CNL-16-123, Response to NRC Request for Additional Information Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5: Difference between revisions

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{{#Wiki_filter:1101 Market Street, Chattanooga, Tennessee 37402  
{{#Wiki_filter:1101 Market Street, Chattanooga, Tennessee 37402 CNL-16-123 July 28, 2016 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 and 2 Facility Operating License Nos. NFP-90 and 96 NRC Docket Nos. 50-390 and 50-391
 
CNL-16-123  
 
July 28, 2016  
 
10 CFR 50.55a  
 
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328  
 
Watts Bar Nuclear Plant, Unit 1 and 2 Facility Operating License Nos. NFP-90 and 96 NRC Docket Nos. 50-390 and 50-391  


==Subject:==
==Subject:==
Response to NRC Request for Additional Information Related to Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5  
Response to NRC Request for Additional Information Related to Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5


==References:==
==References:==
: 1. TVA letter to NRC, CNL-16-022, "Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5," dated May 27, 2016 (ML16151A010)
: 1. TVA letter to NRC, CNL-16-022, "Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5, dated May 27, 2016 (ML16151A010)
: 2. NRC letter to TVA, "Request for Additional Information Related to Relief Request 16-PDI-5 Regarding use of Alternate Calibration Block Reflector Requirements, Tennessee Valley Authority, Watts Bar Nuclear Plant Units 1 and 2, Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Sequoyah Nuclear Plant Units 1 and 2," dated July 12, 2016 (ML16195A030)  
: 2. NRC letter to TVA, "Request for Additional Information Related to Relief Request 16-PDI-5 Regarding use of Alternate Calibration Block Reflector Requirements, Tennessee Valley Authority, Watts Bar Nuclear Plant Units 1 and 2, Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Sequoyah Nuclear Plant Units 1 and 2, dated July 12, 2016 (ML16195A030)


Page E1-1 of 1 CNL-16-123 ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2 Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3 Sequoyah Nuclear Plant (Sequoyah), Units 1 and 2 TVA Response to NRC Request for Additional Information RAI-1 Section III of Enclosure to the relief request contains Item Numbers B5.130, B9.12, C5.12, and C5.52 that do not exist in Table IWB-2500-1 and Table IWC-2500-1 of Section XI of the ASME Code. Provide the correct Item Numbers for the welds for which relief requested.  
U.S. Nuclear Regulatory Commission CNL-16-123 Page 2 July 28, 2016 In Reference 1, Tennessee Valley Authority (TVA) submitted a relief request (16-PDl-5) for Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3, Sequoyah Nuclear Plant (SQN) Units 1 and 2, and Watts Bar Nuclear Plant (WBN) Units 1 and 2 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code), Table 111-3430-1 and paragraph (b)(3) of Supplement 1 of Appendix Ill to Section XI. This relief request pertains to the basic calibration blocks for the calibration of ultrasonic testing (UT) at the aforementioned TVA plants.
In Reference 2, the Nuclear Regulatory Commission (NRC) submitted a request for additional information (RAI) regarding the relief request and requested that TVA respond to the RAI by August 5, 2016. provides the TVA response to the NRC RAI and Enclosure 2 provides a revised Section Ill of the relief request that supersedes the one provided in Reference 1.
There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Mr. Edward D. Schrull at (423) 751 3850.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 28th day of July 2016.
Resettull~
e President, Nuclear Licensing


TVA Response:  
==Enclosures:==
: 1. TVA Response to NRC Request for Additional Information
: 2. Revised Section Ill of Relief Request 16-PDl-5 cc (Enclosure):
NRC    Regional Administrator - Region II NRC  Senior Resident Inspector - Watts Bar Nuclear Plant NRC  Senior Resident Inspector - Browns Ferry Nuclear Plant NRC  Senior Resident Inspector - Sequoyah Nuclear Plant NRR    Project Manager - Watts Bar Nuclear Plant NRR    Project Manager - Browns Ferry Nuclear Plant NRR  Project Manager - Sequoyah Nuclear Plant


