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{{#Wiki_filter:CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390 Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 29, 2009 Mr. Malcolm T. Widmann, Branch Chief Operations Branch U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street S.W. Suite 23T85 Atlanta, Georgia 30303-8931 Browns Ferry Nuclear Plant 10 CFR 55.40 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296  
{{#Wiki_filter:CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390 Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 29, 2009 10 CFR 55.40 Mr. Malcolm T. Widmann, Branch Chief Operations Branch U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street S.W.
Suite 23T85 Atlanta, Georgia 30303-8931 Browns Ferry Nuclear Plant Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296


==Subject:==
==Subject:==
Mr. Widmann REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITIEN EXAMINATIONS  
REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITIEN EXAMINATIONS - POST EXAMINATION RESPONSE Mr. Widmann TVA administered the final NRC Written Examination for the RO and SRO HLT Class 0801 on July 22,2009. Please find enclosed, the supporting documentation required by Section ES-501 of NUREG 1021, Post Examination Activities. The enclosure content listing is provided at the end of this letter.
-POST EXAMINATION RESPONSE TVA administered the final NRC Written Examination for the RO and SRO HLT Class 0801 on July 22,2009. Please find enclosed, the supporting documentation required by Section ES-501 of NUREG 1021, Post Examination Activities.
The results were three Senior Reactor Operator (SRO) Candidates passed the examination with overall scores ranging from 89 percent to 92 percent and four of six Reactor Operator (RO) Candidates passed the RO portion of the exam with scores ranging from 89 percent to 90.6 percent. Two Candidates failed the RO portion of the written exam with scores of 78.6 percent and 76 percent. The SRO scores on the RO portion of the examination ranged from 90.6 percent to 93.3 percent.
The enclosure content listing is provided at the end of this letter. The results were three Senior Reactor Operator (SRO) Candidates passed the examination with overall scores ranging from 89 percent to 92 percent and four of six Reactor Operator (RO) Candidates passed the RO portion of the exam with scores ranging from 89 percent to 90.6 percent. Two Candidates failed the RO portion of the written exam with scores of 78.6 percent and 76 percent. The SRO scores on the RO portion of the examination ranged from 90.6 percent to 93.3 percent. Analysis of the RO portion of the examination indicated five questions, numbers 18, 37, 59, 62, and 68, with a greater than 50 percent failure rate. Analysis of the SRO portion of the examination indicates questions 78 and 96 have a greater than 50 percent failure rate. Additionally, there were specific comments posed by the candidates during the post-examination review. CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390 CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390 Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 29, 2009 Mr. Malcolm T. Widmann, Branch Chief Operations Branch U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street S.W. Suite 23T85 Atlanta, Georgia 30303-8931 Browns Ferry Nuclear Plant 10 CFR 55.40 Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296
Analysis of the RO portion of the examination indicated five questions, numbers 18, 37, 59, 62, and 68, with a greater than 50 percent failure rate. Analysis of the SRO portion of the examination indicates questions 78 and 96 have a greater than 50 percent failure rate. Additionally, there were specific comments posed by the candidates during the post-examination review.
CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390


==Subject:==
Malcolm T. Widmann Page 2 July 29, 2009 Subsequent detailed analysis of high miss-rate questions and those identified during post-exam review indicates potential issues with four questions. There are two questions in the package that TVA believes have two correct answers. There are two questions in the package that may have job-link issues. TVA has submitted these two questions for deletion.
Mr. Widmann REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITIEN EXAMINATIONS
The results of this analysis, where applicable, will be forwarded to the HLT Supervisor for potential inclusion in the appropriate training material.
-POST EXAMINATION RESPONSE TVA administered the final NRC Written Examination for the RO and SRO HLT Class 0801 on July 22,2009. Please find enclosed, the supporting documentation required by Section ES-501 of NUREG 1021, Post Examination Activities.
The enclosure content listing is provided at the end of this letter. The results were three Senior Reactor Operator (SRO) Candidates passed the examination with overall scores ranging from 89 percent to 92 percent and four of six Reactor Operator (RO) Candidates passed the RO portion of the exam with scores ranging from 89 percent to 90.6 percent. Two Candidates failed the RO portion of the written exam with scores of 78.6 percent and 76 percent. The SRO scores on the RO portion of the examination ranged from 90.6 percent to 93.3 percent. Analysis of the RO portion of the examination indicated five questions, numbers 18, 37, 59, 62, and 68, with a greater than 50 percent failure rate. Analysis of the SRO portion of the examination indicates questions 78 and 96 have a greater than 50 percent failure rate. Additionally, there were specific comments posed by the candidates during the post-examination review. CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390 Malcolm T. Widmann Page 2 July 29, 2009 Subsequent detailed analysis of high miss-rate questions and those identified during post-exam review indicates potential issues with four questions.
There are two questions in the package that TVA believes have two correct answers. There are two questions in the package that may have job-link issues. TVA has submitted these two questions for deletion.
The results of this analysis, where applicable, will be forwarded to the HL T Supervisor for potential inclusion in the appropriate training material.
The enclosures to this letter are considered by TVA to be of a personal nature and, as such, are to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).
The enclosures to this letter are considered by TVA to be of a personal nature and, as such, are to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).
If you have any questions or comments, please telephone Mr. Brian P. Stetson at (256) 729-7039.
If you have any questions or comments, please telephone Mr. Brian P. Stetson at (256) 729-7039.
R. G. West Vice President  
r:u~
R. G. West Vice President


==Enclosures:==
==Enclosures:==
  -Form ES-403-1, Written Examination Grading Quality Check Enclosure 2 -Graded Written Examinations (I.E., Each Applicant's Original Answer and Examination Cover Sheets) Plus A Clean Copy of Each Applicant's Answer Sheet Enclosure 3 -Master Examination(s)
Excerpt Annotated to Indicate Any Changes Made While Administering the Examination
-No Changes Made While Grading Enclosure 4 -Questions Asked By and Answers Given to the Applicants During the Written Examination  -Substantive Comments Made By the Applicants Following the Written Examination Malcolm T. Widmann Page 2 July 29, 2009 Subsequent detailed analysis of high miss-rate questions and those identified during post-exam review indicates potential issues with four questions.
There are two questions in the package that TVA believes have two correct answers. There are two questions in the package that may have job-link issues. TVA has submitted these two questions for deletion.
The results of this analysis, where applicable, will be forwarded to the HL T Supervisor for potential inclusion in the appropriate training material.
The enclosures to this letter are considered by TVA to be of a personal nature and, as such, are to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).
If you have any questions or comments, please telephone Mr. Brian P. Stetson at (256) 729-7039.
R. G. West Vice President


==Enclosures:==
Enclosure 1 - Form ES-403-1, Written Examination Grading Quality Check Enclosure 2 - Graded Written Examinations (I.E., Each Applicant's Original Answer and Examination Cover Sheets) Plus A Clean Copy of Each Applicant's Answer Sheet Enclosure 3 - Master Examination(s) Excerpt Annotated to Indicate Any Changes Made While Administering the Examination - No Changes Made While Grading Enclosure 4 - Questions Asked By and Answers Given to the Applicants During the Written Examination Enclosure 5 - Substantive Comments Made By the Applicants Following the Written Examination
  -Form ES-403-1, Written Examination Grading Quality Check Enclosure 2 -Graded Written Examinations (I.E., Each Applicant's Original Answer and Examination Cover Sheets) Plus A Clean Copy of Each Applicant's Answer Sheet Enclosure 3 -Master Examination(s)
 
Excerpt Annotated to Indicate Any Changes Made While Administering the Examination  
Malcolm T. Widmann Page 3 July 29, 2009 Enclosure 6 - Exam Seating Chart Enclosure 7 - Results of Any Written Examination Performance Analysis That Was Performed, With Recommended Substantive Changes
-No Changes Made While Grading Enclosure 4 -Questions Asked By and Answers Given to the Applicants During the Written Examination   -Substantive Comments Made By the Applicants Following the Written Examination Malcolm T. Widmann Page 3 July 29, 2009 Enclosure 6 -Exam Seating Chart Enclosure 7 -Results of Any Written Examination Performance Analysis That Was Performed, With Recommended Substantive Changes Malcolm T. Widmann Page 3 July 29, 2009 Enclosure 6 -Exam Seating Chart Enclosure 7 -Results of Any Written Examination Performance Analysis That Was Performed, With Recommended Substantive Changes ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITTEN EXAMINATION
 
-POST EXAMINATION RESPONSE FORM ES-403-1, WRITTEN EXAMINATION GRADING QUALITY CHECK (SEE ATTACHED)
ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT (BFN)
ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITTEN EXAMINATION  
UNITS 1, 2, AND 3 REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITTEN EXAMINATION - POST EXAMINATION RESPONSE FORM ES-403-1, WRITTEN EXAMINATION GRADING QUALITY CHECK (SEE ATTACHED)
-POST EXAMINATION RESPONSE FORM ES-403-1, WRITTEN EXAMINATION GRADING QUALITY CHECK (SEE ATTACHED)
 
ES-401 Sample Written Examination Question Worksheet Exam i nation Outline Cross-reference
ES-401                                     Sample Written Examination                               Form ES-401*5 ES-401-5 Question Worksheet
: 295038 High Off-site Release Rate I 9 EK1.03 (10CFR 55.41 , 10) Knowledge of the operational implications of the following concepts as they app l y to H I GH OFF-SITE RELEASE RATE:
* Examination Outline Cross-reference:
* Meteorological effects on off-site release I Proposed Question: # 18 Form ES-401-5 Level RO SRO Tier # 1 Group # 1 KIA # 295038EK1.03 Importance Rat i ng 2.8 A General Emergency is declared due to a valid Wide Range Gaseous Rad Monitor (WRGERMS) reading. The current meteorological data is:
295038 High Off-site Release Rate 19 EK1.03 (10CFR 55.41 ,10)   .10)
I9 Knowledge of the operational implications of the following concepts as they apply to HIGH OFF*SITE OFF-SITE RELEASE RATERATE::
Level Tier #
Tier#
Group #
KIA #
KJA#
RO 1
1 SRO 1-295038EK1 .03
* Meteorological effects on off-site release I Proposed Question: # 18 Importance Rating            2.8 1-='
A General Emergency is declared due to a valid Wide Range Gaseous Rad Monitor (WRGERMS) reading. The current meteorological data is:
* 91 meter wind direction:
* 91 meter wind direction:
* 46 meter wind direction:
direction :    120 degrees
120 degrees 115 degrees Which ONE of the following ident i fies the correct data point to use for this release AND the w i nd direction?
* 46 meter wind direction direction::   115 degrees Which ONE of the following identifies the correct data point to use for this release AND the wind direction?
A. (1) 91 (2) wind is blowing from the Southeast B. (1) 46 (2) wind is blowing f r om the Southeast C. (1) 91 (2) wind is blowing from the Northwest D. (1) 46 (2) wind is blowing from the Northwest Proposed Answer: A Post-Exam Delete the question.
A. (1) 91 (2) wind is blowing Itom    from the Southeast B. (1)46 (1) 46 (2) wind is blowing from the Southeast c.
Evaluation Recomme ndation: ," I I A . c ," , ( IllI t l (/U( i t 5 ... ' ; *
C.   (1) 91 (2) wind is blowing from the Northwest D. (1) 46 (2) wind is blowing from the Northwest Proposed Answer:
* ES-401 Sample Written Examination Question Worksheet Examination Outline Cross-reference
Answer:
: 295038 High Off-site Release Rate 1 9 EK1.03 (10CFR 55.41.10) Knowledge of the operational implications of the following concepts as t hey apply to HIGH OFF*SITE RELEASE RATE:
A Post-Exam Post*Exam          Delete the question.
* Meteorolog ic al effects on off-site release I Proposed Question: # 18 Level Tier# Group # KJA# Importance Rating Form ES-401*5 RO SRO 1 1 1-295038EK1.03 2.8 1-=' A General Emergency is declared due to a valid Wide Range Gaseous Rad Monitor (WRGERMS) reading. The current meteorological data is:
Evaluation Recomme ndation:
* 91 meter wind direction:
ndation :
* 46 meter wind direction: 120 degrees 115 degrees Which ONE of the following identifies the correct data point to use for this release AND the wind direction?
                                                                                        ,"I   I   A     . c ,"   ,
A. (1) 91 (2) wind is blowing Itom the Southeast B. (1)46 (2) wind is blowing from the Southeast
(... IllIt l ( /U( i t
: c. (1) 91 (2) wind is blowing from the Northwest D. (1) 46 (2) wind is blowing from the Northwest Proposed Answer: A Post*Exam Delete the quest i on. Evaluation Recomme ndation: 
                                                                                            '   ;
* *
5
* ES-401 Challenge Issue: Sample Written Examination Form ES-401-5 Question Worksheet Answer Key Incorrect I Stem Clarity -The stem requests the candidate demonstrate knowledge of meteorological implications during emergency conditions.
* ES-401                                               Sample Written Examination                                                   Form ES-401-5 Question Worksheet
The stem asks for information that is not a part of a ROs normal job responsibility.
* Answer Key Incorrect I Stem Clarity - The stem requests the candidate Challenge demonstrate knowledge of meteorological implications during emergency Issue:
Part (1) asks information on the correct data point to collect data from [46m or 91 m}. This information is normally collected by RP personnel per EPIP-13, ltDose Assessment," (See excerpt).
conditions. The stem asks for information that is not a part of a ROs normal job responsibility. Part (1) asks information on the correct data point to collect data from [46m or 91 m}. This information is normally collected by RP personnel per EPIP-13, ltDose Assessment," (See excerpt). If SPDS is unavailable, (see excerpt), operations could be asked specifically what parameters to monitorlreport. With SPDS out of service, there is NO information available inside the Control Room to support data collection for Wind Direction.
If SPDS is unavailable, (see excerpt), operations could be asked specifically what parameters to monitorlreport.
BROWNS FERRY                                             DOSE ASSESSMENT EPIP-13 3.6.3         Stack Meteorological Data 3.6.3.1 For stack releases record measurements at the 91 meter reading.
With SPDS out of service, there is NO information available inside the Control Room to support data collection for Wind Direction.
3.6.3.2 The default value for stability cfass with no met data available IS "0" for stack releases.
BROWNS FERRY DOSE ASSESSMENT EPIP-13 3.6.3 Stack Meteorological Data 3.6.3.1 For stack releases record measurements at the 91 meter reading. 3.6.3.2 The default value for stability cfass with no met data available IS "0" for stack releases.
3.6.3.3 The default value for wind speed with no met data available is 4.0 meters/second for the stack.
3.6.3.3 The default value for wind speed with no met data available is 4.0 meters/second for the stack. 3.4 Oetennination of Noble Gas Release Rate In j.lCi/second (Step 3 of Appendix A and B) 3.4.1 Stack Noble Gas Release Rate 3.4.1.4 If SPDS IS unavaIlable, notify OperatIons personnel on the affected unit to gain the information utilizing control room instrumentation.
3.4         Oetennination of Noble Gas Release Rate In j.lCi/second (Step 3 of Appendix A and B) 3.4.1       Stack Noble Gas Release Rate
or if unavailable, notify the Shift Manager/Site Emergency Director that TI-67, "Determination of Stack and Hardened Wetwell Vent Release Rates* (backup method), procedure must be performed by RP and Chemistry personnel.
* 3.4.1.4 If SPDS               IS unavaIlable, notify OperatIons personnel on the affected unit to gain the information utilizing control room instrumentation. or if unavailable, notify the Shift Manager/Site Emergency Director that TI-67, "Determination of Stack and Hardened Wetwell Vent Release Rates* (backup method), procedure must be performed by RP and Chemistry personnel.
The ROs do normally collect and record meteorological data per 1-SR-2, ltlnstrument Checks and Observations," based on TRM 3.3.7 requirements (See excerpt).
The ROs do normally collect and record meteorological data per 1-SR-2, ltlnstrument Checks and Observations," based on TRM 3.3.7 requirements (See excerpt). This information is collected on all three levels (10m, 46m and 91 m), making it non-specific to the requirements of an emergency assessment.
This information is collected on all three levels (10m, 46m and 91 m), making it non-specific to the requirements of an emergency assessment.
Instrument Check** nd Observations Attachment 2 (PIIg8 49 of 96)
TASLE ,48 APPLtCABtliTY C1tal1a So<ro! LOCATION FndoY Instrument Check ** nd Observations Attachment 2 (PIIg8 49 of 96) SUrveillance PrOC8dure Om Pickage. Modes 1, 2, & 3 METEOROLOGICAL
SUrveillance PrOC8dure Om Pickage. Modes 1, 2, & 3
!NSTRUMENTATJON DAY SHIfT WEE" AT ALL TIMES (Note TSR:3371
                                                                                                                          --
'NINO DIRECTION WtNQSPEEO 91104 46M 10M 9114 ---10M uo Uno! SI.1M The need for this information during emergency conditions is the responsibility/function of RP or an SRO if requested by RP, based on the following:
TASLE 1.48
: 1) Per supplied "Guidance for SRO-only Questions," Rev 0, page 5 of 19, (see excerpt) part (1) would be considered SRO knowledge only. * *
                      ,48       METEOROLOGICAL INSTRUMENTATJON
* ES-401 Challenge Issue: Sample Written Examination Form ES-401-5 Question Worksheet Answer Key Incorrect I Stem Clarity -The stem requests the candidate demonstrate knowledge of meteorological implications during emergency conditions.
                                                      !NSTRUMENTATJON                        VA Y SHFT DAY  SHIfT    <NEEI(
The stem asks for information that is not a part of a ROs normal job responsibility.
WEE" APPLtCABtliTY     AT ALL TIMES (Note 2~
Part (1) asks information on the correct data point to collect data from [46m or 91 m}. This information is normally collected by RP personnel per EPIP-13, ltDose Assessment," (See excerpt).
C1tarta C1tal1a &.ute So<ro!    TSR:3371 TSR: 3.3 7 1
If SPDS is unavailable, (see excerpt), operations could be asked specifically what parameters to monitorlreport.
                                                                                                            -
With SPDS out of service, there is NO information available inside the Control Room to support data collection for Wind Direction.
LOCATlON LOCATION          rcs ICS~*_'      .:Nc(e 1
BROWNS FERRY DOSE ASSESSMENT EPIP-13 3.6.3 Stack Meteorological Data 3.6.3.1 For stack releases record measurements at the 91 meter reading. 3.6.3.2 The default value for stability cfass with no met data available IS "0" for stack releases.
                                                      'NINO DIRECTION                                   WtNQSPEEO 91M 91104              46M             10M           9114 91M               46M   10M   uo Uno! SI.1M
3.6.3.3 The default value for wind speed with no met data available is 4.0 meters/second for the stack. 3.4 Oetennination of Noble Gas Release Rate In j.lCi/second (Step 3 of Appendix A and B) 3.4.1 Stack Noble Gas Release Rate 3.4.1.4 If SPDS IS unavaIlable, notify OperatIons personnel on the affected unit to gain the information utilizing control room instrumentation.
                  -
or if unavailable, notify the Shift Manager/Site Emergency Director that TI-67, "Determination of Stack and Hardened Wetwell Vent Release Rates* (backup method), procedure must be performed by RP and Chemistry personnel.
FndoY The need for this information during emergency conditions is the
The ROs do normally collect and record meteorological data per 1-SR-2, ltlnstrument Checks and Observations," based on TRM 3.3.7 requirements (See excerpt).
* responsibility/function of RP or an SRO if requested by RP, based on the following:
This information is collected on all three levels (10m, 46m and 91 m), making it non-specific to the requirements of an emergency assessment.
: 1) Per supplied "Guidance for SRO-only Questions," Rev 0, page 5 of 19, (see excerpt) part (1) would be considered SRO knowledge only.
Instrument Check ** nd Observations Attachment 2 (PIIg8 49 of 96) SUrveillance PrOC8dure Om Pickage. Modes 1, 2, & 3 TASLE 1.48 METEOROLOGICAL INSTRUMENTATJON VA Y SHFT <NEEI( APPLtCABtliTY AT ALL TIMES (Note C1tarta &.ute TSR: 3.3 7 1 L OCATlON rcs .:Nc(e 1 'NINO DIRECTION WtNQSPEEO 91M 46M 10M 91M 46M ---10M uo Uno! SI.1M The need for this information during emergency conditions is the responsibility/function of RP or an SRO if requested by RP, based on the following:
 
