IR 05000482/1999301

Exam Rept 50-482/99-301 on 990726-29.Exam Results:All Nine Applicants Passed Written Exams & Exhibited No Broad Knowledge or Training Weaknesses

ML20211G242
Person / Time
Site:	Wolf Creek
Issue date:	08/17/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20211G226	List: IR 05000482/1999301 ML20211G220
References
50-482-99-301, NUDOCS 9908310210
Download: ML20211G242 (35)

Text

r-- O ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket No.: 50-482 License No.: NPF-42 Report No.: 50-482/99-301 Licensee: Wolf Creek Nuclear Operating Corporation Facility: Wolf Creek Generating Station Location: 1550 Oxen Lane, NE Burlington, Kansas Dates: July 26 to 29,1999 Inspectors: S. L. McCrory Chief Examiner, Senior Reactor Engineer, Operations Branch H. F. Bundy, Senior Reactor Engineer, Operations Branch R. E. Lantz, Reactor Engineer, Operations Branch l Approved By: John L. Pellet, Chief, Operations Branch, Division of Reactor Safety ATTACHMENTS:

Attachment 1: SupplementalInformation Attachment 2: Facility Licensee Post-Examination Comments Attachment 3: Final Written Examinations and Answer Key i

9908310210 990817 PDR ADOCK 05000482 V PDR

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-2-EXECUTIVE SUMMARY Wolf Creek Generating Station NRC inspection Report No. 50-482/99-301 NRC examiners evaluated the competency of six senior operator and three reactor operator license applicants for issuance of operating licenses at the Wolf Creek Generating Station facility. The licensee developed the initial examinations using NUREG-1021, Revision 8. NRC examiners reviewed and approved the examinations. The initial written examinations were administered to all nine applicants on July 21,1999, by facility proctors in accordance with the guidance in NUREG-1021, Revision 8. The NRC examiners administered the operating tests on July 26-29,199 J l

Operatior,s

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The applicants performed well on the written examination and demonstrated good performance skills in communication, performance verification, and procedure use I during the operating examination. However, SRO applicants infrequently communicated I degrading plant conditions up to the subsequent levels of the supervisory and management organization. All applicants passed all portions of the examination (Sections 04.1 and O4.2).

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The licensee submitted an examination of generally good quality that required only moderate changes (Section 05.1).

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-3-Reoort Details l

l Summarv of Plant Status The unit operated at power for the duration of this inspection.

1. Operations 04 Operator Knowledge and Performance

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0 [nitial Written Examination Inspection Scope

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On July 21,1999, the facility licensee proctored the administration of the written

examinations approved by the NRC to three individuals who had applied for reactor

operator (RO) licenses and six individuals who had applied for senior reactor operator l (SRO) licenses. The licensee proposed gra es for the written examinations and evaluated the results for question validity and generic weaknesses. The chief examiner reviewed the licensee's result Observations and Findinas All applicants passed the written examination. Applicant scores ranged from 84 to 93

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percent with an average of 88 percent. The licensee's post-administration analysis identified that four questions common to both examinations were missed by 50 percent or more of all applicants, that two questions, unique to the RO examination, were missed by two or more RO applicants, and that four questions, unique to the SRO examination, wero missed by three or more SRO's. The questions missed were:

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l = Common 39,51,52, and 61

. RO Only 90 and 98

. SRO Only 80,82,86, and 93 The chief examiner reviewed the questions and the applicant responses and determined that there were no broad training or knowledge weaknesses. The licensee provided one post-examination comment and recommended change to the written examination (Attachment 2). The chief examiner concurred with the licensee's recommendatio Conclusions All nine applicants passed the written examinations and exhibited no broad knowledge or training weaknesses.

