ML20006B654
| ML20006B654 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/18/1990 |
| From: | Burdick T, Carrick S, Reidinger T, Shepard D Battelle Memorial Institute, PACIFIC NORTHWEST NATION |
| To: | |
| Shared Package | |
| ML20006B651 | List: |
| References | |
| 50-346-OL-89-02, 50-346-OL-89-2, NUDOCS 9002050177 | |
| Download: ML20006B654 (6) | |
Text
.. '
j U.S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-346/0L-89-02 Docket Nos. 50-346 License No. NPF-3 Licensee:
Davis Besse Toledo, Ohio j
Facility Name: Davis Besse Examination Administered At:
Davis Besse Examination Conducted: Replacement examinations for two reactor operators.and t
ten senior reactor operators.
Examiner:
/Tj[f fr e et,/ M
/8 O 5teve Carrick-fNL
(/
Date RIII Examiner (s):
2 jdt
- /[ld70 DouglaA Shepard Date l
/
(fj M /
-[/8/fC Chief Examiner: [8 U lleidingff Date l
L Approved By:
N
/ /8hD T. Burdick Da,te /
Examination Summary i
Examination administered on December 18-22, 1989 (Report No.- 50-346/0L-89-02)).
Consisted of written and operating replacement examinations administered to two reactor operators and ten senior reactor operators.
Results: All reactor operators and senior reactor operators passed'the examination.
2 l
4 9002050177 poot3g y
hDR ADOCK 05000346 l
PDC b
.o i
REPORT DETAILS 1.
Examiners i
- Timothy Reidinger, NRC Douglas Shepard, NRC 1
Steve Carrick, PNL
- Chief examiner 2.
Exit Meeting a.
On December 22, 1989, an exit meeting was held. The following personnel were present at this meeting:
Ted Myers Director Technial Services George Bradley Nuclear Licensing Richard Simpkins OPS - Nuclear Training Manager Paul Byron Senior Resident Thomas Simonetti OPS Training Supervisor Richard Brandt Operations Manager Mark Bezilla OPS Superintendent Jim Suyrowski Training Superintendent-b.
(1) One weakness was noted. The reactor eperators need a higher emphasis on Davis-Besse External Radiation Administrative Guides and Limits. The reactor operators had a 34% pass rate on R0 question 36 on category 6 " Plant Systems and Generic Responsibilities". The' question dealt with the Davis-Besse quarterly and annual radiation exposure. limits to the whole body.
(2) The following generic strengths were noted:
(A) Operators were very proficient and knowledgeable in administrative areas such as conduct of operations / surveillance testing,--logging / tagging clearance, key control and standing orders.
(B) Operators were very strong'in understanding and-implementing the requirement of the RWPs and the ALARA
- program, i
(C) Operators demonstrated a good proficiency in the l
understanding of control room systems, applying.
L technical specifications and administrative requirements for those selected systems.
~
(D) Operatort demonstrated good understanding in the implementation of the abnormal procedures, normal and emergency procedures.
2
(3) HRC Observation NRC recognizes and acknowledges the progress that Davis-Besse i
training staff has made in the draft development of abnormal procedures relating to Nuclear Instrument Failures for the Source Range Intermediate and Power Range Instruments.
b N
h I
i s
3' I
l NRC RESOLUTIONS + SRO EXAMINATION Question: 5.30 (1.00)
The following plant conditions exist:
Reactor power 68% steady RCS pressure 2100 psig decreasing slowly ALL PRZR heaters On 480 MCC E11D DE-ENERGIZED FOR MAINTENANCE PRZR Spray Valve RC 2 Indicates OPEN,:in manual, and.
held closed for 45 seconds PRZR PORV outlet temp.
108*F and steady RCS water inventory 0.15 'gpm RC PRZR PRESS RLF out temp 108"F and steady Which ONE of the following will most quickly decrease the pressure loss without an RPS actuation?
a.
Close RC-10 (spray line isolation) at Control Room Switch HIS-RC-1).
b.
Close RC-10 (spray line isolation) locally.
c.
Stop RCP 2-2 after reducing reactor power to less than 50%.
d.
Stop RCP 2-2 insnediately.
ANSWER: 5.30 (1.00) d.
RESPONSE: 5.30 l
The stated 480VAC MCC (E11D) is the incorrect' power supply for the initiating plant condictions. The correct MCC is EllA.
E11D was incorrectly identified by the Davis-Besse review team as the proper MCC to have RC-10 (spray line isolation )De-engerized.
As the question is currently worded, the E11D outage is merely a distractor and the correct response should be "a".
(Close RC-10 [ spray line isolation]
at Control Room Switch HIS-RC-10.)
1 Recommend accepting "a" as the correct answer instead of "d"_.
l NRC RESOLUTION: Question deleted.
+
9
,cv..
t t
i
^
QUESTION: 38 (1.00)
The following conditions exist:
i General Emergency declared Sunny and 40*F Wind 0.25 mph from 120 degrees Release has just started, duration is unknown Whole Body Dose Rate 3.9 Rem /hr at~1 mile.
Which ONE of the following would be the recommended protective actions per i
HS-EP-02245, " Protective Action Guidelines" attachment 4 for the range 0 - 2 miles?
(Assume today's date and time.)
a.
No action.
1 b.
Shelter as a minimum. Consider Evacuation. Evacuate unless constraints make it impractical.
c.
Evacuate if possible, otherwise Shelter, d.
Shelter.
NRC Resolution: Question deleted. The answer was inadvertently included l
with the reference material supplied to the candidates.
i l
2~
3 s
NRC RESOLUTION - R0 EXAMINATION Question 2.10 (1.5)
STATE THREE (3) specific methods (equipment / component lineups) available to the operator for core cooling _if an inadequate core cooling condition exists ANSWER: 2.10 (1.5)
(
1.
HPI/LPI 2.
Steam the S/G using MFW 3.
Steam the S/G using AFW 4.
LPI flow out the PORY Any three for [+0.5) each RESPONSE: 2.10 i
l Recommend accepting additional correct responses.
l l
1.
Core flood tanks emptying 2.
Natural circulation 3.
Feed and bleed l
The original review copy was marked up for revision during the pre-examination I
review, but the markup was missed during word processing.
i NRC Resolution:
Comment accepted.
l.
l l
H 1