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| number = ML16020A111
| number = ML16020A111
| issue date = 01/28/2016
| issue date = 01/28/2016
| title = Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate (CAC Nos. MF4851, MF4582 and MF4853)
| title = Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
| author name = Saba F E
| author name = Saba F
| author affiliation = NRC/NRR/DORL/LPLII-2
| author affiliation = NRC/NRR/DORL/LPLII-2
| addressee name = Shea J W
| addressee name = Shea J
| addressee affiliation = Tennessee Valley Authority
| addressee affiliation = Tennessee Valley Authority
| docket = 05000259, 05000260, 05000296
| docket = 05000259, 05000260, 05000296
| license number = DPR-033, DPR-052, DPR-068
| license number = DPR-033, DPR-052, DPR-068
| contact person = Saba F E
| contact person = Saba F
| case reference number = CAC MF4582, CAC MF4851, CAC MF4853
| case reference number = CAC MF4582, CAC MF4851, CAC MF4853
| document type = Letter, Request for Additional Information (RAI)
| document type = Letter, Request for Additional Information (RAI)
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801 January 28, 2016
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 28, 2016 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801


==SUBJECT:==
==SUBJECT:==
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF4851, MF4582, AND MF4853)  
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF4851, MF4582, AND MF4853)


==Dear Mr. Shea:==
==Dear Mr. Shea:==
By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML 15317 A361, ML 15351A 113, and ML 15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt. The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On January 15, 2016, the NRC staff forwarded, by electronic mail, a draft request for additional information (RAI) to TVA. On January 21, 2016, the NRC staff held a conference call to provide the licensee with an opportunity to clarify any portion of the draft RAI and discuss the timeframe for which TVA may provide the requested information.
 
The RAI is enclosed.
By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN),
As agreed by the NRC and TVA staff during the conference call, TVA will respond to this RAI by February 16, 2016.
Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.
J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On January 15, 2016, the NRC staff forwarded, by electronic mail, a draft request for additional information (RAI) to TVA. On January 21, 2016, the NRC staff held a conference call to provide the licensee with an opportunity to clarify any portion of the draft RAI and discuss the timeframe for which TVA may provide the requested information. The RAI is enclosed. As agreed by the NRC and TVA staff during the conference call, TVA will respond to this RAI by February 16, 2016.
Docket Nos. 50-259, 50-260, and 50-296  
 
J. Shea                                     If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296


==Enclosure:==
==Enclosure:==


Request for Additional Information cc w/enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
Distribution via Listserv Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT. UNITS 1. 2. AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15282A 152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML 15317A361, ML 15351A113, and ML 15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt. The U.S. Nuclear Regulatory Commission (NRC) staff from the Electrical Engineering Branch (EEEB) and Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB), Division of Engineering reviewed the information the licensee provided and determined that the following additional information is required in order to complete the evaluation.
 
EEEB-Reguest for Additional Information (RAI) 1 In Section 3.0 of Attachment 43, the licensee states: The [TSS] study evaluated the performance of the 500 kV [kilovolt]
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT. UNITS 1. 2. AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN),
and 161 kV offsite power systems during a DBE [design-basis event] under EPU [extended power uprate] conditions.
Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.
Bus voltages observed during the simulation are compared to acceptance criteria to determine adequacy of the offsite power supply. The TSS considered a loss of the largest single supply to the grid, loss of the largest single load, loss of the nuclear unit, and loss of each bulk transmission line in the TVA transmission system, including all the lines coming into the BFN switchyard.
The U.S. Nuclear Regulatory Commission (NRC) staff from the Electrical Engineering Branch (EEEB) and Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB),
The study used base cases from both 2015 (pre-EPU) and 2019 (post-EPU) to address the load flow analysis at EPU conditions.
Division of Engineering reviewed the information the licensee provided and determined that the following additional information is required in order to complete the evaluation.
A Provide the acceptable voltage range of BFN 500 kV and 161 kV offsite power acceptance criteria.
EEEB-Reguest for Additional Information (RAI) 1 In Section 3.0 of Attachment 43, the licensee states:
Also, clarify whether the voltage criteria corresponding to post-EPU conditions has been agreed upon by the transmission system operator.
The [TSS] study evaluated the performance of the 500 kV [kilovolt] and 161 kV offsite power systems during a DBE [design-basis event] under EPU [extended power uprate] conditions. Bus voltages observed during the simulation are compared to acceptance criteria to determine adequacy of the offsite power supply. The TSS considered a loss of the largest single supply to the grid, loss of the largest single load, loss of the nuclear unit, and loss of each bulk transmission line in the TVA transmission system, including all the lines coming into the BFN switchyard. The study used base cases from both 2015 (pre-EPU) and 2019 (post-EPU) to address the load flow analysis at EPU conditions.
Enclosure   B. Provide a summary of the cases studied, with diagrams to verify that the voltage criteria is met under the following post-EPU conditions:  
A     Provide the acceptable voltage range of BFN 500 kV and 161 kV offsite power acceptance criteria. Also, clarify whether the voltage criteria corresponding to post-EPU conditions has been agreed upon by the transmission system operator.
: i. loss of the largest load (identify the load), ii. loss of the largest generator (identify the generator), and iii. loss of the most critical transmission line (identify the line). EEEB-RAI 2 In Section 2.3.3.1 of Attachment 7, "Safety Analysis Report for Browns Ferry Nuclear Plant Units 1, 2, and 3 Extended Power Uprate," the licensee states: The larger condensate pump motors {1,250 horsepower (hp)), CSP motors (3,000 hp) and reactor recirculation pump motors (8,657 hp) do not change the conclusions of the current Browns Ferry degraded voltage analysis.
Enclosure
The analysis encompasses the safety-related 4.16 kV [kilovolts]
 