The item numbers referenced in the original request for alternative submittal were those utilized in the effective ASME Section XI code of record at the time of block manufacture or as used for previous ultrasound examinations. TVA agrees that these items numbers do not exist in the current ASME codes of record for the TVA nuclear plants and will be deleted from Section III of the enclosure to the request for alternative.
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2 Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3 Sequoyah Nuclear Plant (Sequoyah), Units 1 and 2 TVA Response to NRC Request for Additional Information


of this submittal provides a revised Section III of the enclosure to the relief request that supersedes the one provided in the Reference letter and includes additional item numbers that may apply to the subject calibration blocks during future examinations.  
===RAI-1===
Section III of Enclosure to the relief request contains Item Numbers B5.130, B9.12, C5.12, and C5.52 that do not exist in Table IWB-2500-1 and Table IWC-2500-1 of Section XI of the ASME Code. Provide the correct Item Numbers for the welds for which relief requested.
TVA Response:
The item numbers referenced in the original request for alternative submittal were those utilized in the effective ASME Section XI code of record at the time of block manufacture or as used for previous ultrasound examinations. TVA agrees that these items numbers do not exist in the current ASME codes of record for the TVA nuclear plants and will be deleted from Section III of the enclosure to the request for alternative. of this submittal provides a revised Section III of the enclosure to the relief request that supersedes the one provided in the Reference letter and includes additional item numbers that may apply to the subject calibration blocks during future examinations.


==Reference:==
==Reference:==
TVA letter to NRC, CNL-16-022, "Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5," dated May 27, 2016 (ML16151A010)  
TVA letter to NRC, CNL-16-022, "Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5, dated May 27, 2016 (ML16151A010)
Page E1-1 of 1 CNL-16-123


Page E2-1 of 1 CNL-16-123 ENCLOSURE 2 Revised Section III of Relief Request 16-PDI-5 III. Applicable Code ASME Code Components Affected: ASME Code Classes: 1 & 2  
ENCLOSURE 2 Revised Section III of Relief Request 16-PDI-5 III. Applicable Code ASME Code Components Affected:
ASME Code Classes:       1&2


==References:==
==References:==
IWA-2232 Appendix III, Subsubarticle III-3430 Appendix III, Supplement 1(b)(3)
IWA-2232 Appendix III, Subsubarticle III-3430 Appendix III, Supplement 1(b)(3)
Examination Categories: B-B, B-D, B-F, B-J, B-O, C-A, C-B, C-F-1, C-F-2 Item Numbers: B2.50, B2.60, B2.70, B2.80, B3.150, B5.10, B5.40, B5.70, B5.100, B9.11, B9.22, B9.31, B14.10, B14.20, B14.21, C1.10, C1.20, C1.30, C2.21, C2.22, C2.32, C5.11, C5.21, C5.51,     C5.61  
Examination Categories:   B-B, B-D, B-F, B-J, B-O, C-A, C-B, C-F-1, C-F-2 Item Numbers:             B2.50, B2.60, B2.70, B2.80, B3.150, B5.10, B5.40, B5.70, B5.100, B9.11, B9.22, B9.31, B14.10, B14.20, B14.21, C1.10, C1.20, C1.30, C2.21, C2.22, C2.32, C5.11, C5.21, C5.51, C5.61


==
==
Description:==
Description:==
Alternative to Appendix III Calibration Reflector Requirements  
Alternative to Appendix III Calibration Reflector Requirements Component Numbers:       ASME Class 1 and 2 components subject to examination in accordance with Appendix III of Section XI.
 
Page E2-1 of 1 CNL-16-123}}
Component Numbers: ASME Class 1 and 2 components subject to examination in accordance with Appendix III of Section XI.}}

Latest revision as of 16:55, 30 October 2019

Response to NRC Request for Additional Information Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5
ML16211A337
Person / Time
Site: Browns Ferry, Watts Bar, Sequoyah  Tennessee Valley Authority icon.png
Issue date: 07/28/2016
From: James Shea
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-16-123
Download: ML16211A337 (4)
v • d • e


Text

1101 Market Street, Chattanooga, Tennessee 37402 CNL-16-123 July 28, 2016 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 and 2 Facility Operating License Nos. NFP-90 and 96 NRC Docket Nos. 50-390 and 50-391

Subject:

Response to NRC Request for Additional Information Related to Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5

References:

1. TVA letter to NRC, CNL-16-022, "Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5, dated May 27, 2016 (ML16151A010)
2. NRC letter to TVA, "Request for Additional Information Related to Relief Request 16-PDI-5 Regarding use of Alternate Calibration Block Reflector Requirements, Tennessee Valley Authority, Watts Bar Nuclear Plant Units 1 and 2, Browns Ferry Nuclear Plant, Units 1, 2, and 3, and Sequoyah Nuclear Plant Units 1 and 2, dated July 12, 2016 (ML16195A030)

U.S. Nuclear Regulatory Commission CNL-16-123 Page 2 July 28, 2016 In Reference 1, Tennessee Valley Authority (TVA) submitted a relief request (16-PDl-5) for Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3, Sequoyah Nuclear Plant (SQN) Units 1 and 2, and Watts Bar Nuclear Plant (WBN) Units 1 and 2 from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV Code), Table 111-3430-1 and paragraph (b)(3) of Supplement 1 of Appendix Ill to Section XI. This relief request pertains to the basic calibration blocks for the calibration of ultrasonic testing (UT) at the aforementioned TVA plants.

In Reference 2, the Nuclear Regulatory Commission (NRC) submitted a request for additional information (RAI) regarding the relief request and requested that TVA respond to the RAI by August 5, 2016. provides the TVA response to the NRC RAI and Enclosure 2 provides a revised Section Ill of the relief request that supersedes the one provided in Reference 1.

There are no new regulatory commitments associated with this submittal. Please address any questions regarding this request to Mr. Edward D. Schrull at (423) 751 3850.

I declare under penalty of perjury that the foregoing is true and correct. Executed on this 28th day of July 2016.

Resettull~

e President, Nuclear Licensing

Enclosures:

1. TVA Response to NRC Request for Additional Information
2. Revised Section Ill of Relief Request 16-PDl-5 cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRR Project Manager - Watts Bar Nuclear Plant NRR Project Manager - Browns Ferry Nuclear Plant NRR Project Manager - Sequoyah Nuclear Plant

ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2 Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3 Sequoyah Nuclear Plant (Sequoyah), Units 1 and 2 TVA Response to NRC Request for Additional Information

RAI-1

Section III of Enclosure to the relief request contains Item Numbers B5.130, B9.12, C5.12, and C5.52 that do not exist in Table IWB-2500-1 and Table IWC-2500-1 of Section XI of the ASME Code. Provide the correct Item Numbers for the welds for which relief requested.

TVA Response:

The item numbers referenced in the original request for alternative submittal were those utilized in the effective ASME Section XI code of record at the time of block manufacture or as used for previous ultrasound examinations. TVA agrees that these items numbers do not exist in the current ASME codes of record for the TVA nuclear plants and will be deleted from Section III of the enclosure to the request for alternative. of this submittal provides a revised Section III of the enclosure to the relief request that supersedes the one provided in the Reference letter and includes additional item numbers that may apply to the subject calibration blocks during future examinations.

Reference:

TVA letter to NRC, CNL-16-022, "Browns Ferry Nuclear Plant Units 1, 2, and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Units 1 and 2 - Request for Approval for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5, dated May 27, 2016 (ML16151A010)

Page E1-1 of 1 CNL-16-123

ENCLOSURE 2 Revised Section III of Relief Request 16-PDI-5 III. Applicable Code ASME Code Components Affected:

ASME Code Classes: 1&2

References:

IWA-2232 Appendix III, Subsubarticle III-3430 Appendix III, Supplement 1(b)(3)

Examination Categories: B-B, B-D, B-F, B-J, B-O, C-A, C-B, C-F-1, C-F-2 Item Numbers: B2.50, B2.60, B2.70, B2.80, B3.150, B5.10, B5.40, B5.70, B5.100, B9.11, B9.22, B9.31, B14.10, B14.20, B14.21, C1.10, C1.20, C1.30, C2.21, C2.22, C2.32, C5.11, C5.21, C5.51, C5.61

==

Description:==

Alternative to Appendix III Calibration Reflector Requirements Component Numbers: ASME Class 1 and 2 components subject to examination in accordance with Appendix III of Section XI.

Page E2-1 of 1 CNL-16-123

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