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-4-0 Initial Operatina Test Inspection Scope The examination team administered the operating examination to the nine applicants on July 26 to 29,1999. The team evaluated each applicant with the appropriate number of dynamic simulator scenarios. The team evaluated each RO and instant SRO applicant with 10 system tasks and in 4 administrative areas. The team evaluated the upgrade SRO applicant with five system tasks and in 4 administrative area Observations and Findinas All applicants passed all portions of the operating test. Overall, the applicants performed well in the dynamic simulator scenarios with good procedure use, self verifications and peer checks. The applicants demonstrated strong communication skills and discipline. Communications clearly identified expected actions with consistent acknowledgment by the operators. However, SRO applicants performing in the supervising operator position displayed a very low level of communication up to the subsequent levels of the supervisory and management organization. They did not routinely attempt to notify the shift supervisor or operations management of degrading plant conditions, even when a forced shutdown was imminent, Conclusions All nine applicants passed the operating tests. The applicants demonstrated good performance skills in communication, performance verification, and procedure us However, SRO applicants communicated up to the subsequent levels of the supervisory and management organization very infrequently even as plant conditions degraded significantl Operator Training and Qualification 0 Initial Licensina Examination Devetooment The facility licensee developed the initial licensing examination in accordance with guidance provided in NUREG 1021, " Operating Licensing Examination Standards,"

Revision 8.

l 05.1.1 Examination Outline The facility licensee submitted the initial examination outlines on February 1,1999. The

! chief examiner reviewed the submittal against the requirements of NUREG-1021, Revision 8 and approved the initial examination outlines with very minor comments and advised the licensee to proceed with examination development.

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I -5-05.1.2 Examination Packaae I- Insoection Scooe -

The licensee submitted the draft examinations on May 15,1999, and the completed final

[ examination package on June 24,1999, following the chief examiner's onsite review the l week of June 21,1999.1 The chief examiner and a second examiner reviewed the I

- examinations against the requirements of NUREG-1021, Revision 8.

j Observations and Findinos 1The licensee submitted a technically valid draft examination of good quality that conformed to the original outline submitted by the licensee. The chief examiner 8 challenged 15 of 125 questions as requiring significant revision or replacement. Most of the 15 questions discriminated at too low a level while some were judgad as .

( discriminating too high. The chief examiner provided enhancement comments on an l additional 35 questions. After discussion of the suggested enhancements, the licensee L modified the examinations as agreed. The chief examiner concurred with the resolution l

of the comments, the proposed question modifications and replacements, and the final produc The licensee submitted four scenarios, including a backup, that were of good qualit The chief examiner requested the deletion of one event, considered to be redundant j- with another. event in the scenario, and provided a few enhancement comments during i the in-office review. During the onsite validation, the chief examiner deleted one event from two scenarios because they significantly increased the scenario run time with little -

- or no evaluation enhancement. Additionally, the chief examiner made minor adjustments to event sequences and time line To support the systems walkthrough section of the operating test, the facility licensee provided 20 job performance measures (JPM's) of good quality to evaluate selected operator tasks. The chief examiner noted that the examination administration schedule

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developed by the licensee resulted in 2 of the JPM's being used on subsequent days

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and requested that the licensee provide additional JPM's to preclude reuse. The chief ,

examiner provided a few minor enhancement comments and the licensee made minor !

changes to several JPM's during the chief examiner's onsite revie j l

To support the administrative topics section of the operating test, the licensee submitted three examination sets, two SRO and one RO, that consisted of a mixture of 4 administrative tasks and prescripted questions. While the administrative sets were :

adequate overall,6 of 12 (roughly 2 per set) of the prescripted questions discriminated l i

at too low a level and were required to be replaced. The licensee provided a post-examination recommendation regarding the classification scheme for the emergency j action level determination associated with Scenario 4 (Attachment 2). The chief examiner accepted the licensee's recommendation as an additional correct answe I u

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! Conclusions The licensee submitted an examination of generally good quality that required only moderate change .2 Simulation Facility Performance l

The examiners observed simulator performance with regard to fidelity during the examination validation and administration. During examination validation and administration, the simulator modeled plant performance accurately and did not exhibit I L any performance deficiencies. The simulator supported the examination wel I I

V. Manaaement Meetinas X1 Exit Meeting Summary

The examiners presented the inspection results to members of the licensee management at the conclusion of the inspection on July 29,1999. The licensee acknowledged the findings presente The licensee did not identify as proprietary any information or materials examined during I this inspectio l l

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ATTACHMENT 1

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SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee D. Webb, Lead Simulator Specialist A. Palmer, Initial Operator Licensing Supervising Instructor l J. Pippin, Manager, Training l

J. Smith, License Supervising Instructor M. Westman, Superintendent, Operations Training K. Huges, Engineering Specialist, Licensing C. Younie, Manager, Operations T. Harris, Superintendent, Licensing R. Muench, Vice President, Engineering

