IR 05000320/1987010
| ML20237F989 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/17/1987 |
| From: | Collins S, Keller R, Norris B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20237F964 | List: |
| References | |
| 50-320-87-10OL, NUDOCS 8708210639 | |
| Download: ML20237F989 (42) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION I OPERATOR LICENSING EXAMINATION REPORT
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i EXAMINATION REPORT NO.
87-10 (OL)
l FACILITY DOCKET NO.
50-320 l
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FACILITY LICENSE NO.
DPR-73 LICENSEE:
GPU Nuclear Corporation Post Office Box 480 l
Middletown, Pennsylvania 17057 l
FACILITY:
Three Mile Island Unit 2 EXAMINATION DATES:
July 14 - 16, 1987 l
l LHIEF EXAMINER:
.,a&C[
,
/ de f 7 Sarryg.Norris Date
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i Lead R6 actor Enginee xaminer)
l REVIEWED BY:
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I[M Robert M. Keller, Chief
~ Date Projects Section IC, DRP M[vhd _
hl/fd APPROVED BY:
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Sarffuel J. ColTins, Deputy Director
'Date Division of Reactor Projects SUMMARY:
Written and operating examinations were administered to four Senior Reactor Operator (SRO) candidates. All four SRO's passed the examinations and received licenses.
8708210639 B70817 PDR ADOCK 05000320 y
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DETAILS TYPE OF EXAMINATIONS:
Replacement EXAMINATION RESULTS:
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Written
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CHIEF EXAMINER AT SITE:
M. King (EG&G)
2.
The following is a generic deficiency noted from the-grading of written examinations.
This information is being provided to aid the licensee in upgrading license and requalification training programs.
No licensee response is required.
All Candidates were weak on the classification of hazardous waste as defined by PaDER; additionally, they were unable to. state what the minimum amount of fuel was that would constitute a reportable event to the Pa0ER.
3.
Personnel Present at Exit Interview:
NRC Contractor Personnel M. King (E9&G)
Facility Personnel C. Faust, TMI-2 Instructor 4.
Summary of comments made at exit interview:
The NRC reviewed the comments on the written exam and explained why some of those comments would not be accepted (See Attachment 2).
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Attachments:
1.
Written Examination and Answer Key (SRO)
2.
Facility Comments on Written Examination and NRC Resolution After Facility Review
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f; NUCLE 6R REGULATORY COMMISSION SENIOR ACTOR llPERATOR LICENSE EXAMINAT iN l
FACILITY:
_ T tj.1 - 2_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
l REACTOR TYPE:
_PWB;DW1ZZ______________
DATE ADMINISTERED: _8Z/92/ld_______.____
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EXAMINER:
_ KING, M.
o CANDIDATE:
Iqdzhf f kp __._______
ltJSIBUCIIOtG_IO_CGtLDIDGIE1 Use separate paper for the answers.
Write answers on one side only.
Staple question sheet on top of the answer sheets.
Points for each question are indicated in parentheses after the questi on.
The passing grade requires at least 70% in each category a n d. a f t i..a l grade of at
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least 80%.
Examination papers will be picked up six (6)
nours after the examination starts.
% OF CATEGORY
% OF CANDIDATE'S CATEGORY
__VGLUE_ _IQIGk
___SCOBE___
_yGLU E _ _ _._ _ _ _ _ _ _ _ _ _ _ _ _C GIE G O BL _ _ _ _ _ _ _ _ _ _ __
.?3. + 2-
_22199_
22 12
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__.______ 5.
THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS, AND THERMODYNAMICS 2 7.it?
_.22199__. _222.22
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PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION 23.c20
.23. 6.3
_23 2L__ _23.ji
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PROCEDURES - NORMAL, ADNORMAL, EMERGENCY AND RADIOLOGICAL CONTROL A $. Y6
_25_99__ _fah-fiz ___________
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ADMINISTRATIVE PRCCEDURES,
'78.20 ge CONDITIONS, AND LIMITATIONS
_2 21.h._ _
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Totals
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Final Grade All wori: done on this examination is my own.
I have neither given nor received aid, fg:
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Candidate's Signature fashi vcalaf {c>r ( f./O reakce/
h> %,00,osh, aboe vo /ues cA w y e d
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e NRC RilLES AND GUIDELINES FOR ! ? MNSE F.':AMINATIONS
During th3
.iinist ation of this examinntic the fw towing rules apply:
1.
Cheati n. on the examination means an aut<matic denial of your application l
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resul-in more severe penaltier i
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trips are to be limited and only one candidate at a time may j
2.
RestroomYou must avoid all contacts with anyone outside the examination
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leave.
room to avoid even the appearance or possibility of chetting.
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Use black ink or dark pencil only to facilitate legible reproductions, 4.
Print your name in the blank provided on the cover sheet of the examination.
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Fill in the date on the cover sheet of the examination (if necessary).
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6.
Use only the paper provided for answers.
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in the upper right-hand corner of the first page of each
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7.
Print your name J
section of the answer sheet.
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8.
Consecutively number each answer sheet, write "End of Category _" as j
appropriate, start each category on a new page, write only on one side l
of the paper, and write "Last Page" on the last answer sheet.
J 9.
Number each answer as to category and number, for example, 1.4, 6.3.
10. Skip at least three lines between each answer, j
Separate answer sheets from pad and place finished answer sheets face
down on your desk or table.
12. Use abbreviations only if they are commonly used in facility literature.
13. The point value for each question is indicated in parentheses after the question and can be used as a guide for the depth of answer required.
14. Show all calculations, methods, or assumptions used to obtain an answer
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to mathematical problems whether indicated in the question or not.
l 15. Partial credit may be given.
Therefore, ANSWER ALL PARTS OF THE
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QUESTION AtJD DO NOT LEAVE ANY ANSWER BLANK.
16. If parts of the examination are not clear as to intent, ask questions of Llw examiner only.
17. You must sign the statement on the cover sheet that indicates that the wor's 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.
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you -ball:
complete your exmoino t
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Ascomble yaur examination n:. 1ollows
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(1 Exam questions on top.
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(2)
Exam aids - figures, t a til e s, etc.
(3)
Answer pages including figures which are part of-the answer.
b.
Turn in your copy of the examination and all pages used to answer
the examination questions, j
Turn in all scrap paper and the balance of the paper that you did
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c.
-J not use for answering the questions.
