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| | number = ML060270303 | | | number = ML060270303 |
| | issue date = 02/03/2006 | | | issue date = 02/03/2006 |
| | title = Watts Bar, Unit 1 - Request for Additional Information Relief Request No. ISPT-09 for the First 10 Year Inservice Inspection Interval | | | title = Request for Additional Information Relief Request No. ISPT-09 for the First 10 Year Inservice Inspection Interval |
| | author name = Pickett D V | | | author name = Pickett D |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 |
| | addressee name = Singer K W | | | addressee name = Singer K |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000390 | | | docket = 05000390 |
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| =Text= | | =Text= |
| {{#Wiki_filter:February 3, 2006 | | {{#Wiki_filter:February 3, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 |
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| Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| WATTS BAR NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONALINFORMATION REGARDING RELIEF REQUEST NO. ISPT-09 FOR THE FIRST TEN-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MC8305) | | WATTS BAR NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NO. ISPT-09 FOR THE FIRST TEN-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MC8305) |
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| ==Dear Mr. Singer:== | | ==Dear Mr. Singer:== |
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| By letter dated September 8, 2005 (ADAMS Accession Number: ML052560093), TennesseeValley Authority (TVA), the licensee for the Watts Bar Nuclear Plant, Unit 1 (WBNP-1), | | By letter dated September 8, 2005 (ADAMS Accession Number: ML052560093), Tennessee Valley Authority (TVA), the licensee for the Watts Bar Nuclear Plant, Unit 1 (WBNP-1), |
| submitted Relief Request (RR) No. ISPT-09. In this request, TVA requested relief from the requirements of Paragraph (g)(4) to Section 50.55a of Title 10 of the Code of FederalRegulations and the system leak test requirements that are specified in Table IWB-2500-1,Examination Category B-P and Paragraph IWA-5222(a) of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1. RR No. ISPT-09 is applicable to the First Ten-Year Inservice Inspection Interval for WBNP-1 and pertains to the system leak test requirements for ASME Code Class 1 portions of the safety injection and residual heat removal systems. In order for the staff of the Nuclear Regulatory Commission to complete its review of the subjectrelief request, we request that the licensee respond to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter.Sincerely, | | submitted Relief Request (RR) No. ISPT-09. In this request, TVA requested relief from the requirements of Paragraph (g)(4) to Section 50.55a of Title 10 of the Code of Federal Regulations and the system leak test requirements that are specified in Table IWB-2500-1, Examination Category B-P and Paragraph IWA-5222(a) of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1. RR No. ISPT-09 is applicable to the First Ten-Year Inservice Inspection Interval for WBNP-1 and pertains to the system leak test requirements for ASME Code Class 1 portions of the safety injection and residual heat removal systems. |
| /RA/ Douglas V. Pickett, Senior Project ManagerPlant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-390
| | In order for the staff of the Nuclear Regulatory Commission to complete its review of the subject relief request, we request that the licensee respond to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter. |
| | Sincerely, |
| | /RA/ |
| | Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Information cc w/enclosure: See next page | | Request for Additional Information cc w/enclosure: See next page |
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| ML060270303 NRR-088OFFICELPL2-2/LALPL2-2/PMDCI/CFEBLPL2-2/BCNAMERSolaDPickettJTsao (A)MMarshallDATE02/03/ 0602/03/ 06by memo dated12 / 12 / 05 2 / 03 / 06 Mr. Karl W. Singer Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice PresidentNuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Robert J. Beecken, Vice PresidentNuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. SkaggsSite Vice President Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381General CounselTennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902Mr. John C. Fornicola, ManagerNuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Mr. Paul L. Pace, ManagerLicensing and Industry Affairs Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381Mr. Jay Laughlin, Plant ManagerWatts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381Senior Resident InspectorWatts Bar Nuclear Plant U.S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381County Executive 375 Church Street Suite 215 Dayton, TN 37321County Mayor P. O. Box 156 Decatur, TN 37322Mr. Lawrence E. Nanney, DirectorDivision of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532Ms. Ann P. Harris341 Swing Loop Road Rockwood, Tennessee 37854 ENCLOSUREREQUEST FOR ADDITIONAL INFORAMTION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONFIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAMTENNESSEE VALLEY AUTHORITYREQUEST FOR RELIEF NO. ISPT-09WATTS BAR NUCLEAR PLANT, UNIT 1FACILITY OPERATING LICENSE NO. NPF-90DOCKET NO: 50-3901.Relief Request (RR) No. ISPT-09 requests relief from the requirements of the AmericanSociety of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1 (henceforth Section XI), Table IWB-2500-1, Examination Category