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| {{#Wiki_filter:April 6, 2006Mr. R. T. RidenoureVice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. | | {{#Wiki_filter:April 6, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. |
| Post Office Box 550 Fort Calhoun, NE 68023-0550 | | Post Office Box 550 Fort Calhoun, NE 68023-0550 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| FORT CALHOUN STATION, UNIT NO. 1 - PUMP RELIEF REQUEST E-2 FORTHE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MD0227) | | FORT CALHOUN STATION, UNIT NO. 1 - PUMP RELIEF REQUEST E-2 FOR THE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MD0227) |
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| ==Dear Mr. Ridenoure:== | | ==Dear Mr. Ridenoure:== |
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| By letter dated February 27, 2006, Omaha Public Power District (the licensee) submitted PumpRelief Request E-2 for its Fourth 10-year inservice testing program interval at the Fort Calhoun Station, Unit 1.The Nuclear Regulatory Commission (NRC) staff has completed its review of the subject reliefrequest. Pump Relief Request E-2 is authorized pursuant to Paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations on the basis that the proposed alternative providesan acceptable level of quality and safety. The NRC staff's safety evaluation is enclosed. If you have any questions regarding the safety evaluation, please contact Alan B. Wang at(301) 415-1445.Sincerely,/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-285 | | By letter dated February 27, 2006, Omaha Public Power District (the licensee) submitted Pump Relief Request E-2 for its Fourth 10-year inservice testing program interval at the Fort Calhoun Station, Unit 1. |
| | The Nuclear Regulatory Commission (NRC) staff has completed its review of the subject relief request. Pump Relief Request E-2 is authorized pursuant to Paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations on the basis that the proposed alternative provides an acceptable level of quality and safety. The NRC staffs safety evaluation is enclosed. |
| | If you have any questions regarding the safety evaluation, please contact Alan B. Wang at (301) 415-1445. |
| | Sincerely, |
| | /RA/ |
| | David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl: See next page April 6,2006Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. | | Safety Evaluation cc w/encl: See next page |
| Post Office Box 550 Fort Calhoun, NE 68023-0550 | | |
| | April 6,2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. |
| | Post Office Box 550 Fort Calhoun, NE 68023-0550 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| FORT CALHOUN STATION, UNIT NO. 1 - PUMP RELIEF REQUEST E-2 FORTHE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MD0227) | | FORT CALHOUN STATION, UNIT NO. 1 - PUMP RELIEF REQUEST E-2 FOR THE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MD0227) |
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| ==Dear Mr. Ridenoure:== | | ==Dear Mr. Ridenoure:== |
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| By letter dated February 27, 2006, Omaha Public Power District (the licensee) submitted PumpRelief Request E-2 for its Fourth 10-year inservice testing program interval at the Fort Calhoun Station, Unit 1.The Nuclear Regulatory Commission (NRC) staff has completed its review of the subject reliefrequest. Pump Relief Request E-2 is authorized pursuant to Paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations on the basis that the proposed alternative providesan acceptable level of quality and safety. The NRC staff's safety evaluation is enclosed. If you have any questions regarding the safety evaluation, please contact Alan B. Wang at(301) 415-1445.Sincerely,/RA/David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-285 | | By letter dated February 27, 2006, Omaha Public Power District (the licensee) submitted Pump Relief Request E-2 for its Fourth 10-year inservice testing program interval at the Fort Calhoun Station, Unit 1. |
| | The Nuclear Regulatory Commission (NRC) staff has completed its review of the subject relief request. Pump Relief Request E-2 is authorized pursuant to Paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations on the basis that the proposed alternative provides an acceptable level of quality and safety. The NRC staffs safety evaluation is enclosed. |
| | If you have any questions regarding the safety evaluation, please contact Alan B. Wang at (301) 415-1445. |
| | Sincerely, |
| | /RA/ |
| | David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl: See next pageDISTRIBUTION | | Safety Evaluation cc w/encl: See next page DISTRIBUTION: |
| :PUBLIC LPLIV ReadingRidsNrrDorlLplg (DTerao)RidsNrrPMAWangRidsNrrLALFeizollahiTBloomer, RIV EDORidsAcrsAcnwMailCenter RidsNrrDorl (CHaney/CHolden)RidsRegion4MailCenter (DGraves)RidsOgcRpJMcHaleRidsNrrDeGSBediACCESSION NO.: NRR-028OFFICELPL4/PMLPL4/LACPTB-BCOGCLPL4/BCNAMEAWangLFeizollahiSLeeUwoods (NLO)DTeraoDATE3/31/063/30/063/22/064/5/064/6/06E:\Filenet\ML060970124.wpdOFFICIAL RECORD COPY SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONREQUEST FOR RELIEF FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERSSECTION XI, INSERVICE TESTING PROGRAM OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1DOCKET NO. 50-28
| | PUBLIC LPLIV Reading RidsNrrDorlLplg (DTerao) |
| | RidsNrrPMAWang RidsNrrLALFeizollahi TBloomer, RIV EDO RidsAcrsAcnwMailCenter RidsNrrDorl (CHaney/CHolden) RidsRegion4MailCenter (DGraves) |
| | RidsOgcRp JMcHale RidsNrrDe GSBedi ACCESSION NO.: NRR-028 OFFICE LPL4/PM LPL4/LA CPTB-BC OGC LPL4/BC NAME AWang LFeizollahi SLee Uwoods (NLO) DTerao DATE 3/31/06 3/30/06 3/22/06 4/5/06 4/6/06 E:\Filenet\ML060970124.wpd OFFICIAL RECORD COPY |
| | |
| | SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS SECTION XI, INSERVICE TESTING PROGRAM OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 |
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| | ==1.0 INTRODUCTION== |
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| | By letter dated February 27, 2006, Omaha Public Power District (OPPD/the licensee), |
| | submitted a relief request for the fourth 10-year inservice testing (IST) program interval at Fort Calhoun Station (FCS), Unit 1. The licensee requested relief from a certain inservice test requirement of the 1998 Edition through 2000 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). |
| | The FCS fourth 10-year IST interval commenced in February 2004. |
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| ==51.0INTRODUCTION== | | ==2.0 REGULATORY EVALUATION== |
| By letter dated February 27, 2006, Omaha Public Power District (OPPD/the licensee),submitted a relief request for the fourth 10-year inservice testing (IST) program interval at Fort Calhoun Station (FCS), Unit 1. The licensee requested relief from a certain inservice test requirement of the 1998 Edition through 2000 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The FCS fourth 10-year IST interval commenced in February 2004.
