|
|
| (3 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 12/10/2007 | | | issue date = 12/10/2007 |
| | title = Correction to Authorization of Relief Request ISI-39 for the Second 10-Year Inservice Inspection Interval | | | title = Correction to Authorization of Relief Request ISI-39 for the Second 10-Year Inservice Inspection Interval |
| | author name = Donohew J N | | | author name = Donohew J |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLIV | | | author affiliation = NRC/NRR/ADRO/DORL/LPLIV |
| | addressee name = Naslund C D | | | addressee name = Naslund C |
| | addressee affiliation = Union Electric Co | | | addressee affiliation = Union Electric Co |
| | docket = 05000483 | | | docket = 05000483 |
| Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:December 10, 2007Mr. Charles D. NaslundSenior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251 | | {{#Wiki_filter:December 10, 2007 Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| CALLAWAY PLANT, UNIT 1 - CORRECTION TO AUTHORIZATION OFRELIEF REQUEST ISI-39 FOR THE SECOND 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MD3435) | | CALLAWAY PLANT, UNIT 1 - CORRECTION TO AUTHORIZATION OF RELIEF REQUEST ISI-39 FOR THE SECOND 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MD3435) |
|
| |
|
| ==Dear Mr. Naslund:== | | ==Dear Mr. Naslund:== |
|
| |
|
| In our letter to you dated September 17, 2007, the Nuclear Regulatory Commission (NRC)granted the relief in Relief Request (RR) ISI-39 for the second 10-year inservice inspection interval at the Callaway Plant, Unit 1 (Callaway). Union Electric Company (the licensee) submitted RR ISI-39 in its letter dated October 25, 2006 (ULNRC-05183).In Section 3.2, on RR ISI-39, of the safety evaluation (SE) enclosed with our letter datedSeptember 17, 2007, we documented the basis provided by the licensee to support the granting of RR ISI-39. Although the SE dated September 17, 2007, adequately documented the basis, we are modifying specific statements made in Section 3.2 of the SE to more precisely state the basis provided by the licensee for RR ISI-39. The attached revised pages 5 and 6 of the SE show the locations where modifications were made to the SE by the vertical lines on the right-hand-side of the two pages. Since the modifications did not change the conclusions made by the NRC in the SE, RR ISI-39 remains granted as of our letter dated September 17, 2007.Please replace pages 5 and 6 of the Callaway SE dated September 17, 2007, on RR ISI-39with the enclosed pages.Sincerely,/RA/Jack Donohew, Senior Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-483 | | In our letter to you dated September 17, 2007, the Nuclear Regulatory Commission (NRC) granted the relief in Relief Request (RR) ISI-39 for the second 10-year inservice inspection interval at the Callaway Plant, Unit 1 (Callaway). Union Electric Company (the licensee) submitted RR ISI-39 in its letter dated October 25, 2006 (ULNRC-05183). |
| | In Section 3.2, on RR ISI-39, of the safety evaluation (SE) enclosed with our letter dated September 17, 2007, we documented the basis provided by the licensee to support the granting of RR ISI-39. Although the SE dated September 17, 2007, adequately documented the basis, we are modifying specific statements made in Section 3.2 of the SE to more precisely state the basis provided by the licensee for RR ISI-39. The attached revised pages 5 and 6 of the SE show the locations where modifications were made to the SE by the vertical lines on the right-hand-side of the two pages. Since the modifications did not change the conclusions made by the NRC in the SE, RR ISI-39 remains granted as of our letter dated September 17, 2007. |
| | Please replace pages 5 and 6 of the Callaway SE dated September 17, 2007, on RR ISI-39 with the enclosed pages. |
| | Sincerely, |
| | /RA/ |
| | Jack Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encl: See next page | | As stated cc w/encl: See next page |
|
| |
|
| ML073111442NRR-106OFFICENRR/LPL4/PMNRR/LPL4/LADCI/CVIB/BCNRR/LPL4/BCNAMEJDonohew:spJBurkhardtMMitchellTHiltz DATE12/4/0712/6/0712/5/0712/10/07 ENCLOSUREREVISED PAGES 5 AND 6 OF SEPTEMBER 17, 2007,SAFETY EVALUATION FOR AUTHORIZATION OFCALLAWAY PLANT, UNIT 1, REQUEST FOR RELIEF ISI-39 Licensee's Basis for Relief Request (As stated in the licensee's application in the attachmentfor 10 CFR 50.55a Request Numbers ISI-36 (A.) through ISI-39 (D.))A.[Not for RR ISI-39]B.[Not for RR ISI-39]
| | ML073111442 NRR-106 OFFICE NRR/LPL4/PM NRR/LPL4/LA DCI/CVIB/BC NRR/LPL4/BC NAME JDonohew:sp JBurkhardt MMitchell THiltz DATE 12/4/07 12/6/07 12/5/07 12/10/07 ENCLOSURE REVISED PAGES 5 AND 6 OF SEPTEMBER 17, 2007, SAFETY EVALUATION FOR AUTHORIZATION OF CALLAWAY PLANT, UNIT 1, REQUEST FOR RELIEF ISI-39 |
| C.[Not for RR ISI-39]D.[The licensee for the] Callaway Plant obtained 100% coverage for reflectorsparallel to the weld seam by a combination of radial scan paths (Star scans) and scans from within the nozzle bore (Bore scans). However, the proximity of the nozzle protrusion or boss to the [RPV] Outlet Nozzle-to-Shell welds limits the parallel scans from the vessel ID [inside diameter] (Tangential scans). Because of this, limited coverage of 58.6% was achieved [when] examining for transverse reflectors. Combined final ultrasonic examination coverage was estimated at 79.3%.The design configuration/restriction makes the [ASME] Code-required examinationcoverage requirements impractical. Plant modifications or the replacement of components designed to allow for complete coverage would be needed to meet the ASME Code requirements. This would impose a considerable burden to [the licensee of the] Callaway Plant.Licensee's Proposed Alternative Examination (As stated in the licensee's application)[The licensee for] Callaway proposes to accept the percent coverage obtained on thesubject examinations. The best-effort examination approach, in addition to the other considerations or actions described below, provides reasonable assurance of safety and/or structural integrity.
