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| number = ML13199A049
| number = ML13199A049
| issue date = 08/06/2013
| issue date = 08/06/2013
| title = Request for Additional Information for the 2012 Steam Generator Tube Inspections (TAC No. MF0940)
| title = Request for Additional Information for the 2012 Steam Generator Tube Inspections
| author name = Lamb J G
| author name = Lamb J
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name = Walsh K
| addressee name = Walsh K
Line 9: Line 9:
| docket = 05000443
| docket = 05000443
| license number =  
| license number =  
| contact person = Lamb J G
| contact person = Lamb J
| case reference number = TAC MF0940
| case reference number = TAC MF0940
| 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 NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 AUgust 6,2013 Mr. Kevin Walsh, Site Vice President clo Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 SEABROOK STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION FOR THE 2012 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0940)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 AUgust 6,2013 Mr. Kevin Walsh, Site Vice President clo Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 SUB~'ECT:      SEABROOK STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION FOR THE 2012 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0940)


==Dear Mr. Walsh:==
==Dear Mr. Walsh:==
By letter dated December 31,2012 (Agencywide Documents Access and Management System Accession No. ML 13008A160), NextEra Energy Seabrook, LLC, submitted its 2012 Steam Generator Tube Inspections, performed during the 15 th refueling outage. The U.S. Nuclear Regulatory Commission staff has been reviewing the submittal dated December 31,2012, and determined that additional information is necessary to complete its review. The draft questions were sent via electronic transmission on July 17, 2013, to Mr. Michael Ossing, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
On July 23, 2013, Mr. Ossing indicated that the licensee will submit a response within 45 days of the date of this letter The request for additional information is enclosed.
If you have questions, you can contact me at 301-415-31 0 or at John.Lamb@nrc.gov. . Lamb, Senior Proje Manager Licensing Branch 1-2 Di 'sion of Operating Reactor Licensing o ice of Nuclear Reactor Regulation Docket No.
Request for Additional cc wI enclosure:
Distribution via REQUEST FOR ADDITIONAL INFORMATION 2012 STEAM GENERATOR TUBE INSPECTIONS NEXTERA ENERGY SEABROOK.
LLC. SEABROOK STATION, UNIT 1 DOCKET NO. 50-443 By letter dated December 31,2012 (Agencywide Documents Access and Management System Accession No. ML 13008A160), NextEra Energy Seabrook, LLC submitted its 2012 Steam Generator (SG) Tube Inspections, performed during the 15 th refueling outage (RFO) at Seabrook Station, Unit 1 (Seabrook).
The U.S. Nuclear Regulatory Commission staff has determined that the following additional information is necessary to complete its review. REQUEST FOR ADDITIONAL INFORMATION Provide the effective fUll-power years of SG operation for the last three RFOs. In the Seabrook Final Safety Analysis Report (FSAR), the Main Steam Line Break accident (Section 15.1) assumes leakage of 500 gallons per day (gpd) through the faulted SG, and 940 gpd through the remaining three SGs, for a total leakage of 1440 gpd, which is also equal to 1 gallon per minute (gpm). Section 6.7.6.k.b.2.
of the Seabrook Technical Specifications (TSs) states, in part, "[t]he primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed 1 gpm total or 500 gpd through anyone SG." [emphasis added] Section 9.0 of the letter dated December 31,2012, states, in part, "[b]ecause the predicted accident induced leakage from any of the Seabrook SGs is less [than] 1 gpm, the leakage criteria for condition monitoring are met." [emphasis added] Please clarify the sentence in the letter dated December 31, 2012, given the wording in the TSs and FSAR. Please confirm that the Accident Induced Leakage Performance Criteria were met during the prior cycle. Enclosure August 6, 2013 Mr. Kevin Walsh, Site Vice President clo Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 SEABROOK STATION, UNIT 1 -REQUEST FOR ADDITIONAL INFORMATION FOR THE 2012 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0940)


