ML20210Q936
| ML20210Q936 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/26/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210Q939 | List: |
| References | |
| NUDOCS 9709020215 | |
| Download: ML20210Q936 (16) | |
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t UNITED STA.TES P;
NUCLEAR REGULATORY COMMIS810N f
WASHINGTON, D,o. 90MH001
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DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Aroendment No. 176 License No. NPF 9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The appilcation for amendment to the McGuire Nuclear Station, Unit 1 (the facility), Facility Operating License No. NPF 9 filed by the Duke Power Company (licensee) dated June 12,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9709020215 970826 PDR ADOCK 05000369 P
2-2.
Accordingly, the license is hereby amended by page changes to Facility Operating Llconse No. NPF 9 as indicated in the attachment to this license amendment.
3.
This license amendment is effective as of its date of issuance and shall be '
implemented ' tithin 30 days from the date of issuanco.
FOR THE NUCLEAR REGULATORY COMMISSION 3
Herbert N. Berkow, Director Project Directorate ll 2 Division of Reactor Projects 1/Il Office of Nuclear Reactor Regulation
Attachment:
Changes to the License Date of issuance:
August 26, 1997 4
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i ATTACHMENT TO LICENSE AMENDMENT NO.176 f
FACILITY OPERATING LICENSE NO. NP.f.-g l
i DOCKET NO. 50 369 l
i The revised pages are identmed by Amendment number and contain vertical lines indicating 1
- the areas of change.
i Replace Pages 1 thru 4 and 12s of Facility Operating License No. NPF 9 with the attached new pages, j
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4 UNITED STATES s
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NUCLEAR REGULATORY COMMIS810N k
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DUKE ENERGY CORPORATION l
DOCKET NO. 50-369 KGUIRE NUCLEAR STATION. UNIT 1 FACILITY OPERATINC LICENSE 1.! CENSE NO. NPF-9 i
1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:-
A.
The application for license filed by the Duke Energy Corporation l
A(tomic Energy Act of 1954, as amended (the Act), and thethe licensee) c Commission's regulations set forth in 10 CFR Chapter I and all recuired notifications to other agencies or bodies have been duly mac e; B.
Construction of the McGuire Nuclear Station Unit 1 (the facility hasbeensubstantiallycompletedinconformltywithConstruction)
Permit No. CPPR-83 and the application, as amended, the provisions of the Act and the regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commissioni There is reasonable assurance:
1 that the activities authorized D.
by this operating license can be(co)nducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; E.
The licensee is technically and financially qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.
The licensee has satisfied the applicable-provisions of 10 CFR Part 140, ' Financial Protection Requirements and Indemnity Agreements",
of the Commission's regulations; G.
The issuance of this license will not be inimical to the common
' defense and security or to the health and safety of the public; Amendment No.176
_(
= _ _
2 H.
After weighing the environmental, economic, technical, and Pher benefits of the facility against environmental and other <
.s and considering available alternatives, the issuance of this.acility Operating License No. NPF-9 (subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B) is in accordance with 10 CFR Part 51, of the Commission's regulations and all applicable requirements have been satisfied; 1.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70, 2.
Pursuant to approval by the Nuclear Regulatory Commission at a meeting on June 9, 1981, the License for fuel-Loading and Zero Power Testing issued on January 23, 1981, as amended, is superseded by facility Operating License No. NPF-9 which is hereby issued to the Duke Energy Corporation (the licensee) to read as follows:
A.
This license applies to the McGuire Nuclear Station, Unit 1, a pressurized water reactor and associated equipment (the facility) owned by the Duke Energy Corporation (licensee).
The facility is l
located on the licensee's site in Mecklenburg County, North Carolina on the shore of Lake Norman approximately 17 miles northwest of Charlotte, North Carolins and is described in Duke Energy Corporation's " Final Safety Analysis Report," as supplemented and amended, and in its Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Dtke Energy Corporation:
l (1)
Pursuant to Section 103 of the Act and 10 CFR Part 50, possess, use, and o)erate the facility at the designated location in Mecklen>urg County, North Carolina, in accordance with the limitations set forth in the license; (2)
Pursuant to the Act ind 10 CFR Part 70 to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with tie limitation: for storage and amounts required for reactor operatir, as described in the Final Safety Analysis Report, as supplemented and amended; Am2ndment No.176
3 (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material a sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (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 s)ecial nuclear material without restriction to chemical or p1ysical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to posses, but not separate, such byproduct and special nuclear materials 1
as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2.