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Leave the examination area, as defined by the exarainer.
If after leaving, you are icund in this area while the examination is still in progress, your license may be denied or revoked.
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THEQRL OF tJUCLE61s_LWUl_.yLANT_ d'ERATIO[L.
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E!d!LRs atiD_T.UKRL400Y:itu': CS.
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QUESTION 5.01 (3.00)
A variable speed centrifugal pump operating at 4000 rpm requires 200 horsepower to pump 500 gpn at 100 psig.
Suppose you change the pump speed such that discharge pressure is '/5 psig.
What is the new SPEED, FLOW, and POWER (Show all formulas and work.) ?
QUESTION 5.02 (3.00)
Select one advantage and one disadvantage for each type of pump below.
PUt'.P a.
positive displacement b.
.j e t c.
centrifugal ADVANTAGE DISADVANTAGE 1.
Operate in harsh environments.
1.
Low capacity.
2.
High flow rates.
2.
pump light fluids only.
3.
Metered flow.
3.
Additional piping required.
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QUESTION 5.03 (1.00)
Heat exchangers are designed to have turbulent flow. (choose the correct answer)
l a.
To increase heat transfer.
b.
To reduce tube fouling.
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To prevent water hammer.
I d.
To reduce tube vibration.
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CATEGORY 5 CONTI!4UED ON NEXT PACE *****)
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_ Tll.EQL;Y ( W ra DLEAR_L9WER PLAT 1T OFEBAT10N,.
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QUESTION 5.04 (3.00)
a. Explain how insufficient flow thru a ptimp can cause damage to the pump.
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b.
List a caethod of maintaining sufficient flow thru the pump when normal system flow is insufficient. [1.0]
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QUESTION 5.05 (2.00)
Explain why neutrons are best shielded by light materials and gammas are best shielded by heavy materials.
QUESTION 5.03 (2.00)
Two isotores of Nickel are placed on opposite sides of a balance scale.
Isotope A has a half life of 5 years, isotope B has a half-life of S000 years.
If each 1:sotope is exactly ONE CURIE cf radioactivity which way will the scale tilt (which isotope weighs more) ?
Explain your answer.
QUESTION 5.07 (1.00)
State the formula by which hydrogen is produced in a defueling canister.
QUESTION 5.08 (1.00)
List 2 core conditions that significantly reduce the possibility of a pyrophoric reaction taking place within the reator vessel
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CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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THEORY OF NEGM6F. * s :<.
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i OR :STION 5.09 (3.00)
Because of a misalignment of va.!ves a dilution of the RCS begins. The only indication to the operator is the following source range indications frem the logs.
Inspecting the readings yields:
Time 1200 1300 1400 1500 1600 1700 NI.1 1.25 J.25 1.62 1.92 4.46 8.33 a.
If the cause of the increase is not found when would (could) the
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reactor go critical. [1.5]
b.
If Keff of the core before the unplanned dilution was
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what was
Keff at 1600. [1.5]
l QUESTION 5.10 (2.00)
Isuring the recire mode of a process water storage tank, three tank volumes (approx. i.5 * 10E6 gal.) will recirculate in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The transfer pump capacity is only 275 gpm.
Explain how this recire (quantity) is accomplish-d.
QUESTION 5.11 (2.>0)
Explain which type of heat exchanger. parallel or counterblow, is more effective or efficient (Equations may be used in your answer) ?
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END OF CATEGORY 5 *****)
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PLA.LJI_STE,T :
-:SIGl-COJIBQImANI) JNSTLUM:h/i.
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QUESTION 6.01 1.00)
At what two J ouat i orn do the Chlorine detectio:, systent draw a sample ?
QUESTION 6.02 (2.00)
Tcch. Spec. 3.1 ra<1ai res dedicated equipment for reactor building sump recirculation. Explain how this system would be used 11 an event occured that required it. Include in your explanation the cuction scurce and the discharge point QUESTION 6.03 (2.00)
List 4 signals that will trip the reactor bui.1 ding purge supply fans DAMPERS.
QUESTION F.04 (2.00)
Explain the change in the flow path of the Containment purge exhaust system; caused by the receipt of a high radiatiori signal. Include in your answer what radiation signals (instruments) would cause this action, QUESTION S.05 (2.00)
Assume both Service air (SA) and Instrument air (IA) compressors are available.
a. Explain the effects of a large leak in the SA header.
b. Explain the effects of a large leak in the IA header.
QUESTION 6.06 (2.00)
In the event of a need, can if unit I and unit 2 1A can be cross-connected? If yes explain how, If no explain why.
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PL6: - SYSTEMS DESIGN. U@Xna
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.jiWENTATION age
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ESTIUi:
6.07 (1.50)
Identi.fy six areas by name whj ah are monitored by area gamma inun1t, ors.
QUESTION 6.08 (3.50)
Cnncerning the END EFFEPTOR HANDLING TOOL What design feature protects the hydraulic hoses from damage or a.
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entangling (O.b)?
b.
Why is the handling tool water filled (3 reasons) (3.0)?
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QUESTION 6.09 (2.00)
What two design features prevent radiation streaming through the work
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platform of the Shielded Work Platform?
QUESTION 6.10 (1.00)
What methods (2) are used to decontaminate water in the EPICOR Il system ?
QUESTION 6.11 (1.50)
For the following EPICOR valves list the fail position:
a.
ALC-V-43, Inlet Isolation b.
ALC-V-242, Off-spec tank outlet isolation.
c.
ALC-V-255, Inlet isolation to prefilter.
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QUESTION 6.12 (1.60)
List two places (locations) where the incore thermocourales may be read for unit 2.
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CATEGORY 6 CONTINUED ON NEXT PAGE **44*)
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EL ANT SYSTEE Li:.. l '
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QUESTION 6.13 ( 3. 4
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The f ollowing questions ret'er to the fire protection systems (s) for the air intake tunnel.
a.
The Halon syst.em is divided into what four areas of protectic,7 b.
What 2 signals will initiate the fire protection system (s)?
What will occur if the actuation signals are received?
c.
(Discuss only the primary actions, do not include auxiliary functions
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of fans and dampers.)
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QUESTION 6.14 (2.00)
Draw a one line diagram of the filtration /recire portion of the DWCG.
Include instrumentation and remotely operated valves.
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,c0CEin+ES - NORMAL, nBSo n.M.. m r.
