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Category:Letter
MONTHYEARIR 05000341/20230042024-02-0505 February 2024 Integrated Inspection Report 05000341/2023004 ML23341A1852023-12-0808 December 2023 Acknowledgement of Response to NRC Inspection Report 05000341/2023402 and Disputed Non-Cited Violation ML23310A1492023-12-0808 December 2023 Issuance of Amendment No. 227 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements IR 05000341/20230102023-12-0808 December 2023 Nbsp;Biennial Problem Identification and Resolution Inspection Report 05000341/2023010 IR 05000016/20230012023-12-0101 December 2023 NRC Inspection Report No. 050-00016/2023-001 (Drss) - Enrico Fermi Atomic Power Plant, Unit 1 ML23334A1902023-12-0101 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000341/2024010 ML23335A0062023-12-0101 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000341/2024002 IR 05000341/20230032023-11-0707 November 2023 Integrated Inspection Report 05000341/2023003 and 07200071/2023001 ML23297A0512023-10-30030 October 2023 Issuance of Amendment No. 226 Regarding Revision of Technical Specifications 3.8.1, AC Sources - Operating (Exigent Circumstances) ML23311A3482023-10-20020 October 2023 DTE Electric Company (DTE) - Submittal of the Renewed Fermi 3 Michigan Department of Environmental, Great Lakes, and Energy (EGLE) National Pollutant Discharge Elimination System (NPDES) Permit No. MI0058892 ML23272A1552023-10-10010 October 2023 Letter to Licensee and Federal Register Notification of Amendment to Renewed Facility Operating License and Proposed No Significant Hazards Consideration Determination (Exigent Circumstances) (EPID L-2023-LLA-0134) (Letter) ML23283A0222023-10-0909 October 2023 Follow Up to Fermi Unit 2 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval ML23276B4542023-10-0505 October 2023 Cyber Security Inspection Report 05000341/2023402 ML23243A8852023-09-18018 September 2023 Issuance of Amendment No. 225 Regarding Revision of Technical Specifications 3.7.2, Emergency Equipment Cooling Water, Emergency Equipment Service Water and System and Ultimate Heat Sink (Exigent Circumstances) ML23248A2242023-09-0707 September 2023 Regulatory Audit in Support of Review of License Amendment Request for a Risk-Informed Approach for Addressing the Effects of Debris on ECCS Strainer Performance ML23223A2242023-08-29029 August 2023 Individual Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing (Exigent Circumstances) ML23237B4332023-08-25025 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI IR 05000341/20230052023-08-24024 August 2023 Updated Inspection Plan for Fermi Power Plant, Unit 2 (Report 05000341/2023005) ML23229A0122023-08-17017 August 2023 Issuance of Amendment No. 224 to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 (Emergency Circumstances) IR 05000341/20233012023-08-16016 August 2023 NRC Initial License Examination Report 05000341/2023301 ML23227A2212023-08-15015 August 2023 Emergency Application to Revise Technical Specifications to Adopt TSTF 568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23219A1792023-08-0707 August 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Fermi Power Plant, Unit 2 IR 05000341/20230022023-08-0404 August 2023 Integrated Inspection Report 05000341/2023002 ML23216A1872023-08-0404 August 2023 Submittal of Relief Request RR-A25 for Extended License Period ML23206A1272023-07-26026 July 2023 NOED for Fermi Power Plant, Unit Two Technical Specification 3.7.2, Emergency Equipment Cooling Water Emergency Equipment Service Water System and Ultimate Heat Sink ML23200A2552023-06-28028 June 2023 Post-Exam Letter with Comments and Exam Analysis IR 05000341/20230012023-06-28028 June 2023 Integrated Inspection Report 05000341/2023001 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23122A2332023-06-26026 June 2023 Issuance of Amendment No. 223 Regarding Revision of Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements IR 05000341/20220102023-06-21021 June 2023 Reissue Fermi Power Plant, Unit 2, Design Basis