| |
| ![Not for RR ISI-39]
| |
| l!The reactor vessel shell welds are constructed of low alloy steel [ ... Not for ISI-l39 ... ]. These materials have been shown to be resistant to stress corrosion lcracking in pressurized water environments. There is no [potential] degradationmechanism, other than fatigue, active in the subject welds that would cause weld failure.!VT-2 examinations performed in conjunction with system pressure testing eachrefueling, along with reactor coolant system leak rate limitations imposed by the plant's Technical Specifications, as well as containment atmospheric particulateradioactivity monitoring, provide additional assurance that a leak would be detected prior to any gross failure occurring.NRC Staff's EvaluationASME Code, Section XI requires volumetric examination of 100 percent as required inFigure IWB-2500-7(a) for the RPV Outlet Nozzle-to-Shell Welds numbered 2-RV-107-A, 2-RV-107-B, 2-RV-107-C, and 2-RV-107-D. The licensee was unable to meet the ASME Coderequirements due to the proximity of the nozzle protrusion or boss that limits the parallel scans from the RPV ID for tangential scans. For the licensee to meet the ASME Code requirements, modifications to, or the replacement of, the subject components would be required and would be major changes to the plant, which would place a burden on the licensee. Based on this, the NRC staff concludes that the ASME Code requirements are impractical.The licensee obtained 100 percent coverage for reflectors parallel to the weld seam by acombination of radial scan paths and scans from within the nozzle bore. Because of the configuration of the subject nozzles, the coverage was limited to 58.6 percent in examining for transverse reflectors. The licensee obtained an aggregate examination coverage of 79.3 percent for each of the subject nozzles. Therefore, the NRC staff determined that the lexaminations performed would have detected any significant patterns of degradation, if any had occurred. The NRC staff also determined that the volumetric and ASME Code VT-2 visual examinations during system walkdowns performed provided reasonable assurance of the structural integrity of RPV outlet nozzle-to-shell welds numbered 2-RV-107-A, 2-RV-107-B, 2-RV-107-C, and 2-RV-107-D.
| |
|
| |
|
| ==4.0CONCLUSION==
| | Licensees Basis for Relief Request (As stated in the licensees application in the attachment for 10 CFR 50.55a Request Numbers ISI-36 (A.) through ISI-39 (D.)) |
| The NRC staff has reviewed the licensee's application dated October 25, 2006, which submittedthe licensee's RRs ISI-36, ISI-37, and ISI-39. RR ISI-37 was withdrawn in the licensee's letter dated June 26, 2007.Based on its evaluation in Section 3.1 of this SE, the NRC staff concludes for RR ISI-36 thatrelief is not required for Callaway because the licensee has met the ASME Code volumetric examination requirements for the RPV Lower Torus to Dollar Plate Weld 2-RV-102-151. Furthermore, based on its evaluation in Section 3.2 of this SE, the NRC staff concludes that theASME Code examination coverage requirements are impractical for the subject welds listed in RR ISI-39. Based on the coverages obtained, if significant service-induced degradation were occurring, there is reasonable assurance that evidence of it would be detected by the volumetric examinations that were performed. The volumetric examinations and VT-2 visual lexaminations during plant walkdowns performed provide reasonable assurance of structural integrity of the RPV Outlet Nozzle-to-Shell Welds numbered 2-RV-107-A, 2-RV-107-B, 2-RV-107-C, and 2-RV-107-D. The NRC staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) for RR ISI-39 is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), the NRC staff concludes that RR ISI-39 is granted for Callaway for the second 10-year ISI interval.
| | A. [Not for RR ISI-39] |
| June 2007Callaway Plant, Unit 1 cc:John O'Neill, Esq.
| | B. [Not for RR ISI-39] |
| Pillsbury Winthrop Shaw Pittman LLP 2300 N. Street, N.W.
