ML20214P978
| ML20214P978 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/26/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214P982 | List: |
| References | |
| NUDOCS 8706040193 | |
| Download: ML20214P978 (5) | |
Text
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o UNITED STATES NUCLEAR REGULATORY COMMISSION 3
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DUKE POWER C0'4PANY NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDM0NT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.18 License No. NPF-52 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Doerating 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 August 6,1986, and supplemented March 5,1987, 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 aoplication, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance: (1) 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the
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common defense and security or to the health and safety of the oublic; l
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.
2.
According Facility Operating License No. NPF-57 is hereby changed as follows:
I 8706040193 870526 PDR ADOCK 05000414 P
.. A.
Change paragraph 2.C.(11) to read as follows:
Transamerica Delaval, Inc. (TDI) Diesel Generators (Section 8.3.1 55ER#5, 55ER#6, NUREG-1216)
Duke Power Company shall implement the TDI diesel requirements as specified in Attachment 1 into its maintenance and surveillance program. Attachment 1 is hereby incorporated into this license.
B.
Change Attachment 1 to NPF-52 to read as follows:
Duke Power Company shall comply with the following requirements re-lated to the TDI diesel engines for Catawba Unit 2.
1.
Changes to the maintenance / surveillance program for the TDI diesel engines, as identified in the licensee's submittals of August I and September 11, 1986, shall be subject to the pro-visions of 10 CFR 50.59. The frequency of the major engine overhauls referred to in the license conditions below shall be consistent with Section IV.I.
" Overhaul Frequency," in Revision 2 of Appendix II of the Design Review /Ouality Re-validation Report which was transmitted by letter dated May 1 1986, from J.B. George, Owners Group, to H.R. Denton, NRC.
2.
Connecting rod assemblies shall be subjected to the following in-spections at each major engine overhaul:
(a ) The surfaces of the rack teeth should be inspected for signs of fretting.
If fretting has occurred, it should be subject to an engineering evaluation for appropriate corrective action.
i (b) All connecting rod bolts should be lubricated in accor-l dance with the engine manufacturer's instructions and I
torqued to the specifications of the manufacturer.
The lengths of the two pairs of bolts above the crankpin should be measured ultrasonically before and after tensioning.
l (c) The lengths of the two pairs of bolts above the crankpin should be remeasured ultrasonically before detensioning I,
and disassembly of the bolts.
If bolt tension is less than 93% of the value at installation, the cause should be determined, aporopriate corrective action should be taken, and the inters i between checks of bolt tension should be reevaluated.
l (d)
All connecting (e.d bolts should be visually inspected for ro thread damage g., galling), and the two pairs of connecting rod bolts above the crankpin should be inspected l
l l
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by magnetic particle testing to verify the continued absence of cracking. All washers used with the bolts should be examined visually for signs of galling er cracking, and replaced if damaged.
(e) A visual inspection should be perfomed of all external surfaces of the link rod box to verify the absence of any signs of service-induced stress.
(f) All of the bolt holes in the link rod box should be inspected for thread damage (e.
of abnormalities. In addition, g., galling) or other signs the bolt holes subject to the highest stresses (e.g., the pair innediately above the crankpin) should be examined with an appropriate non-destructive method to verify the continued absence of cracking. Any indications should be recorded for engineering evaluation and appropriate corrective action.
3.
(a) Cylinder blocks shall be inspected for " ligament" cracks,
" stud-to-stud" cracks and " stud-to-end" cracks as defined in a report by Failure Analysis Associates, Inc. (FaAA) entitled " Design Review of TDI R-4 and RV-4 Series Emergency Diesel Generator Cylinder Blocks" (FaAA report no.
FaAA-84-9-11.1) and dated December 1984.
(Note that the FaAA report specifies additional inspections to be per-fomed for blocks with "known" or " assumed" ligament cracks.) The inspection intervals (i.e., frequency) shall not exceed the intervals calculated using the cumulative damage index model in the subject FaAA report.
In addition, inspection methods shall be consistent with or equivalent to those identified in the subject FaAA report.
(b) In addition to inspections specified in the aforementioned j
FaAA report, blocks with "known" or " assumed" ligament cracks (as defined in the FaAA report) should be inspected i
at each refueling outage to detemine whether or not cracks have initiated on the top surface, which was i
exposed because of the removal of two or more cylinder heads. This process should be repeated over several refueling outages until the entire block has been inspected.
l Liquid penetrant testing or a similarly sensitive non-destructive testing technique should be used to detect cracking, and eddy current testing should be used as appropriate to detemine the depth of any cracks discovered.
(c)
If inspection reveals cracks in the cylinder blocks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or " stud-to-end" cracks, this condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable. The engine shall not be restored to " operable status" until the proposed disposition and/or corrective actions have been approved by the NRC staff.
i
4.
The followino air-roll test shall be performed as specified below, except when the plant is already in an Action Statement of Technical Specification 3/4.8.1, " Electric Power Systems, A.C. Sources":
The engines shall be rolled over with the airstart system and with the cylinder stopcocks open before each planned start, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown.
(If an engine is removed from service for any reason other than the rolling-over procedure before expiration of the 8-hour or 24-hour periods noted above, that engine need not be rolled over while it is out of service. The licensee shall air-roll the engine over with the stopcocks open at the time it is returned to service.)
The origin of any water detected in the cylinder must be determined, and any cylinder head that leaks because of a crack shall be replaced.
The above air-roll test may be dis-l continued following the first refueling outage sub,iect to the following conditions:
(a) All cylinder heads are Group III heads (i.e., cast after September 1980).
(b) Quality revalidation 1.ispections, as identified in the Design Review / Quality Revalidatior. report, have been completed for all cylinder heads.
(c) Group III heads continue to demunstrate leak-free perfonnance.
This should be confirmed with TDI before air-roll tests are discontinued.
5.
Periodic inspections of the turbochargers shall include the following:
(a) The turbocharger thrust bearings should be visually inspected for excessive wear after 40 nonprelubed starts since the previous visual inspection.
(b) Turbocharger rotor axial clearance should be measured at each refueling outage to verify compliance with TDl/Elliott specifications.
In addition, thrust bearing measurements should be compared with measurements taken previously to determine a need for further inspection or corrective action.
(c) Spectrographic and ferrographic engine oil analysis shall be perforrred quarterly to provide early evidence of bearing degradation.
Particular attention should be paid to copper level and particulate size, which could signify thrust bearino degradation.
.. (d)- The nozzle ring components and inlet guide vanes should be visually inspected at each refueling outage for missing parts or parts showing distress on a one-turbocharger-per refueling-outage basis.
In addition, these inspections should be perfonned for all turbochargers at each turbocharger overhaul (i.e., at approximately 5-year intervals).
If any missing parts or distress is noted, the entire ring assembly should be replaced and the subject turbocharger should be reinspected at the next refueling outage.
6.
Main bearing No. 7 of emergency diesel generator 2B shall be dissaembled and inspected at each refueling outage, both visually and with liquid penetrant, to verify that the bearings are free of distress. Subsequent to reassembly, run-in testing shall be performed in accorandance with manufacturer's re-commendations.
FOR THE NUCLEAR REGULATORY COMMISSION
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B. J. Youngblood, Director Project Directorate II-3 Division of Reactor Projects-!/II Date of Issuance: May 26, 1987
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