Assurance Inspection (Teams) Inspection Report 05000341/2022010 ML23166A0892023-06-15015 June 2023 Operator Licensing Examination Approval Fermi Power Plant, June 2023 ML23158A1332023-06-0808 June 2023 Notice of Enforcement Discretion (NOED) for Fermi Power Plant, Unit Two (EPID L-2023-LLD-0000) Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/ Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink ML23130A1032023-05-17017 May 2023 Regulatory Audit Summary Regarding License Amendment Request to Revise Technical Specification Surveillance Requirements Relating to Emergency Diesel Generator Voltage and Frequency IR 05000341/20234022023-05-0101 May 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000341/2023402 ML23118A3612023-05-0101 May 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000341/2023402 ML23114A1172023-05-0101 May 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23115A4152023-04-25025 April 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Fermi Power Plant, Unit 2 ML23124A2032023-04-10010 April 2023 DTE Electric Company Submittal of Fermi 3 Periodic Reports ML23200A1842023-04-0606 April 2023 Proposed Exam Submittal Letter IR 05000341/20230112023-04-0606 April 2023 Triennial Fire Protection Inspection Report 05000341/2023011 IR 05000341/20234012023-03-17017 March 2023 Security Baseline Inspection Report 05000341/2023401 ML23074A1972023-03-16016 March 2023 Confirmation of Initial License Examination February 2024 IR 05000341/20220062023-03-0101 March 2023 Annual Assessment Letter for Fermi Power Plant, Unit 2 (Report 05000341/2022006) ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22325A2992023-02-24024 February 2023 Audit Plan in Support of Review of License Amendment Request to Revise Technical Specification Surveillance Requirements Relating to Emergency Diesel Generator Voltage and Frequency ML23039A1552023-02-14014 February 2023 Integrated Inspection Report 05000341/2022004 IR 05000341/20224032023-02-13013 February 2023 Security Baseline Inspection Report 05000341/2022403 ML23200A2162023-01-20020 January 2023 Outline Submittal Letter 2024-02-05
[Table view] Category:License-Operator
MONTHYEARIR 05000341/20233012023-08-16016 August 2023 NRC Initial License Examination Report 05000341/2023301 ML23213A0302023-08-11011 August 2023 Form 5.1-1 Postexamination Check Sheet ML23212A8732023-07-31031 July 2023 Form 1.3-1 Examination Security Checklist ML23200A2182023-06-28028 June 2023 Form 3.4-1 Scenario Events & Evolutions Checklist RO & SRO Final ML23200A2552023-06-28028 June 2023 Post-Exam Letter with Comments and Exam Analysis ML23200A2572023-06-19019 June 2023 Form 2.1-1 Examination Prep Checklist ML23200A2562023-06-19019 June 2023 IP 21 Operator Licensing Exam Schedule ML23166A0892023-06-15015 June 2023 Operator Licensing Examination Approval Fermi Power Plant, June 2023 ML23200A1852023-06-0202 June 2023 Form 2.3-2 Operating Test Quality Checklist ML23200A1862023-06-0202 June 2023 Form 2.3-4 Written Exam Quality Checklist ML23200A1842023-04-0606 April 2023 Proposed Exam Submittal Letter ML23074A1972023-03-16016 March 2023 Confirmation of Initial License Examination February 2024 ML23200A2212023-02-0808 February 2023 Form 2.3-1 Outline Quality Checklist ML23200A2162023-01-20020 January 2023 Outline Submittal Letter ML23200A2172023-01-20020 January 2023 Form 3.4-1 Scenario Events & Evolutions Checklist RO & SRO Draft ML22322A1082022-11-18018 November 2022 Confirmation of Initial License Examination ML21258A0602021-09-15015 September 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21327A1702021-06-16016 June 2021 ES-401-6 ML21327A4272021-06-16016 June 2021 Post Exam Submittal Letter ML21327A4252021-06-16016 June 2021 ES-403-1 ML21327A4242021-06-16016 June 2021 ES-201-3 ML21327A4212021-06-16016 June 2021 ES-201-1 ML21327A1062021-06-16016 June 2021 Proposed Exam Submittal Letter ML21327A1042021-06-16016 June 2021 ES-301-4 ML21327A0952021-06-16016 June 2021 ES-301-3 ML21327A0922021-06-16016 June 2021 ES-301-6 ML21326A1242021-06-16016 June 