HNP-12-050, License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:* Progress Energy                                                                 Christopher L.Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.
{{#Wiki_filter:* Progress Energy APR 2 201Z Christopher L. Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.
APR    2 201Z Serial: HNP-12-050                                                                         10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63
10 CFR 50.90 Serial: HNP-12-050 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63


==Subject:==
==Subject:==
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==Reference:==
==Reference:==
Letter from K. Holbrook to the U.S. NRC, "License Amendment Request for Revision to Technical Specification Core Operating Limits Report," Serial HNP- 11-067 dated August 22, 2011, ADAMS Accession No. ML11238A077 Ladies and Gentlemen:
Letter from K. Holbrook to the U.S. NRC, "License Amendment Request for Revision to Technical Specification Core Operating Limits Report," Serial HNP-11-067 dated August 22, 2011, ADAMS Accession No. ML11238A077 Ladies and Gentlemen:
By letter dated August 22, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., requested approval from the U.S. Nuclear Regulatory Commission (NRC) of a license amendment request (LAR). The proposed amendment would revise Technical Specification (TS) 6.9.1.6, "Core Operating Limits Report," to add a plant-specific methodology that implements AREVA's NRC-approved topical report EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors,"
By {{letter dated|date=August 22, 2011|text=letter dated August 22, 2011}}, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., requested approval from the U.S. Nuclear Regulatory Commission (NRC) of a license amendment request (LAR). The proposed amendment would revise Technical Specification (TS) 6.9.1.6, "Core Operating Limits Report," to add a plant-specific methodology that implements AREVA's NRC-approved topical report EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors,"
Revision 0, and also EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 2 or higher upon approval of the specific revision by the NRC.
Revision 0, and also EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 2 or higher upon approval of the specific revision by the NRC.
CP&L rescinds our request for approval of EMF-2103(P)(A), Revision 2 or higher. The attached retyped Technical Specification page 6-24a has been revised accordingly.
CP&L rescinds our request for approval of EMF-2103(P)(A), Revision 2 or higher. The attached retyped Technical Specification page 6-24a has been revised accordingly.
P.O.
P.O.
Box 165 New Hill, NC 27562 T> 919.362.2502                                                                                             &.
Box 165 New Hill, NC 27562 T> 919.362.2502 F> 919.362.2095
F> 919.362.2095


U.S. Nuclear Regulatory Commission                                                 Page 2 HNP-12-050 This document contains no new Regulatory Commitment.
U.S. Nuclear Regulatory Commission Page 2 HNP-12-050 This document contains no new Regulatory Commitment.
Please direct any questions regarding this submittal to Dave Corlett at (919) 362-3137.
Please direct any questions regarding this submittal to Dave Corlett at (919) 362-3137.
Sincerely, CLB/jrc Enclosed: Revised Technical Specification Page cc:   Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief N.C. DENR Ms. A. T. Billoch Colon, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
Sincerely, CLB/jrc Enclosed: Revised Technical Specification Page cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief N.C. DENR Ms. A. T. Billoch Colon, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II


ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)
ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)
: d. XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Rod Bowing,"
: d.
XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Rod Bowing,"
approved version as specified in the COLR.
approved version as specified in the COLR.
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -
Nuclear Enthalpy Rise Hot Channel Factor).
Nuclear Enthalpy Rise Hot Channel Factor).
: e. EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs," approved version as specified in the COLR.
: e.
EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs," approved version as specified in the COLR.
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
: f. ANP-3011 (P), "Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis,"
: f.
ANP-3011 (P), "Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis,"
Revision 1, as approved by NRC safety evaluation dated (Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
Revision 1, as approved by NRC safety evaluation dated (Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
: g. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," approved version as specified in the COLR.
: g.
(Methodology for Specification 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6   -
XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," approved version as specified in the COLR.
(Methodology for Specification 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 -
Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).
Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).
SHEARON HARRIS - UNIT 1                       6-24a                           Amendment No.}}
SHEARON HARRIS - UNIT 1 6-24a Amendment No.}}

Latest revision as of 02:46, 12 January 2025

License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page
ML12102A016
Person / Time
Site: Harris 
Issue date: 04/02/2012
From: Burton C
Carolina Power & Light Co, Progress Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-12-050
Download: ML12102A016 (3)
v • d • e


Text

  • Progress Energy APR 2 201Z Christopher L. Burton Vice President Harris Nuclear Plant Progress Energy Carolinas, Inc.

10 CFR 50.90 Serial: HNP-12-050 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit No. 1 Docket No. 50-400 / Renewed License No. NPF-63

Subject:

License Amendment Request for Revision to Technical Specification Core Operating Limits Report for Realistic Large Break LOCA Analysis Revised Technical Specification Page

Reference:

Letter from K. Holbrook to the U.S. NRC, "License Amendment Request for Revision to Technical Specification Core Operating Limits Report," Serial HNP-11-067 dated August 22, 2011, ADAMS Accession No. ML11238A077 Ladies and Gentlemen:

By letter dated August 22, 2011, Carolina Power & Light Company (CP&L), doing business as Progress Energy Carolinas, Inc., requested approval from the U.S. Nuclear Regulatory Commission (NRC) of a license amendment request (LAR). The proposed amendment would revise Technical Specification (TS) 6.9.1.6, "Core Operating Limits Report," to add a plant-specific methodology that implements AREVA's NRC-approved topical report EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors,"

Revision 0, and also EMF-2103(P)(A), "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," Revision 2 or higher upon approval of the specific revision by the NRC.

CP&L rescinds our request for approval of EMF-2103(P)(A), Revision 2 or higher. The attached retyped Technical Specification page 6-24a has been revised accordingly.

P.O.

Box 165 New Hill, NC 27562 T> 919.362.2502 F> 919.362.2095

U.S. Nuclear Regulatory Commission Page 2 HNP-12-050 This document contains no new Regulatory Commitment.

Please direct any questions regarding this submittal to Dave Corlett at (919) 362-3137.

Sincerely, CLB/jrc Enclosed: Revised Technical Specification Page cc:

Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, III, Section Chief N.C. DENR Ms. A. T. Billoch Colon, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II

ADMINISTRATIVE CONTROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

d.

XN-75-32(P)(A), "Computational Procedure for Evaluating Fuel Rod Bowing,"

approved version as specified in the COLR.

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -

Nuclear Enthalpy Rise Hot Channel Factor).

e.

EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs," approved version as specified in the COLR.

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

f.

ANP-3011 (P), "Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis,"

Revision 1, as approved by NRC safety evaluation dated (Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

g.

XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," approved version as specified in the COLR.

(Methodology for Specification 3.1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6 -

Control Bank Insertion Limits, and 3.2.2 - Heat Flux Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24a Amendment No.

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