IR 05000336/1988017
| ML20154Q602 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/12/1988 |
| From: | Eselgroth P, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20154Q600 | List: |
| References | |
| 50-336-88-17OL, NUDOCS 8810040015 | |
| Download: ML20154Q602 (98) | |
Text
{{#Wiki_filter:- , . i . . . U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT - EXAMINATION REPORT NO.
50-336/88-17(OL) FACILITY DOCKET NO.
50-336 FACILITY LICENSE NO.
DPR-65 LICENSEE: Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06141 FACILITY: Millstone Unit 2 EXAMINATION DATES: July 20-21, 1988 CHIEF EXAMINF.R: Mm 7st,#W darry/S. Norris uate Senidr' Operations Engineer / / g ' le4 ' /-/2 -T APPROVED BY: .. Peter W. Ese roth, Chief Date PWRSectio[,OperatiensBranch,DRS ! SUMMARY: Written and operating examinations were administered to three Senior Reactor Operator (SRO) upgrade candidates.
All three SR0s passed the examinations and werr. issued their licenses.
8810040015 880919 PDR ADOCK OSOOc
V
m . . . ~. DETAILS . TYPE OF EXAMINATIONS: Replacement EXAMINATION RESULTS: l SR0 l E Pass / Fail I E E E I I I Written E 3/0 E I E E E I E E Operating
3/0 I E E E I E
E Overall E 3/0 I E E E CHIEF EXAMINER AT SITE: B. S, Norris, USNRC, RI 'HER EXAMINERS: R. B. Eaton, USNRC, NRR J. A. Prell, USNRC, RI D. M. Silk, USNRC, RI 1.
GENERIC DEFICIENCIES: The following is a summary of generic deficiencies noted on the examinations. This informatien is being provided to aid the licensee in upgrading license and requalification training programs. No licensee response is required, a.
Operating Exanination , (1) Dur'ng the simu'stor examination, the candidates dismissed two , instances of spurious alarms with "Guess it's a simulator problem." Although their reaction waa :n fact correct, this typr. of action on the part of the operators would tend to distract from the training atmusphere in the simulator.
(2) During transients, thq board operators tend to focus on the digital readouts on the nuclear instrumentation cabinets for extended periods of time (30-40 seconds) while ignoring the other indications on the panels.
b.
Written Examination There were no generic weaknesses identified during the grading of the written examinations.
.
. . . ~ . 2.
EXAMINATION REVIEW: . a.
Written Examination The written examination was reviewed by the training staff in two parts.
Prior to the administration of the examination, it was reviewed for technical accuracy, applicability to the Millstone Unit 2 facility, and assurance that the answer key was consistent with the question.
Twenty of the fifty questions were rewritten as a result of this rev'ew.
As can be seen in Attachment 1 (SR0 Written Examination with Answer Key), most of the changes were minor in nature: terminology, or addition / deletion of a word or phrase for clarification; one question (7.02) was rewritten to reflect the actual responsibilities of the SRO at Millstone Unit 2.
The new questions were retyped and pages replaccd in the examinations before they were given to the candidates.
The examination, as attached, was modified to show the original question and the question as rewritten.
Additionally, the answer key was modified to reflect any technical changes identified during the facility review of the examination.
There was disagreement between the NRC examiners and the facility reviewers as to whether or not two questions (8.03 and 8.11) on Technical Specification basis were required knowledge (see Attachment 2).
NUREG-1021, Operator Licensing Examiner Standards, ES-402, "Scope of Written Examinations Administered to Senior Reactor Operators - Power Reactors," paragraph A.4 states in part "... Questions concerning the Technical Specifications will require a thorough knowledge of... the basis for the requirements..." The facility reviewers for the written examination were R. Cimmino, J. Parillo, and M. Wilson, b.
Operating Examination The scenarios for the simulator portion of the cperating examination were also reviewed by the training scaff prior to being administered to the candidates. One event had to be changed to due a modeling oroolem with one of the malfunccions.
The facility reviewers for the simulator scent.rios were R. Burnside, J. Parillo, and D. Wright.
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PERSONNEL PRESENT AT EXIT MEETING: . NRC Personnel 8. S. Norris - Chief Examiner P. J. Habinghorst - Resident Inspector Facility Personnel R. Burns, Jr. - Simulator Instructor C. Clement - Unit 3 Superintendent D. Pantalone - Program Coordinator J. Parillo - Assistant Supervisor, Operator Training J. Smith - Unit 2 Operations Supervisor M. Wilson - Supervisor, Operator Training 4.
SUMMARY OF COMMENTS MADE AT EXIT MEETING: a.
The NRC and the facility agreed that the pre-administration review of the examinations was an improvement over the previous method of review in that the candidates would be examined on their knowledge and not on their ability to interpret questions that were not clear and specific to Millstone Unit 2.
b, The NRC expressed concern about three items within the plant: (1) During transients the R0's tend to focus their attention on the digital readouts on the NI cabinets rather than the entire control boards. Although this was noticed only in the simulator, training frequently is a reflection of actual practice in the plant.
(see paragraph 1.a(2) above) The facility noted the comment and stated they would reinforce to the operators that the digital readouts were not to be used to the exclusion of the remainder of the control boards.
(2) Technical Specificat'en 3.1.2.2.1 states "Tr:o flew pcths from the boric acid storage tanks via either a boric acid pump or gravity feed connection and a charging pump to the Reactor Coolant System and one associated heat tracing circuit s'.all be , ' CPERABLE. (Modes 1, 2, and 3)" Although there is a management interpretation of what determines two separate paths if one boric acid pump is out of se'evice, the interpretation is not in w-iting.
This could lead to confusion and r.ven contradiction between shifts.
, The facility stated that will review remedies implemented by other facilitie ' , . . ' . , . . (3) In the case of an evacuation of the control room, it is not clear within the procedures which of the shutdown panels the operators should go to.
One procedure directs the operators to the Hot Shutdown panel, and another directs them to the Fire Shutdown panel.
The facility response was that it is the responsibility of the Shift Supervisor to determine which of'the panels would provide better control of the plant.
This determination would be based partially on whether or not it was an Appendix R fire.
Attac hments: 1.
SR0 Written Examination and Answer Key 2.
Facility Comments on Written Examinations af ter Facility Review l l l l L
_, kWhWAWY j . . . .
N . . .
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NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION . FACILITY: MILLSTONE 2 REACTOR TYPE: PWR-CE DATE ADMINISTERED: 88/07/20 EXAMINER: PRE W _J.
CANDIDATE: ,_ _8 _d T INSTRUCTIONS TO CANDIDATE: jpgg U2e separate paper for the ankwors.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the question.
The passing grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the enamination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VAL _UE CATEGORY 25.00 25.00 5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 25,00 _25.00 6.
PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 15.00 25.00 7.
PROCEDURES - NORMAL. ABNORMAL, EMERGENC( AND RADIOLOGICAL L GI D I, Oi _25.00 25.00 8.
ADMINISYRATIVE PROCEDURES, COND'1TIONS, AND LIMITATIONS 100.00 % Totals Final Grade all work done on this enamination is my own.
I have norther given nor received aid.
Candidais's Signature
_. _. .- . . . . . . NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS . During the administration of this examination the f ollowing r ules apply: . 1.
Cheating on the examination means an automatic denial of your application and could result in more severe penalties.
, 2.
Restroom trips are to be limited and only one candidate at a time may
leave.
You must avoid all contacts with anyone outside the examination ! room to avoid even the appearance or possibility of cheating.
' 3.
Use black ink or dark pencil only to facilitate icgibl e reproductions.
' , 4.
Print your name in the blank provided on the cover sheet of the examination.
5.
Write your answers on the examination paper.
If more paper is required, . use the paper provided.
For each extra piece of paper used, print your name in the upper right hand corner and identify the answer, for example, , 1.4, 6.3.
6.
Separate answer sheets from pad and place finished answer sheets face down on your desk or table.
, 7.
Use at' brevi ations onl y i f they are commonly used in facility literature.
I ' O.
The point value for each question as indicated in parentheses after the question and can be used as a guide for the depth of answer required.
l ! 9.
Show all calculations, methods, or assumptions usad to obtain an answer ' to mathematical problems whether indicated in the question or not.
l 10. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE QUESTION AND DO NOT LEAVE ANY ANSWER BLANK.
l 11. If parts of the examination are not clear as to intent, ask questions of the egeminer only.
i t j 12. (ou must bagn the statement on the cover sheet that indicates that the
work is your own and you have not received or been given assistance in ' completing the examination.
This must be done after the examination has been completed.
! , i f I i l .- .. - _ - -. - - - - - -. -.. -. - - -. - - _ -
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, ..., ... , l . < . , l 1L When you complete your examination, you shall ' l a.
Assemble your examination as follows: . (1) Exam questions on top.
. (2) Exam aids - figures, tables. etc.
b.
Turn in your copy of the examination and all pages used to answer i the examination questions.
, c.
Turn in all scrap paper and the balance of the paper that you did not use for answering the questions.
d.
Leave the examination area, ab defined by the examiner.
If after leaving, you are found in this area while the examination is still in progress, your license may be denied or revoked.
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- < , ,- ., , 5.. 'TMORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
THERMODYNAMICS . . QUESTION 5.01 (1.00) Following a reactor trip on low SG 1evel, EXPLAIN why automatic initiation of the AFW system is delayed 3 minutes and 25 seconds.
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5.. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
l THERMODYNAMICS . I
. QUESTION 5.02 (2.00) DEFINE and PROVIDE the basis for the Power Dependent Insertion Limit (PDIL) , b
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- =, . . , '. THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
5 THERMODYNAMI_QE . . QUESTION 5.03 (1.00) A reactor startup is in progress. Shutdown Groups A and B are fully withdrawn. Keff = 0.95 and the countrate is 50 cps and stable.
The control room operator begins regulating rod withdrawal until he has added 3 percent delta k/k reactivity to the core.
As a result of his actions, has the shutdown margin INCREASED, DECREASED. or REMAINED THE SAME7 Explain your answer.
(1.0) se64** CATEGORY 05 CONTINUED ON NEXT PAGE e*6ta)
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THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
THERMODYNAMICS
, . QUESTION S.04 (2.40) QUESTION AS ORIGINALLY WRITTEN i Identif y FOUR changes in core reactivity which take place immediately P following a reactor trip and during the nest 24 hours.
STATE the reason for each change.
Assume the r eactor was at 100 percent power. 9qu11braum r conditions, prior to the trip and that the plant will remain in hot otandby following the trip.
. I OUESTION AS REWRITTEN DURING PRE-EXAM REVIEW i IDENTIFY FOUR changes in core reactivity which take place during a reactor trip and the next 24 hours.
STATE the reason for each change.
Assume the . reactor was at 100 percent power, equilibrium conditions, prior to the
trip and that the plant will remain in hot standby f ollowing the trip.
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THERMODYNAMICS . , . QUESTION 5.05 (2.00) i INDICATE whether the MTC will become LESS NEGATIVE, MORE NEGATIVE, or REMAIN CONSTANT under the following conditions.
c.
BOC, with a reduction in moderator temperature > ) b.
DOC, HFP with a boron addition i c. core ages between BOC and EOC , d.
fission product poison buildup l ' i a I
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i . . . , - - . '.. T'EORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
5 THERMODYNAMICS . . QUESTION 5.06 (2.00'i OUESTION AS ORIGINALLY WRITTEN Assume the reactor is in a steady state condition with no Xenon Oscillations f or the core condi tions identi fied below.
MATCH each core condition to one of the four basic auial power distribution shapes expected for that condition.
c. BOC, hot full power 1.
top peaked b.
EOC, hot full power 2.
bottom peaked c.
BOC, hot zero power 3.
saddle or hourglass shape d.
EOC, stuck rod parti ally inserted 4.
cosine shape OUESTION AS REWRITTEN DijRING PRE-E A AM REVIEW Assume the reactor is in a stendy state condition with no Xenon Occi11ations for the core conditicns identified below.
MATCH each core condition to one of the four basic axial power distribution shapes expected for that condition.
a. BOC, hot full power 1.
top peaked b.
