ML20199E862
| ML20199E862 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/13/1997 |
| From: | Berkow H NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199E868 | List: |
| References | |
| NUDOCS 9711240016 | |
| Download: ML20199E862 (10) | |
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t UNITED STATES 3
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NUCLE /.R REGULATORY COMMISSION f
. WASHINGTON, D.C. 30e06 4001
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DUKE ENERGY CORPORATION 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 Amendment No.154 License No. NPF-52 1.
The Nuclear Regulatory Commisslor, (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 Energy Corporation, acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licer. sere, dated May 27,1997, complies with the standards and requirements of the immic Energy Act of 1954, as
- amended (ti.e 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 acdvities will be cc.nducted 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't regulations and all applicable requirements have been satisfied.
9711240016 97111344}
PDR ADOCK 050 p
_.. 2i 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:.
(2)
Technical Specifications The Technicci Specifications contained in Appendix A, as revised through Amendment No. 154, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporrtion shall operate the facility in accordance witti the Technical Soecifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ff Herbert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes.
Date oflasuance: November 13, 1997 s
i
ATTACHMENT TO LICENSE AMENDMENT NO.154 EACILITY OPERATING LICENSE NO. NPF-fi2 i
i DOCKET NO. FO-414 Replace the folkMing 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.
Bem9XA IDAAd 3/4 4-13 3/4 4-13 3/4 4-15 3/4 4-15 3/4 4-16 3/4 4-16 3/4 4-17 3/4 4-17 3/4 4-19 3/4 4-19 B 3/4 4-3 B 3/4 4-3 B 3/4 4-4 B 3/4 4-4 l'
SURVElll ANCE REOUIREMENTS (Continued 1 1)
All nonplugged tubes that previously had detectable wall penetrations (greater than 20%),
2)
Tubes in those areas where experience has indicated potential problems, and-3)
A tube inspection ()ursuant to S)ecification 4.4.5.4a.8) shall be performed on eac1 selected tu)e.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
The tubes selected as the second and third samples (if required by c.
Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:
1) 1he tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and 1)
The inspections include those portions of the tubes where s
imperfections were previously found.
l The results of e3ch sample inspection shall be classified into one of the following three categories:
Cateaory inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-?
One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5%
and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note: '
In all inspections, previously oegraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
CATAWBA - UNIT 2 3/44-13 Amendment No.154
s.
REACTOR COOLANT SYSTEJ SURVEILLANCE REOUIREENTS (ContinuedI 4.4.5.4 Acceptance C'riteria a '. ' As L. sed-in this spectfication:
1)
Imoerfection means an exception to the dimensions, finish or contour of a tube.from that required by fabrication drawings or l
s )ecifict.tions. Eddy-current testing indications belex 20% of tie nominal tube wall thickness, if detectable, er se l
considered as imperfections; 2)
Dearadation means a service-induced tracking,
~ wastage, wear or general corrosion occur L., on either inside or outside of a tube; I
i
'3)
Dearaded Tube means a tube containing imperfections greater than.
or equal to 20% of the nominal tube wall thickness caused by degradation; 4)
% Dearadation means the percentage of the tube wall thickness l
affected or removed by degradation; 5)
Cefect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective;-
l 6)
Pluaaina Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging. The plugging limit-is equal to 40% of*the nominal tube wall thickness.
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 ilasis Earthquake, a loss-of-coolant accidtat, or a steam line or feedwater line break as specified in 4.4.5.3c., above; 8)
Tube Insoection means an inspection of the steam generator tube from '.he point.of entry (hot leg side) completely around the U-bend to the top support of the cold leg; 4
CATAWBA - UNIT 2 3/44-15 Amend:nent No.154
BEACTOR COOLANT SYSTEM
! SURVEILLANCE REOUIREMENTS (Continued) 9)
Preservice inspection means an inspection of-the full length of each tube in each steam generator perfomed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be perfomed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections..
b.
The steam generator shall be determined OPERABLE after completing the cor esponding actions (plug all tubes exceeding the plugging limit l
andalltubescontainingthrough-wallcracks)requiredby Table 4.4-2.
4.4.5.5 Reports a.
Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged in each steam I
generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; b.