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| ==2.0REGULATORY EVALUATION==
| | Section 50.55a of Title 10 of the Code of Federal Regulations (10 CFR) requires that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year) |
| Section 50.55a of Title 10 of the Code of Federal Regulations (10 CFR) requires that IST ofcertain ASME Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year) | | IST program intervals in accordance with the specified ASME Code incorporated by reference in the regulations, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Commission pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a. In accordance with 10 CFR 50.55a(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month IST program interval. In accordance with 50.55a(f)(4)(iv), IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to Nuclear Regulatory Commission (NRC) approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for the facility. |
| IST program intervals in accordance with the specified ASME Code incorporated by reference in the regulations, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Commission pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a. In accordance with 10 CFR 50.55a(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month IST program interval. In accordance with 50.55a(f)(4)(iv), IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to Nuclear Regulatory Commission (NRC) approval. Portions ofeditions or addenda may be used provided that all related requirements of the respective editions and addenda are met. In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for the facility. Section 50.55a authorizes the Commission to approve alternatives and to grant relief from ASME Code requirements upon making necessary findings. The NRC guidance contained inGeneric Letter (GL) 89-04, "Guidance on Developing Acceptable Inservice Testing Programs," | | Section 50.55a authorizes the Commission to approve alternatives and to grant relief from ASME Code requirements upon making necessary findings. The NRC guidance contained in Generic Letter (GL) 89-04, Guidance on Developing Acceptable Inservice Testing Programs, provides alternatives to ASME Code requirements which are acceptable. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482, Revision 1, Guidance for Inservice Testing at Nuclear Power Plants. |
| provides alternatives to ASME Code requirements which are acceptable. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482, Revision 1, "Guidance for InserviceTesting at Nuclear Power Plants." The FCS, Unit 1, fourth 10-year IST interval commenced in February 2004. The program wasdeveloped in accordance with the 1998 Edition through 2000 Addenda of the ASME OM Code. | |
| By letter dated November 5, 2002, OPPD requested relief from certain requirements of the ASME OM Code for its FCS, Unit 1, fourth 10-year IST interval. Revision 1 to the FCS IST Program Plan, modifying relief requests for certain ASME OM Code requirements, was submitted by letter dated December 5, 2003. By letter dated February 27, 2006, the licenseerequested relief for the pump flow test requirement of ISTB-5121(c).
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| ==3.0TECHNICAL EVALUATION==
| | The FCS, Unit 1, fourth 10-year IST interval commenced in February 2004. The program was developed in accordance with the 1998 Edition through 2000 Addenda of the ASME OM Code. |
| The Nuclear Regulatory Commission (NRC) staff's findings with respect to authorizingalternatives pursuant to 10 CFR 50.55a(a)(3)(i) are given below.3.1Pump Relief Request E-2 3.1.1Code RequirementsThe licensee requested relief from ISTB-5121(c), which requires that where system resistancecannot be varied, flow rate and pressure shall be determined and compared to their respective reference values. The relief requested applies to the following pumps:Low Pressure Safety Injection (LPSI) Pumps SI-1A, SI-1BHigh Pressure Safety Injection Pumps (HPSI) SI-2A, SI-2B Containment Spray (CS) Pumps SI-3A, SI-3B, SI-3C3.1.2Licensee's Basis for Requesting ReliefThe licensee states:The flow rate of the subject pumps cannot be measured when they are operating onminimum flow recirculation because flow instrumentation is not installed on the lines. | | By letter dated November 5, 2002, OPPD requested relief from certain requirements of the ASME OM Code for its FCS, Unit 1, fourth 10-year IST interval. Revision 1 to the FCS IST Program Plan, modifying relief requests for certain ASME OM Code requirements, was submitted by letter dated December 5, 2003. By letter dated February 27, 2006, the licensee requested relief for the pump flow test requirement of ISTB-5121(c). |
| The minimum recirculation flow lines are used when testing the pumps quarterly during power operations. For the LPSI and HPSI pumps, the only other available flow path is to the Reactor Coolant System (RCS) where such flow is undesirable during power operation. The only other available flow path for the CS pumps is into the CS headers, which would result in water damage to equipment in containment.3.1.3Licensee's Proposed Alternative TestingThe licensee states:FCS proposes the following alternative to the ISTB-5121(c) requirement:
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| a.As a minimum, quarterly testing continues to measure pump differential pressureand vibration.b.During each refueling outage, a comprehensive test using Section ISTB-5123 ofthe ASME Code will be conducted under full or substantial flow rates. Pump differential pressure, flow rate, and bearing vibration measurements will betaken.c.Data from both quarterly and comprehensive tests will be monitored andanalyzed as required by Section ISTB-6000 of the ASME Code.This testing regimen provides an effective alternative to ISTB-5121(c).3.1.4 EvaluationThe licensee requests relief from the flow test requirement of ISTB-5121(c) where Group Apump tests are required for the subject pumps. ISTB-5121(c) requires that flow rate and pressure be determined and compared to their respective reference values. The licensee proposes testing the pumps quarterly without flow measurements and performing comprehensive tests using ISTB-5123 of the ASME Code with flow measurements at each refueling outage.The minimum flow recirculation line is the only path where flow can be established for thesubject pumps during quarterly testing with the plant at power. The HPSI and LPSI pumps do not generate sufficient head to overcome RCS pressure at normal operating conditions, and injection of borated water into the RCS at power is undesirable from a reactivity control standpoint. The CS header is undesirable as a flow path for the CS pumps during non-accident conditions due to the potential for water damage to equipment in the containment. T he syst emdesign is such that the recirculation flow path is the only path available for pump testing duringpower operations; however, flow rate cannot be measured due to lack of flow instrumentation in the recirculation line. The licensee has proposed performing quarterly tests via this non-instrumented flow path ensuring that, at a minimum, pump differential pressure and vibration measurements are continued. Additionally, comprehensive tests at full or substantialflow conditions will be performed during refueling outages or other cold shutdown conditionsthat meet IST frequency requirements. These tests will include flow measurements and shallmeet the requirements of ISTB-5123. The NRC staff has determined that this alternativetesting regimen is consistent with Position 9 of Attachment 1 to GL 89-04 and assures pump operability.