EOC, hot full power 2.
bottom peaked c.
SOC. hot ea power saodir or hourglacs s h a p s.
... d.
EOC, 100% power,
cosine shape group 7 at 145 steps (toe ** CATEGORY 05 CONTINUED ON NEXT PAGE 8844*)
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THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
l THERMODYNAMICS ' , .- t . DUESTION 5.07 (1.50) - QUESTION AS ORIGINALLY WRITTEN Assume there is an electrical load i ncrease from 70 percent to 90 percent.
, Indicate how the f ollowing parameters would ch.ange (INCREASE. DECREASE. or REMAIN THE SAME).
Assume steady state to steady state.
EXPLAIN your enswer.
o. Tave.
' b.
rho
j c.
Pressuriger pressure ' ' ,
' QUESTION _,AS REWRITTEN DURING PRE-EXAM REVIEW l . , i Assume there is an electrical load i ncreane from 70 percent to 90 percent.
l
Indicate how the following parameters would change (INCREASE, DECREASE, or i' REMAIN THE SAME).
Assume steady state to steady state.
EXPLAIN your i , enswer.
,
i a.
Tave.
! !
b.
Reactivity , ! l c, Pressurizer pressure L ' ! (s**** CATEGORY 05 CONTINUED ON NEXT PAGE
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. 5, THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
THERMODYNAMICS . . QUESTION 5.08 (3.00) OUESTION AS_ ORIGINALLY WRITTEN Millstone Unit 2 is in Mode 3, BOC, boron concentration is 900 ppm, all shutdown groups are withdrawn, and the actual reactivity present in the i core is minus 4 percent delta k/k.
A dilution of the boron concentration increases source range counts from 100 cps to 196 cps.
Coincident with the dilution, Xenon reactivity changes have added plus 1000 pcm to the core.
CALCULATE the final baron concentration.
Assume a constant differential boron worth of 100 pcm/ ppm.
State all assumptions and show all work.
QUESTION AS REWRITTEN DURING PRE-EXAM REVIEW Millstone Unit 2 is in Mode 3, BOC, boran concentration is 900 ppm, all shutdown groups are wathdrawn, and the actual reactivity present in the core is manus 4 percent delta k/k.
A dilution of the boron concentration increases source range counts from 100 cps to 196 cps.
Coincident with the dilution, Xenon reactivity changas have added plus 1 percent delta k/k to the core.
CALCUl. ATE the final boron concentration.
Assume a constant inverse baron worth of 100 ppm /parcent delta k/k.
State all assumptions and show all work.
(se*** CATEGORY 05 CONTINUED ON NEXT PAGE $4***)
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THERMODYNAMICS . [ .
OUESTION 5.09 (.60) Answer TRUE or FALSE f As th? core ages, differential boron worth decreases.
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'5 THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
l ., THERMODYNAMICS j . ,
GUESTION 5.10 (2.50) P Assume the plant is stable on natural circulation with the following i conditionst ' That - Teold = 30 degrees F Thot subcooled margin = 35 degroes F subcoolod I Steam Generator pressure a 650 psia l , CALCULATE the RCS pressure and LIST any assumptions made.
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. 5.* THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGF.
THERMODYNAMICS . . OUESTION 5.11 (2.00) QQgSTION AS ORIGINALLY WRITTEN _ Answer the following statements as TRUE or FALSE c.
Single phase natural circulation (NC) can take up to 15 minutes to initialty establish.
b.
For single phase NC, the flow rate should be greater than 5 percent.
c.
A sudden decrease in RCS flowrate may indicate a transit from single phase NC to two phase NC.
d.
During singl e phase NC, cool water circulates from the steam generator.
through the cold leg, up through the core, into the head area of the reactor vessel, into the hot leg and back to the s?.eam generator.
DUESTION AS REWRITTEN DURING PRE-EXAM REVIEW Answer the following statements as TRUE or FALSE ' e. Single phase natural circulation (NC) can take up to 15 minutes to initially establish.
b.
For single phase NC, the flow rate should be greater than 5 percent.
c.
A sudden decrease
- .n RCS ficwrate may indicatt= a transit from ningle phace rC. to two phese W,..
d.
During single phase NC, the majority of the cool water cirtulates from the uteam gancrator, through the cold leg, up through thri coro, into the head area of the reactor vessel, into the hot log +ho back to the steam generutor.
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THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS. AND PAGE
THERMODYNAMICS . . QUESTION 5.12 (2.00) QUESTION AS ORIGINALLY WRITTEN For each of the pump characteristics identified below, IDENTIFY whether it coplies to a positive displacement pump (PDP), a centrifugal charging pump (CCP), LOTH ur NEITHER, c. flow varies with the pump discharge head b.
requires a discharge flowpath when starting in order to prevent excess pressure buildup c. discharge head is directly proportional to the pump speed squared d.
high inlet fluid velocity creates a low pressure which i s usnd to draw the inlet fluid into the mixing chamber DUFJJT_lGN AS REWRITTEN DURING PRE-EXA;1 REVIEW For each of the pump characteristics identiftso below, IDENTIFY whether it cppli7s to a positive displacoment pump (PDP). a centrifugal pump (CP), BOTH or NEITHER.
c.
flow varios with the pump discharge head b.
requires a discharge flowpath wnen starting in order to prevent excess pressure butIdup c.
d i t,c h ar (n rm o d i c.
diroctIs p r op or t a cr.a ) tu the pump Lpevu @ ct cd d.
high inlet fluid velocity createn a low prenuure which in used to draw the inlet fluid into the mixing chamber (44648 CATEGORY 05 CONTINUED ON NEXT PAGE
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THEQRY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
THERMODYNAMICS . . QUESTION 5.13 (3.00) INDICATE for each of the following parameter changes whether it will cause en INCREASE, DECREASE, or NO CHANGE in the DNBR.
Assume all other parameters remain constant.
a.
Ducreaso in the core inlet temperature b.
Decrease in RCS pressure c.
ASI changes from 0 to minus 0.3 d.
Increase in reactor c ool arit flow e.
Reactor power tncrease f. Loading high enriched fuel near the core center (***44 END OF CATEGORY 05 44444)
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. of PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
. . QUESTION 6.01 (2.00) OUESTION AS ORIGINALLY WRITTEN What is the purpose of each of the following Control Element Drive System (CEDS) interlocks? c.
Metroscope Inhibst from Shutdown (MISH) b.
Metroscope Inhibit from Regulating Group (MIRG) c.
CEA Motion Inhibit (CMI) d.
CEA Withdrawal Prohibit (CWP) QUESTION AS REWRITTEN DURING PRE-EXAM REVIEW What od mot t on tu prevented by each of the f ollowing Control Element Detve Syntem (CEDS) interlocks? Include t,etpoints for each anterlock.
a.
Metroscope Inhibit from Shutdown (MISH) b.
Metroscope Inhibit from Regulatir.g Group (MIRG) c.
CEA Mocion inhibit (CMI) d.
CEA Withdrawal Prohibit (CWP) (steet CATEGORY 06 CONTINUED ON NEXT PAGE e#444)
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.. 6.* PLANT SYSTEMS DESIGN. CONTROL. AND_ INSTRUMENTATION PAGE
. f . QUESTION 6.02 (2.40) QUESTION AS ORIGINALLY WRITTEN i j MATCH each of the below RCP seal pressure conditions to the appropriate oeal status.
< RCS MIDDLE UFFER VAPOR SEAL STATUS , c.
2250 1125 1125
1.
NORMAL ] i b.
2250 1500 750
2.
FIRST SEAL FAILS
I c.
2250 1125
50 3.
SECOND SEAL FAILS .! ! d.
2250 2250 1125
4 THIRD SEAL FAILS
i , OUEST ION AS _ REWR I TTE_N __DUR ING FR_E-E X AM REV! F;W ! ! l MATCH each of the below RCP seal pressure conditions to the appropriate coal status.
, ' RCS MIDDL.E UPPER VAPOR SEAL STATUS
e.
2250 1125 1125
1.
NORMAL
6.
2250 1500 750
2.
LOWER SEAL FAILS i i c.
2250 1125 3C
5.
MIDDLE SEM Ff.1LG ] c.
2250 2250 1125
4.
UPPER GEAL FAILS (6*4aa CATEGORY 06 CONTINUCD ON NEXT PAGE *646*) ...
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! - OUESTION 6.03 (1.00) l f OUESTION AS ORIGINALLY WRITTEN l Indicate if the following statements are TRUE or FALSE: , ~ a.
During plant heatup, the excess letdown flow puth can be used to draw a f bubble in the pressurizer.
This lineup is preferable to normal letdown i i due to the ancreased driving head.
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b.
While operating in the shutdown cooling mode, the back pressure control l ! valves (2CH-201P and Q) are used for controlling pressure.
i ! ! '
i i t i OUESTION Ay REWRITTEN DURING FRE-EXAM REVIEW ' >
l
Indicate if the following statements are TRUE or FALSE: i l a.
During plant heatup. the excess letdown flow path can be used to draw e bubble in the pressuri:er.
This linreup is preferrale to normal letdown i . due to the increased f l owr'a t r.. l l ! I b.
While operating tre the shutdewn co?1it.q mode, the brick pressure control h valvos (2CH-201P and C) are used f or r.outrolling '/RESGURE.
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i , OUESTION 6.04 (3.00) l l OUESTION AS' ORIGINALLY WRITTEN
i Indicate af the following statements are TRUE or FALSE and JUSTIFY your I answisr.
! I a.
During a plant cooldown, with RCS pressure at 1650 psia and the SIAS r blocked per procedure, if a large LOCA were to occur, the SIAS would be j l prevented.
t ! ! b.
. A CSAS is initiated whenever containment pressure exceeds 27 psig.
[ t i
c. The ESAS sensor cabinet monitors the following parameters: RWST level,
pressuri:or pressure. pressurimer l evel, containment pressure. emergency
bus voltage, steam generator pressure, fuel handling area radiation p l moni tor s, containment radiation monitors and steam generator level.
e t f '
6 j QUESTION AG RFWRITI,GJ DQFijNQ PRE-EX AM REVI.EW ! ! InJicate if c.he following statements are TRUE or FALSE and JUST!F( your
answer.
'
i ! ! c. Duririg a plant cooldown, with RC4 pressure at 1650 psia and the SIAS f f blocked per procedure, if a large LOCA were to occur, the SIAS would be i ) peuvented.
l b.
A CSAS will be initiated af thw ONLY input signal to the CSAS 15 , r.ontatnment prensuro of 27 put9 l } l c.
The ESAS sensor cabinet mon t ter s the fol;owtng parameters: RWST level.
l
persusuri zer orusuure, pressurizer level, containment prueguro, emergent:y i l bus voltage, steam generator prensor a, f uel handling area radiation l j monttors, containment radtatton menttara and steam generator luvul.
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. 6.. PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
9 . DUESTION 6.05 (1.20) One function of the incore anal ys.1 s progr am (INCA) is to calculate s1x (6) different incore power valuun used for estimating incere power distribution.
IDENTIFY any four (4) of these values calculated by INCA.
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, t 6< PLANT BYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
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- . . QUESTION 6.06 (2.00) t I ! DUESTION AS ORI(i!NALLY WRITTEN [ t Assume the plant is at 100 % power, steady state conditions, when an } instrument failure causus the main Feedwater Regulating Valve to No. 1 ! Steam generator (SG) to close.
Buf ore the operators can recover, the plant I traps on low steam generator level.
All othor systnms are functioning j n or mal. , L d.
Assuming no operator action, what is providing RCS heat removal the first two minutes after the reactor trip 7 (0.50) , i b.
Again assuming no further operator-action, what automatic actions occur
ensuring RCS heat removal via the SGs five minutes after the trip 7
(1.0) r c.
Ten minutes after the reactor trip, water from the Condensate
Storage Tank is lort.
What is the secondary source of water [ available to the operators to help unsur e continuud RCS heat ' ! removal ? (0.5) !
!
