ML21098A171
| ML21098A171 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/04/2021 |
| From: | Greg Werner Operations Branch IV |
| To: | Energy Northwest |
| References | |
| 50-397/21-02 50-397/OL-21 | |
| Download: ML21098A171 (8) | |
Text
THE ENCLOSED EXAMINATION MATERIALS SHALL BE WITHHELD FROM PUBLIC DISCLOSURE UNTIL AFTER THE EXAMINATIONS ARE COMPLETE.
GO2-21-045 ENERGY NORTHWEST Regional Administrator U.S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Michael W. Davis Columbia Generating Station P.O. Box 968, MD 1028 Richland, WA 99352-0968 Ph. 509.377.4281 IF. 509.377.8662 mwdavis@energy-northwest.com
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 SUBMITTAL OF WRITTEN EXAMINATION RESULTS
Dear Sir or Madam:
Enclosed are the exam cover sheets, answer sheets, and exam evaluation data for the Reactor Operator (RO) and Senior Reactor Operator (SRO) license written examinations given on March 4, 2021, at Columbia Generating Station. Specifically, the following materials are enclosed:
- 1. Graded written examination answer sheet for each applicant
- 2. Clean written examination answer sheet for each applicant
- 3. Completed written examination cover sheet for each applicant
- 4. Master answer key annotated to indicate any changes made while administering and grading the written examination
- 5. Questions asked by applicants and the answers given to the applicants during the written examination
- 6. The results of performance analysis that was performed for the written examination
- 7. The written examination seating chart
- 8. Completed Form ES-403-1, Written Examination Grading Quality Checklist
- 9. Original Forms ES-201-3, Examination Security Agreement, with a pre-and post-examination signature for every individual who had detailed knowledge of any part of the operating test or written examination No new regulatory commitments are made in this letter.
If you require additional information, please contact CJ Prost, Manager, Operations Training, at (509) 377-4487.
Respectfully,
~~
Michael W. Davis Manager, Training Enclosures as stated cc:
w/o enclosures NRC Branch Chief, Operations Branch NRC Senior Resident Inspector-988C
Question: R0-19 Pass Rate: 9.1%
Evaluation of Questions With a Pass Rate < 50%
Evaluation: Applicants did not understand that FP-P-1 will automatically start on a loss of control power when SH-5 is deenergized. Some candidates did not realize that FP-P-2A loses power and will not start.
Action: This is a weak area that will be covered in gap training.
Question: R0-41 Pass Rate: 45.5%
Evaluation: Applicants did not know that Narrow Range RPV level is not density compensated.
Action: This is a weak area that will be covered in gap training.
Question: SR0-89 Pass Rate: 42.9%
Evaluation: Some applicants did not understand that, for the temperature given, electrolyte level is not the parameter of concern. Additionally, some applicants did not know the reason for restoring battery room temperature above the limit.
Action: This is a weak area that will be covered in gap training.
Question: R0-92 Pass Rate: 42.9%
Evaluation: Some candidates did not know that the given wetwell level was above the SRVTPLL for any given RPV pressure.
Action: This is a weak area that will be covered in gap training.
2021 CGS NRC Written Exam Facility/Applicant Comments If the question is answered using the valve noun names only, then B is correct. If the question is answered using the valve numbers only, then C is the correct answer. However, since there is no correct answer for the valve number and nomenclature together, as listed in the question stem, the facility recommends deleting the question from the exam.
2021 CGS NRC Written Exam Facility/Applicant Comments Applicant Comment (55-75376): ROA-V-2 listed in the system description as closing on an inboard isolation signal.
Applicant Comment (55-42919): Valve noun names not correct for the valve numbers given.
Facility Evaluation/Response: The facility concurs that the valve noun names do not match the valve numbers as listed in the question stem. System Description SD000183, RB HVAC, lists ROA-V-1 as the REACTOR BLDG EXHAUST OUTBOARD ISOLATION and ROA-V-2 as the REACTOR BLDG EXHAUST INBOARD ISOLATION.
COLUMBIA SYSTEMS RBHVAC t) RRA-FN-15 g) RRA-FN-17 January 2020 SD000183, r12 mr2 ANALYZER ROOM A EMERG COOLING FAN with SUPPLY DAMPER ROA-AD-15 ANALYZER ROOM B EMERG COOLING FAN with SUPPLY DAMPER ROA-AD-17
- 2. RRA-FN-19 and 20 FPC EQUIP ROOM EMERG COOLING FANS three position control switch, OFF/AUTO/ON, spring return to AUTO OFF AUTO ON De-energizes fan Fan auto starts on:
F, A, or Z signal or Loss of Nonnal and Startup power (for FN-20 as sensed by bkrs Sl-1 and Nl-1 open, and DG 1-7 or B7 closed, FN-19 is similar)
Fan starts
- 3. FPC EQUIP ROOM SUPPLY/EXH DAMPERS ROA-AD-19/REA-AD-8 three position switch CLOSE/AUTO/OPEN, spring return to AUTO CLOSE AUTO OPEN Closes damper Damper auto closes on F, A, or Z signal.
