ML13170A477: Difference between revisions

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| issue date = 06/26/2013
| issue date = 06/26/2013
| title = Millstone Power Station, Unit Nos. 2 and 3 - Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Request (TAC Nos. MF1779 and MF1780)
| title = Millstone Power Station, Unit Nos. 2 and 3 - Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Request (TAC Nos. MF1779 and MF1780)
| author name = Morgan N S
| author name = Morgan N
| author affiliation = NRC/NRR/DORL/LPLI-1
| author affiliation = NRC/NRR/DORL/LPLI-1
| addressee name = Heacock D A
| addressee name = Heacock D
| addressee affiliation = Dominion Nuclear Connecticut, Inc
| addressee affiliation = Dominion Nuclear Connecticut, Inc
| docket = 05000336, 05000423
| docket = 05000336, 05000423
| license number =  
| license number =  
| contact person = Morgan N S
| contact person = Morgan N
| case reference number = TAC MF1779, TAC MF1780
| case reference number = TAC MF1779, TAC MF1780
| document type = Letter
| document type = Letter
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 26,2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 -ACCEPTANCE REVIEW RESULTS REGARDING ULTIMATE HEAT SINK LICENSE AMENDMENT REQUEST (TAC NOS. MF1779 AND MF1780)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 26,2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
 
==SUBJECT:==
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 - ACCEPTANCE REVIEW RESULTS REGARDING ULTIMATE HEAT SINK LICENSE AMENDMENT REQUEST (TAC NOS. MF1779 AND MF1780)


==Dear Mr. Heacock:==
==Dear Mr. Heacock:==
By letter dated May 3,2013, Dominion Nuclear Connecticut, Inc., the licensee, submitted a license amendment request (LAR) to increase the current ultimate heat sink water temperature limit from 75 degrees Fahrenheit to 80 degrees Fahrenheit for Millstone Power Station, Unit Nos. 2 and 3 (Millstone).
 
The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license, including the technical specifications, must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications.
By letter dated May 3,2013, Dominion Nuclear Connecticut, Inc., the licensee, submitted a license amendment request (LAR) to increase the current ultimate heat sink water temperature limit from 75 degrees Fahrenheit to 80 degrees Fahrenheit for Millstone Power Station, Unit Nos. 2 and 3 (Millstone). The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Section 50.34 of 10 CFR addresses the content of technical information required.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license, including the technical specifications, must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the application address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
This section stipulates that the application address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by July 3, 2013. This will enable the NRC staff to complete its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application.
In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by July 3, 2013. This will enable the NRC staff to complete its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter was discussed with Bill Bartron of your staff on June 20, 2013.
The information requested and associated time frame in this letter was discussed with Bill Bartron of your staff on June 20, 2013.
D. Heacock -2 If you have any questions regarding this issue, please contact me at (301)  
 
/ /7/ . / ! // ..,-'/,/ Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423  
D. Heacock                                       -2 If you have any questions regarding this issue, please contact me at (301) 415-1016.
Sincer~y,
                                              / /7
                                          /   . /   !   /
                                      / ,/ ./
Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423


