ ________
6, PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION
_29199 _ _29199 ___________ ________ 7 PRCCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 29299__ _29199 ___________ ________ ADMINISTRATIVE PROCCDURES, CONDITIONS, AND LIMITATIONS 199:99__ ___________ ________% Totals Final Grade All work done on this examination is my ow I have neither given nor received ai _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - _
Candicate's signature
.
NRC RULES AND GUIDELINFS FOR LICENSE EX AM] NAl lONS During the administration of thi s ex aminati on the following rules aup'y: Cheating on the examination means an automatic denial of your application and coul d resul t in more severe penaltie . Restroom trips are to be limited and only one candidate at a time may leav 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 tne 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 or eact section of the answer shee . Consec uti vel y number each answer sheet, weite "End of Category __" as appropriate, start each category on a new page, write only on one si de of the paper, and write "Last Page" on the last answer shee . Number each answer as to category anc number, for example, 1.4, . Skip at least three lines between each answer, 11. Eeparate answer sheets from pad and pl ace finished answer sheets face down on your desk or tabl . Use abbrevi ations onl y if they are commonly used in facility [iletatut . The point value for each question is indicated in parentheses af ter 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 . Par ti al credit may be give Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLAN . If parts of the examination are not clear as to intent, ask questi ons of the examiner onl You must sign the statement on the cover sheet that i ndi cat es that the work is your own and you have not received or been given assistance in completing the examinatio This must be done after the examination has been complete ._
.
10. When you complete your examination, you shall Assemble your examination as f ollows:
(1) Exam questions on tc (2) Exam aids - figures, tables, et (3) Answer pages includirig figures which are part of the answe Turn in your copy of the examination and all pages used to answer the e< amination question Turn in all scrap paper and the balance of the paper that you did not use for answering the question Leave the exami nation area, as defined by the examine after leaving, you are found in this ar ea while the ex an.i nat i on i r, still in progress, your'Itcense may be denied or revoked.
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QUESTION S.01 (2.50) WHAT are the TWO (2) mechanisms by which Moderator Temperature Coefficient (MTC) becomes MORE NEGATIVE as core life ages from BOL to EOL? ( 1.00) The limits for Maximum and Minimum NEGATIVE MTC values are based cr TWO (2) postulated FSAR accident WHAT are these TWO (2) accidents. WHEN during core life are they assumed to occur, and for which limit (maximum or minimum) do they apply? (1.50)
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QUESTION 5.02 (2.00)
HOW (More Negative, Less Negative, No Change) does the Doppl er Only f'ower Coefficient change if the below parameters change as follows. JUSTIFY WH Include both positive and negative reactivity effect a. Reactor power Increases from 50% to 100% powe (0.75)
b. Core age Increases from BOL to EO (1.25)
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QUESTION 5.03 (2.40)
In WHAT direction would the following parameters be changing (Increatin Decreasing, More Negative, Less Negative, Not Changing) if xenon oe.c i ! ! a- -
tions were induced by a 20 step i nserti on of control rod bank D7 Actuxe the plant is at 90*/. power with rods in manual at 210 steps. With all other systems are in their n or mal at power line u Assume no oper ator actior i taken after T=O hours, the time when the rods are inserte For parameters a through d, assume the xenon oscillation is at T=4 ho.;r s into a 28 hour3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> perio Core power AFD T (hot) T (c ol d )
For parameters e thrcugh h. assume the xenon oscillation is at T = 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> s
into a 28 hour3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> perio core power AFD T (hot ) T(cold)
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QUESTION 5.04 (3.75)
Given Mi11 stone 3 procedure OP-3209A, "Estimated Critical Conditions'
(Attachment 2), FULLY complete OPS Form 3209A-1 usirig the supplied c a '. a .
EXCEPT for those items marked N/A.
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CUESTION 5.05 (3.00)
For EACH of the THREE (3) transients listed below, match tho Stated parameters with the expected tren NOTE: small porturbations and variations ar e not show a. A steam generator atmospheric relief valve fails CPEN with reactoi poner at 65%, EOL equilibrium xenon conditions, rods in AUTO with bani D rede at 170 step . Tavg Reattor Power MWe %
4 Pressurizer Level A 10% step DECREASE in turbine load is performed with reactor pcmer at 100%, EOL equilibrium xenon conditions, rods in AUTO with bent D rc.dt at 180 step . Tavg Steam Pressure Pressurizer Levol 4 Pressurizer Pressure A single Shutdown Bank rod drops into the Core with reactor power at 9 0 *,.
BOL equilibrium xenon conditions, rods in MANUAL with b a n k- D rods at 210 step A reactor trip DOES NOT occu . Tavg MWe Pressurizer Level 4 Pressuri:er Pressure
\ [\
A. --->\ 4---> B. --->/ 4---> C. --->/ \
4./ 4-- '-
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ISES[QQYN9dICS
i QUESTION 5.06 (2.S0)
Given Millstene 3 ENG Form 31002-5. "Core Heat Balance" (Attachnent 3), ti<
i r Steam Tables and steam / water propertles tables (Attachment 4) te fi11 i r-all EMoTY spaces and calculate Core Power in */. .
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QUESTION 5.07 (2.20)
Answer the foliowing questi ons TRUE or FALSE: If a centrifugal pump's speed is DOUBLED. its ficw will DOUBLE on!v 14 it is running against a zero discharge head, If a tentrifugai charging pump is in service and the oper ator INCREASE's its flowrate, the puma's available Net Positive Suction Head (NPSh) wil!
DECREASE because of greater head lossen in the suction pipin If a condensate pump was oper ati ng at "RUNOUT" conditions, cavitaticn would be present, d. When starting a condenser circulating wat er pump, motor starting current is REDUCED by CLOSING the pump's discharge valv (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) :_ _IEE DSy_ DE_ NUQLE 95_ EO' DES _ E6@NI_ DEES $1]QN, _ ELy] Q_S, _ @Np PAGE 9 IbESDgDYN@Digg
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QUESTION 5.08 (2.40)
HOW ( I ric r ea s e , Decreasr, No Change) and WHY wou l t' each of the i o l l c e. : r parameters af f ect the margin to DN Assume no change in powe Pressurizer temperatur e increase S degrees Mass flow rata through the core increases 10'/. AFD incr eases to +10'/.
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QUESTION S.09 (2.25)
HOW.(Increase, Decrease,'No ChangA) does Di f f erenti al God Worth (DRW)
chanje for the following conditions? JUSTIFY your answe Consider each case separately, a. RCS average temperature increases from 557 F, to 597 Core Age increases from BOL to EO Bank D control rods are withdrawn from 100 steps to 228 step (***** CATEGORY 05 CONTINUED ON NEXT PAGE *****) Ei _ldE98Y 9E dWEkE93.59dE3_Cb6M1 GEE 8QI1QS_Ft;UIDS tjQND FAGE i1 IUE6dggYNQDigS
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QUEST 1ON 5.10 (2.00)
.Upon a 1oss of of f si te power, list FOUR (4) indicatiens (parameter ac trend) that natur al ci rcul at i on has been establishe (***** END OF CATEGORY 05 *****)
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QUESTION 6.01 (2.00) For a large break LOCA. WHAT are t he mi ni mum number of e m t, r g e ., c y cor u cooling system pumps required to cover exposed fuel and limit poE M bl e core damage? 10. 7 5 :> Fol l owi ng SI reset. WHAT oper ator ac ti on (s) must be perf or med in or der to reinstate automatic re-initiation of 517 ( r> . 5 5 ' If TWO (2) charging pump are OPERABLE in MODE 4, WHAT RCS syster*, safet y limit can be vi ol at ed if BOTH ar e oper ated^ Include TWO (2) s i g n i f i c a r. t parameter (0.70)
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QUESTION 6.02 (2.40)
MATCil the ESF Status Panel group description f r o rr. the right hand coluw-with its respettive Gr oup number from the left hand c ol umn . Oniv ONE (1)
description matches each Group number . Group 1 1. Consists of lights for those components whose status is changed during a CDA Group 11 Consists of lights covering the steam systen Group II] Consi sts of lights that only light during the injection phase Group IV 4 Most of these lights should alWays bO C44; however, some may illuminate during srs ec t sl or infrequent operation Gro,p V Consists of lights for those components whnse status only changes when in the col d leg recir phase Group VI Consists of lights that are normally ofi and will come on after an SIS Consists of lights for those components whote status only changes for the het leg recirc phase Confists of lights f or t hose component s whosF status i s changed during the cold leg recirc phase and remains in the hot leg retir; phase (***** CATEGORY 06 CONTINUED ON NEXT PAGE *****)
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QUESTION 6.O' (1.70)
a. Briefly ex pl a t ri HOW neutrons produce current in a Source Aenge 1593 Excore Nu'_ l ea r InwLrumentation (NI) system detecto (0. / M b. A reacter s h u t d o.vn is in progress wi th the SR detectors reading about 10,000 cps and both Intermediate Range (IR) detectors reading 1Y10E-11 amp Ten minutes later the SR detectors read about 1.000 cps but t' e IR detectors still read 1X10E-11 amp WHY does the IR detecter output NOT decrease bel ow 1X10E-11 amps? f0.00)
c. The plant is operating at 100*/. p ower with N44 out-of-servic If an automatic reatter trip occurs AND N43 is f ailed as is, WHAT affect, 14 any, will this have on the Ni system's ability to monitor neutron flux as the plant %t abili 2 eE to MDde 3 Corditions? AssuTe no manual att1On is taken to restore N4 (0.50)
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QUEGTION 6.04 (2.40)
a. WHY does letdown pressure control valve PCV-131 maintoir- ;.restw u downstream of the letdown heat e> Changer at about 350 psic' (0.50)
b. WHY must Ietdown heat exchanger 3CHS*E2 cool 1etc wn fIew to 1eu t t,an 135 degress F during Mode 1 operat2ons? to.eu)
c. WHY is Volume Control Tank (VCT) temperature limited to less t h a :35 cegrees F during Mode 1 operations? (0.60)
d. WHAl cover gas is used in the VCT during normal operations and W 4Y is it used? ( O . :-D )
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GUESTION 6.05 (2.50)
A large.bredt LOCA has occured and the Quench Spray system (CEFi ic in operatio ~
a. WHAT ore TWO (2) functions f or the 055 concerning containment pretsar.>-
Include any applicable time constraint (1.00)
b. WHAT is the design purpcse f or using NADH? 'O.b>-
c. HOW long after a CDA signal is generated do the Contair 4ent Recirculation system (RSS) pumps automatically start? Ui. 50 i d. WHY do the RSS pumps require a time delay bef ore runt ing? (0.5n)
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QUESTION 6.06 (3.00)
a. The turbine driven aux 111ary feedwater (TDAFW) pump hos THREE (3' mair, steamline supply line TWO (2) are required to meet single 4ailure cri teri a consi der ati on WHY is the third supply line requirsd? t o . 5r, i b. WHAT are the THREE (3) sources of water for the AFW syste+ in their order of preferred usage? fl.Cra c. WHAT are the FOUR (4) signals which can automatically start the motor driven AFW pumps? (1.00',
d. WHY are the automatic start signals for the TDAFW pump different 4 r oo the MDAFW pumps? (0.Sv)
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QUESTION 6.07 (2,00)
a. WHY would increasing battery charger output vol tage obove 14 3 vo! + 5 ** ,
concern when charging a discharged battery 7 b. WHAT prevents standby battery charger 301A-3 from being used to ford more than one 125 VDC bus?
c. WHAT emergency diesel gener(tor starting system component con NOT b ec energized when either a los s of 125 VDC bus 3OJA-1 occurs OR t h e b v. r r i . c_
gear is engaged?
d. Will a l oss of any ONE (l' class IE 12S VDC bus cause a DIRECT r e 6 :: t e -
trip? If so, briefly explain HO Assume the plant is at 10 0 */. p owei .
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-OUESTION 6.08 (4.00)
For EACH of the f ollowi ng RPF trips, STATE a t s .cosi gn basi s and A W D. , i4 -t all, the trip may be bypassed or blocked:
a. Power Range High Neutron Flux (low setpoint)
b. Low Pretuurizer Pressure c. Power Range High Negative Flux Hate d. Low-Low S/G Level c. Turbine Trip Reactor Trip f. Power Range High Neutron Flux (high setpoint)
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QUESTION 6.09 (3.00:
For EACH of the following situations, explain HOW Tavg is used ti v the indicated control syste Include in your answer t h e s p ec i f t e c i n + cr e.s * i . ;r requested by each par e. While at 100% power, a turbi ne l oad reduct ion at 5% per minutt is-sta-ted with ROD CONTROL in AUT Include all applicable pr ogr amnvr setpoint value PRESSURIZER (PZR) LEVEL CONTROL of P7R level when reactor power i f, increased from 50% power to 100% powe Include all applicable programmed setpoint values, FEDDWA7EF VALVE CONTROL after a turbine trip from 6 0 */. powr- occur Intlude all applicalbe setpoint values, logic, and cointicence (***** CATEGORY 06 CONTINUED ON NEXT PAGE v****)
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QUESTION 6.10 (2.00)
Explain HOW the Cold Overpressure Protection system (COPS) w) !! re'+ ct !4 an operator were to arm both Trains with hot leg wi de-r ange RTD TE- 4 ' ;A failed LOW? Justify your answer by explaining WHY eac h Train is OR 1, not affected because of the RTD failure, and WHAT cctions takes plac At s t ,'ne the plant is shutdown with the RCS at 300 F. and 700 psi .
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(s *** END OF CATEGORY 06 8****)
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6001969 GIG 96_GOU1096
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QUESTION 7.01 . ( 2. 5 0)
Answer the f oll owing questions regarding Residual Heat Removal 'GHR) 53rtu~
operation per procecure OP-33104, "Residual Heat Removal."
a. WHAT is the reason f or the maximum RHR suction pr essure limit of 7t *j psia 7 (0.50)
b. WHY is t he oper at or cautioned not to initiate RHR system oper at i or unt: 1 RCS temperature in less than 350 F? (n.50;
- . WHY should the RHR system NOT be i sol ated with the RCS soli d? (O. Sui If a Sa'ety i n iec t i on signal (SIS) occurs While the RHR syst em is aligned for RC_ cooldown, WHAT ere THREE (3) ac t i ons an oper a + cr s im.11 perform btfo% realigning t',e RHR sye, tem injection flowpath for the G1 mode' (1.001 (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
,7, PROCEDURES' - NORMAL t ABNORtj@Lt_ EMERGENCY _@ND' P F ,E P' I E901060Glce(_(gNISg6-
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QUESTION 7.02 (2.00)
Answer the f oll owing questions regarding Circulating Water C ', s,1; f operation: 1 a. After starting a CW pump, WHY is an oper at or required to wait 2 minutes before starting the another pump? (0.50)
b. WHAT is the minimum number of CW pumps required t o be r unni ng when a radioactive effluent discharge is in progress? (0.50)
c. WHAT is the maximum temperature rise of the discharge water above the intake water temperature and WHY does this limit exist? (1.00)
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'21__E099599359_!_@OSU993_9990fD961_EDESGENCy_gNp PAGE 24 5991960GJ.99t_990IB96
GUESTION 7.03 (1.75)
Answer the f oll owing querstions concerning Fuel Trantfer System pr oacr:or c OP 3303 a. WHAT-major coaponent is used for emergency retrieval of the fuel transfer cor from inside containment when a traverse drive f ailur e occurs due to a GEARBOX FREEZUP? ( 0. 5< '
b. WHAT major component is used for emergency retrieval of the funi transfer car 4 rom inside containment when a traverse drive failure occurs due to a MOTOR BURNOUT? (0.50)
c. WHA'T are TWO (2) resons for performing an emergency retrieval of +he transfer car from inside containment when a traverse dri ve 4atlure occurs? (0.75)
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QUESTION 7.04 (2.25)
Answer the following questions regarding Reactor Coolant Pump (RCP)
. operations:
a. WHY ere.the RCP seal leakoff i sol at i on valves closed when RCS pressore is bel ow 115 psia? (0.75i If the plant is at 90% power, HOW long can-a RCP operate with a seal-failure before power must be below P-8? (0.50)
c. HOW long can a RCP be allowed to operate with a seal failure before its seal leakoff isolation valve must be closed? Assume the pl ant is at 5 0 *'.
powe (0.50) If the plant is operating at 35% power and RCP 1A has a seal failure, WHY is steam gener ator (S/G) level in;eeased to 75% pri or t o s t oppi rig the RCPs? (0.50)
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L QUESTION 7. Oti (3.00)
Answer the f oll owi rg questions ccnc.erning procedure ADP-3566, "In medi at r Boration" a.-WHAT ar e the FIVE (5) entry conditions for AOP-3566? (2.00:
l is . WHY is immediate Boratton charging f1ow required to be < 233 gpm? (O.SO) WHY is immediate Bor a t i on charging flow required to be > 33 O p ^i' (O.SM)
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QUESTION 7.06 (3.00)
Answer the f ollowing questions concerning "Steam Generator Tube Rupture" procedure EOP 35 E- a. WHAT are the TWO (2) criteria for determining whether the RCPs shoulti De stopped? ( '
.00)
b. WHAT are the FOUR (4) criteria for identifying a ruptured steam
_ generator? (1.00)
c. WHAT TWO (2) parameters are used to determine adverse containment conditions? Include setpoint (1.0:n (***** CATEGORY 07 CONTINUED ON NEXT PAGE ****4)
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QUESTION 7.07~ 43.50)
The fol1owlng questions conceen "Reactor Stertup" procedu-o OP 20* a. WHAT TWO-(2) operator actions are required if criticality is NDT achieved when control rods reach the MAXIMUM position on the ECP? t1.00)
b. WHAT operator action is required when diluting the RCS boren concentration by more than 50 ppm? (A.5u!
c WHY is boron concentration adjustment NOT allowed while wi thdrawi ng a control rod bank? (0.50)
d. HOW i s proper alignment and bank overlap determined during rod withdrawal for cri t i c al i t y? Include in your answer WHAT is done and HOW often (or at what points) it is don (1.001 e. Whil e recording critical data at 10E-8 amps, you determine that loop D Tavg has been 535 F. for the last IS mi nuten. WHAT action are voi t required to tako? Include any applicable time l i mi tati ons. Assume no failed instrument (0.50)
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QUESTION 7.09 (2.50)
The following huestions deal with the Emergency Oper at i ng Pr ocedures " utage rules:
a. While implementing the actions required by accident recovery procedure ES-1.2, "Post LOCA Cooldown and Depressurization." the STA reporte the following critical safety function status tree condition Place the below conditions in the order they should be addresse (1.00:
Containment Integrity - ORANGE Inventory - YELLOW Core Cooling - ORANGE Heat Sink - YELLOW b. HOW is the operator made aware of tasks that must be f ull y completed before proceeding to another instruction? (0.50)
c. ARE the CAUTION statements from E-1 still applicable if a transition to FR-H.1 is performed? (0.50)
d. WHAT procedure's Foldout page is applicable for ES-0.4? (0.0 (***** CATEGORY 07 CONTINUED ON NEXT PAGE *****)
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DUESTION 7.10 (2.00)
' Answer the following questions regarding EOP 35 EE-i.'., "SI Ternination,'
and EOP 35 ES-1.2, "Post LOCA Cooldown and Depressurization."
a. If SI i s ter minated while in ES-1,1, WHAT TWO (2) criteria are checked to verify that ECCS flow is not required? ' l . O.:a b. HOW and WHY cas RCS depressurization affect Pressurizer level whilt i l ES-1.2? (1.00)
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QUESTION -G.O! (2.00)
Answer the f oll owing questions using procedure ACP-QA-2.065, "Station Bypass / Jumper Control." (Attachment 5) If a Technical Specification change is required and an unreviewed safety question is found to exist, WHAT TWO (2) organizations must cpprove the change before the installation of a jumper can be authori7ed? (0.50; WHEN is the Shift Supervi sor allowed to grant exception to performing a second verification of a jumper installation? (O.SO, WHO are TWO (2) peopl e - (by job title) that must complete and sign the Assessment Section of the jumper-lifted lead-bypass sheet 9 (n.50i d.-Under WHAT concitions can a jumper be installed WITHOUT using prcredure ACP-DA-2.06B? (0.50)
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QUESTION 8.02 (1.75)
a. WHO are THREE people (by j oti t it l e) that can give aut hoe i r e t t or, to t a t +/
the reactor cri ti cal ? Assume the r eac t or had been previously shutdown using procedure OP-3207, "Reactor Shutdown," (0.75)
b. WHAT TWO (2) actions are required of a licensed operator per ACP-6.0:.