buses and is independent of voltage profiles for the balance of plant buses [BOP]. Provide a summary of the degraded voltage analysis corresponding to post-EPU conditions.
B. Provide a summary of the cases studied, with diagrams to verify that the voltage criteria is met under the following post-EPU conditions:
Also, provide single line diagram(s) showing the safety-related 4.16 kV buses with their connected loads and power sources and the BOP buses with their connected loads and power sources. EEEB-RAI 3 In Section 2.3.3.2 of Attachment 7, the licensee states: The analytical electrical system computer model developed for Browns Ferry updated the main power transformer size to reflect the recent change of main power transformers and the proposed changes to the main generators and condensate pumps. Provide a description of the proposed changes, including the ratings, to the main generators.
: i.     loss of the largest load (identify the load),
EEEB-RAI 4 In Section 2.3.2.2 of Attachment 7, the licensee states: The Unit 1, Unit 2 and Unit 3 isolated phase bus (IPB) duct work, cooling coils and fans have been modified to increase the continuous current rating to provide for operation at EPU output. Provide the IPB duct current rating and the continuous current requirement for EPU conditions to show the adequacy of the IPB duct to support operation under EPU conditions.
ii. loss of the largest generator (identify the generator), and iii. loss of the most critical transmission line (identify the line).
Also, provide a description of the modifications made to the IPB duct, cooling coils, and fans, to increase the continuous current rating for operating at EPU conditions. ESGB-RAI 1 In Section 10.3.6 of the Updated Final Safety Analysis Report, and in information provided in the supplemental letter dated December 15, 2015, it is indicated that a Boral neutron absorber monitoring program is used at BFN, Units 1, 2, and 3. The intent of the monitoring program is to manage potential reduction of neutron-absorbing capacity and loss of material due to general corrosion.
EEEB-RAI 2 In Section 2.3.3.1 of Attachment 7, "Safety Analysis Report for Browns Ferry Nuclear Plant Units 1, 2, and 3 Extended Power Uprate," the licensee states:
However, in the sources mentioned, there is minimal information describing the Boral monitoring program. For this reason, please provide a brief description of the monitoring program. The information provided should include the following discussion:
The larger condensate pump motors {1,250 horsepower (hp)), CSP motors (3,000 hp) and reactor recirculation pump motors (8,657 hp) do not change the conclusions of the current Browns Ferry degraded voltage analysis. The analysis encompasses the safety-related 4.16 kV [kilovolts] buses and is independent of voltage profiles for the balance of plant buses [BOP].
A. If test specimens (i.e., coupons) are used: i. Define the periodicity for evaluation.
Provide a summary of the degraded voltage analysis corresponding to post-EPU conditions.
Also, provide single line diagram(s) showing the safety-related 4.16 kV buses with their connected loads and power sources and the BOP buses with their connected loads and power sources.
EEEB-RAI 3 In Section 2.3.3.2 of Attachment 7, the licensee states:
The analytical electrical system computer model developed for Browns Ferry updated the main power transformer size to reflect the recent change of main power transformers and the proposed changes to the main generators and condensate pumps.
Provide a description of the proposed changes, including the ratings, to the main generators.
EEEB-RAI 4 In Section 2.3.2.2 of Attachment 7, the licensee states:
The Unit 1, Unit 2 and Unit 3 isolated phase bus (IPB) duct work, cooling coils and fans have been modified to increase the continuous current rating to provide for operation at EPU output.
Provide the IPB duct current rating and the continuous current requirement for EPU conditions to show the adequacy of the IPB duct to support operation under EPU conditions. Also, provide a description of the modifications made to the IPB duct, cooling coils, and fans, to increase the continuous current rating for operating at EPU conditions.
 