: 1) Per supplied "Guidance for SRO-only Questions," Rev 0, page 5 of 19, (see excerpt) part (1) would be considered SRO knowledge only.
ES-401                                     Sample Written Examination                             Form ES-401-5 Question Worksheet
* *
* Does the question involve one or more of the                   YES --+ SRO -only following for Tech Specs, Technical Requirements,                             question and/or Offsite Dose Calculation Manual?
* ES-401 Sample Written Examination Question Worksheet Does the question involve one or more of the following for Tech Specs, Technical Requirements, and/or Offsite Dose Calculation Manual? YES --+ SRO -only question
* Application of required actions (Section 3) and surveillance requirements (Section 4) in accordance with rules of application requirements (
* Application of required actions (Section 3) and surveillance requirements (Section 4) in accordance with rules of application requirements ( Section 1) NO
Section 1) NO
* Applications of generic LCO requirements (LCO 3.0.1 thru 3.0.7 and LCO 4.0.1 thru 4.0.7) NO
* Applications of generic LCO requirements (LCO 3.0.1 thru 3.0.7 and LCO 4.0.1 thru 4.0.7) NO
* Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology YES Meteorological Monitoring Instrumentation B 3.3.7 TR 33 INSTRUMENTATION TR 3.3.7 Meteorological Monitoring Instrumentation BASES BACKGROUND A complete description of past meteorological conditions at BFN and the surrounding area is located in the FSAR The meteorology of the Browns Ferry site provides generally favorable atmospheric conditions for transport and dispersion of plant emissions An operational meteorological measurement program ensures that sufficient data is available for estimating potential radiation dose to the public as a result of routine or accidental release of radioactive materials to the atmosphere A 91 meter tower with supporting meteorological instrumentation is located within the BFN site boundary to satisfy this objective Form ES-401-5 However, none of this information is used during emergency conditions, making this NOT within the scope of a RO job function.
* Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology YES Meteorological Monitoring Instrumentation B 3.3.7 TR 33     INSTRUMENTATION TR 3.3.7     Meteorological Monitoring Instrumentation BASES
Thus, there are NO correct answers. Candidate performance:
* BACKGROUND           A complete description of past meteorological conditions at BFN and the surrounding area is located in the FSAR The meteorology of the Browns Ferry site provides generally favorable atmospheric conditions for transport and dispersion of plant emissions An operational meteorological measurement program ensures that sufficient data is available for estimating potential radiation dose to the public as a result of routine or accidental release of radioactive materials to the atmosphere A 91 meter tower with supporting meteorological instrumentation is located within the BFN site boundary to satisfy this objective However, none of this information is used during emergency conditions, making this NOT within the scope of a RO job function.
3 of 9 selected "C", 1 selected "B", and 5 selected "A" Explanation:
Thus, there are NO correct answers.
A. INCORRECT:
Candidate performance: 3 of 9 selected "C", 1 selected "B", and 5 selected "A" Explanation:
Part 1= correct, Per EPIP-13, attachment A Met data is collected from the 91 meter point. This is a stack release. (WRGERMS = stack) This information is collected and documented by RP personnel, or if SPDS were non-operational, a request of Operations.
A. INCORRECT: Part 1= correct, Per EPIP-13, attachment A Met data is collected from the 91 meter point. This is a stack release. (WRGERMS = stack) This information is collected and documented by RP personnel, or if SPDS were non-operational, a request of Operations. However there is NO additional instrumentation within the Control Room that could be used to assess Wind Direction if SPDS were to be NON-OPERATIONAL. Part 2 = correct - Per EPIP-13, Attachment A, wind "from" is correct. Also the RO does collect Meteorological data per 1-SR-2, making this portion not specifically a function of the RO, but
However there is NO additional instrumentation within the Control Room that could be used to assess Wind Direction if SPDS were to be NON-OPERATIONAL.
* within the knowledge range of a RO.
Part 2 = correct -Per EPIP-13, Attachment A, wind "from" is correct. Also the RO does collect Meteorological data per 1-SR-2, making this portion not specifically a function of the RO, but within the knowledge range of a RO. B. INCORRECT:
B. INCORRECT: See above.
See above. C. INCORRECT:
C. INCORRECT: See above.
See above. D. INCORRECT:
D. INCORRECT: See above.
See above. * *
 