"Control Room Procedure." and 10 CFR Part 55 to ensure that when a trainee manipulates the controls of the reactor, the actiond are per f or med correctly? (O.SC:
c. WHAT is the minimum fire brigade composition as required per ACP-DA-2.05? (0.00)
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QUESTION 8.03 (2.00)
For each of the -f c l I c .vi n g safety tags, state the 1 i rni t at i ons wt: 1 c: f . me placed un equipment when the tag is use a. Red b. Yol ) ow c. Green Striped d. Blue i
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OudSTION B,04 (2.00)
Per Section 3/4.5.4 of Technical Specifications (Attachment 6), RWS r ber or'
concentration must be verified through a surveillance test at least on c. e per 7 day Given the f oll owing test dates, have any Technical Speci42ce-tion surveillance requirements been vi ol ated AND is the plant in a Lim; ting Condition for Operation (LCO)? Justify your answer for EACH par As'ume the plant has been at 100'/. power since 11/21/8 NOTE: November has 30 days 12/14/87 at 1000 12/5/87 at 1300 11/28/87 at 2200 11/21/G7 at 1600
(***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
L
.e 1__9991gigIggIlyE_eggCEpygES,_CQND]IJgNS3 _gNp_Ljg91]pNS PAGE 3e
.
QUESTION 8.05 (2.00) For EACH of the f oll owi ng conditions described below, utilize the Code of Federal Regulations provided to you to det ermi ne whet her the NRC sho,ild be notified within ONE hour or FOUR hours AND indicate WHY by specifying the appropriate section number s /l et ter example: xx.xx (1) (i ) (a) A controlled liquid effluent release was determined to have occured at C times the Maximum Permi ssi bl e Concentrati on (MPC), An operator made the decision to take actions that departed from facilit Technical Specifications in an emergency to protect the public husith ar safet During a ref uel i ng outage, several pipe snubbers that wern at* ached to the RCS cold legs wer e fcund to be inoperable, Whil e per f orming a surveillance test at 1 0 0*/. power, a Safety lojection ! signal was mistakenly gener ated and an estimated 2000 gallons of RWST water was injected into the core.
l l l (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
_ _ _ _ - _ _ _ _ _ .h_ 9DU1815I59I1YLE5920tJ5ESt_Cggg111gNgt_QUp_LldlI@l[ONS PAM w . QUESTION 8.06 (1.00) a. WHO are THREE (3) people (by job title) which the shift super v i t.c. 15 DIRECTLY responsible f or noti 4 yi ng of' an emergency during normal wor k i nq hours? (O.75) b. WHICH . NRC c l assi f i c at i on level requires full activation of the SEO?
(0.2S) (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
. a __ _e901b'lSIEellyE _E6QQQDUSES t_ggNQ[ligNS,_@NQ_L{dllQIlgyg 3 D AG! "E
.
QUESllON G.07 (2.00) Classify the f ol l owi rig er.ergenc y events under the NRC I r. c i d er. t classification scheme using EPIP-4701-3 "Emer gency Action Level s. '
(Attachment 7) Justify your answer for EACH par Thuderstorms have caused a loss of offsite power with "A" ciesel gener-ator out-of-servic Di esel generator "B" starts, but doen not load due to a fire in the undervoltage circuitry, Steam generator lA is completely depressurized with the air ejector r adi at i on monitor in the alarmed condition, SI has been actuated and RCS pressure is 1300 psig and decr easi ng , A plant worker has notified the contrcl room that there is a fire in the tur bi ne building.
l (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****)
9:__9pMIN1 DIE 911y[_C6QCEDUBES2,[Oyp]]]QSD2,9ND_ LIM 11971gNp PAGE 34
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QUESTION 8.08 (3.00) Using Attachment 8 Technical Specification sec t i on 3.0.1.1, determ:ne WHEN (date/ time) the plant would be required to be in MODE 3 and WHAT LCD applies at EACH step of the sequence of eventu shown belo Assume-the plant is at 100% powe Consider the information from all previous s t.e p s in the sequence of events to be applicable for each new ste Normal Station Ser vi ce Transformer A (NSSA) is taken out-of-serv 3ce f or maintenance on 12/15/87 at 1100, Emergency Generator A fails its sur vei l l anc e test on 12/1S/87 at l ','o n , NSSA is returned to service on 12/15/87 at 200 Emergency Generator B fails itc survei ll ance test on 12/15/U7 at 20or Emergency Generator A is returned to service on 12/16/87 at 0:00.
l l (***** CATEGORY 08 CONTINUED ON NEXT PAGE *****) l i l l
. _ _ - _ _ _ _
, B a _ _9901NISIEGI lye _eegc t DuSEs t _C QND [IlgNS ,, _9ND _(ldll@l1QU S PAGE 40
.
QUESTION 8.09 (3.00) Answer the following quest ions relat i ve to Technical Speci f i c at i o- B e- e . a. What ar e FOUR (4) reasons WHY the reactor must be made critical wi t h an RCS Tavg'of atleast 551 degr ees F. ? WHY-does the turbine have overspeed protection? List TWO ( :' ) r e a r ;>, WHY is there a l i mi t on the specific activity of the reactcr coe]ent' List TWO~(2) reason (***** CATEGORY 08 CONTINUED ON NEXT PAGE ****8)
- 92_ _ @pD] NJ pIgg]] yE, Pgp;EpuSE}3_ CpNp]]]py$3_ @yp_( J DJ I91] pNS PAC-E 41 .
QUESTION 8.10 (2.00) Per Technic 61 Specifications, WHAT FOUR f4) conditions must be mct so that continuous monitoring of hot channel factors is not requi r ed during normal operations? ! I i ! i f l I , I i l l I
l l l l l
/ ,
(***** CATEGORY 08 CONTINUED ON NEXT PaGE *****)
I l l
:9:__9DDINISIBOIlyE_BBQCEQUBES 2_CQNDJI]QNS3_AND_L]DJI911gNS PAGE 47 .
QUESTION 8.11 (2.75) In accordance with the requirements of Technical Specification 6.17.2, a. Fully explain HOW access into a room, where general area radiation levels exceed 1000 MR/h, is CONTROLLE (: . 2 5 '- b. HOW would access be controlled inside containment, wher e an enclosure CAN NOT be constructed around an individual high radiation area aric general area r adi ation l evel s exceed 1000 MR/h? (1.D0) l l l (***** CATEGORY 08 CONTINUED CN NEXT PAGE *****)
, @2__9pMJUJSIggIlyE_PSOgEQUBES,_gQUQJJJONf3_9Np_L]MJJ@]]Q$$ PAGE 43 .
GUESTION G.12 (1.50) Usi ng Attar hment 4, Technical Specification section 3/4.11. answer t h following Questi ons concerning radioacti ve ef f luent releases, a. State the Technical Specification definition of REAL MEMBER Or THE PUBLI ( o , 7 3 b. Before starting a radioactive liquid effluent release, Health Phys.ics notifies you that the total whole body dose to a REAL MEMBER OF THE PUBLIC would be increased to 20 mrem for the calender year after the releas Could thi s release be per f ormed wi thout exceeding Technical Specification limits? Jusitify WHY or WHY NO t0.7Di l ,
l l l I (***** END OF CATEGORY 08 *****)
(************1 END OF EXAMINATION ***************)
l
5:__IHEg3y_gE_NgCLE95_CgWEB_fL9NI_gfgggIJgN 3 _[(y]pS,,_9Ng PAGE 44 IHgBMgg,YN9[1]CS
- ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAV, ANSWER . 5. 0 (2.50) reduction in baron concentration-CO.503 fission' product buildup CO.503 ejected RCCA CO.253 at BOL 00.25] Mi ni rnum 00.25]
mai n st eart, line break [0.253 at EOL CO.253 Maximum (0.25] REFERENCE Mi l l stone 3 Reac t or Theory EO 84 Mi1Istone 3 Lesson P1an "Reactivity CoeffIctents and Def ec t s" pages 20--22 X/A 192004 kl.06 OO4K106 ...(KA'S) ANSWER 5.02 (7.00) Less Negative C0.253 because the f ut-1 temperature coefficient (FTC) becomes less negative as fuel temperature (Rx power) i n c r e a r.e s [0.503 " * w ., _ :^ ~"' ' -; pi m; c al . va.1 Jug .s .L; ... . . . a r t _, :iC S c: r -- -- - 3 ;t
'^ .25: .; ._ '
m :_ : . Z'_ : -, .m ;;. coa.32 ,
;c=m
-; t; ; ';.' t_ - ;* - .-r ; gmm.,,
-
g c ,, m
-
m; m., y ,. .;;; REFERENCE Mi11 stone 3 Reactor Theory EO 85 Millstone 3 Lesson Plan "Reacti vi ty CJefficients and Defects" page 9
'K/A 192004 K1.07 g' g'M gg (o, yf] h2Cctu.!10 $w k;(i 192OO4K107
,
...(KA'S)
f' y M o a m d N * N C * 3 0 C * # ANSWER 5.03 (2.40) pg g peg ste Me Ce ad , Not Changing bu-t- M2- o* tw94 "*, g"77# More Negative ff 4 M , Decreasing 1 A Decreasing p/MM ky) CO. AG] CVfA 3 q M f Not Changing C8 X O.303 Less Negative -g C- . O I";*st"* L,*
*' .
6 t.feam WA?P "f REFERENCE (O.D.7) Ci?)61
*
Millstone 3 Reactor Theory EO 94 ' Mi11 stone 3 Lesson P1an "Xenon and Samarium" pages 21-24 K/A 001000 K5.38 OO1000K538 ... (KA'S)
.St- ISEQSY_QE_ NUCLE @@_EQWEB_S(@NI_QE(S@llQUt_ELQlgh _@Np PAGE 47 IdESMQQYN@MlCS . ANSWERS -- MILLSTONE 3 -87/12/15- YACHIMIAV, ANSWER 5.04 (3.75) SEE Pages 45A-45C ITEM VALUE ALLOWANCE (+/-)
---- -- -- ------------ +1475 50 O 50 .3 85 { .2 200 40 .4 .4 -2820 (15 X O.2G] .2 331 .2 E+et+- -ACC c ;7 0 (to 10 Mm m c_ $'7 10 REFERENCE Millstone 3 Reactor Theory EO 10 Note to Facility: EO refert, to OP-3304 rather thari the correct OP-3209A Millstone 3 OP-3209A K/A 192008 Kl.07 OOSK107 ...(KA*S)
.
PAGE 45A
, ,~ r W%^ J/Y26l W 3~E'T-/87 .
FORM APPKDVED BY UNIT 3 SUPERIN'tNDENT EFFEC 11vE DATE PORC NIG. NO. - CALCULATED BY DATE APPROVED BY DATE ESTIMATED CRITICAL CONDITION - FIXED R00 POSITION REFERENCE CRITICAL DATA
.
_ DATE 42/15/07 iR 17 [f/7 TIME _ 0100 RCS TAVG c;s7 'F , RCS PRESSURE 2250 PSIA POWER 100 % RCS BORON 900 ppe BURNUP 4015 MWD /MTU CONTROL BANK D 180 STEPS CONTROL BANK C 228 STEFT
- OTHE .,
,
100% cower maintained fnr laet in anye pcm (-)
'
l XENON SAMARIUM _ pcm (-) LAST SHUTDOWN TIME 1550 DATE 11/17/87 ESTIMATED STATUS AT CRITICALITY DATE 12/15/87 TIME 2100 TAVG 557 'F RCS PRESS 2250 psia 1200 ppm BURNUP (PRESENT) _4015 MWD /MTU BORON (PRESENT) DESIRED CRITICAL POSITION e BANK C AT 150 STEPS POWER DEFECT (OPS Form 3209-3) ~ f (STEP 5.3) ' 1.1 Reference Power /OO % 1.2 pcm at Reference Power
.,e /p 7j y25 c$ MODERATOR DEFECT. (OPS Form 3209-4)
..
(STEP 5.4.1)
*
2.1 Tavg (at reference conditions) 587 _F 2.2 Tref (at reference conditions) 587 'F N/A pem/or
~2. 3 MTC (at reference conditions)
2.4 Moderator Defect (at reference conditions) N/A pcm (2.1 - 2.2) X MTC =
. OPS Form 3209A-1 Rev. 0 - Page 1 of 4 . - .. . . . . -
-
- . .
'
' *
,
*
y *,- "PAGE 45B
.
i
' , (STEP 5.4.2)
2.5 Estimated Tavg 557 'F 2.6 MTC (at estimated condittorjs) N/A pcm/'F 2.7 Moderator Defect at estimated conditions (2.5 - 5575 x MTC = N/A pcm
. _ _ XENON DEFECT (Computer or OPS Form 3209-5/6) circle on (STEP 5.5) C 3.1 Estimated Xenon M ' 9 pcm (-) @ -
Ep 3.2 Reference Xenon c28So * So pcm (-) @ I 3.3 Xenon Defect (3.1 - 3.2) -~ibC pcm SAMARIUM DEFECT (Computer or OPS Form IttixX) circle on (STEP 5.6) 4.1 Estimated Samarium 685 pcm (-) 4.2 Reference Samarium GW pcm (-)
-/ bb pcmIb h
4.3 Samarium Defact (4.1 - 4.2)
(STEP 5.7) INTEGRATEDRODWORTH(OPSForm3209-8/RQQ) Use 3209-8 ONLY
. 5.1 Estimated Rod Worth N #W pcm (-) (() 5 . .t Reference Rod Worth * "W pcm (-) @
' ~ O pcm 5.3 Rod Worth Defect (5.1 - 5.2) BORON DEFECT (STEP 5.8)
6.1 Present Boron Concentration /MD ppm 6.2 Reference Boron Concentration Od ppm 6.3 Boron Worth (OPS Fors 3209-1) R V t- 6 I pcm/ppe (-) O 6.4 Boron Defect (6.1 - 6.2) x ~2 N U pcm E l .
* ..
l OPS Form 3209A-1 Rev. 0 -
*
Page 2 of 4 ' ig *, 'g ?
' ~
, .
*
= + em me = = =
. . .m .- e . .
_ _ _ _ _ , .,,., _- . - . - . _ _ , . . .. . . . . __ ~ ____ _ . _ . , , _ - . , . . . . . , - , , - _ . _ _ - _ _ _ ._ . . _ - _ . _ . . - -
l .
. ' *
PAGE 45C s - * i .
; . ' . CALCULATIONS ' (STEP 5.9) + 0 ). G 7.1 Sum Defects (1.2 + 2.4 + 2.7 + 3.3 + 4.3 + 5.3 + 6.4 W pcm O 7.2 . Boron Equivalent of Defects (7.1 + 6.3) -5T & ppm Q 7.3 Nominal PPM at Reference BU N/A ppm 7.4 Nominal PPM at Present BU rl/A ppm 7.5 Burnup Change (7.3 - 7.4) N/A ppm (+) b 7.6 Boron Change to Go Crit'ical (7.2 + 7.5) .
3T- -GS ppm 7.7 Critical Scron Concentration (6.1 - 7.6) 8G ? /EiS' ppm C LIMITS ON CONTROL R00 POSITIO (STEP 5.10) 8.1 Rod Worth at ECP . Bank C at /50 steps // W pcm (-) 8.2 Rod Worth at Minimum Insertion ,gw (8.1 + 900 pcm) M pea h 8.3 Rod Position at Minimum Insertion O ig; Bank & atF*lo teps s @ 8.4 Rod Worth at Maximum Insertion gec,e (8.1 - 900 pen) M pcm (-) @ - 8.5 Rod Position at Maximum Insertion (Cannot be below 0% power rod insertion limit) C, 67 io Bank [ at M ,~ steps b __ ACTUAL CRITICAL DATA (STEP 5.22) DAlf N/A TIME N/A
.
