ML032330508
| ML032330508 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/19/2003 |
| From: | Lanksbury R NRC/RGN-III/DRS/OLB |
| To: | |
| References | |
| 50-373/03-301, 50-374/03-301 | |
| Download: ML032330508 (22) | |
Text
MISCELLANEOUS CORRESPONDENCE FOR THE LASALLE INITIAL EXAMINATION - MAY 2003
Exelon Generation Company, LLC www.exeloncorp.com LaSalle County Station 2601 North 21Road Marseilles, IL 61341-9757 September 7,2001 10 CFR 55.5(a)
United States Nuclear Regulatory Commission Attention: NRC Region Ill Administrator 801 Warrenville Road Lisle, IL 60532-435 1 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Request for Initial License Examination Pursuant to 10 CFR 55.5(a), this letter is to request an Initial License Examination for the weeks of May 19,2003 and May 26, 2003. LaSalle County Station is beginning an initial license course in February 2002 that will contain 14 Reactor Operator and Senior Reactor Operator candidates.
This course is scheduled for completion in April 2003.
Please confirm the availability of this date by contacting Mr. William Riffer, Regulatory Assurance Manager, at (815) 41 5-2800.
Respectfully, m
Site Vice President LaSalle County Station cc: NRC Document Control Desk NRC Senior Resident Inspector - LaSalle County Station
Exelon Generation www.exeloncorp.com 4300 Winfield Road Warrenville, IL 60555 RS 196 September 21, 2001 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Response to Regulatory Issue Summary 2001-17, "Preparation and Scheduling of Operator Licensing Examinations"
Reference:
NRC Regulatory Issue Summary 2001-17, "Preparation and Scheduling of Operator Licensing Examinations," dated August 22, 2001 This letter provides our voluntary response to the request for information contained in the referenced Regulatory Issue Summary (RIS). The NRC requested that a voluntary response to the RIS be submitted within 30 days of receipt of the RIS. We received RIS 2001-17 on August 22, 2001; accordingly, we are submitting our response by September 21, 2001.
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September 21, 2001 U.S. Nuclear Regulatory Commission Page 2
, As requested, Attachment A, "Completed NRC Form 536," contains a separate NRC Form 536 [August 20001, "Operator Licensing Examination Data," for each of our Midwest Regional Operating Group facilities addressed by the RIS. The information provided for each facility includes: the proposed examination preparation schedule for calendar years (CYs) 2002 through 2005; the estimated number of applicants and proposed dates for each of the initial operator license examinations through CY 2005; and the estimated number of candidates that plan to take the Generic Fundamentals Examination in CYs 2002 and 2003.
If you have any questions or concerns regarding this information, please contact J. A. Bauer at (630) 657-2801.
Respectfully,
&@%. A. Ainger u Director - Licensing Mid-West Regional Operating Group Attachment cc: Regional Administrator - NRC Region I l l NRC Senior Resident inspector - Braidwood Station NRC Senior Resident inspector - Byron Station NRC Senior Resident inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident inspector - LaSalle County Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station
NRC FORM 536 U.S NUCLEAR REGULATORY COMMISSION APPROVED BY OM8 NO 3150-0131 EXPIRES 07/31/2002
(&2000) Estimated burden per response to compl with )his vduntaty information collection request: 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This informationcokxtion is used to plan budgets and resources for operator examinations. Send comments r arding burden estimate 0PE RAT0 R LICENSING to the. Records Mana ement Branch (T-6 6) U% Nuclear Regu!atory Commission, Washin 8n. DC 20555-0001 or by internet e-mail to EXAMINATION DATA bjsl@nrc v and to?he Desk Officer Office of Information and R ulatory Affairs d?OB-10202, (31504131), bffice ,of Management and%udge!
Washihgton, DC 20503. If a means used to im se an information collection does not display a currently valid OMB controLumber. the NRC may not conduct or sponsor, and a person is not required lo respond to, the information collection.