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| ==4.0CONCLUSION== | | ==3.0 TECHNICAL EVALUATION== |
| The OPPD Relief Request E-2 has been reviewed by the NRC staff and based on the aboveevaluation, the NRC staff has concluded that the licensee's alternative is authorized pursuant to10 CFR 50.55a(a)(3)(i) on the basis that the proposed alternative provides an acceptable levelof quality and safety for quarterly Group A pump testing activities. This alternative is authorized for the remainder of the fourth 10-year IST interval.
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| All other ASME Code, Section XI, requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.Principal Contributor: J. McHale Date: April 6, 2006 January 2006Ft. Calhoun Station, Unit 1 cc:
| | The Nuclear Regulatory Commission (NRC) staffs findings with respect to authorizing alternatives pursuant to 10 CFR 50.55a(a)(3)(i) are given below. |
| Winston & Strawn ATTN: James R. Curtiss, Esq.
| | 3.1 Pump Relief Request E-2 3.1.1 Code Requirements The licensee requested relief from ISTB-5121(c), which requires that where system resistance cannot be varied, flow rate and pressure shall be determined and compared to their respective reference values. The relief requested applies to the following pumps: |
| 1400 L Street, N.W.
| | Low Pressure Safety Injection (LPSI) Pumps SI-1A, SI-1B High Pressure Safety Injection Pumps (HPSI) SI-2A, SI-2B Containment Spray (CS) Pumps SI-3A, SI-3B, SI-3C 3.1.2 Licensees Basis for Requesting Relief The licensee states: |
| Washington, DC 20005-3502ChairmanWashington County Board of Supervisors
| | The flow rate of the subject pumps cannot be measured when they are operating on minimum flow recirculation because flow instrumentation is not installed on the lines. |
| | The minimum recirculation flow lines are used when testing the pumps quarterly during power operations. For the LPSI and HPSI pumps, the only other available flow path is to the Reactor Coolant System (RCS) where such flow is undesirable during power operation. The only other available flow path for the CS pumps is into the CS headers, which would result in water damage to equipment in containment. |
| | 3.1.3 Licensees Proposed Alternative Testing The licensee states: |
| | FCS proposes the following alternative to the ISTB-5121(c) requirement: |
| | : a. As a minimum, quarterly testing continues to measure pump differential pressure and vibration. |
| | : b. During each refueling outage, a comprehensive test using Section ISTB-5123 of the ASME Code will be conducted under full or substantial flow rates. Pump |
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| P.O. Box 466 Blair, NE 68008Mr. John Hanna, Resident InspectorU.S. Nuclear Regulatory Commission
| | differential pressure, flow rate, and bearing vibration measurements will be taken. |
| | : c. Data from both quarterly and comprehensive tests will be monitored and analyzed as required by Section ISTB-6000 of the ASME Code. |
| | This testing regimen provides an effective alternative to ISTB-5121(c). |
| | 3.1.4 Evaluation The licensee requests relief from the flow test requirement of ISTB-5121(c) where Group A pump tests are required for the subject pumps. ISTB-5121(c) requires that flow rate and pressure be determined and compared to their respective reference values. The licensee proposes testing the pumps quarterly without flow measurements and performing comprehensive tests using ISTB-5123 of the ASME Code with flow measurements at each refueling outage. |
| | The minimum flow recirculation line is the only path where flow can be established for the subject pumps during quarterly testing with the plant at power. The HPSI and LPSI pumps do not generate sufficient head to overcome RCS pressure at normal operating conditions, and injection of borated water into the RCS at power is undesirable from a reactivity control standpoint. The CS header is undesirable as a flow path for the CS pumps during non-accident conditions due to the potential for water damage to equipment in the containment. The system design is such that the recirculation flow path is the only path available for pump testing during power operations; however, flow rate cannot be measured due to lack of flow instrumentation in the recirculation line. The licensee has proposed performing quarterly tests via this non-instrumented flow path ensuring that, at a minimum, pump differential pressure and vibration measurements are continued. Additionally, comprehensive tests at full or substantial flow conditions will be performed during refueling outages or other cold shutdown conditions that meet IST frequency requirements. These tests will include flow measurements and shall meet the requirements of ISTB-5123. The NRC staff has determined that this alternative testing regimen is consistent with Position 9 of Attachment 1 to GL 89-04 and assures pump operability. |
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| P.O. Box 310 Fort Calhoun, NE 68023Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007Mr. David J. Bannister, ManagerFort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant
| | ==4.0 CONCLUSION== |
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| P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Joe L. McManisManager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
