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Category:Letter type:CNL
MONTHYEARCNL-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 CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report 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 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 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-24-020, 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 CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-026, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-013, Cycle 22 Reload Analysis Report2024-03-14014 March 2024 Cycle 22 Reload Analysis Report CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-105, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 222022-11-0808 November 2022 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 22 CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) 2024-05-08
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L44 140613 005 Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-090 June 13, 2014 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
Response to NRC Request for Additional Information on the Proposed License Amendment for Browns Ferry Nuclear Plant, Unit 1 (TAC No. MF3260)
References:
- 1. Letter from TVA to NRC, Browns Ferry Nuclear Plant (BFN), Unit 1 -
Application to Modify Technical Specification 3.4.9, RCS Pressure and Temperature (P/T) Limits (BFN TS-484), dated December 18, 2013 (ADAMS Accession No. ML13358A067)
- 2. Electronic Mail from NRC to TVA, Request for Additional Information on the Proposed License Amendment for Browns Ferry Nuclear Plant, Unit 1, (TAC No. MF3260), dated April 23, 2014 By letter dated December 18, 2013 (Reference 1), the Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) to revise the Browns Ferry Nuclear Plant, Unit 1, Technical Specifications (TS) for Limiting Condition for Operation (LCO) 3.4.9, RCS Pressure and Temperature (P/T) Limits.
By electronic mail dated April 23, 2014 (Reference 2), the Nuclear Regulatory Commission (NRC) transmitted a request for additional information (RAI) to support the review of the LAR.
The original due date for the response of May 30, 2014 was extended to June 13, 2014 by a teleconference with Andy Hon (NRC) on May 28, 2014. The Enclosure to this letter provides TVAs response to the NRC RAI.
Consistent with the standards set forth in Title 10 of the Code of Federal Regulations (10 CFR), Part 50.92(c), TVA has determined that the additional information, as provided in this letter, does not affect the no significant hazards consideration associated with the proposed application previously provided in Reference 1.
There are no new regulatory commitments contained in this submittal. Please address any questions regarding this submittal to Mr. Edward D. Schrull at (423) 751-3850.
U.S. Nuclear Regulatory Commission Page 2 June 13, 2014 I declare under penalty of perjury that the foregoing is true and correct. Executed on this 13th day of June 2014.
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Fie a
Enclosure:
Response to NRC Request for Additional Information on the Proposed License Amendment for Browns Ferry Nuclear Plant, Unit 1 Docket No. 50-259 (TAC No. MF3260) cc (Enclosure):
NRC Regional Administrator- Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Health
ENCLOSURE Response to NRC Request for Additional Information on the Proposed License Amendment for Browns Ferry Nuclear Plant, Unit 1 Docket No. 50-259 (TAC No. MF3260)
The Nuclear Regulatory Commission (NRC) staff has reviewed the proposed license amendment to modify Technical Specification 3.4.9 "Pressure and Temperature (PIT) Limits" submitted by Tennessee Valley Authority (the licensee, TVA) for Browns Ferry Nuclear Plant, Unit 1 (BFN-1 ), dated December 18, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13358A067). The NRC staff has determined that additional information is needed to complete the evaluation pertaining to the request, as detailed below.
NRC RAI No.1 NEDC-33445P (Reference 1), Enclosure 2 to the proposed license amendment, lists the axial electroslag weld (ESW) as the limiting material for the development of the new PIT limit curves for BFN-1. Measured heat-specific Charpy and drop weight toughness data are not available. The initial RT NOT value in Tables B-2, B-4, and B-5 for the ESW is listed as 23.1 OF; Tables B-4 and B-5 use a value of 13°F for the standard deviation of the initial value to calculate the margin term based on Regulatory Guide 1.99, Revision 2. These values are based on previously approved submittals (Reference 2), which were initially presented in BAW-2258 for Dresden, Units 2 and 3 (Reference 3) and BAW-2259 for Quad Cities, Units 1 and 2 (Reference 4) from January 1996. The values came from the nil-ductility-temperature (T NoT) data contained in the weld procedure qualification records (PQRs) that were performed in the general time frame when the Quad Cities and Dresden reactor vessels were fabricated. This represented the best data available to characterize the unirradiated RT NOT for any ESW in the fleet at the time.
