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Category:Letter type:LIC
MONTHYEARLIC-23-0007, Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information2023-12-0606 December 2023 Response to Fort Calhoun, Unit 1 & Independent Spent Fuel Storage Installation Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements Request for Additional Information LIC-23-0005, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 20232023-08-24024 August 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - 2nd Request for Additional Information (EPID L-2021-LIT-0000) June 2, 2023 LIC-23-0004, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2023-04-20020 April 2023 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-23-0003, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2023-03-15015 March 2023 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-23-0001, Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information2023-02-27027 February 2023 Response to Fort Calhoun Station, Unit No. 1 - Review of License Amendment Request to Add License Condition to Include License Termination Plan Requirements - Request for Additional Information LIC-23-0002, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2023-02-20020 February 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-22-0010, Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information2022-06-15015 June 2022 Response to Fort Calhoun Station, Unit No. 1 - Review of License Termination Plan Requirements - Request for Additional Information LIC-22-0005, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2022-04-20020 April 2022 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-22-0009, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2022-03-30030 March 2022 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-22-0006, Reactor Head Disposition Project Overview2022-03-17017 March 2022 Reactor Head Disposition Project Overview LIC-22-0004, Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report2022-02-17017 February 2022 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report LIC-21-0008, Organizational and Management Change2021-10-28028 October 2021 Organizational and Management Change LIC-21-0007, ISFSI Only Emergency Plan Update2021-09-0808 September 2021 ISFSI Only Emergency Plan Update LIC-21-0004, Radiological Effluent Release Report and Radiological Environmental Operating Report2021-04-29029 April 2021 Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-21-0003, Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report2021-03-30030 March 2021 Independent Spent Fuel Storage Installation - 2021 Annual Decommissioning Funding / Irradiated Fuel Management Status Report LIC-21-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2021-02-22022 February 2021 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0015, Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092)2020-07-29029 July 2020 Correction to Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report 2019 (ML20121A092) LIC-20-0014, Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2020-07-15015 July 2020 Submittal of Revision 8 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-20-0012, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2020-05-18018 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration and Certification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool LIC-20-0011, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-05-0707 May 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0009, (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report2020-04-30030 April 2020 (FCS) Radiological Effluent Release Report and Radiological Environmental Operating Report LIC-20-0008, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-04-13013 April 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0006, (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2020-03-26026 March 2020 (Fcs), Unit 1, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E LIC-20-0004, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-03-10010 March 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-20-0003, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2020-02-27027 February 2020 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-20-0002, Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan2020-02-27027 February 2020 Independent Spent Fuel Storage Installation - Submittal of Revision 7 to Physical Security Plan LIC-20-0001, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2020-02-0606 February 2020 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0025, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-12-19019 December 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0007, Post-Shutdown Decommissioning Activities Report2019-12-16016 December 2019 Post-Shutdown Decommissioning Activities Report LIC-19-0021, Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme2019-11-20020 November 2019 Independent Spent Fuel Storage Installation - Response to Request for Additional Information License Amendment for ISFSI-only EP and EAL Scheme LIC-19-0022, Independent Spent Fuel Storage Installation (ISFSI) Cask Registration2019-11-18018 November 2019 Independent Spent Fuel Storage Installation (ISFSI) Cask Registration LIC-19-0018, Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP)2019-11-14014 November 2019 Submittal of Revision 6 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) LIC-19-0020, Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis2019-10-17017 October 2019 Independent Spent Fuel Storage Installation - Updated Information Submittal and Revision 1 of the Blast Analysis LIC-19-0017, Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 20042019-08-0808 August 2019 Clarification to Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 An LIC-19-0010, License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associa2019-05-20020 May 2019 