* ES-401 Sample Written Examination Question Worksheet Does the question involve one or more of the following for Tech Specs, Technical Requirements, and/or Offsite Dose Calculation Manual? YES --+ SRO -only question
ES-401                                     Sample Written Examination                                               Form ES-401-5 ES-401*5 Question Worksheet QUestion Technical Reference(s):           EPlp*13 Rev 38, EPIP-13                                                        (Attach if not previously provided) 1-SR-2 Rev 19                                               (Including version I revision number)
* Application of required actions (Section 3) and surveillance requirements (Section 4) in accordance with rules of application requirements ( Section 1) NO
Proposed references to be provided to applicants during examination:     examination:          NONE
* Applications of generic LCO requirements (LCO 3.0.1 thru 3.0.7 and LCO 4.0.1 thru 4.0.7) NO
                                                                                              --------------------------
* Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology YES Meteorological Monitoring Instrumentation B 3.3.7 TR 33 INSTRUMENTATION TR 3.3.7 Meteorological Monitoring Instrumentation BASES BACKGROUND A complete description of past meteorological conditions at BFN and the surrounding area is located in the FSAR The meteorology of the Browns Ferry site provides generally favorable atmospheric conditions for transport and dispersion of plant emissions An operational meteorological measurement program ensures that sufficient data is available for estimating potential radiation dose to the public as a result of routine or accidental release of radioactive materials to the atmosphere A 91 meter tower with supporting meteorological instrumentation is located within the BFN site boundary to satisfy this objective Form ES-401-5 However, none of this information is used during emergency conditions, making this NOT within the scope of a RO job function.
                                                                                              -------------------
Thus, there are NO correct answers. Candidate performance:
Learning Objective:                 (As available)
3 of 9 selected "C", 1 selected "B", and 5 selected "A" Explanation:
                                                                    ;-                 1.-.
A. INCORRECT:
Question Source:                                   Bank.
Part 1= correct, Per EPIP-13, attachment A Met data is collected from the 91 meter point. This is a stack release. (WRGERMS = stack) This information is collected and documented by RP personnel, or if SPDS were non-operational, a request of Operations.
                                                                    .   -
However there is NO additional instrumentation within the Control Room that could be used to assess Wind Direction if SPDS were to be NON-OPERATIONAL.
                                                                            . -
Part 2 = correct -Per EPIP-13, Attachment A, wind "from" is correct. Also the RO does collect Meteorological data per 1-SR-2, making this portion not specifically a function of the RO, but within the knowledge range of a RO. B. INCORRECT:
                                                                                -'. ..         '.
See above. C. INCORRECT:
(Note changes or attach parent)
See above. D. INCORRECT:
New           X
See above.
                                                                        --~-~--~            ......
ES-401 Technical Reference(s):
History:
Sample Written Examination Question Worksheet EPlp*13 Rev 38, Form ES-401*5 (Attach if not previously provided) 1-SR-2 Rev 19 (Including version I revision number) Proposed references to be provided to applicants during examination:
Question History:                             RCExam (Optional- Ouestions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to (Optional - Questions provide the information will necessitate a detailed review of every question.)
NONE --------------------------
Question Cognitive Level:               Memory or Fundamental Knowledge Comprehension or Analysis                     X 10 CFR Part 55 Content:                 55.41       X 55.43 Comments:
Learning Objective: (As available)  
* ES-401                                     Sample Written Examination                     Form ES-401-5 ES-401-S Question Worksheet
;-1.-. Question Source: Bank. . -. --'. .. '. (Note changes or attach parent) New X  
* Examination Outline Cross-reference:
...... Question History: RCExam (Optional-Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)
EA1.04 EA1  .04 (10CFR 55.41.7)
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:
Wtr Lvi 295029 High Suppression Pool WIt LviIi 5 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL:
* ES-401 T ec hnical Reference(s):
Level Tier #
Sample Written Examination QUestion Worksheet EPIP-13 Rev 38, Form ES-401-5 (Attach if not previously provided) 1-SR-2 Rev 19 (Including version I revision number) Prop osed referen ces to be provided to applicants during examination
Tier#
: NONE -------------------
Group #
Learning Objective: (As available)
KIA #
Question Source: (Note changes or attach parent) New Question History: (Optional-Oue stions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)
RO 1
Question Cognitive Le ve l: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:
22 SRO
ES-401 Sample Written Examination Question Worksheet Examination Ou t line Cross-reference:
                                                                                                      -
295029 High Supp r ession Pool Wtr LviI 5 EA1.04 (10CFR 55.41.7) Ability to ope r ate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL:
295029EA 1.
* RCIC: Plant-Specific I Proposed Question: # 26 Level Tier # Group # KIA # Importance Rating Form ES-401-5 RO 1 2 295029EA 1.04 3.4 During a Unit 2 startup, with power ascension at 20% Reactor Power, a rapid loss of condenser vacuum forces the crew to insert a manual Scram. The following plant conditions exist:
1.04 04
* Reactor Water Level initially lowered to 0 inches and is currently being controlled
* RCIC: Plant-Specific Importance Rating  3.4 I Proposed Question: # 26 During a Unit 2 startup, with power ascension at 20% Reactor Power, a rapid loss of condenser vacuum forces the crew to insert a manual Scram. The following plant conditions exist:
(+) 2 to (+) 51 inches with RCIC AND CRD
* Reactor Water Level initially lowered to 0 inches and is currently being controlled (+) 2 to
(+) 51 inches with RCIC AND CRD
* The MSRVs are being used to control Reactor Pressure AND HPCI was started in pressure control mode
* The MSRVs are being used to control Reactor Pressure AND HPCI was started in pressure control mode
* Suppression Pool Water Level reaches (+) 7 inches Which ONE of the following predicts the current status of RCIC AND the required operator action in accordance with 2-EOI-1, " RPV Control?" RCIC Suction _(1)_ AND the required operator action in accordance with 2-EOI-1, is to _(2)_. A. (1) is aligned to the CST (2) continue RC I C operation in the curren t configuration. C. (1) automatically swaps to the Suppression Pool (2) continue RCIC operation i n the current configuration.
* Suppression Pool Water Level reaches (+) 7 inches Which ONE of the following predicts the current status of RCIC AND the required operator action in accordance with 2-EOI-1, "RPV Control?"
D. (1) automatically swaps to the Supp r ession Pool (2) manually swap RCIC suction path. I propo:ed Answer: I Post-Exam Evaluation Recommendation:
* RCIC Suction _    _(1)_
Accept both "A" and responses  
(ll_AND AND the required operator action in accordance with 2-EOI-1, is to
* *
_(2)_.
* ES-401 Sample Written Examination Question Worksheet E xa mination Outline Cross-reference:
_(2)_.
295029 High Suppression Pool WIt L vi i 5 EA1.04 (10CFR 55.41.7) Ability to ope ra te and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LE V EL:
A. (1) is aligned to the CST (2) continue RCIC operation in the current configuration.
* R C IC: Plant-Specific I Proposed Question: # 26 Level Tier# Group # KIA # Importance Rating Form ES-401-S RO SRO 1 2 -295029EA 1. 04 3.4 During a Unit 2 startup, with power ascension at 20% Reactor Power, a rapid loss of condenser vac uum forces the crew to insert a manual Scram. The following plant conditions exist:
C. (1) automatically swaps to the Suppression Pool (2) continue RCIC operation in the current configuration.
* Reactor Water Level initially lowered to 0 inches and is currently being con trolled (+) 2 to (+) 51 inches with RCIC AND CRD
configuration.
* The MSRVs are being used to control Reactor Pressure AND HPCI was started in pressure control mode
D. (1) automatically swaps to the Suppression Pool (2) manually swap RCIC suction path.     path .
* Suppression Pool Water Level reaches (+) 7 inches Which ONE of the following predicts the current status of RCIC AND the required operator action in accordance with 2-EOI-1, " RPV Control?" RCIC Suction _(ll_AND the required operator action in accordance with 2-EOI-1, is to _(2)_. A. (1) is aligned to the CST (2) continue RCIC operation in the current configuration. C. (1) automatically swaps to the Suppression Pool (2) continue RCIC operation in the current configuration. D. (1) automatically swaps to the Suppression Pool (2) manually swap RCIC suction path. I Answer: I Post-Exam Evaluation Recommendation
I propo~ed propo:ed Answer: I Post-Exam Evaluation                   Accept both "A" and     responses Recommendation:
: Accept both " A" and responses ES-401 Challenge Issue: Sample Written Examination Form ES-401*5 Question Worksheet Answer Key Incorrect
* ES-401                                 Sample Written Examination                                                                                 Form ES-401*5 Question Worksheet Answer Key Incorrect /t Stem Clarity - The stem requests the
/ Stem Clarity -The stem requests the candidate demonstrate knowledge of RCIC operation in accordance with 2*EOI*1. 2*EOI*1 Flowchart step RCIL*4 directs RCIC operation
* Challenge Issue:
[with CST suction if possible}.
candidate demonstrate knowledge of RC/C                                              RCIC operation in accordance with 2*EOI*1.             2-EO/-1. 2-EO/-1      2*EOI*1 Flowchart step RCIL-4                       RCIL*4 directs RCIC operation [with CST suction if possible}. However, 2*EOI RC/C                                                                                                                      2-EOI APPENDIX*SC, INJECTION SYSTEM LINEUP RCIC, APPENDIX-5C,                                                                                            RCtC, the controlling document for placing RC/C                                        RCIC in level control, gives the option in step 11 (see excerpt below) to shift suctions to the Suppression Pool if desired.                  desired.
However, 2*EOI APPENDIX*SC, INJECTION SYSTEM LINEUP RCIC, the controlling document for placing RCIC in level control, gives the option in step 11 (see excerpt below) to shift suctions to the Suppression Pool if desired. L... :r ...... :t 1.5 all.q!l RC:C s*.1ct.ion t.: , the Supp::essic
l:' .
, n
L...  :r. ,.....
* ... OPEN Z-FC'l-71-17, R:::: C POeL :N3D STJCT V ALVE. b. OFEN Z-:: CV-71-B, RC:::; SUPPR POCL O U TS:> SUCT VALVE. c. WHEN ... :-:':V-1 1-17, RC:C SUPPR P".AiL :NED SUCT W * .LVE, and 2-FC" O/-i l-1E. Ro:r C SUPPR wer. Ol: TS!; S U*::;: VAL'.'E, are fully o pen, THEN ... VERIF'l CLOSED :-::C'1-71-19, RC:C CS: Sl'CTION VALVE. The stem did not clarify what portion of 2*EOI*1 to reference
:    _. . ._:t.
[flowchart step RCIL*4 Q! Appendix SC}; only that 2-EOI*1 is the controlling document.
:t      l.5    d~s:.red 1.5 d!!"  s :.re:1 ~o  -'0 all.q!l 1iI:'1.q7'.            s*.1ct.ion t *:*
Also, NO CST level is provided in the stem, forcing the candidate to make an assumption.
RC : : ,'Jct.!.on RC:C                            tt.e
With Suppression Pool level requiring a vety narrow band of control, the candidate(s)thought it was a prudent decision to lower level in the Suppression Pool; thus applying the portion of Appendix SC step 11 (if desired to align RCIC suction to the Suppression Pool). Therefore, with the option to shift suctions in Appendix SC (also within a 2*EOI-1 document) taken in conjunction with the fact that we are now in 2*EOI-2 on High Suppression Pool level, it would be considered a valid operational action that protects containment integrity.
                                                                                                                                    .:, the Supp::essic,n S                          Po~l *
Additionally having 01*71 Precaution  
                                                          *..lpp~e5.l11'i.o;.r.: Olc-:-l,
& Limitation knowledge supports the fact that at +7 uSuppression Pool Level, a suction swap should be performed.
: HE:: ... PERPCRN              tr.*   (e:lc.':'r.Q :
Thus, there are TWO correct answers: uA" and US". Candidate performance:
                                                      ..                 ~-;:"'.:-"1 - 17. It::
3 of 9 selected "8", 6 selected "A" Explanation:
a . OPEN Z-FC'l-71-17,                             :
A CORRECT" Part 1 correct -Normal suction rln8Up for RelC is to the CST and there* no automatic suction swap. Part 2 correct -RCle injection in the EOis is directed to be -with CST SUction if (see procedure excerpt).
R:::: C  SOPP~ POeL SUPO:~    ~'O:::.     :N3:::
ES-401 Sample Written Examination Form ES-401*5 Question Worksheet
:N3D sucr STJCT VALVE.
* C halleng e Issue: Ans w e r Key In c orrect t Stem C larity -The stem requests the candidate demonstrate knowledge of RC/C operation in accordance with 2-EO/-1. 2-EO/-1 Flowchart step RC I L-4 directs RC/C operation
VALVE..
[with CST suction if possible}. However, 2-EOI APPENDIX-5C , INJECTION SYSTEM LINEUP RCtC, the controlling document for placing RC/C in level control , gives the opt i on in step 11 (see excerpt below) to shift suctions to the Suppression Pool if desired.
b . OFEN O                    -i'CV-7 1-B. ac::
* l:'. :., _ .. _:t. l.5 d!!" s:.re:1 -'0 1iI:'1.q7'.
OPEN 2Z-::CV-71-B,                   RC: ::; SUPPR 5UP Pit PO POCLC::" OL  '"7S:::
RC:: ,'Jct.!.on t*:* tt.e Olc-:-l, : HE:: ... PERPCRN tr .* (e:lc.':'r.Q
OUTS:>
: a. OP EN It:::
socr SUCT 'rrLo,,"l.
:N3::: suc r VALVE.. O. O PEN 2-i'CV-7 1-B. ac:: 5UP Pit PO C::" OL'"7S::: socr 'rrLo,,"l. . *. *1f":IEH ... :-F>: v-n-17. R.::: C SUPPR PCO:' ll8:l S U C T V 1.L V I. an d 2-P,;-.... -,!.-:c, ReI": YOC::" Ol'":B: Si:C: 1lAl.'!E. A r e f ,.Jj.ly cp e r., ... VERI FY CLOSED >: C":-'71-19, RC:: CS-: Sr:CTIOti
VALVE..
',,'1U, .. or. The stem did not clarify what portion of 2-EO/-1 to reference
c.
[flowchart step RC I L-4 gr Appendix 5C); only that 2-EO/-1 is the controlling document Also, NO CST level is provided in the stem , forcing the candidate to make an assumption. With Suppression Pool level requiring a vel}' narrow band of control , the candidate(s)thought it was a prudent decision to lower level in the Suppression Pool; thus applying the portion of Appendix 5C step 11 (if desired to align RC/C suction to the Suppression Pool). Therefore , with the option to shift suctions in Append i x 5C (also within a 2-EO/-1 document) taken in conjunction with the fact that we are now in 2-EOI-2 on High Suppression Pool level, it would be considered a valid operational action that protects containment integrity. Additionally hav i ng 01-71 Precaution
                                                      *.      *1f":IEH WHEN ..            :-F>:v -n-17.
& Limitation knowledge supports the fact that at +7 " Suppression Pool Level, a suction swap should be performed.
                                                                            . ... :-:':V-     1 1-17, RC:C  R.::: C SUPPR P".AiL PCO:' ll8:l
Thus , there are TWO correct answers: " A" and " S II. Cand i date perf o rman ce: 3 of 9 s e l e ct e d " 8". 6 sele c ted " A" A. 1 _ -NarmalIIUCIIon
:NED SUCT W   V1.LVI
....., lor RCIC is 10 lhe caT and ... IIUCIIon _. PIr12 _ -RCIC In lhe EOIa is dhdiId 10 be "WillI caT SUctian if JIG II"" e-pllCldln .-rpI) .
                                                                                                *.LVE,. and 2-P,;-....
ES-401 Sample Written Examination Question Worksheet Form ES-401*5 C. INCORRECT:
2-FC"O/-i- ,!.-:c, l -1E. ReI":Ro:rC SUPPR wer.
Part 1 incorrect
suP"~                              SU*::;: 1lAl.'!E Ol:TS!; Si:C:
-Plausibility based on the overwhelming similarities between the HPCI and RCIC Systems; and the frequently confused differences. HPCI automatically swaps suction to the Suppression Pool at +5.25 inches. Part 2 correct -RCIC injection in the EOls is directed to be " with CST Suction if possible" (see procedure excerpt). D. INCORRECT:
YOC::" Ol'":B:                 VAL'.'E,. are Ar e ffully
Parts 1is incorrect and 2 correct as explained in "B". Technical Reference(s)
                                                                                      ,.Jj.ly cpe open, r.,
: 2-01-71 Rev 57, 2-EOI-1 Rev 12, 2-EOI-1 (Attach if not previously provided)
T~N ...
Appendix-5C Rev 4 OPL 171.040 Rev 22 / 042 Rev 19 (Including version / revision number) Proposed references to be provided to applicants during examination
THEN      .. . VERI VERIF'l FY CLOSED :-::C'1-71-19,
: NONE ----------------------
                                                                                                                > : C":-'71 - 19, RC::    RC:C CS-:     Sl'CTION ',,
----Learning Objective: V.B.B , V.B.9. V.B.11. V.B.12 (As available)
CS: Sr:CTIOti            '1U,..or .
Question Source: Question History: Modified Bank # New Last NRC Exam 0610 Audit # 64 (Note changes or attach parent) (Optiona/-
VALVE.
Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)
The stem did not clarify what portion of 2-EO/-1                                          2*EOI*1 to reference
Question Cognitive Level: 10 CFR Part 55 Content: Comments: OPL 171.040 Revision 22 Memory or Fundamental Knowledge Comprehension or Analysis X 55.41 X 55.43 RCIC has no automatic transfer from CST to torus. 01-71 directs transfer of RCIC when HPCI auto transfers on low CST level or high torus level and if RCIC trips on low suction pressure 10" Hg vacuum. *
[flowchart step RCIL-4            RCIL*4 gr          Q! Appendix SC};              5C); only that 2-EOI*1        2-EO/-1 is the controlling document  document. Also, NO CST level is provided in the stem, forcing the candidate to make an assumption. With Suppression Pool level requiring a vel}'                                          vety narrow band of control, the candidate(s)thought it was a prudent decision to lower level in the Suppression Pool; thus applying the portion of Appendix SC step 11 (if desired to align RCIC 5C                                                                    RC/C suction to the Suppression Pool).
* ES-401 Sample Written Examination Question Worksheet Form ES-401-5 C. INCORRE C T: Part 1 incorrect -Plausibility based o n the overwhe lm i ng similarities between the HPCI and Rele Systems: and the frequently confused d ifferences. HPCI automatically swaps suction to the Sup press ion P oo l at +5.25 inches. Part 2 correct -Rel e inj ectio n in the EOls is dire cted to be "w ith CST Suction if (see procedure excerpt). O. INC O RRECT: Parts 1 is incorrect and 2 correct as explained i n Technical Referen ce(s): 2-01-71 Re v 57 , 2-EOI-1 Re v 12 , 2-EOI-1 (Attach If not previously provided)
Therefore, with the option to shift suctions in Appendix                                                Appendix SC     5C (also within a 2*EOI-12-EO/-1 document) taken in conjunction with the fact that we are now in 2-EOI-2                2*EOI-2 on High Suppression Pool level, it would be considered a valid operational action that protects containment integrity.     integrity. Additionally having 01-71                                    01*71 Precaution &        &
Appendix-5C Rev 4 OPL 171.040 Rev 22 1 042 R ev 19 (Including ve r sio n I re v i sio n number) Pr opose d ref e ren c e s t o be provided to applicants during examination:
Limitation knowledge supports the fact that at +7 "uSuppression                                                   Suppression Pool Level, a suction swap should be performed. Thus, there are TWO correct answers: "A"                                  uA" and "US".         S II.
N O NE -------------------
Candidate performance:
Learning Objective: V.B.6, V.B.9 , V.B.ll , V.B.12 (As available)
performance: 3 of 9 selected "8            "8", ". 6 selected "A" Explanation:
Question Source: Modif ied Bank # 0610 Audit # 64 (No te changes or attach parent) Question Hi s to ry: (Op t ional-Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessita t e a detailed review of every question.)
A. CORRECT" Part 1 _correct - NarmalIIUCIIon A                                  Normal suction .....,        rln8Up for   lor RCIC RelC is 10            lhe caT to the     CST and .              . . no automatic there*
Question Cognitive L eve l: 10 C FR Part 55 Co ntent: Co mments: OPL171.040 Revision 22 Memory or Fundam e ntal K n ow ledge Co mprehension or Analysis 55.41 X 55.43 x RCIC has no automatic transfer from CST to torus. 01-71 directs transfer of RCIC when HPCI auto transfers on low CS T level or high torus le ve l and if RCIC trips on low suction pres su re 10" Hg vacuum .
IIUCIIon _ . PIr12 suction swap. Part 2 correct
ES-401 * *
_          RCle ~
* BFN Sample Written Examination Question Worksheet Reactor Cor. Isolation Cooling 2..()1-71 Unlt2 Rev. 0057 Page 22 0176 6.1 Normal Operation (continued)
                                - RCIC      injection In          lhe EOIa in the       EOis is dhdiId directed 10                -with caT to be "WillI          CST SUctionSUctian if JIG POSllble-II""
[5) BEFORE SuppressIOn Pool temperature reaches 95"'F, PLACe RHR in Suppression Pool Cooling Mode. (REFER TO 2-01-74) (5.1) IF Suppression Pool temperature reaches 95&deg;F. THEN ENTER 2-EOI-2 Flowchart
e-(see pllCldln procedure .-rpI) excerpt)..
[5.21 IF Suppression Pool temperature reaches 105"F, THEN SHUT DOWN RCIC System operatIOn and return to Standby ReadIness REFER TO Step 61[12] or 6 1[13J. [6) MAINTAIN Suppression Pool level between *5.5 and -2 in. (REFER TO 2-01-74.)
* ES-401                                     Sample Written Examination                                             Form ES-401-5 ES-401*5 Question Worksheet C. INCORRECT:
[7] MONITOR CST 2 LEVEL, 2-Ll-2-161A, on Panel 2-9-6. [S} IF ANY of the following conditions occur while RCIC IS injecting into the RPV:
INCORRECT: Part 1 incorrect - Plausibility based on              on the overwhelming similarities between the HPCI and Rele      Systems: and the frequently confused differences. HPCI automatically swaps suction to the RCIC Systems; Suppression Pool Pool at +5.25 inches. Part 2 correct - Rele      RCIC injection injection in the EOls is directed to be "with CST Suction if poss    ible~ (see procedure excerpt) .
* Suppression Poolieve!
possible" O. INCORRECT: Parts 1is D. INCORRECT:                  1is incorrect and 2 correct as explained in ~"B". B~ _
reaches +7 in., OR
Technical Reference(s):
* HPCl suctIOn auto transfers to suppressiOn pool, OR
Reference(s):         2-01-71 Rev 57  57,, 2-EOI-1 2-EOI- 1 Rev 12, 12, 2-EOI-1 2- EOI-1        (Attach Ifif not previously provided)
* RCIC Turbine trips on pump low suction pressure, THEN PERFORM the following steps to transfer RCIC Suction to the Suppression Pool: (8.1] OPEN RCIC SUPPR POOL INBD SUCT VALVE, 2-FCV-71-17.
Appendix-5C Rev 4 OPL 171.040 Rev 22 /1042 Rev 19                          (Including    version I/ revision (Including version      revision number)
[8.2] OPEN RCIC SUPPR POOL OUTeD SUCT VALVE, 2-FCV-71-18.
Proposed references Proposed    references to be provided to applicants during examination:examination:       NONE
[83] WHEN RetC SUPPR POOL INBD SUCT VAlVE, 2-FCV-71-17, and the RCIC SUPPR POOL OUTSD SUCT VALVE, 2..fCV-71-18.
                                                                                            --------------------------
are fully open, THEN VERIFY CLOSED RCIC CST SUCTION VALVE, 2*FCV.71-19
                                                                                            -------------------
[J [J [J [J [J o [J o o Form ES-401-5 ES-401 * *
Learning Objective:               V. B.6, V.B.9.
* BFN Sample Written Examination Question Worksheet Reactor Cor. Isolation Cooling 2..()1-71 Unlt2 Rev. 0057 Page 22 0176 6.1 Normal Operation (continued)
V.B.B,   V.B.9, V.B.11.
[5) BEFORE SuppressIOn Pool temperature reaches 95"'F, PLACe RHR in Suppression Pool Cooling Mode. (REFER TO 2-01-74) (5.1) IF Suppression Pool temperature reaches 95&deg;F. THEN ENTER 2-EOI-2 Flowchart
V. B.ll , V.B.12          (As available)
[5.21 IF Suppression Pool temperature reaches 105"F, THEN SHUT DOWN RCIC System operatIOn and return to Standby ReadIness REFER TO Step 61[12] or 6 1[13J. [6) MAINTAIN Suppression Pool level between *5.5 and -2 in. (REFER TO 2-01-74.)
Question Source:
[7] MONITOR CST 2 LEVEL, 2-Ll-2-161A, on Panel 2-9-6. [S} IF ANY of the following conditions occur while RCIC IS injecting into the RPV:
Modified Bank #            0610 Audit # 64                  (Note changes or attach parent)
* Suppression Poolieve!
New Question History:                    Last NRC Exam (Optional- Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to (Optiona/-
reaches +7 in., OR
provide the information will necessitate a detailed review of every question.)
* HPCl suctIOn auto transfers to suppressiOn pool, OR
Question Cognitive Level:Level:          Memory or Fundamental Knowledge
* RCIC Turbine trips on pump low suction pressure, THEN PERFORM the following steps to transfer RCIC Suction to the Suppression Pool: (8.1] OPEN RCIC SUPPR POOL INBD SUCT VALVE, 2-FCV-71-17.
* 10 CFR Part 55 Content:
[8.2] OPEN RCIC SUPPR POOL OUTeD SUCT VALVE, 2-FCV-71-18.
Comments:
[83] WHEN RetC SUPPR POOL INBD SUCT VAlVE, 2-FCV-71-17, and the RCIC SUPPR POOL OUTSD SUCT VALVE, 2..fCV-71-18.
55.41 55.43 Comprehension or Analysis X
are fully open, THEN VERIFY CLOSED RCIC CST SUCTION VALVE, 2*FCV.71-19
x X
[J [J [J [J [J o [J o o Form ES-401-5 ES-401 / .. .... ' ... ... .... t-.. Sample Written Examination Question Worksheet
OPL OPL171 171.040
... .... .. ... "'\ ,. '-"'-' CAUTION I #2 PUMP NPSH AND VORTEX LIMiTS I #3 ELeVATED SUPPR CHMSR PRESS MAY TRIP RCIC I #6 HPCI OR RCIC SUCTION TEMP ABO\l&#xa3; 140 'F !tESTOIIiE AND MAINTAIN RPV WA TER LVL BETWEEN +2 IN. AND +51 IN. WITH ONE OR MORE OF T11E INJ SOURCES: INJSOURCE APPX INJ PRESS CNDSANDFW SA 1250 PS4G eRD 58 1640 PS4G RCIC. 5C 1240 PS4G WITH CST SUCTION IF POSSIBLE HPCI. 50 1240 PS4G CST SUCTION IF POSSIBLE eNOS SA 480 PSIG CS &l.6E 330 PSiG LPGI 68.6C 320 PSIG RCJL-4 " CAN NO L RPV WATER L VL BE RESTORED AND MAINTAINED
                    .040 Revision 22 RCIC has no automatic transfer from CST to torus. 01-71 directs transfer of RCIC when HPCI auto transfers on low CST level or high torus level and if RCIC trips on low suction pressure 10" Hg vacuum. vacuum .
.. A80\I&#xa3; +2IN. RCIL*S YESL I ... ... .... .....
* ES-401                        Sample Written Examination                            Form ES-401-5 Question Worksheet
Form ES-401-5 I I I I L L .. ... '\ MAINT AI" RPV WATER l VL ABO\I&#xa3; *162 IN. . .. ES-401 *
* 6.1 BFN Unlt2 Reactor Cor. Isolation Cooling Normal Operation (continued) 2..()1-71 Rev. 0057 Page 22 0176
* I I I Sample W r itten Examination Question Worksheet CAUT'tON .2 PO .... P t.PSH"'!>(l VORTEX l!MrtS .3 ElEVA TEO SUPPA CHM8R PRESS MAY TRIP RelC #. HPCI 0f'I RelC SUCTION lEW ASO\IE l.o'F _n oa.Nro .... INT .. IN RPV WATER LVL 8E't'MOtN
[5)    BEFORE SuppressIOn Pool temperature reaches 95"'F, PLACe RHR in Suppression Pool Cooling Mode.
.2 IN .o.NO.M IN WITH ONE OR MORE Of 111&#xa3; FDllOIMNO IN.J SOURCES: IIiJ SOURCE '" , ... ,," CNOS"NOFW
(REFER TO 2-01-74)                                            [J (5.1)      IF Suppression Pool temperature reaches 95&deg;F. THEN ENTER 2-EOI-2 Flowchart                                [J
'"
[5.21      IF Suppression Pool temperature reaches 105"F, THEN SHUT DOWN RCIC System operatIOn and return to Standby ReadIness REFER TO Step 61[12] or 6 1[13J.                      [J
CR O ,. 160W PSIG RelC. '" 1240PS/G WITH CST SUCTION IF POSSIBLE """. '" ,Z*OPSIG WITH CS T SUC T ION IF POSSl8 l E CNO' M .., ''''' C' 60 , BE 330 PSiG """ '". oc 320 PSIG ,"'-. """ NO L RPVW"TEl!L\lL8E RESIOREO ... NO wo.INTNNE.D ASO'" +2IN.
[6)    MAINTAIN Suppression Pool level between *5.5 and -2 in.
"'''L I 'CA' Form ES-401-5 I I I L L MAINTAIN RP\!wATE,R.
(REFER TO 2-01-74.)                                          [J
LVi.. A80VE -182"'.
[7]    MONITOR CST 2 LEVEL, 2-Ll-2-161A, on Panel 2-9-6.            [J
ES-401 Sample Written Examination Question Worksheet Form ES-401*5 2-ECI APPENDIX-5C Rev. 4 Pae 3 of 3 11. IF .**** I1: is desired to ali gn ReIC . 1:.l on 1:0 1:he Suppression P 1, THEN *** p 'the fol1o r tlinq: a. 17, ReTe SUC! VAL b. OPEN" 2-FCV-71-18, Rele sueT VALVE. c. L INBD ?R POOL ;,;m IN3 D : C are NOIE.: Step 12.b 5 t be p=r f ed p!' t ly foll . ing 5 1: l2.a to avoi d loss of pa th. 12. T';<' ***** It is desired t.o align RCIC suct:.on to i:he Condensate Tank, THEN *.. PERFORM t.he following:
[S}    IF ANY of the following conditions occur while RCIC IS injecting into the RPV:
: a. CLOSE 2-:CV-71-:7, RCIC SIJPPR POOL :N3D SIJCT VAL'IE. b.
2-FCV-7 1-17, RCIC SUPPR ?OOL INBD SlJeT VJ....LVE starts closed, OPEN 2-FC/-71-19, ReIC CST SUCTION VALVE. c. CLOSE ::-fCV-71-::'B, RClC SUPPR POOL OUTSD SeCT V1>.l. VE . LAST PAGE .... ES-401 * *
* Sample Written Examination Question Worksheet Form ES-401-S 2-E CI APPENDIX-5G Rev. 4 PaGe 3 of 3 11. IF ..... It is to ali qn ReIe to the P oo l, THEN ... PERFORM fol l ow1nq: I!II. aP'&#xa3;5 2-F CV-71-17, RCIC stiP P R POOL INBD suer VAL V!. b. OPEN 2-fCV-71-1B , Rcre S PPR POOL OUTED sue r V ALVE. c. WHEN *** 2-l'CV-1l-1 i, Re IC S UP PR POOL INB D suer VAL\rE, and 2-FCV-71-18, Re!C SUPPR POOL OUlBD $OCT VALVE , are !ul1.,y !"'!iEN VEIUPY Cl.OSED Z-fCV-71-19, R C te CST SUc:nOli VA!. .c. NOtE: 12.b ous t be pe r!orced p:c=pt ly foll ow ing S tep to avoi d loss o f pa th. 11. 1= _ ... ' I t d es ir ed to align R C I e t o t h e Gc r.densa'te 51;.o r age 'lHEl J ..* PERFORM :: h e f o ll owing: a. CLOSE 2-: C'i-il-:'
7 , RCrC SCPPR POOL Sr;CI V AL 'IE. ::rE N 2-F CV-7 1-17 , R Cre SUFPR ?OO;. rNSD SC C! V]..L'lE st arts -:rave lin q clcsed, OPEN R C I C CS T 5UC I!O N V ll V E. c. CWSE :-:CV-7 1-':'3, RCC S r.;PPR POOL OU'IBD scer VA!. VE ' lASI' ?AG!!:
ES-401 Sample Written Examination Question Worksheet Examination Outline Cross-reference:
241000 Reactorrrurbine Pressure Regulator A1.01 (10CFR 55.41.5) Ability to predict and/or monitor changes in parameters associated Level Tier # Group # with operating the REACTORITURBINE PRESSURE REGULATING KIA # SYSTEM controls i ncludi n g:
* Reactor pressure Importance Rating I Proposed Quest i on: # 59 Unit 3 is at 93% Reactor Power. Which ONE of the following completes the statements?
For this power level, EHC Pressure Set is nominally set to _(1)_ psig. Form ES-401-5 RO 2 2 241 OOOA 1.01 3.9 IF ONE Turbine Control Valve were to fail OPEN, then Reactor Pressure, upon stabilizing, would be_(2)_. A. (1) 955 (2) lowe r B. (1) 1036 (2) lower D. (1) 1036 (2) the same Proposed Answer: A Post-Exam Evaluation Recommendation:
Accept both "A" and responses
* *
* ES-401 Sample Written Examination Question Worksheet E xami nation Outline Cross-reference
: 2 4 1000 Re acto rfTurb!ne Pressure Regulat or A1.01 (10C FR 55.41.5) Ability to predict and/or mon i tor changes in parameters assoc i ated wit h operating the REACTORrrURBINE PRESSURE REGULATING SYSTEM controls in clu ding:
* React o r pressure I Pr o posed Question: # 59 Unit 3 is at 93% Reactor Power. Which ONE of the following completes the statements?
Le vel Tier # Group # KIA # Importance Rating For this power level , EHC Pressure Set is nominally set to _(1)_ psig. Form ES-401-5 RO 2 2 SRO -241 OOOA 1.01 3.9 IF ONE Turbine Control Valve were to fail OPEN , then Reactor Pressure , upon stabilizing , would be_(2)_. A. (1) 955 (2) lower B. (1) 1036 (2) lower D. (1) 1036 (2) the same Proposed Answer: A Post-Exam Evaluation Recommendation
: Accept both " A" and. responses ES-401 Challenge Issue: Sample Written Examination Question Worksheet Form ES-401-5 The correct answer originally submitted to the NRC by the BFN Exam Team was IIC" based on theoretical documented system response.
Operations personnel performing exam validation indicated that there was actual plant OE which indicated pressure would lower a small amount for the conditions identified in the question.
The scenario was run on Unit 3 simulator and pressure lowered a small amount (approximately
.5%). If this were an analog display, versus digital, there is a high probability that it wouldn't be noticeable.
But, based on validation input, the correct answer was changed to A. There are several references which would lead a candidate to conclude that pressure would return to setpoint after the perturbation; including FSAR sections 7.11 and 11.2, EHC Controls Lesson Plan OPL 171.228, and Unit 3 Simulator Malfunction Cause & Effects Manual. OPL 171.228 ELECTRO-HYDRAULIC CONTROL LOGIC Steam Pressure Control maintains either the Header Pressure or the Reactor Pressure at a pressure reference setpoint Steam pressure control, as a reactor pressure controlling parameter is utilized at all times , either by the Bypass Valve Control or the Turbine Control. The system controls reactor pressure such that a change of 1 psig in reactor pressure causes a change of 1 .1% in steam flow demanded which the system converts to va l ve opening demanded and sends to the Turbine Control and/or Bypass Control valves (3.3% per psig when selected to control on header pressure). As reactor power is i ncreased, reactor pressure increases and as pressure increases the EHC system opens the Turbine Control valves or Bypass Control valves to use the extra steam produced by the increased power. FSAR 11.2 TURBINE-GENERATOR I During normal operations , the steam admitted to the turbine is controlled by the pressure regulator which maintains essentially constant pressure at the turbine inlet, thus controlling reactor vessel pressure.
The EHC system pressure regulator can control reactor pressure directly.
The ability of the station to follow system load depends on adjustment of reactor power level. This is accomplished by changing Reactor Coolant Recirculation System flow or repositioning of control rods. FSAR 7.11 PRESSURE REGULATOR AND TURBINE-GENERATOR CONTROL The pressure regulation function of the turbine control system is designed to manipulate turbine control valves and turbine bypass valves , individually or in parallel, to maintain reactor pressure within a narrow range of the pressure setpoint as reactor power varies from 0 ES-4Dl
* Challenge Issue: *
* Sample Written Examination Question Worksheet Form ES-4DI-5 The correct answer originally submitted to the NRC by the BFN Exam Team was "C" based on theoretical documented system response.
Operations personnel performing exam validation indicated that there was actual plant OE which indicated pressure would lower a small amount for the conditions identified in the question.
The scenario was run on Unit 3 simulator and pressure lowered a small amount (approximately
.5%). If this were an analog display, versus digital, there is a high probability that it wouldn't be noticeable.
But, based on validation input, the correct answer was changed to A. There are several references which would lead a candidate to conclude that pressure would return to setpoint after the perturbation; including FSAR sections 7.11 and 11.2, EHC Controls Lesson Plan OPL 171.228, and Unit 3 Simulator Malfunction Cause & Effects Manual. OPL 171.228 ELECTRO-HYDRAULIC CONTROL LOGIC Steam Pressure Control ma i nta i ns either the Header Pressure or the Reactor Pressu r e at a pressure reference setpoiO l Steam pressure control , as a reactor pressure controlling parameter is utilized at all times , either by the Bypass Valve Control or the Turbine Control. The system controls reactor pressure such that a change of 1 psig in reactor pressure causes a change of 1.1 % in steam fiow demanded which the system converts to valve opening demanded and sends to the Turbine Control and/or Bypass Control valves (3.3% per psig when selected to control on header pressure).
As reactor power is increased , reactor pressure increases and as pressure increases the EHC system opens the Turbine Control valves or Bypass Control valves to use the extra steam produced by the increased power. FSAR 11.2 TURBINE-GENERATOR I During norma l operations , the steam admitted to the t urbine is controlled by the pressure regulator wh i ch mainta i ns essentially constan t pressure a t the turbine i nle t, thus controlling reactor vessel pressure. The EHC system pressure regulator can control reactor pressure directly. The ability of the station to follow system load depends on adjustment of reactor power level. This is accomplished by changing Reactor Coolant Recirculation System flow or repOSitioning of control rods. FSAR 7.11 PRESSURE REGULATOR AND TURBINE-GENERATOR CONTROL The pressure regulation function of the turbine control system is designed to man i p u late turbine control valves and turb i ne bypass valves , ind i vidually or in pa r allel , t o maintain reactor pressure within a narrow range of the pressure setpo l nt as reactor power varies from 0 ES-401 Sample Written Examination Question Worksheet percent to 1 00 percent nuclea r boiler rated flow. Form ES-401*5 According to the Simulator Cause & Effects Manual: BROWNS FERRY UNIT 3 MALFUNCTION CAUSE AND EFFECTS 06/14/06 . REV 3 TC08 CONTROL VALVE POSITION UNIT FAILURE: A) FCV 1-75 EFFECTS: THIS MALFUNCTION WILL CAUSE THE SELECTED CONTROL VALVE TO BE POSITIONED AS DEMANDED BY THE INSTRUCTOR.
THE POSITION INDICATOR FOR THE CONTROL VALVE WOULD REFLECT THE POSITION CHANGE. ALSO, THE RECORDED TOTAL CONTROL VALVE POSITION COULD RESPOND TO THE VALVE POSITION CHANGE IF THE GENERATOR BREAKER IS CLOSED AND THE OTHER CONTROL VALVES ARE NOT ABLE TO COMPENSATE.
THE EHC SYSTEM PRESSURE CONTROL UNIT WILL RESPOND BY POSITIONING THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES IN RESPONSE TO ANY PRESSURE CHANGE. I F THE SELECTED VALVE IS POSITIONED TO A LOWER VALU E THAN REQUIRED BY THE PRESSURE CONTROL UNIT , THE OTHER CONTROL VALV E S ANDIOR BYPASS VALVES WILL OPEN TO COMPENSA T E AS PRESSURE INCREASES.
I F THE CONTROL VAlVE IS POSITIONED TO A HIGHER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT , THE O THER CONTROL VALVES AND/OR BYPASS VALVES WILL CL OSE TO COMPENSATE AS PRESSURE DECREASES. IF SYSTEM VALVE POSIT I O N ING I S LIMITED BY ANY OTHER MECHANISM (Le. MAX COMBINED FLOW LIMITER , CONTROL VALVES FUL L Y OPEN , ETC.), THE SYSTEM RESPONSE WOULD B E ALTERED AND A REACTOR PRESSURE CHANGE AND IT S ACCOMPANYING EFFECTS ON POWER COULD RESULT. Based on these references the candidate would reasonably expect the EHC System to maintain essentially constant pressure at the turbine inlet, thus controlling reactor vessel pressure.
Therefore, following failure of ONE Turbine Control Valve open, the candidate would conclude that the remaining valves would close to compensate for the pressure decrease ES-401 *
* Sample Written Examination Question Worksheet percent to 100 percent n uclea r boiler rated flow. Form ES-401-5 According to the Simulator Cause & Effects Manual: BROWNS FERRY UNIT 3 MALFUNCTION CAUSE AND EFFECTS 06/14/06 -REV 3 TCOS CONTROL VALVE POSITION UNIT FAILURE: A) FCV 1-75 EFFECTS: THIS MALFUNCTION WILL CAUSE THE SELECTED CONTROL VALVE TO BE POSITIONED AS DEMANDED BY THE INSTRUCTOR.
THE POSITION INDICATOR FOR THE CONTROL VALVE WOULD REFLECT THE POSITION CHANGE. ALSO , THE RECORDED TOTAL CONTROL VALVE POSITION COULD RESPOND TO THE VALVE POSITION CHANGE IF THE GENERATOR BREAKER IS CLOSED AND THE OTHER CONTROL VALVES ARE NOT ABLE TO COMPENSATE.
THE EHC SYSTEM PRESSURE CONTROL UNIT WILL RESPOND BY POSITIONING THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES IN RESPONSE TO ANY PRESSURE CHANGE. IF THE SELECTED VALVE IS POSITIONED TO A L OWER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT , THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES WILL OPEN TO COMPENSATE AS PRESSURE INCREASES. IF THE CONTROL VALVE IS POSITIONED TO A HIGHER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT , THE OT HE R CONTROL VALVES ANDIOR BYPASS VALVES WILL CLOSE TO COMPENSATE AS PRESSURE DECREASES. IF SYSTEM VALVE POSIT I ONING I S LIMITED BY ANY OT HER MECHANISM (i.e. MAX COMBINED FLOW LIMITER , CONTROL VALVES FULLY OPEN , ETC.), THE SYSTEM RESPONSE WOULD BE ALTERED AND A REACTOR PRESSURE CHANG E AND ITS ACCOMPANYING EFFECTS ON POWER COULD RESULT. Based on these references the candidate would reasonably expect the EHC System to maintain essentially constant pressure at the turbine inlet , thus controlling reactor vessel pressure.
Therefore, following failure of ONE Turbine Control Valve open, the candidate would conclude that the remaining valves would close to compensate for the pressure decrease ES-401
* Candidate Performance:  
*
*
* Sample Written Examination Form ES-401-5 Question Worksheet and Reactor Pressure would stabilize at the same pressure.
* Suppression Poolieve! reaches +7 in., OR                o
* HPCl suctIOn auto transfers to suppressiOn pool, OR      [J
* RCIC Turbine trips on pump low suction pressure,    THEN PERFORM the following steps to transfer RCIC Suction to the Suppression Pool:
(8.1]      OPEN RCIC SUPPR POOL INBD SUCT VALVE, 2-FCV-71-17.                                          o
[8.2]      OPEN RCIC SUPPR POOL OUTeD SUCT VALVE, 2-FCV-71-18.
[83]      WHEN RetC SUPPR POOL INBD SUCT VAlVE, 2-FCV-71-17, and the RCIC SUPPR POOL OUTSD SUCT VALVE, 2..fCV-71-18. are fully open, THEN VERIFY CLOSED RCIC CST SUCTION VALVE, 2*FCV.71-19                                            o
* ES-401                                          Sample Written Examination                                                                      Form ES-401-5 Question Worksheet
            /
                    .....                          .......
                                                                          "'\
        ~ ..
                                                            '-  "'-    '
                                                                              ,.
CAUT'tON CAUTION                                          I I .2#2        PUMP PO .... P NPSH    AND VORTEX LIMiTS t.PSH"'!>(l                    l!MrtS I
        ....
I .3    #3    ElEVA ELeVATED  TEO SUPPR SUPPA CHM8R    CHMSR PRESS MAY TRIP RelC        RCIC I
I#.    #6    HPCI OR  0f'I RelC RCIC SUCTION lEW                ASO\IE 140 TEMP ABO\l&#xa3;      l.o 'F
                                                                                                  'F I  L L
                                                                              ~
_n oa. Nro
                                !tESTOIIiE                  .... INT .. IN RPV WA AND MAINTAIN                      WATER TER LVL BETWEEN 8E't'MOtN
                                .2 IN
                                +2      .o.NO.M IN. AND      +51 IN IN. WITH ONE OR MORE OF                  T11E FOLLO~NG Of 111&#xa3;  FDllOIMNO INJ SOURCES:
IN.J SOURCES :
        ~t.                          IIiJ  SOURCE INJSOURCE                                    APPX
                                                                                    "'~                '" ,...,,"
INJ PRESS CNDSANDFW CNOS"NOFW                                                                    '~PSIG 1250  PS4G
                                                                                      ,.'"
SA CRO eRD                                                        58                1640 160W PS4G PSIG
                ...
                '
* RCIC.
RelC.                                                                        1240PS/G 5C                1240  PS4G
                ...        WITH CST SUCTION IF POSSIBLE
                                                                                      '"
                            """ .
HPCI.
50                ,Z*OPSIG 1240  PS4G
                            ~TH WITH  CS CSTT SUCTION IF POSSIBLE    POSSl8 l E
                                                                                      '"
        ~t.                eNOS CNO'                                                      SA M
                                                                                                          .., '''''
480 PSIG
* CS C'                                                      &l.
60, 6EBE              330 PSiG LPGI                                                    68.6C                320 PSIG
                    ,"'-.
RCJL-4
                            """                                                      '". oc                            L
                                                                              "
        ....
RESTORED AND RESIOREO CAN
                                                                            """
RPV WATER L VL BE RPVW"TEl!L\lL8E
                                                                          ... NO MAINTAINED A80\I&#xa3; ASO'"
                                                                            +2IN .
wo.INTNNE.D NO L  L    ~
                                                                                                                    ..                  ..... '\
RCIL*~
RCIL*S
                                                                                                                                              ,~
                                                                                  "''' L YESL t-..      .......                          ........                                                I                    RPV WATER lLVi..
MAINT AI" RP\!wATE,R.
MAINTAIN              VL ABO\I&#xa3; A80VE *162 IN.
                                                                                                                                                            -182"'.
                                                                                                                'CA' RC/l~
                                                                                                                                              ...
 
