ML20207B609
| ML20207B609 | |
| Person / Time | |
|---|---|
| Site: | 05000453, Callaway |
| Issue date: | 05/21/1999 |
| From: | Stephen Dembek NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20207B616 | List: |
| References | |
| NUDOCS 9906020044 | |
| Download: ML20207B609 (7) | |
Text
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'k UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
g WASHINGTON, D.C. 20066-0001
- 4,*****,e UNION ELECTRIC COMPANY l
CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.132 License No. NPF-30 l
l 1.
' The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Union Electric Company (UE, the licensee) dated October 27,1998, as supplemented by letters in 1999 dated January 11, January 29, February 25, April 7 (two letters), and May 17, complies with the l
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, the provisions of the i
Act, and the rules and regulations of the Commission; l
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; D.
The issuance of this amendment will not be inimical to the common defense and 1
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.
2.
Accordingly, the license is amended by 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-30 is hereby amended to read as follows:
l 9906020044 990521 PDR ADOCK 05000483 P
PDR l
l
2-(2)
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.132 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance to be implemented within 30 days from the date ofits issuance.
FOR THE NUCLEAR REGULATORY COMMISSION te en embek, Chief, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications I
Date of issuance: May 21, 1999
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l ATTACHMENT TO LICENSE AMENDMENT NO 132
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l FACILITY OPERATING LICENSE NO. NPF-30 1
DOCKET NO. 50-483 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 INSERT 3/4 4-14 3/4 4-14 3/4 4-15 3/4 4-15 3/4 4-17a 3/4 4-17a
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B 3/4 4-4 B 3/4 4-4 t
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SURVCill.ANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Cntena l
a.
As used in this specification:
1)
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if I
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; l
3)
Degraded Tube means a tube containing imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation; 4)
% Degradation means the percentage of the tube or sleeve wall thickness l
l affected or removed by degradation; l
5)
Defect means an imperfection of such severity that it exceeds the plugging or l
repair limit. A tube ar sleeve containing a defect is defective; 6)
Plunaina or Repair Limit means the imperfection depth at or beyond which the tube shall be removed from service by plugging or repaired by sleeving and is equal to 40% of the nominal tube wall thickness. The plugging limit for i
i laser welded sleeves is equal to 39% of the nominal sleeve wall thickr. ass.
. The plugging limit for Electrosleeves is equal to 20% of the nominal sleeve l
wall thickness; 7)
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating i
Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in Specification 4.4.5.3c., above; 8)
Tube inspection means an inspection of the steam generator tube from the l
point of entry (hot leg side) completely around the U-bend to the top support l
of the cold leg. For a tube repaired by sleeving, the tube inspection shall include the sleeved portion of the tube; 9)
Preservice inspection means an inspection of the full length of each tube in each steam generator performed by oddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections;
- 10) Tube Repair refers to a process that reestablishes tube serviceability.
Acceptable tube repairs will be performed by the following processes:
CALLAWAY - UNIT 1 3/4 4-14 Amendment No. 446,132
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) a)
Laser welded sleeving as described in Westinghouse Technical Report WCAP-14596-P, " Laser Welded Elevated Tube Sheet Sleeves for l
Westinghouse Model F Steam Generators." March 1996 (W Proprietary)
' b)
Electrosleeving as described in Framatome Technical Report BAW-10219P, Revision 3,10/98, "Electrosleeving Qualification for PWR Recirculating Steam Generator Tube Repair." The plugging or repair limit for the pressure boundary portion of Electrosleeves is determined to be 20% through wall of the nominal sleeve wall thickness (as determined by NDE). The 20% plugging repair limit will apply to inner diameter pits in Regions B and C.
All steam generator tubes containing an Electrosleeve will be removed from service within 2 cycles following installation of the first Electrosleeve; and 11)
Degraded Sleeve means a sleeve containing imperfections greater than 0%
but less than 20% of the nominal wall thickness caused by degradation.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair by slaeving all tubes exceeding the plugging or repair limit and all tubes containing through-wall cracks) required by Tables 4.4-2 and 4.4-3.