. C ! OUEST1QN_AS REWSITTEN DURING PRE-EXAM REVlfd [ ' [ l Assume the plant is at 100 % power steady state conditions, when en e
instrument fatture causes the main Feodwater Regulating Valve to No. I j eteam generator (SG) to clown.
Setore the operatcre can recover, the plant
j trips on low stnam genurater l ove). All utner syntoms ar e f unctioning i normal.
l ! t ! 9.
Assuming no opurator action, what system / component i t. providing RCS [ heat removal thu first two minutos after the resactor trip ? (0.50) [
b.
Again assuming no further operator action, what automatic actions occur ' ensuring RCS heat removal via the SGs five minutes after the trip ? (1.0)
l ) c.
Ten minutes after the reactor trap, water from the Condensate l Storage Tank is laut.
What i s the secondary source of water f l available to the operators to help onsure continued RCS heat l l removal ? (0.5) i I t l l \\ r' I ! i ! (4:488 CATCGORY 06 CONTINUED ON NEXT PAGC sesee) ! l l - - -
_ - _ _ - _ _ _ _ _ _ _. . _ _ _ _ _ _ _ _ _ - _ - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ __ - _ - _ r . . - t _ . . . .
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@ T SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
. J F . QUESTION 6.07 (2.40) !
. ' c. DEFINE the purpose / function of the Safety Injection Tanks (SITS)? (1.0) ' b.
DESCRIBE the operational concern associated with operating the SITS with f < a pressure greater than 250 psig? (1.4) ,
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, , 6.* PLANT ESTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
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.. . ., l QUESTION 6.08 (1.00) < < d
Prior to starting the fourth RCP during a plant heatup, the RCS'temperatere ! ' chould be (LESS THAN, GREATER THAN, or EQUAL TO) 500 degrees F.
EXPLAIN I your answer.
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PLANT BYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
' ! . ! !
i OUESTION 6.09 (2.00) '
LIGT any five of the seven conditions which cause enther the EDG to trip or
the EDG output breaker to open after an emergency start following a loss of ' ' normal power.
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l , . ! - OUESTION 6.10 (3.00) i Give the set point and the Technical Specification (TS) Bases for each of l the following RPS trips.
' < c. Reactor Coolant flew
b.
low SG 1evel i c. high P2R pressure i d.
high containment pressuru ,. i ,
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. QUESTION 6.11 (2.50) , With the plant at 100 percont power, a small leak occurs from the RCS to i the RBCCW System.
f . a. What TWO indications does the operator have available to him to identify j that this leak exists? [ ! I
b.
List the three (3) possible sources of this leakage.
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. 6d PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE 2t- . . QUESTION 6.12 (2.50) DRAW the power supplies to the facility 1 v1tal ac panel, 2-VIAC-1.
Include both the normal and alternate power supplios.
(ase** END OF CATEGORY 06 48***)
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. , ~ ~ ' ' . ,
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE
- RADIOLOGICAL CONTROL . . QUESTION 7.01 (3.00) QUESTION _AS ORIGINALLY WRITTEN A 24 year old f emal e wor ker, expecting to get pregnant. is scheduled to work in a Radiation Area where she will be exposed to a field of 50 meem/ hour.
Her lifetime exposure history per NRC Form 4 indicates the has received a lifetime wholebody exposure of 9,600 mrem.
During this present quarter, the woman has received 200 mrems of wholabody radiation.
CALCULATE how long the woman can work in the Radiation Area before , cxceeding her quarterly limit.
LIST all considerations used in arriving et your answer.
, OUESTION AS REWRITTEN DURING PRE-EXAM REVIEW d Answer the following questions concerning radiological exposure control practice at Milstone Stations c.
As a radiation worker, your quarterly whole body exposure limit has ' been increased to the maximum allowed by Millstone Administrative procedures.
During the current quarter, you have received a whole body exposure of 1.5 Rem.
How long could you stay in an area with a dose rate of 200 mrem /hr without exceeding your administrative j quarterly exposure limit? Shen all work.
State all assumptions.
j (1.00) { b.
List FOUR of the areas where a Radiation Work Permit is required for i entry.
(2.00) ! }
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P OCEDURES - NORMAL, ADNORMAL. EMERGENCY AND PAGE
RADIOMfl.11AL CONTk01 . . QUESTION 7. 0;' (2.90) pj)ESTIJN AS ORIGINALLY WRITTEN ANSWER the following qutastions concerning a loss of Instrument Air ( AOP-25e>3) : a. Explain why PZR level is conten11ed by securing the operating charging pump? (0.5) b. With the operating charging pump secured, HOW i s water made up to the RCS to make up for RCP bleedoff? (0.5) c.
IDENTIFY four de*_.1gn cent 1derations that make a t o '. a 1 1ons of instrument air extremely unl i kel y? (1.2) d.
A manual reactor trip must be initiated if instrument air falls below what value? (0.7) QlgSTION AS REWRITTEN OURING THE FRE-EXAM REVIEW ANSWER the following questions concerning a loss of Instrument Air (AOP-2563): e a. Explain why PZR level is controlled by securang the operating chargang pump? (0.5) i b.
W1th t h t.
Optretang char ga ng pump trcured. HOW it water AUT GMe"4T I f_. At t Y mane up t. o ti.- fuZ - ta mai : up f cr RCE a l i_ M W e ~ s' J, ; . c.
IDENTIFY four desagn considerations that make a total loss of i n s t r un,en t ' air extremely un110ely? (1.2) [ r d.
A manual reactor trap must be anatiated if inutrument atr falls below what value? (0.7) t (:4648 CATEGORY 07 CONTINUED ON NEXT PAGE
- 44)
. . . . /, PROG 000 REGAL DONTROL ADNORMAL. EMERGENCY AND PAGE
. . DUESTION 7.03 (1.00) An *,w er the f ul J own rig an accordance with AOPOLc4, " L o t. :, of hDCCW."
A s r.utt e the plant tu at 100 percent power. steady state contJ1tions.
At 14:20 the f ollowing alarms are annunciated: containment air recirc. coolers (H1 TEMP) t, pent fuel pool heat e:: changer (HI TEMP) letdown heat exchanger (H1 TEMPS Rx vessel concrete support cooling coals (LO FLOW) RBCCW-4 pump (TRIP) Also RCP-A bearing oil temperature is at 185 degrees F and slowly trending higher.
The operator immediately begins actions to restore RBCCW flow.
At 14:24 the RCP-A bearing cal temperature at at 190 riege r:es F.
ats seal temperature tu at 225 degreca F and its bloedoff temperature is 200 degrees F.
WHAT actiunt, if any. uh r.u l d the cper at or t al c EG LnIN ) c,ur urit wer. (e664: CATt? GORY 07 CONTINUED ON NEAT PAGE 44444i
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RAD I OL.OGIC AL_ _ CONTROL, . . QUESTION 7.04 (2.50) Assumo that SG No.1 Blowdown Rad Monitor has given a high alarm.
After 20 minutos the opterator trips the reactor because the CVCS 1s not able to maintain P7R level.
He c onipl et ec the st andord post trip actions of EOP252b and trannttions to EOP2534 "SG lobo Rupture."
o. WHY is the operator cautioned in EOP2534 not to use the steam driven AFW pump? (1.0) b. EOP2534 requires the operator to reduce Th to loss than 520 degrees Fahrenheit before manually isolating SG No.l.
WHAT is the reason for this? (1.0) c.
Why does EOP-2534 caution the operator that 1f ruptures are detected in both Steam Generators to only isolate one of the SGs? (0.5) l , t (**646 CATEGOR( 07 CONTINUED ON NExT PAGE 8684*)
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. 7, EROJE11)fM - _NO8[1GL. AriNORMA(. EMERGEN_QY AND PAGE
6AP10t&OLCAL CRNUlG,, . . OUCSTION 7. OS (1.00) In accordance with AOP-2571. "Inadvertent ECCS Actuation." onco an ECCS cetuation has boon determined to have been inadvertent, why is the operator cautioned on using the equipmunt h,$ndswitch to override an ESAS t,t gnal ? <44446 CATEGORY 07 CONTINi)ED ON NEXT FAGE
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. 7.
P. 3 R G E D_U_R E S - N O R M Al.. ADNORMAL. EMERRFECY AND PAGE
RADIOLOGICAL. CONTROL . . OllESTION 7.06 (3.00) A reactor trap occura 100 percont power.
EOP2525, "Standard Post Trip Actions," 1a entered.
a.
LIST thr ee ac t i ons/tmpec t ed r esponses whi ch are used to censure and verify that a turbane trip has occurred? (1.5) b.
Four CFAs remain stuck out.
How long must the operator borate? State any assumptions.
(1.5) i , t P i , , (64s44 CATEGORY 07 CONTINUED ON NEXT F AGE o6446)
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! MMPlJRl9ALcpNJ3QL
. . . ! GUESTION 7.07 (0.00) pjlgjT LON AS ORIGifiALLY WRITTEN Answer the following questions in accordance with Technical Specifications for refunl1nt) operat1ons:
c. WHICH nuclear instrumentation neust be operable? Include WHERE and WHAT type of indication each must provide? (1.0) b.
WHAT TWO reactivity conditions must be met for the RCS and the refueling canal? (1.0) c. GIVE the T6)O b.<ces why at leant one shutdown cooling loop must be ! operablo.
(1.0)
! l OUFSTION AS REWRITT[J1DURING F'RE-EX AM REVIEW _' ) l
Answer the following questions an accordance with Technical Goocificeittonu for ref ueling operations , o. WHICH nuclear instrumentation must be operable? Includo WHERE and WHAT type of indication each must provide? (1.0) i b. WHAT reactavity condit1on must be met for the RCS and the refuelnng Canal' (1.0) > r.
GIVE the T W O ta.. s e s wny at least c,n r shutdown c. col a ne l oo;, must ti t.
euerable.
(1.C)
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- i . (3.00) i i h AOP-2550, "Emergency Doration" i a condattons whtch ploted.
IDENTIFY may require emergency boratton? (1.2) of EOP-2532, tcpo ruqunred to inttnatn emergency boration? Include tione.
(1.0)
- ta reqtitred to
'ing? (2.0)
i CATEGORY 07 CONTINUED ON NEXT PAGE 4*eas) it4*)
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PROCEDURES - NORMAL._ ABNORMAL. EME3QENCY_AND PAGE
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BBD I OL O_G I C AL_ _ CONT ROL _ - , , I i .
QUESTION 7.10 (1.60) ,
< Assume there has been a reactor trap and the post trip actions of EOP-2525 ( . have been completed.
Plant conditions indicate that an excess steam event ' has occurred causing the RCS temperature to go below 500 degrees F.
The i operators have untered ECP-2536 "Excess Stuam Demand", and isolated the { faulted SG.
A CAUTION statement alerts the operators to the potential for r Pressuri;:ed Thermal Shock (PTS) of the reactor vessel.
Per EOP-0536, LIST the actions the operators should take in order to meet the Pressure / Thermal j limits of TS and IDENTIFY the systems used.
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( RADIOLQOICAL _ CONTRQL i ! ! " E . l
QUESTION 7.11 (1.00) ! i .I i t In accordance with AOP-2552, "Cooldown from Outside the Control Room", IDENTIFY the reason for the CAUTION that the Shutdown heat exchanger flow ' control valve be cracked open VERY SLOWLY.
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QUESTION 8.01 (1.00) , , lhe following question is applichble to ACP-QA-2.06A,"Station Tagging".
. MATCH the following tag definitions with the appropriate colored tag.
{
' \\ j o. Placed on equipment to prevent rennergietno 1. Red tag
i if it trips.
t t 2. Blue teg F b.
Placed on mechanical or electrical equipment !
which, if operated, would endanger personnel 3. Green ! j and/or equipment.
stripped ! t q hold tag i c. Placed on a device or piece of equipment as a j caution if other tags do not apply.
4. Yellow tag i
I ! d.
Placed on equipment to indicate tnat the equipment ! i tu to be energt:ed only by order of the indavndual { ] to whom the tag is issued.
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. . QUESTION a.a2 (3,gg) In accordanc s' w1 th ACP-DA-0. 06E4 "Jumper. Laftod Lead and L<ypacu Conteel".