(6)
Pursuant to the Act and 10 CFR Parts 30 and 40, to receiva, possess and process for release or transfer such byproduct material as may be produced by the Duke Energy Corporation l
Training and Technology Center.
C.
This 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 appitcable provisions of the Act and to the rules, regulations, and orders of the Commistion now or hereafter in effect; and is subject to the additional conditions specified or incorporated belows (1) Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (100% power),
(2) I nhnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 176, are hereby incorporated into this license.
The licensee shall op'cate the facility in accordance with the Technical Specifications.
Amendment No.176
i
.4-(3) Initial Test Prooram The licensee shall conduct the initial. test program (set forth in Section 14 of the licensee's Final Safety Analysis Report, es amended) without making any modifications to this program unless such modifications are in accordance with the provisions of 10 CFR Section 50.59.
In addition, the licensee shral not make any major-modifications to this program unless modifications ); ave been identified and have received prior NRC approval. Major modifications are defined as:
a.
Elimination of any test identified as essential in Section 14 of the Final Safety Analysis Report, as amended; b.
Modification of test objectives, methods or acceptance criteria-for any test identified as essential i'n Section 14 of the Final Safety Analysis Report, as amended; c.
Performance of any test at a power level different from that
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descr: red in the program, as limited by this license authorization; and d.
Failure to com)1ete any tests included in the described program (planned or scleduled) for power l'evels up to the authorized power level.
(4) Fire Protection Proaram Duke Energy Corporation shall implement and maintain in effect all l
provisions of the approved fire protection program as described in the Final Safety Analysis Report, as updated, for the facility through the 1989 annual FSAR update and as approved in the SER dated March 1978 and Supplements 2, 5 and 6 dated March 1979, April 1981, ano February 1983, respectively, and the safety evaluation dated May 15, 1989, subject to the following provision: The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire, a.
Duke-shall implement a Standby Shutdown Facility System to assure shutdown capability during certain postulated fire events as indicated in Duke's letter, dated January 31, 1979. All required changes shall be completed three months after Amendment No.176
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2.E.
. Duke Energy Corporation shall fully implement and maintain in l
effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans-including amendments made pursuant to provisions of the Miscellaneous Amendments and Search i
~
Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain safeguards information protected ur.Uer 10 CFR 73.21, are entitled:
- McGuire Nuclear Station Physical Security Plan," with revisions submitted through September 25, l
1987; 'McGuire Nuclear Station Training and Qualification Plan,"
with revisions submitted through July 3,1986; and "McGuire Nuclear Station Safeguards Contingency Plan," with revisions submitted through March 21, 1986. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule-set forth therein.
5 Amendment No.176
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WASHINGTON D.C. - *1 49.....
DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.158 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility), Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated June 12,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied, i
i
2-2.
Accordingly, the license is hereby amended by page changes to Facility Operating License No. NPF-17 as indicated in the attachment to this license amendment, 3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
) m He ert N. Berkcw, Director Project Directorate ll-2 Division of Reactor Projects - l/ll Of0ce of Nuclear Reactor Regulation
Attachment:
Changes to the License Date of issuance:
August 26, 1997 4
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I ATTACHMENT TO LICENSE AMENDMENT NO.158 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-3ZQ The revised pages are identifed by Amendment number and contain vertical lines indicating the areas of change, Replace Pages 1 thru 4 and 7b of Facility Operating License No, NPF 17 with the attached new pages,
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UNITED STATES y
NUCLEAR REGULATORY COMMISSION "g
WASHINGTON, D.C. 1
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DUKE ENERGY CORPORATION l
DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION. UNIT 2 FACILITY OPERATING LICENSE LICENSE NO. NPF-17 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for license filed by the Duke Energy Corporation l
(the licensee) complies with the standards and requirements of the Atomic Energy Act of~1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B.
Corstruction of the McGuire Nuclear Station, Unit 2 (the facility) has been substantially completed in conformity with Construction Permit No. CPPR-84 and the application, as amended, the provisions of the Act and the regulations of the Commission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.0.
below);
D.
There is reasonable assurance:
(i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I-(except as exempted from compliance in Section 2.0. below);
E.
The licensee is technically qualified to engage in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.
The licensee has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements",
of the Commission's regulations; G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; Amendment No.158
1
. H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of this Facility Operating License No. NPF-17, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51, of the Commission's regulations and all applicable requirements have been satisfied; I.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Based on the foregoing findings and the Initial Decisions issued by the Atomic Safety and Licensing Board dated April 18, 1979, and May 26, 1981, and the Decision of the Atomic Safety and Licensing Appeal Board dated March 30, 1982, regarding this facility, Facility Operating License No. NPF-17 is hereby issued to the Duke Energy Corporation (the l
licensee) to read as follows:
A.