FACILITY I NRC REGION LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 Ill NRC Docket Nos. 50-373 and 50-374 PROPOSED NUMBER CY 02 CY 03 CY 04 CY @
ESTIMATED NUMBER OF 0 1 1 1 LICENSEE-PREPARED EXAMINATIONS ESTIMATED NUMBER OF 1 0 0 0 NRC-PREPARED EXAMINATIONS PROPOSED NUMBER I CY 02 I CY 03 NUMBER OF REACTOR 9 6 6 6 OPERATORS NUMBER OF SENIOR REACTOR OPERATORS-INSTANT 10 6 6 6 NUMBER OF SENIOR REACTOR 2 2 0 0 OPERATORS-UPGRADE NUMBER OF SENIOR REACTOR 0 0 0 0 OPERATORS-LIMITED PROPOSED DATES PRIMARY DATE I
04/08/02 - 04/19/02 05/19/03 - 05/30/03 05/17/04 May ALTERNATE DATE May June June June PROPOSED NUMBER CY 02 CY 03 FIRST SECOND THIRD FIRST SECOND THIRD ESTIMATED NUMBER OF 0 12 0 0 12 0 CANDIDATES
Exelon Generation www.exeloncorp.com 4300 Winfield Road Warrenville. IL 60555 RS-02-123 July 18, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units Iand 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456and STN 50-457 Byron Station, Units Iand 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-467 Dresden Nuclear Power Station, Units 2 and 3 Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11and NPF-18 NRC Docket Nos. 50-373 and 50-374 Quad Cities Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Response to Regulatory Issue Summary 2002-09, "Preparation and Scheduling of Operator Licensing Examinations"
Reference:
NRC Regulatory Issue Summary 2002-09, "Preparation and Scheduling of Operator Licensing Examinations," dated June 6, 2002 This letter provides our voluntary response to the request for information contained in the referenced Regulatory Issue Summary (RE).
July 18,2002 U. S. Nuclear Regulatory Commission Page 2 As requested, Attachment A, "Completed NRC Form 536," contains a separate NRC Form 536 [August 20001, "Operator Licensing Examination Data," for each of our Mid-West Regional Operating Group facilities addressed by the RIS. The information provided for each facility includes: the proposed examination preparationschedule for calendar years (CYs) 2003 through 2006; the estimated number of applicants and proposed dates for each of the initial operator license examinations through CY 2006; and the estimated number of candidates that plan to take the Generic Fundamentals Examination in CYs 2003 and 2004.
If you have any questions or concerns regarding this information, please contact Mr.
Brian Sweeney at (630) 657-2836.
Respectfully, Patrick R. Simpson Manager- Licensing, Dresden and Quad Cities Nuclear Power Stations Mid-West Regional Operating Group Attachment cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Braidwood Station NRC Senior Resident Inspector- Byron Station NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector- Quad Cities Nuclear Power Station
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NRC FORM 536. U.S NUCLEAR REGULATORY COMMISSION APPROVED BY OM6 NO 3150-0131 EXPIRES 07/31/2002 (8-2000) Estimated burden per response !o compl with this voluntary information collection request: 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This information cofection is used to plan budgets and resources for operator examinations. Send comments re arding burden estimate 0PERAT0R LICENS ING to the Records Mana ement Branch (T-6 6) U.8. Nuclear Regulatory Commission Washln hi DC 20555-0001 or by internet e-mail to EXAMINATION DATA bjsl@nrc dv and to ?he 'Desk Officer office of Information and Re ulatoly Affairs &Ob-10202. (3150-0131), Office ,of Management and %udget Washikton DC 20503. If a means used lo tm se an information collection does not dsplay a currently valid OMB conlrofiumber, the NRC may not conduct or sponsor, and a person IS not required i o respond to. the information collection.
1 FACILITY NRC REGION LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-I8 I11 NRC Docket Nos. 50-373and 50-374 I
A. PROPOSED EXAMINATION PREPARATION SCHEDULE PROPOSED NUMBER ESTIMATED NUMBER OF CY 03 1
CY 04 1
I CY g?j 1
I CY 06 0
LICENSEE-PREPARED EXAMINATIONS ESTIMATED NUMBER OF 0 0 NRC-PREPARED EXAMINATIONS I
O I I
O I B. INITIAL OPERATOI LICENSING EXAMINATIONS PROPOSED NUMBER CY g?j CY 06 NUMBER OF REACTOR 5 0 0 0 OPERATORS NUMBER OF SENIOR REACTOR OPERATORS-INSTANT 5 6 6 0 NUMBER OF SENIOR REACTOR 1 0 0 0 OPERATORS-UPGRADE NUMBER OF SENIOR REACTOR 0 0 0 0 OPERATORS-LIMITED PROPOSEDDATES 05/02/05- 05113/05 ALTERNATE DATE 06/03 06/04 06/05 I I C. PROPOSED GENERIC FUNDAMENTALS EXAMINATION (G :E) SCHEDULE PROPOSED NUMBER I CY 03 CY 04 FIRST SECOND THIRD FIRST SECOND THIRD ESTIMATED NUMBER OF 0 6 0 0 6 0 CANDIDATES
February 12,2002 Mr. Oliver D. Kingsley, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
Dear Mr. Kingsley:
In response to your facility management letters dated September 7 and September 21 , 2001, and as augmented by discussions with Michael Entwistle of your staff on January 28,2002,we have tentatively scheduled an initial licensing examination for your operator license applicants at the LaSalle County Station during the weeks of May 19 and May 26,2003. Validation of the examination will occur at the station during the week of April 28,2003. In the unlikely event that we are unable to support the examination during the scheduled weeks, we will inform you immediately upon discovery of such conditions and make arrangements to administer the examination at a mutually acceptable date.
