ML073100364
| ML073100364 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 10/29/2007 |
| From: | Gordon Peterson Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DUK073020001 | |
| Download: ML073100364 (4) | |
Text
DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO PRIORITY Normal THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW
- 1) 01623 G L MONTGOMERY MG01WC
- 2) 01749 L C GIBBY-MG01VP
- 3) 02049 NGO PRA MANAGER ECO81
- 4) 02388 DAVID DZIADOSZ LYNCHBG, VA
- 5) 02532 MCG NRC INSP MG-ADMIN MAIL RM
- 6) 02546 WC LIBRARY - MG01WC
- 7) 03044 MCG DOC CNTRL MISC MAN MGO5DM
- 8) 03283 PR TUCKER MG01RP
- 11) 03744 OPS TRNG MGR. MG03OT
- 12) 03759 U S NUC REG WASHINGTON, DC
- 13) 03796 SCIENTECH DUNEDIN, FL
- 14) 04698 D E BORTZ EC08G
- 15) 04809 MCG PLANT ENG. LIBR. MG05SE Duke Energy DOCUMENT TRANSMITTAL FORM REFERENCE MCGUIRE NUCLEAR STATION RECORD RETENTION # 005893 TECHNICAL SPECIFICATIONS (TS)
AND TECHNICAL SPECIFICATIONS BASES (TSB)
Page 2 of 3 Date:
10/29/07 Document Transmittal #:
DUK073020001 QA CONDITION
[: Yes
- No OTHER ACKNOWLEDGEMENT REQUIRED
- Yes IF OA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:
Duke Energy McGuire DCRM MGO2DM 13225 Hagers Ferry Road Huntersville, N.C, 28078 Rec'd By Date DOCUMENT NO QA COND REV #/DATE DISTR CODE 1
2 3
4 5
6 7
8
- 9.
110 11 12 13 14 15 TOTAL F
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F
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F F
+ --
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F TS & TSB MEMORANDUM NPF-9 AMENDMENT 243 (PAGE 3)
NPF-17 AMENDMENT 224 (PAGE 3)
NA NA NA
--- 10/23/07 10/23/07 10/23/07 MADM-04B vi V1 ivi Vl V1 Ix Vl Vl V3 V8 Vl Vl V2 48 REMARKS: PLEASE PLACE IN FRONT OF THE TECHNICAL SPECIFICATION MANUAL (CHANGE TO FACILITY LICENSE)
RECIPIENT # 00422 PREVIOULSY COMPLETED G R PETERSON VICE PRESIDENT MCGUIRE NUCLEAR STATION BY:
BCBEAVER MGO1RC BCB/CMK
October 23, 2007 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)
Manual Holders
Subject:
McGuire Technical Specifications Technical Specification Manual: This is actually a change to the McGuire Nuclear Station Facility License which should be filed at the front of your Technical Specification Book. This change affects only page 3 of the unit 1 (NPF-9) and the unit 2 (NPF-17) License. See instructions below.
REMOVE INSERT Renewed License No. NPF-9 Page 3 only Renewed License No. NPF-I 7 Page 3 only Renewed License No. NPF-9 Page 3 only Amendment No. 243 Renewed License No. NPF-17 Page 3 only Amendment No. 224 Revision numbers may skip numbers due to Regulatory Compliance Filing System.
Please call me if you have questions.
Bonnie Beaver Regulatory Compliance 875-4180 (4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6)
Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3411 megawatts thermal (100%).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 243, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.
Duke shall complete these activities no later than June 12,'2021, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.
Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval,
-provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
Renewed License No. NPF-9 Amendment No. 243
-3.
(4)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2; and, (6)
Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3411 megawatts thermal (100%).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 224, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.
Duke shall complete these activities no later than March 3, 2023, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.
Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forthin 10 CFR 50.59 and otherwise complies with the requirements in that section.
Renewed License No. NPF-17 Amendment No. 224