ML20205B305
| ML20205B305 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 03/26/1999 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205B308 | List: |
| References | |
| NUDOCS 9903310208 | |
| Download: ML20205B305 (9) | |
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t UNITED STATES g
g NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. 20555-0001 49.....,o DUKE ENERGY CORPORATION NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment Ne 176 License No. Ni; 35
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendmen; to the Catawba Nuclear Station, Unit 1 (the facility)
Facility Operating License No. NPF-35 filed by the Duke Energy Corporation, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated January 28,1999, 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 ll B. The facility will operate in conformity with the application, the provir!cns 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.
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. 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:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.176, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the faciity in accordance with the Technical Specifications.
- 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 d'
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ert N. Berkow, Director Project Directorate ll-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance:
March 26, 1999
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l ska "co y-4 UNITED STATES s
., g NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555-0001 DUKE ENERGY CORPORATION NORTH CAROLINA MUNICIPAL POWER AGENCY N_QJ PIEDMO_NT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 168 License No. NPF-52
- 1. The Nuclear Regulatory Commission (the Commission) has found that.
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A. The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) i Fcci!ity Operating License No. NPF-52 filed by the Duke Energy Corporation, acting for
!ts!!, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees), dated January 28,1999, 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 j
sec,urityor 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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- 2. Accordingly, the license is hereby amended by page changes to the Technical Specificatiens 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:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.168, nich are attached hereto, are hereby incorporated into this license. Duke Ener0y Corporation shall operate the facility in accordance with the Technical Specifications.
- 3. This license amenament is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION er ert N. Berko Director roject Directorate 11-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance: Marcii 26, 1999 i
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L ATTACHMENT TO LICENSE AMENDMENT NO.176 TO FACILITY OPERATING LICENSE NO. NPF-35 AND LICENSE AMENDMENT NO. 168 TO FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NOS 50-413 AND 50-414 Replace the following page of the joint Technical Specifications (Appendix A of the Operating i
Licenses) with the enclosed page. The revised page is identified by amendment number and contains verticallines indicating the areas of change.
Remove geg 3.7.13-2 3.7.13-2 Replace the following pages of the Technical Specifications Bases with the enclosed pages.
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The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insed B 3.7.13-1 B 3.7.131 B 3.7.13-2 B 3.7.13-2 B 3.7.13-4 8 3.7.13-4 o
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FHVES 3.7.13 SURVElLLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.13.1 Verify required FHVES train in operation.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.7.13.2 Operate required FHVES train for > 10 continuous hours 31 days with the heaters operating.
SR 3.7.13.3 Perform required FHVES filter testing in accordance with in accordance with the Ventilation Filter Testing Program (VFTP).
the VFTP SR 3.7.13.4 Verify one FHVES train can maintain a pressure 18 months on a s -0.25 inches water gauge with respect to atmospheric STAGGERED p< essure during operation at a flow rate s 36,443 cfm.
TEST BASIS l
SR 3.7.13.5 Verify each FHVES filter bypass damper can be closed.
18 months Catawba Units 1 and 2 3 7.13-2 Anendment No. 176 (Unit 1)
Amendment No. 168 (Unit 2)
e FHVES B 3.7.13 d 3.7 PLANT SYSTEMS B'3.7.13 Fuel Handling Ventilation Exhaust System (FHVES)
I BASES I
BACKGROUND The FHVES filters airborne radioactive particulates from the area of the fuel pool following a fuel handling accident. The FHVES, in conjunction with other normally operating systems, also provides environmental control of temperature and humidity in the fuel pool area.
The FHVES cons;sts of two independent and redundant trains with two filter units per train. Each filter unit consists of a heater, a prefilter, high efficiency particulate air (HEPA) filters, an activated carbon adsorber section for removal of gaseous activity (principally iodines), and a fan.
Ductwork, valves or dampers, and instrumentation also form part of the system. A second bank of HEPA filters follows the adsorber section to collect carbon fines and provide backup in case the main HEPA filter bank fails. The downstream HEPA filter is not credited in the analysis, but serves to collect carbon fines, and to back up the upstream HEPA filter should it develop a leak. The system initiates filtered ventilation of the fuel handling building following receipt of a high radiation signal.