==Dear Mr. Walsh:==
By letter dated December 31,2012 (Agencywide Documents Access and Management System Accession No. ML13008A160), NextEra Energy Seabrook, LLC, submitted its 2012 Steam Generator Tube Inspections, performed during the 15th refueling outage.
By letter dated December 31, 2012 (Agencywide Documents Access and Management System Accession No. ML 13008A 160), NextEra Energy Seabrook, LLC, submitted its 2012 Steam Generator Tube Inspections, performed during the 15 th refueling outage. The U.S. Nuclear Regulatory Commission staff has been reviewing the submittal dated December 31, 2012, and determined that additional information is necessary to complete its review. The draft questions were sent via electronic transmission on July 17, 2013, to Mr. Michael Ossing, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
The U.S. Nuclear Regulatory Commission staff has been reviewing the submittal dated December 31,2012, and determined that additional information is necessary to complete its review. The draft questions were sent via electronic transmission on July 17, 2013, to Mr.
On July 23, 2013, Mr. Ossing indicated that the licensee will submit a response within 45 days of the date of this letter. The request for additional information is enclosed.
Michael Ossing, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On July 23, 2013, Mr. Ossing indicated that the licensee will submit a response within 45 days of the date of this letter The request for additional information is enclosed.
If you have questions, you can contact me at 301-415-3100 or at John.Lamb@nrc.gov.
If you have questions, you can contact me at 301-415-31 0 or at John.Lamb@nrc.gov.
Sincerely, Ira! John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443  
                                                                    ~v
                                                          . Lamb, Senior Proje Manager Licensing Branch 1-2 Di 'sion of Operating Reactor Licensing o  ice of Nuclear Reactor Regulation Docket No. 50-443


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


Request for Additional Infor mation cc wi enclosure:
Request for Additional Information cc wI enclosure: Distribution via ListServ
Distribution via ListServ DISTRIBUTION:
 
PUBLIC LPLI-2 R/F RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resource RidsNrrPMSeabrook Resource RidsNrrLAABaxter Resource RidsAcrsAcnw_MailCTR Resource RidsRgn1 MailCenter Resource KKarwoski, NRR AJohnson, NRR ADAMS Accession No: ML 13199A049
REQUEST FOR ADDITIONAL INFORMATION 2012 STEAM GENERATOR TUBE INSPECTIONS NEXTERA ENERGY SEABROOK. LLC.
**via memo OFFICE LPL 1-2/PM LPL 1-2/LA* ESGB/BC**
SEABROOK STATION, UNIT 1 DOCKET NO. 50-443 By letter dated December 31,2012 (Agencywide Documents Access and Management System Accession No. ML13008A160), NextEra Energy Seabrook, LLC submitted its 2012 Steam Generator (SG) Tube Inspections, performed during the 15th refueling outage (RFO) at Seabrook Station, Unit 1 (Seabrook).
LPL 1-2/BC (A) LPL 1-2/PM NAME JLamb ABaxter GKulesa VRodriguez .ILamb DATE 07103/13 07/31/13 07/16/13 08/06/13 08/06/13 OFFICIAL RECORD}}
The U.S. Nuclear Regulatory Commission staff has determined that the following additional information is necessary to complete its review.
REQUEST FOR ADDITIONAL INFORMATION
: 1.      Provide the effective fUll-power years of SG operation for the last three RFOs.
: 2.      In the Seabrook Final Safety Analysis Report (FSAR), the Main Steam Line Break accident (Section 15.1) assumes leakage of 500 gallons per day (gpd) through the faulted SG, and 940 gpd through the remaining three SGs, for a total leakage of 1440 gpd, which is also equal to 1 gallon per minute (gpm).
Section 6.7.6.k.b.2. of the Seabrook Technical Specifications (TSs) states, in part, "[t]he primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG.
Leakage is not to exceed 1 gpm total or 500 gpd through anyone SG." [emphasis added]
Section 9.0 of the letter dated December 31,2012, states, in part, "[b]ecause the predicted accident induced leakage from any of the Seabrook SGs is less [than] 1 gpm, the leakage criteria for condition monitoring are met." [emphasis added]
: a.      Please clarify the sentence in the letter dated December 31, 2012, given the wording in the TSs and FSAR. Please confirm that the Accident Induced Leakage Performance Criteria were met during the prior cycle.
Enclosure
 