LIST under what condition the Shift Supervisor can grant an exception to the requirement for performing an independent verification of a installed / removed jumper device.
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? ' i .i QUESTION 0.03 (1.00) l l f ! OVESTION AS ORIQJf4ALL.Y WRITTQ f ) ! TS Section 3.9.6 places a maximum loading limit on containment building cranes used in the "fuel only" region.
Give the TS Dasis for
this requirement.
( ! i
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, QlESTION AS REWRITTEN DURING PRE-EXAM REVIEW i i
! TS Section 3.9.6 places a maximum loading limit on containment refueling i machino cranes used in the "fuel onl y" region.
Give the TS Basis for ' this requirement.
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. l (e 8 4 s * CATEGORY 08 CONTINUED ON NEXT F AGE 4*4st) f (
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CONDITIONS._AND LIMITATIONS PAGE
. ' . OUCSTION 0.04 (3.00) I f OME lillOh.Af3__QRI.G_] N A L. t J_W R_!I Tg tj In accordance with ACP-CA-3.02. "Station Procedurns and Forms". would you, cc a licensed on-shift SRO, approve the following proposed coanges? . , Justify your a n t.w er. ' c.
A proposed change to an !&C surveillance would substitute a particular , model of digital volt meter with a newer model of digital volt meter.
b. A proposed change to an Operations Dept. valve lineup procedure would add steps to the procedure that would provide useful information to the operator for locating and identifying certain valves , c. A proposed change to an Operations Dopt. Abn or mal Operating Procedure would reduce the conditions under which the procedure would be applicable.
d.
A proposed change to a Maintenance procedure would add a new OC , hold point.
, OllESTION AS REWRITTEN DURING PRE-EXAM REVIEW In accordance with ACP-OA-3.02, "Station Procedures and Forms", would you, co a incensed on-shift SRO, approve the following proposed changes? Justify your answer.
a.
A crornced change t o ar. !! C sur s, a l l ar,e s would o u ts t, t a t u t e e partsculnr model of d i g t. t a l volt muter with a functionally equtvalent newer model of digital volt meter.
b. A proposed change to an Operations Dept. valve lineup procedure t would add steps to the procedure that would provide useful information to the operator for locating and i denti f ying certaa n l valves c. A proposed change to an Operations Dept. Abnormal Operating Frocedure would reduce the conditions under which the procedure would be applicable.
d.
A proposed change to a Maintenance procedure would add a new OC hold point.
(46448 CATEGORY 08 CONTINUED ON NEXT PAGE to668) - -_ . __
________ . . . a Sg ADMINISTRATIVE FROCEDURES. CONDITIONS. AND LIMITATIONS PAGE
. . QUESTION 8.05 (3.00) In accordance with 15 WHAT th the relationship between Limiting Conditione, for Operations (LCO), Limiting Safety System Setting (LSSS) and Safety Limits in terms of preventing releases of radioactivity to the environment.
, (*e4e* CATEGORY 09 CONTINUED ON NEXT FAGE
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. QUESTION 8.86 (2.00) OUESTION AS ORIGINALLY WRITTEN ' Listed below are the dates two monthly surveillances were performed during 1987.
Al so li s ted, when applicable, are the dates when the operational status of the trenins changed.
IDENTIFY whether or not the surveillance requirements were met.
EXFLAIN your answer.
Notes a calendar ta attached for your use, c.
1/2/87 2/2/87 3/9/87 4/9/87 5/15/87 sury.
surv.
surv.
surv.
surv.
b.
1/7/B7 2/7/87 3/18/87 4/9/87 4/20/87 4/29/87 surv.
surv.
surv.
declared surv.
declared inoperabic operable due to mann-tenance DUESTION AS REWRITTEN DURING FRE-EXAM REVIEW Listed below are the dates two monthly surveillances were performed during 1987.
Al so li sted, when applicable, are the dates when the operational otatus of the trains changed.
IDENTIFY whether or not the surveillance roquirements wete met.
EXPLAIN your answer.
Notes a calendar is attached for your use.
CONSIDER EACH CASE SEPARATELY.
a.
1/2/07 2/2/07 3/9/07 4/9/87 5/16/07 surv.
Surv.
turv.
sur v.
turv.
b.
1/7/07 O/7/67 3/10/67 4/9/87 4/2G/87 4/29/G7 sur y, sur y.
sur v.
declared surv.
declared inoperable operable due to main-tenance (aeaaa CATEGORY OS CONTINUED ON NEXT PAGE 4e644)
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. 8.
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITAT.10N1 PAGE
. . QUEGT!ON 8.07 (2.00) QUESTION _AS ORIGINALLY WRITTEN _ The Shift Supervisor has approved a Unit 2 Discharge permit for liquid rcdioactive waste per ACP6.03, "Radioactive Liquid Waste Discharge Policy", cnd the requtrod dilution flow has been eutabitshed.
Suddonly effluent monitors detect, at the site boundary. luvuls corresponding to 2 R/ hour whol e body exposure.
The concentration is determined to exceed the limits cpecified in 10CFR20.403.
Attached is a copy of Millstone Unit 2 Emergency Action Levels and EPIP Form 4701-4, "Reportability".
c.
IDENTIFY what immediate actions, including reporting requirements, the Shift Supervisor should take.
b.
WHAT level should this event be classified? JUSTIFY your answer by lasting the section of thu Emergency Action Level Tabic uced to clatsafy this event.
QUESTION AS REWRITTEN DURING PRE-EXAM REVIEW The Shift Supervisor has approved a Unit 2 Discharge permit for liquid rcdioactive waste per ACP6.03, "Radioactive Liquid Waste Discharge Policy", cnd the required dilution flow has been established.
Suddenly effluent moni tor s detect. at the site boundary, levels corresponding to 2 R/ hour whole body exposure.
The concentration is determined to exceed the limits cpecified in 10CFR20.403.
Attached is a copy of Millstone Unit 2 Emergency Action Levels and EP!P Form 4701-4, "Reportability".
o.
I IIN T I F i em t..Ttd eto at t cric.
a ric 1m ng r i;wr t a r.9 r 4 n.t. : r a... s. the Shaft Supervisor should take.
b.
WHAT NRC Icvel shoul d thi s event be classifisd? JUSTIFY your answer by listing the section of the Emergency Action Level Table used to classify this event.
(estos CATEGORY 08 CONTINUED ON NEXT PAGE **484) ~
_ - _ _ _. _ _ _ _ _. _ _ _ _ - _ _ -. _ _ _ _. _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _
', s a g.
_.7 , , < - . ~ 9.
ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE
. . i OUEST10N O.00 (1.50) QUESTION AG ORIGINALLY WRITTEN aK In accordance with ACP-DA-10.05 "Log Book Requirements, (Control
Room)", INDICATE whether the following statements are TRUE or FALSE with respect to Control Room Logs.
' o. The on-duty Supervising Control Operator (SCO) may make entries ) into the SS Log.
b. The SS log can have a blank line between entries.
] c. In the event the computer is unavailable, the SCO may make entries into l the POP log.
a
DUESTION AS REWRITTEN _pWRING PRE-EXAM REVIEW ! In accordance with ACP-04-10.05 "Log Dook Requirements. (Control Room)". INDICATE whether the following statements are TRUE or FALSE with . rospect to Control Room Logs.
. j o. The on-duty Supervising Control Operator (SCO) may make entrien
into the SS Log.
! ] b. The SS log can have a blank line oetween entries.
a c. In the event the computer is unavailable, the PPO must take manual
l logs.
l , .i ! l
j l J (estat CATEGORY 09 CONTINUED ON NEXT PAGE 8****)
_ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ - - - _ - _ g g t b
y % , gJ NG . , d.
ADMINISTRATIVE W DURER. CONDITIONS. AND LIMITATIONS PAGE
. . DUESTION 8.09 (1.50) In accordarace with SHP-4912 "Radiation Work Permit Complotton and Fl ow Control", LIST the THREE SS/SCO responsibilities associated with theke oigning Radi ati on Work Permi ts.
( eeea CATEGORY 09 CONTINUED ON NEXT FAGE 44864)
-,,., - -. -. - - - - - - -. - - -, -. - -, - - - - - -, -. - - - - - - - - - - - - - - - - - - - - - - - -,. - - -. - - - - -. - - - - -- - - -- . - - - - - . . .. , , , 9.
AiMINISTRATIVE PROCEDURES. CONDITIQNS. AND LIMITATIONS PAGE
, - l . j '
QUESTION 8.1B (2.50) , i In accordance with Technical Specifications for fare protection and the AOP-2579 series "Contingency Fire Procedures f or... Appendix "R" Fire...": J c. WHAT is the minimum number of Fire Brigade members required to be maintained onsste at all times? (0.5)
b. WHAT is the manimum number of members of the MIN! MUM OFERATING SHIFT CREW, as required by TS, which can be assigned to the Fire Seigade? (8.5) . c. WHAT is the maximum amount ce time that the number of members of the l Fire Brigade can be less than the minimum required by T57 (0.5) d. IDENTIFY the two locations where the two way radn os, used for backup j communtcations, are stored? (1.0) I i i ! .
1 ] d
i (644ss CATEGORY 08 CONTINUED ON NEXT FAGE 48844)
___- _ . _ _ _ _ _ _ - -._ . _ _. _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _. - _ _ - _ _ _ ..
. . , g i i 3%.
] .- - t . 8, ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONA PAGE
< .
i < a . OUESTION B.11 (2.00) ,
i ! TS Section 3.4.4.6 states thet " the pressurtzer shall be "OPERALLE" with ...at least two groups of pressuriter heaters having at least 139 kW."
WHAT to the TS Basis for this requirement?
. I i ) i i
- l
3
6
I i
s
a .
! ) i l } l , teaae4 CATEGORY 03 CONTINUED ON NEXT PAGE 44444)
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ - ~ . ,. '. '. ' "' ' w+ -
s.
AlMINISTRATIVE PROCEDUREE. CONDITIONS. AND LIMITATIONE PAGE
i
1 DUE T10N 8.12 (1.50) . } 911M M ON AS ORIQLUALLY WRITTEN i j In accordance with ACP-QA-9.82, "Station Surveillance Program", assume that the Maintenance Dept. comes to the Shift Supervisor (SS) with a Work Order
j to perf orm a surveillance on HFS! pump "A" that will require that it bei takun out of service, o. LIST what action (s) the SS must perf orm prior to signing the q Surveillance Data Sheet authorizing the work.
(9. 5 ) a I b. Upon completion of the surveillance by Maintenance, IDENTIFY the two actions the SS must perform prior to checking the correct "Acceptance
i Criterka Met" block and signing the Surveillance Data Sheet accepting ) HPS! pump "A".
(1.0)
QUQTION AS RGR.[HE!L,p,VRING PRE-EXAM REYJG i l In accordancee with ACP-CA-9.02, "Station Survet11ance Program", assume that the Maintenance Dept. comes to the Shift Supervisor (SS) with a Worn Order j to perform work on HPS! pump "A" that will requirw that it be taken out of
cer vi c e.
i g o. LIST what action (s) the SS must perform prior to author 1 ring the work.
(0. 5) ' l l b. Jipon completion of the work by Maintenance, IDENTIFY the two actions
the SS must perform on the Surveillance Data Sheet prior to ched ing
t r.o correct " Ac u pt inc e Cr i ter a a Mc t L1ari.no i.apor.e tne Sur w111 anc e Data Sheet acceptang HFS! pump 'A".
t1.0) (44844 CATEGORY 00 CONTINUED ON NEXT PAGE se 4e)
T' , - ' , c ; ;L.: ~ ' ...j, , , , d'. dDMINISTRATIVE_ PROCEDURES.
CONDITIONS. AND LIMITATIONS PAGE
. . QUEDTION 8.
(1.00) An I&C 9 had been trouble shooting a problem with the rod control cystemi m-r-control room operator requests permission from the SCO to ollow t acian to step the rods in one step.
The plant is at 90 percent v SHOULD the SCO grant permission to allow thu technician to operate t;.- controls? JUSTIFY WHY or WHY NOT permi ssi on should be granted.
