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| {{#Wiki_filter:FENOC0E-% 5501 North State Route 2FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449Barry S. Allen 419-321-7676Vice President -Nuclear Fax. 419-321-7582May 25, 2012L-12-185 10 CFR 54ATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001 | | {{#Wiki_filter:FENOC 0E-% 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President |
| | -Nuclear Fax. 419-321-7582 May 25, 2012 L-12-185 10 CFR 54 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Davis-Besse Nuclear Power Station, Unit No. 1Docket No. 50-346, License Number NPF-3Supplemental Reply to Request for Additional Information for the Review of theDavis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application(TAC No. ME4640) and License Renewal Application Amendment No. 26By letter dated August 27, 2010 (Agencywide Documents Access and ManagementSystem (ADAMS) Accession No. ML102450565), FirstEnergy Nuclear OperatingCompany (FENOC) submitted an application pursuant to Title 10 of the Code of FederalRegulations, Part 54 for renewal of Operating License NPF-3 for the Davis-BesseNuclear Power Station, Unit No. 1 (DBNPS). By letter dated August 11, 2011(ML1 1216A236), the Nuclear Regulatory Commission (NRC) issued request foradditional information (RAI) 4.3.2.3.2 (Supplement), to complete its review of theLicense Renewal Application (LRA). By letter dated October 7, 2011 (ML1 1285A064),FENOC responded to the RAI by providing a commitment to perform a fatigue evaluationof selected Class 1 valves and submit an amendment to the LRA.The actions described in the commitment have been completed. The Attachmentprovides a supplemental response to NRC RAI 4.3.2.3.2 (Supplement), including adescription of the Class 1 valve fatigue evaluations performed and results obtained. TheNRC request is shown in bold text followed by the FENOC response.The Enclosure provides Amendment No. 26 to the DBNPS LRA. | | Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 Supplemental Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 26 By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102450565), FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS). By letter dated August 11, 2011 (ML1 1216A236), the Nuclear Regulatory Commission (NRC) issued request for additional information (RAI) 4.3.2.3.2-1 |
| Davis-Besse Nuclear Power Station, Unit No. 1L-1 2-185Page 2There are no regulatory commitments contained in this letter. If there are any questionsor if additional information is required, please contact Mr. Clifford I. Custer, FleetLicense Renewal Project Manager, at 724-682-7139.I declare under penalty of perjury that the foregoing is true and correct. Executed onMay_2, 2012.Sincerely,Barry S en | | -(Supplement), to complete its review of the License Renewal Application (LRA). By letter dated October 7, 2011 (ML1 1285A064), FENOC responded to the RAI by providing a commitment to perform a fatigue evaluation of selected Class 1 valves and submit an amendment to the LRA.The actions described in the commitment have been completed. |
| | The Attachment provides a supplemental response to NRC RAI 4.3.2.3.2-1 |
| | -(Supplement), including a description of the Class 1 valve fatigue evaluations performed and results obtained. |
| | The NRC request is shown in bold text followed by the FENOC response.The Enclosure provides Amendment No. 26 to the DBNPS LRA. |
| | Davis-Besse Nuclear Power Station, Unit No. 1 L-1 2-185 Page 2 There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at 724-682-7139. |
| | I declare under penalty of perjury that the foregoing is true and correct. Executed on May_2, 2012.Sincerely, Barry S en |
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| ==Attachment:== | | ==Attachment:== |
| Supplemental Reply to Request for Additional Information for the Review of theDavis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License RenewalApplication, Section 4.3.2 | | |
| | Supplemental Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License Renewal Application, Section 4.3.2 |
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| ==Enclosure:== | | ==Enclosure:== |
| Amendment No. 26 to the DBNPS License Renewal Applicationcc: NRC DLR Project ManagerNRC Region III Administratorcc: w/o Attachment or EnclosureNRC DLR DirectorNRR DORL Project ManagerNRC Resident InspectorUtility Radiological Safety Board AttachmentL-12-185Supplemental Reply to Request for Additional Information for the Review of theDavis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License Renewal Application,Section 4.3.2Page 1 of 3Section 4.3.2Question RAI 4.3.2.3.2 (Supplement) | | |
| | Amendment No. 26 to the DBNPS License Renewal Application cc: NRC DLR Project Manager NRC Region III Administrator cc: w/o Attachment or Enclosure NRC DLR Director NRR DORL Project Manager NRC Resident Inspector Utility Radiological Safety Board Attachment L-12-185 Supplemental Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License Renewal Application, Section 4.3.2 Page 1 of 3 Section 4.3.2 Question RAI 4.3.2.3.2-1 |
| | -(Supplement) |
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| ==Background:== | | ==Background:== |
| By letter dated June 22, 2011, the applicant responded to RAI 4.1-1 regardingcumulative usage factor (CUF) or It fatigue analyses for Class 1 valves. In itsresponse to RAI 4.1-1, Request 1, Part A, the applicant identified 12 large boreClass 1 valves (i.e., valves with nominal pipe sizes in excess of 4-inches) thatshould have received CUF or It fatigue analyses in accordance with the designcodes (i.e., 1971 or more recent Editions of the ASME Code Section III, or the1968 Edition of the Draft ASME Pump and Valve Code for Nuclear Power Plants).The applicant provided Commitment No. 46 to complete the following, prior toApril 22, 2015:FENOC commits to perform a fatigue evaluation in accordance withthe requirements of the ASME Code of record for the Davis-BesseClass 1 valves that are greater than 4 inches nominal pipe size. Theapplicable valve identification numbers are CF28, CF29, CF30, CF31,DH76, DH77, DH11, DH12, DHIA, DHIB, DH21, and DH23.LRA Section 4.3.2.3.2, as amended by letter dated June 22, 2011, states that thefatigue analyses for these 12 referenced large bore Class I valves are as TLAAsand are dispositioned in accordance with Title 10 of the Code of FederalRegulations 54.21(c)(1)(iii), that the effects of fatigue on Class 1 valves greaterthan 4 inches diameter nominal pipe size will be managed for the period ofextended operation by the Fatigue Monitoring Program. LRA Section 4.3.2.3.2also states that the issue with the missing CUF or It calculations for the12 referenced large bore Class 1 valves has been entered into the applicant'sCorrective Actions Program.Issue:The information provided by the applicant in letter of June 22, 2011, did notprovide information regarding whether the applicant had any ASME Code,Section III NB-3222.4(d) fatigue waiver assessments (or equivalent waiverassessments permitted by the 1968 Draft ASME Pump and Valve Code) for the12 large bore Class 1 valves referenced in Commitment No. 46. Therefore, the AttachmentL-12-185Page 2 of 3staff requests additional information regarding whether fatigue calculations arerequired for these valves.The staff is concerned that without the CUF or It analyses or an appropriatefatigue waiver or exemption for these 12 large bore Class 1 valves, the staff wouldnot be able to evaluate whether the aging effects will be appropriately managedby the commitment.Request:Provide justification for not having the analyses for staff review as part of theLRA, or provide your appropriate fatigue waiver or fatigue exemption bases fornot having such analyses.RESPONSE RAI 4.3.2.3.2 (Supplement)In response to RAI 4.3.2.3.2 (Supplement) submitted by letter dated October 7, 2011(ML1 1285A064), FENOC provided the following commitment:FENOC