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Qui >? ION
.01 (1.00)
Why must loaded canisters be removed from the vessel through the canister removal port?
QUESTION 7 02 (2.00)
Explain why knockout canisters are loaded only at the 324' 11'
elevation AND fuel canisters are loaded only at the 321'
0'
or 317'
0" leve] ?
i QUESTION 7.03 (2.00)
a.
During def uelirig operations who (position title) is required to make the required notifications prior to canister transfer to the fuel I
handling building?
I b.
List 3 of the individuals (position title) required to be notified prior to canister transfer per OPS MEMO 2-86-01.
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I QUES"1Dtl 7.04 (.1.00)
What is required if a load to be lifted by the crane over the reactor
vessel exceeds 2400 lbs?
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CATEGORY 7 CONTINUED ON NEXT PAGE *'****)
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EROCEDURES 7 id
.. ABIL LMAL. EMERGENC'i Page 11
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'AN_D_RADIOLO9IC % < >pTBOL
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QUESTION 7.05 ( 3. :o )
For each of the following identify (Yes or No) which require independent verification for component, lineup.
Include in your answer how (where) the
. verification is documented A locked closed valve is opened by procedure.
a.
b.
A locked open valve is closed by procedure.
c.
The Emerg. Diesel Generator is started for a test run.
I d.
The Emerg. Diesel Generator is secured from a test run.
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e.
Opening a containment integrity valve.
f.
Closing a containment integrity valve.
g.
Opening SNS-V-20 for a sample.
h. Closing SNS-V-20 after a sample.
QUESTION 7.06 (3.00)
I What are 4 of the classification used for hazardous waste as defined byll a.
PaDER. (1.0)
b.
What is the ' reportable quantity" of a fuel oi] spill occurring
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inside the AUX Building? (1.0)
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Under what conditions is a spill of any amount of a hazardous waste substance reportable to PaDER
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(1.0)
QUESTION 7.07 (2.00)
j List 4 places decontaminated water from the clean water receiving tank
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(CC-T-2) may be transferred. Include in your answer the prc;cedure (name or number) you would follow to transfer the water.
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.h / _.J I RE E _ JigBS AL A BN U hMb b,__ r.! ?i n s f J
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QUESTlim 7.00 (1.00)
Choose the correct answers from the list s provided:
Prior to EPICOR startup the ventilation system is adjusted for
___a___ CFM air flow and a CCB pressure of b
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a.1 4000 b.1 Slightly positive
.2 8000
.2 Atmospheric
.3 12000
.3 S1ichtly negative
.4 16000
.4 1 PSID dp l
i QUESTION 7.09 (2.00)
l How and where is the CCB sump normally emptied?
QUESTION 7.10 (2.00)
Explain the use of two specific types of operational taa's utilized in plant operations to designate or identify facility limitations.
(4*** NOTE: NOT personnel safety protection tags *44*)
i QUESTION 7.11 (1.00'
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l What is the required T.S.
ection if a Chlorine detection system is declared inoperable?
QUESTION 7.12 (2.00)
F.i re doors installed in exterior fire wa]]s are not subject to the one i
hour roving fire watch when determined to be inoperable.
Explain the basis for this exemption.
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l QUESTION 7.13 (1.00)
I What is defined as CORE ALTERATION by the TMI-2 Tech. Specs?
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evtl.INI STR ATIVE_PROQ;ijan j u@l;
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e'4D LIMITATIONS
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QUEL. ION 8.01 (2.00)
While starting a Nuclear River Water pump, the pump trips.
What required
information is to be included in the WRA (or control room log) per the l
OPS MEMO, P.-86-04?
j QUESTION 8.02 (0.50)
I Do the TMI-2 Tech. Specs allow dewatering, if in progress, to be continued if the FHB ventilation system becomes inoperable?
QUESTION 8.03 (1.00)
a.
What is tlse minimum number of source range instruments required to be opcr8ble to continue with fuel removal activities?[0.5]
b.
What is the minimum number of intermediate range instruments required to be operable to continue with fuel removal activities?[0.5]
QUESTION 8.04 (2.00)
Explain the Tech. Spec. bases for the minimum and maximum boron concentration required by Tech. Specs. (4360 - 6000).
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CATEGORY 8 CON ~)NUED ON NEXT PAGE *****)
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dOCE; 3 E _QgN_DIT10Nda, Fage 14 8.
ALMitilbildbT 2
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QUESTION 8 05 (3.00)
For eacn of the following systems, identify which are currently (Recovery mode) covered (i.e.
not deleted) by TMI-2 Tech. Specs.
(NOTE. Answers may be limited to YES or NO, Tech. Spec. numbers are not required)
a.
Flood protection
i b.
Mini decay heat removal system.
c.
Nuclear service river water system.
i d.
Emerg. Diesel Generator.
e.
Containment purge exhaust system.
f Essential Parameters monitoring instruments.
J-j QUESTION 8.06 (2.00)
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Rhat action (s) per the TMI Tech. Specs. are required if an LCO and it's i
action statement cannot be satisfied'?
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QUESTION 8.07 (2.00)
a.
If a conflict occurs between a NPDES permit' requirement and an NRC nuclear plant operations requirement, which regulation supersedes?(1.0)
b.
Where is this information stated (found)? (1.0)
QUESTION 8.08 f2.00)
What are the major differences between a TCN and a TCN-2?
s QUESTION 8.09 (2.50)
List five documents that should be reviewed during the course of the shift per procedure 4210-ADM-5020.01, Conduct of Plant Operations.
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CATEGORY 8 CONTINUED ON NEXT PAGE
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QUEaJ10N
,.10 (2.00)
Explain the following terms as they apply to a UNI.
I a.
00 witness point [1.0]
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b WC Hold Point [1.0]
QUESTION 8.11 (2.00)
The cancellation date of a TCN shall not exceed ___a___ from the date of the __..__b QUESTION 8.12 (2.00)
Assume you are the shift foreman.
A UWI-WRA requires a revision.
Under what provisions may you allow work to continue?
l QUESTION 8.13 (2.00)
a.
What is required by procedure 4000-ADM-3240.01, Access to and Work in l
the Containment Bldg, to remove equipment from the containment (1.0]?
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b.
Who's (position title) approval is required [1.0]?