License Amendment Request (LAR) 19-03; Revised Fort Calhoun Station License in Support of the Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated LIC-19-0008, Submittal of 2018 Annual Report2019-04-0404 April 2019 Submittal of 2018 Annual Report LIC-19-0004, Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP)2019-03-28028 March 2019 Independent Spent Fuel Storage Installation - Submittal of Revision 4 to Physical Security Plan (PSP) LIC-19-0005, 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report2019-03-28028 March 2019 2019 Annual Decommissioning Funding I Irradiated Fuel Management Status Report LIC-19-0001, License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2019-02-28028 February 2019 License Amendment Request (LAR) 19-01: Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme LIC-19-0003, Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation R2019-02-28028 February 2019 Revised Response to Orders for Interim Safeguards and Security Compensatory Measures and Implementation of Additional Security Measures Associated with Access Authorization for Fort Calhoun Station Dated 9 November, 2004 and Relaxation Requ LIC-19-0002, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2019-01-0303 January 2019 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report LIC-18-0031, Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update2018-12-17017 December 2018 Independent Spent Fuel Storage Installation - Transmittal of Emergency Plan Update LIC-18-0030, Request for Partial Site Release Phase 22018-11-12012 November 2018 Request for Partial Site Release Phase 2 LIC-18-0028, Letter of Intent to Submit Request for Additional Partial Site Release2018-10-18018 October 2018 Letter of Intent to Submit Request for Additional Partial Site Release LIC-18-0027, Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2018-10-0303 October 2018 Submittal of Foreign Ownership, Control or Influence Five-Year Renewal Filing and NRC Facility Clearance Update LIC-18-0003, License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool2018-09-28028 September 2018 License Amendment Request (LAR) 18-01; Revised Fort Calhoun Station Permanently Defueled Technical Specifications to Align to Those Requirements for Permanent Removal of Spent Fuel from Spent Fuel Pool LIC-18-0025, Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 20192018-07-19019 July 2018 Guarantee of Payment of Deferred Premiums for the Period of July 1, 2018 to June 30, 2019 LIC-18-0023, Fort Calhoun Station, Unit 1 Request for Partial Site Release2018-06-29029 June 2018 Fort Calhoun Station, Unit 1 Request for Partial Site Release LIC-18-0021, Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan)2018-06-0606 June 2018 Transmittal of Revision 3 to the Physical Security Plan (PSP) and Revision 4 to the FCS Protective Strategy (Safeguards Contingency Plan) LIC-18-0017, Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy2018-04-26026 April 2018 Submittal of Revision 2 to the Fort Calhoun Station (Fcs), Physical Security Plan (PSP) and Revision 3 of the FCS Protective Strategy 2023-08-24
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Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 July 15,2005 LIC-05-0086 Mr. Tom McKernon, Chief Examiner U. S. Nuclear Regulatory Commission Region IV 61 1 Ryan Plaza Drive, Suite 1000 Arlington, TX 76001
Reference:
Docket No. 50-285
Subject:
Technical Review of the Reactor Operator (RO) and Senior Reactor Operator (SRO) Licensing Written Examinations The Omaha Public Power District (OPPD) has evaluated the RO and SRO licensing examinations that OPPD administered at Fort Calhoun Station on July 8,2005. In accordance with NUREG- 1021 (Operator Licensing Examination Standards for Power Reactors), OPPDs comments justifying changes made to the examination answer keys are attached. A review of all questions missed by 50% or more of the license candidates revealed no weaknesses that require changes to the licensed operator initial training program.
The following items were provided to you prior to the exit meeting:
The graded written examinations and clean copies 0 The master examinations and answer keys 0 Question asked by and answers given to the applicants during the written examinations 0 The written examination seating chart 0 A completed form ES-403-1 0 An analysis of the preliminary and final examination results 0 A copy of the examination security agreement with signatures obtained thus far (the original will be sent when we have obtained all of the required signatures)
Employment with Equal Opportunity 4171
US Nuclear Regulatory Commission LIC-05-0086 Page 2 If you should have any questions, please contact myself or Mr. Dave Weaver at 402-533-6056.
Sincerely, Division Manager Nuclear Engineering Attachment c: B. S. Mallett, NRC Regional Administrator, Region IV (w/o Enclosures)
A. B. Wang, NRC Project Manager (w/o Enclosures)
John H m a , NRC Senior Resident Inspector (w/o Enclosures)
Document Control Desk (w/o Enclosures)
Attachment Justification for changes made to the exam keys for the RO and SRO written exams conducted at Fort Calhoun Station on 7/8/05
Comment on NRC Written Exam Administered July 8,2005 at Fort Calhoun Station Question Number 002 The question concerns the steps for restoration of letdown, per EOP-AOP Attachment 23, when RCS pressure is 1650 psia and rising following a small break LOCA that resulted in PPLS actuation. Step 3 of Attachment 23 states, IF Engineered Safeguards has NOT been reset, THEN reset Engineered Safeguards PER the applicable EOP/AOP Floating Step. Answer A, Reset Engineered Safeguards relays, is correct as indicated on the answer key.
EOP-03, Floating Step H provides is applicable for resetting Engineered Safeguards. In this situation, the following steps of Floating Step H require manipulation of control devices in order to restore letdown:
Step 3.c. Block PPLS-A and PPLS-B.