B-P, based on the hardship provisions that are specified in Paragraph (a)(3)(ii) of Title 10 of the Code ofFederal Regulations. Specify which Edition of Section XI is the Code of record forWatts Bar Nuclear Plant, Unit 1 (WBN-1). In addition, specify which Inspection Items in Section XI Table IWB-2500-1, Examination Category B-P are applicable to the piping segments that are within the scope of the relief request, as identified in Table 1, "Piping Segment Descriptions," of the Enclosure to the relief request.2.Reference the basis (e.g., Academic Textbook, ASME Section XI paragraph, NUREGReport, etc.) for the following equation that is specified on Page E-4 of the RR No. | | ML060270303 NRR-088 OFFICE LPL2-2/LA LPL2-2/PM DCI/CFEB LPL2-2/BC NAME RSola DPickett JTsao (A) MMarshall by memo dated DATE 02/03/ 06 02/03/ 06 12 / 12 / 05 2 / 03 / 06 Mr. Karl W. Singer Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc: |
| | Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Glenn W. Morris, Manager Nuclear Operations Corporate Nuclear Licensing Tennessee Valley Authority and Industry Affairs 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Mr. Paul L. Pace, Manager Tennessee Valley Authority Licensing and Industry Affairs 6A Lookout Place Watts Bar Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Spring City, TN 37381 Mr. Robert J. Beecken, Vice President Nuclear Support Mr. Jay Laughlin, Plant Manager Tennessee Valley Authority Watts Bar Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Spring City, TN 37381 Mr. Michael D. Skaggs Senior Resident Inspector Site Vice President Watts Bar Nuclear Plant Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 1260 Nuclear Plant Road P.O. Box 2000 Spring City, TN 37381 Spring City, TN 37381 County Executive General Counsel 375 Church Street Tennessee Valley Authority Suite 215 ET 11A Dayton, TN 37321 400 West Summit Hill Drive Knoxville, TN 37902 County Mayor P. O. Box 156 Mr. John C. Fornicola, Manager Decatur, TN 37322 Nuclear Assurance and Licensing Tennessee Valley Authority Mr. Lawrence E. Nanney, Director 6A Lookout Place Division of Radiological Health 1101 Market Street Dept. of Environment & Conservation Chattanooga, TN 37402-2801 Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854 |
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| | REQUEST FOR ADDITIONAL INFORAMTION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM TENNESSEE VALLEY AUTHORITY REQUEST FOR RELIEF NO. ISPT-09 WATTS BAR NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO: 50-390 |
| | : 1. Relief Request (RR) No. ISPT-09 requests relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1 (henceforth Section XI), Table IWB-2500-1, Examination Category B-P, based on the hardship provisions that are specified in Paragraph (a)(3)(ii) of Title 10 of the Code of Federal Regulations. Specify which Edition of Section XI is the Code of record for Watts Bar Nuclear Plant, Unit 1 (WBN-1). In addition, specify which Inspection Items in Section XI Table IWB-2500-1, Examination Category B-P are applicable to the piping segments that are within the scope of the relief request, as identified in Table 1, Piping Segment Descriptions, of the Enclosure to the relief request. |
| | : 2. Reference the basis (e.g., Academic Textbook, ASME Section XI paragraph, NUREG Report, etc.) for the following equation that is specified on Page E-4 of the RR No. |
| ISPT-09 submittal: | | ISPT-09 submittal: |
| L p = L XI x ( P p / P XI )1/23.The relief request proposes to perform the required hydrostatic pressure tests of theASME Code Class 1 piping segments at test pressures lower than those that are required in Section XI Table IWB-5220-1, which is called out by reference in Section XI Paragraph IWB-5222(a). Confirm that the alternative pressure tests proposed in RR No. ISPT-09 will be subject to the minimum hold times that are required by Section XI Paragraph IWA-5213 for hydrostatic pressure tests and the minimum test temperatures that are required by Section XI Article 5000 (e.g., the minimum temperature requirements in Paragraph IWB-5230 in Editions through the 1992 Edition or in Paragraph IWB-5240 in the 1995 Edition and more recent Editions). 4.Table 1, "Piping Segment Descriptions," of the Enclosure to RR No. ISPT-09 (i.e., theenclosure to the Tennessee Valley Authority letter of September 8, 2005) provides the descriptions of the piping segments that are within the scope of the relief request. The staff seeks the following clarifications for the piping segments descriptions that are provided in Table 1:a.Reactor Coolant Loop 1 on Page E-7: "Low pressure safety injection from RHRsystem CKV-63-633 to the 10-inch Loop 1 cold leg injection line." Clarify which component in the 10-inch Loop 1 cold leg injection line bounds the end of the piping segment that requires pressure testing.b.Reactor Coolant Loop 1 on Page E-7: "High pressure safety injection pipingfrom the 3-inch common header from CKV-63-581 to Loop 1 cold leg piping to CKV-63-586." Confirm that the component description should be "High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-586 in the Loop 1 cold leg piping."c.Reactor Coolant Loop 1 on Page E-7: "Safety injection pump piping from CKV-63-543 to the 8-inch Loop 1 hot leg injection line." Clarify which component in the 8-inch Loop 1 hot leg injection line bounds the end of the piping segment.d.Reactor Coolant Loop 1 on Page E-7: "Safety injection pump piping from CKV-63-551 to the 6-inch Loop 1 cold leg injection line." Clarify which component in the 6-inch Loop 1 cold leg