ML15219A016: Difference between revisions
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION . WASHINGTON, D.C. 20555-0001 August 13, 2015 Mr. Edward D. Halpin Senior Vice President and Chief Nuclear Officer Pacific Gas and Ei'ectric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 | ||
. WASHINGTON, D.C. 20555-0001 August 13, 2015 Mr. Edward D. Halpin Senior Vice President and Chief Nuclear Officer Pacific Gas and Ei'ectric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424 | |||
==SUBJECT:== | ==SUBJECT:== | ||
DIABLO CANYON POWER PLANT, UNIT NOS. 1 AND 2 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVIEW OF ALTERNATIVE SOURCE TERM LICENSE AMEN.DMENT REQUEST (TAC NOS. MF6399 AND MF6400) | DIABLO CANYON POWER PLANT, UNIT NOS. 1 AND 2 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVIEW OF ALTERNATIVE SOURCE TERM LICENSE AMEN.DMENT REQUEST (TAC NOS. MF6399 AND MF6400) | ||
==Dear Mr. Halpin:== | ==Dear Mr. Halpin:== | ||
By letter dated June 17, 2015 (Agencywide Documents Access and Management System Accession No. ML 15176A539), | By letter dated June 17, 2015 (Agencywide Documents Access and Management System Accession No. ML 15176A539), Pacific Gas and Electric Company (PG&E, the licensee) submitted a license amendment request (LAR) for Diablo Canyon Power Plant (DCPP), Unit Nos. 1 and 2. The proposed amendment would revise the licensing bases of DCPP, Unit Nos. 1 and 2 to adopt the alternative source term (AST) as allowed by Title 10 of the Code of Federal Regulations, Part 50, Section 50.67, "Accident source term." The AST methodology as established in U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.183, "Alternative Radi9logical Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," July 2000 (ADAMS Accession No. ML003716792), is used to calculate the offsite and control room radiological consequence for DCPP, Unit Nos. 1 and 2. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request. 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 10 CFR 50.90, 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. | ||
Pacific Gas and Electric Company (PG&E, the licensee) submitted a license amendment request (LAR) for Diablo Canyon Power Plant (DCPP), Unit Nos. 1 and 2. The proposed amendment would revise the licensing bases of DCPP, Unit Nos. 1 and 2 to adopt the alternative source term (AST) as allowed by Title 10 of the Code of Federal Regulations, Part 50, Section 50.67, "Accident source term." The AST methodology as established in U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.183, "Alternative Radi9logical Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," | |||
July 2000 (ADAMS Accession No. ML003716792), | |||
is used to calculate the offsite and control room radiological consequence for DCPP, Unit Nos. 1 and 2. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request. | |||
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 10 CFR 50.90, 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. | Section 50.34 of 10 CFR addresses the content of technical information required. | ||
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | ||
In order to make the application | In order to make the application complete, the NRC staff requests that PG&E supplement the application to address the following information by August 25, 2015: | ||
* In Appendix B of Attachment 4 of the LAR, the thermal-hydraulic inputs to the accident dose calculations have been changed from the current licensing basis (CLB) without providing justification. | * In Appendix B of Attachment 4 of the LAR, the thermal-hydraulic inputs to the accident dose calculations have been changed from the current licensing basis (CLB) without providing justification. | ||
For NRC to accept the LAR, the NRC staff E. Halpin requires justification for these changes made to the.thermal-hydraulic analysis from the CLB to the AST contained in Appendix B of Attachment 4 of the LAR. | For NRC to accept the LAR, the NRC staff E. Halpin requires justification for these changes made to the.thermal-hydraulic analysis from the CLB to the AST contained in Appendix B of Attachment 4 of the LAR. |
Revision as of 00:59, 9 July 2018
ML15219A016 | |
Person / Time | |
---|---|
Site: | Diablo Canyon ![]() |
Issue date: | 08/13/2015 |
From: | Lingam S P Plant Licensing Branch IV |
To: | Halpin E D Pacific Gas & Electric Co |
Lingam S P | |
References | |
TAC MF6399, TAC MF6400 | |