will perform a fatigue evaluation in accordance with therequirements of the ASME Code of record for the Davis-Besse Class 1valves that are greater than 4 inches diameter nominal pipe size. Theapplicable valve identification numbers are CF28, CF29, CF30, CF31, DH76,DH77, DH11, DH12, DH1A, DH1B, DH21 and DH23. LRA Sections 4.3.2.3.2and A.2.3.2.13, both titled "Class 1 Valves Fatigue," will be revised to includethe results of the fatigue evaluations, and these changes will be submitted asan amendment to the Davis Besse LRA no later than May 31, 2012.The actions described in the commitment have been completed. This supplementalresponse to RAI 4.3.2.3.2 (Supplement) addresses the fatigue evaluation results ofthe Davis-Besse Class 1 valves that are greater than 4 inches diameter nominal pipesize (valve identification numbers CF28, CF29, CF30, CF31, DH76, DH77, DH1 1,DH12, DHIA, DH1B, DH21 and DH23) and the associated changes to License RenewalApplication (LRA) Sections 4.3.2.3.2 and A.2.3.2.13.Fatigue analyses were prepared for the subject Class 1 valves in accordance withparagraph NB-3550 of ASME Code Section III, 1974 Edition with Addenda through theSummer of 1976, and were reconciled to the valve construction code year. Thecumulative usage factors (CUFs) calculated for the subject Class 1 valves are based onnuclear steam supply system design transients and, as shown in the table below, areless than 1.0. The number of occurrences of design transients is tracked by the FatigueMonitoring Program to ensure that action is taken before the design cycles are reached.Therefore, the effects of fatigue on Class 1 valves greater than 4 inches diameter AttachmentL-12-185Page 3 of 3nominal pipe size (NPS) will be managed for the period of extended operation by theFatigue Monitoring Program in accordance with 10 CFR 54.21(c)(1)(iii).Size Construction MaximumValve ID (dia. NPS) Code Year CUF& TypeCF28CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839CF30 Winter 1972 stop check isolation valveCF31DHI 1 12 inch 1968 Reactor Coolant System to Decay Heat- 0.14594gate Draft Pump & containment isolation valveDH12 gValveDH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732DH23 gate Winter 1972 isolation valveDH76 10 inch 1971 Low Pressure Injection tow/Addenda thru Reactor Coolant System -0.14099DH77 Winter 1972 stop check isolation valveDH1A 10 inch 1968 Low Pressure Injection -gate Draft Pump & outside containment isolation valve 0.18261DH1Bgt ValveLRA Sections 4.3.2.3.2 and A.2.3.2.13 are revised to include the results of the fatigueevaluations.See the Enclosure to this letter for the revision to the DBNPS LRA. | | |
| EnclosureDavis-Besse Nuclear Power Station, Unit No. 1 (DBNPS)Letter L-12-185Amendment No. 26 to theDBNPS License Renewal ApplicationPage 1 of 5License Renewal ApplicationSections AffectedSection 4.3.2.3.2Section A.2.3.2.13The Enclosure identifies the change to the License Renewal Application (LRA) byAffected LRA Section, LRA Page No., and Affected Paragraph and Sentence. Thecount for the affected paragraph, sentence, bullet, etc. starts at the beginning of theaffected Section or at the top of the affected page, as appropriate. Below each sectionthe reason for the change is identified, and the sentence affected is printed in italics withdeleted text hined-ou and added text underlined.
| | By letter dated June 22, 2011, the applicant responded to RAI 4.1-1 regarding cumulative usage factor (CUF) or It fatigue analyses for Class 1 valves. In its response to RAI 4.1-1, Request 1, Part A, the applicant identified 12 large bore Class 1 valves (i.e., valves with nominal pipe sizes in excess of 4-inches) that should have received CUF or It fatigue analyses in accordance with the design codes (i.e., 1971 or more recent Editions of the ASME Code Section III, or the 1968 Edition of the Draft ASME Pump and Valve Code for Nuclear Power Plants).The applicant provided Commitment No. 46 to complete the following, prior to April 22, 2015: FENOC commits to perform a fatigue evaluation in accordance with the requirements of the ASME Code of record for the Davis-Besse Class 1 valves that are greater than 4 inches nominal pipe size. The applicable valve identification numbers are CF28, CF29, CF30, CF31, DH76, DH77, DH11, DH12, DHIA, DHIB, DH21, and DH23.LRA Section 4.3.2.3.2, as amended by letter dated June 22, 2011, states that the fatigue analyses for these 12 referenced large bore Class I valves are as TLAAs and are dispositioned in accordance with Title 10 of the Code of Federal Regulations 54.21(c)(1)(iii), that the effects of fatigue on Class 1 valves greater than 4 inches diameter nominal pipe size will be managed for the period of extended operation by the Fatigue Monitoring Program. LRA Section 4.3.2.3.2 also states that the issue with the missing CUF or It calculations for the 12 referenced large bore Class 1 valves has been entered into the applicant's Corrective Actions Program.Issue: The information provided by the applicant in letter of June 22, 2011, did not provide information regarding whether the applicant had any ASME Code, Section III NB-3222.4(d) fatigue waiver assessments (or equivalent waiver assessments permitted by the 1968 Draft ASME Pump and Valve Code) for the 12 large bore Class 1 valves referenced in Commitment No. 46. Therefore, the Attachment L-12-185 Page 2 of 3 staff requests additional information regarding whether fatigue calculations are required for these valves.The staff is concerned that without the CUF or It analyses or an appropriate fatigue waiver or exemption for these 12 large bore Class 1 valves, the staff would not be able to evaluate whether the aging effects will be appropriately managed by the commitment. |
| EnclosureL-12-185Page 2 of 5Affected LRA Section LRA Page No. Affected Paragraph and Sentence4.3.2.3.2 Pages 4.3-16 Entire Sectionand 4.3-17In response to RAI 4.3.2.3.2 (Supplement), LRA Section 4.3.2.3.2, "Class 1Valves Fatigue," previously revised by FENOC letter dated October 7, 2011(ML1I1285A064), is replaced in its entirety, to read as follows:4.3.2.3.2 Class 1 Valves FatigueThe ASME Code requires a fatigue evaluation for Class 1 valves greater than 4inches diameter nominal pipe size or for valves less than or equal to 4 inches innominal pipe size if specified by the owner's design specification. TheDavis-Besse purchasing specifications did not require a fatigue analysis forClass 1 valves less than or equal to 4 inches in nominal pipe size. Therefore,only valves greater than 4 inches diameter nominal pipe size require a fatigueanalysis. Piping and instrumentation diagrams (P&IDs) were reviewed to identifyClass 1 valves of greater than 4 inches diameter nominal pipe size. There were12 valves of greater than 4 inches diameter nominal pipe size that were identifiedas a result of this effort.Fatigue analyses were prepared for the subject Class 1 valves in accordancewith paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addendathrough the Summer of 1976 and were reconciled to the valve constructioncode year.Since ASME Code fatigue analyses evaluate an explicit number and type ofthermal and pressure transients that are postulated to envelope the number ofoccurrences possible during the design life of the plant, these fatigue analysesare time-limited aging analyses (TLAAs) and therefore, are required to beevaluated in accordance with 10 CFR 54.21(c)(1).The cumulative usage factors calculated for the subject Class 1 valves are basedon nuclear steam supply system design transients and, as shown in the tablebelow, are less than 1.0. The number of occurrences of design transients istracked by the Fatigue Monitoring Program to ensure that action is taken beforethe design cycles are reached. Therefore, the effects of fatigue on Class 1 valvesgreater than 4 inches diameter nominal pipe size (NPS) will be managed for theperiod of extended operation by the Fatigue Monitoring Program.