. .. .
ES-401                          Sample Written Examination                                                          ES-401*5 Form ES-401-S Question Worksheet
* APPENDIX-5C 2-ECI APPENDIX-      5G Rev. 4 Pae 3 of 3 PaGe 11 .
: 11. IF .....
                        .**** It              de~ired to aliqn I1: is desired                  align ReIC ReIe    ~c~      on
                                                                                        . 1:.lon  to 1:he 1:0  the Suppression Suppre      s~ion Pool,  P 1, THEN ..  ***. PERFORM p              ~he fol1o
                                                  'the            rtlinq:
fol l ow1nq:
: a. aP'&#xa3;5 2-I!II.          2- ~      17, ReTe FCV-71-17,          RCIC stiP PR POOL      L INBD suer VAL SUC!    VALV!    ~.
: b. OPEN        2-fCV-71-1B, Rele OPEN" 2-FCV-71-18,                Rcre S PPR  ?R POOL OUTED  ;,;m suer VALVE.
sueT
: c.      WHEN *** 2- l'CV- 1l - 1i, ReIC SUPPR POOL INBD                    IN3D suer VAL\rE, and 2- FCV-71-18, Re!C                :C SUPPR POOL OUlBD $OCT VALVE, are
                                                            !ul1.,y  ~,
                                          !"'!iEN          VEIUPY Cl.OSED Z- fCV 19, RCte CST SUc:nOli VA!. .c .
NOIE.:
NOtE:        Step S~ep 12.b    12 . b oust 5t be p=r  per !f orceded p:c=ptly p !'    t ly foll owing
                                                                                                        . ing Step 5 1:
12.~ to avoid loss of l2.a                                            ct i o n pa of ~ uuction        th..
path
: 12. 1=
: 11.        _*...
T';<' *  * * *' It I t is ~5 des    ir ed t.o desired        to align RCIC  RCI e gsuct:.on uct~o n to  t o i:he t he Condensate 51;.or Gcr.densa'te          S~orage age Tank, T a~k ,
*
                'lHElJ THEN ..*  *.. PERFORM ::h        t.hee ffollowing:
o ll owing:
a.
: a.      CLOSE 2-:CV-71-:7, 2- : C'i-il-:' 7 , RCICRCrC SIJPPR SCPPR POOL :N3D    :~J 3 D Sr;CI SIJCT VAL VAL'IE.'IE.
: b.      i\~HEU            2-FCV-7 1- 1-17, 17 , RCIC RCre SUPPR      ?OOL rNSD SUFPR ?OO;.        INBD SCC! VJ....LVE SlJeT  V]..L'lE st  arts ~raveling starts      -:rave linq clcsed, closed,
::rEN            OPEN 22-FC/-71-19,
                                                                      - fC~-7~-19 , ReIC          CSTT SUCTION RCI C CS      5UC I !ON VALVE.
Vl lVE.
c.
: c.      CLOSE      :-:CV-7 1 - ':' 3, RClC CWSE ::-fCV-71-::'B,              RCC SUPPRSr.;PPR POOL OUTSDOU'IBD scer SeCT      VA!.VE .'
V1>.l.
LAST    PAGE lASI' ?AG!!:
* ES-401                                      Sample Written Examination                        Form ES-401-5 Question Worksheet
* Exami nation Outline Cross-reference:
Examination 241000 Reactorrrurbine A1 .01 (10CFR A1.01    (10C FR 55.41.5)
Cross-reference:
ReactorfTurb!ne Pressure Regulator 55.41 .5)
Ability to predict and/or monitor changes in parameters associated with with operating the REACTORrrURBINE REACTORITURBINE PRESSURE REGULATING Level Tier #
Group #
KIA ##
KIA RO 2
2 SRO
                                                                                                          -
241 OOOA 1.01 SYSTEM controls including:
* Reactor pressure Reactor                                                          Importance Rating    3.9 I Proposed Question:
Question: # 59 Unit 3 is at 93% Reactor Power.
Which ONE of the following completes the statements?
For this power level, level, EHC Pressure Set is nominally set to _(1)_
_ (1)_ psig.
psig .
IF ONE Turbine Control Valve were to fail OPEN        OPEN,, then Reactor Pressure, Pressure, upon stabilizing, stabilizing, would be_(2)_.
A.
A. (1) 955 (2) lower B. (1) 1036
*        (2) lower D. (1) 1036 D.
(2) the same Proposed Answer: A Post-Exam Evaluation                  Accept both "A" and and. responses Recommendation:
Recommendation:
* ES-4Dl ES-401              Sample Written Examination                                    ES-4DI-5 Form ES-401-5 Question Worksheet
* Issue:
Challenge Issue: The correct answer originally submitted to the NRC by the BFN Exam Team was "C"    IIC" based on theoretical documented system response. Operations personnel performing exam validation indicated that there was actual plant OE which indicated pressure would lower a small amount for the conditions identified in the question. The scenario was run on Unit 3 simulator and pressure lowered a small amount (approximately
                    .5%). If this were an analog display, versus digital, there is a high probability that it wouldn't be noticeable. But, based on validation input, the correct answer was changed to A.
There are several references which would lead a candidate to conclude that pressure would return to setpoint after the perturbation; including FSAR sections 7.11 and 11.2, EHC Controls Lesson Plan OPL 171.228, and Unit 3 Simulator Malfunction Cause & Effects Manual.
OPL 171.228 171 .228 ELECTRO-HYDRAULIC CONTROL LOGIC Steam Pressure Control maintains either the Header Pressure or the setpoiOl Steam pressure Reactor Pressure at a pressure reference setpoint control , as a reactor pressure controlling parameter is utilized at all control,
* times, either by the Bypass Valve Control or the Turbine Control.
The system controls reactor pressure such that a change of 1 psig in reactor pressure causes a change of 1        .1%
1.1% in steam flow fiow demanded which the system converts to valve opening demanded and sends to the Turbine Control and/or Bypass Control valves (3        .3% per psig (3.3%
when selected to control on header pressure).
pressure). As reactor power is increased, reactor pressure increases and as pressure increases the increased, EHC system opens the Turbine Control valves or Bypass Control valves to use the extra steam produced by the increased power. power.
FSAR 11.2 TURBINE-GENERATOR I
During normal operations, the steam admitted to the turbine is controlled by the pressure regulator which maintains essentially constant pressure at the turbine inlet, thus controlling reactor vessel pressure. The EHC system pressure regulator can control reactor pressure.
pressure directly.
directly. The ability of the station to follow system load depends on adjustment of reactor power level. This is accomplished by changing Reactor Coolant Recirculation System flow or repOSitioning of control rods .
repositioning FSAR 7.11 PRESSURE REGULATOR AND TURBINE-GENERATOR
* CONTROL The pressure regulation function of the turbine control system is designed to manipulate turbine control valves and turbine bypass valves, individually or in parallel, parallel, to maintain reactor pressure within a narrow range of the pressure setpolnt setpoint as reactor power varies from 0
 