| | C. [Not for RR ISI-39] |
| Washington, D.C. 20037Mr. Keith A. Mills, Supervising EngineerRegional Regulatory Affairs/Safety Analysis AmerenUE P.O. Box 620 Fulton, MO 65251U.S. Nuclear Regulatory CommissionResident Inspector Office
| | D. [The licensee for the] Callaway Plant obtained 100% coverage for reflectors parallel to the weld seam by a combination of radial scan paths (Star scans) and scans from within the nozzle bore (Bore scans). However, the proximity of the nozzle protrusion or boss to the [RPV] Outlet Nozzle-to-Shell welds limits the parallel scans from the vessel ID [inside diameter] (Tangential scans). Because of this, limited coverage of 58.6% was achieved [when] examining for transverse reflectors. Combined final ultrasonic examination coverage was estimated at 79.3%. |
| | The design configuration/restriction makes the [ASME] Code-required examination coverage requirements impractical. Plant modifications or the replacement of components designed to allow for complete coverage would be needed to meet the ASME Code requirements. This would impose a considerable burden to [the licensee of the] Callaway Plant. |
| | Licensees Proposed Alternative Examination (As stated in the licensees application) |
| | [The licensee for] Callaway proposes to accept the percent coverage obtained on the subject examinations. The best-effort examination approach, in addition to the other considerations or actions described below, provides reasonable assurance of safety and/or structural integrity. |
| | ! [Not for RR ISI-39] l |
| | ! The reactor vessel shell welds are constructed of low alloy steel [ ... Not for ISI- l 39 ... ]. These materials have been shown to be resistant to stress corrosion l cracking in pressurized water environments. There is no [potential] degradation mechanism, other than fatigue, active in the subject welds that would cause weld failure. |
| | ! VT-2 examinations performed in conjunction with system pressure testing each refueling, along with reactor coolant system leak rate limitations imposed by the plant's Technical Specifications, as well as containment atmospheric particulate radioactivity monitoring, provide additional assurance that a leak would be detected prior to any gross failure occurring. |
| | NRC Staffs Evaluation ASME Code, Section XI requires volumetric examination of 100 percent as required in Figure IWB-2500-7(a) for the RPV Outlet Nozzle-to-Shell Welds numbered 2-RV-107-A, |
|
| |
|
| 8201 NRC Road Steedman, MO 65077-1302Mr. Les H. KanuckelManager, Quality Assurance AmerenUE P.O. Box 620 Fulton, MO 65251Missouri Public Service CommissionGovernor Office Building 200 Madison Street P.O. Box 360 Jefferson City, MO 65102-0360Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Mr. H. Floyd GilzowDeputy Director for Policy Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102-0176Mr. Rick A. MuenchPresident and Chief Executive Officer Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KA 66839Certrec Corporation4200 South Hulen, Suite 422 Fort Worth, TX 76109Technical Services Branch ChiefFEMA Region VII 2323 Grand Boulevard, Suite 900 Kansas City, MO 64108-2670Mr. Dan I. Bolef, PresidentKay Drey, Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, MO 63130Mr. Lee Fritz, Presiding CommissionerCallaway County Courthouse 10 East Fifth Street Fulton, MO 65251Mr. David E. Shafer, Superintendent, Licensing Regulatory Affairs AmerenUE P.O. Box 620 Fulton, MO 65251Manager, Regulatory AffairsAmerenUE P.O. Box 620 Fulton, MO 65251Mr. Keith G. Henke, PlannerDivision of Community and Public Health Office of Emergency Coordination 930 Wildwood P.O. Box 570 Jefferson City, MO 65102Director, Missouri State Emergency Management Agency P.O. Box 116 Jefferson City, MO 65102-0116Mr. Scott Clardy, DirectorSection for Environmental Public Health P.O. Box 570 Jefferson City, MO 65102-0570}}
| | 2-RV-107-B, 2-RV-107-C, and 2-RV-107-D. The licensee was unable to meet the ASME Code requirements due to the proximity of the nozzle protrusion or boss that limits the parallel scans from the RPV ID for tangential scans. For the licensee to meet the ASME Code requirements, modifications to, or the replacement of, the subject components would be required and would be major changes to the plant, which would place a burden on the licensee. Based on this, the NRC staff concludes that the ASME Code requirements are impractical. |
| | The licensee obtained 100 percent coverage for reflectors parallel to the weld seam by a combination of radial scan paths and scans from within the nozzle bore. Because of the configuration of the subject nozzles, the coverage was limited to 58.6 percent in examining for transverse reflectors. The licensee obtained an aggregate examination coverage of 79.3 percent for each of the subject nozzles. Therefore, the NRC staff determined that the l examinations performed would have detected any significant patterns of degradation, if any had occurred. The NRC staff also determined that the volumetric and ASME Code VT-2 visual examinations during system walkdowns performed provided reasonable assurance of the structural integrity of RPV outlet nozzle-to-shell welds numbered 2-RV-107-A, 2-RV-107-B, 2-RV-107-C, and 2-RV-107-D. |
| | |
| | ==4.0 CONCLUSION== |
| | |
| | The NRC staff has reviewed the licensee's application dated October 25, 2006, which submitted the licensees RRs ISI-36, ISI-37, and ISI-39. RR ISI-37 was withdrawn in the licensees letter dated June 26, 2007. |
| | Based on its evaluation in Section 3.1 of this SE, the NRC staff concludes for RR ISI-36 that relief is not required for Callaway because the licensee has met the ASME Code volumetric examination requirements for the RPV Lower Torus to Dollar Plate Weld 2-RV-102-151. |
| | Furthermore, based on its evaluation in Section 3.2 of this SE, the NRC staff concludes that the ASME Code examination coverage requirements are impractical for the subject welds listed in RR ISI-39. Based on the coverages obtained, if significant service-induced degradation were occurring, there is reasonable assurance that evidence of it would be detected by the volumetric examinations that were performed. The volumetric examinations and VT-2 visual l examinations during plant walkdowns performed provide reasonable assurance of structural integrity of the RPV Outlet Nozzle-to-Shell Welds numbered 2-RV-107-A, 2-RV-107-B, 2-RV-107-C, and 2-RV-107-D. The NRC staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) for RR ISI-39 is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), the NRC staff concludes that RR ISI-39 is granted for Callaway for the second 10-year ISI interval. |