| | Request: Provide justification for not having the analyses for staff review as part of the LRA, or provide your appropriate fatigue waiver or fatigue exemption bases for not having such analyses.RESPONSE RAI 4.3.2.3.2-1 |
| EnclosureL-12-185Page 3 of 5Size Construction MaximumValve ID (dia. NPS) Code Year Description CUF& TypeCF28CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839CF30 Winter 1972 stop check isolation valveCF31Draft1968 Reactor Coolant System to Decay Heat -DH12 gate Valv containment isolation valve 0.14594DH12 ValveDH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732DH23 gate Winter 1972 isolation valveDH76 10 inch 1971 Low Pressure Injection tow/Addenda thru Reactor Coolant System -0.14099DH77 Winter 1972 stop check isolation valveDDrf1A 10 inch 1968 Low Pressure Injection -gae Draft Pump & outside containment isolation valve 0.18261DH-11B at ValveDisposition: 10 CFR 54.21(c)(1)(iii)The effects of fatigue on Class I valvesgreater than 4 inches diameter nominalpipe size will be managed for the periodof extended operation by the FatigueMonitoring Program.
| | -(Supplement) |
| EnclosureL-1 2-185Page 4 of 5Affected LRA Section LRA Paqe No. Affected Paragraph and SentenceA.2.3.2.13 Page A-41 Entire SectionIn response to RAI 4.3.2.3.2 (Supplement), LRA Section A.2.3.2.13, "Class 1Valves Fatigue," previously revised by FENOC letter dated October 7, 2011(ML1I1285A064), is replaced in its entirety, to read as follows:A.2.3.2.13 Class 1 Valves FatigueThe ASME Code requires a fatigue evaluation for Class 1 valves greater than 4inches diameter nominal pipe size or for valves less than or equal to 4 inches innominal pipe size if specified by the owner's design specification. TheDavis-Besse purchasing specifications did not require a fatigue analysis forClass 1 valves less than or equal to 4 inches in nominal pipe size. Therefore,only valves greater than 4 inches diameter nominal pipe size require a fatigueanalysis. Piping and instrumentation diagrams (P&IDs) were reviewed to identifyClass 1 valves of greater than 4 inches diameter nominal pipe size. There were12 valves of greater than 4 inches diameter nominal pipe size that were identifiedas a result of this effort.Fatigue analyses were prepared for the subject Class 1 valves in accordancewith paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addendathrough the Summer of 1976 and were reconciled to the valve constructioncode year.Since ASME Code fatigue analyses evaluate an explicit number and type ofthermal and pressure transients that are postulated to envelope the number ofoccurrences possible during the design life of the plant, these fatigue analysesare time-limited aging analyses (TLAAs) and therefore, are required to beevaluated in accordance with 10 CFR 54.21(c)(1).The cumulative usage factors calculated for the subject Class 1 valves are basedon nuclear steam supply system design transients and, as shown in the tablebelow, are less than 1.0. The number of occurrences of design transients istracked by the Fatigue Monitoring Program to ensure that action is taken beforethe design cycles are reached. Therefore, the effects of fatigue on Class 1 valvesgreater than 4 inches diameter nominal pipe size (NPS) will be managed for theperiod of extended operation by the Fatigue Monitoring Program in accordancewith 10 CFR 54.21 (c)(1)(iii).