ES-401    Sample Written Examination                      Form ES-401*5 ES-401-5 Question Worksheet percent to 100 percent nuclear boiler rated flow.
flow.
According to the Simulator Cause & Effects Manual:
BROWNS FERRY UNIT 3 MALFUNCTION CAUSE AND EFFECTS 06/14/06 .- REV 3 TC08 CONTROL VALVE POSITION UNIT FAILURE:
TCOS                                        FAILURE:
A) FCV 1-75 EFFECTS:
THIS MALFUNCTION WILL CAUSE THE SELECTED CONTROL VALVE TO BE POSITIONED AS DEMANDED BY THE INSTRUCTOR. THE POSITION INDICATOR FOR THE CONTROL VALVE WOULD REFLECT THE POSITION CHANGE. ALSO,        ALSO, THE RECORDED TOTAL CONTROL VALVE POSITION COULD RESPOND TO THE VALVE POSITION CHANGE IF THE GENERATOR BREAKER IS CLOSED AND THE OTHER CONTROL
* VALVES ARE NOT ABLE TO COMPENSATE. THE EHC SYSTEM PRESSURE CONTROL UNIT WILL RESPOND BY POSITIONING THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES IN RESPONSE TO ANY PRESSURE CHANGE.
IF THE SELECTED VALVE IS POSITIONED TO A LOWER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT, THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES WILL OPEN TO COMPENSAT COMPENSATE  E AS PRESSURE INCREASES.
IF THE CONTROL VALVE VAlVE IS POSITIONED TO A HIGHER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT, THE OTHER CONTROL VALVES AND/OR  ANDIOR BYPASS VALVES WILL CLOSE TO COMPENSATE AS PRESSURE DECREASES.
IF SYSTEM VALVE POSITIONING IS LIMITED BY ANY OTHER (Le. MAX COMBINED FLOW LIMITER, CONTROL MECHANISM (i.e.
VALVES FULLY OPEN, ETC.), THE SYSTEM RESPONSE WOULD BE ALTERED AND A REACTOR PRESSURE CHANGE AND ITS ACCOMPANYING EFFECTS ON POWER COULD RESULT.
Based on these references the candidate would reasonably
* expect the EHC System to maintain essentially constant pressure at the turbine inlet, inlet, thus controlling reactor vessel pressure. Therefore, following failure of ONE Turbine Control Valve open, the candidate would conclude that the remaining valves would close to compensate for the pressure decrease
 
ES-401                      Sample Written Examination                       Form ES-401-5 Question Worksheet
* and Reactor Pressure would stabilize at the same pressure.
This makes both tA' and te' a correct response.
This makes both tA' and te' a correct response.
8 of 9 candidates selected 'C' as the correct answer. 1 candidate selected 'A' and this candidate was the SRO Upgrade. ES-401
8 of 9 candidates selected 'C' as the correct answer. 1 candidate Candidate Performance:
* Candidate Performance:
selected 'A' and this candidate was the SRO Upgrade.
*
*
*
* Sample Written Examination Form ES-401-5 Question Worksheet and Reactor Pressure would stabilize at the same pressure.
 