The complete results of the steam generator tube inservice inspeccion shall be submitted to the Commission in a Special Roort pursuant to Specification 6.9.2 withi 2 months following the completion of the inspection. This Special Report shall include:
CATAWBA - llNIT 2 3/44-16 Amendment No.154
RfACTOR COOL ANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued) 1)
Number and extent of tubes inspected, 2) locat'on and percent of wall-thickness penetration for each indication of an imperfection, and 3)
Identificatf 7n of tubes plugged.
l c.
Results of steam generator tube inspections, which fall into Category C-3, shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days and prior to resumption of plant operat:on. This report shall provide a description cf investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
CATAWBA - UNIT-2 3/44-17 Amendment No.154
TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION e-IST SAMPLE IN$ifCT'ON 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required,
Result Action Required A minimum of S C-1 None N.A.
N.A.
M.A.
N.A.
Tubes per 5.G.
C-2 Plug defective tubes C-1 Mone M.A.
N.A.
i and inspect additional 25 tubes in this S.G.
C-2 Plug defective tubes C.1 None l
and inspect additional 45 tubes.in this S.G.
C-2 Plug defective tubes C-3 Perform action for C-3 result of first sample C-3 Perform action for C-3 N.A.
M.A.
t result of first sample C-3 Inspect al tubes in All other Mone N.A.
M.A.
this 5.G., plug S.G.s are C-1 defective tubes and 5 I" S['Cfher 5 me 5.G.s C-Perform action for C-2 N.A.
N.A.
g o 2 but r.-
result of second sample addittoi.. !
Notification to NRC S.G. are C-3 pursuant to 550.72(b)(2) of 10 CFR Additional Inspect all tubes in M.A.
M.A.
Part 50.
S.G.is C-3 each S.G. and plug defective tubes.
Notification to NRC pursuant to $50.72 (b)(2) of 10 CFR 50.
5 = 3 (N/n)% Where N is the number of steam generators in the unit, and n is the number of steas generators inspected during an inspection.
I CATAl!BA - UNIT 2 3/4 4-19 Amendment No.154
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REACTOR COOLANT SYSTEM BASES RELIEF VALVES (Continued) of PORVs to control 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 PORY and/or block valve is closed because of testing and is fully capable of being returned to its normal alignment at any time, provided that 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 contral of a block valve to isolate a stuck-open PORV.
Testing of the PORVs includes the emergency N2 supply from i
the Cold Leg Accumulators. This test 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 PORY operation.
3/4.4.5 STEAM GENERA;0RS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the Rcactor Coolant System will be maintained. The program for inservice inspection of steam gen-erator 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 coaditions 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 tuba degradation so that corrective measures can be taken.
l 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 chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the Reactor Coolant System and the Secondary Coolant System (reactor-to-secondary leakage = 150 gallons per day per steam generator).
CATAWBA - UNIT 2 B3/44-3 Amendment No.154-
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REACTDR COOLANT SYSTEM-BASES-STEAM GENERATOR; (Continued) l Cracks having a freactor-to-secondary leakage less than this limit during operation wi' I have.an adequate margin of safety to withstand the' loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that reactor-tc secondary _ leakage of 150 gallons per day per steam generator can readily be detected. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking
' tubes will be located and repaired.
Wastage-type defects are unlikely with' proper chemistry treatment of the i
secondary coolant. _ However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
-Plugging will be required for all tubes with imperfections exceeding the plugging-limit of 40% of the tube nominal wall thickness.
Steam generator tube inspections of operating plants have demonstrated the capability to reliaoly-detect wastage type degradation that has penetrated 20% of the original: tube wall thickness.
l
_ -Whenever the results of-any steam generator tubing inservice inspection
-fall into Category C-3, these results will be reported to the Commission pur-suant to Specification 6.9.2: prior to resumption cf plant operation. Such cases will be considered by the Commission on a case-by-case basis and may
~
result in a requirement for analysis, laboratory. examinations, tests, addt-tional eddy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.6 REArTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEN6 1The Leakage Detection Systems required by this specification are provided to monitor and detect leakage from the reactor coolant-pressure boundary.
These Detection Systems are consistent'with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973~.
..i CATAWBA - UNIT 2' B3/4_44 Amendment No. 154
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