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{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 13, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LASALLE COUNTY STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF NO. CR-26 (TAC NOS. MD9817 AND MD9818)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 13, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB~IECT:        LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF NO. CR-26 (TAC NOS. MD9817 AND MD9818)


==Dear Mr. Pardee:==
==Dear Mr. Pardee:==
By letter to the Nuclear Regulatory Commission (NRC) dated October 1, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082760276), Exelon Generation Company, LLC (the licensee), submitted a request for its second 10-year interval inservice inspection program plan Request for Relief No. CR-26, for the LaSalle County Station (LSCS), Units 1 and 2. The LSCS has requested  
 
!\IRC approval of relief from existing American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plants Components," requirements on the basis that compliance with the specified requirements was impractical due to plant design. The LSCS also provided supplemental information in letters dated November 18, 2008 (ADAMS Accession No. ML083260525), and May 26, 2009 (ADAMS Accession No. ML091540385).
By letter to the Nuclear Regulatory Commission (NRC) dated October 1, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082760276), Exelon Generation Company, LLC (the licensee), submitted a request for its second 10-year interval inservice inspection program plan Request for Relief No. CR-26, for the LaSalle County Station (LSCS), Units 1 and 2. The LSCS has requested !\IRC approval of relief from existing American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plants Components," requirements on the basis that compliance with the specified requirements was impractical due to plant design.
The NRC staff is reviewing your submittal and the supplemental information, and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. In an e-mail with your staff on July 27, 2009, it was agreed that you would provide a response 30 days from the date of this letter. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of C. Pardee -2 efficient and effective use of staff resources.
The LSCS also provided supplemental information in letters dated November 18, 2008 (ADAMS Accession No. ML083260525), and May 26, 2009 (ADAMS Accession No. ML091540385).
If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3719.
The NRC staff is reviewing your submittal and the supplemental information, and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. In an e-mail with your staff on July 27, 2009, it was agreed that you would provide a response 30 days from the date of this letter.
Sincerely, Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL LASALLE COUNTY STATION (LSCS), UNITS 1 AND DOCKET NOS. 50-373 AND The American Society of Mechanical Engineers (ASME) Code of record for LSCS, Units 1 and 2, second 1 O-year interval inservice inspection program is the 1989 Edition of the ASME Code, Section XI with no Addenda. The staff requires further information to complete its assessment of Request for Relief CR-26. 1 Provide further information to adequately demonstrate the impracticality associated with Weld RH-HX1 B-1 on Residual Heat Removal Heat Exchanger 1 B. Include sketches or drawings as necessary, to show coverage obtained and describe the materials and the ultrasonic techniques applied. 2 State whether the ASME Code surface examination was completed on the subject weld. If the examinations were performed, what were the results of the examinations?
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of
 
C. Pardee                                   -2 efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3719.
Sincerely, Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
 
==Enclosure:==
 
Request for Additional Information cc w/encl: Distribution via ListServ
 
REQUEST FOR ADDITIONAL INFORMATION LASALLE COUNTY STATION (LSCS), UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 The American Society of Mechanical Engineers (ASME) Code of record for LSCS, Units 1 and 2, second 1O-year interval inservice inspection program is the 1989 Edition of the ASME Code, Section XI with no Addenda. The staff requires further information to complete its assessment of Request for Relief CR-26.
1     Provide further information to adequately demonstrate the impracticality associated with Weld RH-HX1 B-1 on Residual Heat Removal Heat Exchanger 1B. Include sketches or drawings as necessary, to show coverage obtained and describe the materials and the ultrasonic techniques applied.
2     State whether the ASME Code surface examination was completed on the subject weld.
If the examinations were performed, what were the results of the examinations?
: 3. Address whether or not additional coverage of the subject weld could have been achieved if advanced inspection technologies (e.g., phased array ultrasonic transducers) had been applied.
: 3. Address whether or not additional coverage of the subject weld could have been achieved if advanced inspection technologies (e.g., phased array ultrasonic transducers) had been applied.
C.Pardee -2 efficient and effective use of staff resources.
 