As stated in your letter, your staff will develop the examination. To support the examination administration date, we have tentatively scheduled the date of March 31 , 2003,to begin our review of your submitted examination.
Your letter indicated you are training approximately 14 candidates for the examination. Please inform us if the number of candidates declines below IO as this will impact the examination schedule. Please also inform us at your earliest opportunity if you discover you are unable to support the examination on the scheduled dates.
Once your staff has determined a schedule for examination development, please have them contact the Chief Examiner to arrange for a suitable examination outline submittal date for NRC review. The intent is for the examination outline to be submitted early in the examination development process. This is to preclude the need to make significant changes to developed examination material as a result of the NRC review of the outline.
David L. Pelton has been tentatively assigned as the Chief Examiner and can be reached at 630-829-9732.
A supplementary letter will be sent to the training department approximately 120 days prior to the examination outlining examination security expectations, listing the materials required by the NRC to conduct the examination, reconfirming the examination dates, and reconfirming the number of candidates you have in the training program. If you have any questions concerning this information, please contact David L. Pelton of my staff at 630-829-9732.
- 0. Kingsley In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www,nrc.aov/NRC/ADAMS/index.html (the Public Electronic Reading Room).
Sincerely, David E. Hills, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18 cc: W. Bohlke, Senior Vice President, Nuclear Services C. Crane, Senior Vice President - Mid-West Regional J. Cotton, Senior Vice President - Operations Support J. Benjamin, Vice President - Licensing and Regulatory Affairs R. Hovey, Operations Vice President J. Skolds, Chief Operating Officer K. Jury, Director - Licensing R. Helfrich, Senior Counsel, Nuclear DCD - Licensing G. Barnes, Site Vice President M. Schiavoni, Station Manager W. Riffer, Regulatory Assurance Supervisor M. Aguilar, Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer Chairman, Illinois Commerce Commission G. Kaegi, Training Department DOCUMENT NAME:
OFFICE RIII:DRS I P! RIII:DRS , I ,& RIII:DRS I NAME MABies:sd -/L- DLPelton /b)# DEHills D&
DATE 02/jK/02 02/19./02 0211do2 OFFICIAL RECORD COPY
- 0. Kingsley ADAMS Distribution:
AJ M DFT DMS6 RidsNrrDipmlipb GEG HBC ERD DRPlI I DRSlll PLBI JRKI DCT M. A. Bies, DRS
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 111 801 WARRENVILLE ROAD LISLE, ILLINOIS 60532-4351 Febhary 13, 2003 Mr. John L. Skolds, President Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
Dear Mr. Skolds:
In a telephone conversation on February 12, 2003, between Mr. P. Leheney, Exam Lead, and Mr. M. Bielby, Chief Examiner, arrangements were made for the administration of licensing examinations at the LaSalle County Station, Units 1 and 2, the weeks of May 19 and May 26, 2003. In addition, the NRC will make an examination validation visit to your facility the week of April 28, 2003.
As agreed during the telephone conversation, your staff will prepare the examinations based on the guidelines in Revision 8, Supplement 1, of NUREG-I021, "Operator Licensing Examination Standards for Power Reactors." The NRC regional office will discuss with your staff any changes that might be necessary before the examinations are administered.
To meet the above schedule, it will be necessary for your staff to furnish the examination outlines by March 5, 2003. The written examinations, operating tests, and the supporting reference materials identified in Attachment 2 of ES-201 will be due by March 31, 2003.
Pursuant to 10 CFR 55.40(b)(3), an authorized representative of the facility licensee shall approve the outlines, examinations, and tests before they are submitted to the NRC for review and approval. All materials shall be complete and ready to use. Any delay in receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be rescheduled.