Step 3.e. Reset BOTH of the following relays:
86APPLS 86BPPLS Step 3.f. Reset BOTH of the following relays:
86AlPPLS 86BlPPLS Step 7. Reset ALL of the following relays:
86A/CIAS 86BUCIAS 86B/CIAS 86AKIAS Other steps in Floating Step H are not applicable in this situation, do not require manipulation of control devices under the conditions established by the question, or are not directly necessary for the restoration of letdown. This means that answer B, Block PPLS, Reset PPLS and CIAS lockout relays, is also a correct answer.
Therefore, we request that two responses, A or B, be accepted as correct answers for question number 002.
CONFIDENTIAL NRC EXAM MATERIAL Do Not Discuss with anyone who has not signed Exam Security Agreement
. ~
QUESTION NUMBER: 002 A small break LOCA resulted in PPLS actuation. The break has been isolated by closing a PORV block valve and pressurizer level has returned to 60% and is continuing to rise. RCS pressure is at 1650 psia and rising. Containment pressure is 0.5 psig. What action should be taken to allow the letdown isolation valves, HCV-204 and TCV-202 to be opened in this situation per EOP-AOP Attachment 23,"Restoration of Letdown"?
A!, Reset Engineered Safeguards relays.
B. Block PPLS, Reset PPLS and ClAS lockout relays C. Place the ClAS override switches for the valves in override.
D. Place the Defeat switch for HCV-204 in the defeat position.
Question 2 WA ## 000009 EA2.08 Ability to determine or interpret the following as they apply to a small break L0CA:Letdown isolation valve position indication RO Importance 2.9* SRO Importance 2.9* 10 CFR 55 Section 43.5 / 45.13 FCS Lesson Plan / Objective 0711-02 01.02 EXPLAIN, the manual and automatic functions of control valves in the CVCS.
KA#: 000009 EA2.08 Bank Ref #:
LP# / Objective: 07 11-02 0 1.02 Exam Level: RO Cognitive Level: HIGH Source: NEW
Reference:
EOP-03 Handout: NONE
EOP/AOP ATTACHMENTS Page 110 of 150 Attachment 23 Restoration of Letdown INSTRUCTIONS CONTINGENCY ACTIONS I
CAUTION Restoring letdown can result in adverse radiological conditions in the Auxiliary Building.
- 1. Verifv letdown restoration criteria are 1.I IF letdown restoration criteria are satisfied: NOT satisfied, THEN letdown can NOT be restored.
0 HPSl Stop and Throttle criteria are satisfied 0 Letdown is needed or desired 0 No LOCA exists in the CVCS
- 2. IF a UHE is the only event in progress, THEN Letdown may be restored by performing the following steps:
- a. Place HIC-101, Letdown Flow Controller, in MANUAL.
- b. Close HIC-101.
(continue)
R18
EOP/AOP ATTACHMENTS Page 111 of 150 Attachment 23 Restoration of Letdown INSTRUCTIONS CONTINGENCY ACTIONS
- 2. (continued)
I I
- c. Place PIC-210, Letdown Pressure Controller, in MANUAL.
- d. Throttle PCV-210 to approximately 10% OPEN.
e- -
Place BOTH of the following CIAS override switches to override:
"HCV-204 ClAS OVERRIDE" "TCV-202 CIAS OVERRIDE"
- f. GO TO Step 8.
- 3. IF Engineered Safeguards have NOT been reset, THEN reset Engineered Safeguards PER the applicable EOP/AOP Floating Step.
R18
EOP/AOP ATTACHMENTS Page 112 of 150 Attachment 23 Restoration of Letdown I NSTRUCTlONS CONTINGENCY ACTIONS
- 4. Place HIC-101, Letdown Flow Cbntroller, in MANUAL.
1
- 5. Clbse HIC-101.
- 6. Place PIC-210, Letdown Pressure Controller, in MANUAL.
- 7. Throttle PCV-210 to approximately 10%
OPEN.
- 8. ODen BOTH of the following Letdown Isolation Valves:
HCV-204 TCV-202
- 9. Initiate letdown using HIC-IO1 while adjusting PCV-210 to maintain letdown pressure approximately 300 psig.
IO. Balance charging and letdown to maintain desired pressurizer level.
End of Attachment 23 R18
EOP-03 Page 94 of 148 8.0 FLOATING STEPS H. RESET OF ENGINEERED SAFEGUARDS INSTRUCTIONS CONTINGENCY ACTIONS CAUTION Do not perform this floating step if CSAS relays are tripped to prevent damage to VIAS relays.
