ML103400189: Difference between revisions

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| issue date = 12/14/2010
| issue date = 12/14/2010
| title = Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
| title = Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
| author name = Wilkins L E
| author name = Wilkins L
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV
| addressee name = Bannister D J
| addressee name = Bannister D
| addressee affiliation = Omaha Public Power District
| addressee affiliation = Omaha Public Power District
| docket = 05000285
| docket = 05000285
Line 23: Line 23:


==Dear Mr. Bannister:==
==Dear Mr. Bannister:==
By letter dated August 16, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 102290067), Omaha Public Power District (OPPD, or the licensee) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would remove the Technical Specification (TS) limiting condition for operation (LCO) 2.15, "Instrumentation and Control Systems," Table 2-5, "Instrumentation Operating Requirements for Other Safety Feature Functions," Items 3, 4, and 5, and the associated Notes a, b, c, and d, for power-operated relief valve (PORV) and pressurizer safety valve (PSV) acoustic position indication and tail pipe temperature from the FCS TSs. The proposed change would also revise the surveillance requirement (SR) for TS 3.1, "Instrumentation and Control," Table 3-3, "Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls," Items 21, 23, and 24 for PORV Operation and Acoustic Position Indication, Safety Valve Acoustic Position Indication, and PORVISafety Valve Tail Pipe Temperature, respectively.
By letter dated August 16, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290067), Omaha Public Power District (OPPD, or the licensee) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would remove the Technical Specification (TS) limiting condition for operation (LCO) 2.15, "Instrumentation and Control Systems," Table 2-5, "Instrumentation Operating Requirements for Other Safety Feature Functions," Items 3, 4, and 5, and the associated Notes a, b, c, and d, for power-operated relief valve (PORV) and pressurizer safety valve (PSV) acoustic position indication and tail pipe temperature from the FCS TSs. The proposed change would also revise the surveillance requirement (SR) for TS 3.1, "Instrumentation and Control," Table 3-3, "Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls," Items 21, 23, and 24 for PORV Operation and Acoustic Position Indication, Safety Valve Acoustic Position Indication, and PORVISafety Valve Tail Pipe Temperature, respectively.
By letter dated September 17,2010 (ADAMS Accession No. ML 102580129), the U.S. Nuclear Regulatory Commission (NRC) informed you that additional information was required to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
By letter dated September 17,2010 (ADAMS Accession No. ML102580129), the U.S. Nuclear Regulatory Commission (NRC) informed you that additional information was required to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
OPPD supplemented its application by letter dated September 27, 2010 (ADAMS Accession No. ML 102720964). 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.
OPPD supplemented its application by letter dated September 27, 2010 (ADAMS Accession No. ML102720964). 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 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.
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.
D. Bannister -2This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application as supplemented and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1377. Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Distribution via Listserv D. Bannister -2This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application as supplemented and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1377.
D. Bannister -2This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application as supplemented and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1377. Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Distribution via Listserv D. Bannister -2This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application as supplemented and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1377.
Sincerely, Ira! Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
Sincerely, Ira! Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
50-285 cc: Distribution via Listserv DISTRIBUTION:
50-285 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDssSrxb Resource LPLIV Branch Reading File RidsNrrLA..IBurkhardt Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMFortCalhoun Resource RidsNrrDirsltsb Resource RidsOgcRp Resource RidsNrrDeEicb Resource RidsRgn4MailCenter Resource RidsNrrDorl Resource PChung, NRRIDE/EICB RidsNrrDorlDpr Resource KBucholtz, NRRIITSB RidsNrrDorlLpl4 Resource ADAMS Accession No. ML 103400189 OFFICE DORULPL4/PM DORULPL4/LA DIRS/ITSB/BC DElEICB/BC DORULPL4/BC DORULPL4/PM NAME LWilkins JBurkhardt RElliott WKemper (ARosenyev for)
PUBLIC RidsNrrDssSrxb Resource LPLIV Branch Reading File RidsNrrLA..IBurkhardt Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMFortCalhoun Resource RidsNrrDirsltsb Resource RidsOgcRp Resource RidsNrrDeEicb Resource RidsRgn4MailCenter Resource RidsNrrDorl Resource PChung, NRRIDE/EICB RidsNrrDorlDpr Resource KBucholtz, NRRIITSB RidsNrrDorlLpl4 Resource ADAMS Accession No. ML103400189 OFFICE DORULPL4/PM DORULPL4/LA DIRS/ITSB/BC DElEICB/BC DORULPL4/BC DORULPL4/PM NAME LWilkins JBurkhardt RElliott WKemper (ARosenyev for)
MMarkley LWilkins DATE 12/811 0 12/6/10 12/13/10 12/13/10 12/14/10 12/14/10 OFFICIAL RECORD}}
MMarkley LWilkins DATE 12/811 0 12/6/10 12/13/10 12/13/10 12/14/10 12/14/10 OFFICIAL RECORD}}