In order to conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-402, and to make the simulation facility available on the dates noted above. In accordance with ES-302, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and levels) generated during the dynamic operating tests until the examination results are final.
Appendix E of NUREG-I021 contains a number of NRC policies and guidelines that will be in effect while the written examinations and operating tests are being administered.
, J. Skolds In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at htt~://vww.nrc.sov/reading-rm/adams.html(the Public Electronic Reading Room).
Sincerely, Roger D.' Lanksbury, Chief Operations Branch Division of Reactor Safety Docket Nos. 50-373; 50-374 License Nos. NPF-11; NPF-18 cc: Site Vice President - LaSalle County Station LaSalle County Station Plant Manager Regulatory Assurance Manager - LaSalle Chief Operating Officer Senior Vice President - Nuclear Services Senior Vice President - Mid-West Regional Operating Group Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Mid-West Regional Operating Group Manager Licensing - Clinton and LaSalle Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing M. Aguilar, Assistant Attorney General Illinois Department of Nuclear Safety State Liaison Officer Chairman, Illinois Commerce Commission J. Burns-Muntz, Training Department OFFICE Rill IU Rill IhJ I I NAME BPalagi:sd ep RLanksburye9&'
DATE 02//3/03 02/b/03 OFFICIAL RECORD COPY
J. Skolds ADAMS Distribution:
AJM DFT DMS6 RidsNrrDiprnIipb GEG HBC ERD DRPlll DRSlll PLBl JRKI DCT M. A. Bies, DRS
Exelon Generation Company, LLC LaSalle County Station www.exeloncorp.com Nuclear 2601 North 21:Road Marseilles, IL 61341-9757 March 31, 2003 10 CFR 55.40 United States Nuclear Regulatory Commission Attention: NRC Region Ill Administrator 801 Warrenville Road Lisle, IL 60532-4351 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-I 1 and NPF-I 8 NRC Docket Nos. 50-373 and 50-374
Subject:
Submittal of Integrated Initial Operator Licensing Examination Materials Enclosed are the examination materials, which LaSalle County Station is submitting in support of the Initial License Examination scheduled for the period of May 19, 2003, through May 30, 2003 at LaSalle County Station.
This submittal includes the Senior Reactor Operator and Reactor Operator Written Examinations, Job Performance Measures, and Integrated Plant Operation Scenario Guides.
These examination materials have been developed in accordance with NUREG -1 021, Operator Licensing Examination Standards, Revision 8, Supplement 1. Please note that reference materials are attached to each individual examination question or item.
Some minor modifications have been made to the Integrated Operating and Written Examination Outline with regards to the operational scenarios in order to improve balance and content. These changes improve examination quality and are in compliance with NUREG -1 021, Revision 8, Supplement 1.
Some modifications or adjustments to the examination material may be required due to procedural changes.
March 31,2003 U.S. Nuclear Regulatory Commission Page 2 In accordance with NUREG -1021, Revision 8, Supplement I, Section ES-201, Initial Operator Licensing Examination Process, please ensure that these materials are withheld from public disclosure until after the examinations are complete.
Should you have any questions concerning this letter, please contact Mr. Glen Kaegi, Regulatory Assurance Manager, at (815) 415-2800. For questions concerning examination outlines, please contact Patrick Leheney at (815) 415-2534.
Respectfu Ily, George P. Barnes Site Vice President LaSalle County Station
Enclosures:
(Hand delivered to Michael Bielby, Chief Examiner, NRC Region 111)
Administrative Topics Outline (Form ES-301-1)
Control Room Systems and Facility Walk-Through Test Outline (Form ES-301-2)
Transient and Event Checklist (Form ES-301-5)
Scenario Outlines (Form ES-D-1)
BWR SRO Examination Outline (Forms ES-401-1 and ES-401-5)
BWR RO Examination Outline (Forms ES-401-2 and ES-401-5)
RO/SRO Composite Examination with references attached Control Room Systems and Facility Walk-Through Job Performance Measures with references attached Administrative Topic Job Performance Measures with references attached Integrated Plant Operation Scenario Guides Examination Security Agreements (Form ES-201-3)(0nlythe first four (4) columns)
Operating Test Quality Checklist (Form ES-301-3)
Simulator Scenario Quality Checklist (Form ES-301-4)
Competencies Checklist (Form ES-301-6)
Written Exam Quality Checklist (Form ES-401-7)
Record of Rejected WAS (Form ES-401-10) cc: Chief, NRC Operator Licensing Branch (w/o enclosures)
Senior Resident Inspector - LaSalle County Station (w/o enclosures)
Exelon Generation Company, LLC LaSalle County Station www.exeloncorp.com Nuclear 2601 North 21"Road Marseilles, IL 61341-9757 May 30, 2002 United States Nuclear Regulatory Commission Attention: NRC Region I l l Administrator 801 Warrenville Road Lisle, IL 60532-4351 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
2003 LaSalle NRC Initial License Exam In accordance with NUREG 1021, ES 402 Section E, LaSalle County Station has completed a facility review of the 2003 LaSalle NRC Initial License Exam, administered between May 19,2003 and May 23,2003.
