ML17328A583
| ML17328A583 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/12/1990 |
| From: | Burdick T, Damon D, Shembarger K, Shepard D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17328A582 | List: |
| References | |
| 50-315-OL-90-01, 50-315-OL-90-1, NUDOCS 9002260272 | |
| Download: ML17328A583 (13) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-315/OL-90-OL Docket Hos. 50-315; 50-316 Licensee:
Indiana Michigan Power Company 1 Riverside Plaza
D.
C.
Cook Examination Administered At:
Bridgeman, Michigan Examination Conducted:
january 29 - February 2, (990 RIII Examiners:
K.
Chief Examiner:
em arger epard Date f~
>u Date i%o D.
i amon 1
Approved By:
ur sc,
>e, 2
Date Date Examination Summar Examination administered on Januar 29 - Februar 2
199G (Re ort No. 50-315/ o s x endor eactor perator candidates t ree reta es an four Reactor Operator candidates (two retakes).
Resu.its:
One reactor operator candidate and one Senior Reactor Operator canaooate failed the examinations.
All other candidates passed the examinations.
9002260272 9002i2 PDR ADOCK 050003l5 V
PNU
REPORT DETAILS l.
Examiners
- D. Damon K. Shembarger D. Shepard
- Chief Examiner 2.
~EI 1I ti On February 2, 1990, the examination team met with members of the faci lity staff to discuss the examination process.
The following persons attended the meeting:
A. A. Blind, Plant Hanager, IHP K. Baker, Assistant Plant f/anager, IHP J.
R. Sampson, Operations Superintendent, IHP H. F. Runser, Operations Production Supervisor, IHP W. R. Burgess, Simulator Supervisor, IHP J. Stubblefield, Program Administrator, IHP S. J. Wolf, Senior gA Auditor, AEPSC B. L. Jorgensen, Senior Resident Inspector, NRC T. Burdick, OLS Section Chief, NRC D. Damon, Chief Examiner, NRC K. Shembarger,
- Examiner, NRC D. Shepard,
- Examiner, NRC The examiners detailed the following comments:
Weaknesses SRO's were weak in Technical Specification application during the simulator examinations.
Some immediate actions in procedures were not performed correctly or were incompletely performed during the simulator examinations.
Weaknesses were noted in candidate knowledge of 10 CFR 20 limits and requirements.
General Comments Progress in cleanup of contaminated areas in the plant is good.
The facility is urged to continue it's efforts.
Interface between the exam team and members of the security staff and radiation protection staff was extremely smooth.
Procedure 4022.012.004 (Dropped Rod Recovery) leaves the control rod system in an abnormal configuration if the recovery was unsuccessful.
The facility has agreed to review the procedure for possible changes.
ENCLOSURE 2
Faci lit Comments and NRC Resolution QUESTION:
(SRO ONLY) 007 (2.00)
State the THREE actions to be performed by the Site Emergency Coordinator during a Site Area Emergency that may NOT be delegated.
ANSNER:
007 (2.00) 1.
Classification [of emergency] [0.5]
2.
Directing the notification [0.5] of offsite officials [0.5]
3.
Making protective action recommendations
[0.5]
REFERENCE:
1 of 4 1940 01A116
.(KA's)
COMMENT:
Request that "directing notifications" be acceptable for full credit for answer 2.
The portion, "of offsite 'officials," is inferred by directing notifications.
Note, offsite notification of protective action recommendations is also inferred for answer 3 but is not required for full credit.
NRC Resolution:
Comment accepted.
Answer key modified.
QUESTION:
(RO/SRO) 025 (1.00)
The plant is in Mode 6 and you are dispatched to the Containment to join a 2 man work crew of operators inspecting the No.
11 RCP.
Which ONE of the following are you required to contact for authority to enter the containment:
a.
Shift Supervisor b.