. (***** CATEGORY 08 CONTINUED ON NEXT PAGE
- )
. . (. 37;: + 1: s..- ,,e- - s ,# , .,,, . 5., ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE
. . - DUESTION O.14 (2.00) According to Technical Specifications, Identif y the FOUR criteria that d::;termine when containment integrity exists? i t
(***** END OF CATEGORY OG
- )
(************* END OF EXAMINATION ***************) ' , - - - - _ _ _ -.., -. - _ _ _ -. _ - -, -
- -_ _ __._m, _ . .__ _.. _ _ _.. - _. _,_ - - .;x
,. : .
. 5.
THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
THERMODYNAMICS . ANSWERS -- HILLSTONE 2-88/07/20-PRELL, J.
. s ANSWER 5.01 (1.00) Allows the delayed neutron population to decrease sufficiently so as to ovatd an unacceptat;10 return to power s i t uat i on. [#.f] 4 '. J i d d hy f
. & *nhW!re ke'n g eoyg }e egget*b/ [*r Con /arkmanf &.Or~f it/. @A
REFERENCE Jy>n,, Air e f ran $ tostjo g gyp, M,,,,o f fe. y} f 1.
LP-2322, EO - 4 2.
SD-2322, p-
). Pped.t-tg.1-?f K/A 035000K109 3.0/4.5 035000K301 4.4/4.6 035000SG04 3.4/3.4 035000K109 035000K301 035000SG04 ...(KA'S) ANSWER 5.02 (2.00) Height above which rods must be maintained C O. 5 3 in order to 1.
provide adequate shutdown margin CO.53 2.
limit ejected rod worth CO.53 3.
limit peaking factors CO.53 REFERENCE 1.
LP-2117 p -X. y f.? E O .+ $ / 4 2.
E:< a m bani: 2117 q - 350 h/A 19200M 115 3.4/3.9 192005K115 ...(KA'S) ANSWER 5.03 (1.00) REMAINED THE SAME CO.43 The SDM is not dependnat on rod height. [0.63 REFERENCE 1.
LP-2116G, p-35 EO-1b 2.
Exam bank 21160, q-111 K/A 192002 K1.14 3.8/3.9 192003 K1.07 3 0/3.0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
. . ' .: ..- < ' !i.
THEORY OF NUCLEAR POWER PLANT DPERATION. FLUIDS. AND PAGE
' THERMODYNAMICJ.
. ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. 192002K114 192003K107 ...(KA'S) ANSWER 5.04 (2.40) [a ny hwr- @ C'. $ d'a c8)CEAs 1.
power drops promptly CO.33 due to negative rho inserted by tire CO.33 2.
positive rho is added CO.33 as moderator temperature decreases CO.3J 3.
negative rho is added during the next 10 hours CO.33 due to the Xenon builrfup CO.33
positive rho is added between 8-10 hours to 24 hours CO.33 due to Xenon decay CO.33 REkRLNCEx adi;< <-4sco.8 hef / d'eemre &..G SG 0 S. pyera {g [o.Q Mw ' e, J u)/V y ,- 1.
LP-2116E, p-10,11, F-EO-2 2.
LP-2116F. p-17,18 EO-4,5 K/A 192008K124 3.5/3.6 192006K107 3.4/3.4 192008K123 2.9/3.1 192008K124 ... WA'S) ANSWER 5.05 (2.00) c. I S NEGATIVE (mare pat /NIe) 6. I NEGATIVE c.
MORE NEGATIVE d.
MORE NEGATIVE CO.5 each] , , REFERENCE LP-2116E, p-16,19,21 EO-03 K/A 192004K106 3.1/3.1 i 192004K1G6 ...(KA'S) ! l l ! l
. . , . . . - ' 55, THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
THERMODYNAMICS . ' ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. ANSWER 5.06 (2.00) c.
A b.
c.
d.
[0.50 each3 REFERENCE 1.
LP-2117, p-23,24,25 EO-lh,16 2. LP-2116D, TP-3 K/A 192005k114 3.2/3.5 192005K110 3.0/3.3 1 2005K115 192005K1.1 ...(KA'S) ANSWER 5.07 (1.50) c.
Increases [0.23 - due to program Tave. CO.33 0 r-e mer C 9_ 2 2 - der te WTC E9_?? . c.
No change CO.23 - due to heaters cycling on and off CO.33 Wo theyt (A t7 - de t" N / N s fe h fo.t h h / S N / ~ 0 [*. U REFERENCE 1. LP -2304 A, p-3,4 EO-5 F/4 010000A105 2. S / 2. 9 0100004106 3.1/3.2 010000A107 3.7/3.7 011000A101 3.5/3.6 011000A104 3.1/3.3 010000A105 010000A106 010000A107 011000A101 011000A104 ...(KA'S) i
.
', ' .,,c n- , , 5., THEORY OF NU_ CLEAR POWER PLANT OPERATION. FLUIt)S. AND PAGE
THERMODYNAMICS . ANSWERS -- MILLSTONE 2-88/07/22-PRELL, J.
. ANSWER 5.08 (3.00) rho 1 = (k1 1) / k1-0.04 CO.253 - = kt 1 / (1 - (-0.04)) = 0.9615 CO.253 = 100 (1 - 0.9615) = 196 (1 - k2) CO.253 k2 = 0.9804 CO.253 rho 2 = (0.9804 - 1) / 0.9804 = -0.02 = 0.02 = g A g / / 5 og CO.253 rho 2 - rho 1 = -0.02 - (-0.04) _.. 0 -.m CO.53 g y g ' 200p a. is due to Xenon, therefore remaining -!S00pcm is due to A the boron.
CO.53 1mempr- - 19??pc- '19p:r pp ' - 100 ppm CO.53 ' ' 900 ppm 100 ppm a 800 ppm the new boron concentration CO.253 - W##'"/ $ } "' '# '"' ' RE ERE 1.
LP-21168 EO-4 K/A 192008K104 3.8/3.8 192007K105 3.0/3.2 192008K104 ...(KA'S) ANSWER 5.09 (.60) False CO.603 REFERENCE 1.
LP-2116D. p-15 EO-7 h/A 192007L104 3.1/0.4 192007K104 ...(KA'5) _ _. _ _ __ . _ _
_ _ _ _ _ _ _ _ _ _ _ _
- .
', "NL ;. . ,. . 5, THEORY OF NUCLEAR POWER PLANT OPERATION. FLUIDS. AND PAGE
THERMODYNAMICS . ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. ANSWER 5.10 (2.50) SGpress.= 650 psia = 495 degrees F sat.
CO.53 Tc wi11 fullow SG temp., thus Tc = 495 degreos F C0.53 Th = 30 + Tc = 525 degrees F C O. 5 3 PZRtemp. = Th + 35 = 525 + 35 = 560 degrees F CO.53 PZRpress. = sat. pressure for 560 degrees F = 1133.4 psia CO.53 REFERENCE 1. LP-2121C, p - 7,B,9,10,11 EO-5 2.
Exam bank 2121C, q-1172 K/A 193003K125 3.3/3.4 193003K117 3.0/3.2 193003K117 193003K125 ...(KA'S) ANSWER 5.11 (2.00) c. True b.
False c.
True d.
False CO.5 each] . REFERENCE 1.
LP-2121J, p-14,18,19,22 EO-4,5,6,8b t/A 19 :00 3 : 1 :J.
4. '? / 4. L 193008K122 ... WA'S) ANSWER 5.12 (2.00) a.MP b.
PDP c.
BOTH d.
NEITHER CO.5 each) REFERENCE 1. LP-2121E, p-17,19,21,32 EO-2a,2b.2c,4 K/A 193006K115 3.1/3.3 193006K115 ...(KA'S)
-. ______-_ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __- _.
_ _ _ _ _ _ _ -. . . . . ' S'. TkDRYDFNUCLEARPOWERPLANTOPERATION. FLUIDS. AND PAGE
- THERMODYNAMICS
. ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. A ANSWER 5.13 (3.00) c.
Increase b.
Decrease c.
Decrease d.
Increase 'O.
Decrease f.
Decrease CO.50 each3 3 Reference 1.
LP-21211, p - 20 EO - 4 2.
LP-2117, p - 29 K/A 193008K105 3.4/3.6 REFERENCE 193008K105 ...(KA'S) ! I .. -_.. - -. __ _ .. . - - - .
. , '. ' b-I ' . - . he PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
ANSWERS -- li!LLSTONE 2-08/07/20-PRELL, J.
. . ANSWER 6.01 (2.00) ft/0 1 c.
prevents the withdrawal or insertion f regulating CEA CO.253 if any shutdown CEA is lower than 163 steps CO.253
b.
prevents withdrawal or insertion o any shutdown CEA [0.253 if any regulating CEA is above 13 steps (0.253 6 # # h / // c. inhibits both insertion and withdrawal motion for any of the 61 CEAs [0.253 with the occurrence of a PDIL, out of sequence overlap, group deviation, MIRG or MISH [0.253 d.
prevents all CEA group withdrawal CO.253 when 2 out of 4 RPS channels of high power or thermal margin low pressure exceed their pre-trip setpoints (0.253 REFERENCE 1.
SD-2302A, p-19,30,32 EO-6 K/A 001000K402 3.8/3.8 001000K504 ...(KA'S) ANSWER 6.02 (2.40) c.
i b.
c.
d.
[0.6 each) REFERENCE l 1.LP-2301, P-35 EO-06 K/A 003000K103 3.3/3.6 003000K103 3.5/3.9 i 003000A201 003000K103 ...(KA'S) i
. , . . - -. - - - - - - -, ,,., , . , ,,., - - -
.. .. .. ;,4 . ;4. ~.' . . , , , . ' ( . . d., PLANT SYSTEMS DEBIGN. CONTROL. AND INSTRUMENTATION PAGE
. ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. ANSWER 6.03 (1.00) c. True 6.
False CO.5 each3 REFERENCE 1.
SD-2304, p-37 EO-3,10 2. OP2304F, p-5 K/A 004010K505 3.8/4.2 C34010K505 ...(KA'S) ANSWER 6.04 (3.00) c. False CO.53-SIAS would still occur on high containment pressure CO.53 b. False CO.53-also need a SIAS present CO.53 c. False CO.5]- does NOT monitor PZR level CO.5] REFERENCE 1.
LP-2384, p-13,16 EO-6,11 K/A 013000K101 4.2/4.4 013000K412 3.7/3.9 013000K101 013000K412 ...(KA'S) ANSWER 6.05 (1.20) 1.
Tq-Azimuthal tilt 2.
ASI-Axial shape index 3.
Fr-Integrated radial peaking factor
FrT-Integrated radial peaking factor total 5.
Fxy-Planar radial peaking factor 6.
FxyT-Planar radial peaking factor total 7, LSM-4/orme Wh/ We ft Cany 4 at 0.3 nach3 REFERENCE LP2117, p-43,44,F30 EO-9 K/A 193009K106 2.8/3.7 193000K106 ...(KA'S) ____ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _
. -. . .- 4.
PLA?dT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. . ANSWER 6.06 (2.00) c. Water steaming off via the Steam Dump system (0.53 b. Both motor driven AFW pumps start (0.53 and both AFW regulating valvou (ejashjfer/ m y w eg-e) " A ft a s'u'& s t(*.r*) open. CD.53 o c. Plant fire water CO.53 REFERENCE 1.
LP-2316A, p-17 E3-14 2.
SD-2322, p - 7,8,9,10 EO-9,10 3.
OP-2322, p -9 K/A 061000K406 4.0/4.2 061000K501 3.6/3.9 035010K101 4.2/4.5 035010K109 3.8/4.5 035010K301 4.4/4.6 035010K402 3.2/3.5 ANSWER 6.07 (2.40) a. Provide a reliable means of rapidily reflooding the core following a ' large-break LOCA.
C1.03 . b. Could introduce Nitrogen into the RCS CO.73 which could r s= s u l t in oat t) niitng of t hi s h.e.t removal flow path. [0.7) REFERENCE 1.
SD-2306, p-1,4 i 2.