During the review, facility representatives identified the issues listed in Attachment 1. Please consider these comments in the grading of the written examinations .
Should you have any questions concerning this letter, please contact Mr. Glen T. Kaegi, Regulatory Assurance Manager, at (815) 41 5-2800.
Respectfully, George P. Barnes Site Vice President LaSalle County Station Attachment cc: NRC Document Control Desk NRC Senior Resident Inspector - LaSalle County Station
Attachment 1
- 1. The following question was identified as having the incorrect answer identified.
RO/SRO Question 56 The answer key stated the correct answer was C. The correct answer is D.
The explanation in the answer key supports D as the correct amswer.
- 2. The following question was identified as having an incorrect answer identified after review with the examinees and discussion with the facility representative.
SRO Question 80 The question asked the minimum water level in the fuel pool that would still allow fuel movement. Validation of the exam looked strictly at the Technical Specification requirement (22 1.4 feet) and not the EAL threshold value of 23 feet as stated in MU1 1 of the LaSalle Annex. This level would require an Unusual Event classification and support the action of stopping fuel moves.
The correct answer was changed from C to D.
LaSalle Annex Exelon Nuclear RECOGNITION CATEGORY SYSTEM MALFUNCTIONS MU11 INITIATING CONDITION Unplanned decrease in Spent Fuel Pool level.
EAL THRESHOLD VALUE
- 1. Spent Fuel Pool water (reference level 841 8).
MODE APPLICABlLlTY ALL BASIS: (References)
Classification of an Unusual Event for the threshold values is warranted as a precursor to more serious events and thus is a potential degradation of the level of safety of the plant. The events described as threshold values tend to have a long lead time relative to a radiological release and thus the threat to public health and safety is very low. The levels provided are the minimum allowed by Technical Specifications.
Level taken from procedures LOS-AA-W1 & LOP-SF-06.
September 2002 LS 3-73 EP-AA- 1005 (Revision 14)
LaSalle Annex Exelon Nuclear SYSTEM MALFUNCTIONS (cont.)
MS7 Loss of decay heat rcmoval and core U 7 Inability to establish or maintain Mode 4 MU7 High coolant activity uncovery EAL\LThmholdValue IAL Threshold V a h ~ EN. Threshold Value
- 1. Reactor core is or will bc uncovcIcd . Inabilityto cstablish Mode 4 when required. I. OKgs system isolationduc to valid Ongas radiation monitor high trip AND OR OR
- 2. h y ofthe Follomng . Inabilityto maintain Mode 4 conditions % indicatedby E17HER
- 2. Coolan1Mivity 2 4.0 wCUg 1-131 dorc equlvlleot Reactor c ~ l a r dtempralw > ZOO '
F Temperature i n c m e that exceeds ZOO OF.
OR OR Unwntrolled temperature nsc approachingZOO O F Uncontrolled temperaturerise approachingZOO OF.
MU8 RCS leakage w # 3 I Table MI Onsitc Communications Equipment I Table MZ Offslte Communications Equipment EAL Threshold Valuf:
I. Uni&niified RCS leakage into UIC primary containmentz 10 g p a
. Plant radio system Plant paging system All telephone lines (commercial and microwave)
NARS 2.
OR Total RCS I d a g e (identified + unidcnlilied) into prirnary containmcnl
. 35 gpln Sound power phones In-plant tclcphones HPN MU9 Unplanned loss of all o n s i c and a Cellular Phones olfsite communications capabilities EAL Thrcshold Value; I. Loss of all onsite comnunications equipment, Tsble MI OR
- 2. Loss orall onsite communicationscapability, Table MZ MU10 Inability IO reach rcquircd made within Technical Specification time limics EAL Thrcshold Value:
Plant k NX b ~ ~ ~(0grequid ht n d e pa T.S.Action Starnmu in h requid urn.