Rod Position Control Bank D at N/A Steps Control Bank C at N/A Steps Other: N/A i Tavg Loop 1 T411A N/A 'F Loop 2 T421A N/A 'F Loop 3 T431A N/A 'F Loop 4 T441A N/A 'F l OPS Forn 3209A-1 Rev. O Page 3 of 4 l .
*
. . . . . . .. . .. . . . . . . . , .. . . . . - . .. ...
..
.
.'
- -
,
. -. . - . .- - . - . . - . . . - - _ . . - - . . . . _ . . . . , . - - - - - . - . . . ,
St _ _IH E Q SY _g[ _NyCL E @ S,, E g EE 6_ @(@NI _ g EE 60 l [g Nt_[6glgSt_99Q PAGr ao IHEQMggyN9 Migs . ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAM, E.
ANSWER 5.05 (3.00)
** . A C R. r- G 06L --+ F A G4L P ( . C 2. )< G 3. F C [12 X O.25]
4 B . H CL 0 D CC H H A REFERENCE Millstone 3 EO ACA-01-C-OO6 Millstone 3 Text " T r a.1s i en t Analysis" pages 37-39 Table 2 K/A 192008 K1.18 K/A 192008 K1.20 K/A 192008 Pl.21 K/A 192008 K1.24 OO8K118 192OO8M120 192OO8K121 192OO8K124 ...(MA'S) ANSWER 5.06 (2.50) See Attached Core Heat Balance Pages 45A & 46B REFERENCE Millstone 3 Heat Transfer, Fluid Flow, and Thermodynamics (HT,FF,0 T) EO 54 Millstone 3 SP-31002 ENG Form 31002-5 K/A 193007 K1.08 OO7K108 ...(KA'S)
PAGE 46A
, .
CORE HE'<1 BALANCE Average over Measurement Interval
! Pzr Pressure 2250 psia RCS Loop 3 Tc 557 *F
'
- Letdown Flow (CHS-F132) 75 gom Charging Flow (CHS-F121) 87 _gpm Charging Pressure (CHS-P120) 2500 psia Charging Temperature (CHS-T126) _
510 *F VCT Temperature (CHS-T116) 100 *F S/G 1 S/G 2 S/G 3 S/G 4 l Steam Pressure (PSIA) 1100 SAME Blowdown Flow (gpm) 50 As Feed Temperature (*F) 420 S/G K .- Feed Pressure (PSIA) 1400 1 Letdown Enthalpy (From A & B) [1] 55 _ BTU /lbmEp Charging Enthalpy (From E & F) Charging Specific Volume (From E & N 4 [1]
[l]
.54-2-5' Sm 3 BTU /lbm 0.016
,g fts/lbe ) Charging Flow Correction Factor
.12716 x 2.0 x 10 -5 x(CHS-T116)+ .9983 = N/A f x 1.0011 3
- /1f Where V is the specific volume of the Charging Fluid (CHS-T116 and CHS-P120). Corrected Charging Flow (DxQ) N/A gpm Charging Flou (60xR)/(7.48xP) N/A lbm/hr l CVCS Heat Loss Sx(M-N)/3412141 4.69 MWT RCP Seal Flow (Total)-12 gpm N/A gpm
- Seal Enthalpy (From E & G) [1] 7 BTU /lbm Seal Specific Volume (From F. & G) N/A ft2/lbm Corrected Seal Flow (60xU)/(7.48xW) N/A lbm/hr Seal Heat Loss (X)x(M-V)/3412141 4.74 Mgr ENG Form 31002-5 Rev. O Page 2 of 3
- - - _ . --. - - - . - -
- . .-. - - - - - - - - -
. PAGE 468 .
S/G 1 $/G 2 S/G 3 S/G 4 Feed Enthalpy BTV/lbm (From J & K) 39 [1] A SAT STM Enthalpy BTU /lbs (From H) 118 [1] BB. SAT Water Enthalpy BTU /lbm (From H) 55 [1] CC. S/G Enthalpy (AA) 118 . S/G A Enthalpy (CC-Z) 79 [1] SAME EE. Actual Feed Flow 1.9 E+6 ---
~AS FF. $/G Power ((EE)(00)) BTU /hr 1.5 E+9 [1] S/G GG. Sat Water Spec. Vol. (From H) 0.02159 [1] 1 HH. 81owdown Flow (60x!)/(7.48 x GG) N/A JJ. Blowdown Loss [h00-BB)] -0-KK. Total S/G Power (FF - JJ) BTU /hr 1.5 E+9 ---
LL. Total NSSS Power I (KK) BTU /hr 6.0 E+9 [1] LL/3412141 = 175 g [1] NN. Net RCP Heat Input = 16 MWT PP. TOTAL CORE POWER ( M-NN+T+Y) = 175 MWT [1] CORE POWER in % (PP)(100)/3411 = 51.36 x [1]
[1] =
0.3 X 3 = [1] = 0.2 X 5 = [1] = 0.1 X 6 = .5 l ,
5 e, _ _ Id E O 8 Y _OE _NUg(C E6_EOW E6_E(@@l _O @ E,@@llOG t _EL U l D St_AND PAGE 47-1SEBdODYb6DlGS
, ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAW, ANSWER 5.07 (2.20) RUE TRUE C4 X 0.553 FALSE TRUE
~ REFERENCE Millstone 3 HT,FF.S T EOs 24,25,27,29
~
Millstone,3 Lesson Plan "Fluid Movement" pages 14,15,24-26 K/A 191004 Kl.05 K/A 191004 V1.07 K/A 191004 K1.12 K/A 191004 K1.15 K105 191094K107 191004K112 1 9 1 0 0 4 K 1 1 5, ...(F4'b) ANSWER 5.08 (2.40) Increases (0.303 as PRZR temperature rises, so does saturation pressure CO.UO3 Increases CO.303 RCS core del t a T will decrease- [0.303 reducing T(hot) [0.201 (because T(cold) is constant) Decreases [0.303 hecause more power i s bei ng produced in the top half of the core CO.303 causing (hot channel factor bt)undc OR DN8) limits in t hi s area to be aoproached [0.203 REFERENCE Millstone 3 HT,FF,t T EOs 55,58 Millstone 3 Lesson Plan "8 oiling Processes" pages 24,25 K/A 193008 K1.05 K105 ...(KA'S) e
;- qs.; ne .:. =
_ ;.x
-
,
-
o- , -' u .- .. . l5>.-THEORY.. QF - NUCliEAR POWFR PLANT. . . OPERATION.~FLUIDSc_AND' , , iPAGE> 49' 4* ' THERMODYNAMICS-
-+ . - -
.<;(.-~
<,_FANSWERS -- MILLSTONE N
'
~
-87/12/15-YACHIM1AK,' n ._
'
4 .
' ,
n ANSWER ^ 15'09
. (2.25).
a.-Increases.CO.25] moderator' density decreases CO.253'intreasing[the'
) ~
"
. probability >for'absorbtion by a ' control rod (because of increased- ' diffusion length)7 C O. 25 3 -
b. ilnce. cases- C O. 25 3 ; boron concentrat ion. is r educed . f 0. 251 r educi ng L the:
.
comp.?t i tion between baron ~ and RCCAs C O. 25]S c.~Dec. eases: CO.25] ther e i s' l ess ' neutron ~f lux fer~ interaction as.the. rods-
. move to the top'of 'the core:CO.50] ~
v - OR ' fCP C G l Co.1S',)
) REFERENCE ~ .
Millstone'3 Reactor Theory.EO 76
.
i u-S (- Adu[ , CC M) "' * #
- . gg % chegg.2s (.p-75 ~ -
Millstone -3 Lesson Plan "Neutron Poi tons" - Just f ication f or Lear ning - LCriteria 3, pages 11,12' K/A 192006 K1.05 '
- K/A 192005 K1.06 K/A-192005 K1.07 2.8'
192OO5K105 192OOSK106 192OOSK107 ...(MA'S) ANSWER 5.10 (2.00)
- cor e s exi t TCs -- stabl e or decreasing
>
- RCS: hot leg temperatures - stable or decreasing C4 X O.501 - RCS-cold leg temperatures -
at saturation for 5/G pressure i- - RCS subcooling based-on core. exit TCs - greater than 30. degrees F
--S/G-pressures - stable or decreasing REFERENCE Millstone'3 HT.FF,6 T EO.67
!. Millstone 3 EOP 35 E-3 Table 2 page 1 of 1 K/A 193008 K1.22.4.2-193OO8K122- ...(KA'S) l l ! l-l !'
.
- 6t__P(@N1_SYSIEMS_QESIGNu_COdlSOkt_GNQ_lN$1 GUM [NI@IlON PA:3E 49 ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAV, . ANSWER 6.01 (2.00) charging pump CO.253 I safety i nj ec ti on pump CO.25] 1 residual heat removal pump CO.253 close the reactor trip breakers CO.55]
" ^ ~ ' RCS overpressurization Ce.3 ] mt --ir;c "C L au.-~
. at a: .
REFERENCE
'
b Millstone 3 EO ECC-02-C-010; RPS-02-C-018 Millstone 3 Text "RPSAS" page 65 Millstone 3 Technical Specifications pages B 3/4 3-3,4-15,5-1 K/A 006000 K6.02 K/A 006000 K6.03 K/A 006020 K4.06 OO6000K602 OO6000K603 OO6020N406 ...(KA'S) ANSWER 6.02 (2.40) . . . [6 X O.40] . . . REFERENCE Millstone 3 EO ECC-02-C-OO6 . Mi l l stone 3 Text "ECCS" pages 86,87,120 K/A 013000 A3.02 A302 ...(KA'S)
>
L
, ,3t__E60MI_SYSIEMS_QESIGNt_CgMI6QLt_BNQ_lNSIRy0EN1@llQN- PAGE 50 LANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAK, . ' ANSWER 6.03 (1.70)
e. a neutron and a boron interart to yield an ionized (+) lithium ~ nucleus-and an ionized (+) alpha particle 10.30] these ions create additional ion pairs CO.203 which migrate to'the detector's charged electrodes CO.20]
. X10E-11 amp signal is used as a ref er er.cc for gamma compensation C O . 5c' ] SR detectors cannot be energized CO 503 REFERENCE Millstone 3 EOs NIS-02-C-OO4,005.OO6 Millstone 3 Text "Excore N.I." pages 6,16,20,26 K/A 015000 K4.01 K/A 015000 K5.01 K/A 015000 K6.02 K401 015000K501 015000K602 ...(KA*S) .
ANSWER 6.04 (2.40) a. prevent flashing CO.30] of water after orifices (0.303 b. prevent damage to demineralizers CO.60] c. protect the RCP seals (0.603 d. hydrogen CO.30] oxygen control [0.303 REFERENCE Millstone 3 EOs CHS-02-C-OOO,002 OO5 Mill stone 3 Text "CVCS" pages 3.16 Millstone 3 OP3304A pages 52.62 K/A 004000 K4.03 K/A.OO4000 K5.04 K/A 004010 k3.01 K/A 004010 K4.01 OO4000K403 OO4000K504 OO40 LOK 301 OO4010K401 ...(KA*S) l
< 63__PL99]_SYSIEdg_pESIGN1_CONIROL1_999_IN_SIBy[EbI9]]Og PAGE St ANSWERS -- MILLSVONE 3 -87/12/15-YACHIMIAX, .
ANSWER 6.05 (2.50) a, li mi t s pressure ri se inside containment (0.S03 reduces pressure to < atmospheric CO.25] within 60 minutes (0.253 minumi ze corrosi on in containment (by increasing pH) CO.503 minutes +/- 10 seconds [0.50] ensure adequate available NPSH for pump operation (0.503 REFERENCE Millstone 3 EOs CDA-02-C-OO1,004,00)
. Millstone 3 Text "CTMT Depress." pages 1,2,25; "ECCS" page 82 K/A'026000 K4.04 K/A 026020 K4.03 K404 02602OK403 ...(KA'E)
ANSWER 6.06 (3.00) a. because one RCS loop can be isolated (0.503 denineralized water storage tank CO.303 condensate storage tank [0.30] CO.103 f or order service water (1. on g Island Sound) CO.30) c. SIS LOP C4 Y 0.253 CDA low-low S/3 level d. reduce the possibility of S/G overfall CO.503 REFERENCE Millstone 3 EOs FWA-02-C-OOO,001,004 Millstone 3 Text "AFW" pages 9,12,17 K/A 061000 K1.01 K/A 061000 K1.07 'r.iA 061000 KA.O2 K101 061000K!O7 061000M402 ...(K4'S) i
j 62_.EL9BI_SYSIED_S_DEg]9N1_C9$1BOL1_9ND_JNSIBUDENI9IJON PAGE 52 ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAX. . ANSWER 6.07 (2.00) significant hydrogen production occurs (r esul t i ng in an increaned riet of explosion) CO.503 Kirk Key interlock 10.503 air start solenoid valve CO.501
- no 00.503 REFERENCE Millstone 3 EOs 125-02-C-OOO,003 Millstone 3 Text "12bVDC System" pages 3,4; "Diesel Generator and Support Systems" page 5 Millstone 3 AOP 3563 Attachments A.B.C.D page 1 X/A 063000 K1.03 K/A 063000 K3.01 K/A 063000 K3.02 K/A 063000 K5.02 OOCK103 063OOOK301 063OOOK302 063OOOK502 ...tVA'E)
ANSWER 6.08 (4.00) r eacti vi ty ex cur si ons CO.503 bypassed when P-10 satisfied CO.253 DNS CO.503 blocked below P7 CO.253 multiple (0.25] drop rod CO.253 heat sink CO.503 b1 :; -:- .- 'r ' c c-p . : c i se c - c1 -n: : I r -: M *^ ~53 Ca M Tb bP minimize RCS thermal transients CO.503 blacked below P-9 CO.253 Q g gy] excessive heat flux CO.25] leading to DNB CO.25] REFERENCE Millstone 3 EOs RPS-02-C-Ol7,036 Millstone 3 Text "RPSAS" pages 42-57 K/A 012000 K4.02 OOOK402 ...(KA'S)
- _ _
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,
.$___PL@N1_SYSlEUS_DESIGMt_CgNIBOLt_@yg_lNSlBy[E91911CN PASE S~
ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAK, ANSWER 6.09 (3.00) Tavg is used with Tref to develop rod speed and di r ec t) on input for ron c on t r ol CO.50] the difference between the two temper atures gener ates a program.aed response as follows:
-1 to +1 ~~
no rod motion (0.25]
> +/- 1 varies from 8 to 72 steps / minute CO.25] Tavg is used to generate a r ef erence level for Pressurizer level EG.50; program level varies from 25% at 557 F. [0.25] ts 61.5*/. at 597 F. [0.25] /4 [0,10] Low Tavg channel s at 564 F. [0.20] coincident with e r eac t or trip (P-4) signal (0.20] causes feedwater i sol at i on [0.50]
REFERENCE Millstone 3 EOs TIS-02-C-OO3; ROD-02-C-OO7.025; PFL-02-C-OO2; F WG-02- C-OO2 Millstone 3 Texts "Rod Con t rol " page 23; "Ptr. Press. L Level" psges 24,25;
"Feedwater" page 12 K/A 001000 A1.01 V/A 011000 A1.04 K/A 059000 A3.06 A10; 011000A104 059000A306 ...WA'S)
ANSWER 6.10 (2.00) T7;g Train B block valve (MV 80008) will ep - r^ 4M 4J2G.we u y) p47 A 4 0 G,W] PORV (PCV-456) will not open CO.40] Train A b!ock valve (MV 8000A) wi11 er ~ "'
'^J 41G4rt cp 'ApSk' CC 4'd PORV (PCV-455A) will open [O.40] because train "A" of CCP system uses autioneered LOW temperature for a pressure setpoint (0.40]
REFERENCE Millstone 3 EOs PPL-02-C-OO3,004 Millstone 3 Text "Pzr. Press. & Level Con t r ol " pages 13-15 K/A 010000 K4.03 OlOOOOK403 ...(KA*S) I
#
ZL__E60gEgySES_ _8080@(t_@pNQS[@(t_{dg8GENQY_@NO PAOE 54 Be91969GICe6_C90Id96 _ ANSWERS -- MILLSTONE 3 -87/12/15-YACHIM1AK, ANOWER 7.01 (2.50) RHR piping protection (prevent overpressurization) [0.503 b. minimize thermal shock to the RHR heat exchangers EO.50] prevent possible RCS overpressurization [0.50] d. STOD the RHR pump Oc'EN the RHR/RWST suction valve ~(3 X O.333 SfART the RHR pump REFERENCE Millstone 3 fos RHR-02-C-OO7,009,010,011 Millstone 3 OP 3209 page 29,32; OP 3310A page 6; Text "RHR" page 3 K/A 005000 K1.11 K/A 005000 K4.01 . K/A 005000 k5.05 K/A 005000 GO.10 OO5000G010 OO5000K111 OO5000K401 OO5000k505 ...(ko'S) ANSWER 7.02 (2.00) to allow time for the (hydraulic transient) pressures associated with a pump start to subside thr oughtout the system [0.50] three (3) CO.503 F [0.50) envi r onment al protection concerns (0.503 RE dRENCE Millstone 3 EOs CWS-02-C-OO1,003,006,007 Millstone 3 OP 3325A page 8,10 K/A 191004 K1.16 K/A 075000 K1.02 K/A 075000 GO.10 G010 075000K102 191004k116 ...(KA'S) i ANSWER 7.03 (1.75) crane or hoist hook CO.503 emergency handwheel 00.503 isolation CO.403 and repair CO.353 REFERENCE Millstone 3 EOs FHS-02-C-OO2,019 Millstone 3 OP 3303C pages 7,8 K/A 000036 EA1.04 . _ _ _ - - _ - _ _ - - - - - - _ _ _ .