2021 Licensee Outline Submittal Letter ML21326A1212021-06-16016 June 2021 ES-301-5 ML21326A1202021-06-16016 June 2021 ES-201-2 ML21327A3362021-06-16016 June 2021 Handouts to Applicants (Summary) ML21327A3262021-06-16016 June 2021 Administered Written Exam with Answer Key ML21328A1382021-06-16016 June 2021 Proposed Admin JPMs ML21327A3212021-06-16016 June 2021 Administered Scenarios ML21328A1622021-06-16016 June 2021 Proposed Control Room and In-Plant JPMs ML21328A1642021-06-16016 June 2021 Proposed Scenarios ML21328A1662021-06-16016 June 2021 Proposed Written Exam with Answer Key ML21327A3082021-06-16016 June 2021 Administered Admin JPMs ML21327A3422021-06-16016 June 2021 Modified Question Source Information ML21327A3142021-06-16016 June 2021 Administered Control Room and In-Plant JPMs ML21120A0202021-05-0303 May 2021 Operator Licensing Examination Approval IR 05000341/20203022021-03-18018 March 2021 NRC Initial License Examination Report 05000341/2020302 ML22158A1462021-02-0505 February 2021 Fer 2020 Ile ES-301-7 Operating Test Review Worksheet-Final ML22158A1302021-02-0505 February 2021 Fer 2020 ES-201-1 Rev 11 ML22158A1332021-02-0505 February 2021 Fer 2020 Ile Final Es 201-3 ML22158A1382021-02-0505 February 2021 Fer 2020 Ile Es 403-1 RO-SRO Written Exam Grading Quality Checklist ML22158A1582021-02-0505 February 2021 Fer 2020 Ile NRC ES-401-4 Record of Rejected KAs Rev 11 2023-08-16
[Table view] Category:Part 55 Examination Related Material
MONTHYEARIR 05000341/20233012023-08-16016 August 2023 NRC Initial License Examination Report 05000341/2023301 ML23213A0302023-08-11011 August 2023 Form 5.1-1 Postexamination Check Sheet ML23212A8732023-07-31031 July 2023 Form 1.3-1 Examination Security Checklist ML23200A2182023-06-28028 June 2023 Form 3.4-1 Scenario Events & Evolutions Checklist RO & SRO Final ML23200A2552023-06-28028 June 2023 Post-Exam Letter with Comments and Exam Analysis ML23200A2572023-06-19019 June 2023 Form 2.1-1 Examination Prep Checklist ML23200A2562023-06-19019 June 2023 IP 21 Operator Licensing Exam Schedule ML23166A0892023-06-15015 June 2023 Operator Licensing Examination Approval Fermi Power Plant, June 2023 ML23200A1852023-06-0202 June 2023 Form 2.3-2 Operating Test Quality Checklist ML23200A1862023-06-0202 June 2023 Form 2.3-4 Written Exam Quality Checklist ML23200A1842023-04-0606 April 2023 Proposed Exam Submittal Letter ML23074A1972023-03-16016 March 2023 Confirmation of Initial License Examination February 2024 ML23200A2212023-02-0808 February 2023 Form 2.3-1 Outline Quality Checklist ML23200A2162023-01-20020 January 2023 Outline Submittal Letter ML23200A2172023-01-20020 January 2023 Form 3.4-1 Scenario Events & Evolutions Checklist RO & SRO Draft ML22322A1082022-11-18018 November 2022 Confirmation of Initial License Examination ML21258A0602021-09-15015 September 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21327A1702021-06-16016 June 2021 ES-401-6 ML21326A1202021-06-16016 June 2021 ES-201-2 ML21326A1212021-06-16016 June 2021 ES-301-5 ML21326A1242021-06-16016 June 2021 Licensee Outline Submittal Letter ML21327A0922021-06-16016 June 2021 ES-301-6 ML21327A0952021-06-16016 June 2021 ES-301-3 ML21327A1042021-06-16016 June 2021 ES-301-4 ML21327A1062021-06-16016 June 2021 Proposed Exam Submittal Letter ML21327A4212021-06-16016 June 2021 ES-201-1 ML21327A4242021-06-16016 June 2021 ES-201-3 ML21327A4252021-06-16016 June 2021 ES-403-1 ML21327A4272021-06-16016 June 2021 Post Exam Submittal Letter ML21327A3362021-06-16016 June 2021 Handouts to Applicants (Summary) ML21327A3262021-06-16016 June 2021 Administered Written Exam with Answer Key ML21327A3212021-06-16016 June 2021 Administered Scenarios ML21327A3142021-06-16016 June 2021 Administered Control Room and In-Plant JPMs ML21327A3082021-06-16016 June 2021 Administered Admin JPMs ML21328A1662021-06-16016 June 2021 Proposed Written Exam with Answer Key ML21328A1642021-06-16016 June 2021 Proposed Scenarios ML21328A1622021-06-16016 June 2021 Proposed Control Room and In-Plant JPMs ML21327A3422021-06-16016 