Download: ML15219A016 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION . WASHINGTON, D.C. 20555-0001 August 13, 2015 Mr. Edward D. Halpin Senior Vice President and Chief Nuclear Officer Pacific Gas and Ei'ectric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424
SUBJECT:
DIABLO CANYON POWER PLANT, UNIT NOS. 1 AND 2 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: REVIEW OF ALTERNATIVE SOURCE TERM LICENSE AMEN.DMENT REQUEST (TAC NOS. MF6399 AND MF6400)
Dear Mr. Halpin:
By letter dated June 17, 2015 (Agencywide Documents Access and Management System Accession No. ML 15176A539), Pacific Gas and Electric Company (PG&E, the licensee) submitted a license amendment request (LAR) for Diablo Canyon Power Plant (DCPP), Unit Nos. 1 and 2. The proposed amendment would revise the licensing bases of DCPP, Unit Nos. 1 and 2 to adopt the alternative source term (AST) as allowed by Title 10 of the Code of Federal Regulations, Part 50, Section 50.67, "Accident source term." The AST methodology as established in U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 1.183, "Alternative Radi9logical Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," July 2000 (ADAMS Accession No. ML003716792), is used to calculate the offsite and control room radiological consequence for DCPP, Unit Nos. 1 and 2. The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request. 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 10 CFR 50.90, 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 submittal 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 PG&E supplement the application to address the following information by August 25, 2015:
- In Appendix B of Attachment 4 of the LAR, the thermal-hydraulic inputs to the accident dose calculations have been changed from the current licensing basis (CLB) without providing justification.
For NRC to accept the LAR, the NRC staff E. Halpin requires justification for these changes made to the.thermal-hydraulic analysis from the CLB to the AST contained in Appendix B of Attachment 4 of the LAR.
- Please provide a license condition indicating that the modifications will be completed in support of the commitments made in Attachment 7 of the LAR. During the clarification call on July 28, 2015, the licensee stated that these . modifications will be implemented prior to issuance of the LAR. Once NRC staff receives the above requested information, the staff will perform an audit of the analyses to verify the accuracy of the* information provided by the licensee.
The NRC staff will then proceed 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 were discussed during the conference call held with your staff on July 28, 2015, and also with Mr. Phillippe Soenen on August 6, 2015. If you have any questions regarding this matter, I may be reached at 301-415-1564.
Docket Nos. 50-275 and 50-323 cc: Additional Distribution via Listserv Sincerely, Siva P. Lingam, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation E. Halpin requires justification for these changes made to the thermal-hydraulic analysis from the CLB to the AST contained in Appendix B of Attachment 4 of the LAR.
- Please provide a license condition indicating that the modifications will be completed in support of the commitments made in Attachment 7 of the LAR. During the clarification call on July 28, 2015, the licensee stated that these modifications will be implemented prior to issuance of the LAR. Once NRC staff receives the above requested information, the staff will perform an audit of the analyses to verify the accuracy of the information provided by the licensee.
The NRC staff will then proceed 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 were discussed during the conference call held with your staff on July 28, 2015, and also with Mr. Phillippe Soenen on August 6, 2015. If you have any questions regarding this matter, I may be reached at 301-415-1564.
Docket Nos. 50-275 and 50-323 cc: Additional Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4-1 Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorllpl4-1 Resource RidsNrrDssSrxb Resource ADAMS Accession No.: ML 15219A016 OFFICE NRR/DORL/LPL4-1
/PM NRR/DORL/LPL4-1/LA NAME Slingam JBurkhardt DATE 8/11/15 8/11/15 Sincerely, IRA/ Siva P. Lingam, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLAJBurkhardt Resource RidsNrrPMDiabloCanyon Resource RidsRgn4MailCenter Resource MHardgrove, NRR/DSS/SRXB NRR/DSS/SRXB/BC NRR/DORL/LPL4-1/BC NRR/DORL/LPL4-1
/PM CJackson MMarkley (LRegner for). SLingam 8/12/15 8/13/15 8/13/15 OFFICIAL RECORD COPY