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ATTACHMENT 2 FACILITY LICENSEE POST-EXAMINATION COMMENTS l

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FINAL WRITTEN EXAMINATION AND ANSWER KEYS

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SUPPLEMENTAL INFORMATION l

l PARTIAL LIST OF PERSONS CONTACTED l

Licensee

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D. Webb, Lead Simulator Specialist l A. Palmer, initial Operator Licensing Supervising Instructor J. Pippin, Manager, Training J. Smith, License Supervising Instructor l

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M. Westman, Superintendent, Operations Training K. Huges, Engineering Specialist, Licensing l C. Younie, Manager, Operations

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T. Harris, Superintendent, Licensing l R. Muench, Vice President, Engineering l

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ATTACHMENT 2 FACILITY LICENSEE POST-EXAMINATION COMMENTS l

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. n WedLF CREEK NUCLEAR OPERATING CORPORATION Bntt T. Mc-Kinney Vice President Plant Operations and Plant Manager E 3 1999 WO 99-0069 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D. Reference: Initial Licensed Operator Examination Submittal of May 15, 1999 Subject: Docket N : Modification of Examination Questions Gentlemen:

Wolf Creek Nuclear Operating Corporation licensed operator candidates were given their written examination on July 20, 199 The simulator examinations and job performance measures were given July 26 through July 29, 199 Exam analysis, conducted after the examinations were given, identified that the answer key for one question on the written test and event classification for one job performance measure required modificatio The enclosure provides a description of and justification for the proposed modification. Technical references are also enclose If you have questions regarding the modification of these two examination items, please contact me at (316) 364-4112, or Mr. Jack Pippin at (316) 364-416 Very truly you s,

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9 i Britt T. Mc-Kinne CCW/rir Enclosure cc: N. Donohew (NRC), w/o D. M. Graves (NRC), w/o E. W. Merschoff (NRC), w/o L. McCrory (NRC), w/e Senior Resident Inspector (NRC), w/o {

l PO Box 411 Burhngton. KS 66839 Phone: 1316) 364 8031 An Eaual Opportunity Empiover M F HC VET ]

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' Enclosure 1 Modification to Wolf Creek Initial License Exam of July 26, 1999 1. Written Exam o Question 052

• Correct Answer: B

• The original question submittal had "A" as the correct answe During the analysis of'those questions missed by 50%'or more of the applicants it was determined that "B" is the correct

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answer. The "A" answer is based on a pressurizer-pressure input of 705 psia. The pressurizer pressure instrumentation has a range of 1700 - 2500 psig. It would not be operable at 705 psia. The input available'at lower pressures is wide range

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RCS pressure. It was reading 731 psia. The combination of 731 psia and 4 92 F places RCS subcooling at - 16*F. This corresponds to answer "B".

• The applicants requested a clarification as to where the subcooling indication was being read (i.e. computer point or control room console). The clarification "on the main control board (RLO22)" was made to the whole group taking the exa * Facility Recommendation: Change correct answer from "A" to

"B".

• Technical References: Attached

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2. Administrative JPM Change e JPM Number: ADU-SRO-A.4-e Classify NRC Dynamic scenario #4 e- Event classification should be from the event path of EAL-5, Fuel Element Failure. The correct path is FEFl*FEF2-+FEF3-+FEF54 SITE AREA EMERGENCY. EAL-8 does provide the correct classification for this event but EAL-5 should be selected based on EPP 06-005, Emergency Classification. If the event fits more than one EAL and results in an identical classification, then the classification shall be made using

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the first EAL encountere l'

e Facility Recommendation : Change 2.* .f rom SFM1-+SSFM4-+SSFMS-+

SSFM6-+ SITE AREA EMERGENCY to . FEF1-+FEF2-+FEF3-+FEF5-+ SITE AREA EMERGENC * Technical References: Attached i

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Question Number 052 Question The Operating Crew is perfoiming ES-04 " Natural Circulation Cooidown'

The following values are current conditions:

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e # OF CRDM Fans Running 4

• WR Hot Leg 1 Temp 488 F e WR Cold Leg i Temp 465*F e WR Cold Leg 2 Temp 470 F e Core Exit Thermocouples 492 F e RCS Pressure 731 psia e Pressurizer Pressure 705 psia l

l What would be the displayed value for RCS Subcooling Margin?