Work Crew Member
'S ~ z'.w>> nnna Wn '
n'nijnn ~'n
~ i',: n
~"C ~net
.-' n~ i
~
~ i~ n'<<w nate
~ nann
~, ; nn'c i l> ~r n' i V ii'n'
~n.
~
w n" w.,
,il < t,
~
c.
Security Captain d.
Unit Supervisor ANSNER:
025 (1.00) b.
[1.0]
REFERENCE'HI4010, p2-3 194001K 105 COl Il1ENT:
..(KA s)
The question as stated implies that authorization is required prior to entry
(.
. contact for authority to enter the containment).
The question is actually testing the candidate's knowledge of proper application of the two man rule for containment access.
We are requesting that either answer 3, "Unit Supervisor" or answer b.
"Work Crew Member" be accepted for full credit.
NRC Resolution:
Comment partially accepted.
question deleted.
QUESTION:
(RO/SRO) 035 (1.00)
LIST the TWO interlocks/permissives which must be satisfied to start a Reactor Coolant Pump.
Include setpoints where applicable.
ANSWER:
035 (1.00) 1.
Lift oil pressure
[0.25], greater than or equal to 510 psig [0.25].
2.
Oil lift pump motor starter switch [0.25] must be ON [0.25].
REFERENCE:
RO-C-NS2P, pg.
13.
003000K113
.(KA's)
COMMENT:
Request that a
+
10% be applied to setpoint or a statement that "white light is lit" be acceptable for full credit to keyed answer No.
1.
Request that "oil lift pump is running" be acceptable for full credit as answer to keyed answer No. 2.
REFERENCE:
2-OHP 4021.002.003 Section
- 6. l. 11 which states:
"Start oi 1 lift pump at least two minutes before starting RCP.
Observe pressure permissive interlock clears."
NRC RESOLUTION:
Comment not accepted.
A range of acceptable answers is standard for values that must be calculated.
A well defined setpoint is allowed no tolerance.
Since the question was testing the candidate's knowledge of interlock requirements, and not the indications used to verify that interlocks are met, "white light lit" is not accepted for credit.
Since the interlock stated in answer No.
2 is clearly dependent on switch
- position, answer key remains unchanged.
QUESTION:
(RO/SRO) 037 (1.00)
Which ONE of the following is the basis for opening the Reactor Trip Breakers and/or the IIG set Output Breakers when cooling down the plant with all shutdown and control rods inserted:
a.
Prevents inadvertent rod withdrawal.
b.
Minimizes stationary coil wear.
c.
Prevents damage to the flux ring in the CRDN.
d.
Prevents mechanical binding of the rods.
ANSWER:
037 (1.00) d
[1.00j
>r
~'>: "4
>r > ~ r >r ~ : v
~ >>r>
~ > r ". "}, s,
> ~ > >>
~ >> e>>. c'.>>.
>~,'r>>%
~
. ', ~ 'r
~ '
~ ', ~ >> >r v >'
> "l
~ eLrjv >
~ D
~ >~'4
>> e.
~ >'
'>2>'
~:
REFERENCE:
OHP 4021.001.004 Paragraph 6.1 COMMENT'Key Points" in referenced procedure states:
Prevents mechanical binding of rods during cooldown, prevents rod control system from being capable of rod withdrawal with startup STP's not current.
Request that answer (a) "prevents inadvertent rod withdrawal or answer (d)
"prevents mechanical bihding of rods" be accepted for full crecHt.
NRC Resolution:
Comment partially accepted.
guestion deleted.
QUESTION:
(RO/SRO) 041 (3.00)
Match the Control Rod System function/purpose in COLUMN A with its associated controlling component(s) in COLUMN B.
COLUMN A functions/purposes may have more than one answer.
COLUMN B choices may be used more than once or not at all [0.5 each].
COLUMN A COLUMN B
a.
Provides input into the Rod Insertion Limit Circuits.
l.
Auctioneered Hi Tavg 2.
Auctioneered Hi delta T
b.