injection line bounds the end of the piping segment.e.Reactor Coolant Loop 2 on Page E-8: "Low pressure safety injection from RHRsystem CKV-63-632 to the 10-inch Loop 2 cold leg injection line." Clarify which component in the 10-inch Loop 2 cold leg injection line bounds the end of the piping segment.f.Reactor Coolant Loop 2 on Page E-8: "High pressure safety injection pipingfrom the 3-inch common header from CKV-63-581 to Loop 2 cold leg piping to CKV-63-587." Confirm that the component description should be "High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-587 in the Loop 2 cold leg piping."g.Confirm that the Loop 2 piping segment descriptions on page E-8 should notinclude an entry from a check valve in the Safety Injection pump piping to a valve in an 8-inch or 6-inch Loop 2 hot leg injection line in the manner they have been included for Reactor Coolant System Loops 1, 3, and 4. If the Loop 2 entries should include such a piping segment description and the entry has not been included in Table 1, please amend Table 1 to add it. If the Loop 2 entries in Table 1 do include such a piping segment entry, please identify which entry contains the applicable component description.h.Reactor Coolant Loop 2 on Page E-8: "Safety Injection pump piping from CKV-63-553 to the 6-inch Loop 2 cold leg injection line." Clarify whichcomponent in the 6-inch Loop 2 cold leg injection line bounds the end of the piping segment.I.Reactor Coolant Loop 3 on Page E-9: "Low pressure safety injection from RHRsystem CKV-63-634 to the 10-inch Loop 3 cold leg injection line." Clarify which component in the 10-inch Loop 3 cold leg injection line bounds the end of the piping segment.j.Reactor Coolant Loop 3 on Page E-9: "High pressure safety injection pipingfrom CKV-63-581 to Loop 3 cold leg piping to CKV-63-588." Confirm that the component description should be "High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-588 in the Loop 3 cold leg piping."k.Reactor Coolant Loop 3 on Page E-9: "Safety injection pump piping from CKV-63-545 to the 8-inch Loop 3 hot leg injection line." Clarify which component in the 8-inch Loop 3 hot leg injection line bounds the end of the piping segment.l. Reactor Coolant Loop 3 on Page E-9: "Safety injection pump piping from CKV-63-555 to the 6-inch Loop 3 cold leg injection line." Clarify which component in the 6-inch Loop 3 cold leg injection line bounds the end of the piping segment.m.Reactor Coolant Loop 4 on Page E-10: "Low pressure safety injection from RHRsystem CKV-63-635 to the 10-inch Loop 4 cold leg injection line." Clarify which component in the 10-inch Loop 4 cold leg injection line bounds the end of the piping segment.n.Reactor Coolant Loop 4 on Page E-10: "High pressure safety injection pipingfrom the 3-inch common header from CKV-63-581 to Loop 4 cold leg piping to CKV-63-589." Confirm that the component description should be "High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-589 in the Loop 4 cold leg piping."o.Reactor Coolant Loop 4 on Page E-10: "Safety injection pump piping from CKV-63-557 to the 6-inch Loop 4 cold leg injection line." Clarify which component in the 6-inch Loop 4 cold leg injection line bounds the end of the piping segment.p.Reactor Coolant Loop 4 on Page E-10: "RHR piping between FCVs-74-1 and 8and FCVs-74-2 and 9." The staff recommends that the pipe segment description be broken into two separate entries because it is confusing exactly which flow control valves are the valves that bound the length of the piping segments.}}
| | Lp = LXI x ( Pp / PXI )1/2 |
| | : 3. The relief request proposes to perform the required hydrostatic pressure tests of the ASME Code Class 1 piping segments at test pressures lower than those that are required in Section XI Table IWB-5220-1, which is called out by reference in Section XI Paragraph IWB-5222(a). Confirm that the alternative pressure tests proposed in RR No. ISPT-09 will be subject to the minimum hold times that are required by Section XI Paragraph IWA-5213 for hydrostatic pressure tests and the minimum test temperatures that are required by Section XI Article 5000 (e.g., the minimum temperature requirements in Paragraph IWB-5230 in Editions through the 1992 Edition or in Paragraph IWB-5240 in the 1995 Edition and more recent Editions). |
| | ENCLOSURE |
| | : 4. Table 1, Piping Segment Descriptions, of the Enclosure to RR No. ISPT-09 (i.e., the enclosure to the Tennessee Valley Authority letter of September 8, 2005) provides the descriptions of the piping segments that are within the scope of the relief request. The staff seeks the following clarifications for the piping segments descriptions that are provided in Table 1: |
| | : a. Reactor Coolant Loop 1 on Page E-7: Low pressure safety injection from RHR system CKV-63-633 to the 10-inch Loop 1 cold leg injection line. Clarify which component in the 10-inch Loop 1 cold leg injection line bounds the end of the piping segment that requires pressure testing. |
| | : b. Reactor Coolant Loop 1 on Page E-7: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 1 cold leg piping to CKV-63-586. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-586 in the Loop 1 cold leg piping. |
| | : c. Reactor Coolant Loop 1 on Page E-7: Safety injection pump piping from CKV-63-543 to the 8-inch Loop 1 hot leg injection line. Clarify which component in the 8-inch Loop 1 hot leg injection line bounds the end of the piping segment. |
| | : d. Reactor Coolant Loop 1 on Page E-7: Safety injection pump piping from CKV-63-551 to the 6-inch Loop 1 cold leg injection line. Clarify which component in the 6-inch Loop 1 cold leg injection line bounds the end of the piping segment. |