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(********** END OF EXAMINATION **********)
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b THEQBX OF tWiiLEAR iM' W NT__E SATIGLL
.ge'16 s
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FillIDS u6tlR_THESMOI)YN AM! "
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AN: NER 5.01 (3.00)
(E = exponent,
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proportional)
SPEED N-E2
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head
[0.33 for formula]
100/'/b
[0.33 for mat.h]
{
(4000-E2)/(x-E2)
=
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x-E2 : (4000-E2)(75)/100 l
x: 3464 rpm (3400 -- 3470)
[0.33-for answer]
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FLOW N ~ flow
[0.33 for formula]
<.
e 4000/3464 : 600/x f,
1.154: 500/x
[0.33 for math]
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x: 433.27 gpm (430 -- 435)
[0. 33 f or answel-]
POWER
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N-E3 ~ power
[0.33 for formula]
(
(4000-E3)/(34o4-E3)
200/x
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1.539,: 200/x
[0. 33 f or niath]'
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x: 129 HP (125 -- 135)
[0.33 for answer]
i REFERENCE
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TMI-2 Lesson Plan tib2, 11.2.01.114, pg 44-46 j
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ANSWER 5.02 (3.00)
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a.
1
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I b.
3-l c.
2 (6 @ 0.5 ea.)
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THM1 id _
JCLE6: 10WER ELJali'LO)MBA'i it u.,.
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REFERENCE
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TMI-2 #5L, 11.2.0:1.114, pg 14, 23-25, 39 l
ANSWER 5.03 (1.00)
a REFERENCE TMI-2 Lesson Plan #48, 11.2.01.047, pg 16-17
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J ANSWER 5.04 (3.00)
a. Heat is added to the fluid in the pump due to " pump work'.
11 the flow is insufficient to remove this heat then cavitation may result and cause damage to the pump components. Pump components
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(such as seals) may be damaged by heat / temp alone.[2.01 b. A recirc line t.o allow minimum required flow.[1.0]
REFERENCE TMI-2 NET 4~6, Pumps and Fluid Flow Dynamics ANSWER b.05 (2.00)
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Neutrons have no electrical charge and lose / reduce their energy by collisions.
Maximum energy is lost with collisions with small/ light atoms. [1.0)
Gammas have neither mass or electrical charge and lose / reduce their energy thru gamma interactions with matter This requires a high l
density / heavy material to maximize the samma interactions with the
'
shield. [1.0)
,
l REFERENCE TMJ-2 NET 2-7, pg 7.4-1
,
(
.
(*****
CATEGORY 5 CONTINUED ON NEXT PAGE *****)
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_.... _ _ - - - - - - _ _ - - - - _ - _ _ _ - - - -
TBri :Y( OE_lilCLEAR POWERE. ?!
XlE Ju ragt
-
'ELp: Uddt1D_TE RMQDYNAM19.S
-
.
ANSWER 5.06 (2.00)
"B" side will tilt down or the "B" isotope weighs more. (1.0)
A curie of any material is based on a given number of disintegrations per second. The isotope with the longer half-life (isotope B) would require a large amount of material to produce the required DPS and would therefore weigh more. (1 0)
REFERENCE TMJ-2, RADIATION UNITS, GUIDES AND LIMITS, NET b-2, l'G 2.1 - 3 ANSWER b.07 (1.00)
radiation
+ O2 (4 @ 0.25 ea.)
l 2 H2O ------ ---- ---> 2H2 REFERENCE l
i
!
TMI-2 LICENSE CLASE HANDOUT I
ANSWER 5.08 (1.00)
a.
Most of the material is already oxidized
!
b.
Core under water (cooled)
c.
Most mhter)al is > SO microns d.
Pyrophoric taaterials diluted with non pyrophoric mater.lais.
(2 @ 0.5 ea.)
REFERENCE
<
TMI-2 LICENSE CLASS HANDOUT i
l
.
f (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
i t
-__ _.
_
_
','..S.
/IBK01<Y f 6; uuCLE6,): _EOWER _Ph6ET,__REERanolk Page 16 F1,U I den. :' TL{Elp^^.)XNAMI.QS
.
.
AtJSWER b.09 (3.00)
j a.
[0.75 for 1/m plot,] [0.75 for answer]
' ' * '
1. 1.25/1.62 :.771 (1400)-
\\
2. 1.25/1.92
.651.(1500)
\\
3. 1.25/4.46 :.280 (1600)
4. 1.25/8.33 :.144 (1700)
\\
a3
N a. CRITICALITY AT 1800 s
(1730 -- 1830)
as a.5 0.4
\\
\\
\\
o.2 g
\\
y
\\
o.o.
15
\\
21 b.
crl/cr2 : (1-k2)/(1-k1)
[ 0. 5 f cir f ormula] -
1.25/4.46 : (1-k2)/(1.7)
'
.280 (.3) = 1-k2
[0.5 for math]
.084: 1-k2 1.084 : k2
.916 : k2 (.91 --.92)
[0.5 for answer]
REFERENCE l
TMI-2 NET 3-12, pg 12.2-1 - 12.2-3 I
l
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_. -
_
_ _ _ - - _
_
_ - - -
OPN 7 PION;.
~1 s 20
'
5.
4.10EQBX OF B]LgLEAE__lg.ijm c;
-
-
._ ljJJLAUD._'[HERMODXN AM3 CS
-
.,
,
.
ANSkER 5.10 (2.00)
The transfer pump supplies TWO SOBMERGED EDUCTORS in the PW storage tank.
The eductors raise the INTERNAL recire flow to 1100 gpm.
REFERENCE TMT.-2 LESSON PLAN 12.2.01.124, PROCESS WATER STORAGE AND RECYCLE, PG 110 ANSWER 5.11 (2.00)
Assume remaining design features are equal for both heat exchangers.
Counterblow Parallel 21b F
+--------------+ 125 F 215 F
+------ -------+ 125 F
_______);
- _________>
_______);
- _________>
l l
l l
60 F l
l 90 F 90 F l
l 60 F
______.j;
- _________)
<_______;
- <-________
,______________4
+.__-__-_-_____4 TA : 215 - 60 165
[0.25]
TA : 215 - 90 = 125 [0'.25]
'
TB = 125 - 90 =
[0.25]
TB = 125 - 60 :
65 [0.25]
Using the above calculated TA & TB for each HX in the formulae:
dT = (TA - TBi/(Jn(TA-TB)) ( mean log dT) it is shown that counterblow HX has a higher dT and therefore is more efficient (effective) (assuming equal size HXs). [1.0]
REFERENCE TMI-2 LESSON PLAN 11.2.01.047, HX FUND., PG 21, REV. 3 I
.