| | The OPPD Relief Request E-2 has been reviewed by the NRC staff and based on the above evaluation, the NRC staff has concluded that the licensees alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) on the basis that the proposed alternative provides an acceptable level of quality and safety for quarterly Group A pump testing activities. This alternative is authorized for the remainder of the fourth 10-year IST interval. |
| | All other ASME Code, Section XI, requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector. |
| | Principal Contributor: J. McHale Date: April 6, 2006 |
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| P.O. Box 550 Fort Calhoun, NE 68023-0550Mr. Daniel K. McGheeBureau of Radiological HealthIowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319}}
| | Ft. Calhoun Station, Unit 1 cc: |
| | Winston & Strawn Bureau of Radiological Health ATTN: James R. Curtiss, Esq. Iowa Department of Public Health 1400 L Street, N.W. Lucas State Office Building, 5th Floor Washington, DC 20005-3502 321 East 12th Street Des Moines, IA 50319 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm. |
| | P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee January 2006}} |
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Category:Code Relief or Alternative
MONTHYEARML16104A0742016-04-15015 April 2016
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LIC-15-0086, Supplement to License Amendment Request (LAR) 14-04, Request to Adopt ASME Code, Section III, 1980 Edition (No Addenda) as an Alternative to Current Code of Record2015-07-0202 July 2015
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LIC-15-0066, Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds2015-05-0909 May 2015
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ML14323A5992014-12-0202 December 2014
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ML14316A1672014-11-19019 November 2014
Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building
ML1022101332010-08-20020 August 2010
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ML0712300902007-04-27027 April 2007
Part 21 Interim Report, Dresser Investigation File No. 2007-02, Interim Reporting of a Potential Defect Involving Power Actuated Pressure Relief Valves Supplied to Calvert Cliffs, Fort Calhoun and Oconee Plants
ML0634504072007-01-0505 January 2007
Request for Relief Use of Later Edition and Addenda of ASME Code for Examination of Cast Austenitic Stainless Steel Piping
ML0609701242006-04-0606 April 2006
Relief E-2, 4-th 10-year Pump and Valve Inservice Testing Program
ML0519600742005-10-0303 October 2005
Relief Request - Alternative Test Requirements for Containment Repairs
ML0514407352005-05-24024 May 2005
5/24/05 Fort Calhoun - Relaxation Request from U.S. NRC Order EA-03-009 for the Control Element Drive Mechanism Nozzles
ML0501203572005-02-28028 February 2005
Request for Relief from ASME Code Repair Requirements and Using an Alternative for the Pressurizer Nozzle Repair.
LIC-04-0008, Relief Request Pertaining to Reactor Vessel Nozzle Inspections for the Third 10-Year Interval, Revision2004-04-0202 April 2004
Relief Request Pertaining to Reactor Vessel Nozzle Inspections for the Third 10-Year Interval, Revision
ML0326000132003-09-12012 September 2003
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Relief Request Pertaining to Visual Inspection of Inaccessible Piping & Components
LIC-02-0142, Relief Requests Pertaining to the Fort Calhoun Inservice Inspection (ISI) of the Reactor Pressure Vessel (RPV) for the Third Ten Year ISI Interval (1993-2003)2002-12-20020 December 2002
Relief Requests Pertaining to the Fort Calhoun Inservice Inspection (ISI) of the Reactor Pressure Vessel (RPV) for the Third Ten Year ISI Interval (1993-2003)
2016-04-15
[Table view]
Category:Letter
MONTHYEARIR 05000285/20240032024-10-29029 October 2024
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LIC-24-0011, Independent Spent Fuel Storage Installation - Response to Application for License Amendment Request to Revise the License Termination Plan - Supplemental Information Needed, EPID L-2024-LLA-00952024-10-0202 October 2024
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ML24243A1042024-09-12012 September 2024
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ML24255A0962024-09-12012 September 2024
License Amendment Request to Revise the License Termination Plan - Request Supplemental Information (License No. DPR-40, Docket No. 50-285)
IR 05000285/20240022024-08-21021 August 2024
NRC Inspection Report 05000285/2024002
ML24235A0822024-08-10010 August 2024
Response to Fort Calhoun Station, Unit No. 1 - Phase 1 Final Status Survey Report to Support Approved License Termination Plan - Request for Additional Information - Request for Additional Information (EPID L-2024-DFR-0002) July 8, 2024
ML24180A2082024-07-0808 July 2024
Phase 1 Final Status Survey Reports Request for Additional Information Letter
ML24183A3222024-07-0808 July 2024
Proposed Revision to the Omaha Public Power District Fort Calhoun Station Decommissioning Quality Assurance Plan - Acceptance Review
LIC-24-0007, License Amendment Request (LAR) to Revise License Termination Plan (LTP)2024-06-18018 June 2024
License Amendment Request (LAR) to Revise License Termination Plan (LTP)
IR 05000285/20240012024-06-0505 June 2024
NRC Inspection Report 05000285/2024001
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
LIC-24-0008, Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI2024-05-16016 May 2024
Proposed Revision to the Omaha Public Power District (OPPD) Fort Calhoun Station (FCS) Decommissioning Quality Assurance Plan (Dqap), Unit No. 1 and ISFSI