| | In response to RAI 4.3.2.3.2-1 |
| EnclosureL-12-185Page 5 of 5size Construction MaximumValve ID (dia. NPS) Code Year Description CUF& TypeCF28CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839CF30 Winter 1972 stop check isolation valveCF31Draft1968 Reactor Coolant System to Decay Heat -DH1g Draft Pump & containment isolation valve 0.14594DH12 gaeValveDH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732DH23 gate Winter 1972 isolation valveDH76 10 inch 1971 Low Pressure Injection tow/Addenda thru Reactor Coolant System -0.14099DH77 Winter 1972 stop check isolation valveDH1A 10 inch 1968 Low Pressure Injection -Dae Draft Pump & outside containment isolation valve 0.18261DH-11B at Valve III
| | -(Supplement) submitted by letter dated October 7, 2011 (ML1 1285A064), FENOC provided the following commitment: |
| }} | | FENOC will perform a fatigue evaluation in accordance with the requirements of the ASME Code of record for the Davis-Besse Class 1 valves that are greater than 4 inches diameter nominal pipe size. The applicable valve identification numbers are CF28, CF29, CF30, CF31, DH76, DH77, DH11, DH12, DH1A, DH1B, DH21 and DH23. LRA Sections 4.3.2.3.2 and A.2.3.2.13, both titled "Class 1 Valves Fatigue," will be revised to include the results of the fatigue evaluations, and these changes will be submitted as an amendment to the Davis Besse LRA no later than May 31, 2012.The actions described in the commitment have been completed. |
| | This supplemental response to RAI 4.3.2.3.2-1 |
| | -(Supplement) addresses the fatigue evaluation results of the Davis-Besse Class 1 valves that are greater than 4 inches diameter nominal pipe size (valve identification numbers CF28, CF29, CF30, CF31, DH76, DH77, DH1 1, DH12, DHIA, DH1B, DH21 and DH23) and the associated changes to License Renewal Application (LRA) Sections 4.3.2.3.2 and A.2.3.2.13. |
| | Fatigue analyses were prepared for the subject Class 1 valves in accordance with paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addenda through the Summer of 1976, and were reconciled to the valve construction code year. The cumulative usage factors (CUFs) calculated for the subject Class 1 valves are based on nuclear steam supply system design transients and, as shown in the table below, are less than 1.0. The number of occurrences of design transients is tracked by the Fatigue Monitoring Program to ensure that action is taken before the design cycles are reached.Therefore, the effects of fatigue on Class 1 valves greater than 4 inches diameter Attachment L-12-185 Page 3 of 3 nominal pipe size (NPS) will be managed for the period of extended operation by the Fatigue Monitoring Program in accordance with 10 CFR 54.21(c)(1)(iii). |
| | Size Construction Maximum Valve ID (dia. NPS) Code Year CUF& Type CF28 CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839 CF30 Winter 1972 stop check isolation valve CF31 DHI 1 12 inch 1968 Reactor Coolant System to Decay Heat- 0.14594 gate Draft Pump & containment isolation valve DH12 gValve DH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732 DH23 gate Winter 1972 isolation valve DH76 10 inch 1971 Low Pressure Injection to w/Addenda thru Reactor Coolant System -0.14099 DH77 Winter 1972 stop check isolation valve DH1A 10 inch 1968 Low Pressure Injection |
| | -gate Draft Pump & outside containment isolation valve 0.18261 DH1Bgt Valve LRA Sections 4.3.2.3.2 and A.2.3.2.13 are revised to include the results of the fatigue evaluations. |
| | See the Enclosure to this letter for the revision to the DBNPS LRA. |
| | Enclosure Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS)Letter L-12-185 Amendment No. 26 to the DBNPS License Renewal Application Page 1 of 5 License Renewal Application Sections Affected Section 4.3.2.3.2 Section A.2.3.2.13 The Enclosure identifies the change to the License Renewal Application (LRA) by Affected LRA Section, LRA Page No., and Affected Paragraph and Sentence. |
| | The count for the affected paragraph, sentence, bullet, etc. starts at the beginning of the affected Section or at the top of the affected page, as appropriate. |
| | Below each section the reason for the change is identified, and the sentence affected is printed in italics with deleted text hined-ou and added text underlined. |
| | Enclosure L-12-185 Page 2 of 5 Affected LRA Section LRA Page No. Affected Paragraph and Sentence 4.3.2.3.2 Pages 4.3-16 Entire Section and 4.3-17 In response to RAI 4.3.2.3.2-1 |
| | -(Supplement), LRA Section 4.3.2.3.2, "Class 1 Valves Fatigue," previously revised by FENOC letter dated October 7, 2011 (ML1I1285A064), is replaced in its entirety, to read as follows: 4.3.2.3.2 Class 1 Valves Fatigue The ASME Code requires a fatigue evaluation for Class 1 valves greater than 4 inches diameter nominal pipe size or for valves less than or equal to 4 inches in nominal pipe size if specified by the owner's design specification. |
| | The Davis-Besse purchasing specifications did not require a fatigue analysis for Class 1 valves less than or equal to 4 inches in nominal pipe size. Therefore, only valves greater than 4 inches diameter nominal pipe size require a fatigue analysis. |
| | Piping and instrumentation diagrams (P&IDs) were reviewed to identify Class 1 valves of greater than 4 inches diameter nominal pipe size. There were 12 valves of greater than 4 inches diameter nominal pipe size that were identified as a result of this effort.Fatigue analyses were prepared for the subject Class 1 valves in accordance with paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addenda through the Summer of 1976 and were reconciled to the valve construction code year.Since ASME Code fatigue analyses evaluate an explicit number and type of thermal and pressure transients that are postulated to envelope the number of occurrences possible during the design life of the plant, these fatigue analyses are time-limited aging analyses (TLAAs) and therefore, are required to be evaluated in accordance with 10 CFR 54.21(c)(1). |
| | The cumulative usage factors calculated for the subject Class 1 valves are based on nuclear steam supply system design transients and, as shown in the table below, are less than 1.0. The number of occurrences of design transients is tracked by the Fatigue Monitoring Program to ensure that action is taken before the design cycles are reached. Therefore, the effects of fatigue on Class 1 valves greater than 4 inches diameter nominal pipe size (NPS) will be managed for the period of extended operation by the Fatigue Monitoring Program. |
| | Enclosure L-12-185 Page 3 of 5 Size Construction Maximum Valve ID (dia. NPS) Code Year Description CUF& Type CF28 CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839 CF30 Winter 1972 stop check isolation valve CF31 Draft1968 Reactor Coolant System to Decay Heat -DH12 gate Valv containment isolation valve 0.14594 DH12 Valve DH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732 DH23 gate Winter 1972 isolation valve DH76 10 inch 1971 Low Pressure Injection to w/Addenda thru Reactor Coolant System -0.14099 DH77 Winter 1972 stop check isolation valve DDrf1A 10 inch 1968 Low Pressure Injection |
| | -gae Draft Pump & outside containment isolation valve 0.18261 DH-11B at Valve Disposition: |
| | 10 CFR 54.21(c)(1)(iii) |
| | The effects of fatigue on Class I valves greater than 4 inches diameter nominal pipe size will be managed for the period of extended operation by the Fatigue Monitoring Program. |
| | Enclosure L-1 2-185 Page 4 of 5 Affected LRA Section LRA Paqe No. Affected Paragraph and Sentence A.2.3.2.13 Page A-41 Entire Section In response to RAI 4.3.2.3.2-1 |
| | -(Supplement), LRA Section A.2.3.2.13, "Class 1 Valves Fatigue," previously revised by FENOC letter dated October 7, 2011 (ML1I1285A064), is replaced in its entirety, to read as follows: A.2.3.2.13 Class 1 Valves Fatigue The ASME Code requires a fatigue evaluation for Class 1 valves greater than 4 inches diameter nominal pipe size or for valves less than or equal to 4 inches in nominal pipe size if specified by the owner's design specification. |
| | The Davis-Besse purchasing specifications did not require a fatigue analysis for Class 1 valves less than or equal to 4 inches in nominal pipe size. Therefore, only valves greater than 4 inches diameter nominal pipe size require a fatigue analysis. |