ML13199A049                                          **via memo OFFICE       LPL1-2/PM   LPL 1-2/LA*         ESGB/BC**         LPL 1-2/BC (A)     LPL 1-2/PM NAME         JLamb       ABaxter             GKulesa           VRodriguez       .ILamb DATE         07103/13   07/31/13             07/16/13           08/06/13         08/06/13}}

Latest revision as of 15:51, 4 November 2019

Request for Additional Information for the 2012 Steam Generator Tube Inspections
ML13199A049
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 08/06/2013
From: John Lamb
Plant Licensing Branch 1
To: Walsh K
NextEra Energy Seabrook
Lamb J
References
TAC MF0940
Download: ML13199A049 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 AUgust 6,2013 Mr. Kevin Walsh, Site Vice President clo Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874 SUB~'ECT: SEABROOK STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION FOR THE 2012 STEAM GENERATOR TUBE INSPECTIONS (TAC NO. MF0940)

Dear Mr. Walsh:

By letter dated December 31,2012 (Agencywide Documents Access and Management System Accession No. ML13008A160), NextEra Energy Seabrook, LLC, submitted its 2012 Steam Generator Tube Inspections, performed during the 15th refueling outage.

The U.S. Nuclear Regulatory Commission staff has been reviewing the submittal dated December 31,2012, and determined that additional information is necessary to complete its review. The draft questions were sent via electronic transmission on July 17, 2013, to Mr.

Michael Ossing, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. On July 23, 2013, Mr. Ossing indicated that the licensee will submit a response within 45 days of the date of this letter The request for additional information is enclosed.

If you have questions, you can contact me at 301-415-31 0 or at John.Lamb@nrc.gov.

~v

. Lamb, Senior Proje Manager Licensing Branch 1-2 Di 'sion of Operating Reactor Licensing o ice of Nuclear Reactor Regulation Docket No. 50-443

Enclosure:

Request for Additional Information cc wI enclosure: Distribution via ListServ

REQUEST FOR ADDITIONAL INFORMATION 2012 STEAM GENERATOR TUBE INSPECTIONS NEXTERA ENERGY SEABROOK. LLC.

SEABROOK STATION, UNIT 1 DOCKET NO. 50-443 By letter dated December 31,2012 (Agencywide Documents Access and Management System Accession No. ML13008A160), NextEra Energy Seabrook, LLC submitted its 2012 Steam Generator (SG) Tube Inspections, performed during the 15th refueling outage (RFO) at Seabrook Station, Unit 1 (Seabrook).

The U.S. Nuclear Regulatory Commission staff has determined that the following additional information is necessary to complete its review.

REQUEST FOR ADDITIONAL INFORMATION

1. Provide the effective fUll-power years of SG operation for the last three RFOs.
2. In the Seabrook Final Safety Analysis Report (FSAR), the Main Steam Line Break accident (Section 15.1) assumes leakage of 500 gallons per day (gpd) through the faulted SG, and 940 gpd through the remaining three SGs, for a total leakage of 1440 gpd, which is also equal to 1 gallon per minute (gpm).

Section 6.7.6.k.b.2. of the Seabrook Technical Specifications (TSs) states, in part, "[t]he primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG.

Leakage is not to exceed 1 gpm total or 500 gpd through anyone SG." [emphasis added]

Section 9.0 of the letter dated December 31,2012, states, in part, "[b]ecause the predicted accident induced leakage from any of the Seabrook SGs is less [than] 1 gpm, the leakage criteria for condition monitoring are met." [emphasis added]

a. Please clarify the sentence in the letter dated December 31, 2012, given the wording in the TSs and FSAR. Please confirm that the Accident Induced Leakage Performance Criteria were met during the prior cycle.

Enclosure

ML13199A049 **via memo OFFICE LPL1-2/PM LPL 1-2/LA* ESGB/BC** LPL 1-2/BC (A) LPL 1-2/PM NAME JLamb ABaxter GKulesa VRodriguez .ILamb DATE 07103/13 07/31/13 07/16/13 08/06/13 08/06/13

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