This makes both tA' and te' a correct response.
, .
8 of 9 candidates selected 'C' as the correct answer. 1 candidate selected 'A' and this candidate was the SRO Upgrade.
ES-401                                    Sample Written Examination                                           Form ES-401-5 ES-401*5 Question Worksheet
ES-401 Technical Reference(s)
* Technical Reference(s)
: Sample Written Examination Question Worksheet 2-GOl-100-1A Rev 139 Form ES-401-5 (Attach if not previously provided)
Reference(s)::          2*GOI*100*1A 2-GOl-100-1A Rev 139                                     (Attach if not previously provided)
OPL 171.228 Rev 3 (Including version I revision number) Proposed references to be provided to applicants during examination
OPL 171.228 Rev 3                                         (Including version I revision number)
: NONE ------------------
Proposed references to be provided to applicants during examination:                       NONE
---------Learning Objective:
                                                                                              ---------------------------
V.B.9 (As available)
                                                                                              -------------------
Question Source: Bank. (Note changes or attach parent) New X Question History: (Optional-Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)
Objective:
Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments: , . * *
Learning Objective:              V.B.9                            (As available)
* ES-401 Technical Reference(s)
Question Source:
: Sample Written Examination Question Worksheet 2*GOI*100*1A Rev 1 39 OPL 171.228 Rev 3 Form ES-401*5 (Attach if not previously provided) (Including versio n I revision number) Proposed references to be prov ided to applicants during examination
Source:                              Bank.
: NONE -------------------
(Note (Nole changes or attach parent)
Learning Objective: V.B.9 (As available)
New         X
Question Source: (Nole changes or attach parent) Question History: (Optional-Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a de t ailed review of every question.) Question Cognitive Level: Memory or Fundamenta l Knowledge Comprehension o r Analysis X 10 CFR Part 55 Conlen!: 55.4 1 X 55.43 Comments:
                                                                    ~---------------~
ES-401 Sample Written Examination Question Worksheet Examination Outline Cross-reference:
Question History:
2.2.13 -Knowledge of tagging and clearance procedures. I Proposed Ques t ion: # 68 Level Tier# Group # KIA # Importance Rating Form ES-401*5 RO 3 SRO G2.2.13 4.1 Which ONE of the following completes the following statements regarding the thawing process for a freeze p l ug in accordance with SPP-10.2, Appendix E , "Special Requirements For Mechanical Clearances?" During the time that the freeze plug is being thawed , the clearance is required to be _(1)_ AND the vents/drains are required to be verified _(2)_. A. (1) Released but tags still on boundary valves (2) OPEN B. (1) Released but tags still on boundary valves (2) CLOSED C. (1) Actively Issued (held) all tags in place (2) OPEN D. (1) Actively Issued (held) all tags in place (2) CLOSED Proposed Answer: B Post-Exam Evaluation Recommendation
History:
: Delete the Question ES-401 Sample Written Examination Question WorkSheet E x amination Outline Cross-reference
10195 will generally undergo less rigorous review by the NRC; failure to (Optional- Questions validated at the facility since 10/95 provide the information will necessitate a detailed review of every question.)
: 2.2.13* Knowledge of tagging and c learan ce procedures. I Proposed Question: # 68 Le ve l Tier# Group # KIA # Importance Rating Fonn ES-401*5 RO 3 SRO -I G2.2.13 4.1 Which ONE of the following completes the following statements regarding the thawing process for a freeze plug in accordance with SPP*10.2 , Appendix E , " Special Requirements For Mechanical Clearances?" During the time that the freeze plug is being thawed , the clearance is required to be _(1)_ AND the vents/drains are required to be verified _(2)_. A. (1) Released but tags still on boundary valves (2) OPEN B. (1) Released but tags still on boundary valves (2) CLOSED
Question Cognitive Level:
* C. (1) Actively Issued (held) all tags in place (2) OPEN
Level:          Memory or Fundamental Knowledge Comprehension or Analysis                   X 10 CFR Part 55 Conlen!:
* D. (1) Actively Issued (held) all tags in place (2) CLOSED Proposed Answer: B Post-Exam Evaluat io n Recommendation
Content:           55.41 55.41      X 55.43 Comments:
: Delete the Question ES-401
  *
* Challenge Issue:
* ES-401                                 Sample Written Examination                     Fonn Form ES-401*5 Question Worksheet WorkSheet Examination Outline Cross-reference:
* Candidate Performance:
Cross-reference:                        Level Level              RO      SRO 2.2.13*
* Sample Written Examination Question Worksheet Form ES-401-5 This question was drafted after we returned from the Atlanta In-office review with the NRC. The question was unintentionally written at the wrong license level (RO versus SRO) and not linked to job requirements of a Reactor Operator.
2.2 .13 - Knowledge of tagging and clearance procedures.
The requirements for releasing a clearance associated with a freeze seal would be determined, briefed, and directed by a SRO. There are no objectives in OPL 171.086, "TVAN CLEARANCE PROGRAM" Lesson Plan specific to the requirements of Freeze Seals. OPDP-1, "Conduct of Operations," provides the following guidance:
Tier#                3 Group #                      - I KIA #                  G2.2.13 Importance Rating  4.1 I Proposed Question:
6.3C Preparation for Clearance Removal When preparing to remove a clearance the SRO will: o Review restoration of clearance sequencing to ensure the restoration specified is accurate for plant conditions, specific tags to remove, and precautions o Ensure verification of components configuration inside the clearance boundary based on work performed and controls imposed by work documents before the tags are removed o Ensures the operator removing the clearance reviews the lift and then ensures a pre-job brief is conducted This question evaluates knowledge and abilities at a level that is unique to the SRO job position.
Question: # 68 Which ONE of the following completes the following statements regarding the thawing process for a freeze plug in accordance with SPP*10.2 SPP-10.2,, Appendix E, "Special Requirements For Mechanical Clearances?"
Therefore, in accordance with NUREG 1021 ES-401, this is an SRO-Only question.
During the time that the freeze plug is being thawed , the clearance is required to be _(1)_ AND the vents/drains are required to be verified _(2)_.
Additional information provided during Exam Analysis with the candidates (from the SRO Upgrade) was that in fact, due to conservative decision-making practices, in his only experience in dealing with a freeze seal to replace a CRD Valve, the clearance was revised to keep the tags that were still hanging active, versus the Clearance being released with the tags still hanging; as the shift felt like there would no longer be any "administrative controls" over the tags that were still hanging. All RO candidates selected an incorrect answer. 4 selected 'D' and 2 selected 'C'. All SRO candidates selected the correct answer. ES-401
A.
* Challenge Issue:
A. (1) Released but tags still on boundary valves (2) OPEN B. (1) Released but tags still on boundary valves B.
* Candidate Performance:
(2) CLOSED C. (1) Actively Issued (held) all tags in place
* Sample Written Examination Question Worksheet Form ES-401-5 This question was drafted after we returned from the Atlanta In-office review with the NRC. The question was unintentionally written at the wrong license level (RO versus SRO) and not linked to job requirements of a Reactor Operator.
* C. (2) OPEN D. (1) Actively Issued (held) all tags in place (2) CLOSED Proposed Answer:
The requirements for releasing a clearance associated with a freeze seal would be determined, briefed, and directed by a SRO. There are no objectives in OPL 171.086, "TVAN CLEARANCE PROGRAM" Lesson Plan specific to the requirements of Freeze Seals. OPDP-1, "Conduct of Operations," provides the following guidance:
Answer: B Post-Exam Evaluation Evaluation          Delete the Question Recommendation::
6.3C Preparation for Clearance Removal When preparing to remove a clearance the SRO will: o Review restoration of clearance sequencing to ensure the restoration specified is accurate for plant conditions, specific tags to remove, and precautions o Ensure verification of components configuration inside the clearance boundary based on work performed and controls imposed by work documents before the tags are removed o Ensures the operator removing the clearance reviews the lift and then ensures a pre-job brief is conducted This question evaluates knowledge and abilities at a level that is unique to the SRO job position.
Recommendation
Therefore, in accordance with NUREG 1021 ES-401, this is an SRO-Only question.
* ES-401                     Sample Written Examination                               Form ES-401-5 Question Worksheet
Additional information provided during Exam Analysis with the candidates (from the SRO Upgrade) was that in fact, due to conservative decision-making practices, in his only experience in dealing with a freeze seal to replace a CRD Valve, the clearance was revised to keep the tags that were still hanging active, versus the Clearance being released with the tags still hanging; as the shift felt like there would no longer be any "administrative controls" over the tags that were still hanging. All RO candidates selected an incorrect answer. 4 selected 'D' and 2 selected 'C'. All SRO candidates selected the correct answer.
* Challenge Issue:       This question was drafted after we returned from the Atlanta In-office review with the NRC. The question was unintentionally written at the wrong license level (RO versus SRO) and not linked to job requirements of a Reactor Operator. The requirements for releasing a clearance associated with a freeze seal would be determined, briefed, and directed by a SRO. There are no objectives in OPL 171.086, "TVAN CLEARANCE PROGRAM" Lesson Plan specific to the requirements of Freeze Seals.
ES-401 Sample Written Examination Question Worksheet Form ES-401-5 Technical Reference(s)
OPDP-1, "Conduct of Operations," provides the following guidance:
: SPP-10.2 Rev 12 (Attach if not previously provided)
6.3C    Preparation for Clearance Removal When preparing to remove a clearance the SRO will:
Proposed references to be provided to applicants during examination:
o      Review restoration of clearance sequencing to ensure the restoration specified is accurate for plant conditions, specific tags to remove, and precautions o      Ensure verification of components configuration inside the clearance boundary based on work performed and controls imposed by work documents before the tags are removed o      Ensures the operator removing the clearance reviews the lift and
NONE ---------------------------
* then ensures a pre-job brief is conducted This question evaluates knowledge and abilities at a level that is unique to the SRO job position. Therefore, in accordance with NUREG 1021 ES-401, this is an SRO-Only question.
Learning Objective: (As available)
Additional information provided during Exam Analysis with the candidates (from the SRO Upgrade) was that in fact, due to conservative decision-making practices, in his only experience in dealing with a freeze seal to replace a CRD Valve, the clearance was revised to keep the tags that were still hanging active, versus the Clearance being released with the tags still hanging; as the shift felt like there would no longer be any "administrative controls" over the tags that were still hanging.
Question Source: Bank' (Note changes or attach parent) New X Question History: Last NRC Exam (Optional
Candidate Performance: All RO candidates selected an incorrect answer. 4 selected 'D' and 2 selected 'C'. All SRO candidates selected the correct answer.
-Questions validated at the facility since 10/95 will generally undergo less rigorous review by the NRC; failure to provide the information will necessitate a detailed review of every question.)
* ES-401                                    Sample Written Examination                                            Form ES-401-5 ES-401*5 Question Worksheet Technical Reference(s):
Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:
Reference(s) :        SPP-10.2 SPP*10.2 Rev 12                                        (Attach if not previously provided)
F. The following instructions govern the use of freeze plugs 1. The clearance should be in place, but not issued , before establishing the freeze plug. 2. The need for the freeze plug should be identified on the Remarks Section of the clearance sheet. The freeze plug should not be listed as a device held on the clearance sheet. The establishment and maintenance of the freeze plug shall be in accordance with approved procedures or work documents.
Proposed references to be provided to applicants during examination:      examination : _ NONE N"O"N.:.E
3 The freeze plug must be attended by qualified personnel to ensure that it is maintained intact until all work is complete and the proper Post Maintenance Tests (PMT s) are performed.
                                                                                                    =-_ _ _ _ _ _ _ _ __
: 4. If the clearance must be released to allow performance of a PMT, the equipment must be retagged before allowing the freeze plug to thaw. This will prevent miQration of a portion of the pluQ. 5. The clearance must be released before allowing the freeze plug to thaw. However, to prevent migration of the freeze plug. tags on boundary valves shall not be removed until the freeze plug has completely thawed. 6. All vents and drains must be verified CLOSED before allowing the freeze plug to thaw.
                                                                                            ---------------------------
* ES-401 Sample Written Examination Question Worksheet Form ES-401*5 Technical Reference(s)
Learning Objective:
: SPP*10.2 Rev 12 (Attach if not previously provided)
Objective:                                                (As available)
Proposed references to be provided to applicants during examination
Question Source:                                  Bank' (Note changes or attach parent)
: _N" O"N.:.E=-_________ _ Learning Objective: (As available)
New        rX X"-_ _ _ _ _- ,
Question Source: (Note changes or attach parent) New r X"-_____ -, Question History: I..aBt NRC Elcam (Optiona/-
                                                                    ~--------------~
Questions validated at the facility since 1005 will generally undergo less rigorous review by the NRC; failure to provide the i nformation wi/I ne c essitate a detailed re v iew of every question.)
Question History:                    Last NRC Elcam I..aBt        Exam 1005 will generally undergo less rigorous review by the NRC; failure to (Optiona/-- Questions validated at the facility since 10/95 (Optional wi/I necessitate a detailed review provide the information will                        re view of every question.)
Question Cognitive Level: Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments: F_ The following i nstructions govem the use of freeze plugs 1. The clearance should be in place , but not issued. before establishing the freeze plug. 2. The need for the freeze plug should be identified on the Remarks Section of the clearance sheet. The freeze plug should not be listed as a device held on the clearance sheet. The establishment and maintenance of the freeze plug shall be In accordance with approved procedures or work documents. 3 The freeze plug must be attended by qualified personnel 10 ensure that il is mainta i ned intact until all work is complete and the proper Post Maintenance Tests (PMT s) are performed. 4. If the c l earance must be released to allow performance of a PMT, the equIpment must be relagged before aHowing the freeze plug to thaw. This will prevent miQralion of a portion of the pluQ. 5. The clearance must be released before allowing the freeze plug to thaw. However , to prevent migration of the freeze plug, tags on boundary valves shall not be removed until the freeze plug has completely thawed. 6. All vents and drains must be verified CLOSED before allowing the freeze plug to thaw.}}
Question Cognitive Level:Level :        Memory or Fundamental Knowledge                  X Comprehension or Analysis 10 CFR Part 55 Content:                  55.41      X 55.43 Comments:
Comments:
* F.
F_    The following instructions govern govem the use of freeze plugs
: 1. The clearance should be in place    place,, but not issued.
issued, before establishing the freeze plug .
plug.
2.
: 2. The need for the freeze plug should be identified on the Remarks Section of the clearance sheet. The freeze plug should not be listed as a device held on the clearance sheet. The establishment and maintenance of the freeze plug shall be in In accordance with approved procedures or work documents. documents.
3    The freeze plug must be attended by qualified personnel to           10 ensure that itil is maintained intact until all work is complete and the proper Post Maintenance Tests (PMT s) are performed.
performed .
4.
: 4. If the clearance must be released to allow performance of a PMT, the equIpment      equipment must be retagged relagged before aHowingallowing the freeze plug to thaw.
thaw . This will prevent miQration of a portion of the pluQ miQralion                            pluQ..
5.
: 5. The clearance must be released before allowing the freeze plug to thaw.                thaw .
However, However,      to  prevent    migration    of  the freeze  plug.
plug, tags  on  boundary  valves shall not be removed until the freeze plug has completely thawed.          thawed .
6.
: 6. All vents and drains must be verified CLOSED before allowing the freeze plug to thaw..
thaw}}

Revision as of 02:53, 14 November 2019

Initial Exam 2009-301 Post Exam Comments
ML092390396
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 07/29/2009
From: West R
Tennessee Valley Authority
To: Widmann M
Division of Reactor Safety II
References
50-259/09/301, 50-260/09/301, 50-296/09/301
Download: ML092390396 (22)
v • d • e


Text

CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390 Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 29, 2009 10 CFR 55.40 Mr. Malcolm T. Widmann, Branch Chief Operations Branch U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth Street S.W.

Suite 23T85 Atlanta, Georgia 30303-8931 Browns Ferry Nuclear Plant Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITIEN EXAMINATIONS - POST EXAMINATION RESPONSE Mr. Widmann TVA administered the final NRC Written Examination for the RO and SRO HLT Class 0801 on July 22,2009. Please find enclosed, the supporting documentation required by Section ES-501 of NUREG 1021, Post Examination Activities. The enclosure content listing is provided at the end of this letter.

The results were three Senior Reactor Operator (SRO) Candidates passed the examination with overall scores ranging from 89 percent to 92 percent and four of six Reactor Operator (RO) Candidates passed the RO portion of the exam with scores ranging from 89 percent to 90.6 percent. Two Candidates failed the RO portion of the written exam with scores of 78.6 percent and 76 percent. The SRO scores on the RO portion of the examination ranged from 90.6 percent to 93.3 percent.

Analysis of the RO portion of the examination indicated five questions, numbers 18, 37, 59, 62, and 68, with a greater than 50 percent failure rate. Analysis of the SRO portion of the examination indicates questions 78 and 96 have a greater than 50 percent failure rate. Additionally, there were specific comments posed by the candidates during the post-examination review.

CONFIDENTIAL INFORMATION SUBMITIED UNDER 10 CFR 2.390

Malcolm T. Widmann Page 2 July 29, 2009 Subsequent detailed analysis of high miss-rate questions and those identified during post-exam review indicates potential issues with four questions. There are two questions in the package that TVA believes have two correct answers. There are two questions in the package that may have job-link issues. TVA has submitted these two questions for deletion.

The results of this analysis, where applicable, will be forwarded to the HLT Supervisor for potential inclusion in the appropriate training material.

The enclosures to this letter are considered by TVA to be of a personal nature and, as such, are to be withheld from public disclosure in accordance with 10 CFR 2.390(a)(6).