LIC-24-0003, Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report2024-04-25025 April 2024
Independent Spent Fuel Storage Installation - Radiological Effluent Release Report and Radiological Environmental Operating Report
LIC-24-0006, (Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan2024-04-17017 April 2024
(Fcs), Unit 1, Independent Spent Fuel Storage Installation, Phase 1 Final Status Survey Report to Support Approved License Termination Plan
ML24079A1702024-03-10010 March 2024
ISFSI, Unit 1 - 10 CFR 50.59 Report, Quality Assurance (QA) Program Changes, Technical Specification Basis Changes, 10 CFR 71.106 Quality Assurance Program Approval, Aging Management Review, Commitment Revisions and Revision of Updated Safe
LIC-24-0005, Annual Decommissioning Funding / Irradiated Fuel Management Status Report2024-03-0101 March 2024
Annual Decommissioning Funding / Irradiated Fuel Management Status Report
LIC-24-0002, Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report2024-02-27027 February 2024
Independent Spent Fuel Storage Installation - Submittal of Annual Radioactive Effluent Release Report
ML24019A1672024-01-31031 January 2024
Issuance of Amendment to Renewed Facility License to Add License Condition to Include License Termination Plan Requirements
IR 05000285/20230062023-12-21021 December 2023
NRC Inspection Report 05000285/2023006
LIC-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
IR 05000285/20230052023-11-0202 November 2023
NRC Inspection Room 05000285/2023005
ML23276A0042023-09-28028 September 2023
U.S. EPA Response Letter to NRC Letter on Consultation and Finality on Decommissioning and Decontamination of Contaminated Sites MOU - Fort Calhoun Station, Unit 1 – (License No. DPR-40, Docket No. 50-285)
IR 05000285/20230042023-09-13013 September 2023
NRC Inspection Report 05000285/2023-004
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
ML23234A2412023-08-18018 August 2023
Email - Letter to M Porath Re Ft Calhoun Unit 1 LTP EA Section 7 Informal Consultation Request
ML23234A2392023-08-18018 August 2023
Letter to B Harisis Re Ft Calhoun Unit 1 LTP EA State of Nebraska Comment Request.Pdf
IR 05000285/20230032023-07-10010 July 2023
– NRC Inspection Report 05000285/2023003
ML23082A2202023-06-26026 June 2023
Consultation on the Decommissioning of the Fort Calhoun Station Unit 1 Pressurized Water Reactor in Fort Calhoun, Nebraska
ML23151A0032023-06-0505 June 2023
– 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
IR 05000285/20230022023-06-0505 June 2023
NRC Inspection Report 05000285/2023002
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
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
IR 05000285/20230012023-02-24024 February 2023
NRC Inspection Report 05000285/2023001
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
ML23020A0462023-01-19019 January 2023
Threatened and Endangered Species List: Nebraska Ecological Services Field Office
IR 05000285/20220062023-01-0505 January 2023
NRC Inspection Report 05000285/2022-006
ML22357A0662022-12-30030 December 2022
Technical RAI Submittal Letter on License Amendment Request for Approval of License Termination Plan
IR 05000285/20220052022-10-26026 October 2022
NRC Inspection Report 05000285/2022-005
ML22276A1052022-09-30030 September 2022
Conclusion of Consultation Under Section 106 NHPA for Ft. Calhoun Station LTP
ML22258A2732022-09-29029 September 2022
Letter to John Swigart, SHPO; Re., Conclusion of Consultation Under Section 106 Hnpa Fort Calhoun Station Unit 1
ML22265A0262022-09-26026 September 2022
U.S. Nuclear Regulatory Commissions Analysis of Omaha Public Power Districts Decommissioning Status Report (License No. DPR-40, Docket No. 50-285)
IR 05000285/20220042022-09-14014 September 2022
NRC Inspection Report 05000285/2022004
ML22138A1252022-08-0303 August 2022
Letter to Mr. Timothy Rhodd, Chairperson, Iowa Tribe of Kansas and Nebraska, Re., Ft Calhoun LTP Section 106
ML22138A1222022-08-0303 August 2022
Letter to Mr. John Shotton, Chairman, Otoe-Missouria Tribe of Indians, Oklahoma, Re., Ft Calhoun LTP Section 106
ML22138A1302022-08-0303 August 2022
Letter to Justin Wood, Principal Chief, Sac and Fox Nation, Oklahoma, Re., Ft Calhoun LTP Section 106
ML22214A0922022-08-0303 August 2022
Letter to Stacy Laravie, Thpo, Ponca Tribe of Nebraska, Re., Ft Calhoun LTP Section 106
2024-09-18
[Table view]
Category:Safety Evaluation
MONTHYEARML24019A1682024-01-31031 January 2024
Safety Evaluation Report for Approval of License Termination Plan
ML21271A5992021-08-0303 August 2021
License Amendment Request (LAR) 21-01, Chapter 8, 12, Omaha Public Power District, FCS-SAF-103, FCS Deconstruction Health and Safety Plan CAC2
ML20056E4872020-02-26026 February 2020
Staff Review of Fort Calhoun Independent Spent Fuel Storage Installation Physical Security Plan, Security Training and Qualification Plan, and Safeguard Contingency Plan, Revision 0 and the Verification of Additional Security Measures (ASM)
ML19297D6742019-12-0909 December 2019
FCS ISFSI Only Tech Specs SER
ML18017B0052018-03-30030 March 2018
Review of the Irradiated Fuel Management Plan (CAC No. MF9553; EPID L-2017-LLL-0009)
ML18047A6612018-03-28028 March 2018
Issuance of Amendment No. 298, Request to Modify License Condition 3.C to Delete Requirement for Commission-Approved Cyber Security Plan (CAC No. MF9850; EPID L-2017-LLA-0236)
ML18010A0872018-03-0606 March 2018
Issuance of Amendment No. 297, Request for Technical Specification Changes to Align to Those Requirements for Decommissioning (CAC No. MF9567; EPID L-2017-LLA-0192)
ML17338A1722018-01-19019 January 2018
