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| number = ML090710705
| number = ML090710705
| issue date = 03/23/2009
| issue date = 03/23/2009
| title = 02/26/09 Summary of Meeting with Tennessee Valley Authority (TVA) to Discuss Proposed Extended Power Uprate (EPU) Analyses Revision
| title = Summary of Meeting with Tennessee Valley Authority (TVA) to Discuss Proposed Extended Power Uprate (EPU) Analyses Revision
| author name = Brown E A
| author name = Brown E
| author affiliation = NRC/NRR/DORL/LPLII-2
| author affiliation = NRC/NRR/DORL/LPLII-2
| addressee name =  
| addressee name =  
Line 19: Line 19:


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 23, 2009 LICENSEE:
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 23, 2009 LICENSEE:       Tennessee Valley Authority FACILITIES:     Browns Ferry Nuclear Plant, Units 1 and 2
Tennessee Valley Authority FACILITIES:
Browns Ferry Nuclear Plant, Units 1 and 2  


==SUBJECT:==
==SUBJECT:==


==SUMMARY==
==SUMMARY==
OF FEBRUARY 26,2009, MEETING WITH THE TENNESSEE VALLEY AUTHORITY (TVA) TO DISCUSS PROPOSED EXTENDED POWER UPRATE ANALYSES REVISION (TAC NOS. MD5262 AND MD5263) On February 26,2009, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 1 pUblic meeting with Tennessee Valley Authority (TVA, the licensee) at NRC Headquarters, 11555 Rockville Pike, One White Flint North, Rockville, Maryland.
OF FEBRUARY 26,2009, MEETING WITH THE TENNESSEE VALLEY AUTHORITY (TVA) TO DISCUSS PROPOSED EXTENDED POWER UPRATE ANALYSES REVISION (TAC NOS. MD5262 AND MD5263)
The purpose of the meeting was to discuss analyses revisions proposed by TVA in support of the extended power uprate amendment request for Browns Ferry Nuclear Plant. Enclosure 1 contains a list of attendees.
On February 26,2009, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 1 pUblic meeting with Tennessee Valley Authority (TVA, the licensee) at NRC Headquarters, 11555 Rockville Pike, One White Flint North, Rockville, Maryland. The purpose of the meeting was to discuss analyses revisions proposed by TVA in support of the extended power uprate amendment request for Browns Ferry Nuclear Plant. Enclosure 1 contains a list of attendees. The licensee presented a slide presentation [see the Agencywide Documents Access and Management System (ADAMS) accession No. ML090710768]. The licensee also presented proposed answers to questions that the Advisory Committee on Reactor Safeguards (ACRS) had posed to the NRC staff (see the ADAMS accession No. ML090710807).
The licensee presented a slide presentation  
DISCUSSION TVA revised the net positive suction head/containment accident pressure (NPSH/CAP) short term loss-of-coolant accident (LOCA) analyses by reducing the residual heat removal (RHR) pump flow rate into the broken recirculation loop by an excess flow rate value included in previous short-term LOCA NPSH calculations, thereby reducing the required NPSH at 10 minutes into the scenario. The relative humidity was also reduced to a more realistic number that would increase the amount of noncondensible gases in containment during the scenario, which results in an increase in CAP. Additionally, the time-dependent nature of the required NPSH was added to the model. TVA has concluded that these changes would allow the RHR pumps to remain within the vendor's performance curves while performing their functions during a LOCA. On a related note, a representative from the pump vendor Sulzer stated that the commercial pump specifications referenced in the analyses are minimal performance values and that actual performance, as demonstrated by pump tests, would be far better.
[see the Agencywide Documents Access and Management System (ADAMS) accession No. ML090710768].
There was discussion of the time dependence of the required NPSH and how it is calculated.
The licensee also presented proposed answers to questions that the Advisory Committee on Reactor Safeguards (ACRS) had posed to the NRC staff (see the ADAMS accession No. ML090710807).
The licensee explained that the time dependence of the required NPSH is based on integrated wear over the 8000 hours. Since the integrated wear over the 8000 hrs is constant, the ordering of the amount of the wear over time is arbitrary and the shape of the plot of the required NPSH over time as related to wear can be varied.
DISCUSSION TVA revised the net positive suction head/containment accident pressure (NPSH/CAP) term loss-of-coolant accident (LOCA) analyses by reducing the residual heat removal (RHR) pump flow rate into the broken recirculation loop by an excess flow rate value included in previous short-term LOCA NPSH calculations, thereby reducing the required NPSH at 10 minutes into the scenario.
The staff spoke on attempting to determine the acceptance criteria for Appendix R scenarios requiring CAP. The licensee suggested that it would be helpful if the Boiling Water Reactor Owners Group would generate a standard approach to the issues.
The relative humidity was also reduced to a more realistic number that would increase the amount of noncondensible gases in containment during the scenario, which results in an increase in CAP. Additionally, the time-dependent nature of the required NPSH was added to the model. TVA has concluded that these changes would allow the RHR pumps to remain within the vendor's performance curves while performing their functions during a LOCA. On a related note, a representative from the pump vendor Sulzer stated that the commercial pump specifications referenced in the analyses are minimal performance values and that actual performance, as demonstrated by pump tests, would be far better. There was discussion of the time dependence of the required NPSH and how it is calculated.
 