| | Piping and instrumentation diagrams (P&IDs) were reviewed to identify Class 1 valves of greater than 4 inches diameter nominal pipe size. There were 12 valves of greater than 4 inches diameter nominal pipe size that were identified as a result of this effort.Fatigue analyses were prepared for the subject Class 1 valves in accordance with paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addenda through the Summer of 1976 and were reconciled to the valve construction code year.Since ASME Code fatigue analyses evaluate an explicit number and type of thermal and pressure transients that are postulated to envelope the number of occurrences possible during the design life of the plant, these fatigue analyses are time-limited aging analyses (TLAAs) and therefore, are required to be evaluated in accordance with 10 CFR 54.21(c)(1). |
| | The cumulative usage factors calculated for the subject Class 1 valves are based on nuclear steam supply system design transients and, as shown in the table below, are less than 1.0. The number of occurrences of design transients is tracked by the Fatigue Monitoring Program to ensure that action is taken before the design cycles are reached. Therefore, the effects of fatigue on Class 1 valves greater than 4 inches diameter nominal pipe size (NPS) will be managed for the period of extended operation by the Fatigue Monitoring Program in accordance with 10 CFR 54.21 (c)(1)(iii). |
| | Enclosure L-12-185 Page 5 of 5 size Construction Maximum Valve ID (dia. NPS) Code Year Description CUF& Type CF28 CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839 CF30 Winter 1972 stop check isolation valve CF31 Draft1968 Reactor Coolant System to Decay Heat -DH1g Draft Pump & containment isolation valve 0.14594 DH12 gaeValve DH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732 DH23 gate Winter 1972 isolation valve DH76 10 inch 1971 Low Pressure Injection to w/Addenda thru Reactor Coolant System -0.14099 DH77 Winter 1972 stop check isolation valve DH1A 10 inch 1968 Low Pressure Injection |
| | -Dae Draft Pump & outside containment isolation valve 0.18261 DH-11B at Valve III}} |
Letter Sequence Response to RAI |
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TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples, L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems., L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21, L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal, L-12-444, Submittal of Contractor Equivalent Margins Assessments for Reactor Vessel Welds (Nonproprietary Versions), L-12-456, Notification of Closure of Commitments Related to the Review of the License Renewal Application, L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45), L-13-330, License Renewal Application Amendment No. 46 - Annual Update, L-13-341, Review of the Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 48, L-14-206, License Renewal Application Amendment No. 50 - Annual Update, L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55, L-15-139, License Renewal Reactor Vessel Internals Inspection Plan, L-15-214, License Renewal Application Amendment No. 59 - Annual Update, L-15-309, License Renewal Application Amendment No. 60, L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits., ML102450565, ML111050091, ML11110A089, ML11110A091, ML11110A092, ML11110A093, ML11110A094, ML11110A095, ML11110A105, ML11110A106, ML11110A107, ML11122A014, ML11126A017, ML11126A018, ML11126A019, ML11126A020, ML11126A021, ML11126A022, ML11126A023, ML11126A024, ML11126A025, ML11126A026, ML11126A032, ML11126A033, ML11126A034, ML11126A035, ML11126A036, ML11126A037, ML11126A038, ML11126A039, ML11126A040, ML11126A041, ML11126A042, ML11126A043... further results
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MONTHYEARML11126A0882008-01-12012 January 2008
Drawing No. LR-M041B, Revision 1, Piping & Instrument Diagram Primary Service Water System. Job Code 12501
Project stage: Other
ML11126A0902008-01-15015 January 2008
Drawing No. LR-OS41A1, Revision 1, Operational Schematic Emergency Diesel Generator Systems.
Project stage: Other
L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.2008-01-15015 January 2008
Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems.
Project stage: Other
ML11126A0682008-05-0505 May 2008
Drawing No. LR-M-037E, Revision 28, Piping & Instrument Diagram Clean Liquid Radioactive Waste System.
Project stage: Other
ML11126A0652008-08-0606 August 2008
Drawing No. LR-M036B, Revision 1, Piping & Instrument Diagram Component Cooling Water System.
Project stage: Other
ML11126A0592008-10-0909 October 2008
Drawing No. LR-M033A, Revision 1, Piping & Instrument Diagram High Pressure Injection.
Project stage: Other
ML11126A0632008-10-10010 October 2008
Drawing No. LR-M033B, Revision 1, Piping & Instrument Diagram Decay Heat Train 1.
Project stage: Other
ML11126A0702008-10-10010 October 2008
Drawing No. LR-M033C, Revision 1, Piping & Instrument Diagram Decay Heat Train 2.
Project stage: Other
ML11126A0742008-11-0606 November 2008
Drawing No. LR-M043, Revision 1, Piping & Instrument Diagram Auxiliary Building Chilled Water System.
Project stage: Other
ML11126A0832008-12-18018 December 2008
Drawing No. LR-M038C, Revision 2, Piping & Instrument Diagram Gaseous Radioactive Waste System. Job Code 12501
Project stage: Other
ML11126A0712009-04-0707 April 2009
Drawing No. LR-M034, Revision 1, Piping & Instrument Diagram Emerg. Core Cooling System Ctmt. Spray & Core Flooding Systems.
Project stage: Other
ML11126A0892009-04-0707 April 2009
Drawing No. LR-OS002, Revision 1, Operational Schematic Makeup and Purification System.
Project stage: Other
ML1024505652010-08-27027 August 2010
License Renewal Application and Ohio Coastal Management Program Consistency Certification
Project stage: Other
ML1104500462011-02-17017 February 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Fire Protection
Project stage: RAI
ML11126A0792011-02-25025 February 2011
Drawing No. LR-M900A, Revision 0, Instrument Air System Piping Schematic.
Project stage: Other
ML1104205972011-02-28028 February 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 2.4
Project stage: RAI
ML1106801722011-03-17017 March 2011
Request for Additional Information on the Reactor Vessel Surveillance Aging Management Program, Time-Limited Aging Analyses for Neutron Embrittlement of the Rv and Internals, and Other TLAAs for the Review of the Davis-Besse Nuclear Power S
Project stage: RAI
ML1107007322011-03-18018 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.2 & 2.3
Project stage: RAI
L-11-078, Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 12011-03-18018 March 2011
Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 1
Project stage: Response to RAI
ML11068A0002011-03-21021 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 4.7 (TAC Number ME4640)
Project stage: RAI
L-11-079, Reply to Request for Additional Information for the Review of the License Renewal Application2011-03-23023 March 2011
Reply to Request for Additional Information for the Review of the License Renewal Application
Project stage: Response to RAI
L-11-089, Reply to Request for Additional Information for the Review License Renewal Application2011-03-23023 March 2011
Reply to Request for Additional Information for the Review License Renewal Application
Project stage: Response to RAI
ML1108206242011-03-30030 March 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.1 (Tac No. ME4640)
Project stage: RAI
ML1109002952011-03-31031 March 2011
Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station
Project stage: Approval
ML1108204902011-04-0505 April 2011
Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Batch 1
Project stage: RAI
ML11110A0932011-04-15015 April 2011
Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System
Project stage: Other
ML11110A1072011-04-15015 April 2011
Drawing No. M-045, Rev. 56, Chemical Addition Systems
Project stage: Other
ML11110A1062011-04-15015 April 2011
Drawing No. M-042C, Rev. 33, Sampling System Sh. 3
Project stage: Other
ML11110A1052011-04-15015 April 2011
Drawing No. M-040A, Rev. 76, Reactor Coolant System Details
Project stage: Other
ML11110A0952011-04-15015 April 2011
Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste
Project stage: Other
ML11110A0942011-04-15015 April 2011
Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste
Project stage: Other
ML11110A0922011-04-15015 April 2011
Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System
Project stage: Other
L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples2011-04-15015 April 2011
Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples
Project stage: Other
L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...2011-04-15015 April 2011
Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application...