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A. 12 F c . ., +. . I bea<) )

B. 16 F (b0 *

C. 20 F D. 38*F Answer A (Revised answer is B)

Allowed references Steam Tables LP and objective SY1300202. Rev. 005 Obj. 4. Steam Tables WCGS procedure - None print references NRC KA Topic 002 K5.17 Knowledge of the operationalimplications of the following concepts as they apply to the RCS: need for monitonng in-core thermocouples during natural circulatio NRC KA topic 3.8/ importance factors NRC 1122 KA . 41.5/4 CFR55 41/43 tie NRC difficulty rating Not Available

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WCGS difficulty A3 - Higher Order Question. The candidate must look at the existing rating and explanation parameters and determine which ones would be feeding the subcooling monitor calculation. This information must then be applied to the steam tables to calculate the value of subcoolin Distracter explanation Incorrect - This answer is subcooling based on pressurizer pressure of 705 and references psia. This is not provided to the subcooling margm momtor because these pressure transmitters have a lower range of 1700 psi l B. Correct - This answer is correct because it uses RCS pressure of 731 psi j This is wide range RCS pressure which has a range of 0 - 3000 psig. It l would be the pressure reference because pressurizer pressure lower range is I

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1700 psig. The saturation temperature for 731 psia is 508 F. The highest temperature parameter is 492't. '1 his gives 16"F subcoolin C. Incorrect - This answer is incorrect because it uses RCS pressure of 731 psia and the WR hot leg temperature of 488 F. This is a plausible distracter j because both feed the subcooling monito !

D. Incorrect - This answer is incorrect because it uses RCS pressure of 731 psia and the WR cold leg 2 temperature of 470'F. This is a plausible distracter because both feed the subcooling monito NRC ES-401 Tier and SRO Tier 2 Group 2 section location RO: Tier 2 Group 2 Question original Modified Bank j source {

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o RCS Instrumentation '7'#

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Objective 4: Core Subcooling Monitor Introduction The Core Subcooling Monitoring System functions to monitor RCS subcooling and provide both local and remote indications and alarm l I

Objective Explain the function and operation of the Core Subcooling Monitor Content:

The Core Subcooling Monitoring System is comprised of two trains. Refer to drawing WCGS-BB 112. Each train receives inputs from the followine ore E t Thermocouples(TCs)

3 Thermocouple Reference Junction RTDs (compensation for TCs)

e ___2 Wide Range Loop Twand 2 Wide Range Loop T. channels e Ifule Range and 2 Narrow Range pressure channels

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Operauons Irammg Page: 37 of 44 05/08/98

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RCS Instrumentation

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CORE SUBCOOLING MONITOR SYSTEM s a <

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4 4 L14 25 TCa am 2sTes  : Processor ' Y Y R " "*E : Cabinet A Cabnet Pnnter

1. l 25 TCs

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h MCB Subcookng Meter

ControlRoom Annuncators v

Tram B Simitar

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E Plant Computer WCGS-BB-112

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Operations Iraining Page 38 of 44 05/08/98

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PROCESS Specific instrumentation inputs to the Core Subcooling Monitor are as follows:

TRAIN INSTRUMENT DESCRIPTION A TE-413A Loop I WR Tw ,

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A TE 423A Loop 2 WR Tw A TE 433B Loop 3 WR A TE-443B Loop 4 WR A 25 Thermocouples Half of the incore Thermocouples A 3 Reference RTDs Reference Junction for TC Correction A PT-455 Pressuruer Pressure (NR)

A PT-457 Pressuruer Pmssure(NR)

A PT-405 RCS Pressure (WR)

B TE 413B Loop i WR B TE 423B Loop 2 WR B TE-433A Loop 3 WR B TE-443A Loop 4 WR Tw B 251hermocouples Otber half of the lacore Hermocouples B 3 Reference RTDs Reference Junction for TC Correction B PT-456 Pressuruer Pressure (NR) PT-458 Pressurizer Pressure (NR)

B PT-403 RCS Pressure (WR)

Systern microprocessors calculate core saturation temperature for the RCS based on auctioneered low RCS pressure and auctioneered high wide range or thermocouple temperature Meters (BB TI-1390A & 1390B) display subcooihMain Control Board panel RLO22. The of the meter is green with a range of 20 - 200*F subcooled, the middle is a faded yellow with a range from 5 - 20*F subcooled, and the top is red with a range of 5'F