If you have any questions or comments, please telephone Mr. Brian P. Stetson at (256) 729-7039.

r:u~

R. G. West Vice President

Enclosures:

Enclosure 1 - Form ES-403-1, Written Examination Grading Quality Check Enclosure 2 - Graded Written Examinations (I.E., Each Applicant's Original Answer and Examination Cover Sheets) Plus A Clean Copy of Each Applicant's Answer Sheet Enclosure 3 - Master Examination(s) Excerpt Annotated to Indicate Any Changes Made While Administering the Examination - No Changes Made While Grading Enclosure 4 - Questions Asked By and Answers Given to the Applicants During the Written Examination Enclosure 5 - Substantive Comments Made By the Applicants Following the Written Examination

Malcolm T. Widmann Page 3 July 29, 2009 Enclosure 6 - Exam Seating Chart Enclosure 7 - Results of Any Written Examination Performance Analysis That Was Performed, With Recommended Substantive Changes

ENCLOSURE 1 BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 REACTOR OPERATOR (RO) AND SENIOR REACTOR OPERATOR (SRO) INITIAL LICENSE WRITTEN EXAMINATION - POST EXAMINATION RESPONSE FORM ES-403-1, WRITTEN EXAMINATION GRADING QUALITY CHECK (SEE ATTACHED)

ES-401 Sample Written Examination Form ES-401*5 ES-401-5 Question Worksheet

  • Examination Outline Cross-reference:

295038 High Off-site Release Rate 19 EK1.03 (10CFR 55.41 ,10) .10)

I9 Knowledge of the operational implications of the following concepts as they apply to HIGH OFF*SITE OFF-SITE RELEASE RATERATE::

Level Tier #

Tier#

Group #

KIA #

KJA#

RO 1

1 SRO 1-295038EK1 .03

  • Meteorological effects on off-site release I Proposed Question: # 18 Importance Rating 2.8 1-='

A General Emergency is declared due to a valid Wide Range Gaseous Rad Monitor (WRGERMS) reading. The current meteorological data is:

  • 91 meter wind direction:

direction : 120 degrees

  • 46 meter wind direction direction:: 115 degrees Which ONE of the following identifies the correct data point to use for this release AND the wind direction?

A. (1) 91 (2) wind is blowing Itom from the Southeast B. (1)46 (1) 46 (2) wind is blowing from the Southeast c.

C. (1) 91 (2) wind is blowing from the Northwest D. (1) 46 (2) wind is blowing from the Northwest Proposed Answer:

Answer:

A Post-Exam Post*Exam Delete the question.

Evaluation Recomme ndation:

ndation :

,"I I A . c ," ,

(... IllIt l ( /U( i t

'  ;

5

  • Answer Key Incorrect I Stem Clarity - The stem requests the candidate Challenge demonstrate knowledge of meteorological implications during emergency Issue:

conditions. The stem asks for information that is not a part of a ROs normal job responsibility. Part (1) asks information on the correct data point to collect data from [46m or 91 m}. This information is normally collected by RP personnel per EPIP-13, ltDose Assessment," (See excerpt). If SPDS is unavailable, (see excerpt), operations could be asked specifically what parameters to monitorlreport. With SPDS out of service, there is NO information available inside the Control Room to support data collection for Wind Direction.

BROWNS FERRY DOSE ASSESSMENT EPIP-13 3.6.3 Stack Meteorological Data 3.6.3.1 For stack releases record measurements at the 91 meter reading.

3.6.3.2 The default value for stability cfass with no met data available IS "0" for stack releases.

3.6.3.3 The default value for wind speed with no met data available is 4.0 meters/second for the stack.

3.4 Oetennination of Noble Gas Release Rate In j.lCi/second (Step 3 of Appendix A and B) 3.4.1 Stack Noble Gas Release Rate

  • 3.4.1.4 If SPDS IS unavaIlable, notify OperatIons personnel on the affected unit to gain the information utilizing control room instrumentation. or if unavailable, notify the Shift Manager/Site Emergency Director that TI-67, "Determination of Stack and Hardened Wetwell Vent Release Rates* (backup method), procedure must be performed by RP and Chemistry personnel.

The ROs do normally collect and record meteorological data per 1-SR-2, ltlnstrument Checks and Observations," based on TRM 3.3.7 requirements (See excerpt). This information is collected on all three levels (10m, 46m and 91 m), making it non-specific to the requirements of an emergency assessment.

Instrument Check** nd Observations Attachment 2 (PIIg8 49 of 96)

SUrveillance PrOC8dure Om Pickage. Modes 1, 2, & 3

--

TASLE 1.48

,48 METEOROLOGICAL INSTRUMENTATJON

!NSTRUMENTATJON VA Y SHFT DAY SHIfT <NEEI(

WEE" APPLtCABtliTY AT ALL TIMES (Note 2~

C1tarta C1tal1a &.ute So<ro! TSR:3371 TSR: 3.3 7 1

-

LOCATlON LOCATION rcs ICS~*_' .:Nc(e 1

'NINO DIRECTION WtNQSPEEO 91M 91104 46M 10M 9114 91M 46M 10M uo Uno! SI.1M

-

FndoY The need for this information during emergency conditions is the

  • responsibility/function of RP or an SRO if requested by RP, based on the following:
1) Per supplied "Guidance for SRO-only Questions," Rev 0, page 5 of 19, (see excerpt) part (1) would be considered SRO knowledge only.

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

  • Application of required actions (Section 3) and surveillance requirements (Section 4) in accordance with rules of application requirements (

Section 1) NO

  • Applications of generic LCO requirements (LCO 3.0.1 thru 3.0.7 and LCO 4.0.1 thru 4.0.7) NO
  • Knowledge of tech spec bases that is required to analyze tech spec required actions and terminology YES Meteorological Monitoring Instrumentation B 3.3.7 TR 33 INSTRUMENTATION TR 3.3.7 Meteorological Monitoring Instrumentation BASES
  • BACKGROUND A complete description of past meteorological conditions at BFN and the surrounding area is located in the FSAR The meteorology of the Browns Ferry site provides generally favorable atmospheric conditions for transport and dispersion of plant emissions An operational meteorological measurement program ensures that sufficient data is available for estimating potential radiation dose to the public as a result of routine or accidental release of radioactive materials to the atmosphere A 91 meter tower with supporting meteorological instrumentation is located within the BFN site boundary to satisfy this objective However, none of this information is used during emergency conditions, making this NOT within the scope of a RO job function.

Thus, there are NO correct answers.

Candidate performance: 3 of 9 selected "C", 1 selected "B", and 5 selected "A" Explanation:

A. INCORRECT: Part 1= correct, Per EPIP-13, attachment A Met data is collected from the 91 meter point. This is a stack release. (WRGERMS = stack) This information is collected and documented by RP personnel, or if SPDS were non-operational, a request of Operations. However there is NO additional instrumentation within the Control Room that could be used to assess Wind Direction if SPDS were to be NON-OPERATIONAL. Part 2 = correct - Per EPIP-13, Attachment A, wind "from" is correct. Also the RO does collect Meteorological data per 1-SR-2, making this portion not specifically a function of the RO, but

  • within the knowledge range of a RO.

B. INCORRECT: See above.

C. INCORRECT: See above.

D. INCORRECT: See above.

ES-401 Sample Written Examination Form ES-401-5 ES-401*5 Question Worksheet QUestion Technical Reference(s): EPlp*13 Rev 38, EPIP-13 (Attach if not previously provided) 1-SR-2 Rev 19 (Including version I revision number)

Proposed references to be provided to applicants during examination: examination: NONE

Learning Objective: (As available)

- 1.-.

Question Source: Bank.

. -

. -

-'. .. '.

(Note changes or attach parent)

New X

--~-~--~ ......

History:

Question History: RCExam (Optional- Ouestions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to (Optional - Questions provide the information will necessitate a detailed review of every question.)

Question Cognitive Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

  • ES-401 Sample Written Examination Form ES-401-5 ES-401-S Question Worksheet
  • Examination Outline Cross-reference:

EA1.04 EA1 .04 (10CFR 55.41.7)

Wtr Lvi 295029 High Suppression Pool WIt LviIi 5 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL:

Level Tier #

Tier#

Group #

KIA #

RO 1

22 SRO

-

295029EA 1.

1.04 04

  • RCIC: Plant-Specific Importance Rating 3.4 I Proposed Question: # 26 During a Unit 2 startup, with power ascension at 20% Reactor Power, a rapid loss of condenser vacuum forces the crew to insert a manual Scram. The following plant conditions exist:
  • Reactor Water Level initially lowered to 0 inches and is currently being controlled (+) 2 to

(+) 51 inches with RCIC AND CRD

  • The MSRVs are being used to control Reactor Pressure AND HPCI was started in pressure control mode
  • Suppression Pool Water Level reaches (+) 7 inches Which ONE of the following predicts the current status of RCIC AND the required operator action in accordance with 2-EOI-1, "RPV Control?"
  • RCIC Suction _ _(1)_

(ll_AND AND the required operator action in accordance with 2-EOI-1, is to

_(2)_.

_(2)_.

A. (1) is aligned to the CST (2) continue RCIC operation in the current configuration.

C. (1) automatically swaps to the Suppression Pool (2) continue RCIC operation in the current configuration.

configuration.

D. (1) automatically swaps to the Suppression Pool (2) manually swap RCIC suction path. path .

I propo~ed propo:ed Answer: I Post-Exam Evaluation Accept both "A" and responses Recommendation:

  • ES-401 Sample Written Examination Form ES-401*5 Question Worksheet Answer Key Incorrect /t Stem Clarity - The stem requests the
  • Challenge Issue:

candidate demonstrate knowledge of RC/C RCIC operation in accordance with 2*EOI*1. 2-EO/-1. 2-EO/-1 2*EOI*1 Flowchart step RCIL-4 RCIL*4 directs RCIC operation [with CST suction if possible}. However, 2*EOI RC/C 2-EOI APPENDIX*SC, INJECTION SYSTEM LINEUP RCIC, APPENDIX-5C, RCtC, the controlling document for placing RC/C RCIC in level control, gives the option in step 11 (see excerpt below) to shift suctions to the Suppression Pool if desired. desired.

l:' .

L... :r. ,.....

_. . ._:t.
t l.5 d~s:.red 1.5 d!!" s :.re:1 ~o -'0 all.q!l 1iI:'1.q7'. s*.1ct.ion t *:*

RC : : ,'Jct.!.on RC:C tt.e

.:, the Supp::essic,n S Po~l *

  • ..lpp~e5.l11'i.o;.r.: Olc-:-l,
HE:: ... PERPCRN tr.* (e:lc.':'r.Q :

.. ~-;:"'.:-"1 - 17. It::

a . OPEN Z-FC'l-71-17,  :

R:::: C SOPP~ POeL SUPO:~ ~'O:::. :N3:::

N3D sucr STJCT VALVE.

VALVE..

b . OFEN O -i'CV-7 1-B. ac::

OPEN 2Z-::CV-71-B, RC: ::; SUPPR 5UP Pit PO POCLC::" OL '"7S:::

OUTS:>

socr SUCT 'rrLo,,"l.

VALVE..

c.

  • . *1f":IEH WHEN ..  :-F>:v -n-17.

. ... :-:':V- 1 1-17, RC:C R.::: C SUPPR P".AiL PCO:' ll8:l

NED SUCT W V1.LVI
  • .LVE,. and 2-P,;-....

2-FC"O/-i- ,!.-:c, l -1E. ReI":Ro:rC SUPPR wer.

suP"~ SU*::;: 1lAl.'!E Ol:TS!; Si:C:

YOC::" Ol'":B: VAL'.'E,. are Ar e ffully

,.Jj.ly cpe open, r.,

T~N ...

THEN .. . VERI VERIF'l FY CLOSED :-::C'1-71-19,

> : C":-'71 - 19, RC:: RC:C CS-: Sl'CTION ',,

CS: Sr:CTIOti '1U,..or .

VALVE.

The stem did not clarify what portion of 2-EO/-1 2*EOI*1 to reference

[flowchart step RCIL-4 RCIL*4 gr Q! Appendix SC}; 5C); only that 2-EOI*1 2-EO/-1 is the controlling document document. Also, NO CST level is provided in the stem, forcing the candidate to make an assumption. With Suppression Pool level requiring a vel}' vety narrow band of control, the candidate(s)thought it was a prudent decision to lower level in the Suppression Pool; thus applying the portion of Appendix SC step 11 (if desired to align RCIC 5C RC/C suction to the Suppression Pool).

Therefore, with the option to shift suctions in Appendix Appendix SC 5C (also within a 2*EOI-12-EO/-1 document) taken in conjunction with the fact that we are now in 2-EOI-2 2*EOI-2 on High Suppression Pool level, it would be considered a valid operational action that protects containment integrity. integrity. Additionally having 01-71 01*71 Precaution & &

Limitation knowledge supports the fact that at +7 "uSuppression Suppression Pool Level, a suction swap should be performed. Thus, there are TWO correct answers: "A" uA" and "US". S II.

Candidate performance:

performance: 3 of 9 selected "8 "8", ". 6 selected "A" Explanation:

A. CORRECT" Part 1 _correct - NarmalIIUCIIon A Normal suction ....., rln8Up for lor RCIC RelC is 10 lhe caT to the CST and . . . no automatic there*

IIUCIIon _ . PIr12 suction swap. Part 2 correct

_ RCle ~

- RCIC injection In lhe EOIa in the EOis is dhdiId directed 10 -with caT to be "WillI CST SUctionSUctian if JIG POSllble-II""

e-(see pllCldln procedure .-rpI) excerpt)..

  • ES-401 Sample Written Examination Form ES-401-5 ES-401*5 Question Worksheet C. INCORRECT:

INCORRECT: Part 1 incorrect - Plausibility based on on the overwhelming similarities between the HPCI and Rele Systems: and the frequently confused differences. HPCI automatically swaps suction to the RCIC Systems; Suppression Pool Pool at +5.25 inches. Part 2 correct - Rele RCIC injection injection in the EOls is directed to be "with CST Suction if poss ible~ (see procedure excerpt) .

possible" O. INCORRECT: Parts 1is D. INCORRECT: 1is incorrect and 2 correct as explained in ~"B". B~ _

Technical Reference(s):

Reference(s): 2-01-71 Rev 57 57,, 2-EOI-1 2-EOI- 1 Rev 12, 12, 2-EOI-1 2- EOI-1 (Attach Ifif not previously provided)

Appendix-5C Rev 4 OPL 171.040 Rev 22 /1042 Rev 19 (Including version I/ revision (Including version revision number)

Proposed references Proposed references to be provided to applicants during examination:examination: NONE

Learning Objective: V. B.6, V.B.9.

V.B.B, V.B.9, V.B.11.

V. B.ll , V.B.12 (As available)

Question Source:

Modified Bank # 0610 Audit # 64 (Note changes or attach parent)

New Question History: Last NRC Exam (Optional- Questions validated at the facility since 10195 will generally undergo less rigorous review by the NRC; failure to (Optiona/-

provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:Level: Memory or Fundamental Knowledge

Comments:

55.41 55.43 Comprehension or Analysis X

x X

OPL OPL171 171.040

.040 Revision 22 RCIC has no automatic transfer from CST to torus. 01-71 directs transfer of RCIC when HPCI auto transfers on low CST level or high torus level and if RCIC trips on low suction pressure 10" Hg vacuum. vacuum .

  • 6.1 BFN Unlt2 Reactor Cor. Isolation Cooling Normal Operation (continued) 2..()1-71 Rev. 0057 Page 22 0176

[5) BEFORE SuppressIOn Pool temperature reaches 95"'F, PLACe RHR in Suppression Pool Cooling Mode.

(REFER TO 2-01-74) [J (5.1) IF Suppression Pool temperature reaches 95°F. THEN ENTER 2-EOI-2 Flowchart [J

[5.21 IF Suppression Pool temperature reaches 105"F, THEN SHUT DOWN RCIC System operatIOn and return to Standby ReadIness REFER TO Step 61[12] or 6 1[13J. [J

[6) MAINTAIN Suppression Pool level between *5.5 and -2 in.

(REFER TO 2-01-74.) [J

[7] MONITOR CST 2 LEVEL, 2-Ll-2-161A, on Panel 2-9-6. [J

[S} IF ANY of the following conditions occur while RCIC IS injecting into the RPV:

  • Suppression Poolieve! reaches +7 in., OR o
  • HPCl suctIOn auto transfers to suppressiOn pool, OR [J
  • RCIC Turbine trips on pump low suction pressure, THEN PERFORM the following steps to transfer RCIC Suction to the Suppression Pool:

(8.1] OPEN RCIC SUPPR POOL INBD SUCT VALVE, 2-FCV-71-17. o

[8.2] OPEN RCIC SUPPR POOL OUTeD SUCT VALVE, 2-FCV-71-18.

[83] WHEN RetC SUPPR POOL INBD SUCT VAlVE, 2-FCV-71-17, and the RCIC SUPPR POOL OUTSD SUCT VALVE, 2..fCV-71-18. are fully open, THEN VERIFY CLOSED RCIC CST SUCTION VALVE, 2*FCV.71-19 o

/

..... .......

"'\

~ ..

'- "'- '

,.