Project stage: Response to RAI
ML11110A0882011-04-15015 April 2011
Reply to Request for Additional Information for the Review of the License Renewal Application, Sections 2.2 & 2.3, License Renewal Application Amendment No. 3, and Revised License Renewal
Project stage: Response to RAI
ML11110A0912011-04-15015 April 2011
Drawing No. M-011, Rev. 61, Domestic Water System
Project stage: Other
ML11110A0892011-04-15015 April 2011
Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System
Project stage: Other
ML1110500912011-04-19019 April 2011
Scoping and Screening Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application
Project stage: Other
L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 42011-04-20020 April 2011
Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4
Project stage: Response to RAI
ML1109807182011-04-20020 April 2011
Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2
Project stage: RAI
ML11126A0362011-04-29029 April 2011
Drawing No. LR-M017D, Revision 1 Piping & Instrument Diagram, Steam Blackout Diesel Generator.
Project stage: Other
ML11126A0352011-04-29029 April 2011
Drawing No. LR-M017C, Revision 2, Piping & Instrument Diagram, Fuel Oil.
Project stage: Other
ML11126A0342011-04-29029 April 2011
Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start.
Project stage: Other
ML11126A0332011-04-29029 April 2011
Drawing No. LR-M016B, Revision 1, Piping & Instrument Diagram Station Fire Protection System
Project stage: Other
ML11126A0322011-04-29029 April 2011
Drawing No. LR-M016A, Revision 1, Piping & Instrument Diagram Station Fire Protection System
Project stage: Other
ML11126A0262011-04-29029 April 2011
Drawing No. LR-M010C, Revision 1, Piping & Instrument Diagram Make-up Water Treatment System
Project stage: Other
ML11126A0252011-04-29029 April 2011
Drawing No. LR-M010A, Revision 1, Piping & Instrument Diagram Make-Up Water Treatment System
Project stage: Other
ML11126A0242011-04-29029 April 2011
Drawing No. LR-M009B, Revision 1, Piping & Instrument Diagram Cooling Water System
Project stage: Other
ML11126A0192011-04-29029 April 2011
Drawing No. LR-M003A, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 1
Project stage: Other
ML11126A0452011-04-29029 April 2011
Drawing No. LR-M024H, Revision 1, Piping & Instrument Diagram, No. 2 Main and Auxiliary Turbine Driven Feed Pumps.
Project stage: Other
2011-02-25
[Table View] |
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Category:Letter
MONTHYEARIR 05000346/20243012024-02-0202 February 2024
NRC Initial License Examination Report 05000346/2024301
IR 05000346/20230042024-01-31031 January 2024
Integrated Inspection Report 05000346/2023004
ML23313A1352024-01-17017 January 2024
Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program
ML23353A1192023-12-19019 December 2023
Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024
L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023
Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station
L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023
Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23338A3172023-12-0606 December 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001
IR 05000346/20234032023-11-0202 November 2023
Security Baseline Inspection Report 05000346/2023403
ML23293A0612023-11-0101 November 2023
Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant
L-23-215, Changes to Emergency Plan2023-10-19019 October 2023
Changes to Emergency Plan
ML23237B4222023-09-28028 September 2023
Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments
ML23269A1242023-09-27027 September 2023
Request for Withholding Information from Public Disclosure
IR 05000346/20234012023-09-13013 September 2023
Security Baseline Inspection Report 05000346/2023401 (Public)
L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023
Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023
Quality Assurance Program Manual
IR 05000346/20230112023-08-30030 August 2023
Biennial Problem Identification and Resolution Inspection Report 05000346/2023011
ML23129A1722023-08-25025 August 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1
IR 05000346/20230052023-08-24024 August 2023
Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005)
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023
Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
IR 05000346/20230502023-08-0303 August 2023
Special Inspection Report 05000346/2023050
IR 05000346/20230902023-08-0101 August 2023
EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public)
ML23178A2742023-08-0101 August 2023
Letter to the Honorable Marcy Kaptur from Chair Hanson Responds to Letter Regarding the License Transfer Application for the Davis-Besse Nuclear Power Station
L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023
Submittal of Fifth Ten Year Inservice Testing Program
IR 05000346/20230022023-07-27027 July 2023
Integrated Inspection Report 05000346/2023002
ML23193A7842023-07-13013 July 2023
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000346/2023402
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
ML23160A2342023-06-13013 June 2023
Confirmation of Initial License Examination
L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023
2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
IR 05000346/20235012023-06-13013 June 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000346/2023501
L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023
Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
L-23-065, Annual Financial Report2023-05-22022 May 2023
Annual Financial Report
ML23124A1742023-05-17017 May 2023
Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1
ML23129A0112023-05-16016 May 2023
Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter)
ML23131A2732023-05-15015 May 2023
Notification of NRC Supplemental Inspection 95001 and Request for Information
L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023
Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022
L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023
Readiness for Resumption of NRC Supplemental Inspection
IR 05000346/20230102023-05-0909 May 2023
Commercial Grade Dedication Inspection Report 05000346/2023010
ML23123A1272023-05-0303 May 2023
Information Request to Support Upcoming Problem Identification and Resolution Inspection at Davis-Besse Nuclear Power Station
IR 05000346/20230012023-05-0101 May 2023
Integrated Inspection Report 05000346/2023001 and 07200014/2022001
L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023
Occupational Radiation Exposure Report for Year 2022
ML23111A1972023-04-26026 April 2023
Information Meeting with Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Plant Station
ML23114A1062023-04-25025 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023
ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments
ML23096A1382023-04-11011 April 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023
Submittal of the Decommissioning Funding Status Reports
L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023
and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments
L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023
Annual Notification of Property Insurance Coverage
ML23066A2892023-03-14014 March 2023
Request for Threshold Determination Under 10 CFR 50.80 and 10 CFR 72.50 for an Amendment to the Voting Agreement
ML23066A2592023-03-14014 March 2023
Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2, Davis Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit 1
2024-02-02
[Table view] |
Text
FENOC 0E-% 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Barry S. Allen 419-321-7676 Vice President
-Nuclear Fax. 419-321-7582 May 25, 2012 L-12-185 10 CFR 54 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 Supplemental Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 26 By letter dated August 27, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102450565), FirstEnergy Nuclear Operating Company (FENOC) submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS). By letter dated August 11, 2011 (ML1 1216A236), the Nuclear Regulatory Commission (NRC) issued request for additional information (RAI) 4.3.2.3.2-1
-(Supplement), to complete its review of the License Renewal Application (LRA). By letter dated October 7, 2011 (ML1 1285A064), FENOC responded to the RAI by providing a commitment to perform a fatigue evaluation of selected Class 1 valves and submit an amendment to the LRA.The actions described in the commitment have been completed.