ESGB-RAI 1 In Section 10.3.6 of the Updated Final Safety Analysis Report, and in information provided in the supplemental letter dated December 15, 2015, it is indicated that a Boral neutron absorber monitoring program is used at BFN, Units 1, 2, and 3. The intent of the monitoring program is to manage potential reduction of neutron-absorbing capacity and loss of material due to general corrosion. However, in the sources mentioned, there is minimal information describing the Boral monitoring program. For this reason, please provide a brief description of the monitoring program. The information provided should include the following discussion:
A. If test specimens (i.e., coupons) are used:
: i. Define the periodicity for evaluation.
ii. Provide the number of coupons available.
ii. Provide the number of coupons available.
iii. Describe any adverse conditions identified from coupon evaluation thus far. iv. Discuss the ambient conditions for the coupons in the spent fuel pool (e.g., surrounded by freshly discharged spent fuel assemblies).  
iii. Describe any adverse conditions identified from coupon evaluation thus far.
iv. Discuss the ambient conditions for the coupons in the spent fuel pool (e.g.,
surrounded by freshly discharged spent fuel assemblies).
: v. Discuss whether coupons are returned to the spent fuel pool after inspection.
: v. Discuss whether coupons are returned to the spent fuel pool after inspection.
B. If coupons are not used, discuss the periodicity of surveillance.
B. If coupons are not used, discuss the periodicity of surveillance.
C. Describe the types of tests performed during the periodic inspection.  
C. Describe the types of tests performed during the periodic inspection.
: a. Describe the test procedure.  
: a.     Describe the test procedure.
: b. Discuss whether neutron-attenuation testing is performed to determine the boron-1 O (B-10) areal density of the absorber material during periodic testing. D. Define the acceptance criteria for the surveillance program, including what constitutes an adverse condition.
: b. Discuss whether neutron-attenuation testing is performed to determine the boron-1 O (B-10) areal density of the absorber material during periodic testing.
E. Describe those measures taken to address a failure to meet the acceptance criteria for either the surveillance program and/or the B-10 areal density. F. Address any adverse conditions, other than identified corrosion, which may be identified during testing, and whether different acceptance criteria apply to those other adverse conditions.
D. Define the acceptance criteria for the surveillance program, including what constitutes an adverse condition.
J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
E. Describe those measures taken to address a failure to meet the acceptance criteria for either the surveillance program and/or the B-10 areal density.
Sincerely, IRA/ Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296  
F. Address any adverse conditions, other than identified corrosion, which may be identified during testing, and whether different acceptance criteria apply to those other adverse conditions.
 
J. Shea                                       If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.
Sincerely, IRA/
Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296