- 1. IF CPHS has actuated AND Containment pressure is less than or equal to 3.0 psig, THEN reset CPHS by performing the following steps:
NOTE Resetting CPHS Lockout Relays may reset SGIS. HCV-1105 and HCV-1106 may reopen.
- a. Reset BOTH of the following relays:
0 86A/CPHS 0 86B/CPHS
- b. Reset BOTH of the following relays:
0 86Al/CPHS 0 86Bl/CPHS R28
EOP-03 Page 95 of 148 8.0 FLOATING STEPS H. RESET OF ENGINEERED SAFEGUARDS INSTRUCTIONS CONTINGENCY ACTIONS
- 2. IFi PPLS has NOT actuated, I
THEN GO TO Step 4.
1
- 3. deset PPLS by performing the following steps:
- a. IF RCS pressure is greater than 1700 psia, THEN GO TO Step 3.e.
- b. Verify BOTH of the following RCS b.1 IF either RCS Temperature Temperature instruments are instrument is inoperable, operable: THEN disable the PORVs by closing BOTH PORV Block Valves:
1-113 0 T-123 HCV-150 HCV-151 c- -
Block PPLS-A and PPLS-B.
(continue)
EOP-03 Page 96 of 148 8.0 FLOATING STEPS H. RESET OF ENGINEERED SAFEGUARDS INSTRUCTIONS CONTINGENCY ACTIONS
- 3. (continued)
- d. Verifv ALL of the PPLS Blocked d.1 IF any of the PPLS Blocked alarms alarms annunciate: do NOT annunciate, 0 "PPLS " A BLOCKED" THEN continue attempts to block (CB-1,2,3; A4) PPLS until all alarms annunciate.
0 "PPLS "B" BLOCKED" (CB-1,2,3; A4)
"PPLS-B BLOCKED" (AI-30B; A34-1)
"PPLS-A1 BLOCKED" (AI-308; A34-2)
"PPLS-B1 BLOCKED (AI-30A; A33-2) 0 'IPPLS-A BLOCKED" (AI-30A; A33-I)
- e. Reset BOTH of the following relays:
0 86NPPLS 0 86B/PPLS
- f. -Reset BOTH of the following relays:
0 86AUPPLS 0 86Bl/PPLS
EOP-03 Page 97 of 148 8.0 FLOATING STEPS H. RESET OF ENGINEERED SAFEGUARDS INSTRUCTIONS CONTINGENCY ACTIONS
- 4. Rlace ALL of the Containment Cooler dCW Valve Hand Controllers in "OPEN":
HCV-400C HCV-4O1C HCV-402C 0 HCV-403C
- 5. Place BOTH of the following EHC Pump control switches in "PULL-TO-LOCK:
EHC3A EHC3B
- 6. IF OPLS has actuated, THEN place ALL of the following Condenser Evacuation Pump control switches in "PULL-TO-LOCK:
FW-8A FW-8B FW-8C
EOP-03 Page 98 of 148 8.0 FLOATING STEPS H. RESET OF ENGINEERED SAFEGUARDS INSTRUCTIONS CONTINGENCY ACTIONS NOTE When SlAS relays are reset, ALL of the following equipment may reposition:
HCV-489A/B, 490A/B, 491AIB, and 492A/B, RW/CCW HX CCW valves - upon reset, valves will return to their pre-SIAS position LCV-218 if in AUTO or OPEN, valve will reopen CH-4AIB - will stop unless control switch has been red-flagged WD-2A/B - RCDT pumps may restart WD3AIB - Containment Sump Pumps may restart WD-27A/B, 40AIB, 41NB Aux Building Sump pumps may restart Pressurizer Backup Heater Bank 1, Group 2 and 3; Bank 2, Group 5; Bank 3, Group 9; and Bank 4, Group 11 and 12 will reenergize if previously in service and pressurizer level above the low level cutoff VD-7A - Vacuum priming pump will restart if selected WD-26A/B, Aux Bldg Sump Tank Pumps may restart
- 7. Reset ALL of the following relays:
0 86AISIAS 0 86MSIAS 0 86AICIAS 0 868 1BIAS 0 86B1X/S IAS 0 86B1/CIAS 0 86B/SIAS 0 86BWSIAS 0 86B/CIAS 0 86A1/SIAS 0 86A1X/SIAS 0 86A1/CIAS