, ' . ,
t 5.7h ~PROCEDbRES -~ NORM k ABNORMALc_ EMERGENCY-AND ~
~ PAGE 55-1 - : BAD 1969GICe6_CQNIGQQ- y w: s .: ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAK, - . 'K/A OOOO36 EK3.03.: OOOO36A104 OOOO36K30 ...(KA'S)
ANSWER- 7 . 0 4' (2.25) a.iprevent contamination;[0.353 f r om the seal leakof f line from being forced back into the-RCP seal ~ chamber CO.403 l b. 30 minutes [0.503 c. 5 minutes'CO.503-d. . prevent a reactor trip on l ow-l ow -l evel due.to S/G shrink CO.50] REFERENCE Mi l l stone 3. EOs RCP-02-C-010; AS4-01-C-OO3,005 Millstone 3 AOP-3554 page 3; OP-3301D page 5 K/A'OO3OOO K6.02 K/A 000015 EK3.03 4.0
- K/A-OOOO15-EK3.07 OOOO15K303 OOOO15K307 OO3OOOK602 ...(KA*S)
ANSWER 7.05 (3.00) control ban 4geight below the low-low limit
- failure of ese or more control rods to f ully insert following a reactor trip-or shutdown - uncontrolled couldown of the RCS f ollowing a reactor trip or shutdown . , - uncontrolled or unexplained reactivity addition (i ndi c ated by abnormal -
control bank insertion, increasing Tavg. or increasing nuclear power)
- failure of the reactor. makeup control system mudfften A'#J A $ ras p9 05 X O.403 b.hlia i' - 1 0 m o ;d_.t'r- trary to,So3 provide a minimum rate of negative reactivity insertion (GAEa 00.503 -
REFERENCE Millstone 3 EOs A66-02-C-OO1,002,004 Millstone 3 AOP-3566 pages 2,3 f: _K/A 000024 EK3.01 K/A 000024 EK3.02 4.4 q- OOOO24K301 OOOO24K302 ...(KA*S) . I-i { l- ! ! l ! \ ,
.2A__E89EE9k'8ED ~ BOBU961_@p30B0961_ Egg 69g@Cy_9ND PAGE 56 S99196ggIC96_C99IB96 . ANSWERS -- MILLSTONE 3 -87/12/15-VACHIMIAK. .
ANSWER 7.06 (3.00) a. at least one charging or S1 pump running CO.50] RCS pressure < 1435 psia (1700 psia for adverse containment) C0.50' b. - unexpected increase in S/G 1evel
'
- high S/G sample radiation
- high S/G st eaml i ne radi at i on C4 X O.251
- high S/G b]ondgOwn.line radiation Y % .253 ) 15.s nas 'F c. containment hE g CO.25]
{
radiation CO.25] > 1m ' ~'c CO.25] REFERENCE Millstone 3 EOs E30-01-C-OO1,009; EOU-01-C-OO7 Millstone 3 EOP 35 E-3 pages 3,4.13 Millstone 3 exam 85/05/14 question 7.05 K/A 000038 EK3.06 OOOO38K306 ...(KA'S) ANSWER 7.07 (3.50) a. - terminate the startup by fully inserting all control bant s C0.50]
- recalculate the ECP CO.503 b. manually energize the PZR heaters (to induce sprav flow) CO.50]
c. posi t ive reacti vi ty must not be changed by more than one t c.n t r c l i e d method at a t ime CO.50] d. rod motion is stopped CO.25] at every 114 steps CO.25] 4nd bam domand position [O.25) is compared to digital rod position i ndi c a t i on CO.253 e. be in Hot Standby CO.25] within the newt 15 minutes CO.25] REFERENCE l Mi l l st one 3 EOs GO2-01-C-OOO,007,011.016,019 i Millstone 3 OP 3202 pages 6-10 K/A 001000 GO.10 K/A 001010 A3.01 K/A 001010 A3.02 K/A 001010 A3.03 OO1000G010 OO1010A301 OO1010A302 OO1010A303 ...WA'S)
- _ _ _ _ _ _ _ _ _
[ PROrEDURES - NORMALg_gBNgRM962_EMg3GENCY_9Np PAGE 57 B99196gG1ceg_CpNI6g6 . ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAK, ANSWER 7.08 (2.50) standby instrument air shutdown instrument air C3 X O.331-service air air pressure decreasing rapidly-[0.503-loss of turbine /f eedwater control CO.503 use of S/G atmospheric steam bypass valves-CO~.50] REFERENCE Millstone ? ECs A62-01-C-OOO,001 Millstone 3 AOP 3562 page 3 K/A 000065 EK3.08 K/A 000065 EA2.06 A206 OOOO65K308 ...(KA'S) ANSWER 7.09 (2.50) ) Core Ccoling 2) Containment Integrity [0.25 X 43 3) Heat Sink 4) I nvent ory the step containing the task or an associated NOTE or CAUTION will explicitiy state the raqui rement (0.50] yes [0.50] E-O CO.bO'] RECERENCE Millstone 3 EOs COU-01-C-OOO,001.OO2 Milstone 3 EOPs E-3 page 11, E-O f ol dout page Westinghouse Owners Group ERG Users Guide pages 5.6.10 K/A 194001 A1.02 A102 ...(KA'S)
. ,
o
'Zz__EBOCEQQ3ES_2_NQ856bt_9@bQ8MBbt_EME8QENCY_@UQ PA3E Se BeQ196901G06 GQUISQ6 , ANSWERS -- MILLSTONE 3 -87/12/15-YACHIMIAM. ANSWER 7.10 (2.00)
a. RCS subcooling CO.503 PZR level CO.503 b. PZR level raptdly increases CO.50] due to voi ding in the reacto- vessel head region (0.50] REFERENCE Millstone 3 "EOP 35 ES-1.1, EG-1.2" EO Millstone 3 ES-1.1 page 7; ES-1.2 page 12 X/A 000040 EK3.04 X/A 000040 EA2.05 OOOO40A205 OOOO40K304 ...(NA-5)
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) ' - : 3 __eDdjN]SISSIJyE_BBQQEQUBES,[ggNQJJJQN$2_@Np,(JMJIhljpNS PAGN 'StT ANSWERS - MILLSTbNE13 -87/12/15-YACHIM1Ak,-E.' ' [ . . >
L
- [ ANSWER: 8.01 -(2.00)
a..NRB CO.253 and NRC CO.253 b.'. I f ' the second , veri f i cat i on woul d ' resul t? i n si gni f i cant -r adi ati on
~
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exposurtt CO.503 _
.c. 55 CO.253 Duty officer'CO.253 _ ..
Ld. . lf identified and to trolled.in'another approved procedure CO.503 e-Ol? . . y:p. mar 'vs 68ee m d art p A a W c
.O . REFERENCE- .
Millstone 3 Terminal Objective 1(TO) BYJ-02-C-OOO Mi l l stone 3 ACP-DA-2.06B pages 3,9.10,12
- AN'SWER 8.02- ( l'. 75 )
a.' Station Superintendent CO.253
. Unit Superintendent (0.253 Operation's Supervisor CO.253 ~b. instruct CO.253 and directly observe the i ndi vi dual CO.253 c. one fire brigade leader CO.253
- four' fire-brigade members C0.253
' REFERENCE
'
. Millstone 3 Enabling Objectives (EOs) CRP-02-C-012; CRP-02-C-024; FPP-02-C-OO2 Millstone 3 ACP-04-2.05 page 10, ACP-GA-6.01 page 6 10 CFR Par t 55 Section 55. 9 (b)
ANSWER 8.03 (2.00)
, 'not to be operated under any circumstance C0.603 b. contains precautions or information which should be understood prior to operating CO.503 c. prevents-reenergizing equipment if it trips CO.503 d. only to be' energized by order of the individual to whom the tag was issued CO.503 REFERENCE Millstone 3 EOs TAG-02-C-010,021.023,025-Millstone 3 ACP-QA-2.06A pages 3,4
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.IBI_ ggdlNi@l8911ME~ PROGEQy@CQt_QONQlllONQt_@@Q_ljldl1911QNS'
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-PAGE' 60 ANSWERS - ? MILLSTdNEL /12/15-YACHIM1AK... ,
ANSWER B.04 (2.00) .
- YES CO.203 because the' interval between-12/5 andI12/14 CO.403 exceeds trm ~
maximum allowable extension of.25*/ of the surveillance i nterval CO.403-
- , - YES CO.203'because'a failure to perform the surveillance test within the speci fied time- interval CO.403 constitutes a failure to' meet the
_OPERABIL11Y recuirements for the LCO CO.403-
-REFERENCE Mi l l stone - 3 EO SRV-02-C-OO1 Millstone 3 ACP-DA-9.02 page: 4 Technical Specification (T.S.) 4. ANSWER 8.05 (2.00) . hour 50. 72 ' .(b) (2) (i v) (B) CO.503 I hour 50.72 (b) (1) (i ) (B) C O. 50 3 - hour 50.72 (b) (2) (1 ) CO.503 i'~; '5 ' . : - * hodr Oc N (b) D)(U) ., 1. ; . < ; CO.503 f
REFE ENCE ACP-DA-10.01 10 CFR 50.72 ANSWER 8.06 (1.00) security shift supervisor CO.253 8" OQ M1 *
- duty officer-CO.253 -
- operati ons supervi sor CO.253
;
h} b, alert (or higher) CO.253 C,c9 '
~ REFERENCE V ,
Millstone 3 Emergency Plan Training EOs 12,16 , EPIP-4010A page 3 i EPIP-4112_page 3
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-nw- m , , , n--- ,- - , - , . - . - - - , , , , -
,-. , , , , - . , , , , -n , , .y., -y-. r,, --
7 g
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BL__hDMidlS;R@llVE PROCEDURESt_QQNQlTigNht 'AND L k MITA110NG- PAGE~ 6 ). 3.
Y ANSWERS ~~- MILLSTON '
-87/12/15-YACHIMIAK,, u .
. ANSWER' 8.07' (2.00) SITE' AREA -- for > 15 minutes CO,503 ALERT -- steamline break with rimary to secondary CO.503 SITE'~ AREA--- LOCA.CO.503 9 - 2 W w l A Ak4pwi4r l ea kag{e J 41 h c c c d g.iv,
' UNUSUAL EVENT -- if-fire last for < 15 minutes (0.50] ,
"
fA
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REFERENCE- Gh4 Millstone 3 Emergency Plan Training EO 6-EPIP-4701-3' NCQ- &gm ( , c.QOoo: ANSWER 8.08 (3.00) w d {bcucmo %
,
a. 12/.8/87 at 1700 CO.503 LCO 3.8.1.1.a. Co.253 b.- 12/16/87'at 0600 CO.503 LCO 3.8.1.1.b.. [0.253 c. .12/16/87 at 0400 LO.50] LCO 3.8.1.1.s(6.CO.25] /)JY/87 at 1.:T t-t' CO.503 LCO 3.8.1.1.pfC.CO.253 (9 O200 REFERENCE Mi ll st one 3 TO TSG-02-C OOO TS 3.8. . ANSWER 8.09 (3.00) to ensures - MTC within analyze (< range
- trip instrumentation within operating range
- P-12 above its setpoint [4 x 0.253
- the pressurizer is in an OPERABLE status
- the reactor vessel is abone its minimum RT(NDT) temperature protects safety related components, equipment, and structures (0.503 against ar e ne ni o- r.c :pcc' _ "ir" "mn e nn n-,+ e mi ssi l es C O. 50 3
' ensures that SITE BOUNDARY doses will not exceed 10 CFR Part 100 guideline values CO.503 f ollowing a SGTR accident CO.503 REFERENCE Millstone 3 TO TSG-02-C-OOO TS Bases 3/4.1.1.4, 3/4.3.4, 3/4. , s
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, d, .'Bi._{ADMINi@l6911YEi.EBOCEDyBES
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tiCONDillONS [@UD_(1M11@110NS' t s .FAGE. 62: 1 ANSWERS -- M'!LLSTONEh3 -B'7 /12/15-YACHI MI AK, - ,
. < " - -
a ,-+ - _
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=aM ANSWER'- 8.10' (2.00) -
,
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- control i ro' d s ' ire a' si ngl e gr oup. move-together with1nofindividual ro (insertion differing.by'more than 1'/ '12 steps,1.indtcated, from - t he' .g roup
,
. demand position CO.503 ,
- . control rod groups =are sequenced:with overlapping groups CO.503-
- the control ' rod-insertion 11mi ts are L mai ntained . CO.503 1the ax i alx power ' di stri but. ion ;(expressed i n terms of ! AFD) -i s' mai ntai ned
-
within li mi ts. C O.50 3- *
.
REFERENCE-Mi1Istone.3'EO1TSG-02-C-OO5 Millstone'3-Technical; Specifications.page B 3/4 2-5 K/A 193009 K1.07 ;193009K107) - ...(KA*S)
'. * ANSWER -
G.11 '( 2. 75) , a.-doors are locked CO.503 and the key maintained under administrative con-trol CO.50] of the SCO CO.253 and/or Health Physics Supervisi on C O. 25 3 : ; FACILITY NOTE: T. S secti on 6.12. 2 states that 't he shi f t Foreman maintains key contro ACP-6.01 does not~ define who'this person i P
' barricade the area C O. 50 3 :
conspicuously post the' radiation l evel s C O. DO T , a fl ashi ng . light shall - be acti vated -as a warning devi ce CO. 503 ' t REFERENCE' Millstone 3 EO TSG-02-7.-016 T;S. 6.12.2 page 6-24 K/A 194001-K1.03 k1O3 ...(KA'S)
.
ANSWER 8.12 (1.50) . a. an individual who is exposed CO.253 to existing dose pathways CO.253 at I one particular location CO.253 b. Yes CO.253 because T.S. 3.11.3 allows 25 mrem to the whole body CO.503 l REFERENCE Millstone 3 EOs TSG-02-C-OO1; LWS-02-C-OO2; GWS-02-C-OOO Millstone 3 T.S. section 1.0 page 1-4, section 3/4-11 page 11-6
'K/A 068000 GO.05 L i
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.e _0DulNESISell K E6QQEQUEEL _GQNQIllQUS3_@UQ_(lM11@llgMS PAOl' 67 ANSWERS -- MTLLSTONE 3 -87/12/15-YACHIM1AK, .. - -
e M/A 071000 GO 05 G00S' 071000G003 ...(KA'5)
. f//Cdfeid b<. $ $aC lH /1e d I .I
' v = s/t -
'
Cyc1'e' efficien'cy = (Net work f = ma out)/(Energy in)
w = eg .s = V,t + 1/2 at 2 , E = mc KE = 1/2 av a = (Vf - V,)/t A = AN A=Ae" g PE = agn Vf = V, + a t w = e /t x = an2/ti/2 = 0.693/t1/2
,o r '
t y , , /2*ff = C(tus)(tw il A= , , ((t1/2) * I*b)3
*
fE = 931 am -Ex a = V,yAo , O,
. . ~'
-.
Q = mCpat 6 = UAa T I = I ,e'"* pwr = Wyah I = 1,10-* N TYL = 1.3/u P = P 10 sur(t) HY1. = -0.693/w
'
p=pe/T o t SUR = 26.06/T SCR = S/(1 - K,ff) CRx " 3/(I ~ Keffx) SUR = 25s/t= + (s - s)T Caj (1 - K,ff)) = CR2 (I ~ Ieff2) T = ( t*/s ) + ((s - o Y Io ] M = 1/(1 - K,ff) = Gj /G, T = t/(o - s) M = (1 - K,ffa)/(1 - K,ffj) T = (s - o)/(Io) SDM = ( - K,ff)/K,ff t* = 10 seconds a = (K ,ff-1)/K ,ff = aKeff /Keff I = 0.1 seconds-I
'
o = ((t=/(T K,ff)] e (T,ff (1 + IT)]
/
d Ij j = I d2 =2 2 P = (I4V)/(3 x 1010) Idjj Id 22 '
I = oN R/hr = (0.5 CE)/d (ceters) R/hr = 6 CE/d2 (f,,g) Water Parameters _ s Miscellaneous Conversions curie = 3.7 x 1010 gps 1 gal. = 8.345 le gal. = 3.78 liters 1 kg = 2.21 lbm 1 ft4 = 7.48 ga I hp = 2.54 x 10 3 8tu/hr Oensity = 62.4 lbm/f t3 1 mw = 3.41 x 106 stu/hr Oensity = 1 gm/c..r3 lin = 2.54 cm Hest of vaoorization = 970 5tu/lem 'F = 9/5'C + 32 He at of fusion = M4 St:./itm *C = 5/9 ('F-32) 1 Atm = 14.7 psi = 29.9 in. n I BTU = 778 ft-lbf 1 ft. H 2O = 0.4335 Itf/i . _ _ .
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* . . . . . ATTACHMENT 2 r- . . *
E. J. Mros4ka~ ~
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2-1-85 Fgrm e,..' roved.by Station Superintendant Effcctive Date
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STATION PROCEDURE COVER SHEET IDENTIFICATION Number OP 3209A ,
,Rev. O Title REACTIVITY CALCULATIONS - ESTIMATED CRITICAL CONDITIONS Prepared By DAVID MC OANIEL REVIEW I have reviewed the above proJedure and have found it to be satisfactor TITLE SIGNATURE DATE DEPARTMENT HEAD / n[w bJb OI & \Dh W -
y i UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:
(Significant change in procedure method or scope YES [ ] NO [;/J as described in FSAR) (If yes, document in PORC/SORC meeting minutes)
ENVIRONMENTAL IMPACT (Adverse environmental impact) YES [ ] NO (If yes, document in PORC/SORC meeting minutes) INTEGRATED SAFETY REVIEW REQUIRED (Affects response of Safety Systems, performance YES [ ] NO $d of safety-related control systems or performance of control systems which may indirectly affect safety system response.)