==Enclosure:==
==Enclosure:==


Request for Additional Information cc w/enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION:
Distribution via Listserv DISTRIBUTION:
PUBLIC                             RidsNrrLABClayton                  SKrepel, NRR LPL2-2 R/F                         RidsACRS_MailCTR                  RidsNrrDeEsgb RidsNrrDorllpl2-2                 RidsRgn2MailCenter                RisdNrrDeEeeb KWood, NRR                         RidsNrrPMBrownsFerry ADAMS Access1on No.: ML16020A111                    *b>Y memoran d um     **b>Y e-ma1*1 OFFICE NRR/DORL/LPLll-2/PM NRR/DORL/LPLll-2/LA                   NRR/DE/EEEB/BC**
PUBLIC LPL2-2 R/F RidsNrrDorllpl2-2 KWood, NRR RidsNrrLABClayton RidsACRS_MailCTR RidsRgn2MailCenter RidsNrrPMBrownsFerry SKrepel, NRR RidsNrrDeEsgb RisdNrrDeEeeb ADAMS A ccess1on N ML16020A111 o.: *b d >Y memoran um **b *1 >Y e-ma1 OFFICE NRR/DORL/LPLll-2/PM NRR/DORL/LPLll-2/LA NRR/DE/EEEB/BC**
NAME     FSaba                     (LRonewicz for) BClayton JZimmerman DATE     1/21/2016                 1/22/2016                   1/28/2016 OFFICE NRR/DE/ESGB/BC*               NRR/DORL/LPLll-2/BC         NRR/DORL/LPLll-2/PM NAME     GKulesa                   BBeasley                   FSaba DATE     1/13/2016                 1/28/2016                   1/28/2016 OFFICIAL RECORD COPY}}
NAME FSaba (LRonewicz for) BClayton JZimmerman DATE 1/21/2016 1/22/2016 1/28/2016 OFFICE NRR/DE/ESGB/BC*
NRR/DORL/LPLll-2/BC NRR/DORL/LPLll-2/PM NAME GKulesa BBeasley FSaba DATE 1/13/2016 1/28/2016 1/28/2016 OFFICIAL RECORD COPY}}

Latest revision as of 06:21, 19 March 2020

Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate
ML16020A111
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 01/28/2016
From: Farideh Saba
Plant Licensing Branch II
To: James Shea
Tennessee Valley Authority
Saba F
References
CAC MF4582, CAC MF4851, CAC MF4853
Download: ML16020A111 (6)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 28, 2016 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE (CAC NOS. MF4851, MF4582, AND MF4853)

Dear Mr. Shea:

By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN),

Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.

The U.S. Nuclear Regulatory Commission (NRC) staff reviewed the licensee's submittals and determined that additional information is needed. On January 15, 2016, the NRC staff forwarded, by electronic mail, a draft request for additional information (RAI) to TVA. On January 21, 2016, the NRC staff held a conference call to provide the licensee with an opportunity to clarify any portion of the draft RAI and discuss the timeframe for which TVA may provide the requested information. The RAI is enclosed. As agreed by the NRC and TVA staff during the conference call, TVA will respond to this RAI by February 16, 2016.

J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.

Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST REGARDING EXTENDED POWER UPRATE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT. UNITS 1. 2. AND 3 DOCKET NOS. 50-259, 50-260, AND 50-296 By letter dated September 21, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15282A152), as supplemented by letters dated November 13, December 15, and December 18, 2015 (ADAMS Accession Nos. ML15317A361, ML15351A113, and ML15355A413, respectively), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for Browns Ferry Nuclear Plant (BFN),

Units 1, 2, and 3. The proposed amendment would increase the authorized maximum steady-state reactor core power level for each unit from 3,458 megawatt thermal (MWt) to 3,952 MWt. This LAR represents an increase of approximately 20 percent above the original licensed thermal power level of 3,293 MWt, and an increase of approximately 14.3 percent above the current licensed thermal power level of 3,458 MWt.

The U.S. Nuclear Regulatory Commission (NRC) staff from the Electrical Engineering Branch (EEEB) and Steam Generator Tube Integrity and Chemical Engineering Branch (ESGB),

Division of Engineering reviewed the information the licensee provided and determined that the following additional information is required in order to complete the evaluation.

EEEB-Reguest for Additional Information (RAI) 1 In Section 3.0 of Attachment 43, the licensee states:

The [TSS] study evaluated the performance of the 500 kV [kilovolt] and 161 kV offsite power systems during a DBE [design-basis event] under EPU [extended power uprate] conditions. Bus voltages observed during the simulation are compared to acceptance criteria to determine adequacy of the offsite power supply. The TSS considered a loss of the largest single supply to the grid, loss of the largest single load, loss of the nuclear unit, and loss of each bulk transmission line in the TVA transmission system, including all the lines coming into the BFN switchyard. The study used base cases from both 2015 (pre-EPU) and 2019 (post-EPU) to address the load flow analysis at EPU conditions.

A Provide the acceptable voltage range of BFN 500 kV and 161 kV offsite power acceptance criteria. Also, clarify whether the voltage criteria corresponding to post-EPU conditions has been agreed upon by the transmission system operator.

Enclosure

B. Provide a summary of the cases studied, with diagrams to verify that the voltage criteria is met under the following post-EPU conditions:

i. loss of the largest load (identify the load),

ii. loss of the largest generator (identify the generator), and iii. loss of the most critical transmission line (identify the line).

