ML20099J824
| ML20099J824 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/14/1992 |
| From: | Mathews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099J829 | List: |
| References | |
| NUDOCS 9208210243 | |
| Download: ML20099J824 (7) | |
Text
.g~y#
M h
UNITED STATES
- . 3 ~
i NUCLEAR REGULATORY COMMISSION WASHINoTON, D.C 20666 a.4*****/
=
DVKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-411 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENS_E Amendment No. 99 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-3S filed by the Duke. Power Company,- acting for itself, North Carolina Electric Membership-Corporation and Saluda River Electric Cooperative, Inc.
(licensces) dated May 19, 1992, as supplemented' June 15 1992, 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 i_s 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.
- 9208210243 920E'14 -..
'PDR ADOCK 03000413 P
i
' )
)
2.
Accordingly, the license is hereby amended by p=ce 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 Specification _1 The Technical Specifications contained in Appendix A, as revised through Amendment No. 99, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
/*
- l. L.
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: -August 14, 1992
'fp esov,"'a
(*'
y UNITED STATES j'
'i NUCLEAR REGULATORY COMMISSION I
WASHINoTON, D.C 20666
\\* *l DUKE POWER COMPANY NORTH CAROLINA Mt)fNICIPAL POWER AGENCY NO. 1 PIEDM0NT MUNICIPAL POWER AGENCY.
DOCKET NO, 50-414 CATAWBA NUCLEAR STATION.jlNJLZ AMENDMENT TO FACILITY OPERATING LICENS1 Amendment No. 93 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Comission) 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 dunicipal Power Agency (licensees) dated May 19, 1992, as supplemented June 15, 1992, 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 Comission; 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 ( i) that such _ activities will be.
conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I;.
D.
The ' issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
w.
v m
-m
- - - ~
~
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:
J31bnical Specifications
-The Technical Specifications contained in. Appendix A, as revised
-through Amendment No. 93, and-the Environmental Protection P1an
-contained in-Appendix B, both of which are-attached hereto, are hereby incorporated into this license.
Duke Power Con:pany 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 fl
' avid 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:
August 14, 1992 i.
1
_..___,2-
ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-411 MQ TO LICENSE AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. NPF-52 Q.0CKET 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 Pages Insert Paaes t,}]lll 3/4 4-15 3/4 4-15 B 3/4 4-3 B 3/4 4-3 I
_m
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria a.
As used in this specification:
1)
Imperfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specificctions.
Eddy-current testing indications below 20% of the nominal tube or sleeve wall thickness, if detectable, may be considered as imperfections; 2)
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve; 3)
Degraded Tube means a tube or sleeve containing imperfections greater than or equal to 20% of the nominal tube or sleeve wall thickness caused by degradation; 4)
% Degradation means the percentage of the tube or sleeve wall thickness affected or removed by degradation; a
5)
Defect means an imperfection of such severity that it exceeds the repair limit.
A tube or sleeve containing a defect is defective; 6)
Re) air Limit means the imperfection depth at or beyond which the tuae shall be removed from service by plugging or repaired by
- sleeving, It also means the imperfection depth at or beyond which a sleeved tube shall be plugged.
The repcir limit is equal to 40% of the nominal tube or sleeve wall thickness.
For Unit 1, this definition does not apply to the region of the tube subject to the alternate tube plugging criteria.
If a tube is sleeved due to degradation in the F* distance, then any defects found in the tube below the sleeve will not necessi-tate plugging.
The Babcock & Wilcox process described in Topical Report BAW-2045(P)-A, Rev. 1 will be used for sleeving.
l 7)
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integ-rity in the event of an Operating Basis Earthquake, a loss of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3c., above; 8)
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U bend to the top support of the cold leg; CATAWBA - UNITS 1 & 2 3/4 4-15 Amendment No. 99 (Unit 1)
Amendment No. 93 (Unit 2)
.l _
REACTOR COOLANT SYSTEM BASES RELIEF VALVES (Continued) reactor coolant system pressure except for limited periods where the PORV has been isolated due to excessive seat leakage and except for limited periods where the PORV and/or block valve is closed because of testing and is full-capable of being returned to its normal alignment at any tima, provided th'at this evolution is covered by an approved procedure.
This is a function that reduces challenges to the code safety valves for overpressurization events.
- 5) Manual control of a block valve to isolate a stuck-open PORV.
Testing of the PORVs includes the emergency N supply from the Cold Leg Accumulators.
This test 2
demonstrates that the valves in the supply line operate satisfactorily and that the nonsafety, portion of the instrument air system is not necessary for proper PORV operation.
3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the Reactor Coolant System will be maintained.
The program for inservi a inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to main-tain-surveillance of the conditions of the tubes in the' event that there is evidence of mechanical damage or progressive degradation due to design, manu-
-facturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradatioa so that corrective measures can be taken.
The BW process (or method equivalent) to the inspection method described in TopicJ Report BAW-2045(P)-A Rev Inservice inspection of l
steamge.2ratorsleevesisalsore.1,willbeused.
quired to ensure RCS integrity.
Because the sleeves-introduce changes in the wall thickness and diameter, they reduce the sensitivity of eddy nrrent testing, therefore, special ins)ection methods must be used.
A method is described in Topical Report BAW-2045 ))-A, Rev. I with l
suppm+ingvalidationdatathatdemonstratestheinspectab(ilityofthesleeve and-Srlying tube. As required by NRC for licensees authorized to use this rep-process, Catawba commits to validate the adequacy of any system that is useo ror periodic inservice inspections of the sleeves, and will evaluate and, as deemed appropriate by Duke Power Company, implement testing methods as better methods are developed and validated for commercial use.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant enemistry is not maintained within these limits, localized corrosion may likely result in stress ccrrosion cracking.
The extent of cracking during plant opera-tion would be limited by the limitation of steam generator tube leakage betwaen the Reactor Coolant System and the Secondary Coolant System (reactor-to-secondary leakage = 500 gallons per day per steam generator).
Cracks having a reactor-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents.
Operating plants have demonstrated that reactor-to-secondary leakaa af 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown.
Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and repaired.
CATAWBA - UNITS 1 & 2 B 3/4 4-3 Amendment No. 99 Unit 1 Amendment No. 93 Unit 2