June 2021 Modified Question Source Information ML21328A1382021-06-16016 June 2021 Proposed Admin JPMs ML21120A0202021-05-0303 May 2021 Operator Licensing Examination Approval IR 05000341/20203022021-03-18018 March 2021 NRC Initial License Examination Report 05000341/2020302 ML22158A1582021-02-0505 February 2021 Fer 2020 Ile NRC ES-401-4 Record of Rejected KAs Rev 11 ML22158A1382021-02-0505 February 2021 Fer 2020 Ile Es 403-1 RO-SRO Written Exam Grading Quality Checklist ML22158A1332021-02-0505 February 2021 Fer 2020 Ile Final Es 201-3 ML22158A1302021-02-0505 February 2021 Fer 2020 ES-201-1 Rev 11 ML22158A1642021-02-0505 February 2021 Ile Outline Review Comments 2023-08-16
[Table view] |
Text
July 11, 2008
Mr. Jack M. Davis Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166
SUBJECT:
ERRATA TO FERMI POWER PLANT, UNIT 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000341/2008301
Dear Mr. Davis:
On March 25, 2008, the U.S. Nuclear Regulatory Commission (NRC) issued Initial License Examination Report 05000341/2008301 (ML080880166) for your Fermi Power Plant, Unit 2. A report enclosure for Post Examination Comments with NRC Resolution was omitted from the original report. In addition, the proposed vice administered RO and SRO written examinations were inadvertently identified as the administered examinations, uploaded to ADAMS and attached to the report. The enclosed errata contains the omitted enclosure and administered written examinations with answer key. The enclosure should be inserted as Enclosure 2A, the RO and SRO written examinations with answer key (ML081920353) should replace the RO and SRO written examinations with answer key in Enclosure 3 of Initial License Examination Report 05000341/2008301. Sincerely, /RA/
Hironori Peterson, Chief Operations Branch Division of Reactor Safety Docket No. 50-341 License No. NPF-43
Enclosures:
2A. Errata to Inspection Report No. 05000341/2008301(DRS) 3. RO and SRO written examinations with answer key See Attached Distribution
Mr. Jack M. Davis Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 - 210 NOC 6400 North Dixie Highway Newport, MI 48166
SUBJECT:
ERRATA TO FERMI POWER PLANT, UNIT 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000341/2008301
Dear Mr. Davis:
On March 25, 2008, the U.S. Nuclear Regulatory Commission (NRC) issued Initial License Examination Report 05000461/2008301 (ML080880166) for your Fermi Power Plant, Unit 2. A report enclosure for Post Examination Comments with NRC Resolution was omitted from the original report. In addition, the proposed vice administered RO and SRO written examinations were inadvertently identified as the administered examinations, uploaded to ADAMS and attached to the report. The enclosed errata contains the omitted enclosure and administered written examinations with answer key. The enclosure should be inserted as Enclosure 2A, the RO and SRO written examinations with answer key should replace the RO and SRO written examinations with answer key in Enclosure 3 of Initial License Examination Report 05000461/2008301. Sincerely, /RA/ Hironori Peterson, Chief Operations Branch Division of Reactor Safety
Docket No. 50-341 License No. NPF-43
Enclosures:
2A. Errata to Inspection Report No. 05000341/2008301(DRS) 3. RO and SRO written examinations with answer key See Attached Distribution
DOCUMENT NAME: G:\DRS\WORK IN PROGRESS\FER 2008 301 DRS OL ERRATA 1.DOC G Publicly Available G Non-Publicly Available G Sensitive G Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII E RIII NAME MBielby:co HPeterson
DATE 07/11/08 07/11/08 OFFICIAL RECORD COPY Letter to Jack M. Davis from Hironori Peterson dated July 11, 2008
SUBJECT:
ERRATA TO FERMI POWER PLANT, UNIT 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000341/2008301 cc w/encls: J. Plona, Vice President, Nuclear Generation K. Hlavaty, Plant Manager R. Gaston, Manager, Nuclear Licensing D. Pettinari, Legal Department Michigan Department of Environmental Quality M. Yudasz, Jr., Director, Monroe County Emergency Management Division Supervisor - Electric Operators T. Strong, State Liaison Officer Wayne County Emergency Management Division Letter to Jack M. Davis from Hironori Peterson dated July 11, 2008