The FHVES train does not actuate on any signal. One train is required to be in operation whenever irradiated fuel is being moved in the fue!
handling building. The operation of one train of FHVES ensures, if a fuel j
handling accident occurs, ventilation exhaust will be filtered before being j
released to the environment. The profilters remove any large particles in the air, and any entrained water droplets present, to prevent excessive loading of the HEPA filters and carbon adsorbers.
The FHVES is discussed Iri the UFSAR, Sections 6.5,9.4, and 15.7 (Refs.1,2, and 3, respectively) because it may be used for normal, e.s well as atmospheric cleanup functions after a fuel handling accident in the spent fuel pool area.
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1 APPLICABLE The FHVES design basis is established by the consequences of SAFETY ANALYSES the limiting Des *gn Basis Accident (DBA), which is a fuel handling I
accident. The analysis of the fuel handling accident, given in j
Heference 3, assumes that all fuel rods in an assembly are damaged.
The DBA analysis of the fuel nandling accident assumes that only one
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Catawba Units 1 and 2 B 3.7.13-1 Revision No.1 1
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FHVES B 3.7.13 BASES APPLICABLE SAFETY ANALYSES (continued) train of the FHVES is OPERABLE and in operation. The amount of fission products available for release from the fuel handling building is i
determined for a fuel handling accident. These assumptions and the coatysis follow the guidance provided in Regulatory Guide 1.25 (Ref. 4).
The FHVES satisfies Criterion 3 of 10 CFR 50.36 (Ref. 5).
LCO One train of the F1-;VES s required to be OPERABLE and in operation whenever irradiated fuelis being moved in the fuel handling building.
Total system failure could esult in the atmospheric release from the fuel handling building excesc ej the 10 CFR 100 (Ref. 6) limits in the event of a fuel handling accident.
The FHVES is considered OPERABLE when the individual components necessary to control exposure in the fuel handling building are OPERABLE. An FHVES train is considered OPERABLE when its associated:
a.
Fans are OPERABLE; l
b.
HEPA filters and carbon adsorbers are not excessively restricting l
flow, and are capable of performing their filtration function; and c.
Ductwork, valvt 9, and dampers are OPERABLE, and air circulation can be maintained.
APPLICABILITY During movement of irradiated fuel in the fuel handling area, the FHVES is required to be OPERABLE and in operation to alleviate the consequences of a fuel bandling accident ACTIONS 6,,1
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Required Action A.1 is modified by a Note indicating that LCO 3.0.3 does not epply.
With the movernent of irradiated fuel in the fuel handling building, one train of FHVES is required to be OPERABLE and in operation. The movement of irradiated fuel must be immediately suspended, if the train
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Catawba Units 1 and 2 B 3.7.13-2 Revision No. 1
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FHVES B 3.7.13 BASES l
SURVElLLANCE REQUIREMENTS (continued)
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' SR 3.7.13.3 This SR verifies that the required FHVES testing is performed in accordance with the Ventilation Filter Testing Progre.m (VFTP). The FHVES filter tests are in accordance with Regulatory Guide 1.52 (Ref. 7).
The VFTP includes testing HEPA filter performance, carbon adsorber efficiency, minimum system flow rate, and the physical properties of the l
activated carbon (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the VFTP.
SR 3.7.13.4 This SR verifies the integritv of the fuel building enclosure. The ability of the fuel building to maintain negative pressure with respect to potentially uncontaminated adjacent areas is periodically tested to veiify proper function of the FHVES. During operation, the FHVES is designed to maintain a slight negative pressure in the fuel building, to prevent unfiltered LEAKAGE. The FHVES is designed to maintain s -0.25 inches water gauge with respect to atmospheric pressure at a flow rate of s 36,443 cfm. The Frequency of 18 months (on a STAGGERED TEST l
BASIS) is consistent with the guidance provided in NUREG-0800, Section 6.5.1 (Ref. 8).
SR 3.7.13.5 Operating the FHVES filter bypass damper is necessary to ensure that the system functions properly. The OPERABILITY of the FHVES filter bypass damper is verified if it can be manually closed. An 1E, month Frequency is consistent with Reference D.
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Catawba Units 1 and 2 B 3.7.13-4 Revision No.1 I
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