4.4.5.5 Reoorts a.
Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged or repaired in each steam generator shall be reported to the Commission in a Special Report pursuant to Specification 6.9.2; b.
The complete results of tha steam generator tube inservice inspection shall be submitted to the Commtssion in a Special Report pursuant to Specification 6.9.2
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within 12 months following the completion of the inspection. This Special Report shallinclude:
1)
Number and extent of tubes and sleeves inspected, 2)
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3)
Identification of tubes plugged or repaired.
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 operation. This report shall provide a description of investigations conducted to determine cause of the tube deg%EM and corrective measures taken to prevent recurrence.
CALLAWAY-UNIT 1 3/4 4-15 Amendment No. +46,132
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l TABLE 4.4-3 STEAM GENERATOR REPAIRED _TMBfJNSEED.IiQh 1" SAMPLE INSPECTION 2* SAMPLE INSPECTION Sample Slas Result Action Required Result Action Required A minimum of 20% of repaired tubes (1)(2)
C-1 None NA NA j
C2 Plug defectrwe repaired tubes C-1 None i
and inspect 100% of the repaired tubes in this S.G.
C-2 Plug defective repaired tubes C-3 Perform action for C-3 result of first sample C-3 Inspect all repaired tubes in this All other None S.G., plug defective tubes and S.G.s are inspect 20% of the repaired C-1 tubes in each other S.G.
Notification to NRC pursuant to Some S.G.s Perform action for C-2 result of
$50.72 (b)(2) of 10 CFR Part 50 C-2 but no first sarrois i
additional S.O are C-3 Additional Inspect all repaired tubes in i
S.G. is C-3 each S.G. and plug defecthre tubes. Notificatioc,to NRC l
pursuant to $50.72 (b)(2) of 10 CFR Part 50 (1) Each repair method is considered a separate population for determination of initial inservice inspection and scope expansion.
l (2) The inspection of repaired tubes may be performed on tubes from 1 to 4 steam generators based on outage plans.
l CALLAWAY - UNIT 1 3/4 4-17a Amendment No. 446,132 j
REACTOR COOLANT SYSTEM BASES STEAM GENERATORS (Continued)
The plugging or repair limit for the pressure boundary portion of laser welded sleeves is determined to be 39% through-wall (by NDE). The laser welded sleeve repair limit applicable to the pressure boundary portion of the sleeve is established in WCAP-14596. Appropriate NDE techniques are also discussed in WCAP-14596.
The plugging or repair limit for the pressure boundary portion of Electrosleeves is determined to be 20% through wall of the nominal sleeve wall thickness (as determined by NDE).
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to Specification 6.g.2 prior to resumption of 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, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE E4.4.,6.1 LEAKAGE DETECTION SYSTEMS The RCS 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.
3/4.4.6.2 OPERATIONAL LEAKAGE PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. Therefore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.
Industry experience has shown that while a limited amount of leakage is expectod from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 gpm. This threshold value is sufficiently low to ensure early detection of additional leakage.
The total steam generator tube leakage limit of 600 gpd for all steam generators not isolated from the RCS ensures that the dosage contribution from the tube leakage will be limited to a small fraction of 10 CFR Part 100 dose guideline values in the event of either a steam generator tube rupture or steam line break. The 600 gpd limit is conservative compared to the assumptions used in the analysis of these accidents. The 150 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.
The 10 gpm IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the Leakage Detection Systems.
The CONTROLLED LEAKAGE limitation restricts operation when the total flow from the l
reactor coolant pump seals exceeds 8 gpm per RC pump at a nominal RCS pressure of l
2235 psig. This limitation ensures adequate performance of the RC pump seals.
CALLAWAY - UNIT 1 B 3/4 4-4 Amendment No. 446,132
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