The Attachment provides a supplemental response to NRC RAI 4.3.2.3.2-1
-(Supplement), including a description of the Class 1 valve fatigue evaluations performed and results obtained.
The NRC request is shown in bold text followed by the FENOC response.The Enclosure provides Amendment No. 26 to the DBNPS LRA.
Davis-Besse Nuclear Power Station, Unit No. 1 L-1 2-185 Page 2 There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Clifford I. Custer, Fleet License Renewal Project Manager, at 724-682-7139.
I declare under penalty of perjury that the foregoing is true and correct. Executed on May_2, 2012.Sincerely, Barry S en
Attachment:
Supplemental Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License Renewal Application, Section 4.3.2
Enclosure:
Amendment No. 26 to the DBNPS License Renewal Application cc: NRC DLR Project Manager NRC Region III Administrator cc: w/o Attachment or Enclosure NRC DLR Director NRR DORL Project Manager NRC Resident Inspector Utility Radiological Safety Board Attachment L-12-185 Supplemental Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License Renewal Application, Section 4.3.2 Page 1 of 3 Section 4.3.2 Question RAI 4.3.2.3.2-1
-(Supplement)
Background:
By letter dated June 22, 2011, the applicant responded to RAI 4.1-1 regarding cumulative usage factor (CUF) or It fatigue analyses for Class 1 valves. In its response to RAI 4.1-1, Request 1, Part A, the applicant identified 12 large bore Class 1 valves (i.e., valves with nominal pipe sizes in excess of 4-inches) that should have received CUF or It fatigue analyses in accordance with the design codes (i.e., 1971 or more recent Editions of the ASME Code Section III, or the 1968 Edition of the Draft ASME Pump and Valve Code for Nuclear Power Plants).The applicant provided Commitment No. 46 to complete the following, prior to April 22, 2015: FENOC commits to perform a fatigue evaluation in accordance with the requirements of the ASME Code of record for the Davis-Besse Class 1 valves that are greater than 4 inches nominal pipe size. The applicable valve identification numbers are CF28, CF29, CF30, CF31, DH76, DH77, DH11, DH12, DHIA, DHIB, DH21, and DH23.LRA Section 4.3.2.3.2, as amended by letter dated June 22, 2011, states that the fatigue analyses for these 12 referenced large bore Class I valves are as TLAAs and are dispositioned in accordance with Title 10 of the Code of Federal Regulations 54.21(c)(1)(iii), that the effects of fatigue on Class 1 valves greater than 4 inches diameter nominal pipe size will be managed for the period of extended operation by the Fatigue Monitoring Program. LRA Section 4.3.2.3.2 also states that the issue with the missing CUF or It calculations for the 12 referenced large bore Class 1 valves has been entered into the applicant's Corrective Actions Program.Issue: The information provided by the applicant in letter of June 22, 2011, did not provide information regarding whether the applicant had any ASME Code,Section III NB-3222.4(d) fatigue waiver assessments (or equivalent waiver assessments permitted by the 1968 Draft ASME Pump and Valve Code) for the 12 large bore Class 1 valves referenced in Commitment No. 46. Therefore, the Attachment L-12-185 Page 2 of 3 staff requests additional information regarding whether fatigue calculations are required for these valves.The staff is concerned that without the CUF or It analyses or an appropriate fatigue waiver or exemption for these 12 large bore Class 1 valves, the staff would not be able to evaluate whether the aging effects will be appropriately managed by the commitment.
Request: Provide justification for not having the analyses for staff review as part of the LRA, or provide your appropriate fatigue waiver or fatigue exemption bases for not having such analyses.RESPONSE RAI 4.3.2.3.2-1
-(Supplement)
In response to RAI 4.3.2.3.2-1
-(Supplement) submitted by letter dated October 7, 2011 (ML1 1285A064), FENOC provided the following commitment:
FENOC will perform a fatigue evaluation in accordance with the requirements of the ASME Code of record for the Davis-Besse Class 1 valves that are greater than 4 inches diameter nominal pipe size. The applicable valve identification numbers are CF28, CF29, CF30, CF31, DH76, DH77, DH11, DH12, DH1A, DH1B, DH21 and DH23. LRA Sections 4.3.2.3.2 and A.2.3.2.13, both titled "Class 1 Valves Fatigue," will be revised to include the results of the fatigue evaluations, and these changes will be submitted as an amendment to the Davis Besse LRA no later than May 31, 2012.The actions described in the commitment have been completed.
This supplemental response to RAI 4.3.2.3.2-1
-(Supplement) addresses the fatigue evaluation results of the Davis-Besse Class 1 valves that are greater than 4 inches diameter nominal pipe size (valve identification numbers CF28, CF29, CF30, CF31, DH76, DH77, DH1 1, DH12, DHIA, DH1B, DH21 and DH23) and the associated changes to License Renewal Application (LRA) Sections 4.3.2.3.2 and A.2.3.2.13.
Fatigue analyses were prepared for the subject Class 1 valves in accordance with paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addenda through the Summer of 1976, and were reconciled to the valve construction code year. The cumulative usage factors (CUFs) calculated for the subject Class 1 valves are based on nuclear steam supply system design transients and, as shown in the table below, are less than 1.0. The number of occurrences of design transients is tracked by the Fatigue Monitoring Program to ensure that action is taken before the design cycles are reached.Therefore, the effects of fatigue on Class 1 valves greater than 4 inches diameter Attachment L-12-185 Page 3 of 3 nominal pipe size (NPS) will be managed for the period of extended operation by the Fatigue Monitoring Program in accordance with 10 CFR 54.21(c)(1)(iii).
Size Construction Maximum Valve ID (dia. NPS) Code Year CUF& Type CF28 CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839 CF30 Winter 1972 stop check isolation valve CF31 DHI 1 12 inch 1968 Reactor Coolant System to Decay Heat- 0.14594 gate Draft Pump & containment isolation valve DH12 gValve DH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732 DH23 gate Winter 1972 isolation valve DH76 10 inch 1971 Low Pressure Injection to w/Addenda thru Reactor Coolant System -0.14099 DH77 Winter 1972 stop check isolation valve DH1A 10 inch 1968 Low Pressure Injection
-gate Draft Pump & outside containment isolation valve 0.18261 DH1Bgt Valve LRA Sections 4.3.2.3.2 and A.2.3.2.13 are revised to include the results of the fatigue evaluations.