The submittal does not establish how the previously approved values of initial RT NOT (23.1 OF) and standard deviation (13°F) from PQRs for the ESWs at Dresden, Units 2 and 3 and Quad Cities, Units 1 and 2 is applicable to BFN-1.
Discuss the limited PQR database in BAW-2258 and BAW-2259 and explain how that database is relevant to the axial vessel welds at BFN-1. Include a summary of the plant fabrication records for the axial welds and any other newer test results that could be used to supplement the limited PQR database. Justify why the previously approved values can be used at BFN-1.
REFERENCES:
- 1. NEDC-33445P - Pressure and Temperature Limits Report Up to 25 and 38 Effective Full- Power Years, December, 2013.
- 2. U.S. Nuclear Regulatory Commission (NRC) staff's safety evaluation, dated February 28, 1997, to Dresden and Quad Cities concerning a revision of their Pressure-Temperature Limits, ADAMS No. ML021150615.
- 3. Evaluation of RT NoT, USE, and Chemical Composition of Core Region Electroslag Welds for Dresden Units 2 and 3, BAW-2258, January 1996, ML14091A387.
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- 4. Evaluation of RT NoT, USE, and Chemical Composition of Core Region Electroslag Welds for Quad Cities Units 1 and 2, BAW-2259, January 1996, ML14091A388.
TVA Response The materials and fabrication information for the Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 reactor vessel core region components is summarized in BAW-1845 "Browns Ferry Core Region Materials Information (Units 1, 2, and 3)," dated August 1984 (Reference 1). BAW-1845 (full report) was previously submitted as an attachment in TVA to NRC letter, "TVA BFNP TS 191 Supplement 1," dated March 20, 1985. The report provides a beginning of life RT NOT for each of the seven welds and six plates that constitute the core region portion of the reactor vessels. The information provided is based on a review of quality assurance (QA) manufacturing records supplemented by information not available in the QA files.
No drop weight specimens were tested for the electroslag weld (ESW) metal. Three sets of Charpy impact toughness data exists for the surveillance welds, with 50 ft-lb temperatures of
+33aF, +1 oaF, and -21aF. With no other information available, a value of RT NOT= +OaF was estimated for the ESW metal for BFN Units 1, 2, and 3.
In TVA to NRC letter, "Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN),
and Watts Bar Nuclear Plant (WBN) - Response to Generic Letter 92-01 (Reactor Vessel Structural Integrity)," dated July 7, 1992 (Reference 2) , TVA provided the requested chemistry and initial RT NOT information for the three BFN units. The ESW data was identical for the three units with a conservative initial RT NOT value of 1oaF. BFN Unit 1 received NRC approval in the Amendment No. 121 Safety Evaluation (SE), dated September 16, 1985 (Reference 3).
In NRC to TVA letter, "Request for Additional Information Regarding Reactor Pressure Vessel Integrity at Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MA 1179, MA1180, and MA1181)," dated June 10, 1998 (Reference 4), NRC staff requested a re-evaluation of the RPV weld chemistry values that had been previously submitted in light of bounding data included in BWRVIP-46 that included the recommendation to consider the Framatome Technology analysis of ESWs referenced in the Dresden and Quad Cities SE dated September 20, 1996 (Reference 5). TVA responded by letter dated September 8, 1998 (Reference 6) by addressing the limiting materials. The "best estimate" chemistry values approved in the Quad Cities and Dresden analysis were adopted for BFN Units 2 and
- 3. Because BFN Unit 1's ESW was not a limiting material, the "best estimate" chemistry values were not adopted. The response did not address the initial RT NOT values.
Consequently, the ESW RT NoT values for all three BFN units remained at 10°F.