(If yes, document in PORC/50RC meeting minutes,.) PROCEDURE REQUIRES PORC/GG4E- REVIEW YES $4 NO [ ] PORC/5Me APPROVAL PORC/GMe-Meeting Number }- 8F-/89 APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below: G -* 3 1Il2?llW Stadonhervice/ Unit Superintendent Effective Date SF 301 l Rev. 7 l Page 1 of 1
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- OP 3209A Pag: 1 Rev, 0
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REACTIVITY CALCULATIONS - ESTIMATED CRITICAL CONDITIONS
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Page N Eff. Re I-9 ,
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OP 32 m Page 2 Rev. 0
. OBJECTIVE 1.1 This procedure provides a method and forms for determining Estimated Critical Conditions (ECC). An ECC m3y be determined *
by performing this procedure, or running SP-3R11 on the Modcomp Process Computer, when it is deemed valid by Reactor Engineerin .' -PREREQUISITES
~
2.1 The most recent steady-state critical position data is available for calculating an ECC (this data will be supplied by Reactor Engineering). INITIAL CONDITIONS 3.1 None PRECAUTIONS 4.1 The Rod Insertion Limit (RIL) shasl never be exceeded when the reactor is critical (except during Low Power Physics Testing)
(LPPT). Whenever the reactor is in Hot or Cold Shutdown the RCS must be borated such that the reactor would not be critical ~" .. . . with rods below the RI '
i ' C. 41 If criticality is not achieved within i .9% Ak/k (900 pcm) of
- -
the calculated ECC, insert the Control Banks in sequence to zero steps and recalculate the ECC. If the newly calculated ECC does not differ from the original ECC (as modified for any conditions which have changed) notify Reactor Engineering. If Reactor Engineering can not find any mistakes place the plant in Hot Standby. An evaluation will be conducted by PORC. Upon approval,startupwillcommenceusingReactqrfnginogidp recommendation .. . 2- ,% 4.3 This procedure shull be performed no more than four hours prior to going critical per Technical Specification 4.1.1.1.l _ .. .. .. - . . - .
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OP 3209A Page 3 Ree 'O
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4.4 The reactor shall not be brought critical with rods below the Rod Insertion Limit per Technical Specification 3.1. unless allowed per Special, Test Exception 3.1 . NOTE: Computer Program SP 3R11 "Estimated Critical Position"
,
may be used to determine an ECC in place of this
## 49. g3 a af c, .t N keg AoA be ewe, 3e(
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# ' PROCE$RU " " 5'r4S . i NOTE 1: The burnup (in megawatt days per metric tonne ie. Knt/MTU)
change from the reference '4ition to the present conditions should not exceed 200 HnD/MTV unless designated by Reactor Engineering on the ECC Data Shee NOTE 2: If it is desired to select a critical rod position and vary boron concentration perform Steps 5.1 through 5.10 and complete OPS Form 3209A- If it is desired to select a critical boron concentration and vary rod position perform Steps 5." , through 5.20 and
" fcd complete OPS Form 3209A-2.* j 5.1 Enter reference critical position date. This should be the most recent steady state data available (supplied by Reactor Engineering) on OPS Form 3209-1 CAUTION: Ensure proper use of signs (+ or -) throughout this calculatio .2 Enter Estimated Conditions at Time of Criticalit Data for Date, Time, Temperature, and Pressure, are estimated. Rod Position is the Desired Position. Boron and Burnup are entered at the existing conditions.
.--.. .. . . - ..
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'
-Page :
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5.3 Item Determine the power defect at the Reference Powe . The number.on the curve is negative', .but'a po'sitive numbe-stiould be entered on OPS Form 3209A-1. (Use OPS' Form 3209-3).
5l4 Moderator Defects - Item NOTE: The power defect curve assumes the reactor is operating with Tavg equal to Tref i 2 If Tavg is not equal to Tref i 2*F'it will be necessary to perform Step 5. . Determine the difference between T average at the reference condition and Tref at the reference conditio Multiply this difference by the Moderator Temperature Coefficient (MTC) (OPS Form 3209-4/5) at the reference condition to determine the moderator defect. (This number will be negative if Tavg > Tref and MTC is negative.)
NOTE: If the estimated critical temperature is other than 557*F 12*F, it will be necessary
~
to perform Step 5.4.2, . . .
- } Y C, t
5. Determine the difference between Tavg at the estimated - condition and 557*F. Multiply by the MTC (OPS Form 3209-4/5) to determine Moderator Defect at the Estimated Condition. (The value is negative if Tavg
> 557*F and MTC negative.)
- NOTE: If the computer is not available, use OPS Form 3209-5 and OPS Form 3209-6 to obtain Xenon worth if the reactor was shutdown from an equilibrium Xenon stat If the reactor was not at or near an equilibrium Xenon state prior to shutdown, '
. , ,
Reactor Engineering will determine Xenon wort . . ... . . .. ... . . _.... . . . . . ,-. _ - - --..y .-
. . _ _ . _ _ __ _ _ _ _ _ _ _ _ _ _ . _ ___ ___-_-_
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OP 3209A Pa;c 5 Rev. 0 .
.
5.5 Item Determine the Xenon worth at the estimated time of criticality (use SP 3R7/3R9 or OPS Form 3209-5/6. Subtract the reference Xenon worth from the estimated Xenon worth to obtain
'
the Xenon defect. (The value is negative if estimated Xenon.is greater than reference Xenon.)
5.6 Item 4. Repeat Step 5.5 for determining Samarium worth. (Use SP 3R7/3R9 or OPS Form 3209-7).
~ 5.7 Item Determine the integrated rod worths at the estimated and reference conditions. Subtract the reference rod wortn from the estimated rod worth to obtain the rod worth defec (Use OPS Form 3209-8, 9, or 10.) The value is Negative if the estimated position is below the reference positio .8 Item 6. Determine the Differential Boron Worth at the present boron concentration. Multiply by the change in boron concentration from the present condition to the reference condition to obtain the boron defect. The value is Negative if the present boron concentration is greater than the reference boron concentration. (Use OPS Form 3209-11.)
5.9 Item 7. Add all the reactivity defects. Divide by the differential boron worth to obtain the boron equivalen Use OPS Form 3209-13 to compensate for burnup if the difference between the reference burnup and present burnup is greater than 200 Kn'D/MTU. Add this to~the boron equivalent of the summation l of the reactivity defect to obtain the boron change required to I go critical at the desired rod positio If the value is - -' t .- , , positive, dilution is required (i.e. addition of + reacti0it[).
'
'
If the value is negative, boration is required (i.e. negative reactivity should be added).
.
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OP 3209A P:ge 6 Rev. 0
.
5.10 Item S. Determine the 1 900 pcm limits around the ECC by using the rod worth at the ECC. Add and subtract 900 pcm from the ECC and obtain the equivalent rod position using OPS Form 3209-8,
*
9, or 10. Do not allow the maximum rod insartion to exceed the 0% power Rod Insertion Limit (RIL) or the minimum rod insertion-to exceed any rod withdrawal limits imposed unless physics tests are in progres _
.
NOTE: If Steps 5.1 through 5.10 were performed to calculate an ECC by selecting control rod position and varying boron skip to Step 5.2 If it is desired to select a boron concentration and vary control rod position perform Steps 5.11 through 5.20 and complete OPS Form 3209A- Normally Steps
, . . 5.11 through 5.20 should be done if it is desired to '
go critical on the existing RCS boron concentratio .11 Enter reference critical position data. This should be the most recent steady state data available_(supplied by Reactor Engineering) on OPS Form 3209-1 CAUTION: Ensure proper use of signs (+ or -) throughout this calculatio .12 Enter Estimated Conditions at Time of Criticalit Data for Date, Time, Temperature, and Pressure, are estimated. The , Burnup is entered at the existing conditions. The boron - concentration should be the desired critical boron concentration (normally the existing boron concentration).
5.13 Item 1. Determine the power defect at the Reference Powe The number on the curve is negative but a positive number should be entered on OPS Form 3209A-2 (Use OPS Form 3209-3).
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OP 3209A Page 7 Riv. 0
. . .
5.14 Moderator Defects - Item NOTE: The power defect curve assumes the reactor is operating
, -
with Tavg equal to Tref i 2 If Tavg is not equal to Tref i 2'F it will be necessary to perform Step 5.1 . 5.1 Determine the difference between T average at the reference condition'and Tref at the reference conditio Multiply this difference by the Moderator Temperature Coefficient (MTC) (OPS Form 3209-4/5) at the reference T., :- I' condition to determine the moderator defect. (This
~1[f 2 I- "number will be negative if Tavg > Tref and MTC is negative.)
NOTE: If the estimated critical temperature is other than 557 F it'will be necessary to perform Step 5. .1 Determine the difference between Tavg at the estimated condition and 557 F. Multiply by the MTC (OPS Form 3209-4/5) to determine Moderator Defect at the Estimated Condition. (The Value is Negative if Tavg
> 557'F and MTC negative.)
i NOTE: If the computer is'not available, use OPS Form 3209-5 and OPS Form 3209-6 to obtain Xenon worth if the reactor was shutdown from an equilibrium Xenon state. If the reactor was not at or near an equilibrium
. . Xenon state prior to shutdown, Reactor Engineering will determine Xenon wort '
l
.
.
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OP 3209A Page8'[ .? Rev.*0
.
5.15 Item 3. Determine the Xenon worth at the estimated time of criticality (use SP 3R7/3R9 or OPS Form 3209-5/6. Subtract the reference Xenon worth fromLthe estimated Xenon worth to obtain the Xenon defect. (The value is Negative if estimated Xenon is
*
greater than reference Xenon.)
5.16 Item 4. Repeat Step 5.15 for determining Samarium worth. (Use SP 3R7/3R9 or OPS Form 3209-7).
~ 5.17 Item 5. Determine the Differential Boron Worth at the present boron rencentration. Multiply by the change in boron
~
concentration from the present condition to the reference condition to obtain the boren defect. The value is Negative if the present boron concentration is greater than the reference boron concentration. (Use OPS Form 3209-11.)
5.18 Item 6. Add all the reactivity defect Cerrect for burnup if the difference between the reference burnup and present burnup is greater than 200 Kn'D/HT .19 Item 7. Multiply the total Reactivity Defect by -1 and add it to the control rods worth inserted at the reference conditio If the resulting value is positive dilute the RCS or wait for Xenon to deca .20 Item 8. If the value determined in Step 5.19 is negative determine critical rod height from OPS Form 3209-8. Determine the i 900 pcm lim' ts around the ECC by using the rod worth at the ECC. Add ano subtract 900 pcm from the ECC and obtain the equivalent rod position using OPS Form 3209-8, 9, or 10. Do not allow the maximum rod insertion to exceed the 0% power Rod Insertion Limit (RIL) or the minimum rod insertion to exceed any rod withdrawal limits imposed unless physics tests are ir progres .21 Give OPS Form 3209A-1/0PS Form 3209A-2 completed through
, , , . , ,
item 8 to another licensed operator for review and approva .22 Af ter going critical, stabilize power in the zero power range
.s (approximately 10 amp on the intermediate range) and record
' actual critical dat .
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OP 3209A Page 9
. - Rev. 0 .
5.23 Forwcrd completed OPS Form 3209A-1/3209A-2 to Reactor Fngineering for revie . CNECK0FF LISTS 6.1 OPS Form 3209A-1, Estimated Critical Condition, Fixed Rod .2 OPS Form 3209A-2, Estimated Critical Condition, Fixed Boro . 3 OPS Form 3209-3, Power Defect 6.4 OPS Form 3209-4, Moder'ator Temperature Coefficient 6.5 OPS Form 3209-5, Xenon Worth At Steady State 6.6 OPS Form 3209-6, Xenon Worth After Trip 6.7 OPS Form 3209-7, Samarium Worth After Trip 6.8 OPS Form 3209-8, Integral Rod Worth In Overlap HFP, EQ Xenon, BOL 6. 9 OPS Form 3209-9, Integral Rod Worth Bank D only HF?, EQ Xenon, BOL 6.10 OPS Form 3209-10, Integral Rod Worth HZP, Xenon Free, BOL 6.11 OPS Form 3209-11, Boron Worth 6.12 OPS Form 3209-12, Boron Required For Shutdown 6.13 OPS Form 3209-13, Boron Rundown 6.14 CPS Form 3209-14, Core Data 6.15 OPS Form 3209-15, ECC Reference Data DH:jlm H l l l l-l l l ? !
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CALCULATED BY 0 ATE APPRKE0 SY OATE ESTIMATED CRITICAL CONDITION - FIXE 0 R00 POSITION REFERENCE CRITICAL DATA G,/ h ) TIME 0100 DATE 62V4&BP / //r7// 7 RCS TAVG SR7 'F , RCS PRESSURE 2250 PSIA POWER 100 % RCS BORON 900 ppm BURNUP 4015 , MWD /MTU CONTROL BANK 0 180 STEPS CONTROL BANK C 2E' STEPS OTHER _ 100% oower maintainna h lao m a2 j e pcm (-)
'
XENOR SAMARIUM pcm (-) LAST SHUTOOWN TIME 1550 DATE 11/17/87 ESTIMATED STATUS AT CRITICALITY DATE 12/15/87 TIME 2100
'F RCS PRESS 2250 psia TAVG 557 ppia BURNUP (PRESENT) 4015 MWD /MTU BORON (PRESENT) 1200
,
DESIRED CRITICAL POSITION AT 150 STEPS BANK C _ POWER DEFECT (OPS Form 3209-3)
(STEP 5.3)
1.1 Reference Power % pcm 1.2 pcm at Reference Power
. MODERATOR DEFECT. (OPS Form 3209-4)
(STEP 5.4.1)
'F
.
2.1 Tavg (at reference conditions) 587 2.2 Tref (at reference conditions) 587 'F N/A pcm/'F 2.3 MTC (at reference conditions) 2.4 Moderator Defect (at reference conditions) ti/A pcm (2.1 - 2.2) X MTC =
.
OPS Form 3209A-1 Rev. O Page 1 of 4
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(STEP 5.4.2)
2.5 Estimated Tavg 557 'F 2.6 MTC (at estimated conditior)s) N/A pcm/*F 27 Moderator Defect at estimated conditions N/A pcm (2.5 - 557) x MTC = 3. XENON DEFECT (Computer or OPS Form 3209-5/6) circle on (STEP 5.5) 3.1 Estimated Xenon pcm (-) 3.2 Reference Xenon ~ pcm (-) pcm 3.3 Xenon Defect (3.1 - 3.2) SAMARIUM DEFECT (Computer or OPS Form 3RQ9xX) circle on (STEP 5.6) 4.1 Estimated Samarium 685 pcm (-) 4.2 Reference Samarium pcm (-) pcm 4.3 Samarium Defect (4.1 - 4.2)
(STEP 5.7) INTEGRATED ROD WRTH (OPS Form 3209-8/QgQ) Use 3209-8 ONLY
' 5.1 Estimated Rod Worth pcm (-) 5.2 Reference Rod Worth pcm (-) pcm 5.3 Rod Worth Defect (5.1 - 5.2) BORON DEFECT l (STEP 5.8) 6.1 Present Boron Concentration ppm ppm 6.2 Reference Boron Concentration 6.3 Boron Worth (OPS Form 3209-1) p',m/ ppm (-) l pcm 6.4 Boron Defect (6.1 - 6.2) x 6.3 '
.
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_ OPS Form 3209A-1 Rev. 0 - Page 2 of 4 'ig 9 'g ; - '._ o . _ . __
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- . CALCULATIONS I (STEP 5.9)
7.1 Sum Defects (1.2 + 2.4 + 2.7 + 3.3 + 4.3 + 5.3 + 6.4) pcm 7.2 . Boron Equivalent of Defects (7.1 + 6.3) ppm 7.3 Nominal PPM at Reference BU , fl/A ppm 7,4 Nominal PPM at Present BU _ fl/A _ ppm 7.5 Burnup Change (7.3 - 7.4) fl/A ppm (+)
~
7.6 Boron Change 1,o Go Critical (7.2 + 7.5) ppm 7.7 Critical Boron Concentration (6.1 - 7.6) ppm LIMITS ON CONTROL R0D POSITIO (STEP 5.10) 8.1 Rod Worth at ECP , Bank at ,_,,_ steps pcm (-) 8.2 Rod Worth at Minimum Insertion (8.1 + 900 pcm) pcm
- 8. 3 Rod Position at Minimum Insertion Bank , at steps 8.4 Rod Worth at Maximum Insertion (0.1 - 900 pcm) pcm (-)
8.5 Rod Position at Maximum Insertion (Cannot be below 0% power rod insertion limit) Bank at steps ACTUAL CRITICAL DATA (STEP 5.22) DATE f1/A TIME N/A
.
i Rod Position Control Bank D at f1/A Steps Control Bank C at fl/A Steps Other: N/A Tavg Loop 1 T411A N/A *F Loop 2 T421A N/A 'F Loop 3 T431A fl/A *F Loop 4 T441A fl/A 'F OPS Form 3209A-1 Rev. O Page 3 of 4
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' o DIFFE.iENTIAl. BORON WORTH VS. BORON CONCENTRATION AT BOL AND EOt. CYCLE 1 5(
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EDIN APPKND BY UNIT 3 SUPDm7FENDE;7F EFTMII\E DME POIC FnG 17), MISmrJ ANEOUS 00RE D7CA Total Shutdcun and Control Bank Worth Ibt Zero Pcwar Xenon Frec 9010 pcm
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ibrst Case Stuck Pod at B3L is F-2 #! 1110 pcm
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t RIuilibriun Samarim after 25 days of operation at a steady state pcuer level -600 pan
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hy at BOL .0069 ".j:'i-Refueling Boron (bncentration to traintain kdf < .95 with all rods inserte ppn RefuelingBoron (bncentration to naintain k 2000 ppu eff < .95 with all reds out Ops Pom 3209-14 rev 0 Page 1 of 1 (
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ATTACH!iENT 3
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CORE HEAT BALANCE Average over Measurement Interval Pzr Pressure 2250 psia RCS Loop 3 Tc 557 *F Letdown Flow (CHS-F132) 75 gpm Charging Flow (CHS-F121) 87 gpm Charging Pressure (CHS-P120) 2500 psia Charging Temperature (CHS-T126) 510 *F VCT Temperature (CHS-T116) 100 F S/G 1 S/G 2 S/G 3 S/G 4 l
. Steam Pressure (PSIA) 1100 SAFE Blowdown Flow (gpm) 50 As Feed Temperature (*F) 420 S/G Feed Pressure (PSIA) 1400 1 l Letdown Enthalpy (From A & B) BTU /lbm Charging Enthalpy (From E & F)
4 BTU /lbm ,g P .' Charging Specific Volume (From E & fy ft3/lbm ) Charging Flow Correction Factor-5 N/A
.12716 x 2.0 x 10 x(CHS-T116)+ .9983 =
x 1.0011 ) p
@r n
l Where V is the specific volume of the Charging Fluid (CHS-T116 and CHS-P120).
l l l Correcteu Charging Flow (DxQ) N/A gpm , Charging Flow (60xR)/(7.48xP) N/A lbm/hr CVCS Heat Loss Sx(M-N)/3412141 4.69 MWT RCP Seal Flow (Tetal)-12 gpm N/A gpm l Seal Enthalpy (From E & G) BTU /lbm l Seal Specific Volume (From E & G) N/A ft3/lbm Corrected Seal Flow (60xU)/(7.48xW) N/A lbm/hr Seal Heat Loss (X)x(M-V)/3412141 4.74 m(T I ENG form 31002-5 Rev. O Page 2 of 3
.
