ML13210A227: Difference between revisions
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| issue date = 08/02/2013 | | issue date = 08/02/2013 | ||
| title = 6/26/13, Summary of Pre-Application Meeting to Discuss Pending License Amendment Request to Modify the CNP Unit 1 Normal Operating Pressure and Temperature | | title = 6/26/13, Summary of Pre-Application Meeting to Discuss Pending License Amendment Request to Modify the CNP Unit 1 Normal Operating Pressure and Temperature | ||
| author name = Wengert T | | author name = Wengert T | ||
| author affiliation = NRC/NRR/DORL/LPLIII-1 | | author affiliation = NRC/NRR/DORL/LPLIII-1 | ||
| addressee name = | | addressee name = | ||
Line 9: | Line 9: | ||
| docket = 05000315 | | docket = 05000315 | ||
| license number = DPR-058 | | license number = DPR-058 | ||
| contact person = Wengert T | | contact person = Wengert T | ||
| case reference number = TAC MF1973 | | case reference number = TAC MF1973 | ||
| package number = ML13210A230 | | package number = ML13210A230 | ||
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=Text= | =Text= | ||
{{#Wiki_filter:'" UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 2, 2013 LICENSEE: | {{#Wiki_filter:'" UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 2, 2013 LICENSEE: INDIANA MICHIGAN POWER COMPANY FACILITY: DONALD C. COOK NUCLEAR PLANT (CNP) | ||
INDIANA MICHIGAN POWER COMPANY FACILITY: | |||
DONALD C. COOK NUCLEAR PLANT (CNP) | |||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF JUNE 26,2013, PRE-APPLICATION MEETING TO DISCUSS PENDING LICENSE AMENDMENT REQUEST TO MODIFY THE CNP UNIT 1 NORMAL OPERATING PRESSURE AND TEMPERATURE (TAC NO. MF1973) On June 26, 2013, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Indiana Michigan Power Company (I&M, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. | OF JUNE 26,2013, PRE-APPLICATION MEETING TO DISCUSS PENDING LICENSE AMENDMENT REQUEST TO MODIFY THE CNP UNIT 1 NORMAL OPERATING PRESSURE AND TEMPERATURE (TAC NO. MF1973) | ||
The purpose of the meeting was to discuss I&M's pending license amendment request (LAR) to modify the normal reactor coolant system operating conditions on CNP Unit 1 . . The proposed change would modify the plant's technical specifications to allow operation near the originally licensed normal operating pressure and temperature. | On June 26, 2013, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Indiana Michigan Power Company (I&M, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss I&M's pending license amendment request (LAR) to modify the normal reactor coolant system operating conditions on CNP Unit 1. | ||
A notice for this meeting was issued on June 12, 2013, and is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. | . The proposed change would modify the plant's technical specifications to allow operation near the originally licensed normal operating pressure and temperature. A notice for this meeting was issued on June 12, 2013, and is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML13161A380. The licensee's meeting slides can be found in ADAMS at Accession No. ML13176A133. | ||
The licensee's meeting slides can be found in ADAMS at Accession No. | During the meeting, the licensee described the operating history of the Unit 1 steam generators (SGs) and the tube wear observed at the SG fan bar supports, which it has attributed to resonance-related tube vibration due to low steam pressure. The licensee explained that, although the wear rate is low, it plans to correct this condition by restoring the reactor coolant system normal operating pressure and temperature to near the' previously licensed conditions. | ||
During the meeting, the licensee described the operating history of the Unit 1 steam generators (SGs) and the tube wear observed at the SG fan bar supports, which it has attributed to resonance-related tube vibration due to low steam pressure. | |||
The licensee explained that, although the wear rate is low, it plans to correct this condition by restoring the reactor coolant system normal operating pressure and temperature to near the' previously licensed conditions. | |||
The licensee further described the impacts of this change on the current analyses of record and the technical specifications. | The licensee further described the impacts of this change on the current analyses of record and the technical specifications. | ||