==Enclosure:==
==Enclosure:==
As stated cc w/encl: Distribution via Listserv


As stated cc w/encl: Distribution via Listserv SUPPLEMENTAL REGARDING ULTIMATE HEAT LICENSE AMENDMENT DOMINION NUCLEAR CONNECTICUT, MILLSTONE POWER STATION, UNIT NOS. 2 AND DOCKET NOS. 50-336 AND By letter dated May 3, 2013 (Agencywide Documents Access and Management Systems Accession No. ML 13133A032 and ML 13133A033), Dominion Nuclear Connecticut, Inc. submitted a license amendment request to increase the current ultimate heat sink water temperature limit from 75 degrees Fahrenheit CF) to 80 OF for Millstone Power Station, Unit Nos. 2 and 3. In order to complete its acceptance review, the Nuclear Regulatory Commission staff needs the following additional information: Please provide the following information for each safety related heat exchanger cooled by service water: 1. Design heat load 2. Design fouling factor 3. As-tested fouling factor 4. Tube plug allowance  
SUPPLEMENTAL INFORMATION REGARDING ULTIMATE HEAT SINK LICENSE AMENDMENT REQUEST DOMINION NUCLEAR CONNECTICUT, INC.
: 5. Actual number of plugged tubes 6. Calculated heat removal capability  
MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 DOCKET NOS. 50-336 AND 50-423 By letter dated May 3, 2013 (Agencywide Documents Access and Management Systems Accession No. ML13133A032 and ML13133A033), Dominion Nuclear Connecticut, Inc.
: 7. Design minimum flow rate 8. Actual flow rate 9. Vendor supplied heat exchanger specification sheet 10. Description of Generic Letter 89-13 testing/cleaning program for each heat exchanger Provide an 18" x 24" piping and instrumentation diagram of the service water system. Please state whether or not the increase in service water temperature from 75 OF to 80 OF will result in a derating of the emergency diesel generators.
submitted a license amendment request to increase the current ultimate heat sink water temperature limit from 75 degrees Fahrenheit CF) to 80 OF for Millstone Power Station, Unit Nos. 2 and 3. In order to complete its acceptance review, the Nuclear Regulatory Commission staff needs the following additional information:
Enclosure D. Heacock -2 If you have any questions regarding this issue, please contact me at (301) 415-1016.
A)      Please provide the following information for each safety related heat exchanger cooled by service water:
Sincerely, Ira! Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423  
: 1. Design heat load
: 2. Design fouling factor
: 3. As-tested fouling factor
: 4. Tube plug allowance
: 5. Actual number of plugged tubes
: 6. Calculated heat removal capability
: 7. Design minimum flow rate
: 8. Actual flow rate
: 9. Vendor supplied heat exchanger specification sheet
: 10. Description of Generic Letter 89-13 testing/cleaning program for each heat exchanger B)      Provide an 18" x 24" piping and instrumentation diagram of the service water system.
C)      Please state whether or not the increase in service water temperature from 75 OF to 80 OF will result in a derating of the emergency diesel generators.
Enclosure
 
D. Heacock                                       -2 If you have any questions regarding this issue, please contact me at (301) 415-1016.
Sincerely, Ira!
Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423


==Enclosure:==
==Enclosure:==
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsN rrDorlLpl1-1 RidsNrrPM Millstone LPL 1-1 RtF RidsNrrLAKGoldstein RidsAcrsAcnw_MailCTR RidsNrrDorlDpr RidsRgn1 MailCenter GPurciarello, NRR RidsOGCMailCenter RidsNrrDssSbpb RWolfgang, NRR RisNrrDeEpnb PSahay. NRR RidsNrrDeEeeb GCooper, NRR RidsNrrDraAfpb BTitus. NRR MHamm, NRR RidsNrrDssStsb KBucholtz.
PUBLIC                       RidsN rrDorlLpl1-1           RidsNrrPM Millstone LPL1-1 RtF                   RidsNrrLAKGoldstein         RidsAcrsAcnw_MailCTR RidsNrrDorlDpr               RidsRgn1 MailCenter         GPurciarello, NRR RidsOGCMailCenter           RidsNrrDssSbpb               RWolfgang, NRR RisNrrDeEpnb                 PSahay. NRR                 RidsNrrDeEeeb GCooper, NRR                 RidsNrrDraAfpb               BTitus. NRR MHamm, NRR                   RidsNrrDssStsb               KBucholtz. NRR ADAMS Accession No.: ML13170A477                         *See email dated June 13, 2013 I'OFFICE     LPLI-1IPM           LPLI-1/LA         DSS/SBPB/BC             LPLI*1/BC
NRR ADAMS Accession No.: ML13170A477  
, NAME       NMorgan             KGoldstein        GCasto                   RBeall (A)
*See email dated June 13, 2013 I'OFFICE LPLI-1IPM LPLI-1/LA DSS/SBPB/BC LPLI*1/BC , NAME NMorgan KG old stein GCasto RBeall (A) DATE 6/25/13 6/21/13 6/13/2013*
DATE       6/25/13             6/21/13           6/13/2013*               6/26/13 OFFICIAL RECORD COpy}}
6/26/13 OFFICIAL RECORD COpy}}