Provides input into the AUTO Rod Speed Circuits.
3.
Group Position Indication [step counters]
c.
Controls rod withdrawal and insertion sequence.,
4.
Individual Rod Position Indication.
5.
Pulse to Analog Converter 6.
Auctioneered Hi Reactor Power
~ ',
1
-4 ~ 1
~ '
4
'14 ~
4 41 1
~
~
1 J
- '1~ 1 ~ 8 4 1 1
i '4
'111 j '
7.
Turbine Impulse Pressure 8.
Bank Overlap Unit 9.
Master Cycler 10.
S lave Cyc 1ers ANSWER:
041 (3.00) a.
2.
[0.5],
b.
1.
[0.5],
c'8.'O'.5]'.
[0.5]
6.
[0.5]
[0.5]
REFERENCE:
10.
001000K403 COMMENT:
..(KA's)
Request COLUMN A question (c) "Controls rod withdrawal and insertion sequence" to include COLUMN B answer 9, "Master Cycler."
Reference RO-C-NS04, pg.
12 of 25 C.2 which states:
Master Cycler - Receives pulses from pulser and applies "GO" pulses to 4 slave cyclers to ensure groups w/i a bank move properly.
Receives input from bank overlap unit to tell it which bank to move.
Master C cler then sends "GO" ulses to correct slave c clers to move t e rou s se uentsa s reverss e so t at rou ss t e ast to receive out
, st w~
e erst to et sn
'RC RESOLUTION:
Comment not accepted.
The Bank Overlap Unit is the controlling device that determines which slave cyclers receive a signal from the master cycler.
The master cycler itself does not determine which slave cycler receives a signal.
The Bank Overlap Unit also biases multiplexor thyr ister networks in the power
- cabinets, thus determining which group receives a signal from the slave cycler.
Thus, the Bank Overlap Unit (only) and not the master cycler controls the rod withdrawal and insertion sequence.
Answer key remains unchanged.
~<ay ~
<< "s4
~ Aw 'v>sw<'
w'
',tt> a,,',P'
'~a i>'<'
P
'Owl'ANv) ~ '< '
f
%L g'a, s R ~ A 1",'
N,', 'y~ 'e "CR ; ~'
'w N I,O>, l: s C)
~UESTION:
(RO/SRO) 062 (1.00) l<hich ONE of the following describes actions to be taken for a malfunction of ONE source range channel during a refueling outage (per 1-OHP 4022.013.001, Source Range lialfunctiorc):
a.
Containment Integrity must be maintained until the inoperable source range channel is returned to service.
b.
All operations that could add negative reactivity to the core must be suspended until the channel is returned to service.
c.
Refueling operations must be suspended unti 1 the remaining source range channel is verified to be functioning properly.
d.
The audio count circuit must be verified operable and selected to the operable source range channel.
ANSNER:
062 (1.00)
'1.0]
REFERENCE:
1-OHP 4022.013.001, pg 2 of 2 COt MENT:
Distractor (c) refueling operations must be suspended...
is a modification of a subsequent action to make it false.
Answer (d) is subsequent action 3 of this procedure.
Immediate manual action 2 (4.2.2) states "If refueling is in progress stop all core alterations or positive reactivity changes.
This statement is very similar to keyed answer (c).
Candidates are only responsible for immediate automatic and manual actions.
Request deletion of question as answer(c) is misleading and very similar to required immediate manual action.
NRC Resolution:
Facility agrees that distractor (c) is false.
Comment noted.
Answer key remains unchanged.
()UESTION:
(RO/SRO) 063 (1.00) l<hich ONE of the following statements is MOST accurate concerning the basis for transferring to hot leg recirculation:
A transfer from cold leg recirculation to hot leg recirculation is performed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a large break LOCA event because...
a....