U l 1 Major fucl damage or fuel unwvcry MU 11 UnplaMcd defrear in S p i Fuel Pool level in the Spent Fuel Pool
.ALThreshold Value
> 10 R/hr on Refuel Flwr Radmon Monitors OD21-KUA EAL Threshold Value:
G F o e l Pool wdter level L 23 IL (level 841' 8") )
-[
!. Report of visual observation of a rapid decrease of water level such that inadiated fuel is predicted IO become uncovered tl.412 UnplannodlwofRefuelmgCawtyVohune A L Threshold Values,
@&#g MU12 UnplaMedlussofRefuelmgCantyhcl EAL Thrcshold Value I Report ofa rapiddecrease of water level such that inadlatd fuel will bcwme uncovered Inability io maintain Refueling Cavity Lcwel OR 2 22 rL (ICVCI M I * ~1'7n b o v ~I ~ C VC~VI nangc.
- 2. Reactor vssel level S -161" (top OfAcuve Fuel) t 55" on Shutdown Level Range (reference level 845 feet - 7 inches)
Plant Modes (white boxes indicae applicablc modcs)
September 2002 LS 3-11 EP-AA-1005 (Revision 14)
Enclosure 2 Post Examination Comments and Resolution (continued)
Which of the following is the minimum water level that would meet the requirements to perform this evolution?
above the spent fuel seated in the fuel pool.
A. 20 feet B. 21 feet C. 22 feet D. 23 feet Comment: The question as,,ed the minimum water level in the fuel poc at would still allow fuel movement. Validation of the exam looked strictly at the Technical Specification requirement e21.4 feet) and not the EAL threshold value of 23 feet as stated in the MU11 of the LaSalle Annex. This level would require an Unusual Event classification and support the action of stopping fuel moves. The correct answer was changed from C to D.
Resolution: NRC examiner, licensee training, and an operations representative agreed during the facility written examination review that the question term minimum water level that would meet the requirements... was sufficient to illicit the water level identified in Technical Specification 3.7.8. The EAL (Emergency Action Level) MU1Iis based on an unplanned decrease in Spent Fuel Pool level which was not part of the initial conditions. The question basically asked what was the minimum water level requirement for spent fuel movement, and that minimum water level is specified by Technical Specifications. There was no reference documentation submitted that would prevent operators from performing a planned decrease of spent fuel pool water level (ie, for pool clarity) below the MU1Ilevel of 23 feet as long as they did not exceed the minimum Technical Specification level of 21 feet 4 inches. There were no applicant concerns recorded for this question during the written examination administration.
As a result, the reference supports the original answer C not D.
8
. 3 Enclosure 2 Post Examination Comments and Resolution Question #56 on the Reactor Operator and Senior Reactor Operator examination was reviewed:
QUESTION: 056 (1.00)
Unit 1 Primary Containment Chillers A & C are off.
Unit 1 Primary Containment Chiller B trips.
Which below describes...
(I) the status of containment cooling, AND (2) the expected IMMEDIATE (within one minute) effect on Unit 1 Drywell pressure?
A. (I) All cooling is lost.
(2) Drywell pressure will rise.
- 6. (I) All cooling is lost.
(2) Drywell pressure will remain constant.
C. (1) Limited cooling is still maintained.
(2) Drywell pressure will rise.
D. (I) Limited cooling is still maintained.
(2) Drywell pressure will remain constant.
Comment: The answer key stated the correct answer was C. The correct answer is D. The explanation in the answer key supports ID as the correct answer.
Resolution: The lesson plan reference submitted (with applicable paragraph circled) for the question was entitled 096 Primary Containment Cooling, page 16 of 56, paragraph 7. Chiller Unit Trip, LIC Objective 096.00.12. The reference does not support question answer D. As stated in the reference, the Holdup Tank provides enough cooling to allow starting standby equipment; however, the same paragraph reference also states that Drywell air temperature and pressure will begin to rise when the chiller unit trips. As a result, the reference supports the original answer C.
Question #80 on the Senior Reactor Operator examination was reviewed:
QUESTION: 080 (I .OO)
Unit 1 is Refuel.
Spent fuel movements within the Unit 1 Spent fuel pool are in progress.
7