SUBJECT:
ERRATA TO FERMI POWER PLANT, UNIT 2 NRC INITIAL LICENSE EXAMINATION REPORT 05000341/2008301 cc w/encls: J. Plona, Vice President, Nuclear Generation K. Hlavaty, Plant Manager R. Gaston, Manager, Nuclear Licensing D. Pettinari, Legal Department Michigan Department of Environmental Quality M. Yudasz, Jr., Director, Monroe County Emergency Management Division Supervisor - Electric Operators T. Strong, State Liaison Officer Wayne County Emergency Management Division DISTRIBUTION
- Tamara Bloomer
Lois James Justin Poole RidsNrrDirsIrib Resource Mark Satorius Kenneth Obrien Jared Heck Carole Ariano Linda Linn Cynthia Pederson (hard copy - IR's only) DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports@nrc.gov
Enclosure 2A 1ERRATA TO NRC INTEGRATED INSPECTION REPORT 05000341/2008301 POST EXAMINATION COMMENTS AND RESOLUTIONS RO Question Number 49 Which malfunction below, were it to occur during a Design Basis Loss of Coolant Accident (DBA-LOCA), would threaten Primary Containment Integrity?
Consider each malfunction, independently, as the ONLY malfunction. Assume that NO operator action is taken in response to the malfunction.
A. Safety Relief Valve B2104-F013H has a break in its Tailpipe located in the Drywell.
B. SST 65 TRIPS and Emergency Diesel Generator 13 FAILS TO START.
C. ALL Drywell Spray Valves FAIL TO OPEN when attempting to initiate Drywell Spray.
D. ALL Torus to Drywell Vacuum Breaker Check Valves FAIL TO OPEN when Drywell Spray is in operation.
Answer: D Applicant Comment
An applicant commented that answer "C" should also be accepted as correct.
Fermi 2 is a Mark 1 Containment and is susceptible to the phenomenon of "chugging." (See Appendix B, Revision 2 of the Emergency Procedure Guidelines (EPG), page B-7-35, for additional information regarding the following.)
Following a DBA-LOCA (Design Basis Accident-Loss of Coolant Accident), Drywell Pressure (DW/P) would rapidly increase and force steam and non-condensible gasses from the Drywell (DW) into the Torus. Torus Pressure would rapidly rise and exceed the Suppression Chamber Spray Initiation Pressure (SCIP), which is 9 psig for Fermi 2. Once the Torus Pressure exceeds 9 psig, the EPGs assume that a large fraction (95%) of the non-condensible gases (nitrogen inerting the DW) in the DW have been transferred to the Torus. Once this occurs, chugging becomes a primary concern.
Chugging is defined as the repeated collapsing, and reformation, of steam bubbles at the Downcomer Vent opening. When the steam bubbles collapse at the exit of the Downcomers, the rush of water drawn into the Downcomer, to fill the void, induces severe stresses at the junction of the Downcomers and Vent Header in the Mark 1 Containment. Repeated application of such stresses could cause fatigue failure of these joints, thereby creating a direct path between the Drywell and Suppression Chamber. Steam discharged through the Downcomers could then bypass the Suppression Pool and directly pressurize the Primary Containment.
Enclosure 2A 2Initiating Drywell Sprays when Torus Pressure exceeds 9 psig will cause the non-condensible gasses to be drawn back into the Drywell atmosphere, thereby preventing "chugging."
With Drywell Sprays not available (as stated in distractor "C") chugging could not be prevented and containment integrity could be threatened as described in the EPGs.
Facility Proposed Resolution
- The question grading for the exam should be changed to accept both "C" and "D" as correct answers. This is due to the additional information identified during the post-exam review. This question is correct, as written, and does not require any changes prior to incorporation into the exam bank.
NRC Resolution
- Upon review of the question, the applicant comment, and the facility proposed resolution, it was decided to accept both "C" and "D" as correct answers.