| | |
| | Callaway Plant, Unit 1 cc: |
| | John ONeill, Esq. Technical Services Branch Chief Pillsbury Winthrop Shaw Pittman LLP FEMA Region VII 2300 N. Street, N.W. 2323 Grand Boulevard, Suite 900 Washington, D.C. 20037 Kansas City, MO 64108-2670 Mr. Keith A. Mills, Supervising Engineer Mr. Dan I. Bolef, President Regional Regulatory Affairs/Safety Analysis Kay Drey, Representative AmerenUE Board of Directors Coalition for the P.O. Box 620 Environment Fulton, MO 65251 6267 Delmar Boulevard University City, MO 63130 U.S. Nuclear Regulatory Commission Resident Inspector Office Mr. Lee Fritz, Presiding Commissioner 8201 NRC Road Callaway County Courthouse Steedman, MO 65077-1302 10 East Fifth Street Fulton, MO 65251 Mr. Les H. Kanuckel Manager, Quality Assurance Mr. David E. Shafer, AmerenUE Superintendent, Licensing Regulatory Affairs P.O. Box 620 AmerenUE Fulton, MO 65251 P.O. Box 620 Fulton, MO 65251 Missouri Public Service Commission Governor Office Building Manager, Regulatory Affairs 200 Madison Street AmerenUE P.O. Box 360 P.O. Box 620 Jefferson City, MO 65102-0360 Fulton, MO 65251 Regional Administrator, Region IV Mr. Keith G. Henke, Planner U.S. Nuclear Regulatory Commission Division of Community and Public Health 611 Ryan Plaza Drive, Suite 400 Office of Emergency Coordination Arlington, TX 76011-4005 930 Wildwood P.O. Box 570 Jefferson City, MO 65102 Mr. H. Floyd Gilzow Deputy Director for Policy Director, Missouri State Emergency Department of Natural Resources Management Agency P.O. Box 176 P.O. Box 116 Jefferson City, MO 65102-0176 Jefferson City, MO 65102-0116 Mr. Rick A. Muench Mr. Scott Clardy, Director President and Chief Executive Officer Section for Environmental Public Health Wolf Creek Nuclear Operating Corporation P.O. Box 570 P.O. Box 411 Jefferson City, MO 65102-0570 Burlington, KA 66839 Certrec Corporation 4200 South Hulen, Suite 422 Fort Worth, TX 76109 June 2007}} |
Letter Sequence Other |
|---|
|
|
MONTHYEARULNRC-05423, Responses to Requests for Additional Information Regarding Requests for Relief from ASME Section XI Code Examination Requirements, RRs ISI-34, ISI-37, ISI-38, and ISI-402007-06-29029 June 2007
Responses to Requests for Additional Information Regarding Requests for Relief from ASME Section XI Code Examination Requirements, RRs ISI-34, ISI-37, ISI-38, and ISI-40
Project stage: Response to RAI
ML0724000922007-09-17017 September 2007
Issuance of Relief Requests (Rrs) ISI-36, ISI-37, and ISI-38 for Second Year Inservice Inspection (ISI) Interval
Project stage: Approval
ML0729803972007-10-30030 October 2007
Relief Request ISI-38, Reactor Pressure Vessel Inlet Safe-End to-Elbow Welds Proposed Alternative Examination for Second 10-Year Inservice Inspection Interval
Project stage: Other
ML0731114422007-12-10010 December 2007
Correction to Authorization of Relief Request ISI-39 for the Second 10-Year Inservice Inspection Interval
Project stage: Other
2007-12-10
[Table View] |
|
|---|
Category:Code Relief or Alternative
MONTHYEARML20225A2922020-08-12012 August 2020
Request to Use a Portion of a Later Edition of the ASME B&PV Code, Section XI
ML19079A1482019-04-0101 April 2019
Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051
ML18313A0692018-11-26026 November 2018
Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping
ULNRC-06420, Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds2018-04-0909 April 2018
Request 14R-05 for Relief from Requirements of ASME Code Case N-770-2 Regarding Inspection Intervals for Reactor Vessel Nozzle Dissimilar Metal Welds
ML17262A7002017-10-0303 October 2017
Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval
ML17254A1202017-09-25025 September 2017
Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval
ML17058A4432017-03-0606 March 2017
Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval
ML16223A7122016-08-30030 August 2016
Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval
ML16055A4642016-03-17017 March 2016
Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737)
ML16027A1582016-01-29029 January 2016
Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval
ML15064A1252015-05-12012 May 2015
Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval
ML15035A1482015-02-10010 February 2015
Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval
ML14239A0972014-09-0404 September 2014
Request for Relief I3R-15, ASME Code Class 1 Pressure-Retaining Piping/Components Leakage Testing at Full Pressure, Third 10-Year Inservice Inspection Interval
ML14234A4512014-09-0404 September 2014
Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval
ML14178A7692014-07-15015 July 2014
Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval
ML14027A0572014-01-29029 January 2014
Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
ML13246A3042013-08-30030 August 2013
Verbal Authorization Email, Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
ML13126A3202013-05-0707 May 2013
Summary of Telephone Conference, Verbal Authorization of Relief Request I3R-14. Proposed Alternative to ASME Code Requirements for Leakage Testing of RPV Head Flange Leakoff Lines, Third 10-Year ISI Interval.
ML12258A0452012-09-18018 September 2012
Relief Request VR-01 from Requirements of ASME OM Code, Mandatory Appendix I, One-time Extension for 5-Year Replacement Interval, from 4/11/12 to 6/2013, Main Steam Isolation Valve Actuator Rupture Disks
ML1211502472012-05-0303 May 2012
Memo to File, Verbal Authorization, Relief Request VR-01 from Requirements of ASME OM Code Mandatory Appendix I, One-time Extension Replacement of Main Steam Isolation Valve Actuator Rupture Disks
ML1201907482012-02-16016 February 2012
Relief Request 13R-13, Alternative to ASME Code Section XI Requirements for Performance of Second Successive Exam of C Cold Leg Safe-End to Elbow Weld, Third 10-Year Inservice Inspection
ML0831002882008-11-0707 November 2008
Relief Request 13R-10 Approved on October 31, 2008, for Third 10-Year Inservice Inspection Interval for Use of Polyethylene Pipe in Lieu of Carbon Steel Pipe in Buried Essential Service Water Piping System
ML0818406062008-07-0303 July 2008
Approval of Second Extension Request for Corrective Actions GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.