| | : e. Reactor Coolant Loop 2 on Page E-8: Low pressure safety injection from RHR system CKV-63-632 to the 10-inch Loop 2 cold leg injection line. Clarify which component in the 10-inch Loop 2 cold leg injection line bounds the end of the piping segment. |
| | : f. Reactor Coolant Loop 2 on Page E-8: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 2 cold leg piping to CKV-63-587. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-587 in the Loop 2 cold leg piping. |
| | : g. Confirm that the Loop 2 piping segment descriptions on page E-8 should not include an entry from a check valve in the Safety Injection pump piping to a valve in an 8-inch or 6-inch Loop 2 hot leg injection line in the manner they have been included for Reactor Coolant System Loops 1, 3, and 4. If the Loop 2 entries should include such a piping segment description and the entry has not been included in Table 1, please amend Table 1 to add it. If the Loop 2 entries in Table 1 do include such a piping segment entry, please identify which entry contains the applicable component description. |
| | : h. Reactor Coolant Loop 2 on Page E-8: Safety Injection pump piping from |
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| | CKV-63-553 to the 6-inch Loop 2 cold leg injection line. Clarify which component in the 6-inch Loop 2 cold leg injection line bounds the end of the piping segment. |
| | I. Reactor Coolant Loop 3 on Page E-9: Low pressure safety injection from RHR system CKV-63-634 to the 10-inch Loop 3 cold leg injection line. Clarify which component in the 10-inch Loop 3 cold leg injection line bounds the end of the piping segment. |
| | : j. Reactor Coolant Loop 3 on Page E-9: High pressure safety injection piping from CKV-63-581 to Loop 3 cold leg piping to CKV-63-588. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-588 in the Loop 3 cold leg piping. |
| | : k. Reactor Coolant Loop 3 on Page E-9: Safety injection pump piping from CKV-63-545 to the 8-inch Loop 3 hot leg injection line. Clarify which component in the 8-inch Loop 3 hot leg injection line bounds the end of the piping segment. |
| | : l. Reactor Coolant Loop 3 on Page E-9: Safety injection pump piping from CKV-63-555 to the 6-inch Loop 3 cold leg injection line. Clarify which component in the 6-inch Loop 3 cold leg injection line bounds the end of the piping segment. |
| | : m. Reactor Coolant Loop 4 on Page E-10: Low pressure safety injection from RHR system CKV-63-635 to the 10-inch Loop 4 cold leg injection line. Clarify which component in the 10-inch Loop 4 cold leg injection line bounds the end of the piping segment. |
| | : n. Reactor Coolant Loop 4 on Page E-10: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 4 cold leg piping to CKV-63-589. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-589 in the Loop 4 cold leg piping. |
| | : o. Reactor Coolant Loop 4 on Page E-10: Safety injection pump piping from CKV-63-557 to the 6-inch Loop 4 cold leg injection line. Clarify which component in the 6-inch Loop 4 cold leg injection line bounds the end of the piping segment. |
| | : p. Reactor Coolant Loop 4 on Page E-10: RHR piping between FCVs-74-1 and 8 and FCVs-74-2 and 9. The staff recommends that the pipe segment description be broken into two separate entries because it is confusing exactly which flow control valves are the valves that bound the length of the piping segments.}} |
Letter Sequence RAI |
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MONTHYEARML0525600932005-09-0808 September 2005
American Society of Mechanical Engineers (ASME) Section XI Inservice Pressure Testing Program Request for Relief ISPT-09
Project stage: Request
ML0602703032006-02-0303 February 2006
Request for Additional Information Relief Request No. ISPT-09 for the First 10 Year Inservice Inspection Interval
Project stage: RAI
ML0609502532006-03-31031 March 2006
American Society of Mechanical Engineers (ASME) Section XI Inservice Pressure Testing Program Request for Relief ISPT-09
Project stage: Request
ML0617303862006-07-11011 July 2006
Relief, Relief Request No. ISPT-09 for the First Ten-Year Inservice Inspection Interval
Project stage: Other
2006-02-03
[Table View] |
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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024
Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI)
CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
IR 05000390/20243012024-10-17017 October 2024
Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301
ML24282B0412024-10-15015 October 2024
Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2
ML24260A1682024-10-0404 October 2024
Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5
ML24261C0062024-10-0404 October 2024
Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96
ML24284A1072024-09-26026 September 2024
Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2
CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024
Decommitment of Flood Mode Mitigation Improvement Systems
CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024
Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description
ML24262A0602024-09-23023 September 2024
Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan
CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024
Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024
Automatic Reactor Trip Due to Main Generator Protection Relay Actuation
IR 05000390/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005
ML24218A1442024-08-27027 August 2024
Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate
IR 05000390/20244022024-08-20020 August 2024
– Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public
CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024
Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),
ML24219A0262024-08-12012 August 2024
Request for Withholding Information from Public Disclosure
IR 05000390/20240022024-08-0707 August 2024
Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev
ML24204A2652024-07-25025 July 2024
Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate
ML24199A0012024-07-22022 July 2024
Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2)
ML24170A8002024-07-15015 July 2024
Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts
ML24172A1342024-07-15015 July 2024
Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter
IR 05000390/20244402024-07-12012 July 2024
95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter
05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024
Inoperability of Both Trains of Unit 2 Low Head Safety Injection
ML24131A0012024-07-0202 July 2024
Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2
CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024
Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024
License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS
ML24089A1152024-06-21021 June 2024
Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2)
ML24141A0482024-05-17017 May 2024
EN 56958_1 Ametek Solidstate Controls, Inc
ML24100A7642024-05-16016 May 2024
Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062)
IR 05000390/20240012024-05-14014 May 2024
Integrated Inspection Report 05000390/2024001 and 05000391/2024001
CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024
Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO
IR 05000391/20240072024-04-30030 April 2024
Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007
ML24120A1182024-04-29029 April 2024
– Notification of NRC Supplemental Inspection (95001) and Request for Information
CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42
ML24087A1912024-04-18018 April 2024
Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024
Hydrologic Engineering Center River Analysis System Project Milestone Status Update
CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024
License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)
CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML24072A0052024-04-15015 April 2024
Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report
CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024
Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)
IR 05000390/20244012024-04-0202 April 2024
– Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public)
CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024
Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements
CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024
Guarantee of Payment of Deferred Premiums - 2023 Annual Report
05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024
Automatic Reactor Trip Due to Main Generator Protection Relay Actuation
CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024
Annual Insurance Status Report
CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024
Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule
ML24081A0262024-03-21021 March 2024
Emergency Plan Implementing Procedure Revisions
ML24079A0312024-03-19019 March 2024
Wb 2024-301, Corporate Notification Letter (210-day Ltr)
2024-09-05
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24309A0552024-11-0101 November 2024
NRR E-mail Capture - Request for Additional Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 Re TS Table 3.3.2-1, Function 5
ML24304A3752024-10-29029 October 2024
NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) to Revise Watts Bar Updated Final Safety Analysis Report (UFSAR) for Hydrologic Analysis
ML24260A0322024-09-10010 September 2024
NRR E-mail Capture - Request for Additional Information Regarding the Watts Bar Unit 2 Steam Generator Tube Inspection Report for U2R5
ML24155A1372024-05-29029 May 2024
Email from K. Green to S. Hughes Request for Additional Information Related to License Amendment Request to Revise Residual Heat Removal Flow Rate
ML24120A1182024-04-29029 April 2024
– Notification of NRC Supplemental Inspection (95001) and Request for Information
ML24116A2012024-04-17017 April 2024
Nrctva ISFSI CBS (RFI)
ML24045A0312024-02-14014 February 2024
NRR E-mail Capture - Request for Additional Information Related to the Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule
ML23166A1142023-06-15015 June 2023
Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03
ML23067A2372023-03-0808 March 2023
WB_2023-02_RP_inspection_doc_request
ML23030A3512023-01-25025 January 2023
Notification of Watts Bar Nuclear Plant - Design Bases Assurance Inspection (Programs) and Initial Information Request
ML22343A0692022-12-0808 December 2022
NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103)
ML22227A0272022-08-11011 August 2022
NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2
ML22144A1002022-05-12012 May 2022
NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans
ML22115A1402022-04-25025 April 2022
NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017)
ML22083A2372022-03-24024 March 2022
NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8
ML22056A3802022-02-25025 February 2022
Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02
ML21267A1392021-09-23023 September 2021
Document Request for Upcoming RP Inspection at Watts Bar