(*****
END OF CATEGORY 5 *****)
-
_ _ _ _ _ _ _ _ - -
_ _ _ _ _. _ _ _ _.
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,
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p_.
PLivNT SYbfr.a
, 1IGN
- )HBQLgh.tJD -1?;SThuftly.b i
. hee 21
.
o,
.
'
.
ANSWER 6.ul
.00)
!
1. Air intake t.unnel. to.5)
i 2. Control room air duct. (0.5)
REFERENCE
{
TMI-2 T.S 3.3.3.7 ANSWER 6.02 (2.00)
a.
Suction source is the reactor building sump.
b. Discharge point is IIF via flex hose connected to discharge of pump (s)
i RF'FERENCE TMI-2 T.S.
3.1 ANSWER 6.03 (2.00)
a. Fire in the air intske tunnel.
b.
Fire in the reactor building.
c. High radiation in purge exhaust duct. (HP-R 225, HP-R-226)
'
{
d. Figh radiation in station. vent. (HP-R-219)
L e. Purge recire. damper not closed.
,
f.
Discharge damper not full open.
i l
g. High pressure in the reactor building i
h.
Supply damper not full open.
(4 @ 0.5 ea.)
!
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l
.th._
J
. f Si; ;iMS DESIGNdt@lBOL.
- ..is TRW f.J.i )N
'
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l l
REFEiGG,CE
'
2 LEt UN PLAN, Rx. BLDG. VENTli. 710N IA PURGE SYSTEM, 12.2.01.i:
..
,
I'.
6, REV 1 i
,
ANSWER 6.04 (2.00)
i Upon high radiation in its respective DISCHARGE DUCT or STATION VENT the discharge dampers close and th; recire. dampers open.
(NOTE: HP-R-225, HP-R-22G are discharge duct, rad, instruments and HP-R-219 is the station vent rad. instrument.)
REFERENCE TMI-2 LESSON PLAN, Rx. BLDG. VENTILATION AND PURGE SYSTEM, 12.2.0:.G45, ANSWER 6.05 (2.00)
to isolate S/ i a.
When SA pressure f alls to '/0 psig valve SA-V358 will shut from IA[U.33]. The SA header will continue to depressurice [0.33]
SA 6l IA compressors in standby or auto will start.[0.33]
U
.c ha -/.5 b.
If the leak is in IA header, valve SA-V358 4= -im-np m.to direct the discharge of all compressors to the IA header [0.33] in an attempt to keep the vital air cystem in service [0.33]. SA & IA compressors in standby or auto will start [0.33].
REFERENCE TMI-2 INST. & SERVICE A1R, 12.2.01.048, PG 15, REV 1
,
I l
I ANGWER 6.06 (2.00)
NO. the cross-connect has been cut & capped. (This line now used to supply air to EPICOR II)
l
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i
.J
e 6.
,[% ANT SYSPEtai.A
& Ct., TROLuAND INSTRUMNW.W ; of-Page 23
,;
.
REFERENCE
TMI-2 INST. & Gi. J ICE Ai:
12-.2.01.048, PG 16, RL
ANSWER 6.07 (1.50)
a.1 Control Room
.2 Cable Room
.3 R.B.
Emergency Cooling Booster Pump area
.4 R.C Evap Control Panel Area
.5 Make-up Tank Area
.6 Intermediate Cooling Pump Area
.7 Waste Disposal Storage Area
.8 Aux Bldg Sump Tank Filter Room
.9 Aux Bldg Access Corr. (1)
Aux b1dg Access Corr. (2)
Control & Service Bldg Corr
.12 Reactor Blds Purge unit Area
.13 Aux Bldg Exhaust Unit Area
.14 Fuel Handling Bldg Exhaust Unit Area
,
'
.15 End fitting storage area criticality monitors
. 16 FHB A & B pool area rad. mon.
.17 Ion exchanger area rad. mon.
.18 Shielded work platform area rad. man.
(6 @ 0.25 ea.)
REFERENCE TM1-2 LESSON PLAN, RADIATION MONITORING, 12.2.01.070, PG 6, REV O ANSWER 6.08 (3.50)
a.
The hoses are inside the (3") tool segments. (0.5)
b.
Prevent radiation streaming. [1.0]
2.
Make the tool more stable when in use. {1.0]
3.
Make the tool lighter (when out of the water) [1.0]
REFERENCE TMI-2 Lesson Plan #29, 12.2.01.145, pg 6.0
.
(*****
CATEGORY 6 CONTINUED ON NEXT PAGE *****)
_ __ __
. _ _ _.
~, ft ___Ztar a.STEb _ iLESIGN. CONTROLuhE._ ;:.3
_ jiEtB e
. 0 11
.c a --
.
.
.
.
l ANSWER d.09 (2.00)
1.
The plates (3" SS shielding plates) are placed with the joints over " webs' (I-beam) when possible [1.0].
2.
Joints, not over webs, are ' stepped" [1.0J.
REFERENCE TMI-2 Lesson Plan #30, 12.2.01.147, pg 14
,
!
ANSWER 6.10 (1.00)
a.
Filtration (Accept ' rou ghi n tt" )
b.
Ion exchange (Accept " polishing")
REFERENCE TMI-2 LESSON PLAN 12.2.01.023, EPICOR 11, PG b, REV O ANSWER 6.11 (1.50)
a.
as-is.
I b.
closed.
f
!
I c.
closed.
l
i REFERENCE TMI-2 LESSON PLAN 12.2.01.023. EPICOR II. PG 23, REV O
i l
ANSWER 6.12 (1.60)
a.
cable room b.
Mimic panel (Main Control room)
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r><-
6.
6NT SlfiTEMS DESIGus. M?
Ali NSTRUMELLIbL oN
,
.
,
REFEhWNCE
- 11-2 NET
'/-2, INSTRUt4ENT! J ON SYt JEMS, PART 2 l
l ANSWER 6.13 (3.00)
a.1 vertical shaft
area below veriical shaft (sump)
tunnel north of divider
.4 tunnel south of divider
[4 @ 0.25 ea.]
b.
Ultra-violet detectors detecting a flame front (Flame detectors)[0.5]
or a rat.e of pressure rise device [0.b]
c.