The Fermi 2 UFSAR, Section 6.2.1.3.2, states that for a DBA-LOCA, [Drywell] Sprays are not needed to keep drywell pressure below the design limit which would imply the primary containment integrity was not threatened. However, the issue of chugging is not addressed. As identified by the applicant, the BWROG EPGs/SAGs, Appendix B, Section 7, states that Drywell Sprays are required to preclude chugging when the SCIP is exceeded. Chugging results in an application of cyclic stresses to the joint between the downcomer and vent pipe that could cause fatigue failure of these joints. A review of NUREG 0661, Mark 1 Containment Long-Term Program, states that chugging can occur for DBA-LOCA, Intermediate and Small Break LOCAs. The potential for chugging exists for a longer period of time in the Intermediate and Small Break LOCAs and thus has more potential to defeat the primary containment integrity.
The term "threat" used in the question stem is not quantitatively defined. Any loss of preventive measure to reduce containment pressure during a LOCA could be considered an increase in threat to the primary containment integrity. Both choices "C" and "D" could be considered a threat to primary containment integrity.
RO Question Number 63 Which ONE of the following is the reason for having the Main Steam Tunnel High Temperature Isolation?
The main Steam Tunnel High Temperature Isolation will:
A. LIMIT the escape of radioactivity from the MSL Tunnel to the Reactor Building HVAC system. B. PREVENT exceeding the Environmental Qualification temperature limits on the MSIV control solenoids.
Enclosure 2A 3C. PROTECT the integrity of the Secondary Containment AND ensure the continued operability of safe shutdown equipment. D. MINIMIZE radioactive releases to the environment AND limit the inventory loss from the reactor under all accident conditions.
Answer: D Applicant Comment
- An applicant commented that answer "C" should also be accepted as correct.
The term reason [leads one] to not look for the basis of the Main Steam Tunnel High Temperature Auto Isolation. The stem should have stated the auto isolation and the basis per 10 CFR 100. This allowed Answer "C" to also be correct. Answer "C" is a reason to isolate MSIVs [Main Steamline Isolation Valves] manually. Since the stem doesn't state an auto isolation.
The Secondary Containment and Radioactive Release EOP purpose is to protect equipment important to safety in the Secondary Containment, to protect the integrity of the Secondary Containment, and to limit radioactivity release to and from the Secondary Containment.
Facility Proposed Resolution
- The question grading for the exam should be changed to accept both "C" and "D" as correct answers. The question originally had "basis" instead of "reason" in the stem. It was changed upon NRC request.
NRC Resolution
- Upon review of the question, the applicant comment, and the facility proposed resolution, it was decided to accept only the original correct answer.
The semantics of the question stem, as written, is clear in asking for the reason for the isolation, vice not a reason to isolate the Main Steam Tunnel. The term "Main Steam Tunnel High Temperature Isolation" uses capitol letters to infer and identify a specific automatic feature, and is referenced as such in the Fermi Technical Specifications. The term "basis" as used by technical specifications, provides the explanation or justification of why the automatic Main Steam Tunnel Isolation is required. The term "reason" as used in the question stem, is defined in the Merriam-Webster Collegiate Dictionary as "a statement offered in explanation or justification." The references supplied with the post examination comments for this question to support "C" as a correct answer were described as the "purpose" of the Secondary Containment Control and Radioactive Release EOP; however, the same reference for the question distractor described "C" as a "basis" type reference. Both references were used to address the "reason" for the Main Steam Tunnel High Temperature Isolation. As such, the terms "basis," "reason,"
and "purpose" have been interchangeably used by both the examiners and the licensee to ask and answer the question.
Enclosure 2A 4The post examination comment identified "C" as a correct answer and referenced the Secondary Containment Control and Radioactive Release EOP purpose as a reason to isolate the Main Steam Tunnel. However, the EOP incorporates the purpose of various systems and designs, and is not focused on a specific isolation. The reason (bases, or purpose) of isolating the Main Steam Tunnel on High Temperature was addressed by the licensee supplied documents ST-OP-315-0048 and Technical Specification Basis 3.3.6.1-1, Revision 38, which support only "D" as the only correct answer.
Enclosure 3 WRITTEN EXAMINATIONS AND ANSWER KEYS (RO/SRO)
RO/SRO Initial Examination ADAMS Accession # ML081920353.