ML20073S426
| ML20073S426 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/25/1994 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073S428 | List: |
| References | |
| NUDOCS 9406030119 | |
| Download: ML20073S426 (7) | |
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Jg UNITED STATES
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'E NUCLEAR REGULATORY COMMISSION
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WASHINGTON D.C. 20555-0001 g
.....f DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET N0. 50-413 CATAWBA NUCI_ EAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 118 License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Larolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated January 27, 1994, 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.
9406030119 940525 ADOCK0500g3 DR
4
. 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.
NPF-35 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 118
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into thi.s license.
Duke Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dwi David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: May 25, 1994 1
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UNITED STATES c
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-4001
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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY-DOCKET NO. 50-414 l
CATAWBA NUCLEAR STATION. UNIT 2
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 112 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Cctawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company, acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (licensees), dated January 27, 1994, 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; t
l B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the commission; l
C.
There is reasonable assurance (1) 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.
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l l l 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.
NPF-52 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications. contained in Appendix A, as revised l
'through Amendment No. 112
, and the Environmental Protection Plan l-contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
Duke Power Company shall operate'the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This.icense amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION cv -
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David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification l
Changes Date of Issuance: May 25, 1994 l
l
ATTACHMENT TO LICENSE AMENDMENT NO.
118 FACILITY OPEPATING LICENSE NO. NPF-35 DOCKET NO. 50-413 MQ TO LICENSE AMENDMENT NO.112 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO, 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
Remove Paaes Insert Paaes 3/4 6-21 3/4 6-21 3/4 9-4 3/4 9-4 l
l l
l i
d a
e CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i j
4.6.3.2 Each isolation valve specified in Tables 3.6-2a and 3.6-2b shall be -
demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once e
i per 18 months by:
l a.
Verifying that on a Phase "A" Isolation test signal, each Phase "A" isolation valve actuates to its isolation position;**
b.
Verifying that on a Phase "B" Isolation test signal, each Phase "B" isolation valve actuates to its isolation position,**
c.
Verifying that on a containment Radioactivity-High test signal, each purge and exhaust valve actuates to its isolation position.
4.6.3.3 The isolation time of each power-operated or automatic valve of 2
Tables 3.6-2a and 3.6-2b shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
This surveillance need not be performed until prior to entering HOT SHUTDOWN following the Unit 1 first refueling.
CATAWBA - UNITS 1 & 2 3/4 6-21 Amendment No.118(Unit 1)
Amendment No.112(Unit 2)
l l
l REFUELING OPERATIONS i
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS l
LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
a.
The equipment hatch closed and held in place by a minimum of four
- bolts, b.
A minimum of one door in each airlock is closed, and t
c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1)
Closed by an isolation valve, blind flange, or manual valve, or 2)
Exhausting through an OPERABLE Reactor Building Containment Purge System HEPA filters and activated carbon adsorbers.
APPLICABILITY:
During CORE ALTERATIONS or movement of irradiated fuel within the containment.
ACTION:
l a.
With the requirements of the above specification not satisfied for reasons other than the heaters tested per 4.9.4.2.a and 4.9.4.2.d.2, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.
l b.
With a heater tested per 4.9.4.2.a and 4.9.4.2.d.2 inoperable, restore the inoperable heater to operable status within 7 days, or file a Special Report in accordance with Specification 6.9.2 within 30 days, specifying the reason for inoperability and the planned actions to return the heater to operable status.
SURVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated condition or exhausting through an OPERABLE Reactor Building Containment Purge System within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement l
of irradiated fuel in the containment building by:
l a.
Verifying the penetrations are in their closed / isolated condition, or l
b.
Exhausting through an OPERABLE Reactor Building Containment Purge System.
l CATAWBA - UNITS 1 & 2 3/4 9-4 Amendment No. 118 (Unit 1) t l
Amendment No. 112 (Unit 2) l l
1