ML11294A104

From kanterella
Jump to navigation Jump to search
2/3/11, Summary of Telecon Call Held Between USNRC and NextEra Seabrook, Llc. Concerning Request for Additional Information Pertaining to the Seabrook Station LRA
ML11294A104
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 11/01/2011
From: Plasse R
License Renewal Projects Branch 1
To:
Plasse R
References
Download: ML11294A104 (7)


Text

\.~,..!\ RfGI.J<.q UNITED STATES

~",Ci r~ NUCLEAR REGULATORY COMMISSION

! ~ WASHINGTON, D.C. 20555-0001

<t

~

ca.

0 p; November 1, 2011

~ ~

"'" ~o LICENSEE: NextEra Energy Seabrook, LLC FACILITY: Seabrook Station

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 03, 2011, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NEXTERA ENERGY SEABROOK, LLC, CONCERNING REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE SEABROOK STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4028)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of NextEra Energy Seabrook, LLC (NextEra or the applicant), held a telephone conference call on February 03, 2011, to discuss and clarify the staff's draft request for additional information (RAI) concerning the Seabrook Station license renewal application. The telephone conference call was useful in clarifying the intent of the staff's RAls.

Enclosure 1 provides a listing of the participants and Enclosure 2 contains a listing of the draft RAls that were discussed with the applicant, including a brief description on the status of the item. In addition RAI 3.4.2.2.2, issued by the staff on January 21,2011, was discussed with the applicant and is documented in Enclosure 2.

The applicant had an opportunity to comment on this summary.

RiC~rOject Projects Branch 1 Manager Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosures:

As stated cc w/encls: Listserv

TELEPHONE CONFERENCE CALL SEABROOK STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS February 03, 2011 PARTICIPANTS AFFILIATIONS Richard Plasse U.S. Nuclear Regulatory Commission (NRC)

William Holston NRC Jim Gavula NRC John Wise NRC Richard Cliche NextEra Energy Seabrook, LLC. (NextEra)

Ali Kodal NextEra Bill Roberts NextEra Paul Willoughby NextEra ENCLOSURE 1

TELEPHONE CONFERENCE CALL SEABROOK STATION LICENSE RENEWAL APPLICATION Draft RAI 3.2.2.2.4.2-1

Background:

The Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR) Section 3.2.2.2.4, item 2, is associated with SRP-LR Table 3.2.1, item 3.2.1-10 and states that reduction of heat transfer due to fouling could occur for stainless steel heat exchanger tubes exposed to treated water. The SRP-LR also states that the existing program relies on control of water chemistry to manage reduction of heat transfer due to fouling but that since control of water chemistry may have been inadequate, the effectiveness of the chemistry control program should be verified to ensure that reduction of heat transfer due to fouling is not occurring. SRP-LR Table 3.2.1, item 3.2.1-10 states that it applies to both boiling water reactors (BWRs) and pressurized water reactors (PWRs), and cites related item EP-34, which corresponds to the Generic Aging Lessons Learned (GALL) items V.A-16 for PWR containment spray system heat exchanger tubes and V.D2-13 for BWR emergency core cooling system heat exchanger tubes. Although the SRP-LR and the GALL Report list the environment as treated water, the basis for including GALL item EP-34, as documented in NUREG-1833, was a precedent established in the R.E. Ginna Nuclear Power Plant (Ginna) safety evaluation report (SER), NUREG-1786. The environment specifically noted in the Ginna SER was'1reated water borated," and as such, the applicable environment for this item is not strictly limited to treated water, and also includes treated borated water.

License renewal application (LRA) Section 3.2.2.2.4, item 2 states that item 3.2.1-10 is not applicable to Seabrook, and that there are no stainless steel heat exchanger tubes exposed to treated water in the emergency safeguard feature systems. However, the staff noted that LRA Section 3.2 includes several systems with heat exchanger tubes exposed to treated borated water with an intended function of heat transfer that do not indicate that reduction in heat transfer due to fouling is an aging effect being managed.

Issue:

It is not clear to the staff why LRA Section 3.2.2.2.4, item 2 and LRA Table 3.2.1, item 3.2.1-10 state that this item is not applicable, given that NUREG-1833 states that the item is applicable to both BWR and PWR heat exchanger tubes exposed to treated water and treated borated water.

It is also not clear to the staff why several heat exchanger items in LRA Section 3.2 specify an intended function of heat transfer, but do not indicate that reduction in heat transfer due to fouling is an aging effect being managed.

Request:

1) Provide the technical bases for the determination that LRA Section 3.2.2.2.4, item 2, which is associated with LRA Table 3.2.1 item 3.2.1-10, is not applicable to Seabrook. If it is determined to be applicable, provide the information regarding how Seabrook intends to meet the further evaluation criteria specified in the corresponding SRP-LR section.

ENCLOSURE 2

2

2) For the line items in LRA Section 3.2 which have an intended function specified as "heat transfer," provide the technical bases for not managing reduction in heat transfer due to fouling as an aging effect.