Cold leg recirculation only fills the downcomer region, and no flushing of the core occurs.
b.
hot leg recirculation is a more effective means of providing boric acid to the core.
c.
heat transfer from the fuel to the reactor coolant is improved during hot leg recirculation, since in this mode, cooler water enters the core.
d.
cold leg recirculation allows for boron precipitation on the control rods, which reduces the rod worth and resultant shutdown margin.
ANSWER:
063 (1. 00) a ~
REFERENCE:
COliNENT:
The keyed answer states that "cold leg recirculation only fills the downcomer
..for large breaks the downcomer level is low and injection flow is primarily refilling the downcomer as opposed to the core, and no flushing of the core occurs."
Therefore answer (a) as written is not accurate and therefore is a distractor, not an answer.
Request that the question be deleted from examination.
HRC RESOLUTION:
Comment accepted.
guestion deleted.
()NEST(ON:
(RO/SRO) 081 (1.00) 10
Pressurizer Power Relief Valve tPORV],
NRV 151, is leaking while in Node l.
The leakage is stopped by closing its associated block valve, NYiO 151, and operation in Node 1 continues.
Which ONE of the following is the basis for continued operation in Rode 1 under this condition:
a.
The PORY's are not required by Technical Specifications.
b.
Closing the block valve prevents further damage to NRV 151 valve seat.
c.
NRV 151 is not required for overpressure protection in Mode l.
d.
The remaining two unisolated PORV's provide the required overpressure protection in llode l.
ANSNER:
081 (1.00) c.
E1.03
REFERENCE:
COl1MENT:
The question does not reference a procedure or document for basis.
Therefore the candidate is forced to choose from only true statements:
1)
Answer (a) is true for the reason stated.in answer (c).
2)
Answer (b) is true because closing the clock valve will prevent further leakage past the PORV.
3)
Answer (d) is correct because this is the basis for FR-H. 1 step 16.
"if at least two PZR PORV's are not maintained
- open, the RCS may not depressur ize sufficiently to permit adequate feed of subcooled SI flow to remove core decay heat.
Request that answers (a) or (c) or (d) be accepted as correct for full credit.
NRC RESOLUTION:
Comment partially accepted.
guestion deleted.
The facility should note that the original question does reference a procedure, 2-OHP 4022.002.009, page l.
The facility is cautioned to provide a complete submittal for comments per ES-201,, Enclosure 4, Paragraph 3.
QUESTION:
(RO/SRO) 088 (1.50)
Fill in the blanks:
[Each blank may require more than one word]
[0.5 each].
the limitation on the specific activity of the RCS ensures that the resul ting
[time] doses at the site boundary will not exceed an pp phd i
fP10Diiit fii ig accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of ANSWER:
088
( 1. 50) l.
2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
[0.5]
2.
[0.5]
3.
1.0 gpm [0 5 REFERENCE'echnical Specification basis for T.S.
3/4.4.8 000076G004 COMMENT:
The basis for limitations on the specific activity in the RCS is:
1)
Viinimize dose at the site boundary.
2)
Following an SGTR.
3)
In conjunction with primary to secondary steam generator leakage.
The question as written requires the candidate to memorize specific details about the basis that does not enhance their knowledge/understanding of the actual basis.
For this reason we request that the question be deleted from the examination.
It should also be noted that this topic 000076G004 has an importance factor of 2.1 for RO's.
NRC Resolution:
guestion deleted from RO exam.
SRO exam remains unchanged, since the KA importance for the SRO question is 3.7.
12
SIMULATIOH FACILITY REPORT Facility Licensee:
D.
C.
Cook Facility Licensee Docket No. 50-315; 50-316 Operating Tests Administered At:
Bridgeman, MI During the conduct of the simulator portion of the operating tests, the following items were observed:
ITEM DESCRIPTIOH 1.
Modeling during LOCA allows steam generator pressure to decrease, thus preventing exit to procedure ECA-l. 1.
2.
Yalue on intermediate range nuclear instrument fai lure is incorrectly ranged.