ML20006B654

Exam Rept 50-346/OL-89-02 on 891218-22.Exam Results:All Reactor & Senior Reactor Operators Passed Exam

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: ML20006B654
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 5teve Carrick-fNL fr e et,/ M /8 O

(/ Date .

RIII Examiner (s): 2 jdt - /[ld70 DouglaA Shepard Date l

Chief Examiner: [8 / (fj M / -[/8/fC U lleidingff Date l L Approved By:

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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.

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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

L understanding of control room systems, applying.

technical specifications and administrative requirements for those selected systems.

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(D) Operatort demonstrated good understanding in the implementation of the abnormal procedures, normal and  ;

emergency procedures.

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(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.  ;

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.*- 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.) ,

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Recommend accepting "a" as the correct answer instead of "d"_.

l NRC RESOLUTION: Question deleted.

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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.

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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.

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l 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.

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