The explosive diaphragms are triggered which releases the Halon [0.5]
and the activation of any Halon system triggers all tunnel deluge systems (0.5]
REFERENCE Tt4I-2 OP 2106-6.1, FIRE PROTECTION SYSTEM, REV 16, PG 16 i
)
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.,
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.a
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ANSWER t i.14 (2.00)
- - - -..
. - - - - - -
..
.
/3 r--l Turb.l IV f
je
/2.
To I1 F T
n W ->C'
'
Y F
F a &
L l5 j&:
From o
.--J
!
JIF
Suction from IIF (Rx Vesse.1)
9.
d/p insk 2.
Orfice line 10.
System Branch 3.
Pump
Flow inst 4.
Level inst 12. Isol valve
=
)
5.
Pressure inst 13. Turbidity inst 6.
Inlet isol 14. Return to IIF (Rx Vessel)
'/. Inlet to filters 15. Filter (1)
8.
Outlet from. filters 16. Filter (2)
I (10 @ 0.125 ea.)
REFERENCE TMJ-2 LESSON PLAN DWCS SYSTEM, SYSTEM OP PROC 12.2.01.148
,
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l
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l i t_._,f n u n td.?. -
N Oi.. L,.'ABNORMAhmEMEh ;&U r>a gy x.
-
-
AND BADi,JOICA!, MONIBOL
.
,
.
ANSWER i 01-( )
10 )
The canister removal port is designed with extra radiation shie3 ding specifically for canister-removal.[1.0]
REFERENCE TMI-2 Lesson Plan 1835, 12.2.01.156, pg 6 ANSWER 7.02 (2.00)
1.
The connections to the vacuum system are only at the 324' 11'
elevation. Knockout canisters must be connected to the vacuum system [1.0].
2.
Fuel canisters are loaded at the 321' and 317' elevations due to shielding reasons [1.0).
REFERENCE TMI-2 Lesson Plan #36, 12.2.01.156, pg 7 ANSWER 7.03 (2.00)
a.
FHSRO b.1 On-shift group Rad Con Supervisor
.2 Unit 1 Shift, Sui >ervisor
.3 The Security Sergeant
. 4 Rad waste operations fereman
.5 Special Nuclear Materials Coordinator (S @ 0.5 ea.)
REFERENCE TMI OPS MEMO 2-86-01 ANSWER 7.04 (1.00)
A docketed Safety Evaluation approved by the NRC. (1.0)
.
(*****
CATEGORY 7 CONTINUED ON NEXT PAGE *****)
. _ _ _ - _ _ _ _ - _
_ _ _ _
. _ _ _ _ _ _ -
EMin ":NCY Pm
i UO3]E]LUfiES - NOME I,1% >r -
<
'
hH _BbMDbDGIChk.GQBTynb
-
.
.
REFERENCE TM;-2 T.S.
3.10.1 ANSWER 7.05 (3.20)
a. YES, Signntura on procedure'OR Jock valve book b. YES,' Signature on procedure OR lock valve book c.
NO d.
NO e. YES, Signature on procedure (Accept record in control room Ic>g)
f. YES, Signature on procedure (Accept record' in control room log)
!
g.
NO b. YES, Signature on procedure (Accept record in control room log)
(8 0 0.4 ea.)
REFERENCE THI-2 OPS MEMO 2-84-17 ANSWER 7.06 (3,00)
a.1 Hasardous (H)
.2 Toxic (T)
.3 Ignitable (1)
.4 Corrosive (C)
.5 Reactive (R)
.6 Toxicity (E/EP)
(4 @ 0.25 ea.)
b.
10 gallons, (fuel oil is class
'I",
ignitable)(1.0)
c. Any spill ( af a huardous material) to a surface or ground water source. ( 1. ;i )
,
(*****
CATEGORY 7 CONTINUED ON NEXT PAGE *****)
.,
,
7, PROA DURES -
t, }
t..
Al, OkMAL&_EMiihqEhEf Face as l
+
_
ANfLRADlMNGIC/J @!E8pb
-
)
,
.
REFERENCE
]
TMI-2 GPUNC ENV! ONMENTi,, CONTROL, 11. 2. 01. 3 ti8,. i 8, RE',
l l
ANSWER 7.07 (2.00)
l a.
Unit 2 liquid waste disposal sys.
l
)
l b.
Truck fill station i
l
,
f c.
Spenc fuel rtorage pool.
d.
PWST
receiving tank f or f urther processing. (c(- F /)
l e.
Off-spec f.
Reactor coolant bleed tanks.
g.
Condensate test tanks (Evaps)
h.
BWST (8 @ 0.25 ea.)
(NOTE: CAF for proc. references)
REFERENCE TMI-2 LESSON PLAN 12.2.01.023, EPICOR II, PG 4, REV O
.
ANSWER 7.08 (1.00)
l f
a.
2 (8000)
b.
3 (Slightly negative)
J REFERENCE TMI-2 LESSON PLAN 12.2.01.023, EPICOR II, PG 11, REV U i
ANSWER 7.09 (2.00)
By EPICOR pump ALC-P-1, sending sump contents througi) tite EPICOR process string.
-
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.
i l
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L.
Lbf EMBEE.
NOBM & _ABNObdA_Lu._K x 9
. an.
'
Atr SDLQ[,niIQAL CONTROh
-
.
.
REFEREW j
TMi. LESSV PLAN 12.2.01.023, EPICOF I,
PG
>s, REV O AN3WER 7.10 (2.00)
a.
CAUTION TAGS ('Ye])ow Card) are to used to attach to a component, control switch or other device to indicate an off normal canoition or to caution the operator to a specific condition which must be satisfied prior to using the component
>r device.[1.0]
b.
OUT-OF-SERVICE (Yellow Sticker) to be used to identify a component,
'
control switch, or equipment that has been declared 003 due to a
'
malfunction, testing or repair work.L1.0]
REFERENCE TM1-2 UNIT FACILITIES STATUE TAGGING PROCEDURE, 4000-ADM-3020.06 PG 3, 4, &. 5 ANSWER 7.11 (1.00)
Within one hour operate the control room emergency ventilation system in the recirc. mode. (1,0)
i REFERENCE l
TM1-2 T.S.
3.3.3.7 ANSWER 7.12 (2.00)
Only fire doors required for separation of safe shutdown re. lated areas are required and subject to the one hour roving fire watch.
REFERENCE TMI OPS MEMO 2-87-02
.