ML0731114422007-12-10010 December 2007
Correction to Authorization of Relief Request ISI-39 for the Second 10-Year Inservice Inspection Interval
ML0729803972007-10-30030 October 2007
Relief Request ISI-38, Reactor Pressure Vessel Inlet Safe-End to-Elbow Welds Proposed Alternative Examination for Second 10-Year Inservice Inspection Interval
ML0724000922007-09-17017 September 2007
Issuance of Relief Requests (Rrs) ISI-36, ISI-37, and ISI-38 for Second Year Inservice Inspection (ISI) Interval
ML0725504882007-08-30030 August 2007
10 CFR 50.55a Request: Proposed Alternative to ASME Section Xi Requirements for Replacement of Class 3 Buried Piping
ML0715203292007-07-10010 July 2007
Request for Alternatives for Application of Structural Weld Overlays to Pressurizer Dissimilar Metal Nozzle Welds for Third 10-Year Inservice Inspection Program Interval
ML0705803332007-03-15015 March 2007
Authorization of Relief Request No. ISI-33 for Second 10-Year and Third 10-Year ISI Interval
ML0635203182007-01-18018 January 2007
Request for Relief No. ISI-35 for Second 10-year Inservice Inspection Interval
ML0700303362007-01-18018 January 2007
Relief Request ISI-41 for the Second 10-year Inservice Inspection Interval
ML0630604782006-12-0707 December 2006
Relief Request 13R-04 for the Third 10-Year Interval Inservice Inspection
ML0629302822006-11-17017 November 2006
Relief Requests I3R-05 and I3R-06 for the Third Inservice Inspection Interval
ULNRC-05183, Requests for Relief from ASME Section XI Code Inservice Examination Requirements2006-10-25025 October 2006
Requests for Relief from ASME Section XI Code Inservice Examination Requirements
ML0614301312006-06-15015 June 2006
Relief, Third 10-Year Interval Inservice Inspection Program Relief Request I3R-02
ML0520802152005-08-18018 August 2005
Relief, Use a Subsequent Edition of ASME Code Examinations for the Third Inservice Inspection Interval
ML0515302072005-06-22022 June 2005
6/22/05 Callaway, Unit 1 - Relief Requests ISI-24,ISI-25 and ISI-26 of the Second 10-Year Inservice Inspection (ISI) Interval (Tacs. MC4435 and MC4436)
ML0507601292005-05-19019 May 2005
Relief, Request for Relief from Certain ASME Code Examinations for the Second Inservice Inspection Interval
ULNRC-05092, Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program2004-11-18018 November 2004
Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program
ULNRC-05049, Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements2004-09-0303 September 2004
Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements
ML0414100712004-05-19019 May 2004
Relief, ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping.
ML0414100352004-05-19019 May 2004
Relief, Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method
ULNRC-04993, Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement2004-05-0707 May 2004
Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement
ML0409806642004-04-0707 April 2004
4/7/04 Callaway Plant - Request for Relief from ASME Code Requirements on the Use of Weld Overlay Reinforcement to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping
ULNRC-04879, Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements2003-08-14014 August 2003
Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements
ML0318305352003-07-0101 July 2003
Second Ten-Year Interval Inservice Inspection Program Relief Request to Use an Alternative Examination Method (Tac. MB6534)
ML0134602652002-01-30030 January 2002
Relief, Application of Risk-Informed Inservice Inspection Program for the American Society of Mechanical Engineers Boilers and Pressure Vessel Code Class 1 and 2 TAC No MB1205)
2020-08-12
[Table view]
Category:Letter
MONTHYEARULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024
Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717
IR 05000483/20230042024-01-19019 January 2024
Integrated Inspection Report 05000483/2023004
ML24008A0552024-01-19019 January 2024
Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061)
ML23353A1712024-01-18018 January 2024
Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6
ML23317A0012024-01-12012 January 2024
Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6
ML23347A1212024-01-11011 January 2024
Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046)
ML24011A1492024-01-11011 January 2024
Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011)
ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023
Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)
ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023
License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds
ML23346A0392023-12-14014 December 2023
Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System
ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023
Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification
05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023
Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications
ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023
Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)
IR 05000483/20230102023-11-15015 November 2023
NRC License Renewal Phase 1 Inspection Report 05000483 2023010
IR 05000483/20233012023-11-0909 November 2023
NRC Examination Report 05000483-2023301
ML23311A2082023-11-0909 November 2023
Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV
ML23297A2502023-11-0606 November 2023
Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter
IR 05000483/20240122023-10-24024 October 2023
Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012)
ML23293A2652023-10-24024 October 2023
3rd Quarter 2023 Integrated Inspection Report
ML23240A3692023-10-0505 October 2023
Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary)
ML23234A1522023-10-0505 October 2023
Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter)
ML23305A0942023-10-0202 October 2023
10-CW-2023-09 Post-Exam Submittal
ML23270B9662023-09-27027 September 2023
10 CFR 50.55a(z)(I) Request for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval
ML23228A0252023-09-25025 September 2023
Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
ML23261C3852023-09-25025 September 2023
Safety Evaluation for Operating Quality Assurance Manual Revision 36A
ML23166B0882023-09-20020 September 2023
Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications
ML23206A1992023-09-15015 September 2023
Regulatory Audit Summary Regarding License Amendment and Regulatory Exemptions Request for Fuel Transition to Framatome Gaia Fuel (Epids L-2022-LLA-0150 and L-2022-LLE-0030)
IR 05000483/20234012023-09-13013 September 2023
NRC Security Baseline Inspection Report 05000483/2023401
ML23240A7572023-08-31031 August 2023
NRC Initial Operator Licensing Examination Approval 05000483/2023301
IR 05000483/20230052023-08-23023 August 2023
Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023
ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023
Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A
ML23219A1392023-08-15015 August 2023
Request for Withholding Information from Public Disclosure
ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023
Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak
ML23215A1972023-08-0303 August 2023
Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002)
ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023
Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)
ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023
Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications
IR 05000483/20230022023-07-10010 July 2023
Integrated Inspection Report 05000483/2023002
ML23174A1272023-06-23023 June 2023
Cw FFD Document Request List 2023
ML23171A9942023-06-22022 June 2023
Acceptance of Request for Approval of Operating Quality Assurance Manual Revision 36a
ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023
Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)
IR 05000483/20230112023-06-15015 June 2023
Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011
ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023
Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a
ML23158A1462023-06-13013 June 2023
Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010)
ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023
Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a
ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .
ML23093A0952023-05-10010 May 2023
Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage
ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023
Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)
ML23129A7942023-05-0909 May 2023
Post-Audit Supplement to License Amendment Request and Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (Iepid L-2022-LLA-0150 and EPID L-2022-LLE-0030)
ML23122A3172023-05-0808 May 2023
Review of the Spring 2022 Steam Generator Tube Inservice Inspections
ML23118A3492023-05-0808 May 2023
Request for Withholding Information from Public Disclosure
2024-01-29
[Table view]
Category:Safety Evaluation
MONTHYEARML23353A1712024-01-18018 January 2024
Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6
ML23347A1212024-01-11011 January 2024
Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046)
ML23234A1522023-10-0505 October 2023
Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter)
ML23240A3692023-10-0505 October 2023
Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary)
ML23228A0252023-09-25025 September 2023
Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
ML23261C3852023-09-25025 September 2023
Safety Evaluation for Operating Quality Assurance Manual Revision 36A
ML23166B0882023-09-20020 September 2023
Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications
ML22361A0702023-02-24024 February 2023
Issuance of Amendment No. 231 for Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals
ML23019A1752023-01-30030 January 2023
Issuance of Amendment No. 230 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections
ML22301A0072022-12-0202 December 2022
Issuance of Amendment No. 229 to Revise Technical Specifications to Adopt TSTF-505, Revision 2, and TSTF-439, Revision 2
ML22220A1302022-10-21021 October 2022
Exemptions from the Requirements of 10 CFR 50.46 and 10 CFR Part 50 Appendix a, General Design Criteria 35, 38, and 41 (EPID L-2021-LLE-0021) (Cover Letter)
ML22220A1322022-10-21021 October 2022
Issuance of Amendment No. 228 Re; Revise Technical Specifications to Address Generic Safety Isusue-191 and Respond to Generic Letter 2004-02 Using Risk-Informed Approach
ML22053A2832022-04-0707 April 2022
Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-529, Revision 4, Clarify Use and Application Rules
ML21344A0052021-12-29029 December 2021
Issuance of Amendment No. 226 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants
ML21053A1262021-03-24024 March 2021
Issuance of Amendment No. 225 to Revise Technical Specification Administrative Control 5.3.1 to Remove Details Specified for the Qualification of Certain Positions within the Unit Staff
ML20218A4102020-11-0303 November 2020
Issuance of Amendment No. 224 Performance Based Method Alternative for Thermal Insulation Material
ML20246G5702020-10-16016 October 2020
Issuance of Amendment No. 223 One-Time Deferral of the Steam Generator Tube Inspections
ML20230A3872020-08-31031 August 2020
Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML20216A6812020-08-0606 August 2020
Operating Quality Assurance Manual Change Revision 34B (EPID L-2020-LLQ-0004 (COVID-19))
ML20141L7452020-06-0808 June 2020
Operating Quality Assurance Manual Change Revision 34A
ML20107H9782020-04-20020 April 2020
COVID-19 Relief Request CC-01 Containment Tendon Inspection
ML19283C4812019-12-0606 December 2019
Issuance of Amendment No. 221 Main Turbine Control Slave Relay Testing
ML19158A2902019-07-30030 July 2019
Issuance of Amendment No. 220 Regarding Emergency Action Level Scheme Changes
ML19073A0012019-04-18018 April 2019
Issuance of Amendment No. 219 to Add New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System
ML19079A1482019-04-0101 April 2019
Request for Alternative I4R-05 to Reactor Vessel Nozzle Weld Examination Frequency Requirements (EPID L-2018-LLR-0051
ML18313A0692018-11-26026 November 2018
Request for Relief I4R-01 Related to the Inservice Inspection Program for Class 3 Buried High Density Polyethylene Piping
ML18124A0262018-05-30030 May 2018
Issuance of Amendment No. 218 FSAR Revision Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection
ML17262A7002017-10-0303 October 2017
Request for Alternative I4R-04 Applicable to the Fourth 10-Year Inspection Program Interval
ML17254A1202017-09-25025 September 2017
Request for Alternative No. PR-07 from the Requirements of the ASME Code for the Fourth 10-Year Inservice Testing Interval
ML17236A0822017-09-15015 September 2017
Issuance of Amendment No. 217 Replacement of Methodology in Technical Specification 5.6.5, Core Operating Limits Report (Colr),
ML17170A3202017-06-20020 June 2017
Safety Evaluation Input - for Ameren Missouri Request to Amend Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report -
ML17058A4432017-03-0606 March 2017
Request for Alternative I4R-03 Applicable to the Fourth 10-Year Inservice Inspection Program Interval
ML17010A3322017-02-0202 February 2017
Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
ML16223A7122016-08-30030 August 2016
Relief Request No. 13R-08 from Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, for Piping Welds, Third 10-Year Inservice Inspection Interval
ML16089A1672016-04-0101 April 2016
Review and Approval of Quality Assurance Plan Change Per Nuclear Energy Institute (NEI) 14-05A, Revision 1
ML16055A4642016-03-17017 March 2016
Relief Requests 13R-09 (Steam Generator Tubesheet Weld), 13R-11 (Pressurizer Welds) from Code Case N-460 and 13R-18 (SG Weld), from Appendix Viii Requirements, Third 10-Year Inservice Inspection Interval (CAC MF6735-MF6737)
ML16020A5162016-02-29029 February 2016
Issuance of Amendment No. 216, Revise Technical Specification (TS) 2.1.1.1 and TS 5.6.5, to Remove Uncertainties from Departure from Nucleate Boiling Ratio Safety Limit and Adopt WCAP-14565-P-A Methodology