S/G 1 S/G 2 S/G 3 S/G 4 Feed Enthalpy BTV/lbm (From J & K) AA. SAT STM Enthalpy BTV/lbm (From H) BB. SAT Water Enthalpy BTV/lbm (From H) CC. S/G Enthalpy (AA) 00. S/G a Enthalpy (CC-Z) SAME EE. Actual Feed Flow 1.9 E+6 AS FF. S/G Power [(EE)(OD)] BTU /hr S/G GG. Sat Water Spec. Vol. (From H) 1 HH. Blowdown Flow (60xl)/(7.48 x GG) N/A JJ. Blowdown Loss (EdkOD-BB)] -0- } KK. Total S/G Power (FF - JJ) BTU /hr LL. Total NSSS Power I (KK) BTU /hr _ _ _ _ MM. LL/3412141 = MWT NN. Net RCP Heat Input = 16 MWT PP. TOTAL CORE POWER (MM-NN+T+Y) = MWT CORE POWER in % (PP)(1CO)/3411 = % l l
' l 26 I i - ATTACHMENT 4 Table 3 .
Properties Of superheated steam and compressed water (temperature and pressure) I Abs pres Temperature, F ; J lb/sq i (sat. temp) 100 200 300 400 500 600 700 800 900 1000 1100 1200 1300 1400 1500 , I l 63 .7 1 r 0 0161 392 5 45 .9 57 h 68 00 1150 2 1195 7 1241.8 1288 6 1336 1 13845 (101.74) : 0.1295 2.0509 2.1152 2.1722 2 2237 2 2708 23144 ,
'
r 0 0161 78 14 90 24 102 24 114.21 126.15 138 08 150 01 161 94 173 86 185 78 197.70 209 62 221.53 23345 I ' 5 h 68 01 1148.6 1194 8 1241.3 1288 2 1335 9 1384.3 1433 6 1483.7 1534.7 1586 7 1639 6 1693 3 1748 0 1803 5 I (162 24) s 0.1295 1 8716 1.9369 1.9943 2.0460 2.0932 2.1369 2.1776 2 2159 2.2521 2.2866 2 3194 2 3' 99 2.3811 2.4101 I i e 0.016) 38 84 44 98 51.03 57.04 63 03 69 00 74 98 80 94 86 91 92 87 98 84 104 80 110 76 116 72 10 h 68 02 1146.6 1193 7 1240 6 1287.8 1335 5 1384 0 1433 4 1483 5 1534 6 1586 6 1639 5 1693.3 1747.9 1803 4 l (193.21) s 0 1295 1.7928 1.8593 1.9175 1.9692 2.0166 2.0603 2.1011 2.1394 2 1757 2.2101 2.2430 2 2744 2.3046 2 3337 { r 0 0161 0 0166 29 899 33 963 37.985 41.986 45.978 49.964 53 946 57.926 61.905 65 882 69 858 73 833 77.807 15 h 68 04 168 09 1192 5 1239.9 1287.3 1335 2 1383.8 1433 2 1483.4 1534 5 1586 5 1639 4 1693 2 1747.8 1803 4 (213 03) s 0 1295 0 2940 1.8134 1 8720 1.9242 1.9717 2.0155 2.0563 2.0946 2.1309 2.1653 2.1982 2 2297 2 2599 2 2890 i r 0.0161 0 0166 22.356 25 428 28 457 31.466 34.465 37.458 40 447 43 435 46 420 49 405 52 388 55 370 58 352 6 20 h 68 05 168.11 11?l.4 1239 2 1286.9 1334 9 1383.5 1432 9 1483 2 1534 3 1586.3 1639 3 1693.1 1747.8 1803 3 (227.96) s 0.1295 02940 1.7605 1.8397 18921 1.9397 1.9836 2.0244 2.0628 2 0991 2 1336 2 1665 2 1979 2 22S2 2 2572 r 0 0161 0 0166 11.036 12 624 14.165 15 685 17.195 18 699 20 199 21 697 23 194 24 689 26.183 27.676 29 168 > 40 h 68.10 168.15 l 1186 6 1236.4 1285 0 1333 6 1382.5 14321 1482 5 1533 7 15S5F 1638 8 1992.7 1747.5 1803 0 '
(267 25) s 0 1295 0 2940 'l6992 1.7608 1.8143 1.8624 1.9065 1 9476 1.9360 2 0224 2 0569 2 0S99 2.1224 2.1516 2.1807 i r 00161 00166 7 257 8 354 9 400 10.425 11.438 12 446 13450 14 452 '.5.452 16 450 17.448 18 445 19 441 60 h 68 15 168 20 1181.6 1233.5 1283 2 1332.3 1381.5 1431 3 1481 8 1533.2 1585.3 1633 4 1692 4 1747.1 1802 8 (292 71) s 0 1295 02939 1.6492 17134 1.7681 1.8168 1.8612 1.9024 1.9410 1.9774 2.0120 2 0450 2.0765 2.1068 2.1359 ,
r 0 0161 0.0166 0.0175 6 218 7.018 7.794 8.560 9 319 10 075 10 829 11 581 12 331 13 081 13.829 14 577 , 80 h 68;.1 168 24 269 74 1230 5 1281.3 1330.9 1380.5 143v.5 1481.1 1532 6 1584 9 1638 0 1692.0 1746 8 180 (312.04) s 0.1295 0 2939 0.4371 1.6790 1.7349 1.7842 1.8289 1.8702 1.9089 1.9454 1.9800 2.0131 2.0446 2.0750 2.1041 r 00161 00166 0.0175 4 935 5.588 6 216 6 833 7.443 8 050 8 655 9 258 9 860 10 460 11.060 11.659 100 t 68 26 168 29 269 77 1227.4 1279 3 1329 6 1379 5 1429 7 1480 4 1532 0 1584.4 1637,6 1691 6 1746.5 1802 2 (327.82) s 0 1295 0 2939 0.4371 1.6516 1.7088 1.7586 1.8036 1.8451 1.8839 1.9205 1.9552 1.98B3 2 0199 2 0502 2.0794 r 0 0161 0 0166 0 0175 4 0786 4 6341 5 1637 5 6831 6.1928 6 7006 7.2060 7.7096 82119 8 7130 9 2134 9 7130 120 h 68 31 IE.8 33 269 81 1224.1 1277 4 1320 1 1378 4 1428 8 1479 8 1531 4 1583.9 1637.1 1591 3 1746 2 180 (341.27) s C.1295 0 2939 0.4371 1.6286 1.6872 1.7376 1 7829 1.8246 1.8635 1 9001 1.9349 1.9680 1.9996 2 0300 2 0592 l r 0 0161 0 0166 0 0175 3.4661 3 9526 4.4119 4 8585 5.2995 5.7364 6.1709 6 6036 7.0349 7.4652 7 8946 8 3233 140 h 68.37 16S 33 269 85 1220 8 1275.3 1326 8 1377.4 1428.0 1479.1 1530 6 15S3 4 1636 7 1690 9 1745 9 180 (353 04) s 0.1295 0 2939 0.4370 1.6085 1.6686 1.7196 1.7652 1.8071 1 8461 1.8328 1 9176 1.9508 1 9325 2.0129 2 0421 v 00161 0.0166 0 C175 3.0060 3 4413 3 8430 42420 4 6205 5.0132 5 3945 5.7741 6.1522 6 5293 6 9055 7 2811 160 h 68 42 168 42 269.89 1217.4 1273.3 1325 4 1376 4 1427.2 1478 4 1530 3 1582 9 1636.3 16905 1745 6 180 (363 55) : 0.1294 02938 0 4370 1.5906 1.6522 1.7039 1.7499 17919 1.8310 1.8678 1.9027 19359 1.9676 1.9980 2 0273 v 0.0161 0.0166 0 0174 2 6474 3.0433 3 4093 3.7621 4.1084 4 4505 4 7907 5.1289 5.4657 5.8014 6.1363 6.47,04 180 h 68 47 168 47 269.92 1213 8 1271.2 1324 0 1375.3 1426.3 1477.7 1529 7 1582.4 1635.9 1690 2 1745.3 1801 2 (373 08) s 0.1294 02938 0.4370 1.5743 L6376 1.6900 1.7362 1.7784 1.8176 1.8545 1.8894 1.9227 1 9545 IS849 2 0142 v 0 0161 0 0166 0 0174 2 3598 2.7247 3 0583 3 3783 3 6915 4.0008 4 3077 4 6128 4.9165 5.2191 55209 5 8219 200 h 68 52 168 51 269.96 1210.1 1269 0 1322 6 1374 3 1425.5 1477.0 1529.1 1581.9 1635 4 1689.8 1745 0 180 (381.80) s 0.1294 0 2938 0 4369 1.5593 1.6242 1.6776 1.7239 1.7663 1.8057 1.8426 1.8776 1 9109 1 9427 1.9732 2.0025 v 0.0161 0 0166 0 0174 0 0186 2.1504 2.4662 2.6872 2.9410 3.1909 3.4352 3 6837 3 9278 4 1709 4 4131 4 6546 250 h 68 66 168 63 270 05 375 10 1263.5 1319 0 1371.6 1423 4 1475.3 1527 6 1580.6 1634 4 1688 9 1744 2 1800 2 (400.97) s 0 1294 0.2937 0 4368 0.5667 1.5951 1.6502 1.6976 1.7405 1.7801 18173 18524 1 8858 1.9177 1 9482 1.9776 v 0 0161 0 0166 0 0174 0.0186 1.7655 2.0044 2 2263 2 4407 2.6509 2 8585 3 0643 3 268S 3 4721 3 6746 3 8764 300 A 68 79 16834 270.14 375.15 1257.7 1315 2 1368 9 1421.3 1473 6 1526 2 1579 4 1633 3 16800 1743 4 1799 6 (417 35) : 0.1294 0 2937 0 4307 0.5665 1.5703 1.6274 1 6758 1.7192 1 7591 1.7964 1.8317 1.8652 1 8972 1.9278 1.9572 v 0 0161 0 0166 0 0174 0.0186 1.4913 1.7028 1 8970 2.0832 2 2652 2.4445 2.6219 2 7980 2 9730 3 1471 3 3205 350 h 68 92 168 85 27024 375 21 1251.5 1311.4 1366 2 1419 2 1471.8 1524 7 1578 2 1632 3 16.87.1 1742 6 1798 9 (431 73) s 01293 0 2936 0 4367 05664 1 5483 1.6077 16571 1.7009 1.7411 1.7787 18:41 18477 18795 19105 19400 v 0 0161 0 0166 0 0174 0 0162 12841 1.4763 1 6499 '. 8151 19759 2 1339 2 2901 2 4450 2 5987 2 7515 2 9037 400 h 69 05 168 97 270 33 37527 12451 1307 4 1363 4 14170 14701 1523 3 1576 9 1631 2 16S6 2 1741 9 1795 2 (444 60) s 01293 0 2935 0 4366 0.5663 15282 1.5901 1 6406 16850 1.7255 17532 1.793S 18325 1 8647 18955 19250 r 0 0161 0 0166 0 0174 0 0186 0 9919 1.1584 1 3037 1.4397 1.5708 1 6992 1 8256 1 9507 2 0746 2 1977 2 3200
$00 h 69 32 169 19 270 51 375 38 1231.2 12991 1357 7 1412 7 1466 6 1520 3 1574 4 16291 1634 4 1740 3 1796 9 (467 01) s 0 1292 0 2934 0 4364 0 5660 1 4921 1.5535 1 6123 1 6578 1 6990 1 7371 1 7730 1 8069 1 8393 1.8702 1 3993 . . _ _
f
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. st'eami thstmodyn2mics of steam 27 '
4-
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. ' Table 3 Properties of superheated steam and compressed water (temperature and pressure).
_ Abs pres Temperature, F lb/sq i ,
(sat. temp) 100 -200 300 400 500 _600 700 800 900 1000 1100' 1200 1300 1400 1500 v 0 0161 ,0 0166 0 0174 0.0186 0.7944 0 9456 1 0726 'I.1892 1.3008 1.4093 ~1.5160 1.6211 1.7252 1.8284 1.9339 600 h 69 58 -169 42 270 70 375 49 1215 9 1290 3 1351.8 1408 3 1463 0 1517.4 1571.9 '1627.0 1682.6 1738 8 1795 6 (486.20) s 0.1292 0.2933 0 4362 0.5657 1.4590. 1.5329 1.5844 -l.6351 1.6769 1.7155 1.7517 1.7859 1.8184 1.8494 1.8792 v 0 0161' O.0166 'O.0174 00186 0.d204 0.7928 0.9072'l.0102 1.1078 1.2023 1.2948 1.3858' l.4757 1.5647 1.6530 700 h 69.84 169.65 270 89 375.61 487.93 1281.0 1345.6 1403.7 1459.4 1514.4 1569 4 1624.8 1680.7 1737.2 179 (503.08) s 0.1291 0.2932' 0 4360 0 5655 0.6889 1.5090 1.5673 1.6154 1.6580 1.6970'l.7335 1.7679 1.8006 1.8318 1.861 .v 0.0161 0.0166 0 0174 0.0186 0.0204 0.6774 0.7828 0 8759 0.9631 1.0470 1.1289 -1 2093 1.2885 1.3669 1.4446 800- h 70.11 169 88 271.07 375.73 487.88 1271.1 1339 2 1399.1 1455.8 1511.4 1566.9 1622.7 1678.9 1735.0 179 (518.21) s 0.1290 0.2930 0.4358 'O.5652 0 6885 1.4869 1.5484 1.5980 1.6413 1.6807 1.7175 1.7522 1.7851 1.8164 1.8464 v 0 0161 0.0166 0 0174 0.0186 0 0204 0.5869 0 6858 0 7713 0 8504 .0 9262 0.9998 1.0720 1.1430 1.2131 1.2825 900 h -70.37 170.10 271.26 375.84 487.83 1260 6 1332.7 1394.4 1452.2 1508.5 1564.4 1620 6 1677.1 1734.1 179 ' (531.95) s 0.1290 0.2929' O.4357 0.5649 0.6881 1.4659 1.5311 1.5822 1.6263 1.6662 1.7033 - 1.7382 1.7713 1.8028 1.8329 y 0.0161 0.016f 0 0174 0.0186 0.0204 0.5137 0 6080 0 6875 0.7603 0 8295 0.6966 0.9622 1 0266 1.0901 1.1529 '1000 h 70.63 170 33 271.44 375.96 487.79 1249 3 1325.9 1389 6 1448.5 1504.4 1561.9 1618 4 1675.3 1732.5 179 (544 58) s 0.1289 02928 0 4355 0.5647 0.6876 1.4457 1.5149 1.5677 1.6126 1.6530 1.6905 1.7256 1.7589 1.7905 1.8207-v 0 0161 0.0166 0.0174 0.0185 0 0203 0 4531 0 5440 0.6188 0 6865 0.7505 0 8121 0.8723 0.9313 0.9894 1.0468 1100 h 70.90 170.56' 271.63 376.08 487.75 1237.3 1318 8 1384.7 1444.7 1502.4 1559 4 1616.3 1673.5 1731.0 178 (556.28) s 0 1289 0.2927 0.4353 0.5644 0 6872 1 4259 1.4996 I.5542 1.6000 1.6410 1.6787 1.7141 1.7475 1.7793 1.8097 .