Issuance of Amendment No. 296, Revise Technical Specifications (TS) to Delete Dry Spent Fuel Cask Loading Limits from TS 3.8.3(6), Figure 2-11, Table 3-4, Table 3-5, and TS 4.3.1.3 (CAC No. MF9831; EPID L-2017-LLA-0235)
ML17276B2862017-12-12012 December 2017
Issuance of Amendment No. 295, Revise the Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition (CAC No. MF8951; EPID L-2016-LLA-0036)
ML17263B1982017-12-11011 December 2017
Letter and Safety Evaluation, Request for Exemption from 10 CFR 50.47 and 10 CFR 50 Appendix E to Reduce Emergency Planning Requirements for Permanently Defueled Condition (CAC MF9067; EPID L-2016-LLE-0003)
ML17289A0602017-11-22022 November 2017
Issuance of Amendment No. 294, Revise Cyber Security Plan Implementation Schedule for Milestone 8 and Associated License Condition (CAC No. MF9559; EPID L-2017-LLA-0184)
ML17275A2642017-11-21021 November 2017
Safety Evaluation Input on Fort Calhoun Station Request for Approval of Permanently Defueled Emergency Plan and Emergency Action Level Scheme, Docket No. 50-285
ML17278A6072017-11-17017 November 2017
Issuance of Amendment No. 293, Request to Revise Current Licensing Basis for the Auxiliary Building to Use American Concrete Institute Ultimate Strength Requirements (CAC No. MF8525; EPID L-2016-LLA-0013)
ML17165A4652017-07-28028 July 2017
Fort Calhoun Station, Unit 1 - Issuance of Amendment No. 292, Revise Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (CAC No. MF8437)
ML17123A3482017-07-27027 July 2017
Issuance of Amendment No. 291, Revise the Radiological Emergency Response Plan for Permanently Defueled Condition
ML17144A2462017-06-21021 June 2017
Approval of Certified Fuel Handler Training and Retraining Program to Facilitate Activities Associated with Decommissioning and Irradiated Fuel Handling Management
ML17053A0992017-04-0707 April 2017
Issuance of Amendment No. 290, Request to Delete License Condition 3.D., Fire Protection Program, No Longer Needed for Permanently Shutdown and Defueled Condition
ML16141A7392016-05-27027 May 2016
Safety Evaluation, Review of Aging Management Program of Reactor Vessel Internals Based on MRP-227-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines
ML16104A0742016-04-15015 April 2016
Relief Request, Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI, Fourth 10-Year Inservice Inspection Interval
ML16084A7552016-04-0505 April 2016
Issuance of Amendment No. 287, Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours/Month, Using CLIIP
ML15307A0132016-02-23023 February 2016
Issuance of Amendment No. 286, Request to Make Administrative Changes to the Technical Specifications to Update Titles, Delete Obsolete Actions in Appendix B, and Relocate a Definition
ML16041A3082016-02-19019 February 2016
Relief Requests P-1 - LPSI and CS Pumps; P-2 - Adjusting Hydraulic Parameters Consistent W/Code Case OMN-21; G-1 - Test Frequency Consistent W/Code Case OMN-20, Fifth 10-Year Inservice Testing Interval
ML15288A0052015-12-15015 December 2015
Issuance of Amendment No. 285, Adopt Emergency Action Level Scheme Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML15294A2792015-11-19019 November 2015
Issuance of Amendment No. 284, Request to Revise License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date
ML15232A0032015-08-21021 August 2015
Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval
ML15209A8022015-08-10010 August 2015
Issuance of Amendment No. 283, Revise Updated Safety Analysis Report to Allow Pipe Stress Analysis to Be Performed in Accordance with ASME Code Section III
ML15111A3992015-06-30030 June 2015
Issuance of Amendment No. 282, Revise Updated Safety Analysis Report for Controlling Raw Water Pump Operation and Safety Classification of Components During a Flood
ML15035A2032015-03-27027 March 2015
Issuance of Amendment No. 281, Revise Technical Specification 3.1, Table 3-3 to Correct Administrative Error in Surveillance Method for Containment Wide Range Radiation Monitors
ML15015A4132015-02-20020 February 2015
Issuance of Amendment No. 280, Revise Technical Specification 3.2, Table 3-5 to Add New Surveillance Requirement
ML14356A0122014-12-29029 December 2014
Issuance of Amendment No. 279, Revise Technical Specification Surveillance Requirements for One-Time Extension from Refueling Frequency of Once Per 18 Months to Maximum of 28 Months
ML14328A8142014-12-22022 December 2014
Issuance of Amendment No. 278, Revise Technical Specification 2.5, Auxiliary Feedwater (AFW) System to Allow 7-Day Completion Time for Turbine-Driven AFW Pump Based on TSTF-340, Revision 3
ML14323A5992014-12-0202 December 2014
Relief Request RR-13, Relief from Inservice Testing Requirements to Perform Testing of 4 Valves During the April 2015 Refueling Outage
ML14316A1672014-11-19019 November 2014
Relief Request RR-14, Proposed Alternative for Temporary Acceptance of a Pin Hole Leak in Raw Water System 20-Inch Elbow Located in Room 19 of Auxiliary Building
ML14279A2752014-11-0606 November 2014
Issuance of Amendment No. 277, Revise Technical Specification Surveillance Requirement 3.2, Table 3-5, Item 3, for One-Time Extension of Frequency to Maximum of 28 Months
ML14209A0272014-08-0707 August 2014
Issuance of Amendment No. 276, Request to Revise Updated Safety Analysis Report for Westinghouse Plant-Specific Leak-Before-Break Analysis
ML14098A0922014-06-16016 June 2014
Issuance of Amendment No. 275, Adopt National Fire Protection Association Standard 805, Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants (2001 Edition)
ML14003A0032014-01-28028 January 2014