ML15324A1142016-02-0202 February 2016
Issuance of Amendment No. 215, Adopt Technical Specification Task Force (TSTF) Traveler TSTF-510, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection
ML16027A1582016-01-29029 January 2016
Relief Request I4R-02 from Requirements of ASME Code Section XI, Table IWF-2500-1 for 100% Visual Examination of Class 1 Supports, Fourth 10-Year Inservice Inspection Interval
ML15328A0592016-01-28028 January 2016
Issuance of Amendment No. 214, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone 8 Full Implementation Date
ML15258A5102015-10-28028 October 2015
Issuance of Amendment No. 213, Adopt Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation
ML15251A4932015-10-0707 October 2015
Issuance of Amendment No. 212, Request to Upgrade the Emergency Action Level Scheme by Adopting Nuclear Energy Institute NEI 99-01, Revision 6
ML15064A1252015-05-12012 May 2015
Request for Relief I4R-01 from ASME Code Requirements for Replacement of Class 3 Essential Service Water Buried Piping with High Density Polyethylene Piping, for the Fourth 10-year Inservice Testing Interval
ML15064A0282015-03-31031 March 2015
Issuance of Amendment No. 211, Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion
ML15035A1482015-02-10010 February 2015
Relief Request 13R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Reactor Vessel Inservice Inspection Frequency from 10 to 20 Years, Third 10-Year Interval
ML14350B2392015-01-20020 January 2015
Issuance of Amendment No. 210, Revise Technical Specification LCO 3.4.12, Cold Overpressure Mitigation System (Coms), to Clarify No Limitation on Normal Charging Pump Use During Modes 4-6
ML14234A4512014-09-0404 September 2014
Relief Request I3R-16, Temporary Non-Code Repair of the Train a Component Cooling Water Heat Exchanger to Control ESW Leakage, Third 10-Year Inservice Inspection Interval
ML14178A7692014-07-15015 July 2014
Requests for Relief PR-01, PR-02, PR-03, PR-04, and PR-06 (PR-05 Withdrawn), ASME OM Code Cases for Group a and B Pumps for Fourth 10-Year Inservice Testing Interval
ML14175A3902014-07-0101 July 2014
Issuance of Amendment No. 209, Adoption of Technical Specification Task Force Change Traveler TSTF-522-A, Revision 0, Revise Ventilation System to Operate for 10 Hours Per Month, Using CLIIP
ML14027A0572014-01-29029 January 2014
Relief Request PR-07, Testing Frequency for Pumps and Valves, Third 10-year Inservice Testing Interval
2024-01-18
[Table view] |
Text
December 10, 2007 Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - CORRECTION TO AUTHORIZATION OF RELIEF REQUEST ISI-39 FOR THE SECOND 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MD3435)
Dear Mr. Naslund:
In our letter to you dated September 17, 2007, the Nuclear Regulatory Commission (NRC) granted the relief in Relief Request (RR) ISI-39 for the second 10-year inservice inspection interval at the Callaway Plant, Unit 1 (Callaway). Union Electric Company (the licensee) submitted RR ISI-39 in its letter dated October 25, 2006 (ULNRC-05183).
In Section 3.2, on RR ISI-39, of the safety evaluation (SE) enclosed with our letter dated September 17, 2007, we documented the basis provided by the licensee to support the granting of RR ISI-39. Although the SE dated September 17, 2007, adequately documented the basis, we are modifying specific statements made in Section 3.2 of the SE to more precisely state the basis provided by the licensee for RR ISI-39. The attached revised pages 5 and 6 of the SE show the locations where modifications were made to the SE by the vertical lines on the right-hand-side of the two pages. Since the modifications did not change the conclusions made by the NRC in the SE, RR ISI-39 remains granted as of our letter dated September 17, 2007.
Please replace pages 5 and 6 of the Callaway SE dated September 17, 2007, on RR ISI-39 with the enclosed pages.
Sincerely,
/RA/
Jack Donohew, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483
Enclosure:
As stated cc w/encl: See next page
ML073111442 NRR-106 OFFICE NRR/LPL4/PM NRR/LPL4/LA DCI/CVIB/BC NRR/LPL4/BC NAME JDonohew:sp JBurkhardt MMitchell THiltz DATE 12/4/07 12/6/07 12/5/07 12/10/07 ENCLOSURE REVISED PAGES 5 AND 6 OF SEPTEMBER 17, 2007, SAFETY EVALUATION FOR AUTHORIZATION OF CALLAWAY PLANT, UNIT 1, REQUEST FOR RELIEF ISI-39
Licensees Basis for Relief Request (As stated in the licensees application in the attachment for 10 CFR 50.55a Request Numbers ISI-36 (A.) through ISI-39 (D.))
A. [Not for RR ISI-39]
B. [Not for RR ISI-39]
C. [Not for RR ISI-39]
D. [The licensee for the] Callaway Plant obtained 100% coverage for reflectors parallel to the weld seam by a combination of radial scan paths (Star scans) and scans from within the nozzle bore (Bore scans). However, the proximity of the nozzle protrusion or boss to the [RPV] Outlet Nozzle-to-Shell welds limits the parallel scans from the vessel ID [inside diameter] (Tangential scans). Because of this, limited coverage of 58.6% was achieved [when] examining for transverse reflectors. Combined final ultrasonic examination coverage was estimated at 79.3%.
The design configuration/restriction makes the [ASME] Code-required examination coverage requirements impractical. Plant modifications or the replacement of components designed to allow for complete coverage would be needed to meet the ASME Code requirements. This would impose a considerable burden to [the licensee of the] Callaway Plant.
Licensees Proposed Alternative Examination (As stated in the licensees application)
[The licensee for] Callaway proposes to accept the percent coverage obtained on the subject examinations. The best-effort examination approach, in addition to the other considerations or actions described below, provides reasonable assurance of safety and/or structural integrity.