The licensee explained that the time dependence of the required NPSH is based on integrated wear over the 8000 hours. Since the integrated wear over the 8000 hrs is constant, the ordering of the amount of the wear over time is arbitrary and the shape of the plot of the required NPSH over time as related to wear can be varied. The staff spoke on attempting to determine the acceptance criteria for Appendix R scenarios requiring CAP. The licensee suggested that it would be helpful if the Boiling Water Reactor Owners Group would generate a standard approach to the issues.
                                                -2 The Sulzer representative responded to an ACRS staff member's question on how pump testing at a lower temperature can give reliable indication of NPSH at a higher suction temperature.
-2 The Sulzer representative responded to an ACRS staff member's question on how pump testing at a lower temperature can give reliable indication of NPSH at a higher suction temperature.
The representative stated that testing at a lower inlet temperature and using that temperature without correction at the higher inlet temperature is conservative since required NPSH decreases with increased temperature.
The representative stated that testing at a lower inlet temperature and using that temperature without correction at the higher inlet temperature is conservative since required NPSH decreases with increased temperature.
Environmental qualification of containment equipment was briefly discussed.
Environmental qualification of containment equipment was briefly discussed. The licensee stated that all equipment in containment is qualified to 281 degrees Fahrenheit for 100 days.
The licensee stated that all equipment in containment is qualified to 281 degrees Fahrenheit for 100 days. Also, there was a brief discussion regarding the ACRS request for information on how much cavitation of the pump was acceptable.
Also, there was a brief discussion regarding the ACRS request for information on how much cavitation of the pump was acceptable.
No members of the public were in attendance, and no feedback forms were received.
No members of the public were in attendance, and no feedback forms were received. No commitments or regulatory decisions were made by the NRC staff during the meeting.
No commitments or regulatory decisions were made by the NRC staff during the meeting. Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259 and 50-260  
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259 and 50-260


==Enclosure:==
==Enclosure:==
List of Attendees cc w/encl: Distribution via Listserv


List of Attendees cc w/encl: Distribution via Listserv 
Attendees Nuclear Regulatory Commission Public Meeting with Tennessee Valley Authority Regarding Browns Ferry Power Uprate February 26, 2009 U. S. NUCLEAR REGULATORY COMMISSION Zena Abdullahi Sher Bahadur Tom Boyce Eva Brown Robert Dennig John N. Flack Daniel Frumkin John Lehning Richard Lobel Tracy Orf Bill Ruland Farideh Saba Ahsan Sallman Steve Smith TENNESSEE VALLEY AUTHORITY Gordon P. Arent James Emens Robert Marks Bertram C. Morris J.D. Wolcott SULZER Steven Schoenbrun Enclosure


Nuclear Regulatory Public Meeting with Tennessee Valley Regarding Browns Ferry Power February 26, U. S. NUCLEAR REGULATORY COMMISSION Zena Abdullahi Sher Bahadur Tom Boyce Eva Brown Robert Dennig John N. Flack Daniel Frumkin John Lehning Richard Lobel Tracy Orf Bill Ruland Farideh Saba Ahsan Sallman Steve Smith TENNESSEE VALLEY AUTHORITY Gordon P. Arent James Emens Robert Marks Bertram C. Morris J.D. Wolcott SULZER Steven Schoenbrun Enclosure 
                                                -2 The Sulzer representative responded to an ACRS staff member's question on how pump testing at a lower temperature can give reliable indication of NPSH at a higher suction temperature.
-2 The Sulzer representative responded to an ACRS staff member's question on how pump testing at a lower temperature can give reliable indication of NPSH at a higher suction temperature.
The representative stated that testing at a lower inlet temperature and using that temperature without correction at the higher inlet temperature is conservative since required NPSH decreases with increased temperature.
The representative stated that testing at a lower inlet temperature and using that temperature without correction at the higher inlet temperature is conservative since required NPSH decreases with increased temperature.
Environmental qualification of containment equipment was briefly discussed.
Environmental qualification of containment equipment was briefly discussed. The licensee stated that all equipment in containment is qualified to 281 degrees Fahrenheit for 100 days.
The licensee stated that all equipment in containment is qualified to 281 degrees Fahrenheit for 100 days. Also, there was a brief discussion regarding the ACRS request for information on how much cavitation of the pump was acceptable.
Also, there was a brief discussion regarding the ACRS request for information on how much cavitation of the pump was acceptable.
No members of the public were in attendance, and no feedback forms were received.
No members of the public were in attendance, and no feedback forms were received. No commitments or regulatory decisions were made by the NRC staff during the meeting.
No commitments or regulatory decisions were made by the NRC staff during the meeting. Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259 and 50-260  
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259 and 50-260