In TVA to NRC letter, "Browns Ferry Nuclear Plant (BFN)- Units 2 and 3- Technical Specification (TS) Change No. 393, Supplement 1 -Pressure-Temperature (P-T) Curve Update," dated December 15, 1998 (Reference 7) , TVA addressed two issues raised by NRC staff. The issue relevant to this response was the applicability of additional generic initial RT NOT data reported by Framatome Technologies Inc. to the BFN Units 2 and 3 reactor pressure vessels. In light of the NRC SE for the Dresden and Quad Cities ESWs (Reference 5), NRC staff requested that TVA "...explain why it is appropriate for TVA to use a value of 10 *F for the BFN electroslag welds. This issue must be resolved in order to complete the review of the Browns Ferry P- T limits and the licensee 's response to Generic Letter 92-01, Supplement 1. " In response, the best estimate initial RT NoT value (23.1 oF) and E-2
associated standard deviation (13.0°F) reported by Framatome Technologies, Inc. (FTI) in the Quad Cities and Dresden reports were incorporated in the re-evaluation of the BFN Units 2 and 3 reactor pressure vessel ESWs.
In NRC to TVA letter, "Amendment Nos. 257 and 217 to Facility Operating Licenses Nos.
DPR-52, and DPR-68: Pressure and Temperature Limits- Technical Specification Change TS-393 (TAC Nos. MA1304 and MA1305)," dated January 15, 1999 (Reference 8), " ... the NRC staff verified that the licensee used the recommended initial RT NoT and sigma initial values of 23.1 oF and 13°F, respectively, for electroslag welds, as previously found acceptable ... "
The previously approved RT NOT and sigma initial values of 23.1 oF and 13°F are applicable to BFN Unit 1 based on the initial RT NoT estimation and generic chemistry information for BFN Units 1, 2, and 3 provided in BAW-1845 (Reference 1) and NRC's approval of the values for BFN Units 2 and 3 (Reference 7) based on the NRC SE (Reference 5) for the Dresden and Quad Cities ESWs.
References:
- 1. Babcock & Wilcox Report, BAW-1845 "Browns Ferry Core Region Materials Information (Units 1, 2, and 3)," dated August 1984.
- 2. TVA to NRC letter, "Browns Ferry Nuclear Plant (BFN), Sequoyah Nuclear Plant (SQN), and Watts Bar Nuclear Plant (WBN) - Response to Generic Letter 92-01 (Reactor Vessel Structural Integrity)," dated July 7, 1992.
- 3. Safety Evaluation for Amendment Nos. 121, 116 and 92 to License Nos. DPR-33, DPR-52 and DPR-68, dated September 16, 1985.
- 4. NRC to TVA letter, "Request for Additional Information Regarding Reactor Pressure Vessel Integrity at Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MA 1179, MA1180, and MA1181)," dated June 10, 1998.
- 5. NRC to Commonwealth Edison letter, "Issuance of Amendments (TAC Nos. M96898, M96899, M96900 and M96901)," dated February 28, 1997.
- 6. TVA to NRC letter, "Browns Ferry Nuclear Plant (BFN)- Units 1, 2, and 3- Generic Letter (GL) 92-01, Revision 1, Supplement 1, Reactor Vessel Structural Integrity-Response to Request for Additional Information (TAC Nos. MA1179, MA1180, and MA 1181 ),"dated September 8, 1998.
- 7. TVA to NRC letter, "Browns Ferry Nuclear Plant (BFN)- Units 2 and 3- Technical Specification (TS) Change No. 393, Supplement 1 -Pressure-Temperature (P-T)
Curve Update," dated December 15, 1998.
- 8. NRC to TVA letter, "Amendment Nos. 257 and 217 to Facility Operating Licenses Nos.
DPR-52, and DPR-68: Pressure and Temperature Limits- Technical Specification Change TS-393 (TAC Nos. MA1304 and MA1305)," dated January 15, 1999.
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