ML21221A2602021-08-0909 August 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Watts Bar, Unit 1 Tech Specs Related to Continuous Opening of the Auxiliary Building Secondary Containment Enclosure Boundary
ML21102A1312021-04-19019 April 2021
Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1
ML21095A0422021-04-0202 April 2021
NRR E-mail Capture - Added Clarification to RAI 2 for Thot LAR
ML21095A0402021-04-0202 April 2021
NRR E-mail Capture - Request for Additional Information Re Generic Letter 95-05 90-Day Report and LAR to Adjust Growth Rate for Thot (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21091A0772021-04-0101 April 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program
ML21095A0412021-04-0101 April 2021
NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21095A0442021-04-0101 April 2021
NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21095A0462021-03-22022 March 2021
NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Generic Letter 95-05 90-Day Report for Watts Bar Unit 2
ML21039A6402021-02-0808 February 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 1 Technical Specifications Related to Steam Generator Tube Inspection Frequency
ML21012A2032021-01-11011 January 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar UFSAR to Use Alternate Probability of Detection
ML20350B5592020-12-15015 December 2020
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Adopt Traveler TSTF-490 Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
ML20338A3202020-12-0303 December 2020
Notification of an NRC Fire Protection Team Inspection (NRC Inspection Report 05000390/2021011 and 05000391/2021011) and Request for Information
ML20322A4412020-11-17017 November 2020
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement
ML20322A4392020-11-0505 November 2020
NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement
ML20308A3512020-11-0202 November 2020
Request for Additional Information on WBN Request for Exemption from 10 CFR Part 73, Appendix B, Section VI for the Conduct of an Annual Force-on-Force Exercise (EPID L-2020-LLE-0165 (COVID-19))
ML20253A1782020-09-0909 September 2020
Emergency Preparedness Program Inspection Request for Information
ML20266G4592020-08-14014 August 2020
Notification of Inspection and Request for Information
ML20196L8622020-07-14014 July 2020
NRR E-mail Capture - Watts Bar Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Implement the Full Spectrum LOCA Methodology
ML20086G4802020-03-26026 March 2020
NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) - Part 2
ML20085G3572020-03-25025 March 2020
NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000)
ML20084M1942020-03-24024 March 2020
NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000)
ML20083J3952020-03-12012 March 2020
NRR E-mail Capture - Draft Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000)
ML19340A6842019-12-0505 December 2019
NRR E-mail Capture - Request for Additional Information for WBN2 Request for One-Time Extension of Completion Time for TS 3.7.8 (L-2019-LLA-0020)
ML19218A0302019-08-0505 August 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2
ML19218A0282019-07-25025 July 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Draft Second-Round Request for Additional Information Related to Application to Revise Technical Specifications Regarding DC Electrical Systems, TSTF-500, Revision 2
ML19186A4352019-07-0505 July 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Correction to Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69
ML19169A3592019-06-18018 June 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Application to Adopt 10 CFR 50.69
ML19148A7912019-05-28028 May 2019
NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements
ML19106A0462019-04-15015 April 2019
NRR E-mail Capture - Watts BAR, Units 1 and 2 Request for Additional Informatin (RAI) Regarding Changes to Technical Specifications Sections 3.8.1, 3.8.7, 3.8.8, and 3.8.9
ML19071A3542019-03-0808 March 2019
NRR E-mail Capture - Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request to Adopt TSTF-425 to Relocate Specific Surveillance Frequency Requirements to Licensee-Controlled Program
ML18313A2202018-11-0707 November 2018
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
ML18282A6372018-10-0909 October 2018
NRR E-mail Capture - RAIs (Final) - LAR to Revise the Steam Generator Technical Specifications for Watts Bar Nuclear Plant, Unit 2
ML18270A2362018-09-26026 September 2018
NRR E-mail Capture - Watts Bar Units 1 and 2 RAIs - Modify TS 3.8.9 Completion Time for Inoperable 120V AC Vital Buses (L-2018-LLA-0050)
2024-09-10
[Table view] |
Text
February 3, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NO. ISPT-09 FOR THE FIRST TEN-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MC8305)
Dear Mr. Singer:
By letter dated September 8, 2005 (ADAMS Accession Number: ML052560093), Tennessee Valley Authority (TVA), the licensee for the Watts Bar Nuclear Plant, Unit 1 (WBNP-1),
submitted Relief Request (RR) No. ISPT-09. In this request, TVA requested relief from the requirements of Paragraph (g)(4) to Section 50.55a of Title 10 of the Code of Federal Regulations and the system leak test requirements that are specified in Table IWB-2500-1, Examination Category B-P and Paragraph IWA-5222(a) of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1. RR No. ISPT-09 is applicable to the First Ten-Year Inservice Inspection Interval for WBNP-1 and pertains to the system leak test requirements for ASME Code Class 1 portions of the safety injection and residual heat removal systems.