The NRC staff queried the licensee and provided feedback throughout the presentation. | The NRC staff queried the licensee and provided feedback throughout the presentation. The licensee stated that they plan to submit the LAR in October of 2013, and will request the NRC staff to complete its review in August 2014, to support the licensee's Unit 1 refueling outage schedule. | ||
The licensee stated that they plan to submit the LAR in October of 2013, and will request the NRC staff to complete its review in August 2014, to support the licensee's Unit 1 refueling outage schedule. | Members of the public were not in attendance. Public Meeting Feedback forms were not received. A list of attendees is included as an enclosure. | ||
Members of the public were not in attendance. | |||
Public Meeting Feedback forms were not received. | -2 Please direct any inquiries to me at 301-415-4037, or thomas.wengert@nrc.gov. | ||
A list of attendees is included as an enclosure. | Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315 | ||
-2 Please direct any inquiries to me at 301-415-4037, or thomas.wengert@nrc.gov. | |||
Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315 List of cc w/encl: Distribution via LIST OF JUNE 26, 2013, PRE-APPLICATION MEETING INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR NAME ORGANIZATION Q. Shane Lies I&M M. Scarpello I&M G.Hill I&M D. Hafer Sargent & Lundy M. Blumberg NRC/NRR/DRAlAADB J. Gall NRC/NRR/DSS/SRXB S. Mazumdar NRC/NRR/DE/EICB G. Kulesa NRC/NRR/DE/ESGB K. Karwoski NRC/NRR/DE A. Sallman NRC/N RR/DSS/SCVB C. Jackson NRC/NRR/DSS/SRXB T. Wengert NRC/NRR/DORL K. Bucholtz* | ==Enclosure:== | ||
NRC/NRR/DSS/STSB J. Giessner* | |||
NRC/Rill E. Sanchez* NRC/Rill J. Ellegood* | List of Attendees cc w/encl: Distribution via Listserv | ||
NRC/RIII J. Vandenbroek* | |||
Scientech | LIST OF ATTENDEES JUNE 26, 2013, PRE-APPLICATION MEETING WITH INDIANA MICHIGAN POWER COMPANY (I&M) | ||
* PartiCipated via teleconference ACRONYMS AADB. : AcCident Dose Branch DE, Division of Engineering DORL Division of Operating Reactor Licensing DPR Division of Policy and Rulemaking DSS . Division of Safety Systems EICB Instrumentation and Controls ESGB Steam Generator Tube Integrity Branch NRC U.S. Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulafion . SCVB Containment and Ventilation Branch SRXB. Reactor Systems Branch STSB Technical SpeCifications Branch Enclosure | DONALD C. COOK NUCLEAR PLANT NAME ORGANIZATION Q. Shane Lies I&M M. Scarpello I&M G.Hill I&M D. Hafer Sargent & Lundy M. Blumberg NRC/NRR/DRAlAADB J. Gall NRC/NRR/DSS/SRXB S. Mazumdar NRC/NRR/DE/EICB G. Kulesa NRC/NRR/DE/ESGB K. Karwoski NRC/NRR/DE A. Sallman NRC/N RR/DSS/SCVB C. Jackson NRC/NRR/DSS/SRXB T. Wengert NRC/NRR/DORL K. Bucholtz* NRC/NRR/DSS/STSB J. Giessner* NRC/Rill E. Sanchez* NRC/Rill J. Ellegood* NRC/RIII J. Vandenbroek* Scientech | ||
* PartiCipated via teleconference ACRONYMS AADB. : AcCident Dose Branch DE, Division of Engineering DORL Division of Operating Reactor Licensing DPR Division of Policy and Rulemaking DSS . Division of Safety Systems EICB Instrumentation and Controls Branc~ | |||
ESGB Steam Generator Tube Integrity Branch NRC U.S. Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulafion . | |||
SCVB Containment and Ventilation Branch SRXB. Reactor Systems Branch STSB Technical SpeCifications Branch Enclosure | |||
Package ML13210A230 Meeting Notice: ML13161A380 Meeting Summary: ML13210A227 Meelng t' I es: ML13176A133 Srd OFFICE NRR/LPL3-1/PM NRRlLPL3-lILA NRR/LPL3-1/BC NRRlLPL3-1/PM NAME "!Wengert ITBeltz for SRohrer RCarlson ITBeltz for "!Wengert IKFeintuch for | |||
!DATE 08/01/13 07/31/13 08/02/13 08/02/13}} | |||
"!Wengert ITBeltz for 08/01/13 | |||
Latest revision as of 15:28, 4 November 2019
ML13210A227 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 08/02/2013 |
From: | Thomas Wengert Plant Licensing Branch III |
To: | |
Wengert T | |
Shared Package | |
ML13210A230 | List: |
References | |
TAC MF1973 | |
Download: ML13210A227 (4) | |
Text
'" UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 2, 2013 LICENSEE: INDIANA MICHIGAN POWER COMPANY FACILITY: DONALD C. COOK NUCLEAR PLANT (CNP)
SUBJECT:
SUMMARY
OF JUNE 26,2013, PRE-APPLICATION MEETING TO DISCUSS PENDING LICENSE AMENDMENT REQUEST TO MODIFY THE CNP UNIT 1 NORMAL OPERATING PRESSURE AND TEMPERATURE (TAC NO. MF1973)
On June 26, 2013, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Indiana Michigan Power Company (I&M, the licensee) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss I&M's pending license amendment request (LAR) to modify the normal reactor coolant system operating conditions on CNP Unit 1.