CAUT'tON CAUTION I I .2#2 PUMP PO .... P NPSH AND VORTEX LIMiTS t.PSH"'!>(l l!MrtS I

....

I .3 #3 ElEVA ELeVATED TEO SUPPR SUPPA CHM8R CHMSR PRESS MAY TRIP RelC RCIC I

I#. #6 HPCI OR 0f'I RelC RCIC SUCTION lEW ASO\IE 140 TEMP ABO\l£ l.o 'F

'F I L L

~

_n oa. Nro

!tESTOIIiE .... INT .. IN RPV WA AND MAINTAIN WATER TER LVL BETWEEN 8E't'MOtN

.2 IN

+2 .o.NO.M IN. AND +51 IN IN. WITH ONE OR MORE OF T11E FOLLO~NG Of 111£ FDllOIMNO INJ SOURCES:

IN.J SOURCES :

~t. IIiJ SOURCE INJSOURCE APPX

"'~ '" ,...,,"

INJ PRESS CNDSANDFW CNOS"NOFW '~PSIG 1250 PS4G

,.'"

SA CRO eRD 58 1640 160W PS4G PSIG

...

'

RelC. 1240PS/G 5C 1240 PS4G

... WITH CST SUCTION IF POSSIBLE

'"

""" .

HPCI.

50 ,Z*OPSIG 1240 PS4G

~TH WITH CS CSTT SUCTION IF POSSIBLE POSSl8 l E

'"

~t. eNOS CNO' SA M

..,

480 PSIG

60, 6EBE 330 PSiG LPGI 68.6C 320 PSIG

,"'-.

RCJL-4

""" '". oc L

"

....

RESTORED AND RESIOREO CAN

"""

RPV WATER L VL BE RPVW"TEl!L\lL8E

... NO MAINTAINED A80\I£ ASO'"

+2IN .

wo.INTNNE.D NO L L ~

.. ..... '\

RCIL*~

RCIL*S

,~

" L YESL t-.. ....... ........ I RPV WATER lLVi..

MAINT AI" RP\!wATE,R.

MAINTAIN VL ABO\I£ A80VE *162 IN.

-182"'.

'CA' RC/l~

...

. .. .

ES-401 Sample Written Examination ES-401*5 Form ES-401-S Question Worksheet

  • APPENDIX-5C 2-ECI APPENDIX- 5G Rev. 4 Pae 3 of 3 PaGe 11 .
11. IF .....

.**** It de~ired to aliqn I1: is desired align ReIC ReIe ~c~ on

. 1:.lon to 1:he 1:0 the Suppression Suppre s~ion Pool, P 1, THEN .. ***. PERFORM p ~he fol1o

'the rtlinq:

fol l ow1nq:

a. aP'£5 2-I!II. 2- ~ 17, ReTe FCV-71-17, RCIC stiP PR POOL L INBD suer VAL SUC! VALV! ~.
b. OPEN 2-fCV-71-1B, Rele OPEN" 2-FCV-71-18, Rcre S PPR ?R POOL OUTED  ;,;m suer VALVE.

sueT

c. WHEN *** 2- l'CV- 1l - 1i, ReIC SUPPR POOL INBD IN3D suer VAL\rE, and 2- FCV-71-18, Re!C :C SUPPR POOL OUlBD $OCT VALVE, are

!ul1.,y ~,

!"'!iEN VEIUPY Cl.OSED Z- fCV 19, RCte CST SUc:nOli VA!. .c .

NOIE.:

NOtE: Step S~ep 12.b 12 . b oust 5t be p=r per !f orceded p:c=ptly p !' t ly foll owing

. ing Step 5 1:

12.~ to avoid loss of l2.a ct i o n pa of ~ uuction th..

path

12. 1=
11. _*...

T';<' * * * *' It I t is ~5 des ir ed t.o desired to align RCIC RCI e gsuct:.on uct~o n to t o i:he t he Condensate 51;.or Gcr.densa'te S~orage age Tank, T a~k ,

'lHElJ THEN ..* *.. PERFORM ::h t.hee ffollowing:

o ll owing:

a.

a. CLOSE 2-:CV-71-:7, 2- : C'i-il-:' 7 , RCICRCrC SIJPPR SCPPR POOL :N3D  :~J 3 D Sr;CI SIJCT VAL VAL'IE.'IE.
b. i\~HEU 2-FCV-7 1- 1-17, 17 , RCIC RCre SUPPR ?OOL rNSD SUFPR ?OO;. INBD SCC! VJ....LVE SlJeT V]..L'lE st arts ~raveling starts -:rave linq clcsed, closed,
rEN OPEN 22-FC/-71-19,

- fC~-7~-19 , ReIC CSTT SUCTION RCI C CS 5UC I !ON VALVE.

Vl lVE.

c.

c. CLOSE  :-:CV-7 1 - ':' 3, RClC CWSE ::-fCV-71-::'B, RCC SUPPRSr.;PPR POOL OUTSDOU'IBD scer SeCT VA!.VE .'

V1>.l.

LAST PAGE lASI' ?AG!!:

  • Exami nation Outline Cross-reference:

Examination 241000 Reactorrrurbine A1 .01 (10CFR A1.01 (10C FR 55.41.5)

Cross-reference:

ReactorfTurb!ne Pressure Regulator 55.41 .5)

Ability to predict and/or monitor changes in parameters associated with with operating the REACTORrrURBINE REACTORITURBINE PRESSURE REGULATING Level Tier #

Group #

KIA ##

KIA RO 2

2 SRO

-

241 OOOA 1.01 SYSTEM controls including:

  • Reactor pressure Reactor Importance Rating 3.9 I Proposed Question:

Question: # 59 Unit 3 is at 93% Reactor Power.

Which ONE of the following completes the statements?

For this power level, level, EHC Pressure Set is nominally set to _(1)_

_ (1)_ psig.

psig .

IF ONE Turbine Control Valve were to fail OPEN OPEN,, then Reactor Pressure, Pressure, upon stabilizing, stabilizing, would be_(2)_.

A.

A. (1) 955 (2) lower B. (1) 1036

  • (2) lower D. (1) 1036 D.

(2) the same Proposed Answer: A Post-Exam Evaluation Accept both "A" and and. responses Recommendation:

Recommendation:

  • Issue:

Challenge Issue: The correct answer originally submitted to the NRC by the BFN Exam Team was "C" IIC" based on theoretical documented system response. Operations personnel performing exam validation indicated that there was actual plant OE which indicated pressure would lower a small amount for the conditions identified in the question. The scenario was run on Unit 3 simulator and pressure lowered a small amount (approximately

.5%). If this were an analog display, versus digital, there is a high probability that it wouldn't be noticeable. But, based on validation input, the correct answer was changed to A.

There are several references which would lead a candidate to conclude that pressure would return to setpoint after the perturbation; including FSAR sections 7.11 and 11.2, EHC Controls Lesson Plan OPL 171.228, and Unit 3 Simulator Malfunction Cause & Effects Manual.

OPL 171.228 171 .228 ELECTRO-HYDRAULIC CONTROL LOGIC Steam Pressure Control maintains either the Header Pressure or the setpoiOl Steam pressure Reactor Pressure at a pressure reference setpoint control , as a reactor pressure controlling parameter is utilized at all control,

  • times, either by the Bypass Valve Control or the Turbine Control.

The system controls reactor pressure such that a change of 1 psig in reactor pressure causes a change of 1 .1%

1.1% in steam flow fiow demanded which the system converts to valve opening demanded and sends to the Turbine Control and/or Bypass Control valves (3 .3% per psig (3.3%

when selected to control on header pressure).

pressure). As reactor power is increased, reactor pressure increases and as pressure increases the increased, EHC system opens the Turbine Control valves or Bypass Control valves to use the extra steam produced by the increased power. power.

FSAR 11.2 TURBINE-GENERATOR I

During normal operations, the steam admitted to the turbine is controlled by the pressure regulator which maintains essentially constant pressure at the turbine inlet, thus controlling reactor vessel pressure. The EHC system pressure regulator can control reactor pressure.

pressure directly.

directly. The ability of the station to follow system load depends on adjustment of reactor power level. This is accomplished by changing Reactor Coolant Recirculation System flow or repOSitioning of control rods .

repositioning FSAR 7.11 PRESSURE REGULATOR AND TURBINE-GENERATOR

  • CONTROL The pressure regulation function of the turbine control system is designed to manipulate turbine control valves and turbine bypass valves, individually or in parallel, parallel, to maintain reactor pressure within a narrow range of the pressure setpolnt setpoint as reactor power varies from 0

ES-401 Sample Written Examination Form ES-401*5 ES-401-5 Question Worksheet percent to 100 percent nuclear boiler rated flow.

flow.

According to the Simulator Cause & Effects Manual:

BROWNS FERRY UNIT 3 MALFUNCTION CAUSE AND EFFECTS 06/14/06 .- REV 3 TC08 CONTROL VALVE POSITION UNIT FAILURE:

TCOS FAILURE:

A) FCV 1-75 EFFECTS:

THIS MALFUNCTION WILL CAUSE THE SELECTED CONTROL VALVE TO BE POSITIONED AS DEMANDED BY THE INSTRUCTOR. THE POSITION INDICATOR FOR THE CONTROL VALVE WOULD REFLECT THE POSITION CHANGE. ALSO, ALSO, THE RECORDED TOTAL CONTROL VALVE POSITION COULD RESPOND TO THE VALVE POSITION CHANGE IF THE GENERATOR BREAKER IS CLOSED AND THE OTHER CONTROL

  • VALVES ARE NOT ABLE TO COMPENSATE. THE EHC SYSTEM PRESSURE CONTROL UNIT WILL RESPOND BY POSITIONING THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES IN RESPONSE TO ANY PRESSURE CHANGE.

IF THE SELECTED VALVE IS POSITIONED TO A LOWER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT, THE OTHER CONTROL VALVES ANDIOR BYPASS VALVES WILL OPEN TO COMPENSAT COMPENSATE E AS PRESSURE INCREASES.

IF THE CONTROL VALVE VAlVE IS POSITIONED TO A HIGHER VALUE THAN REQUIRED BY THE PRESSURE CONTROL UNIT, THE OTHER CONTROL VALVES AND/OR ANDIOR BYPASS VALVES WILL CLOSE TO COMPENSATE AS PRESSURE DECREASES.

IF SYSTEM VALVE POSITIONING IS LIMITED BY ANY OTHER (Le. MAX COMBINED FLOW LIMITER, CONTROL MECHANISM (i.e.

VALVES FULLY OPEN, ETC.), THE SYSTEM RESPONSE WOULD BE ALTERED AND A REACTOR PRESSURE CHANGE AND ITS ACCOMPANYING EFFECTS ON POWER COULD RESULT.

Based on these references the candidate would reasonably

  • expect the EHC System to maintain essentially constant pressure at the turbine inlet, inlet, thus controlling reactor vessel pressure. Therefore, following failure of ONE Turbine Control Valve open, the candidate would conclude that the remaining valves would close to compensate for the pressure decrease

ES-401 Sample Written Examination Form ES-401-5 Question Worksheet

  • and Reactor Pressure would stabilize at the same pressure.

This makes both tA' and te' a correct response.

8 of 9 candidates selected 'C' as the correct answer. 1 candidate Candidate Performance:

selected 'A' and this candidate was the SRO Upgrade.

, .

ES-401 Sample Written Examination Form ES-401-5 ES-401*5 Question Worksheet

  • Technical Reference(s)

Reference(s):: 2*GOI*100*1A 2-GOl-100-1A Rev 139 (Attach if not previously provided)

OPL 171.228 Rev 3 (Including version I revision number)

Proposed references to be provided to applicants during examination: NONE

Objective:

Learning Objective: V.B.9 (As available)

Question Source:

Source: Bank.

(Note (Nole changes or attach parent)

New X

~---------------~

Question History:

History:

10195 will generally undergo less rigorous review by the NRC; failure to (Optional- Questions validated at the facility since 10/95 provide the information will necessitate a detailed review of every question.)

Question Cognitive Level:

Level: Memory or Fundamental Knowledge Comprehension or Analysis X 10 CFR Part 55 Conlen!:

Content: 55.41 55.41 X 55.43 Comments:

  • ES-401 Sample Written Examination Fonn Form ES-401*5 Question Worksheet WorkSheet Examination Outline Cross-reference:

Cross-reference: Level Level RO SRO 2.2.13*

2.2 .13 - Knowledge of tagging and clearance procedures.

Tier# 3 Group # - I KIA # G2.2.13 Importance Rating 4.1 I Proposed Question:

Question: # 68 Which ONE of the following completes the following statements regarding the thawing process for a freeze plug in accordance with SPP*10.2 SPP-10.2,, Appendix E, "Special Requirements For Mechanical Clearances?"

During the time that the freeze plug is being thawed , the clearance is required to be _(1)_ AND the vents/drains are required to be verified _(2)_.

A.

A. (1) Released but tags still on boundary valves (2) OPEN B. (1) Released but tags still on boundary valves B.

(2) CLOSED C. (1) Actively Issued (held) all tags in place

  • C. (2) OPEN D. (1) Actively Issued (held) all tags in place (2) CLOSED Proposed Answer:

Answer: B Post-Exam Evaluation Evaluation Delete the Question Recommendation::

Recommendation

  • Challenge Issue: This question was drafted after we returned from the Atlanta In-office review with the NRC. The question was unintentionally written at the wrong license level (RO versus SRO) and not linked to job requirements of a Reactor Operator. The requirements for releasing a clearance associated with a freeze seal would be determined, briefed, and directed by a SRO. There are no objectives in OPL 171.086, "TVAN CLEARANCE PROGRAM" Lesson Plan specific to the requirements of Freeze Seals.

OPDP-1, "Conduct of Operations," provides the following guidance:

6.3C Preparation for Clearance Removal When preparing to remove a clearance the SRO will:

o Review restoration of clearance sequencing to ensure the restoration specified is accurate for plant conditions, specific tags to remove, and precautions o Ensure verification of components configuration inside the clearance boundary based on work performed and controls imposed by work documents before the tags are removed o Ensures the operator removing the clearance reviews the lift and

  • then ensures a pre-job brief is conducted This question evaluates knowledge and abilities at a level that is unique to the SRO job position. Therefore, in accordance with NUREG 1021 ES-401, this is an SRO-Only question.

Additional information provided during Exam Analysis with the candidates (from the SRO Upgrade) was that in fact, due to conservative decision-making practices, in his only experience in dealing with a freeze seal to replace a CRD Valve, the clearance was revised to keep the tags that were still hanging active, versus the Clearance being released with the tags still hanging; as the shift felt like there would no longer be any "administrative controls" over the tags that were still hanging.

Candidate Performance: All RO candidates selected an incorrect answer. 4 selected 'D' and 2 selected 'C'. All SRO candidates selected the correct answer.

  • ES-401 Sample Written Examination Form ES-401-5 ES-401*5 Question Worksheet Technical Reference(s):

Reference(s) : SPP-10.2 SPP*10.2 Rev 12 (Attach if not previously provided)

Proposed references to be provided to applicants during examination: examination : _ NONE N"O"N.:.E

=-_ _ _ _ _ _ _ _ __

Learning Objective:

Objective: (As available)

Question Source: Bank' (Note changes or attach parent)

New rX X"-_ _ _ _ _- ,

~--------------~

Question History: Last NRC Elcam I..aBt Exam 1005 will generally undergo less rigorous review by the NRC; failure to (Optiona/-- Questions validated at the facility since 10/95 (Optional wi/I necessitate a detailed review provide the information will re view of every question.)

Question Cognitive Level:Level : Memory or Fundamental Knowledge X Comprehension or Analysis 10 CFR Part 55 Content: 55.41 X 55.43 Comments:

Comments:

  • F.

F_ The following instructions govern govem the use of freeze plugs

1. The clearance should be in place place,, but not issued.

issued, before establishing the freeze plug .

plug.

2.

2. The need for the freeze plug should be identified on the Remarks Section of the clearance sheet. The freeze plug should not be listed as a device held on the clearance sheet. The establishment and maintenance of the freeze plug shall be in In accordance with approved procedures or work documents. documents.

3 The freeze plug must be attended by qualified personnel to 10 ensure that itil is maintained intact until all work is complete and the proper Post Maintenance Tests (PMT s) are performed.

performed .

4.

4. If the clearance must be released to allow performance of a PMT, the equIpment equipment must be retagged relagged before aHowingallowing the freeze plug to thaw.

thaw . This will prevent miQration of a portion of the pluQ miQralion pluQ..

5.

5. The clearance must be released before allowing the freeze plug to thaw. thaw .

However, However, to prevent migration of the freeze plug.

plug, tags on boundary valves shall not be removed until the freeze plug has completely thawed. thawed .

6.

6. All vents and drains must be verified CLOSED before allowing the freeze plug to thaw..

thaw

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