In order for the staff of the Nuclear Regulatory Commission to complete its review of the subject relief request, we request that the licensee respond to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
Request for Additional Information cc w/enclosure: See next page
ML060270303 NRR-088 OFFICE LPL2-2/LA LPL2-2/PM DCI/CFEB LPL2-2/BC NAME RSola DPickett JTsao (A) MMarshall by memo dated DATE 02/03/ 06 02/03/ 06 12 / 12 / 05 2 / 03 / 06 Mr. Karl W. Singer Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Glenn W. Morris, Manager Nuclear Operations Corporate Nuclear Licensing Tennessee Valley Authority and Industry Affairs 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Mr. Paul L. Pace, Manager Tennessee Valley Authority Licensing and Industry Affairs 6A Lookout Place Watts Bar Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Spring City, TN 37381 Mr. Robert J. Beecken, Vice President Nuclear Support Mr. Jay Laughlin, Plant Manager Tennessee Valley Authority Watts Bar Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Spring City, TN 37381 Mr. Michael D. Skaggs Senior Resident Inspector Site Vice President Watts Bar Nuclear Plant Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 1260 Nuclear Plant Road P.O. Box 2000 Spring City, TN 37381 Spring City, TN 37381 County Executive General Counsel 375 Church Street Tennessee Valley Authority Suite 215 ET 11A Dayton, TN 37321 400 West Summit Hill Drive Knoxville, TN 37902 County Mayor P. O. Box 156 Mr. John C. Fornicola, Manager Decatur, TN 37322 Nuclear Assurance and Licensing Tennessee Valley Authority Mr. Lawrence E. Nanney, Director 6A Lookout Place Division of Radiological Health 1101 Market Street Dept. of Environment & Conservation Chattanooga, TN 37402-2801 Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854
REQUEST FOR ADDITIONAL INFORAMTION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM TENNESSEE VALLEY AUTHORITY REQUEST FOR RELIEF NO. ISPT-09 WATTS BAR NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO: 50-390
- 1. Relief Request (RR) No. ISPT-09 requests relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1 (henceforth Section XI), Table IWB-2500-1, Examination Category B-P, based on the hardship provisions that are specified in Paragraph (a)(3)(ii) of Title 10 of the Code of Federal Regulations. Specify which Edition of Section XI is the Code of record for Watts Bar Nuclear Plant, Unit 1 (WBN-1). In addition, specify which Inspection Items in Section XI Table IWB-2500-1, Examination Category B-P are applicable to the piping segments that are within the scope of the relief request, as identified in Table 1, Piping Segment Descriptions, of the Enclosure to the relief request.
- 2. Reference the basis (e.g., Academic Textbook, ASME Section XI paragraph, NUREG Report, etc.) for the following equation that is specified on Page E-4 of the RR No.
ISPT-09 submittal:
Lp = LXI x ( Pp / PXI )1/2
- 3. The relief request proposes to perform the required hydrostatic pressure tests of the ASME Code Class 1 piping segments at test pressures lower than those that are required in Section XI Table IWB-5220-1, which is called out by reference in Section XI Paragraph IWB-5222(a). Confirm that the alternative pressure tests proposed in RR No. ISPT-09 will be subject to the minimum hold times that are required by Section XI Paragraph IWA-5213 for hydrostatic pressure tests and the minimum test temperatures that are required by Section XI Article 5000 (e.g., the minimum temperature requirements in Paragraph IWB-5230 in Editions through the 1992 Edition or in Paragraph IWB-5240 in the 1995 Edition and more recent Editions).