Revision as of 01:47, 11 July 2019

Acceptance Following Review of Supplemental Information, License Amendment Request to Relocate Acoustic Position and Tail Pipe Temperature Indication Surveillance Requirements from Technical Specifications
ML103400189
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/14/2010
From: Lynnea Wilkins
Plant Licensing Branch IV
To: Bannister D
Omaha Public Power District
Wilkins, L E, NRR/DORL/LPL4, 415-1377
References
TAC ME4542
Download: ML103400189 (3)
v • d • e


Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 14, 2010 Mr. David J.

Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 FORT CALHOUN STATION, UNIT 1 -

ACCEPTANCE OF REQUESTED LICENSING ACTION RE: AMENDMENT REQUEST (TAC NO. ME4542)

Dear Mr. Bannister:

By letter dated August 16, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102290067), Omaha Public Power District (OPPD, or the licensee) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would remove the Technical Specification (TS) limiting condition for operation (LCO) 2.15, "Instrumentation and Control Systems," Table 2-5, "Instrumentation Operating Requirements for Other Safety Feature Functions," Items 3, 4, and 5, and the associated Notes a, b, c, and d, for power-operated relief valve (PORV) and pressurizer safety valve (PSV) acoustic position indication and tail pipe temperature from the FCS TSs. The proposed change would also revise the surveillance requirement (SR) for TS 3.1, "Instrumentation and Control," Table 3-3, "Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls," Items 21, 23, and 24 for PORV Operation and Acoustic Position Indication, Safety Valve Acoustic Position Indication, and PORVISafety Valve Tail Pipe Temperature, respectively.

By letter dated September 17,2010 (ADAMS Accession No. ML102580129), the U.S. Nuclear Regulatory Commission (NRC) informed you that additional information was required to enable the NRC staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.

OPPD supplemented its application by letter dated September 27, 2010 (ADAMS Accession No. ML102720964). 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 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.

D. Bannister -2This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application as supplemented and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1377. Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Distribution via Listserv D. Bannister -2This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The NRC staff has reviewed your application as supplemented and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. If you have any questions, please contact me at (301) 415-1377.

Sincerely, Ira! Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.

50-285 cc: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrDssSrxb Resource LPLIV Branch Reading File RidsNrrLA..IBurkhardt Resource RidsAcrsAcnw_MailCTR Resource RidsNrrPMFortCalhoun Resource RidsNrrDirsltsb Resource RidsOgcRp Resource RidsNrrDeEicb Resource RidsRgn4MailCenter Resource RidsNrrDorl Resource PChung, NRRIDE/EICB RidsNrrDorlDpr Resource KBucholtz, NRRIITSB RidsNrrDorlLpl4 Resource ADAMS Accession No. ML103400189 OFFICE DORULPL4/PM DORULPL4/LA DIRS/ITSB/BC DElEICB/BC DORULPL4/BC DORULPL4/PM NAME LWilkins JBurkhardt RElliott WKemper (ARosenyev for)

MMarkley LWilkins DATE 12/811 0 12/6/10 12/13/10 12/13/10 12/14/10 12/14/10 OFFICIAL RECORD

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