LP-2306-9 EO - 1,17
K/A 006000K602 3.4/3.9 I 006020A107 3.5/3.7 006000SG04 3.5/3.8 006000SG07 3.8/3.9 i ' 006000k602 006000SG04 006000SG07 006020A107 ...(MA'S) l l
I I
. . , . .. - -
. 6., PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATION PAGE
ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. . ANSWER 6.08 (1.00) Greater than CO.53 Prevents uplifting of the core internals due to the higher density of the RCS below 500 degrees F.
CO.53 REFERENCE 1.
LP-2301, p-19 EO-12 K/4 002000A105 3.4/3.7 002000K501 3.1/3.4 002000A105 002000K501 ...(KA'S) ANSWER 6.09 (2.00) 1.
Lubo oil pressure low 2.
Engine overspeed 3.
Voltage restraint overcurrent 4.
Generator differential overcurrent 5.
Start failure 6.
Generator under frequency 7.
DG trip / shutdown Cany 5 of 7, 0.4 pts each3 REFERENCE 1.
LP-2346, p-78,79 EO-2 L/A 0640006402 0.7/4.2 064000L402 ... O:A'5'e
- - - - - - - -
.. _. _ _. _ _ _ _ _. _ _ _ _ _. .. - __ .. . . . . ,,- < . , '6.
PLANT SYSTEMS DESIGN._ CONTROL. AND INSTRUMENTATION PAGE
ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
- . s ANSWER 6.10 (3.00) c.
1. greater than or equal to 91.7% CO.253 2. protects core from a DNBR 1.3 or less if a RCP is lost,CO.503 few re d sftw th RdJ fhu) b.
1. greater than or equal to 36 percen, CO.253 2. assures that a minimum inventory of secondary cooling exists after a trip OR protects RCS from inadequate cooling and overpressurization CO.503 c.
1.less than or equal to 2400 psia CO.253 2.to protect RCS from overpressurization due to loss of load that does not cause a Rx trip CO.503 d.
1.less than or equal to 4.75 psig CO.253 2.to assure a Rx trip occurs concurrently with a SI AS CO.503 REFERENCE LP-2380-1, p-4.5 EO-9 TS 2.2.1, p - 2-3, 2-4, 2-5, B2-4, B2-5, B2-6 K/A 012000K402 3.9/4.3 012000K402 ...(KA'S) ANSWER 6.11 (2.50) $***ple e-rJh/4 een A8 CC l<.) er$mf.$W %ftern b o . ham et t on marit t or i nc t cz,s e cs r el ur m.
surge t a ro le.ol t r i c r * * e, i
de*/$ @ G.frnoA) , b.
Letdown heat exchanger, RCPs, primary sample coolers CO.5 each3 REFERENCE 1. LP-2230A, p-7 & T-A EO-11 A. A W G* N EI /*] ' e'/A 000000K102 3.3/3.4 000000K104 3.3/3.3 , l\\ t i.
,,, _ _. _ - _. - _ _.
. . . . 6., PLANT SYSTEMS DESIGN. CONTROL. AND INSTRUMENTATIOR PAGE
ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
, . . ANSWER 6.12 (2.50) g ggg4ggy sus teln -ISCvoc . MtReto-13Evpc 2 - INV*l ? % VS #l C' L 2 *IN V"5 C INvt M ER n A TI C.s ulten INVERTER 3-, m.. , L - Vid C ~ l $$. 95K Sua attached sketch C 2. 5.1 REFERENCE 1.
SD-2345, p - 3, f 1,2 - 2.
LP-2345, EO-2 K/A 062000K104 3.7/4.2 062000K104 ...(KA's)
. . . . 7.. PROCEDURES - NORMAL. ADNORMAL. EMERGFNCY AND PAGE
RADIOLOGICAL CONTROL . ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
A.
NMlps $/ pjf *def~dU op9/*9 egis = [Oof)"
of$~99 = M'Ft.* m / M oor r to [d.9J) 4~ Arnn Co. s12 /099 Y a sto e 4 4,js Raasa% Ria r, b,de, h Ra C.WA /7se.,' C d a.,v!e N 8es'**,fds, W9Ak tR,a,'.s / e 4,s.,s // 4 ANSWER 7.01 (3.00) /Virlornd $s!>eds chP w ar se /V/ t's L 4.my f @ 0.1~ee c'N :e> - 7e --- t t :e :1 111et i-r 1 1 -4 t ri i erre te,r3
%4---2W 4 -~--20400 r t r 1cft brfcrc she-e*cerd: 1. 2 :".- 1i-i t t 9. '" 3-SCO - -!qtr. 211cx:d f =:10, rupreted p gnancy, MMece-nted cured qu r terl y :::p::ur:-- - C 2. 5 3-- 522 reme - 2 22 - e.wo-=--32 2 - :n; 1 ft th!: quarter CO "' w na m.mm te m-w_11mi, tin 9--4.hsr_s i cr_a 300 / Sammelh-6 !we M 51 " REFERENCE 1.
SHP-4902.
P-7.8,9 50 ~~ /1?A *0A *'l 0.~f077"' AW'#~ ~ ,R,s,fM** HeA f* $ 7 /77at - 09 -4 cf077~ ~/9 Dir!/M*$N~$* A* l s A/A 194001K104 3.3/3.5 8*d'/ 194001K104 ...(KA'S) ANSWER 7.02 (2.90) c. letdown flow control valves fail closed on loss of instrument air CO.53 6.
the bactuo charging pumo cyclon on and off CO.53 c.
1.
rt>dundancy of t ratrument air compres. sors 2.
station to instrument air crons-tio 3.
Unit 1 to Unit 2 cross-tie 4.
the uno of flow limiting orificos throughout the air system J~ d' '/t f.C/> fen.) e6eck s/< fog / 6,n,y y gG, f0.3 oach3 d.
00psig CO.7) REFERENCE 1.
AOP2563, p-0,6 EO-1 .2. lP of J.%1)[l9,o y **3 0 K/A 000065K303 2.9/3.4 000065K304 3.0/3.2 000065A103 2.9/3.1 000065A206 3.6/4.2 000065A103 000065A206 000065F303 000065K304 ...(KA'S)
_ _ _ - _ _ _ - _ _ - _ _ _ - - _ _ _ - _ _ _ _ . . . . - 7'g PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE
RADIOLOGi_ CAL CONTROL . ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. ANSWER 7.03 (1.00) a Trip the reactor C O. 53 RCP bleedoff temperature greater than 195 degrees F.
CO.53 REFERENCE 1.
AOP2564, p-2,3 EO-1b,c,dt7 K/A 000000K102 3.3/3.4 l 808000K301 3.4/3.5 008000K102 008000K301 ...(KA'S) . ANSWER 7.04 (2.50) l
a. it would result in an unmonttored radioactive release C 1. 0 3-b. this minimizes the potential for the subsequent lifting of the SG
safeties C1.03 c. SGs are vital for RCS heat removal CO.5] REFERENCE 1.
AOP2569 p-2 EO-2
2.
EOP2534 p-6.9 EO-3.5 i h/A 00003/L305 3.7/4.0 ' 000037K307 4.2/4.4 000037K305 000037K307 ...(KA'S)
p - - - - - --.:-.-..._...-... ......... _ _ . . ' . . PROCEDURES - NORMALA ABNORMAL. EMERGENCY AND PAGE
. RADIOLOGICAL CONTROL . ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
. ANSWER 7.05 (1.00) Future ESAS signals will not be processed for that equipment until the ESAS modules have been reset.
C1.03 REFERENCE 1.
AOP 2571, p-3,4 EO-1 c, 2 K/A 006000K413 4.1/4.3 006000K405 4.3/4.4 006000K418 3.3/3.8 006000K405 006000K413 006000K418 ...(KA*S) ANSWER 7.06 (3.00) a.
1.
Depress the turbine trip button 2.
Verify steam admission valves are closed 3. Verify the generator megawatts equal zero CO.5 each) 6.
two charging pumps running CO.5] //vN 8 /O ( J A *s <h /r*/ ' /
- f/* -' t 10 minutes / stuck rod CO.53
- / / d/Jhat J M, /A me'n/W/
(# rods stuck - 1) X 18 = 54 minutes (0.52 REFERENCE 1.
E r f, * e.15.
p.6 c. 0 - 4 ' K/A 000007K301 4.0/4.6 000024K301 4.1/4.4 000024K302 4.2/4.4 000007K301 000024K301 000024K302 ...(KA'S)
. _ _ ______.... _ _ _. ... ,__.._.. - _ -.- -1 -
. . . . . ~ 7.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE
RADIOLOG.JSAL CONTROL . ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
> .
ANSWER 7.07 (3.00) a. Two source range neutron flux monitors (wide range log NI) CO.53 Each must provide a continuous visual indication in the control room CO.253 and one an audible ndication inside containment.
CO.253 716e me bE/*AQ * { [C O.# 0.
b.
Keff </= 0.95 WO3 Cb >/= 1720 ppm C O.%0 3 c.
1. Ensures sufficient cooling capacity to remove decay heat CD.253 and maintain less than 140 degrees F.
CO.253 2. Ennures sufficient coolant circulation to minima::o af f ects of a boron dilution incident CO.253 and prevent baron stratification.
CO.233 REFERENCE 1. TS 3.9.2 and 3.9.1.
P3/4.9.8 EO-7ce_4_/gpc/[fgent TAfr-f274 K/A 000036SG03 2.9/3.8 000036SG04 2.6/3.8 R33000K302 034000A401 034000K602 ...(KA'S)
r -- .. , < o.
. ., '. ' + "..
- ?.v.'L2ll v
- 'P ' W:. f Ma z
' .m ' e.
,, . + ~ " .;',
- ' '
> % $;ik':; Q l' . - 7.
PROCEDURES - NORMAL. ABNORMAL. F.MERGENCY AND' PAGE
RADIOLOGICAL CONTROL . ANSWERS -- MILLSTONE 2-89/07/20-PRELL, J.
. ANSWER 7.00 (3.00) c.
1.
Two or more CEAs have not inserted following a trip 2.
An unanticipated reactor cooldown has been initiated 3. PDIL alarm is annunciated 4.
While shutdown, an unexplained increase in reactivity is noted Cany 3, 0.4 each3 b.
1.
Open BA pump discharge to charging pump suction valve (2CH-514) CO.33 2.
Start both BA pumps CO.33 3.
Close BA pump Recirc. v.ives (2-CH-510 and 2-CH-511) CO.33 4.
Start all available charging pumps CO.33 OR IF BA pumps fail to start 2a. then open BA gravity feed valves to charging pump suction (2-CH-508 and 2-CH-509) CO.33 3a. then close VCT outlet valve (2-CH-501) CO.33 REFERENCE 1.
AOP2558, p-2,3 EO-la, DJT K/A 200024EK301 4.1/4.4 000024EK302 4.2/4.4 0:0024EK30 ...(KA'S)
M.
j, L - . , ,. , ! :,,
- $
, . -. - {... : 3 .4 ' S. - ,, e- .
PRDCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE' 69 f RADIOLOGICAL CONTROL
ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
, ANSWER 7.09 (3.00) a.
1.
Abnormal change in PZR level 2.
Decreasing PZR pressure 3.
Increasing containment pressure 4.
High containment radiation 5. Unbalanced charging / letdown flows tany 4, 0.25 each3 b.
1.
PZR level increases greater than expected using Aux. spray 2.
P2R level increases slower than expected for existing HPSI and charging flow 3.
Unheated thermoccuples in the upperhead indicate saturated conditions 4.
RX vessel level is less than 100 percent CO.5 each] REFERENCE 1.
EOP2532, p-2,10,11 EO-16,4c,6b K/A 000011Ek312 4.4/4.6 000011EA114 3.9/4.1 000011EA201 4.2/4.7 000011A114 000011A201 000011K312 ...(KA'S) ANSWER 7.10 (1.60) o hafo4*rx dy sw(WJ h ey'd'ra & J'G[A E& /. By 1%f slb 9 7'/3J er~ en, ,2.
Control heat removal by careful addition of feedwatcr to operating SG C0.25] - '- ^ '- ** " ' t '- -'- ' '
- 2 = = =
t'- . ;: .:t : 4 ?" !?..-9:- 3. Control of RCS repressurization CO.33 via HPSI CO.253 and CVCS CO.253.