. The proposed change would modify the plant's technical specifications to allow operation near the originally licensed normal operating pressure and temperature. A notice for this meeting was issued on June 12, 2013, and is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML13161A380. The licensee's meeting slides can be found in ADAMS at Accession No. ML13176A133.
During the meeting, the licensee described the operating history of the Unit 1 steam generators (SGs) and the tube wear observed at the SG fan bar supports, which it has attributed to resonance-related tube vibration due to low steam pressure. The licensee explained that, although the wear rate is low, it plans to correct this condition by restoring the reactor coolant system normal operating pressure and temperature to near the' previously licensed conditions.
The licensee further described the impacts of this change on the current analyses of record and the technical specifications.
The NRC staff queried the licensee and provided feedback throughout the presentation. The licensee stated that they plan to submit the LAR in October of 2013, and will request the NRC staff to complete its review in August 2014, to support the licensee's Unit 1 refueling outage schedule.
Members of the public were not in attendance. Public Meeting Feedback forms were not received. A list of attendees is included as an enclosure.
-2 Please direct any inquiries to me at 301-415-4037, or thomas.wengert@nrc.gov.
Sincerely, Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-315
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
LIST OF ATTENDEES JUNE 26, 2013, PRE-APPLICATION MEETING WITH INDIANA MICHIGAN POWER COMPANY (I&M)
DONALD C. COOK NUCLEAR PLANT NAME ORGANIZATION Q. Shane Lies I&M M. Scarpello I&M G.Hill I&M D. Hafer Sargent & Lundy M. Blumberg NRC/NRR/DRAlAADB J. Gall NRC/NRR/DSS/SRXB S. Mazumdar NRC/NRR/DE/EICB G. Kulesa NRC/NRR/DE/ESGB K. Karwoski NRC/NRR/DE A. Sallman NRC/N RR/DSS/SCVB C. Jackson NRC/NRR/DSS/SRXB T. Wengert NRC/NRR/DORL K. Bucholtz* NRC/NRR/DSS/STSB J. Giessner* NRC/Rill E. Sanchez* NRC/Rill J. Ellegood* NRC/RIII J. Vandenbroek* Scientech
- PartiCipated via teleconference ACRONYMS AADB. : AcCident Dose Branch DE, Division of Engineering DORL Division of Operating Reactor Licensing DPR Division of Policy and Rulemaking DSS . Division of Safety Systems EICB Instrumentation and Controls Branc~
ESGB Steam Generator Tube Integrity Branch NRC U.S. Nuclear Regulatory Commission NRR Office of Nuclear Reactor Regulafion .
SCVB Containment and Ventilation Branch SRXB. Reactor Systems Branch STSB Technical SpeCifications Branch Enclosure
Package ML13210A230 Meeting Notice: ML13161A380 Meeting Summary: ML13210A227 Meelng t' I es: ML13176A133 Srd OFFICE NRR/LPL3-1/PM NRRlLPL3-lILA NRR/LPL3-1/BC NRRlLPL3-1/PM NAME "!Wengert ITBeltz for SRohrer RCarlson ITBeltz for "!Wengert IKFeintuch for
!DATE 08/01/13 07/31/13 08/02/13 08/02/13