Latest revision as of 04:45, 6 February 2020

Millstone Power Station, Unit Nos. 2 and 3 - Acceptance Review Results Regarding Ultimate Heat Sink License Amendment Request (TAC Nos. MF1779 and MF1780)
ML13170A477
Person / Time
Site: Millstone  Dominion icon.png
Issue date: 06/26/2013
From: Nadiyah Morgan
Plant Licensing Branch 1
To: Heacock D
Dominion Nuclear Connecticut
Morgan N
References
TAC MF1779, TAC MF1780
Download: ML13170A477 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 26,2013 Mr. David A. Heacock President and Chief Nuclear Officer Dominion Nuclear Connecticut, Inc.

Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 - ACCEPTANCE REVIEW RESULTS REGARDING ULTIMATE HEAT SINK LICENSE AMENDMENT REQUEST (TAC NOS. MF1779 AND MF1780)

Dear Mr. Heacock:

By letter dated May 3,2013, Dominion Nuclear Connecticut, Inc., the licensee, submitted a license amendment request (LAR) to increase the current ultimate heat sink water temperature limit from 75 degrees Fahrenheit to 80 degrees Fahrenheit for Millstone Power Station, Unit Nos. 2 and 3 (Millstone). The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license, including the technical specifications, must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.

This section stipulates that the application address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by July 3, 2013. This will enable the NRC staff to complete its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC staff will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

The information requested and associated time frame in this letter was discussed with Bill Bartron of your staff on June 20, 2013.

D. Heacock -2 If you have any questions regarding this issue, please contact me at (301) 415-1016.

Sincer~y,

/ /7

/ . /  ! /

/ ,/ ./

Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423

Enclosure:

As stated cc w/encl: Distribution via Listserv

SUPPLEMENTAL INFORMATION REGARDING ULTIMATE HEAT SINK LICENSE AMENDMENT REQUEST DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION, UNIT NOS. 2 AND 3 DOCKET NOS. 50-336 AND 50-423 By letter dated May 3, 2013 (Agencywide Documents Access and Management Systems Accession No. ML13133A032 and ML13133A033), Dominion Nuclear Connecticut, Inc.

submitted a license amendment request to increase the current ultimate heat sink water temperature limit from 75 degrees Fahrenheit CF) to 80 OF for Millstone Power Station, Unit Nos. 2 and 3. In order to complete its acceptance review, the Nuclear Regulatory Commission staff needs the following additional information:

A) Please provide the following information for each safety related heat exchanger cooled by service water:

1. Design heat load
2. Design fouling factor
3. As-tested fouling factor
4. Tube plug allowance
5. Actual number of plugged tubes
6. Calculated heat removal capability
7. Design minimum flow rate
8. Actual flow rate
9. Vendor supplied heat exchanger specification sheet
10. Description of Generic Letter 89-13 testing/cleaning program for each heat exchanger B) Provide an 18" x 24" piping and instrumentation diagram of the service water system.

C) Please state whether or not the increase in service water temperature from 75 OF to 80 OF will result in a derating of the emergency diesel generators.

Enclosure

D. Heacock -2 If you have any questions regarding this issue, please contact me at (301) 415-1016.

Sincerely, Ira!

Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-336 and 50-423

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsN rrDorlLpl1-1 RidsNrrPM Millstone LPL1-1 RtF RidsNrrLAKGoldstein RidsAcrsAcnw_MailCTR RidsNrrDorlDpr RidsRgn1 MailCenter GPurciarello, NRR RidsOGCMailCenter RidsNrrDssSbpb RWolfgang, NRR RisNrrDeEpnb PSahay. NRR RidsNrrDeEeeb GCooper, NRR RidsNrrDraAfpb BTitus. NRR MHamm, NRR RidsNrrDssStsb KBucholtz. NRR ADAMS Accession No.: ML13170A477 *See email dated June 13, 2013 I'OFFICE LPLI-1IPM LPLI-1/LA DSS/SBPB/BC LPLI*1/BC

, NAME NMorgan KGoldstein GCasto RBeall (A)

DATE 6/25/13 6/21/13 6/13/2013* 6/26/13 OFFICIAL RECORD COpy