EEEB-RAI 2 In Section 2.3.3.1 of Attachment 7, "Safety Analysis Report for Browns Ferry Nuclear Plant Units 1, 2, and 3 Extended Power Uprate," the licensee states:

The larger condensate pump motors {1,250 horsepower (hp)), CSP motors (3,000 hp) and reactor recirculation pump motors (8,657 hp) do not change the conclusions of the current Browns Ferry degraded voltage analysis. The analysis encompasses the safety-related 4.16 kV [kilovolts] buses and is independent of voltage profiles for the balance of plant buses [BOP].

Provide a summary of the degraded voltage analysis corresponding to post-EPU conditions.

Also, provide single line diagram(s) showing the safety-related 4.16 kV buses with their connected loads and power sources and the BOP buses with their connected loads and power sources.

EEEB-RAI 3 In Section 2.3.3.2 of Attachment 7, the licensee states:

The analytical electrical system computer model developed for Browns Ferry updated the main power transformer size to reflect the recent change of main power transformers and the proposed changes to the main generators and condensate pumps.

Provide a description of the proposed changes, including the ratings, to the main generators.

EEEB-RAI 4 In Section 2.3.2.2 of Attachment 7, the licensee states:

The Unit 1, Unit 2 and Unit 3 isolated phase bus (IPB) duct work, cooling coils and fans have been modified to increase the continuous current rating to provide for operation at EPU output.

Provide the IPB duct current rating and the continuous current requirement for EPU conditions to show the adequacy of the IPB duct to support operation under EPU conditions. Also, provide a description of the modifications made to the IPB duct, cooling coils, and fans, to increase the continuous current rating for operating at EPU conditions.

ESGB-RAI 1 In Section 10.3.6 of the Updated Final Safety Analysis Report, and in information provided in the supplemental letter dated December 15, 2015, it is indicated that a Boral neutron absorber monitoring program is used at BFN, Units 1, 2, and 3. The intent of the monitoring program is to manage potential reduction of neutron-absorbing capacity and loss of material due to general corrosion. However, in the sources mentioned, there is minimal information describing the Boral monitoring program. For this reason, please provide a brief description of the monitoring program. The information provided should include the following discussion:

A. If test specimens (i.e., coupons) are used:

i. Define the periodicity for evaluation.

ii. Provide the number of coupons available.

iii. Describe any adverse conditions identified from coupon evaluation thus far.

iv. Discuss the ambient conditions for the coupons in the spent fuel pool (e.g.,

surrounded by freshly discharged spent fuel assemblies).

v. Discuss whether coupons are returned to the spent fuel pool after inspection.

B. If coupons are not used, discuss the periodicity of surveillance.

C. Describe the types of tests performed during the periodic inspection.

a. Describe the test procedure.
b. Discuss whether neutron-attenuation testing is performed to determine the boron-1 O (B-10) areal density of the absorber material during periodic testing.

D. Define the acceptance criteria for the surveillance program, including what constitutes an adverse condition.

E. Describe those measures taken to address a failure to meet the acceptance criteria for either the surveillance program and/or the B-10 areal density.

F. Address any adverse conditions, other than identified corrosion, which may be identified during testing, and whether different acceptance criteria apply to those other adverse conditions.

J. Shea If you have any questions, please contact me at 301-415-1447 or Farideh.Saba@nrc.gov.

Sincerely, IRA/

Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrLABClayton SKrepel, NRR LPL2-2 R/F RidsACRS_MailCTR RidsNrrDeEsgb RidsNrrDorllpl2-2 RidsRgn2MailCenter RisdNrrDeEeeb KWood, NRR RidsNrrPMBrownsFerry ADAMS Access1on No.: ML16020A111 *b>Y memoran d um **b>Y e-ma1*1 OFFICE NRR/DORL/LPLll-2/PM NRR/DORL/LPLll-2/LA NRR/DE/EEEB/BC**

NAME FSaba (LRonewicz for) BClayton JZimmerman DATE 1/21/2016 1/22/2016 1/28/2016 OFFICE NRR/DE/ESGB/BC* NRR/DORL/LPLll-2/BC NRR/DORL/LPLll-2/PM NAME GKulesa BBeasley FSaba DATE 1/13/2016 1/28/2016 1/28/2016 OFFICIAL RECORD COPY

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