See the Enclosure to this letter for the revision to the DBNPS LRA.
Enclosure Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS)Letter L-12-185 Amendment No. 26 to the DBNPS License Renewal Application Page 1 of 5 License Renewal Application Sections Affected Section 4.3.2.3.2 Section A.2.3.2.13 The Enclosure identifies the change to the License Renewal Application (LRA) by Affected LRA Section, LRA Page No., and Affected Paragraph and Sentence.
The count for the affected paragraph, sentence, bullet, etc. starts at the beginning of the affected Section or at the top of the affected page, as appropriate.
Below each section the reason for the change is identified, and the sentence affected is printed in italics with deleted text hined-ou and added text underlined.
Enclosure L-12-185 Page 2 of 5 Affected LRA Section LRA Page No. Affected Paragraph and Sentence 4.3.2.3.2 Pages 4.3-16 Entire Section and 4.3-17 In response to RAI 4.3.2.3.2-1
-(Supplement), LRA Section 4.3.2.3.2, "Class 1 Valves Fatigue," previously revised by FENOC letter dated October 7, 2011 (ML1I1285A064), is replaced in its entirety, to read as follows: 4.3.2.3.2 Class 1 Valves Fatigue The ASME Code requires a fatigue evaluation for Class 1 valves greater than 4 inches diameter nominal pipe size or for valves less than or equal to 4 inches in nominal pipe size if specified by the owner's design specification.
The Davis-Besse purchasing specifications did not require a fatigue analysis for Class 1 valves less than or equal to 4 inches in nominal pipe size. Therefore, only valves greater than 4 inches diameter nominal pipe size require a fatigue analysis.
Piping and instrumentation diagrams (P&IDs) were reviewed to identify Class 1 valves of greater than 4 inches diameter nominal pipe size. There were 12 valves of greater than 4 inches diameter nominal pipe size that were identified as a result of this effort.Fatigue analyses were prepared for the subject Class 1 valves in accordance with paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addenda through the Summer of 1976 and were reconciled to the valve construction code year.Since ASME Code fatigue analyses evaluate an explicit number and type of thermal and pressure transients that are postulated to envelope the number of occurrences possible during the design life of the plant, these fatigue analyses are time-limited aging analyses (TLAAs) and therefore, are required to be evaluated in accordance with 10 CFR 54.21(c)(1).
The cumulative usage factors calculated for the subject Class 1 valves are based on nuclear steam supply system design transients and, as shown in the table below, are less than 1.0. The number of occurrences of design transients is tracked by the Fatigue Monitoring Program to ensure that action is taken before the design cycles are reached. Therefore, the effects of fatigue on Class 1 valves greater than 4 inches diameter nominal pipe size (NPS) will be managed for the period of extended operation by the Fatigue Monitoring Program.
Enclosure L-12-185 Page 3 of 5 Size Construction Maximum Valve ID (dia. NPS) Code Year Description CUF& Type CF28 CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839 CF30 Winter 1972 stop check isolation valve CF31 Draft1968 Reactor Coolant System to Decay Heat -DH12 gate Valv containment isolation valve 0.14594 DH12 Valve DH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732 DH23 gate Winter 1972 isolation valve DH76 10 inch 1971 Low Pressure Injection to w/Addenda thru Reactor Coolant System -0.14099 DH77 Winter 1972 stop check isolation valve DDrf1A 10 inch 1968 Low Pressure Injection
-gae Draft Pump & outside containment isolation valve 0.18261 DH-11B at Valve Disposition:
10 CFR 54.21(c)(1)(iii)
The effects of fatigue on Class I valves greater than 4 inches diameter nominal pipe size will be managed for the period of extended operation by the Fatigue Monitoring Program.
Enclosure L-1 2-185 Page 4 of 5 Affected LRA Section LRA Paqe No. Affected Paragraph and Sentence A.2.3.2.13 Page A-41 Entire Section In response to RAI 4.3.2.3.2-1
-(Supplement), LRA Section A.2.3.2.13, "Class 1 Valves Fatigue," previously revised by FENOC letter dated October 7, 2011 (ML1I1285A064), is replaced in its entirety, to read as follows: A.2.3.2.13 Class 1 Valves Fatigue The ASME Code requires a fatigue evaluation for Class 1 valves greater than 4 inches diameter nominal pipe size or for valves less than or equal to 4 inches in nominal pipe size if specified by the owner's design specification.
The Davis-Besse purchasing specifications did not require a fatigue analysis for Class 1 valves less than or equal to 4 inches in nominal pipe size. Therefore, only valves greater than 4 inches diameter nominal pipe size require a fatigue analysis.
Piping and instrumentation diagrams (P&IDs) were reviewed to identify Class 1 valves of greater than 4 inches diameter nominal pipe size. There were 12 valves of greater than 4 inches diameter nominal pipe size that were identified as a result of this effort.Fatigue analyses were prepared for the subject Class 1 valves in accordance with paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addenda through the Summer of 1976 and were reconciled to the valve construction code year.Since ASME Code fatigue analyses evaluate an explicit number and type of thermal and pressure transients that are postulated to envelope the number of occurrences possible during the design life of the plant, these fatigue analyses are time-limited aging analyses (TLAAs) and therefore, are required to be evaluated in accordance with 10 CFR 54.21(c)(1).
The cumulative usage factors calculated for the subject Class 1 valves are based on nuclear steam supply system design transients and, as shown in the table below, are less than 1.0. The number of occurrences of design transients is tracked by the Fatigue Monitoring Program to ensure that action is taken before the design cycles are reached. Therefore, the effects of fatigue on Class 1 valves greater than 4 inches diameter nominal pipe size (NPS) will be managed for the period of extended operation by the Fatigue Monitoring Program in accordance with 10 CFR 54.21 (c)(1)(iii).
Enclosure L-12-185 Page 5 of 5 size Construction Maximum Valve ID (dia. NPS) Code Year Description CUF& Type CF28 CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839 CF30 Winter 1972 stop check isolation valve CF31 Draft1968 Reactor Coolant System to Decay Heat -DH1g Draft Pump & containment isolation valve 0.14594 DH12 gaeValve DH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732 DH23 gate Winter 1972 isolation valve DH76 10 inch 1971 Low Pressure Injection to w/Addenda thru Reactor Coolant System -0.14099 DH77 Winter 1972 stop check isolation valve DH1A 10 inch 1968 Low Pressure Injection
-Dae Draft Pump & outside containment isolation valve 0.18261 DH-11B at Valve III