ENCLOSURE
- 4. Table 1, Piping Segment Descriptions, of the Enclosure to RR No. ISPT-09 (i.e., the enclosure to the Tennessee Valley Authority letter of September 8, 2005) provides the descriptions of the piping segments that are within the scope of the relief request. The staff seeks the following clarifications for the piping segments descriptions that are provided in Table 1:
- a. Reactor Coolant Loop 1 on Page E-7: Low pressure safety injection from RHR system CKV-63-633 to the 10-inch Loop 1 cold leg injection line. Clarify which component in the 10-inch Loop 1 cold leg injection line bounds the end of the piping segment that requires pressure testing.
- b. Reactor Coolant Loop 1 on Page E-7: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 1 cold leg piping to CKV-63-586. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-586 in the Loop 1 cold leg piping.
- c. Reactor Coolant Loop 1 on Page E-7: Safety injection pump piping from CKV-63-543 to the 8-inch Loop 1 hot leg injection line. Clarify which component in the 8-inch Loop 1 hot leg injection line bounds the end of the piping segment.
- d. Reactor Coolant Loop 1 on Page E-7: Safety injection pump piping from CKV-63-551 to the 6-inch Loop 1 cold leg injection line. Clarify which component in the 6-inch Loop 1 cold leg injection line bounds the end of the piping segment.
- e. Reactor Coolant Loop 2 on Page E-8: Low pressure safety injection from RHR system CKV-63-632 to the 10-inch Loop 2 cold leg injection line. Clarify which component in the 10-inch Loop 2 cold leg injection line bounds the end of the piping segment.
- f. Reactor Coolant Loop 2 on Page E-8: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 2 cold leg piping to CKV-63-587. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-587 in the Loop 2 cold leg piping.
- g. Confirm that the Loop 2 piping segment descriptions on page E-8 should not include an entry from a check valve in the Safety Injection pump piping to a valve in an 8-inch or 6-inch Loop 2 hot leg injection line in the manner they have been included for Reactor Coolant System Loops 1, 3, and 4. If the Loop 2 entries should include such a piping segment description and the entry has not been included in Table 1, please amend Table 1 to add it. If the Loop 2 entries in Table 1 do include such a piping segment entry, please identify which entry contains the applicable component description.
- h. Reactor Coolant Loop 2 on Page E-8: Safety Injection pump piping from
CKV-63-553 to the 6-inch Loop 2 cold leg injection line. Clarify which component in the 6-inch Loop 2 cold leg injection line bounds the end of the piping segment.
I. Reactor Coolant Loop 3 on Page E-9: Low pressure safety injection from RHR system CKV-63-634 to the 10-inch Loop 3 cold leg injection line. Clarify which component in the 10-inch Loop 3 cold leg injection line bounds the end of the piping segment.
- j. Reactor Coolant Loop 3 on Page E-9: High pressure safety injection piping from CKV-63-581 to Loop 3 cold leg piping to CKV-63-588. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-588 in the Loop 3 cold leg piping.
- k. Reactor Coolant Loop 3 on Page E-9: Safety injection pump piping from CKV-63-545 to the 8-inch Loop 3 hot leg injection line. Clarify which component in the 8-inch Loop 3 hot leg injection line bounds the end of the piping segment.
- l. Reactor Coolant Loop 3 on Page E-9: Safety injection pump piping from CKV-63-555 to the 6-inch Loop 3 cold leg injection line. Clarify which component in the 6-inch Loop 3 cold leg injection line bounds the end of the piping segment.
- m. Reactor Coolant Loop 4 on Page E-10: Low pressure safety injection from RHR system CKV-63-635 to the 10-inch Loop 4 cold leg injection line. Clarify which component in the 10-inch Loop 4 cold leg injection line bounds the end of the piping segment.
- n. Reactor Coolant Loop 4 on Page E-10: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 4 cold leg piping to CKV-63-589. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-589 in the Loop 4 cold leg piping.
- o. Reactor Coolant Loop 4 on Page E-10: Safety injection pump piping from CKV-63-557 to the 6-inch Loop 4 cold leg injection line. Clarify which component in the 6-inch Loop 4 cold leg injection line bounds the end of the piping segment.
- p. Reactor Coolant Loop 4 on Page E-10: RHR piping between FCVs-74-1 and 8 and FCVs-74-2 and 9. The staff recommends that the pipe segment description be broken into two separate entries because it is confusing exactly which flow control valves are the valves that bound the length of the piping segments.