REFERENCE 1.
EOP-2536, p-
2.
LP-2536 EO - 10 . K/A 000040K106 3.7/3.0 000040A106 4.0/4.1 000040SG03 3.1/3.9 000040A106 000040K106 000040SG03 ...(KA'S) i l _.-.. -___ _ . _ _ -. -
- - - __ __ _ _ _, _ _ _ _ _ _ _ _ _ _ _ - _ - - - - - _ - - _ _ - - - - - - - - .
t, :, ;;. .,
.. ;, -
- ,.
'/ E/;, v at, ' MSJOULI;J-;'> _ .s . r < Nie y i 4 M' -Ja., ,. .s n, lllu; q, ' ' s.
,. .
- e+
, . . ,,- . , + s - . f.
PROCEDURES - NORMAL. ABNORMAL. EMERGENCY AND PAGE
- *
BADIOLOGICAL CONTROL
ANSWERS -- MILLBTONE 2-88/07/20-PRELL, J.
. ANSWER 7.11 (1.00) Prevents excessive thermal shock to the shutdown heat exchanger C1.03 REFERENCE 1. ADP-2552, p - 10 EO-ax(,_,[yf/f!______ K/A 004000K509 3.7/4.2 004000SG10 3.1/3.4 004010A401 3.6/3.1 004010K622 2.3/2.6
004010K403 3.1/3.6 004000K509 004000SG10 004010A401 004010K403 004010K622 ...(KA'S) . ! ! , , , i
-- . , , ~~, 3 . ;,y _ , , ,,
- =,
',,. . , ' f 3?;QqQy '; I':.~"V,r% '
- ,
^ .' ' ' o ir.>- ,- " ' ,, . .,. ,,, , . r~
- I
,. 8,. ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE
ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
, . ANSWER 8.01 (1.00) c. 3 b.
c.
d.
(0.25 each] REFERENCE 1. ACP-QA-2.06A, p-3,4 - EO-5 K/A 194001K192 3.7/4.1 194001K102 ...(KA'S) ANSWER 8.02 (1.00) If verification would result in significant radiation exposure C1.0) REFERENCE 1. ACP-OA-2.06B, p-10 EO-5e,6a K/A 194001K102 3.7/4.1 194001K102 ...(KA'S) AN3WER 0.07 (1.00) The coro internals and pressure vessel are protected from excessive lifting force in thu event they are inadvertuntly engaged during lifting operations.
C1.03 REFERENCE 1.
TS 3.9.6, p - 3/4 9-6, D3/4 9-2 2.
SD-2303A, p
EO-6 - K/A 034000SG06 2.5/3.6 034000SG06 ...(VA'S)
. __ __ _ _ . . . . g.
kDMINISTRATIVEPROCEDURES. CONDITIONS. AND LIMITATIONS PAGE 72-ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
, . ANSWER H.04 (3.00) c. Yes CO.253, Non-intent CO.53 b.
Yes CO.253, Non-intent CO.53 c.
No CO.253, Intent (0.53 d.
No CO.253, Intent (0.53 REFERENCE 1.
ACP-QA-3.02, p-5,6,27,30 EO-3,7,10 K/A 194001A102 4.1/3.9 194001A102 ...(KA'S) ANSWER 8.05 (3.00) LCOs indicate the lowest performance level of equipment reautend for safe operation of the plant C1.03.
If automatic actuation of protective aquipment related to those variables having significant safety functions occurs prior to the LSSS, then the Safety Limits will not be exceeded C 1. 0 3.
If Safety Limits are not exceeded then fuel and RCS integrity will be maintained C1.03.
REFERENCE 1.
10CFR50.36(c) 2.
TS EO-5 h/A 002020$G05 3.6/4.1 002020GG06 2.6/3.0 002020SG05 002020SG06 ...(KA'S) ANSWER O.06 (2.00) a. Roqs. were NOT mot (0.33 - The combined time interval for the last thrco consecutive surveillance totervals exceeded 3.25 times the specified survuillance. CO.73 b.
Roqs. were mot CO.33 - Surveillanco ruquiramonts do not have to be performed on inoperable equipment. CO.73
. . . . d ADMINISTRATIVE PROCEDURES. CONDITIONS. AND LIMITATIONS PAGE
i ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
, . REFERENCE 1.
TS-4.02 4.03; 4.3.3.3 2.
TPG 2400,2600/ Generic "Surveillance Procedures": EO - 1 K/A 016000SG05 2.9/3.5 0160005G05 ... ( >; A ' S ) ANSWER 8.07 (2.00) a.
1.
terminate the discharge (0.53 2.
classify the ovent (0.53 3. notify the NRC(wi thin one hourf CO.5] b.
General emergency CO 51 , REFERENCE 1.
ACP-6.03, p -5 L 2.
EPIP 4701, p-3, F - 4701-2,4701-4 EO-1
3.
EPIP 4112, p-2 K/A 0000685G01 3.3/4.1 0000685G02 2.9/4.1 0000685G01 0000685G02 ...(KA'S)
I AN3WER 3.03 (1.50) t c.
True b.
Falso i c. "21 r r 77we, CO.5 each] ! r REFERENCE - , L 1.
ACF-0A-10.05, p-4,7 EO~gt2~.e2 4 c1927-f]Dt?WW* Al'? . ' YQd K/A 194001A106 3.4/3.4 194001A106 ...(LA'S) N #' I
I ( f I ! f
-- . . .
[ m,g% .n
- .
, ', ', /d:.9;% '=' X. 3' ;l% + *:., > n . , "; g c.
, q.., i. '., , s , 9,. 8DMINISTRATIVE PROCEDURES.'CONDITIDNS. AND LIMITATIDNS PAGE-74 ANSWERS -- MILLSTONE 2-89/07/29-PRELL, J.
, . ANSWER G.09 (1.50) 1. That no plant evolutions are planned which could change the radiological conditions in the area listed on the RWP.
[0.53 2. That HP will be notified whenever any plant evolution takes place that changes the radiological conditions in the area listed on the RWP.
C B. 5 3 3.
That the plant is not jeopardized by the work indicated on the RWP.
CO.53 REFERENCE 1.
SHP-4912, p-4 EO-14a K/A 194001K104 3.3/3.5 194001K104 ...(KA'S) ANSWER 8.10 (2.50) c.
CO.53 b.
CO.53 c.
2 hours CO.53 [e,/ A 8 # f'en Y c.
1.
SS Staii Asstatants Ofitce I; ' 2.
Hot Shutdown Panel Storage Box ! ?. 5; 3. Y**rn** l lntk W / f M JteYe 08 o Anw #g (5 /9; 4 /eral orrae N A) REFERENCE V Fthe toe J sh 1.
AOP2579A,B.C,D,...g p-3 2.
LP2579A D,C,D,...; p-7 EO-2 3.
TS 6.2.2 p 6-1, 6-4 - % /! W M.f $ f *) K/A 194001K116 3.5/4.2 194001k116 ...(KA'S)
r - - ' ....
, y ',. . ' ~ 3; y. ' v 4. :C y;,.
' ,. . , - ,
, (, ADMINISTRATIVE' PROCEDURES. CONDITIONS. AND LIMITA'f!ONS PAGE
ANSWERS -- MILLSTONE 2-88/07/20-PRELL, J.
, . ANSWER 8.11 (2.00) Provides assurance that these heaters can be energized during a loss of offsite power condition C1.03 in order to, maintain natural circulation g ^ ' " ^ * 3 ; ;~ ~ v 1 4;.2% es g=e jf,jf a, a! g fj ad . ten & l Ad.$ ps r/fyre [0.J] REFERENCE 1.
TS3.4.4.6, p - 3/4 4-4, B3/4 4-2 EO-18 (TS) 2.
LP-2304A, p - 49 EO-14 K/A 010000SG05 3.2/3.8 010000K201 3.0/3.4 010000K301 3.8/3.9 010000K603 3.2/3.6 010000K201 010000K301 010000K603 010000SG05 ...(KA'S) ANSWER 8.12 (1.50) c. Ensure the operability of HPSI pump "B" CO.53 b.
Ensure all systems / components are returned to an operable condition CO.53 and verify that the data on the Surveillance Data Sheet is in compliance with the acceptance criteria.
CO.53 REFERENCE 1.
nCV 9.02, p - 10.12 LQ -ft),?.- Ck-/,p2077' /?bonry ppep 2.
TS3.5.2a Y* h K/A 006000SG01 4.1/4.3 006000SG05 3.5/4.2 006000SG01 006000SG05 ...(KA'S)
.;..=- , _ _=.m._ - e, , , , . - .v. L ' a ' u.. %; w.. s.
..: e' .,. . . . . _ -
5.
ADMIPQ1IBAI15_f3Qfg&UBLS. CONDITIONS. AND' LIMITATIONS ~ PAGE
ANSWERS -- MILLSTONE 2-08/07/20-PRELL, J.
. . ANSWER 8.13 (1.00) The SCO should i,OT grant permission CO.503 because only liesnsed operators CO.253 or individuals in training under the direct supurvistoc of a Incensed operator can operate the controls 6'O.253.
REFERENCE 1. ACP-QA-6.Oi, p-9,10,11 EO-g-pf_,gA__fP.Aepx-A/t#Ar#-fa-d 2.
12CFR55.113 10CFR58.54(il 10CFR55.3 3.
IN08-20 K/A 1940a1A103 2.5/3.4 194001A103 ...(KA'S) ANSWER 8.14 (2.00) 1. All penetrations required to be closed during accident conditions are either a.
capable of being closed by an operable containment isolation valve system CO.53 b.
closed by manual valves, blind flanges or deactivated automatic valves secured in their closed positions.
CO.53 2.
the equipment hatch in closed and scaled C0.53 4.
tho airlock is operable (pursuant to TS 3.6.1.3) [0.53 REFERENCE 1.
TS, pt-2 2. LP2313, p-11,12 EO-13a M/A 000069A201 3.7/4.3 C00069A201 ...(KA'S)
..... _ , , ' ' EQUATION SHEET - , , f = ma v = s/t Cycle efficiency = Net Work (out) Energy (in) .
o = ag a = V,t + 1/2at
E = aC aa ( v, - v,)/t a KE = 1/2av V " t V.
+ at A = AN A,e*** PE = agh ua 8/t A = In 2/t /, 0.693/t = 1/2 w = vat 4E = 931oa (ti f, ) ( t, ) - t,3(eff) = ----------- . . . .
Q = aC,4T Q = a Ah (t + t,) gj, I = 1,e*8' h=UA&T h=UA(T,,, - T,,, ) - I = I*e,,, Pwr = W a
I = I ' 10 ' ' ' ' ' F = P,10
TVL = 1.3/u P = P,e HVL = 0.693/p SUR = 26.06/T T = 1.44 DT S/(1 - K,,,,) CR, = A e i SUR = 26 _o f f CR (1 - K,,,)g = CR II~K I g
eti n IB a M = 1/(1 - K,,,) CR,/CR, = T=(t */e) + ( t il - e )/A.,, e l M = (1 - K,,,),/(1 - K,,) , T= t */ (e - )) SDM = (1 - K,,,}/K,,, oK,,,/K,,, s' = 1 x 10 seconds (K,,,-1)/K,, p = =
0.1 seconds-*
- -(t /TK,,1 + lb/(1 + A.,,T))
A.,, = P = t(V/( 3 x 10' ' ) I d, g I,d, =
I = Na Id Id = g
n AT AT, - g i LMTD = --------- In AT,/67
R/hr = (0.5 Cp()/d (aeters) WATER PARAMETERS i 1 gal.
R/hr = 6 CE/d feet) 5.345 lba =
}.=3.78 liters MISCELLANEOUS CONV S!0NS -
= 7.48 al.