! [Not for RR ISI-39] l
! The reactor vessel shell welds are constructed of low alloy steel [ ... Not for ISI- l 39 ... ]. These materials have been shown to be resistant to stress corrosion l cracking in pressurized water environments. There is no [potential] degradation mechanism, other than fatigue, active in the subject welds that would cause weld failure.
! VT-2 examinations performed in conjunction with system pressure testing each refueling, along with reactor coolant system leak rate limitations imposed by the plant's Technical Specifications, as well as containment atmospheric particulate radioactivity monitoring, provide additional assurance that a leak would be detected prior to any gross failure occurring.
NRC Staffs Evaluation ASME Code,Section XI requires volumetric examination of 100 percent as required in Figure IWB-2500-7(a) for the RPV Outlet Nozzle-to-Shell Welds numbered 2-RV-107-A,
2-RV-107-B, 2-RV-107-C, and 2-RV-107-D. The licensee was unable to meet the ASME Code requirements due to the proximity of the nozzle protrusion or boss that limits the parallel scans from the RPV ID for tangential scans. For the licensee to meet the ASME Code requirements, modifications to, or the replacement of, the subject components would be required and would be major changes to the plant, which would place a burden on the licensee. Based on this, the NRC staff concludes that the ASME Code requirements are impractical.
The licensee obtained 100 percent coverage for reflectors parallel to the weld seam by a combination of radial scan paths and scans from within the nozzle bore. Because of the configuration of the subject nozzles, the coverage was limited to 58.6 percent in examining for transverse reflectors. The licensee obtained an aggregate examination coverage of 79.3 percent for each of the subject nozzles. Therefore, the NRC staff determined that the l examinations performed would have detected any significant patterns of degradation, if any had occurred. The NRC staff also determined that the volumetric and ASME Code VT-2 visual examinations during system walkdowns performed provided reasonable assurance of the structural integrity of RPV outlet nozzle-to-shell welds numbered 2-RV-107-A, 2-RV-107-B, 2-RV-107-C, and 2-RV-107-D.
4.0 CONCLUSION
The NRC staff has reviewed the licensee's application dated October 25, 2006, which submitted the licensees RRs ISI-36, ISI-37, and ISI-39. RR ISI-37 was withdrawn in the licensees letter dated June 26, 2007.
Based on its evaluation in Section 3.1 of this SE, the NRC staff concludes for RR ISI-36 that relief is not required for Callaway because the licensee has met the ASME Code volumetric examination requirements for the RPV Lower Torus to Dollar Plate Weld 2-RV-102-151.
Furthermore, based on its evaluation in Section 3.2 of this SE, the NRC staff concludes that the ASME Code examination coverage requirements are impractical for the subject welds listed in RR ISI-39. Based on the coverages obtained, if significant service-induced degradation were occurring, there is reasonable assurance that evidence of it would be detected by the volumetric examinations that were performed. The volumetric examinations and VT-2 visual l examinations during plant walkdowns performed provide reasonable assurance of structural integrity of the RPV Outlet Nozzle-to-Shell Welds numbered 2-RV-107-A, 2-RV-107-B, 2-RV-107-C, and 2-RV-107-D. The NRC staff has determined that granting relief pursuant to 10 CFR 50.55a(g)(6)(i) for RR ISI-39 is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), the NRC staff concludes that RR ISI-39 is granted for Callaway for the second 10-year ISI interval.
Callaway Plant, Unit 1 cc:
John ONeill, Esq. Technical Services Branch Chief Pillsbury Winthrop Shaw Pittman LLP FEMA Region VII 2300 N. Street, N.W. 2323 Grand Boulevard, Suite 900 Washington, D.C. 20037 Kansas City, MO 64108-2670 Mr. Keith A. Mills, Supervising Engineer Mr. Dan I. Bolef, President Regional Regulatory Affairs/Safety Analysis Kay Drey, Representative AmerenUE Board of Directors Coalition for the P.O. Box 620 Environment Fulton, MO 65251 6267 Delmar Boulevard University City, MO 63130 U.S. Nuclear Regulatory Commission Resident Inspector Office Mr. Lee Fritz, Presiding Commissioner 8201 NRC Road Callaway County Courthouse Steedman, MO 65077-1302 10 East Fifth Street Fulton, MO 65251 Mr. Les H. Kanuckel Manager, Quality Assurance Mr. David E. Shafer, AmerenUE Superintendent, Licensing Regulatory Affairs P.O. Box 620 AmerenUE Fulton, MO 65251 P.O. Box 620 Fulton, MO 65251 Missouri Public Service Commission Governor Office Building Manager, Regulatory Affairs 200 Madison Street AmerenUE P.O. Box 360 P.O. Box 620 Jefferson City, MO 65102-0360 Fulton, MO 65251 Regional Administrator, Region IV Mr. Keith G. Henke, Planner U.S. Nuclear Regulatory Commission Division of Community and Public Health 611 Ryan Plaza Drive, Suite 400 Office of Emergency Coordination Arlington, TX 76011-4005 930 Wildwood P.O. Box 570 Jefferson City, MO 65102 Mr. H. Floyd Gilzow Deputy Director for Policy Director, Missouri State Emergency Department of Natural Resources Management Agency P.O. Box 176 P.O. Box 116 Jefferson City, MO 65102-0176 Jefferson City, MO 65102-0116 Mr. Rick A. Muench Mr. Scott Clardy, Director President and Chief Executive Officer Section for Environmental Public Health Wolf Creek Nuclear Operating Corporation P.O. Box 570 P.O. Box 411 Jefferson City, MO 65102-0570 Burlington, KA 66839 Certrec Corporation 4200 South Hulen, Suite 422 Fort Worth, TX 76109 June 2007