==Enclosure:==
==Enclosure:==
List of Attendees*
List of Attendees*
cc w/encl: Distribution via Listserv ADAMS Accession No.: ML090710705 NRC-001 OFFICE LPLlI-2/PM LPLlI-2/PM LPLlI-2/LA LPLlI-2 NAME TOrf EBrown BClayton TBoyce (FSaba for) DATE 3/19/09 3/19/09 3/19/09 3/23/09 OFFICIAL RECORD COpy Summary of February 26,2009, Meeting with TVA to Discuss Proposed Extended Power Uprate Analyses Revision DISTRIBUTION:
cc w/encl: Distribution via Listserv ADAMS Accession No.: ML090710705                         NRC-001 OFFICE             LPLlI-2/PM     LPLlI-2/PM       LPLlI-2/LA         LPLlI-2 TBoyce NAME             TOrf           EBrown           BClayton (FSaba for)
PUBLIC Lp12-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown Ridsl\lrrPMTOrf RidsNrrPMFSaba RidsNrrLABClayton RidsAcrsAcnw_MailCTR RidsNrrScvb
DATE               3/19/09         3/19/09           3/19/09         3/23/09 OFFICIAL RECORD COpy


RidsNrrDss RLobel, NRRISCVB RidsOgcRp RidsRgn2MailCenter CTucci JAdams, EDO Zena Abdullahi, ACRS John N. Flack, ACRS Sher Bahadur, NRR Daniel Frumkin, NRR John Lehning, NRR Ahsan Sallman, NRR Steve Smith, NRR}}
Summary of February 26,2009, Meeting with TVA to Discuss Proposed Extended Power Uprate Analyses Revision DISTRIBUTION:
PUBLIC Lp12-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown Ridsl\lrrPMTOrf RidsNrrPMFSaba RidsNrrLABClayton RidsAcrsAcnw_MailCTR RidsNrrScvb RidsNrrDss RLobel, NRRISCVB RidsOgcRp RidsRgn2MailCenter CTucci JAdams, EDO Zena Abdullahi, ACRS John N. Flack, ACRS Sher Bahadur, NRR Daniel Frumkin, NRR John Lehning, NRR Ahsan Sallman, NRR Steve Smith, NRR}}

Latest revision as of 03:10, 7 December 2019

Summary of Meeting with Tennessee Valley Authority (TVA) to Discuss Proposed Extended Power Uprate (EPU) Analyses Revision
ML090710705
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 03/23/2009
From: Ellen Brown
Plant Licensing Branch II
To:
Tennessee Valley Authority
Orf, Tracy J.; NRR/DORL 415-2788
Shared Package
ML090710755 List:
References
TAC MD5262, TAC MD5263
Download: ML090710705 (5)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 23, 2009 LICENSEE: Tennessee Valley Authority FACILITIES: Browns Ferry Nuclear Plant, Units 1 and 2

SUBJECT:

SUMMARY

OF FEBRUARY 26,2009, MEETING WITH THE TENNESSEE VALLEY AUTHORITY (TVA) TO DISCUSS PROPOSED EXTENDED POWER UPRATE ANALYSES REVISION (TAC NOS. MD5262 AND MD5263)

On February 26,2009, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 1 pUblic meeting with Tennessee Valley Authority (TVA, the licensee) at NRC Headquarters, 11555 Rockville Pike, One White Flint North, Rockville, Maryland. The purpose of the meeting was to discuss analyses revisions proposed by TVA in support of the extended power uprate amendment request for Browns Ferry Nuclear Plant. Enclosure 1 contains a list of attendees. The licensee presented a slide presentation [see the Agencywide Documents Access and Management System (ADAMS) accession No. ML090710768]. The licensee also presented proposed answers to questions that the Advisory Committee on Reactor Safeguards (ACRS) had posed to the NRC staff (see the ADAMS accession No. ML090710807).