(4**** CATEGORY 7 CONTINUED 014 NEXT PAGE *** * * )
>
..... -....
.
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..... _ _ _
f L..._.P_EOCEDURES - tJORt1&Lt._eltyu 'j E _.,?RGEtigy age 31
-
A_tJQ_ RADIOLOGICAL cot 1TROI
+
.
.
i AIEdER 7.13 (1,00)
CORE ALTERATION shall be the movement or manipulation of any reactor
component (including fuel)[0.33] within the reactor pressure vesse1[0.33]
j vith the vessel head removed and fuel in the vessel.[0.33]
l REFEREt1CE
1 TMi-2 T.S. DEFINITION 1.15
1
.
i j
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I I
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L_________________
_ _ _ _ _ _ _. _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.
_ _ _ _
y Pad:e 32 l
8mMliflllinIh!1I' _ _fBQ.Vr AMhEfL_ fC.'iD1ILOLE
-
.
Mip_IdtjlTAT INS
- -
i
l
=
i l
At1SWER 8.01 (2.00:
.1. Component / system conditions at time of trip.
j 2.
Identify ALL relay " targets" tripped.
REFERENCE TMI OPS MEMO 2-86-04
)
>
ANSWER 8.02 (0.50)
No (Dewatering is considered movement. of radioactive liquid). (0.5)
j
}
I REFERENCE I
l THI-2 T.S.
3.9.12.1 & 3.9.12.2, AND OPS MEMO 2-85-18 l
ANSWER 8.03 (1.00)
l a.
1 [0.5]
b.
0 [0.5)
REFERENCE TMI-2 T..S.
3.3.1 ANSWER 8.04 (2.00)
The minimum (4350) to ensure reactor remains shut down under all expected conditions, the maximum (6000) is to prevent precipitation of boron which could cause flow restrictions.
REFERENCE TMI-2 T.S. 3.1.1 2.C (BASES PG B3/4 1-1)
(***** CATEGORY 8 CONTINUED ON NEXT PAGE *****)
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.._,. AMy N ISTRATI VE PROCEDUIE...
J' - 0 TIO:,.,.
Page
bFr; 910373.TJgg
i t
.
- ANSWER 8.05 (3.00)
a.
YES (3.7.6)
l
b.
NO (3.7.33)
!
i I
c. NO (3.7.3.1)
d. NO (3.8.1.1.B)
l e.
YES (3.6.3)
f YES (3.3.3.5)
(6 w 0..S ea.)
REFEREt4CE TMI-2 T.S.
(IDENTIFIED IN ANSWER)
i i
ANSWER 8.06 (2.00)
In the event a Limiting Condition Or operation and/or associat,e6 ACTION l
requirements cannot be satisfied because of circumstances in excess of l
those addressed in the specification, initiate appropriate act4ons to rectify the problem [.5] to the extent possible under the ci retaslances,[. S]
and take all other actions necessary to maintain the unit in a stabla condition [.5] and submit required reports to NRC.[.5]
REFERENCE l
l TM1-2 T.S.
LOO 3.0.3 l
i l
ANSWER 8.07 (2.00i I
/
a.
NRC regulat, ions [ 1.
0 ]
b. TMI-2 NPDES permit. 11.2.01.28/l, (pg 11) (Other answer, with references will be acceptable). [1.0]
(*****
CATEGORY 8 CONTINUED ON NEXT PAGE **4**)
I L
. _ _ _ _ - _ _ _ _ _ _
...
_EERUr J !ESS_130HI21I19dem P6 @ 34 R.,._MMLN CnIB6r i
'
AND LIMJTAT 4: >
'
.
.
REFERENCE TM1 -2 LESSui'. l'L AN, NiDES PERMIT, 21.2.01.284, N 11, i:lV ?
!
ANSWER e.00 (2.00)
procedure (and a TCN-2 may not)[1 O] and A TUN may chnnge the intent of a
has to complete the full review, concurrence and approval requirements prior to. implementation [0.S]. A TCN-2 requires fewer (usually 4) signatures prior to ituplementution and han 14 days to complete review and approval requi remer:ts[ 0. b ).
REFERENCE TMI-2 Admin proc 4000-ADM-3000.01 pg 12 ANSWER 8.03 (2.60)
a.
Active taJging book b.
Locked valve book c.
Gurvea11ance schedules d.
TCN book e.
i.OP book f
Operations men >o book g.
Revision Review Book (b e D.5 ea.)
REFERENCE TMJ-2 Admin proc 4210-ADM-3020.01, pr 4 l
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CATEGORY 8 CONTINUED OH NEXT PAGE *****)
l
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_ _ _ _ _ _ _ _ _
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AIM R uiIRATIVE P80CEDURES _.W;9'
. IOrE age.
,
-
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!
.
.
f ANSWER 8.10 (2.00)
a.
UC Witness Points may be intentionally deleted, by passed, or inserted at the option of.1.he QC Supervisor..
Activities may continue provided QC was notifled of the time t.o witness and is not present at the start time [1.0].
b QC Ilold Points may not be by-passed or deleted without documented just,1fication and the approval of the QC Manager The QC Inspector's signature on the UW1 indicates satisfactory completion of the specific step (s) that the Hold Point addressen and permits the activity to proceed {1.0].
p (Answers need not be verbatim per above.)
REFERENCE TM1-2 Admin proa. 4000-ADM-3000.01, pg 1C-37 ANSWER 6.11 (2.00)
a.
90 days b.
Responsible Supervisors signoff I
REFERENCE TMI-2 Admin proc. 4000-ADM-3000.01, pg 16
.
ANSWER 8.12 (2.00)
s a
l Work not affected by the revision may continue [0.5] provided the planning group indicates to the work supervisor [0.5] the portions of the UWI that may and may not be worked [0.5) and the work or steps deferred as a result of the revision is/are clearly not a prerequisite or sequence dependent to the continued work or steps [0.5].
j REFERENCE l
TMI-2 Admin proc. 4000-ADM-3000.01, pg 19-20
,
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)
ANP L1MlIAT100F
l
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!
ANSWER 8.13 (Z uo)
i a.
A containment transfer record is required to be comp]eted [1 0].