If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3719.
C. Pardee                                   -2 efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3719.
Sincerely, IRA! Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and Request for Additional cc w/encl: Distribution via DISTRIBUTION:
Sincerely, IRA!
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 Resource Ridsl\lrrDorlDpr Resource RidsNrrPMLaSalie Resource RidsNrrLATHarris Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR Resource ADAMS A . N ML092190390 NRR 088 *S ee prevIous c oncurrence ccesslon o. OFFICE LPL3-2/PM*
Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374
LPL3-2/LA*
 
LPL3-2/PM LPL3-2/BC NAME SSands THarris CGoodwin SCampbell DATE 08/10/09 08/12/09 08/13/09 08/13/09 OFFICIAL RECORD}}
==Enclosure:==
 
Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC                 LPL3-2 R/F     RidsNrrDorlLpl3-2 Resource Ridsl\lrrDorlDpr Resource RidsNrrPMLaSalie Resource               RidsNrrLATHarris Resource RidsOgcRp Resource RidsRgn3MailCenter Resource             RidsAcrsAcnw_MailCTR Resource ADAMS A ccesslon  . No. ML092190390           NRR 088       *See prevIous concurrence LPL3-2/PM       LPL3-2/BC OFFICE LPL3-2/PM*          LPL3-2/LA*
NAME                       THarris         CGoodwin       SCampbell SSands 08/13/09       08/13/09 DATE        08/10/09       08/12/09 OFFICIAL RECORD COPY}}

Latest revision as of 04:25, 14 November 2019

Request for Additional Information Related to Request for Relief No. CR-26
ML092190390
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/13/2009
From: Goodwin C
Plant Licensing Branch III
To: Pardee C
Exelon Generation Co, Exelon Nuclear
Goodwin, Cameron S, NRR/DORL, 415-3719
References
TAC MD9817, TAC MD9818
Download: ML092190390 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 13, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB~IECT: LASALLE COUNTY STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF NO. CR-26 (TAC NOS. MD9817 AND MD9818)

Dear Mr. Pardee:

By letter to the Nuclear Regulatory Commission (NRC) dated October 1, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082760276), Exelon Generation Company, LLC (the licensee), submitted a request for its second 10-year interval inservice inspection program plan Request for Relief No. CR-26, for the LaSalle County Station (LSCS), Units 1 and 2. The LSCS has requested !\IRC approval of relief from existing American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plants Components," requirements on the basis that compliance with the specified requirements was impractical due to plant design.

The LSCS also provided supplemental information in letters dated November 18, 2008 (ADAMS Accession No. ML083260525), and May 26, 2009 (ADAMS Accession No. ML091540385).

The NRC staff is reviewing your submittal and the supplemental information, and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. In an e-mail with your staff on July 27, 2009, it was agreed that you would provide a response 30 days from the date of this letter.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of

C. Pardee -2 efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3719.

Sincerely, Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ

REQUEST FOR ADDITIONAL INFORMATION LASALLE COUNTY STATION (LSCS), UNITS 1 AND 2 DOCKET NOS. 50-373 AND 50-374 The American Society of Mechanical Engineers (ASME) Code of record for LSCS, Units 1 and 2, second 1O-year interval inservice inspection program is the 1989 Edition of the ASME Code,Section XI with no Addenda. The staff requires further information to complete its assessment of Request for Relief CR-26.

1 Provide further information to adequately demonstrate the impracticality associated with Weld RH-HX1 B-1 on Residual Heat Removal Heat Exchanger 1B. Include sketches or drawings as necessary, to show coverage obtained and describe the materials and the ultrasonic techniques applied.

2 State whether the ASME Code surface examination was completed on the subject weld.

If the examinations were performed, what were the results of the examinations?

3. Address whether or not additional coverage of the subject weld could have been achieved if advanced inspection technologies (e.g., phased array ultrasonic transducers) had been applied.

C. Pardee -2 efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3719.

Sincerely, IRA!

Cameron S. Goodwin, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-374

Enclosure:

Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:

PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 Resource Ridsl\lrrDorlDpr Resource RidsNrrPMLaSalie Resource RidsNrrLATHarris Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR Resource ADAMS A ccesslon . No. ML092190390 NRR 088 *See prevIous concurrence LPL3-2/PM LPL3-2/BC OFFICE LPL3-2/PM* LPL3-2/LA*

NAME THarris CGoodwin SCampbell SSands 08/13/09 08/13/09 DATE 08/10/09 08/12/09 OFFICIAL RECORD COPY

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