Discussion: Following discussion of the draft request for additional information, the applicant stated that they understood what was being requested and would be able to respond.

Draft RAI 3.3.2.2.2-1

Background:

SRP-LR Section 3.3.2.2.2 is associated with SRP-LR Table 3.3.1, item 3.3.1-3 and states that reduction of heat transfer due to fouling could occur for stainless steel heat exchanger tubes exposed to treated water. The SRP-LR also states that the existing program relies on control of water chemistry to manage reduction of heat transfer due to fouling but that since control of water chemistry may have been inadequate, the effectiveness of the chemistry control program should be verified to ensure that reduction of heat transfer due to fouling is not occurring.

SRP-LR Table 3.3.1, item 3.3.1-3 states that this item applies to BWRs and PWRs, and cites related item AP-62, which corresponds to GALL items VII.A4-4 for BWR spent fuel pool cooling and cleanup heat exchanger tubes and VII.E3-6 for reactor water cleanup system heat exchanger tubes. Although the SRP-LR and the GALL Report list the environment as treated water, the basis for including GALL item AP-62, as documented in NUREG-1833, was a precedent established in the RE. Ginna SER, NUREG-1786. The environment specifically noted in the Ginna SER was "treated water - borated," and as such, the applicable environment for this item is not strictly limited to treated water, and also includes treated borated water.

LRA Section 3.3.2.2.2 states that item 3.3.1-3 is not applicable for auxiliary system components at Seabrook, and that this line item is associated with GALL Report item, VIIE3-6 which is applicable to BWR reactor water cleanup system heat exchangers. However, the staff noted that LRA Section 3.3 includes several systems with heat exchanger tubes exposed to treated borated water with an intended function of "heat transfer," that do not indicate that reduction of heat transfer due to fouling is an aging effect being managed.

Issue:

It is not clear to the staff why LRA Section 3.3.2.2.2, which is associated with SRP-LR Table 3.3.1 item 3.3.1-3, states that this item is not applicable, given that NUREG-1833 states that the item is applicable to both BWR and PWR heat exchanger tubes exposed to treated water and treated borated water. It is also not clear to the staff why several heat exchanger items in LRA Section 3.3 specify an intended function of "heat transfer," but do not indicate that reduction in heat transfer due to fouling is an aging effect being managed.

Request:

1) Provide the technical bases for the determination that LRA Section 3.3.2.2.2, which is associated with LRA Table 3.3.1 item 3.3.1-3, is not applicable to Seabrook. If it is determined to be applicable, provide information regarding how Seabrook intends to meet the further evaluation criteria specified in the corresponding SRP-LR section.

3

2) For the line items in LRA Section 3.3 which have an intended function specified as "heat transfer," provide the technical bases for not managing reduction in heat transfer due to fouling as an aging effect.

Discussion: Following discussion of the draft RAI, the applicant stated that they understood what was being requested and would be able to respond.

RAI 3.4.2.2-2 By letter dated January 21, 2011, the staff issued RAI 3.4.2.2-2 concerning site use of potable water from the town of Seabrook. Following discussion of the RAI, the applicant stated that they understood what was being requested and would be able to respond.

November 1, 2011 LICENSEE: NextEra Energy Seabrook, LLC FACILITY: Seabrook Station

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 03, 2011, BElWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NEXTERA ENERGY SEABROOK, LLC, CONCERNING REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE SEABROOK STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4028)

The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of NextEra Energy Seabrook, LLC (NextEra or the applicant), held a telephone conference call on February 03, 2011, to discuss and clarify the staffs draft request for additional information (RAI) concerning the Seabrook Station license renewal application. The telephone conference call was useful in clarifying the intent of the staffs RAls. provides a listing of the participants and Enclosure 2 contains a listing of the draft RAls that were discussed with the applicant, including a brief description on the status of the item. In addition RAI 3.4.2.2.2, issued by the staff on January 21,2011, was discussed with the applicant and is documented in Enclosure 2.

The applicant had an opportunity to comment on this summary.

IRA!

Richard Plasse, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-443

Enclosures:

As stated cc w/encls: Listserv DISTRIBUTION:

See next page ADAMS Accession No'.. ML11294A104 OFFICE LA:DLR* PM:RPB1:DLR BC:RPB1 :DLR PM:RPB1 :DLR NAME SFigueroa RPlasse DMorey RPlasse DATE 10/21/2011 10/24/2011 10/31/2011 11/112011 OFFICIAL RECORD COpy

Memorandum to NextEra Energy Seabrook, LLC from R. Plasse dated November 1, 2011

SUBJECT:

SUMMARY

OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 03, 2011, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND NEXTERA ENERGY SEABROOK, LLC, CONCERNING THE DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE SEABROOK STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4028)

DISTRIBUTION:

HARD COPY:

DLR RF E-MAIL:

PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource MWentzel RPlasse DMorey DWrona EMilier ICouret,OPA EDacus,OCA MSpencer,OGC WRaymond, RI DT ifft , RI NMcNamara, RI NSheehan, RI DScrenci, RI JJohnson, RI ABurritt, RI