DISCUSSION TVA revised the net positive suction head/containment accident pressure (NPSH/CAP) short term loss-of-coolant accident (LOCA) analyses by reducing the residual heat removal (RHR) pump flow rate into the broken recirculation loop by an excess flow rate value included in previous short-term LOCA NPSH calculations, thereby reducing the required NPSH at 10 minutes into the scenario. The relative humidity was also reduced to a more realistic number that would increase the amount of noncondensible gases in containment during the scenario, which results in an increase in CAP. Additionally, the time-dependent nature of the required NPSH was added to the model. TVA has concluded that these changes would allow the RHR pumps to remain within the vendor's performance curves while performing their functions during a LOCA. On a related note, a representative from the pump vendor Sulzer stated that the commercial pump specifications referenced in the analyses are minimal performance values and that actual performance, as demonstrated by pump tests, would be far better.

There was discussion of the time dependence of the required NPSH and how it is calculated.

The licensee explained that the time dependence of the required NPSH is based on integrated wear over the 8000 hours0.0926 days <br />2.222 hours <br />0.0132 weeks <br />0.00304 months <br />. Since the integrated wear over the 8000 hrs is constant, the ordering of the amount of the wear over time is arbitrary and the shape of the plot of the required NPSH over time as related to wear can be varied.

The staff spoke on attempting to determine the acceptance criteria for Appendix R scenarios requiring CAP. The licensee suggested that it would be helpful if the Boiling Water Reactor Owners Group would generate a standard approach to the issues.

-2 The Sulzer representative responded to an ACRS staff member's question on how pump testing at a lower temperature can give reliable indication of NPSH at a higher suction temperature.

The representative stated that testing at a lower inlet temperature and using that temperature without correction at the higher inlet temperature is conservative since required NPSH decreases with increased temperature.

Environmental qualification of containment equipment was briefly discussed. The licensee stated that all equipment in containment is qualified to 281 degrees Fahrenheit for 100 days.

Also, there was a brief discussion regarding the ACRS request for information on how much cavitation of the pump was acceptable.

No members of the public were in attendance, and no feedback forms were received. No commitments or regulatory decisions were made by the NRC staff during the meeting.

Sincerely, IRA!

Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259 and 50-260

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv

Attendees Nuclear Regulatory Commission Public Meeting with Tennessee Valley Authority Regarding Browns Ferry Power Uprate February 26, 2009 U. S. NUCLEAR REGULATORY COMMISSION Zena Abdullahi Sher Bahadur Tom Boyce Eva Brown Robert Dennig John N. Flack Daniel Frumkin John Lehning Richard Lobel Tracy Orf Bill Ruland Farideh Saba Ahsan Sallman Steve Smith TENNESSEE VALLEY AUTHORITY Gordon P. Arent James Emens Robert Marks Bertram C. Morris J.D. Wolcott SULZER Steven Schoenbrun Enclosure

-2 The Sulzer representative responded to an ACRS staff member's question on how pump testing at a lower temperature can give reliable indication of NPSH at a higher suction temperature.

The representative stated that testing at a lower inlet temperature and using that temperature without correction at the higher inlet temperature is conservative since required NPSH decreases with increased temperature.

Environmental qualification of containment equipment was briefly discussed. The licensee stated that all equipment in containment is qualified to 281 degrees Fahrenheit for 100 days.

Also, there was a brief discussion regarding the ACRS request for information on how much cavitation of the pump was acceptable.

No members of the public were in attendance, and no feedback forms were received. No commitments or regulatory decisions were made by the NRC staff during the meeting.

Sincerely, IRA!

Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259 and 50-260

Enclosure:

List of Attendees*

cc w/encl: Distribution via Listserv ADAMS Accession No.: ML090710705 NRC-001 OFFICE LPLlI-2/PM LPLlI-2/PM LPLlI-2/LA LPLlI-2 TBoyce NAME TOrf EBrown BClayton (FSaba for)

DATE 3/19/09 3/19/09 3/19/09 3/23/09 OFFICIAL RECORD COpy

Summary of February 26,2009, Meeting with TVA to Discuss Proposed Extended Power Uprate Analyses Revision DISTRIBUTION:

PUBLIC Lp12-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMEBrown Ridsl\lrrPMTOrf RidsNrrPMFSaba RidsNrrLABClayton RidsAcrsAcnw_MailCTR RidsNrrScvb RidsNrrDss RLobel, NRRISCVB RidsOgcRp RidsRgn2MailCenter CTucci JAdams, EDO Zena Abdullahi, ACRS John N. Flack, ACRS Sher Bahadur, NRR Daniel Frumkin, NRR John Lehning, NRR Ahsan Sallman, NRR Steve Smith, NRR

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