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subcooled to 2000*F superheated. The Plant Computer also receives subcooling informatio The processor cabinet (RP081 A/ B) is located in the Control Room near the 7300 Process Protection Rack I Various system information (e.g., individual thermocouple readings, individual pressures, reference junction temperatures) may be printed out or displayed on the CRT at the cabinet. Operating instructions are posted inside the cabinet doo i Opersuons Irammg Page; 39 of 44 05/08/98

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, ; Revision: 1 EMERGENCY CLASSIFICATION EPP 06-005 l

t Reference Use Page 6 of 8 m

' PROCEDURE

}, Diaanosing And Classifying An Event 2 _ .0 CAUTION

\

y Outage / shutdown conditions should be given special consideration y as they are likely to create abnormalities such as the loss of

\ RCS pressure boundary (refueling, mid-loop operations, equipment W hatch open, etc. ) . This type of boundary violation combined with

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a plant transient (loss of AC power, e tc. ) may create a worse situation than would be expected if the Unit was in power operation i 7. Upon recognition that an abnormal or emergency condition exists, the Shift Supervisor shall be immediately notifie .142 Plant parameters and instrument readings or any other symptoms which would be indicative of further systems degradation shall be monitore . The appropriate EMGs and OENs shall be referenced and any actions called for, based upon the indicated symptoms, shall be take . The EALs shall be used to determine whether or not the event fits the general description for any of the initiating conditions liste . The EAL resulting in the highest classification shall be used to classify the even , IF the event fits more than one EAL and results in an identical emergency classification, THEN the classification shall be made using the first EAL encountere '

• Step numbers of the EAL used to classify the event shall be entered on EPF 06-007-01, WOLF CREEK GENERATING STATION EMERGENCY NOTIFICATION, to show the path used to make the classificatio . IF the event does not fit any of the EAL general descriptions, THEN the implications of the event shoulc be evaluated and the emergency condition classified, if appropriate, based upon professional judgment. If no classification is warranted, no further action is required except to continue monitoring the even I

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-- ADU-S RO-A.4

. Rev. 001 Date: S'5,99 WCGS SRO/RO TRAINING PROGRAM JOB PERFORMANCE MEASURE EVALUATION FORM TASK: Given a plant event, classify the event with a 100% accurac TASK /JTA: Knowledge of the emergency action level thresholds and classification K/A #s: 2.4.41 References: AP 06-002, Rev. 0; APF 06-002-01, Rev. 0 Examinee's Name SS N SRO RO The examinee's performance was evaluated against the standards in this JPM and determined to be:

SATISFACTORY MARGINAL UNSATISFACTORY Reason, if MARGINAL or UNSATISFACTORY:

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Estimated JPM completion Time: 15 mi Actual Performance Time: mi Location of Performance: Control Room ___ Simulator 4 Method of Performance: Simulate Perform 4 Tools and Equipment: Simulator .

Evaluators Signature: Date

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• Rev. 001 WCGS SRO/RO TRAINING PROGRAM JOB PERFORMANCE MEASURE EVALUATION FORM Notes:

The examiner shall verify that the procedure revision far this JPM is current and that any changes against the referenced procedure does not invalidate this JP Simulator Set-up:

Used with 1999 NRC exam Dynamic Scenario No. Initial Conditions:

Dynamic Scenario No. 4 has been completed. Classify the even i

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ADU SRO- * Rev. 001 WCGS SRO/RO TRAINING PROGRAM  !

JOB PERFORMANCE MEASURE EVALUATION FORM Element Step #

Element Standard Score

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Start Tune j 1.* N/A Analyze the even Utilize Emergency Action Levels, APF 06 SU 002-01, to locate the emergency action level and start the event pat ;

Comments: N/A Classify the even Complete element N/A Comments:

I 2.* N/A Event path from EAL-5, Fuel Element Failure: FEFl + FEF2+FEF3+ FEF5 + SU j

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I SITE AREA EMERGENCY Comments:

Termination: Properly classifying the event completes the JP Stop Time

• Critical step I

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WCGS SRO/RO TRAINING PROGRAM JOB PERFORMANCE MEASURE EVALUATION FORM

Initial Conditions:

Dynamic Scenario No. 4 has been completed. Classify the event.

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