ML20094D171
| ML20094D171 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/30/1995 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094D174 | List: |
| References | |
| NUDOCS 9511030196 | |
| Download: ML20094D171 (7) | |
Text
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@ Effo Y
t UNITED STATES f
j NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. 20066 4001
.....,o DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 i
CATAWBA NUCLEAR STATION. UNIT 1 I
I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.136 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 Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated April 10, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, 1
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.
9511030196 951030 PDR ADOCK 05000413 P
PDR I
. 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.136
, and the Environmental Protection Plan 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 license amendment is effective as of its date of issuance and shall l
l be implemented within 30 days from the date of issuance.
l l
FOR THE NUCLEAR REGULATORY COMMISSION f.
e H bert N. Berk w, Director P oject Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: October 30, 1995
s asa uq t
UNITED CTATES I
Ij NUCLEAR REGULATORY dOMMISSION e
WASHINGTON, D.C. 20066 4 001
'+4 * * * *
- g o
DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE j
Amendment No. 130 License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba 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 April 10, 1995, complies with the standards and r
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; 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.
. ~
1 i
i '
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.
4 NPF-52 is hereby amended to read as follows:
T_e_chnical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.130
, and the Environmental Protection Plan 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 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 He bert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
October 30, 1995
&TTACHMENT TO LICENSE AMENDHENT NO.136 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 MQ TO LICENSE AMENDMENT NO.130 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 6-40 3/4 6-40 B 3/4 6-4 B 3/4 6-4 4
CONTAINMENT SYSTEMS HYDROGEN MITIGATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.4.3 Both trains of the Hydrogen Mitigation System shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTION:
With one train of the Hydrogen Mitigation System inoperable, restore the inoperable train to OPERABLE status within 7 days or decrease the surveillance interval of S)ecification 4.6.4.3a. from 92 days to 7 days on the OPERABLE train until tie inoperable train is returned to OPERABLE status.
j SURVEILLANCE REQUIREMENTS 4.6.4.3 Each train of the Hydrogen Mitigation System shall be demonstrated OPERABLE:
a.
At least once per 92 days by energizing the supply breakers and verifying that at least 34 of 35 igniters are energized,* and l
b.
At least once per 18 months by verifying the temperature of each igniter is a minimum of 1700*F.
- Inoperable igniters must not be on corresponding redundant circuits which provide coverage for the same region.
CATAWBA - UNITS 1 & 2 3/4 6-40 Amendment No.136 (Unit 1)
Amendment No.130 (Unit 2)
CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS The OPERABILITY of the Containment Spray System ensures that containment depressurization and cooling capability will be available in the event of a LOCA. The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the safety analyses.
However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere, and therefore the time requirements for restoring an ino)erable Spray System to OPERABLE status have been maintained consistent with tiose assigned other inoperable ESF equipment.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR Part 50. Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environ-ment will be consistent with the assumptions used in the analyses for a LOCA.
3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit is capable of controlling the expected hydrogen generation associated with:
(1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of metals within containment. These Hydrogen Control Systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations Following a LOCA," March 1971.
The OPERABILITY of at least 34 of 35 igniters per train (68 of 70 for l
both trains) ensures tha6 the Distributed Ignition System will maintain an effective coverage throughout the containment provided the two inoparable ignitors are not on corresponding redundant circuits which provide coverage for the same region. This system of igniters will initiate combustion of any significant amount of hydrogen released after a degraded core accident. This system is to ensure burning in a controlled manner as the hydrogen is released instead of allowing it to be ignited at. high concentrations by a random ignition source.
CATAWBA - UNITS 1 & 2 B 3/4 6-4 Amendment No.136 (Unit 1)
Amendment No.130 (Unit 2)
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