This license applies to the McGuire Nuclear Station, Unit 2, a pressurized water reactor and associated equipment (the facility) owned by the Duke Energy Corporation (licensee).
The facility is l
located on the licensee's site in Mecklenburg County, North Carolina, on the shore of Lake Norman approximately 17 miles northwest of Charlotte, North Carolina, and is described in Duke Enorgy Corporation's ' Final Safety Analysis Report," as supplemented and amended through Revision No. 45, and in its Environmental Report, as supplemented and amended through Revision No. 6; B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Duke Energy Corporation:
l (1)
Pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Mecklenburg County, North Carolina, in accordance with the procedures and limitations set forth in this license; (2)
Pursuant to the Act and 10 CFR Part 70 to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report,.as supplemented and amended through Revision No. 45; (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectars in amounts as required; Amendment No.158 1
. (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 byproduct 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 Part 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Energy Corporation l
Training and Technology Center.
C.
This 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 reactor core power levels not in excess of 3411 megawatts thermal (100% power) in accordance with the conditions soecified herein and in Attachment I to this license.
The preoperatio'nal tests, startup tests and other items identified in Attachment I to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.158, are hereby incorporated into license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Antitrust Conditions The licensee shall comply with the antitrust conditions delineated in Appendix C to this license; Amendment No.158
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(4) Thermal Sleeves (Section 3.9.2 of SSER #6)*
1 By December-31, 1983, the licensee-shall provide, for NRC staff review and approval, justification for continued operation with the seven thermal sleeves removed from selected locations in the reactor coolant system;-
1(5) Model D-3 Steam Generator _(Section 5.3.1 of SSEN #6)-
Prior to operation in excess of 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> at power levels in excess of 5% power or operation at power levels in excess of 50%
>ower, the licensee shall provide appropriate steam generator-1ardware modifications and implement appropriate surveillance measures with respect _to the steam generator modification; (6) Environmental Oualification (Section 7.8 of SER, SSER #4, #5, #6,
- 7)
The licensee shall environmentally qualify all electrical equipment within_the scope of 10 CFR 50.49 in accordance with the implementation requirements of 10 CFR 50.49 (g).
i j
(7) Fire Protection Duke Energy Corporation shall implement and maintain in effect all l
provisions of the approved fire protection program as described in the Final Safety Analysis Report, as updated,-for the facility through1the 1989 annual FSAR update and as approved in the SER dated
. March 1978 and Supplements 2, 5 and 6 dated March 1979, April 1981, and February 1983, respectively, and the safety evaluation dated May 15, 1989, subject to the following provision: _The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the j
event of a fire.
(b) The license shall perfere required modifications to the oil collection system and fire suppression system for the-Reactor Coolant Pump (RCP) motor no later than March 1,1984.
(c)
Prior to exceeding 5% power, the licensee-shall submit a schedule for installation of system instrumentation provisions for source range neutron flux and reactor coolant system-
. temperature-(Tm)-
monitors as an integral part of the Standby' Shutdown System; The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein-the license-condition is discussed, i
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D.
The facility requires an exemption from certain requirements of Appendix 0 to 10 CFR Part 50.
This exemption is described in the Office of Nuclear Reactor Reaulation's Safety Evaluation Report, Supplement No. 2 and in Supplement No. 4 (Section 5.2.3).
This exem) tion is authorized by law and will not endanger life or property or tie common defense and security and is otherwise in the public.
interest.
The exemption is, therefore, hereby granted pursuant to 10 CFR 50.12.
With the granting of this exemption, the facility will operate, to the extent authorized therein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; E.
Duke Energy Corporation shall fully implement and maintain in effect i
all provisions of the Commission-approved physical security, guard tra'ning and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain safeguards information protected under 10 CFR 73.21, are entitled:
"McGuire Nuclear Sthtion Physical Security Plan,"
with revisions submitted through September 25, 1987; "McGuire Nuclear Station Training and Qualification Plan," with revisions submitted through July 3, 1986; and McGuire Nuclear Station Safeguards Contingency Plan," with revisions submitted through March 21, 1986.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F.
The licensee shall report any violations of the requirements contained in Section 2 Items C.(1), C.(4) through C.(ll), and E of this license within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-by telephone and confirm by telegram, r..ailgram, or facsimile transmission to the NRC Regional Administrator, Reg. II, or his designate, no later than the first working day following the violation, with a written followup report within 14 days; Amendment No. 158