v 0 0161 0 0166 0 0174 0.0185 0.0203 0 4016 0 4905 0 5615 06250 0.6845 0.7418 0.7974 0 8519 0.9055 0.9584 l 1200 h 7Ll6 170.78 271.82 . 376.20 487.72 1224 2 1311.5 1379 7 1440 9 1499.4 1556.9 1614 2 1671.6 1729.4 178 g (567.19) s 0.1288 0.2926 04351 0.5642 0.6868 1.4061 1.4851 1.5415 1.5883 1.6298 1.6679 1.7035 1.7371 1.7691 1.7996 ; y 0.0161 0 0166 .0.0174 0.0185 0.0203 0.3176 04059 0.4712 0.5282 0 5809 0 6311 0.679S 0.7272 0.7737 0.8195 5 1400 h 71 68 171.24 272.19 376.44 487.65 1194.1 1296.1 1369.3 1433 2 1493 2 155) 8 1609 9 1668 0 1726.3 178 {
(587.07s s 0.1287 0 2923 0.4348 '0 5636 0 6859 1.3652 1.4575 1.5182 1.5670 1.6096 1.6484 1.6845 1.7185 1.7508 1.7815
[
v 0 0161 0 0166 0.0173 0.0185 0 0202 0 0236 0.3415 0 4032 0.4555 0.5031 0.5482 0 5915 0.6336 0.6748 0.7153-1600 h 72 21 171.69 272.57 376.69 487.60 616.77 1279.4 1358.5 1425.2 1486.9 1546.6 1605.6 1664.3 1723.2 178 (604.87) s 0.1286 0.2921 0 4344 0.5631 0 6851 0 8129 1.4312 1.4968 1.5478 1.5916 1.6312 1.6678 1.7022 1.7344 1.7657 y 0 0160 0.0165 0 0173 0.0185 0 0202 0 0235 0 2906 0.3500 0.39S8 0.4426 0 4836 0 5229 0 5609 05930 0 6343 * 1800 A 72.73 172.15 272.95 376.93 487.56 615.58 1261.1 1347.2 1417.1 1480.6 1541.1 1601.2 1660,7 1720.1 1779 7 (621 02) s 0.1284 0 2918 0.4341 0 5626 0.6843 0 8109 1.4054 1.4768 1.5302 1.5753 1.6156 1.652S 1.6876 1.7204 1.7516 v 0.0160 0.0165 0 0173 0 0184 0 0201 0.0233 0.2488 0 3072 0 3534 0.3942 0 4320 -0 4680 0.5027 0.5365 0.5695
. 2000 h *
73 26 172.60 273.32- 377.19 487.53 614.48 1240.9 1353.4 1408 7 1474.1 1536.2 1596.9 1657.0 1717.0 177 (635 80) s 0.1283 0.2916 0.4337 05621 0.6834 0 8091 1.3794 1.4578 1.5123 1.5603 1(014 16391 1.6743 1.7075 1.7333 v 0.0160 0.0165 0 0173 0 0184 0.0200 '0 0230 0.168) 0 2293 0.2712 0.306S -0.3390 0.3692 0 3980 0.4259 0.4529 22500 h 74.57 173.74 274 27 377.82 487.50 612.08 1176.7 1303.4 1386.7 1457.5 1522 9 1585.9 16478 1709.2 177i4 (668.11) s 0.1280 0.2910 0.4329 0.5609 0.6815 0.8048 1.3076 1.4129 1.4766 1.5269 1.5703 1.6094 1.6456 1.6796 1.7116 , v 0.0160 0 0165 0.0172 0.0183 0.0200 0 0228 00982 0.1759 0 2161 0.2484 0.2770 0.3033 0.3282 . 0.3522 0.3753 3000 h 75 88 174.88 275 22 378 47 487.52 '610 08 10o0.5 1267.0 1363 2 1440 2 1509.4 1574.8 1638.5 1701.4 176 (695.33) s 0.1277.0.2904 0.4320 0.5547 0.6796 0.8009 1.1966 1.3692 1.4429 1.4976 1.5434 1.5841 1.6214 1.6561 1.6888 v 0.0160 0.0165 0.0172 0 0183 0.0199 00227 00335 0.1588 0.1987 0.2301 0 2576 0 2827 0.3065 0.3291 0.3510 3200 h .7 .3 27 .7 48 .4 800 8 1250.9 1353 4 1433.1 1503.8 1570.3 1634.8 1698.3 176 (705.08) s .0.1276 0.2902 0.4317 0.5592 0.6788 0.7994 0 9708 1.3515 1.4300 1.4866 1.5335 1.5749 1.6126 1.6477 1.6806 v 0.0160 0.0164 0.0172 0 0183 0 0199 0.0225 0 0307 0.1364 0.1764 0.2066 0.2326 0 2563 0.2784 0 2995 0.3198 3500 h 7 .0 276 2 379.1 487.6 608 4 779.4 1224.6 1338.2 1422 2 1495.5 1563 3 1629 2 1693.6 175 s 0.1274 0.2899 0.4312 0.5585 0.6777 0.7973 0.9508 1.3242 1.4112 1.4709 1.5194: 1.5618 1.6002 1.6358 1.6691 l'
.
v 0.0159 0.0164 0.0172 0 0182 0 0198 0.0223 0.0287 0.1052 0.1463 0.1752 0.1994 0 2210 0 2411 0.2601 0.2783 ) 4000 h 78 5 17 .1 37 .7 606 9 763 0 1174 3 1311.6 1403 6 1481.3 1552.2 1619 8 1685.7 175 : s 01271 0 2893 0.4304 0.5573 0.6760 03940 0.9343 1 2754 1.3307 1.4461 1.4976 1.5417 1.5812 1.6177 1.6516 v 0.0159 0.0164 0.0171 0 0181 0 0196 0.0219 0.0268 0 0591 0.1038 0.1312 0.1520 0.1718 0.1890 0 2050 0.2203 5000 h '8 S81 C04 6 746 0 1042.9 125?.9 1364 6 1452.1 1529.1 1600.9 1670 0 173 s 01265 0 2881 0 4287 0 5550 06726 0 7880 0 9153 1.1593 1 3207 1.4001 1 45S2 1 5061 15481 1.5S63 1.6216 v 0 0159 0 0163 0.0170 0 0,80 0.0195 0.0216 0 0256 0 0397 0 0757 0.1020 0.1221 0 1391 0 1544 01634 0.1617 6000 h 83 7 18 .0 31, .9 736.1 9451 1IP3 S 1323 6 1422 3 1505 9 1532 0 1654 2 1724 2 s 0.1258 02870 0 4771 0 5528 0.6693 0 7826 0.9026 10176 1 2615 1.3574 1 4229 14743 1.5194 1 5593 15962 , y 0.0158 0 0163 0 0170 0.0180 0 0193 0.0213 0.0248 0 0334 0 0573 0 0816 0.1004 0 1160 0 1293 0.1424 0 1542 7000 h 86 2 184 4 283 0 384 2 4E9 3 60 .8 1124 9 12Al 7 1397 2 1426 1%31 1633 6 171 s 0.1252 0 2859 0 4256 0 5507 0 6663 0 7777 0.8926 1 0350 1.2055 1.3171 1.3904 1 4466 14935 1 5355 1 5735
! . ~ .,
l
. .. .
ACP-QA 2.068 Page g 1-
. Rev, 7 ATTACHMENT 5'-
: .
.
.
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NUCLEAR ENGINEERING AND OPERATIONS PRO,CEDURE
' NEO 8.01 JUMPER, LIFTED IIAD AND BYPASS CONTROL
.
APPROVED h 'F GuL Senior.# ice Pr'e dident, Nuclear Engineering and Operations REVISION 1A
'
DATE August 15, 1986 __ CONCURRENCE A e_ s'suranc V m_b
Manager, ! i
, , . _ . ~~ ~ ~ ~ ~ - - - _ _ . . , , - - . . . . . . _ _ . . . . . .
ACP-QA-2.06B Page 3
.'. .
J
7 Rev. 7
* *
NUCLEAR ENGINEERING AND OPERATIONS PROCEDURE NEO 8.01 JUMPER, LIFTED LEAD AND BYPASS C0hTROL ," 1.0 PURPOSE The purpose of this procedure is to define, control and specify the review requirements for jumpers, lif ted leads, and bypasses in a manner that . ensures conformity with design intent and operability requirements and preserves plant and personnel safety. Changes that are not defined in this procedure are addressed in Reference Jumpers, lifted leads, and bypasses that are positively identified and controlled in other station-approved procedures that meet the requirements of Section 6.1 are excluded from the requirements of this procedure. However, this procedure may be, in part or in, entirety, r ' implemented whenever additional control is desired even though implementation is not specifically require .0 APPLICABILITY
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This procedure applies to the Nuclear Engineering and Operations (NEO) Group, including the Northeast Nuclear Energy Company (KNECO) and the Connecticut Yankee Atomic Power Company (CYAPCO).
3.0 REFERENCES Northeast Utilities Quality Assurance Topical Report, Section 3 - l I Design Control; Section 11 - Test Control; and Section 14 - l Inspection, Test, and Operating Statu .2 ANSI N18.7-1976 - Aoministrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plant .3 NEO 3.03 - Preparation, Review, and Disposition of Plant Design Change Request (PDCRs).
3.4 NEO 3.12 - Safety Evaluation .- l
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4.0 DEFINITIONS l l Blind or Blank Flange _ A plate-like device in a mechanical system to stop flo .2 Disabled Annunciator Alarm A change that disables the visual and/or audible alarm function of an annunciator.
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., * 4.3 Electrical Jumper l . A temporary electrical connection that byp.sses a component within an electrical circuit, changing the circuit design or configuration. Jumpers may be made permanent through the PDCR process (Reference 3.2) in which case the jumper become permanent and is no longer referred to as a jumpe .
4.4 Hechanical Jumper
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A ' temporary connection such as a spool piece, bose, tubing, or piping that joins two systems together or bypasses a component within a system, thus changing the system's design or configu-ratio (This does not include hoses connected from syst drains to floor drains or providing air to pneumatic tools or breathing apparatus.)
4.5 Lifted Lead A break in continuity of a circuit such that one connection of a wire previously connected to two terminals is renove , 4.6 Shielding Material used to attenuate radiatio .7 Other Bypass and Jueper Devices 4. In addition to the items defined in 4.1 to 4.6 the following are also considered bypasses or jumper device .7. Gagged relief or safety valves 4.7. Installed / removed filters or strainers (other than for routine maintenance) 4.7. Plugged floor drains 4.7. Pulled circuit cards 4.7. Gagged or blocked proce-ss control valves , 4.7. Block walls .- 4.8 Jumper, Lif ted l ead and Bypass Control Log A log maintained by operations personnel in the control roo This log shall consist of all active Jumper, Lif ted Lead and Bypass Sheets (Attachment 8. A) and the Jumper, Lif ted Lead and Bypass Index sheets (Attachment 8.B). Each Jumper, Lifted Lead or Bypass request shall have a unique number assigne . NEO 8.01 Rev. Date: 08/15/86 Page 2 of 12
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. Bypass - Lif ted Lead and Jumper Control Tag - .
A uniquely numbered tag (Attachment 8.C) used to identify each Jumper, Lif ted Lead or Bypass in accordance with this procedur ,
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4.10 Safety Evaluation A safety evaluation is a written review of the change completely
. in accordance with Reference 3.4. The review is the responsi-bility of the Unit Engineering Staff (it may be performed by NUSCO Engineering) and independently reviewed by the Unit Engineering Supervisor or his designe .11 Technical Evaluation A technical evaluation is a written in-depth evaluation of items checked either "YES" or "DON'T KN0k"' on Attachment 8. A, Section A - Technical Assessment. The review is the responsi-bility of the Unit Engineering Staf f (it may be performed by NUSCO Engineering) and independently reviewed by the Unit Engineering Supervisor or his designe .12 Operable The definition of operable is the current definition found in the associated unit's technical specificatio .13 Safety-Related Systems Category I, radioactive waste and fire protection system .14 Safety Assessment A safety assessment is a review of the proposed Jumper, Lif ted Lead or Bypass to determine whether a safety evaluation is require .15 Technical Assessment A technical assessment is a review of the proposed Jumper, Lif ted Lead or Bypass to determine whether a technical evalua-tion is require .-
4.16 Duty Officer Qualified Person A station employee who periodically stands Unit Duty Officer watches. He need not be on duty to execute his responsibilities under this procedure.
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Rev. 7 5.0 RESPONSIBILITIES
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5.1 Vice President, Nuclear Operations Responsible for maintaining this procedure curren .2 Plant Operations Review Committee (PORC) Responsible for reviewing all Jumpers, Lif ted Leads and Bypasses made in accordance with this procedure within 14 days following
* in'stallatio If the Jumper, Lif ted Lead or Bypass requires a safety evaluation, the PORC is responsible for reviewing the safety evaluation and determining that the change is safe and does not constitute an unreviewed safety question before the Jumper, Lifted Lead or Bypass is installed on operable equipmen .3 operations Supervisor Responsible for ensuring overall compliance with this procedur .4 operations Shif t Supervisor ,
Responsible for overall control, i.e., administration and authorization, of Jumpers, Lifted Leads or Bypasses during the assigned shift. Responsible for approving the installation and restoration of Jumpers, Lifted Leads and Bypasses. Responsible for completing the technical and safety assessment sections of Attachment .5 Plant Personnel Responsible for ensuring that operations personnel are properly notified prior to placement or removal of any Jumper, Lif ted Lead or Bypass. Responsible for installing, removing, and proper placement of Jumpers, Lif ted Leads and Bypasses in accordance with this procedure. Responsible for ensuring that devices are compatible with their intended functions; e.g., current capacity of wire, termination, insulation, pressure and temperatire ratings, etc. Additionally, responsible for ensuring that Jumpers, Lif ted Leads and Bypasses meet the requirements of the technical evaluation and applicable special instructions noted on Attachment , 5.6 Engineering Supervisor .. l Responsible for perferming and documenting technical evaluations l and safety evaluations before a Jumper, Lif ted Lead or Bypass is installed on operable equipment when required by this procedure.
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5.7 Duty Officer Qualified Person Responsible for completing the technical and safety assessment sections of Attachment .
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5.8 Department Heads Responsible for reviewing installations to determine if they are
* still needed or if they should be made permanent. Responsible for initiating design changes for those Jumpers, Lifted Leads or Bypasses that are to be made permanen .0 IN'STRUCTIONS 6.1 General 6. This procedure shall be considered for safety-related and nonsafety-related systems. If the equipment is declared inoperable, then this procedure does not need to be implemented. This procedure, the udit tag-out procedure, or station-approved procedure (including a work order) can be used as desired to control Jumpers, Lif ted Leads and Bypasses in equip-ment that is declared inoperabl . Jumpers (both electrical and mech.1ical) shall be compatible for the use intended; e.g. , size, terminal, type, insulation, pressure rating, material, F Pi DE i
construction, et . When they are installed on operable equipment, Jumpers, Lifted Leads and Bypasses that are positively identified and controlled in other station-approved procedures In are excluded from the requirements of this procedur order to qualify for this exclusion, the other procedure must specify the following: 6.1. Either Shif t Supervisor or Senior Control l Room Operator notification and sign-off when Jumpers, Lifted Leads and Bypasses are ' installed and remove .1. Documentation of the placement or removal l ' of Jumpers, Lifted Leads and Bypasses.
6.1. Independent verification when Jumpers, Lifted Leads and Bypasses are installed or j removed on safety-related system . Multiple Jumper, Lif ted Lead or Bypass Control tags may be issued under a single "Jumper, Lifted Lead and , Bypass Control sheet." The devices may be both ! Rev. 1.A 1 NEO 8.01 Date: 08/15/86 Page 5 of 12 l e =a o .
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electrical and mechanical davices cs long as they are issued foi a common purpose.
' . Initiation 6. The requestor shall fill out the description section of the Jumper - L!f ted Lead - Bypass Control Sheet (Attachment 8.A).
6, The following information shall be recorded on
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Attachment .2. Dat .2. Unique index numbe .2. The equipment and functions that are affecte .2. The reason (purpose) f or the reques * 6.2. The applicable drawings or design document .2. The tag number, location, and type (s) shall be indicate ' 6.2. Description necessary to locate the device including termination , 6.2. Any special actions, instructions, or requirement .2. The requestor shall sign and date the description sectio .3 Assessment 6. The Assessment Section Items 1 to 3 of Attachment shall be completed by both a Shift Supervisor and a Duty Officer qualified member of the affected uni They shall add any spacial-action instructions / requirements (description section) as necessar . They shall ensure that the installation does not adversely affect the intended safety, reliability, or ~ efficiency of the plan .3. They shall determine if the equipment is to be declared operable with the Jumper, Lifted Lead or Bypass installed. If the equipment is declared inoperable, Steps 6.3.1.2, 6.3.1.3, 6.3.3, 6.3.4, and 6.3.5 need not be completed. Jumpers, Lif ted Leads or h*EO 8.01 Rev. Date: 08/15/86 Page 6 of 12
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Bypasses installed on inoperable equipment shall be reviewed to ensure that they are either removed or controlled in accordance with this procedure by being assessed prior to returning the equipment to operabilit .3. They shall determine (technical assessment) L if a more detailed written technical review
* is needed by answering the questions in Section A (Attachment 8.A). .If any of the answers in this section are "YES" or "DON'T KNOW," then Attachment 8. A shall be forwarded to the associated unit's Engineering Department which is responsible for completing a detailed technical evaluation. The detailed technical evaluation will address items marked "YES" and "DON'T KNOW" from the technical assessmen .3. They shall determine (safety assessmen't) if a detailed safety evaluation is needed by answering the questions in Section B (Attachment 8.A). If any of the answers in this section are marked "YES" or "DON'T KNOW," then Attachment 8. A shall be forwarded to the associated unit's Engineering Department which is responsible for completing a safety evaluatio .3. All special actions, such as temporary operating instructions, etc., shall be noted on Attachment 8. A (descrip'. ion section). The results of the assessments, if applicable, will be appended to Attach-ment .3. The Shif t Supervisor and Duty Of ficer .
Qualified persons who complete the assess-ment section must document their approval with their signature (Documentation of phone conversations is acceptable if the Duty Officer Qualified Person is not onsit If performed by a phone converk l sation, then note the date, time, and when called on Attachment 8.A or Attachment to . If all of tbc questions in Sections A ar.d B are marked "NO," or are not required to be performed or are addressed with completed assessments and approvals, the Shift Supervisor may authorize approval for installatio Rev. NEO 8.01 Date: 08/15/86 Page 7 of 12
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6. The associated unit's Engineering Dipartnant sball be responsible for completing a dateiled technical
. - evaluation applicable to the questions in Section A that are marked "YES" or "DON'T KNOW." The Engineering Department shall be responsible for completing a detailed safety evalustion if any of the questions in Section B are marked "YES" or "DON'T KNOW." ,
6. The PORC must review and recommend approval of all safety evaluations required by Attachment 8.A,
+ Section B before installation on operable equipmen Copies of the approved technical evaluations and/or safety evaluations shall be attached to Attachment to be forwarded to the Shif t Supervisor for instal-lation approval. Copies of the safety evaluation shall also be attached to the PORC meeting minutes and forwarded to the Nuclear Review Board (NRB) for revie . If a technical specification change is required or an unreviewed safety question is found to exist, then, NRB and NRC approval is required before installatioh can be authtrize .4 Installation 6. Shif t Supervisor approval is required for installatio Responsibilities are as follows:
6.4. Assigning a unique number f rom the Jumper, Lifted Leads and Bypass Control Index (Attachment 8.B) to the Jumper, Lif ted Leads and Bypass Control Sheet (Attachment 8.A).