Issuance of Amendment No. 274, Revise Technical Specification 2.16, River Level, and Establish EAL Classification Criteria for External Flooding Events Under Radiological Emergency Response Plan
ML13296A5842013-10-25025 October 2013
Issuance of Amendment No. 273, Revise Current Licensing Basis of Pipe Break Criteria for High Energy Line Breaks (Exigent Circumstances)
ML13203A0702013-07-26026 July 2013
Issuance of Amendment No. 272 - Revise Current Licensing Basis to Adopt Revised Design Basis/Methodology for Addressing Design-Basis Tornado/Tornado Missile Impact (Exigent Circumstances)
ML13141A6082013-06-25025 June 2013
Safety Assessment in Response to Request for Information Pursuant to 10 CFR 50.54(f) - Recommendation 9.3 Communications Assessment
ML13070A0422013-03-29029 March 2013
Issuance of Amendment No. 271, Relocate Technical Specification LCO 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report
ML13043A6612013-02-28028 February 2013
Issuance of Amendment No. 270 to Revise Technical Specification 2.15 to Establish Limiting Condition for Operation Requirements for Reactor Protective System Actuation Circuits
ML13017A4672013-01-31031 January 2013
Approval of Request for Change to the Reactor Vessel Surveillance Capsule Removal Schedule
ML12333A1192012-12-31031 December 2012
Issuance of Amendment No. 269, Incorporate New Radial Peaking Factor Definition and Clarify Limiting Condition for Operation (LCO) 2.10.2(6)
ML1126204022011-09-30030 September 2011
Issuance of Amendment No. 268, Revise Updated Safety Analysis Report to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
ML1118615712011-08-31031 August 2011
Issuance of Amendment No. 267, Revise Technical Specification (TS) 2.15 and TS 3.1 Related to Operability of Secondary Control Element Assembly Position Indication System Channels; Correction to TS 2.10.2(7)c
ML1122702902011-08-18018 August 2011
Relief Request RR-12 from Code Case N-722, Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials, Fourth 10-Year Inservice Inspection Interval
ML1118010942011-07-27027 July 2011
Issuance of Amendment No. 266, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule
ML1022101332010-08-20020 August 2010
Request for Use of Alternative to Depth-Sizing Qualification for Volumetric Examinations of Reactor Pressure Vessel Welds for 4th 10-year Inservice Inspection Interval
ML1009100772010-05-14014 May 2010
License Amendment, 264, Revision of Tech Spec Sections 2.0.1 and 2.7 for Inoperable System, Subsystem, or Component Due to Inoperable Power Source and Deletion of Diesel Generator Surveillance Requirement 3.7(1)e
2024-01-31
[Table view] |
Text
April 6, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - PUMP RELIEF REQUEST E-2 FOR THE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MD0227)
Dear Mr. Ridenoure:
By letter dated February 27, 2006, Omaha Public Power District (the licensee) submitted Pump Relief Request E-2 for its Fourth 10-year inservice testing program interval at the Fort Calhoun Station, Unit 1.
The Nuclear Regulatory Commission (NRC) staff has completed its review of the subject relief request. Pump Relief Request E-2 is authorized pursuant to Paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations on the basis that the proposed alternative provides an acceptable level of quality and safety. The NRC staffs safety evaluation is enclosed.
If you have any questions regarding the safety evaluation, please contact Alan B. Wang at (301) 415-1445.
Sincerely,
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Safety Evaluation cc w/encl: See next page
April 6,2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1 - PUMP RELIEF REQUEST E-2 FOR THE FOURTH 10-YEAR PUMP AND VALVE INSERVICE TESTING PROGRAM (TAC NO. MD0227)
Dear Mr. Ridenoure:
By letter dated February 27, 2006, Omaha Public Power District (the licensee) submitted Pump Relief Request E-2 for its Fourth 10-year inservice testing program interval at the Fort Calhoun Station, Unit 1.
The Nuclear Regulatory Commission (NRC) staff has completed its review of the subject relief request. Pump Relief Request E-2 is authorized pursuant to Paragraph 50.55a(a)(3)(i) of Title 10 of the Code of Federal Regulations on the basis that the proposed alternative provides an acceptable level of quality and safety. The NRC staffs safety evaluation is enclosed.
If you have any questions regarding the safety evaluation, please contact Alan B. Wang at (301) 415-1445.
Sincerely,
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
Safety Evaluation cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLIV Reading RidsNrrDorlLplg (DTerao)
RidsNrrPMAWang RidsNrrLALFeizollahi TBloomer, RIV EDO RidsAcrsAcnwMailCenter RidsNrrDorl (CHaney/CHolden) RidsRegion4MailCenter (DGraves)
RidsOgcRp JMcHale RidsNrrDe GSBedi ACCESSION NO.: NRR-028 OFFICE LPL4/PM LPL4/LA CPTB-BC OGC LPL4/BC NAME AWang LFeizollahi SLee Uwoods (NLO) DTerao DATE 3/31/06 3/30/06 3/22/06 4/5/06 4/6/06 E:\Filenet\ML060970124.wpd OFFICIAL RECORD COPY
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS SECTION XI, INSERVICE TESTING PROGRAM OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285
1.0 INTRODUCTION
By letter dated February 27, 2006, Omaha Public Power District (OPPD/the licensee),
submitted a relief request for the fourth 10-year inservice testing (IST) program interval at Fort Calhoun Station (FCS), Unit 1. The licensee requested relief from a certain inservice test requirement of the 1998 Edition through 2000 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code).