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Radwaste enttineer approval (Accept Shift Supervisor, Fuel Handling Shift, Supervisor, Rad Con Engineer or Radwast9 engineer)(1.01
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REFERENCE
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I TMI-2 Admin proe 4 00 0 - AI)M-3 2 4 0. 01, pg 3.0
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(***** END OF CATEGORY 8 *****)
(********** END OF EXAMINATION **********)
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Resolution to Facility comments cn
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TMI 2 3RO exam of 7/14/87 Comment on Question / Answer 6.03 i
Additional answers that may be given are-High pressure in reactor building, reference lesson plan 12.1.01.045 step C.1.c.f4) page 6
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Note that the station <ent monitor is HP-R-219 Note that radiation purge exhaust duct monitors are HP-R-225 and 226.
Note that as per reference 12.1.01.045 page 5.0 Tee leads are i
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lifted to supply fan mutors but all interlocks still functional i
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with regard tc. fan -lampers.
The supply fans are not operational.
Resolution P a r.m.e n t accepted, High pressure in the reactor building added to answer key Instrument designation added to answer key.
Question reworded to clarify fan dampers interlocks vice fan motors interlocks.
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Ccmmerit on Quest:.on/ Answer 6. 04 I
'lo t e that HP-R-219 is the nation vent monitor and HP-R-225 and 22G
are disenarge dumt radiaticn mar.itors that may be stated in answers, i
2es c 1...t ion t
Or ant ac, pted, instrument duc.ignatiens add-to answer sey.
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l Co:r. ment :n Question'An w.r 6.07:
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A idi r i anal area gamma mcnitcrs that may be con.sidered in unit II ara:
End fitt ir.g storage area criticality mcr.itore vr T.S.
4.3-4a.
Fuel Har.dling building A & B pool area radiati, n monitors. Ion exchanger area radiation monitor CN-RIT-:XO3 per 4215-CPS-3527.03
page 1.c.0.
Shield +d u:>rk pla t f or:
'0WP) radietion area monitor per 4200-OFS-
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Recclution l
Comme r_ t accepted, listed gamma mor.tiors added tc answer key I
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i Comment en Questian/ Answer 6.10:
Not-that 6.10 a.&b. may also be referren to as roughing and J
polaching per 4215-OP3-3526.01 (same meaning different words)
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Comment accepted, per supplied reference, roughing and polishing
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are normal TMI-2 terras and are acceptable.
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Comment on Question / Answer 6.12:
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Note that the balance of plant computer is out of service and not
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to be restored to service.
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Resolution Comment accepted, question changed to two locations vice three. Plant i
computer deleted frem answer key.
Pcint value spr-tad between j
remaining two anawers.
Total point calae remain the came.
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Comnent on Questicn/Answ or 6.13 :
Note that 6.13 a.O answer can be referr=d to a.s sump are a which is commonly how it is done.
Note that 6.10 b answer of
.5 paid is a rate of prescure rice device.
Resolution
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Comment accepted,
' sump' :,0ceptable as ' area belcw intake shaft" l
Ancwer 6.13.b changed to ' rate cf pressure rise device"
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Comment en Question / Answer 8 14:
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l Note that IIF and Reactar ceccel are can e paints.
l Note that I provided ycu with a drawing t, hat
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exchanger portion of the DWC2 system and your question only asked for the f L1tratiarm/recire pc rtion.
Also note that remotely aperated valves are ti-air operated valve symbole. indicated on my haad drawingc.
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nesolut on Ccmment acceted. IIF or Rea:ter es.sel acceptable, answer key modified. Remaining comment noted, no change required.
Comment or. Quer t 1..r./ Anawer 7. 0 3 :
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Note that the opa memo alco hn: the :.hift superviscr/ foreman insure J
the calls were made, l
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Comment not accepted, OPS memu and TMI-2 proc:dures clearly state j
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it is the FHSRO's responsibility to make the required notifications.
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Comment on Question /Ancwer 7.05:
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Note that the emergency diesels are not Tech. Spec. items. (ops memo needc to be revised).
See attached referenced memo 2-84-1" e.
should be yes g.
should be no Resolution
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Comment accepted, answer
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changed to " NO ', reflecting change in i
diesels generator Tech Spec status, Answer "e"
& "g" changed per
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comment ud referenced memo.
l Comment un Question / Answer 7.00:
This questien referc tc fuel oil as being considered a Hazardous waste under ster 8.4.1 page 43 per attached 1501-PLN-4500.01.
Per the PPC plan 011 is considered under step 8.4.2 page 44 of this same reference, which talks of deportability if the oil enters the yard drainage system or reaches the river regardless of quantity.
If the oil ic centained from reaching the yard drainage system, which in this
case it is, no report need he made per the PPC plan.
But according to
4210-EAP-4500.01 (OIL CP! LLC) emergency procedure, and our 4000 - ADM -30 00. 01 (incident / event reports) GPU nuclear requires a repor+ to be made at 50 gallons er more.
Resciutica l
Cummer.t n,t immpted, q u e s t i:.n does
.at refer tc 1501-PLN-4500.01.
GP L'N': Zreironmental Cantrol, 11.2.01.288 rev dated 2/18/87
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is listed as question reference.
Reading the references included with the comment and the criginal references does nct clarify hcw fuel oil thould be co..sidered as a hasardous waste.
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were n c, t inclu kd to determine that fuel oil chould not be considered
- i as an ' i g r i t a b '. e ' hacard.
No change t: answer hey.
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I Comment on G wst cn/An wer 7.07 La additicnal a:.swer shculd include the f ollc wing:
RCE" (Feactor coolant bleed tankt)
WDL T-9A or 9B (conden. tate tast tanks)
EW3T fBorated water stcrage tank)
References identifying these ar.
4215-OPS-3526.11, 4215-OP3-3526.10,
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3.,., y_.. _. _.
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,o Ncte that we d o r. ' t r.crmally memorize procedure number or titles.
Resoluticn Comment accepted, Listed tank; and procedures added to answer key In reply to last comment,- a verbatim procedure title is not required, however an operator should be familiar with a procedute name (or number) to identify the procedural method he would use
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Comment on Question / Answer 7.10:
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Note that Do Not Operate tags (DNO) are not used any more.
See reference 4000-ADM-3020.06.
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Resolution l
Comment accepted, Question changed to
'two'
tags vice "three",
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"DNO" section of answer key deleted.
Question point value reduced to 2.0 from 3.0.
Conanent on Question / Answer 8.11:
Note the respor.sible supervisors sign off is commonly referred to as
l the date of implementation.
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Resolution
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" late of implementation acceptable as ' responsible
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l supervisors sign off"
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