6.4. Entering into the index the number, type, affected equipment / function,. restoration required by (date/ mode), installation date, and the department requesting the installatio .4. Reviewing Attachment 8.A to ensure that it is complete and that all required reviews and approvals have been.obtaine .4. Reviewing the Jumper, Lif ted Leads or -
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Bypass to ensure it is compatible with existing plant condition .4. Implementing any special actions or technical specification requirement .4. Issuing caution tags (as appropriate) and noting the issuance in the comments sectio . NEO 8.01 Rev. Date: 08/15/86 Page C of 12
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- ' 6.4.1.7- Filling out or have filled out a Jumper, Lif ted Leads - Bypass Control Tag for each Lifted Lead or device. The tag shall identify the termination point ~
Jumpers that are of such length that both ends are not visible when installed shall have a Tag attached at each en . 6.4. Signing and dating Attachment 8.A to identify that the Sbif t Supervisor has authorized approval for installatio .4. Ensuring that a verification of the instal-lation is complete .4.1.10 Placing the original copy of Attachment in the Jumper, Lif ted Leads and Bypass Control Log (including supporting documen-** tation). A copy can be put in the log until appropriate PORC approval is obtaine . The plant personnel performing the installation (installer) shall implement the following: 6.4. Install each jumper, lif ted lead, bypass., or device in accordance with safe statioa work practice .4. Install at least one Jumper, Lifted Lead - Bypass Control tag for each Lifted Lead or devic .4. Insulate lifted leads from other circuits and from groun .4. Ensure jumpers ani other devices (both electrical and mechanical) are compatible for the intended us .4. Identify the proper circuits or other ( components before disconnecting any leads ( or installing any device ,. l 6.4. Sign and date Attachment 8.A after instal-lation is complet . The plant personnel performing the independe verification (verifier) shall, by means of a visual verification or functional check, ensure proper installation. If verification is done by performing a functional check, the method of performing the 1 Rev. NEO 8.01 Date: 08/15/86
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check shall b2 dascribrd in the ccam nts sectico of Attachment An exception to performing a second verification may be granted by the shif t supervisor if the second verification would result in a significant radiation exposure. However, every reasonable effort shall- be made to confirm operability; e.g. , functional test, i remote viewing, etc. The basis for this exception shall be noted in the comments section of Attachment ' 6.4. The person performing the independent verification then signs and dates Attachment 8.A after verification is complet . Tor those Jumpers, Lifted Leads and Bypasses whi:h did not require prior PORC approval, the Operations Supervisor shall have Attachment 8. A (or a copy of Attachment 8. A) forwarded to the PORC once the installation is complete. PORC must then perform a
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review within 14 days following installation 6.5 Restoration 6. The shift supervisor is responsible for the f ollowicg: 6.5. Authorizing restoration by signing and dating Attachment 8.A after ensuring that the restoration is permissibl .5. Entering the restoration date into the Index after the restoration is verified.
l 6.5. Removing any caution tags and deleting any special instructions that were. issued as a result of that installation and briefing operators on the shif .f. Ensuring that an appropriate verification of the restoration is completed and per-forming any functional chec . 6. The plant personnel performing the restoration (restorer) shall ensure proper restoration and that ,. all tags are removed. -After restoration is complete, the restorer shall sign and date Attachment 8.A.
I 6. The plant personnel performing the independent c verification (verifier) shall, by means of a visual verification or functional : beck, ensure proper l
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restoration. If the verification is done by performing
'- a functional check, the method shall be noted in the comments section of Attachment An exception to performing a second verification.may be granted by the shif t supervisor if the secon verification would result in a significant radiation exposur However, every reasonable effort shall be made to confirm restoration to full operability; e.g., function test, remote viewing, etc. The basis ,
for this exception shall be noted in the comments section of Attachment .5. The person (s) performing the independent verification then signs and dates Attachment 8.A after verification is complet .6 Reviews and Audits ' 6. The Jumper, Lifted Lead and Bypass Control Log shall' be reviewed during each shift and prior to a mode change to ensure technical specification requirements are being me . The Operations Department shall perform a monthly review of the log for administrative errors. This review also will identify those Jumpers, Lifted Leads or Bypasses either no longer needed or in effect for more than six month .6. A copy of administrative errors that have l been discovered as a result of the review j shall be forwarded to the Operations j
Supervisor for corrective actio .6. Those installations that are determined to be no longer needed shall be restored per Section .6. A copy of those installations that have ' been installed for longer than six months shall be forwarded, after each time the audit is performed, by the Operations Supervisor to the responsible Department Head to determine if they are still neede .6. Completed Index Sheets (Attachment 8.B) l that reflect restoration shall be forwarded I to the Operations Supervisor for review, disposition and forwarding to nuclear record Rev. NEO 8.C1 Date: 08/15/86 Page 11 of 12 l l . . . . . . 1 - - . _ _ _ _
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16.6. Tha Op2roticos D:partazat revisv cf jumpar, liftsd leads, cod bypass'c:ntrol sheets
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shall be documented by noting it in the
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audit section of Attachment .6. The Operations Supervisor will coordinate with other departments as part of this audit, to include a check for correct * place-ment, condition, and tagging of Jumpers, Lifted Leads and. Bypasse ' 6.6. The Operations Supervisor shall review results of the audit with POR . The responsible Department Head shall review instal-lations that are installed longer than six months to see if they are still needed or if they should be made permanen .6. 'shose that are determined to be no longer needed shall be restored per Section *
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6.6. For those that are to be made permanent, submit design changes per.9eference .0 FIGURES . Figure N Figure Title Jumper, Lif ted Leads and Bypass Control Flowchart 8.0 ATTACHMENTS Attachment N Attachment Title 8A Jumper - Lif ted Lead - Bypass Control Sheet Jumper - Lif ted Lead - Bypass Control Log Jumper - Lif ted Lead - Bypass Control Tag Hajor Changes from Previous Revision '
(Rev. 1 Updated to Rev. 1.A).
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. ATTACHMENT 6 EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK b 01 Ibb6 LIMITING CONDITION FOR OPERATION 3. The refueling water storage tank (RWST) ' hall be OPERABLE with: A contained borated water volume between 1,166,000 and 1,207,000 gallons, A boron conceacration between 2000 and 2200 ppm of boron, A minimum solution temperature of 40*F, and A maximum solution temperature of 50* APPLICABILITY: MODES 1, 2, 3, and ACTION With the RWST inoperable, restore the tank to OPERABLE status within 1 hour or be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hour .
i SURVEILLANCE REQUIREMENTS __ l l 4. The RWST shall be demonstrated OPERABLE: At least once per 7 days by: 1) Verifying the contained borated water volume in the tank, and l l 2) Verifying the boron concentration of the wate At least once per 24 hours by verifying the RWST temperature, o MILLSTONE - UNIT 3 3/4 5-9
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N0Y 15 1985 s _
_ - . . .. ATTACHPENT 8
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3/4.8 ELECTRICAL POWER SYSTEMS 3/4. A.C. SOURCES d'N d'l isS6 OPERATING LIMITING CONDITION FOR OPERATION 3. 8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE: Two physically independent circuits between the offsite transmission network and the onsite Class IE Distribution System, and Two separate and independent diesel generators, each with: 1) A separate day tank containing a minimum volume of 205 gallons of fuel, 2) A separate Fuel Storage System containing a minimum volume of 32,760 gallons of fuel, 3) A separate fuel transfer pump, 4) Lubricating oil storage containing a minimum total volume of 280 gallons of lubricating oil, and 5) Capability to transfer lubricating oil from storage to the diesel generator uni APPLICABILITY: MODES 1, 2, 3, and ACTION: With either an offsite circuit or diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Specifi-cations 4.8.1.1.la, and 4.8.1.1.2a.5) within 1 hour and at least once per 8 hours thereafter; restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours, With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Specifica-tions 4.8.1.1.la and 4.8.1.1.2a.5) within 1 hour and at least once per 8 hours thereafter; restore at least one of the inoperable sources to OPER/.BLE status within 12 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hour Restore at least two offsite circuits and two diesel generators to OPERABLE status within 72 hourt from the time of initial loss or be in at least HOT STANDBY within the ' next 6 hours and in COLD SHUTDOWN within the following 30 hour With one diesel generator inoperable in addition to ACTION a. or above, verify that: All required systems, subsystems, trains, components, and devices that depend on the remaining OPERABLE diesel generator as a source of emergency power are also OPERABLE, and
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MILLSTONE - UNIT 3 3/4 8-1
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ELECTRICAL POWER SYSTEMS Jgg 3 y LIMITING CONDITION FOR OPERATION ACTION (Continued) When in MODE 1, 2, or 3, the steam-driven auxiliary feedwater pump is OPERABL If these conditions are not satisfied within 2 hours be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hour With two of the above required offsite A.C. circuits inoperable, demonstrate the OPERABILITY of two diesel generators by performing the requirements of Specification 4.8.1.1.2a.5) within I hour and at least once per 8 hours thereafter, unless the diesel generators are already operating; restore at least one of the inoperable offsite sources to OPERABLE status within 24 hours or be in at least HOT STANDBY within the next 6 hours. With only one offsite source restored, restore at least two offsite circuits to OPERABLE status within 72 hours from time of initial loss or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours, With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing the require-ments of Specification 4.8.1.1.la. within 1 hour and at least once per 8 hours thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. Restore at least two diesel generators to OPERABLE status within 72 hours from time of initial loss or be in least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hour SURVEILLANCE REQUIREMENTS
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4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite Class 1E Distribution System shall be: Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and Demonstrated OPERABLE at least once per 18 months during shutdown by transferring (manually and automatically) unit power supply from the normal circuit to the alternate circui .8.1. Each diesel generator shall be demonstrated OPERABLE: MILLSTONE - UNIT 3 3/4 8-2
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ATTACHMENT 9 3/4.11 RADIOACTIVE EFFLUENTS
- JAN 311986 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION *
LIMITING CCNDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentra-tion shall be limited to 2 x 10 4 microcurie /m1 total activit APPLICABILITY: At all time ACTION: Wish the concentration of radioactive material released from the site exceeding the above limits, restore the concentration to within the above limits within 15 minute SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program specified in Section I of the REM 00CM.
' 4.11.1.1.2 The results of radioactive analyses shall be used in accordance l with the methods of Section II of the RD40DCM to assure that the concentrations at the point of release are maintained within the limits of Specification
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MILLSTONE - UNIT 3 3/4 11-1 ! !
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REACTOR OPERATOR EXAM PRINCIPLES OF NUCLEAR POWER PLANT OP2 RATION, THERMODYNAMICS, HEAT TRANSFER AND FLUID FLO .0lb (5)' Answer key is incorrec Should be "remains the same".
OPS Form 3209B-1, steps 3.4 and 3.5 negate changes in reactivity effect .05 c RCCA worth decreases with core age, as described in attached Neutron Poisons Lesson Plan (RTI-01-C), pages 21 and 2 .06 b Answer should be "Less Negative", because the smaller change in fuel temperature per percent power change at EOL outweighs the more negative FTC. (Reference: Reactivity Coefficients and Defects Lesson Plan, pages 13, 14 previously provided) 1.07 c Agreed that "cold leg temperature decrease" wculd bs an acceptable alternative for the second half of the answer ke . 1.09 (2) Question does not elicit numerical values for, Xenon concentration. Operators cre not*-re' quired to memorize
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the level of specificity provided in the answer ke Based upon the question, any response indicating higher concentration at 100% should be acceptabl . PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS 2.01 (3) Agreed that either TRUE or FALSE can be acceptable answer (Reference: P&ID EM 122B] 2.02 Agreed that Containment Instrument Air compressors could be part of an accep?.able answer (Reference: P&ID EM 122B] 2.07 Question does not elicit the response provided in the answer key. Implication is to give three reasons for the designed sequence delay, for which there is not three discreet reason Any three true statements concerning elapsed time should be considered acceptabl .
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2.08 a. . Original RO question was deleted during administration of exam and replaced with SRO exan question 6.01'with increased point valu Facility questions the validity of this action; design basis information may not be . appropriate at the RO leve .08 Agreed that RCS overpressure is an acceptable answe (Reference: T/ Spec 3/4 1-10, 1-9, a 3/4 1-3] 2.09 c Agreed that acceptable answer is diesel has lost control powe [ References ESK 8KC) Question badly worde To elicit correct response, SRO exam question 6.07 a is better worde . INSTRUMENTS AND CONTROLS 3.03 Agreed that all thermocouple temperatures read out on
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control room CRT,'not'just the' highest one, ( Re f e'rence
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SPDS Text, rigure 5.1) 3.05 c Agreed answer could assume steam dumps in either steam pressure or T-AVE mode, if explained properl .07 c Agreed excessive KW/rT is complete answe (Reference: Reactor Trip List)
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3.08 c Agreed that "except 480 volt load center and motor control center supply breakers and the running charging pumps," should not be required as part of the answer as this statement does not constitute an automatic action due to LO .09 b Agreed that any answer consistent with concept stated in ' answer key is acceptable. i.e "live zero" current is
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also an acceptable answe (Reference: Excore NI Text p. 20]
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<- 3.11 Agreed that block valves would probably be open in given plant condition Therefore, any answer which indicated this or explained the fact that the block valves receive an open signal when the COPS switch is placed in the ARM, position, is an acceptable response to that aspect of the question. (Reference: PZR Pressure and Level Control, p. 12] PROCEDURES - NORMAL, ABNORMAL, EAERGENCY AND RADIOLOGICAL CONTROL 4.05 a. Agreed that correct answer does not need to include "do not use cheater bars" as this is a prohibition vice a requirement as regards manual seating of motor operated valve [ Reference: OPS-3.07 p.6) 4.09 a. Agreed. answer should include "failure of two or more
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control rods" vice on .
(Reference: AOP 3566 Rev. 1]
4.09 b Agreed answer is "to maintain sufficient NPSH to boric acid transfer pumps." [ Reference: Immediate Boration Lesson Plan - p. 4]
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4 SENIOR REACTOR OPERATOR EXAM THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS AND , THERMODYNAMICS
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5.02 . Answer should be "Less Negative", because the smaller change in fuel temperature per percent power change at EOL outweighs the more negative FTC. [ Reference Reactivity Coefficients and Defects Lesson Plan, pages 13, 14 previously provided] 5.04 Correction to reference data (Ops Form 3209A-1) was made during administration of exam, which makes answer t key invali Based upon the correction, student would also need Samarium curves, which were not provide .05 Trends provided in the question are mis)eading and confusing when used as an evaluation device (rather than instructional aid as intended). Examiner should assess human factors of using word processing equipment to draw graphs Part a.2 should be answered by power going up and stabilizing at a higher valu This was not one of
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Part b.3 answer key is incorrect. Pzr leve'l will increase on heatup, then trend to a lower than initial value on program. Answer should be Part b.2 elicits a trend that is not one of the choices. Recommend this be delete .07 d Millstone 3 cire water pumps are propeller-type pump As such, the question does not provide enough - information to allow a meaningful evaluation.
t 5.09 b RCCA worth decreases with core age, as described in attached Neutron Poisons Lesson Plan (RTI-01-C), pages l l 21 and 22.
l PLANT SYSTEMS DESIGN, CONTROL AND INSTRUMENTATION I
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6.01 c - sare as 2.08c l 6.03 b - same as 3.09b
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6.08 d Loop isolation valves no longer interlocked with steam generator low low level tri (Reference: 108 D. 684 sh. 7 Rev. 6]
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6.10 - same as 3.11 PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL 7.01 d racility expressed concern that we do not expect operators to memorize cautions or notes contained, within normal operating procedure (Reference: OP 3310A p. 12] 7.03 c Same concern as 7.01 d. Many reasons could have been given for emergency retrieval of transfer ca Primary reasons involve drive failure and desire to move transfer ca ' [ Reference: OP'3303C p.,7-]
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7.05 a same as 4.09 a , 7.05 b same as 4.09 b
' 7.06 Agreed correct answer is 180*r and 10'R (References E-O Rev. 1 p. 4] 7.07 c Information given in question is-not clear, and as such may not elicit expected response. Clarification was not provided to all students. Correct answers based upon interpretation of question may var l-5-
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. . . . . . , ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS 8.01 Agreed that "if equipment is deemed inoperable" is -
acceptable answe [ Reference ACP-QA-2.068 p.5] 8.05 d Agreed that 4 hours is correct answer based on 50.72 (b) (2) (ii) vice 1 hour based on 50.72 (b) (1) (iv) as signal initiating safety injection was "mistakenly generated" and hence is not a "valid signal."
[ Reference 10CFR50.72 pp. 509-510] 8.06 racility argued that this question was ambiguous and
, that any person in chain of command should be appropriate answer since definition of what *
constitutes."emergency" as framed,in. question.is . -
, nebu'lous. In any event, agreed th'at'any superintendent listed in EPIP 4112 can be substituted for duty officer in answe (References EPIP 4112 p. 5)
8.07 a/d Agreed to grade per valid assumptions made, as regards
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to length of time casualty e.xisted, since length of time casualty existed determines emergency classificatio ! 8.07 c Agreed to grade per valid assumptions made by examinee ' as to the cause of SI and decreasing RCS pressure as a variety of accidents could have resulted in these plant conditions, i e, SGTR, steam break, as well as a
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LOCA could have resulted in similar plant indications.
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8.08 b Agreed to accept 12/15/87 2000 as alternative answe If examinee with proper explanation assumes 3.8. (c) applies, then hot standby is required within 8 hrs vice 18 hrs as required by 3.8.1.1.(b).
-(Reference LCO 3/4 8.1] 8.08 c Agreed that 3.8.1.1.(e) applies at this point vice 3.8.1.1(d).
(Reference LOCO 3/4 8.1) 8.08d Agreed that 12/19/87 at 0200 is an acceptable alternative answe If examinee assumes "initial loss" indicates time starts from initial loss of both diesel generators vice loss of one generator, this will add 9 hours to anstre (Reference LCO 3/4 8.1)
, . . j racility argued'that question' asked'for two reasons
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/$I' when proper answer really was one reason with two part Hence, due to the nature of the question, extraneous information may have been elicited by examinees in attempting to answer question full .,
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