1 Curie = 3.7 x 10 s Density = 62.
Iby/ft' 1 kg = 2.21 lba - l D0nsity = 1 gn/cm i hp = 2.54 x 10,s aTU/hr ?oot of va ortsation = 970 stu/lba 1 Mw = 3.41 x 10 stu/hr NCat of fu ton = 144 Stu/lba 1 Stu = 778 ft-lbf 1 Ata = 14.7 psi = 29.9 ip. Hg 1 inch a 2.54 ca 1 ft. N,0 = 0.4335 lbf/in 'P= (9/5'C) + 32 'C = 5/9 ('P - 32 , RO Exas Answers (2)Pg48 i
_ _ _ _ _ - _ _ _ _ - - _ _ _ . .
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s > . , le assoas of 1stysse.71.,.hle a es aspilcele cg.4,V <p l Se letrate.4et aos 3s M E.
- $7 - p aessesualee asterts: e M.... les accident.
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- (A) The jaltfotles of any esteer pleet sheedom regulegd M.
See 30tFtte.73(aM2X8) f, , , , by the p!ast's Tectolomb%1ficettees.
W( 7.j - ) .,_ l'jf '% (8) Any thseletten from the M's Techalcel , ,.* m W itsceti m to M.54(a).
- < a f.
. , [-Q i iNl Asy event er esadittee spyrima hiep that reamits BBW" See 3etrete.73(aM2XII) 58.72(b)(1Xil)
- . g is the ee'efftles of the ses * $mmer pleet, teclaslag
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.f deiphot: 4-7.H ' - er m I.. enem u e. est d ay m.,ient. iL,
aparetleg and smargoesy psenetsres.
I I "'Unless reported as higher cleestricatiess ~ EPIP fore 4791-4 E (1.o. 4LPten. SAAWO. OenatIE-esqE. GenatIE-Tis new. 6 . DELIA-OME.,9ELIA-Ine) Page 2 of 34 { ,, 3, G~d I L'.2 7 B3
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===* Aegilment essenecE ' - t
Any asteret phonememme er other esternal condities that W See leEFMe.23(e)(2)(Ill) [.j
- i
.- A.1 54.72(bXIXill)
- y[$ 1emmelate pesos as acteel threat te see esseer of the aucwr . p' i pesar plant er sipiricantly hampers site persammel in
G,.2.: y , , the peresemence er deales namessary ne the safe aparettaa '
.{ : , Amy esset that resents er steeld home mited le SEGHE" See IAEFEBS.n(aM2Xiv) h'.
5s.72(hMIXiv)
Emergoesy care c elles spaces (ents) discheep less the .M d
~ ~.[' ".', e anecter ca neet system as a sweest er e enlld signal.
. +: L . ., ru r: g,y;,W N so.n(tXIXv) Any seems tant reelts in a anser less et emmegnesy seuMe" me camperemie ascrass.n
. . -., . meeeemmet capability, effelte resposee capstility, maapeleemmet.
P y y- - ]g ';:[;i M.
er commescaths capenlilty (e.g., sipiricast perth art: Inn w e et a system 'i* er ca trei a loewsw. assegency a ttricaties syst. re,. lees te e, ort tas ser V. J{r, - a-
, , $ ;'g er Offelte Antificetten spese).
esador ecclemet cemettless is 5" ~ met repertene (Sof. IP-$-403t) ' 7
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Amy most test p e.
actant snee c to sne esseer.f sne saw' See ne:suse.n(ex2Xe) se.72(mXIX,5) . . ~. h j ' g ... nuclear peep plant er slptfismatly W site t'* ,- pereommel $d the performannedt stualer, oncessary for the .. '..,., )o' safe aparetles of the nuclear pesar plant laclueleg y gtg.
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N o.1 54.72(b)(2)(lli)
Amy event er conditten that alene emeld hose prevented ECW" See 1eCF58.7)(eM2)(v) i,, g -
I M iete the felfillammt of the eefety ftenstles of structures and leCFete.7Me)(2)(vi) F , w. 1. 6 , - or systems that are needed to: Esemples of (S): jfg 1; (A) Shut ease the reacter and astetala it la a safe 1) thplammed less of att feet Poets * J: sketdemn condittee, Coellas that can met he restored * s
l sv c.; (B) asmoso reelemal heet, withle ene hour.
k.,.,., . i , (C) Castrol the reloeee of redleestles enterfel, or 2) thplammed lesa of h Cae45eg; 4 .-c, . (D) Mittgste the consegnances of an accidmet.
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A.1 $0.72(b)(1)(lv) (A) Amy alcheres redleectlwe reigene thet onceeds 2 times MLie-RS* , M ). he release
immediate (contieund) the appilcele r r asettees of the lletts ylffed of ro deactive esserlet le , le Appendia B. Tele II of 3ACFR Part 2e la aerostricted cancentretless sele, if ( . erees. = hen esorepad euer a ties period of een hear.
everaged ever a pe @ et j.. ;i. j (B) Any lipid effleest releens that escoeds 2 tiens the M heers, unsid amened S m (
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for.Il redlenecildes asempt tettles and dissolved mele [ N
emees,enen e oraged euer a glas period of ese hear.
See 30Ergge.73(eX2XellO and [[ i ' (ammedlete estificetless ende seder this pareyeph eine 3 strums.73( M: Mis).
< '. ~ j e settery the reselreemets of pareyephs (ext) med (bM2) l M , et sae.es3 et leCra, Port as).
j e . . t 6,40MDXI). The rolesse l l l ~ of vesseacties emeerlei la , j coneestsettees tele, if J.- ) euerups seer a parted of f Ii , v 24 heers, useld emesed SAS tiens, ' the limits speelfled ter once
i metertels le App. S. Te le II
er leCFR Part 20.
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EWNT MSC33Pf305 pegagE EEWWES. M . CATEGORY CRITERIA -- WITimant egenstr - , i .
c 5s.72(hx2)(el) 5.
salireed car seretlesmuchloriae.
see applic.ble Erle prece ,e.
Pidbile (centlemed) 6.
Beretlag caused by regolatory acties.
for additlemal actions.
Interest c.
Amy -led statemmes estlested te last an're thee # hours.
d.
Sorotleg (greater thee SS poseemt) caused by costgeset aalfeesttien last$ag more than 72 hours.
5ctodeled shutemmen for teetles, ent=a , or ECWa see Casperable 10Cf aSe.73 , e.
refeelleg espected te last esse then 72 hours Angstrement.
, dr and emefleend by IErg/rnaastm.
' " f.
As enwireemental candities ediless any be of gesoral 'g latesest (fish kill er emerupseets ahese aevuel envireemental sample aselpste het est==r==alog Tech. Specs., etc.)
d ' . l - _ - - , 50.72(b)(2)(vi) Any lecident lavetulag Ilceased estarlal (by predact.
ECW" 18CFR38.49)(a)(1) (3), and {
source, or special nuclear materiel) edbich may home (4) angetressats.
, caused er taurnetens to camme: - ) , Esposare of the uhele bog of any ladtvidual of
a.
25 anos '&r serv er ree8=eien* esposare of the ekte of the stole he$ of any hl of 154 Asen er more of radiatles; er espeense of foot, antles.
k . hands, er tereaves of any ladleidual of 375 Soms
g er a m of radlettee.
}
- Weless reported as higher classiflcatles EPIP Form 4701-4 (l.a. ALPten, taAve. DemaLIE-esE. DenALIE-Two new. 6
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CATEsteY CRITEa!A m ang71esent esteessCE
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A lose of one morting emelt er more of the sporetten g. p f ll .e, [' 4,L e; d . pielle (continess) of any facilities affected.
- g . Intern t c.
sammes se any peuporty le emesse of stas.ees.
./g r - , - , ,.;} E ~$ - . .;*- St.72(b)(2Mwl) e Asy facident,levolvies licensed motorial (by protet.
W 38CTR23.483(a)(3), (3), and (4) g ' J1 , eserce, er speciel noclear assertel) t4lch any home angetrements.
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caused er threatene to cause: ,
US i . . y.
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Esqueesse of tsee ehele W et any ledivlesel of ,,.y - . 5 arums er more of redlettens espeeses of the entle [ '
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of the eeele % of any ledtv66mel of 30 Amme or I' gjf , '% more of redletten; or esquesere of feet. aattles.
{ {'!;'- l, ,..- y..f. 4.. no.es. er f.r.a e of, lessela.ei.f 7s some > . or more of radletten.
ji 'g1 g ,
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A less of one day or esse of the aparetles of any ^u(< - > .- . F r s ...d '
factittles affected.
"x - s >n c.
semese to any peuporty la emmene of $2.888.
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CATEG0eV CRITERIA CM AADITasmas gasagnecr .:
8 v.
(,e ts samlefee 30 ser assert te m - h, 30 ser f LIa agTg: Tag aEquieES 30 ANT SEPWET 8t4Y AL50 aEquhat ' I , AE 38eESIATE MPGET IM 18CrtSG.72 (SEE A.1 AASW).
.f c.! (A) The CaWellen of any nuclear plast etesteam AAt See 3ACPEEs.72(hM1MI) for .gl M.7XaM2XI) .* ~ -
required by the plant's Teshetest Specificettems; '? Immediate amperties spirements a . er ' g (8) Asy sporetles or comeltlen puuhtbited by the RAL Kmle of (S): Mased ' 'N plant's Technical specifteettene; er sorwelliances ' (C) Any deviatlen from the pleet's Technical . specificassens eueherimed parement to 3acrate.M(x).
. 50.73(a)(2)(ll) Amy event, er seedittee that reentled in the candities of Ain see 1eCF354.72(bHI)(ll) er e , the nuclear pane plant, lacledleg its prlacipal safety 18CTR58.72(b)(2)(l) for l - herriers, teles'oerleusly doyeMd; er that resultad ./, Immediate Supertlag segelrements l la the aucMN plant M, LA' l ,* (A) la se a lyzed condities that sigolficantly ! comprM S M plant safety;, [ 2,* l
(S) Is's esNilen that was esb the deelyn bests , . .e sa.
of the, plast; er pg, - g . , (C) In a senditlea not covered By the pleet's T aperstleg ame emergency precedores.
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, u . 30 Say (centlemed) peces an arten1 throet to the serody of the ancieer . 3-ediate asporties mpleummets g,i A.C p a
a . . - *q T,., s LIR poser pient er significantly tagers site pereenmei le . .. - g; .% ..J-W 4.
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n . ,,
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3 act tw air se 157. Sect . tant reesised frne 3, 1 j;7 ' , .. N and uns part of the propi _, -- durlag testles er '
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~ ~ ' Mf Jf .. a. j. -y (i;t Amy esent er senditien that eteen ameld hees prevented EfA see 30 E M S.72(bH2)(Itt) ter - 50.73(a)(2)(v)
-y u. reirm et.r tne areer.einstsee.f.treet 3-adt.se n.orties s, ire-et.
a
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30 aar (centleund) 2 tiens the app 15 cable senemmeretiene of the lletts ".
. . Immeelete taportleg AngeGeensate ' 1 I.. ^. LD spectrieslaappenstes..yutteIIetsaanpart2ela
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i .: - - - <. .1 (B) Amy 189 4 efflueet rolesse that oneeed 2 tiens the
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. (i.e., eerestricted eres) Ser all renntemmcilens emcept ,.3"~ 'N trithe end else.1.e4 seek gases, emme reced **er . 'A ' e slee part.d er e near.
j.h. , -- /.15' if '
- aw n 50.73(a)(2)(Is)
asports estaltted to the Camelesten le accordance erith N/A See 3etrate.72(6 H2X iv) ter t
. f/f/ j Peregraph (AX2)(vill) eheve. Atee meet the erriment lesedlese emporties s,strements j.
f's* S, a i roiease @les rewireamste w seresreen as.ess(Axs>
u iM er 3etFE part,30.
E '
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.* 44,..M Asy seemt.M posed en acteel theast to the safety of Am A{ 5ee 18CFate.72(b)(1)(wl) for 50.73(a)(2)(a)
(.K".s.)
the esclerk plant ar elgstflematly keepered site N Immedlete emportles tegelrumeets 4, ~ persons.1'de. h, perfe easse. , the sete lee of the gemer pleet laclueleg . 32. ? ' see esco eery ter s . 3 . g - -- fires, roleseos, time rolesees.
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