Damper opens if no F, A, or Z signal
- 4. ROA-V-1 (2) REACTOR BLDG SUPPLY OUTBOARD (INBOARD)
ISOLATION three position switch CLOSE/AUTO/OPEN, spring return to AUTO
2021 CGS NRC Written Exam Facility/Applicant Comments Questions/Comments During Exam Review Question: RO-18 CGS is in Mode 1.
An event causes the following readings on the Reactor Building Exhaust Plenum Radiation Monitors:
REA-RIS-609A: 11 mr/hr, steady REA-RIS-609B: 11 mr/hr, steady REA-RIS-609C: 14 mr/hr, steady REA-RIS 609D: Downscale The CRS enters PPM 5.3.1, Secondary Containment Control.
With respect to Reactor Building Ventilation, what should the operator verify?
In accordance with PPM 5.3.1, verify ROA-V-1, Reactor Building Supply Inboard Isolation, is (1), and ROA-V-2, Reactor Building Supply Outboard Isolation, is~.
A. (1) closed (2) closed B. (1) closed (2) open C. (1) open (2) closed D. (1) open (2) open Answer:
B
2021 CGS NRC Written Exam Facility/Applicant Comments Explanation:
A. Incorrect. Plausible since ROA-V-1 will be closed. However, ROA-V-2 will remain open B. Correct. REA-RIS-609C & D will provide a close signal to the RB HVAC inboard isolation valves when both monitors are > Hi-Hi level (13 mr/hr), Downscale, or a combination of either condition.
C. Incorrect. Plausible if it is believed that REA-RIS-609C & D operate the outboard valves.
However, these monitors provide input to the inboard valves.
D. Incorrect. Plausible since ROA-V-2 will be open. Plausibility is enhanced if it is believed that a monitor downscale will not provide a close signal. However, for the conditions given, ROA-V-1 will close.
Tier 1 Discussion: This question requires knowledge of the expected system response while performing step SC-1 of EOP PPM 5.2.1, Secondary Containment Control.
Technical Reference(s)
SD000147, Process Radiation Monitoring PPM 5.3.1, Secondary Containment Control Attached w/ Revision #
See Comments I Reference
2021 CGS NRC Written Exam Facility/Applicant Comments Comments/
Reference:
SO000147
!Rev:
Major: 15
- 2. Reactor Building Exhaust Plenum RMS (Figure 2)(REA-RIS-609A/B/C/D) a) The range of this RMS is.01 - 102 mR/hr.
b) This radiation monitor has two local alarms as follows:
LOW (white)
Instrwnent INOP indication that activates due to any of:
Indication LT. 01 mR/lrr.
Loss of power to the RMS.
Control Switch "OUT-OF-OPERATE".
HIGH (red)
If sensed on both REA-RIS-609 A & B, or C & D causes alam1 on H13-P602 AND a "Z" signal trip.
c) RESET Pushbutton Depress to reset alam1s.
d) Monitor Fw1ction Switch 3-position switch, TRIP TEST /ZERO/OPERA TE Minor: 001 OPERATE - Monitor operates nomially (other positions are for testing; ZERO position generates a trip signal that can be used to trip the channel when required by Technical Specifications).
L0-5647g e) A HI-Hi trip for channels A & B initiates an alann on H13-P602 and a Group ill containment isolation signal [i.e.. closure of the Reactor Building, Containment and Radwaste Building ventilation outboard isolation valves, and initiates startup of Standby Gas Treatment (SGT)
Train A Lead Fan and Train B Lag Fan]. Logic is "TWO-OUT-OF-T\\\\'O" (trip of both channels in either division are required to cause the isolation.)
f) A downscale condition (LE 0.01 mR/hr) sensed on both channels A &
B, causes alarm 011 H 13-P602 AND a "Z" signal trip as described in "e above.
g) The same condition for Challllels C & D initiates closure of the corresponding inboard valves and initiates startup of SGT Train B Lead Fan and Trah1 A Lag Fan (see NS 4 text for details).
h) An additional trip signal for high radiation ala.nu is provided by Recorder REA-RR-603 (on H13-P600) and actuates a control room imrnmdatnr I
2021 CGS NRC Written Exam Facility/Applicant Comments Comments I
Reference:
PPM 5.3.1 Rev:
Major: 21 Minor: N/A 5.3.1 Secon Re-.t1$ion 21 CONTROi
- RB differential pressure at or above O in. of water IF FAZ signal exisls
- RB area differential temp above alarm level, Table 22
- RB area temp above alam, level, Table 23
- RB exhaust plenum radiation level above 13 mR!hr
- RB area radiation level above alarm level, Table 24
- RB area water level above alann level, Table 25
- SFP temp above 124°F
- SFP level below 22 ft 4 in.
THEN ensure RB HVAC lsob1bn aoo SGT lnitiatlon IF SGT cannot restore and maintain RB differential pressure below O in. of water THEN re.start RB HVAC AND radioactivity release from RB hinders operation of systems required for damage control or systems required to be operated by EOPs IF RB HV AC is shutdown THEN re.set RB HVAC Isolation bg,<:
AND operate available RBH\\fAC