The FCS fourth 10-year IST interval commenced in February 2004.
2.0 REGULATORY EVALUATION
Section 50.55a of Title 10 of the Code of Federal Regulations (10 CFR) requires that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year)
IST program intervals in accordance with the specified ASME Code incorporated by reference in the regulations, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Commission pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (f)(6)(i) of 10 CFR 50.55a. In accordance with 10 CFR 50.55a(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month IST program interval. In accordance with 50.55a(f)(4)(iv), IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to Nuclear Regulatory Commission (NRC) approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for the facility.
Section 50.55a authorizes the Commission to approve alternatives and to grant relief from ASME Code requirements upon making necessary findings. The NRC guidance contained in Generic Letter (GL) 89-04, Guidance on Developing Acceptable Inservice Testing Programs, provides alternatives to ASME Code requirements which are acceptable. Further guidance is given in GL 89-04, Supplement 1, and NUREG-1482, Revision 1, Guidance for Inservice Testing at Nuclear Power Plants.
The FCS, Unit 1, fourth 10-year IST interval commenced in February 2004. The program was developed in accordance with the 1998 Edition through 2000 Addenda of the ASME OM Code.
By letter dated November 5, 2002, OPPD requested relief from certain requirements of the ASME OM Code for its FCS, Unit 1, fourth 10-year IST interval. Revision 1 to the FCS IST Program Plan, modifying relief requests for certain ASME OM Code requirements, was submitted by letter dated December 5, 2003. By letter dated February 27, 2006, the licensee requested relief for the pump flow test requirement of ISTB-5121(c).
3.0 TECHNICAL EVALUATION
The Nuclear Regulatory Commission (NRC) staffs findings with respect to authorizing alternatives pursuant to 10 CFR 50.55a(a)(3)(i) are given below.
3.1 Pump Relief Request E-2 3.1.1 Code Requirements The licensee requested relief from ISTB-5121(c), which requires that where system resistance cannot be varied, flow rate and pressure shall be determined and compared to their respective reference values. The relief requested applies to the following pumps:
Low Pressure Safety Injection (LPSI) Pumps SI-1A, SI-1B High Pressure Safety Injection Pumps (HPSI) SI-2A, SI-2B Containment Spray (CS) Pumps SI-3A, SI-3B, SI-3C 3.1.2 Licensees Basis for Requesting Relief The licensee states:
The flow rate of the subject pumps cannot be measured when they are operating on minimum flow recirculation because flow instrumentation is not installed on the lines.
The minimum recirculation flow lines are used when testing the pumps quarterly during power operations. For the LPSI and HPSI pumps, the only other available flow path is to the Reactor Coolant System (RCS) where such flow is undesirable during power operation. The only other available flow path for the CS pumps is into the CS headers, which would result in water damage to equipment in containment.
3.1.3 Licensees Proposed Alternative Testing The licensee states:
FCS proposes the following alternative to the ISTB-5121(c) requirement:
- a. As a minimum, quarterly testing continues to measure pump differential pressure and vibration.
- b. During each refueling outage, a comprehensive test using Section ISTB-5123 of the ASME Code will be conducted under full or substantial flow rates. Pump
differential pressure, flow rate, and bearing vibration measurements will be taken.
- c. Data from both quarterly and comprehensive tests will be monitored and analyzed as required by Section ISTB-6000 of the ASME Code.
This testing regimen provides an effective alternative to ISTB-5121(c).
3.1.4 Evaluation The licensee requests relief from the flow test requirement of ISTB-5121(c) where Group A pump tests are required for the subject pumps. ISTB-5121(c) requires that flow rate and pressure be determined and compared to their respective reference values. The licensee proposes testing the pumps quarterly without flow measurements and performing comprehensive tests using ISTB-5123 of the ASME Code with flow measurements at each refueling outage.
The minimum flow recirculation line is the only path where flow can be established for the subject pumps during quarterly testing with the plant at power. The HPSI and LPSI pumps do not generate sufficient head to overcome RCS pressure at normal operating conditions, and injection of borated water into the RCS at power is undesirable from a reactivity control standpoint. The CS header is undesirable as a flow path for the CS pumps during non-accident conditions due to the potential for water damage to equipment in the containment. The system design is such that the recirculation flow path is the only path available for pump testing during power operations; however, flow rate cannot be measured due to lack of flow instrumentation in the recirculation line. The licensee has proposed performing quarterly tests via this non-instrumented flow path ensuring that, at a minimum, pump differential pressure and vibration measurements are continued. Additionally, comprehensive tests at full or substantial flow conditions will be performed during refueling outages or other cold shutdown conditions that meet IST frequency requirements. These tests will include flow measurements and shall meet the requirements of ISTB-5123. The NRC staff has determined that this alternative testing regimen is consistent with Position 9 of Attachment 1 to GL 89-04 and assures pump operability.
4.0 CONCLUSION
The OPPD Relief Request E-2 has been reviewed by the NRC staff and based on the above evaluation, the NRC staff has concluded that the licensees alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i) on the basis that the proposed alternative provides an acceptable level of quality and safety for quarterly Group A pump testing activities. This alternative is authorized for the remainder of the fourth 10-year IST interval.
All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved in this relief request remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: J. McHale Date: April 6, 2006
Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn Bureau of Radiological Health ATTN: James R. Curtiss, Esq. Iowa Department of Public Health 1400 L Street, N.W. Lucas State Office Building, 5th Floor Washington, DC 20005-3502 321 East 12th Street Des Moines, IA 50319 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee January 2006
