ML20072F206
| ML20072F206 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/16/1994 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20072F202 | List: |
| References | |
| NUDOCS 9408230246 | |
| Download: ML20072F206 (5) | |
Text
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(4)
Emergency Planning (Section 13.3, SER and SSERs 2, 3, 4, and 51 In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication, that a major substantive oroblem exists in achieving or maintaining an adequate state of emergency preoaredness, the orovisions of 10 CFR Section 50.54(s)(2) will apply.
(5)
Steam Generator Tube Ruoture (Section 15.6.3, SER and SSER 3)
By March 1,1988, GPC shall submit for NRC review a revised plant-soecific steam generator tube rupture analysis based on j
the Westinghouse Owner's Group generic resolution, which includes radiological consequence analyses, analysis of steamline static load in the event of overfill, and justification that systems and components credited in the analysis to mitigate accident con-sequences are safety related.
he[cP (6) tr:=:me Deleve!. Ian MI) Cia;el 0;c.ereten t5e stM and sstxs 4 and b)
GPC shall implement the M di.;d.
a=
rator requirements as specified in Attachment 1.
Attachment s n., ey i orocrated into this license.
(7)
NUREG-0737 Items a.
Compliance with NUREG-0737. Item II.F.2 (Section' 4.4.8 SER and SSERs 1 and 4)
In accordance with NUREG-0737. Item II.F.2, GPC shall submit the proposed reactor vessel level instrumentation systerr (RVLIS) report by June 1, 1987.
b.
Supolemental Report on Safety Parameter Display System (Section 18.2, SSER 6)
GPC shall submit by March 1,1988, a supplemental' report on the safety. parameter display system as discussed in Section 18.2 of SSER 6.
Supoiemental Sumary Report on Detailed Control Room Design c.
Review (Section 18, SSER 5)
GPC shall submit by March 1,1988, a Supolemental Sumary Reoort on the detailed control room design review discussing:
1.
the final results of the remaining control room surveys (ambient noise'; illuminationi heating, ventilation, and air conditioning; olant safety monitoring system comeuter survey'; automatic turbine supervisory instrumentation computer survef; and comunications) and the resolution of any human engineering discrepancies (HEDs) resulting from these surveys 940823024694003g24 fDR ADOCK 05000 PDR
H.
Reporting to the Commission Except as otherwise orovided in the Technical Specifications or Environ-mental Protection Plan, GPC shall report any violations of the require-1 ments contained in Section 2.C. of this license in the following manner:
initial notification shall be made within twenty-four (24) hours to the NRC Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
The licensees shall have and maintain financial protection of such tyoe I.
and in such amounts as the Commission shall require in accordarce with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability clairs.
This license is effective as of the date of issuance and shall exofre at-J.
midnight on January 16, 2027.
FOR THE NUCLEAR REGULATORY COMMISSION l
Harold R. Denton, Director Office of Nuclear Reactor Regulation 1.
Attachment !
-T0! Requt ;r:< - De/e7kec/
Enclosures:
2.
Apoendix A - Technical Specifications i
3.
Appendix B - Environmental Protection Plan 4
Appendix C - Antitrust Conditions Date of Issuance:
March 16, 1987 v
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AMAGHMEXT 1 inMgust-ypp41 TDI DIESEL ENGINE REOUIREMENTS anges to the maintenance and surveillance programs for the TOI diesel 1.
ines, as identified in Section 9.5.4.1 of Sucolement 4 to the Vogtle e
El tric Generating Plant Safety Evaluation. Report, shall be subject to
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the rovisions of 10 CFR 50.59.
The fr uency of the major engine overhauls referred to in the license conditio s below shall be consistent with Section IV.I. " Overhaul in Revision 2 of Appendix !! of the Design Review /Ouality Frequency Revalidati report which was transmitted 'by letter dated May 1,1986, from J. Geor
, Owners Group, to H. Denton, NRC.
2.
Connecting rod semblies shall be subjected to the following inspections at each major eng e overhaul:
a.
The surfaces of e rack teeth shall be inspected for signs of fretting.
If fretting has occurred, it shall be subject to an engineering evaluat1 n for appropriate corrective action.
b.
All connecting-rod bo s shall be lubricated in accordance with instructions and torqued to the speciff-the engine manufacturer The lengths of the two cairs of bolts cations of the manufactu r.
above the crankoin shall b measured ultrasonically pre-and post-tensioning, c.
The lengths of the two pairs o olts above the crankpin shall be etensioning and disassembly of the measured ultrasonically orior -to If bolt tension is less thAq 93% of the value at installation, bolts.
the cause shall be detemined, aoorocriate corrective action shall be taken, and the interval between ch cks of bolt tension shall be re-evaluated.
d.
All connecting-rod bolts shall be visual inspected for thread connecting rod bolts damage (e.g. galling), and the two pairs o above the crank pin shall be insoected by ma netic carticle testing (MT)toverifythecontinuedabsenceofcrackkg. All washers usea with the bolts shall be examined visually for si ns of galling or cracking, and reolaced if damaged.
Visual inspection shall be perfonned of all externa surfaces of e.
the link rod box to verify the absence of any signs o service induced distress.
All of the bolt holes in the link rod box shall be inspected for f.
thread damage (e.g., galling) or other signs of abnomalitths.
In addition, the ooit holes subject to the highest stresses 0.e.,
the pair irrinediately above the crankoin) shall be examined wit an cf aporocriate nondestructive method to verify the continued absen \\
cracking.
Any indications shall be recorded for engineering evaluation and appropriate corrective action.
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2.
The cylinder blocks shall be subjected to the following inspections at the interval specified in the inspections:
Cylinder blocks shall be inspected for " ligament" cracks, " stud-to-stud" cracks and " stud-to-end" cracks as defined in a report
- by Failure a
alysis Associates, Inc. (FaAA) entitled, " Design Review of T01 and RV-4 Series Emergency Diesel Generator Cylinder Blocks" R
dated December 1984.
(Note that report no. FaAA-84-9-11.1),
(Fa AA report specifies additional inspections to be perfonned for the-with "known" or " assumed" ligament cracks). The inspection block s (i.e., frequency) shall not exceed the intervals calculated interv cumulative damage index model in the subject FaAA report.
using th the inspection method shall be consistent with or equiv-In additi alent to t se identified in the subject FaAA report.
nspections specified in the aforementioned FaAA b.
In addition t i ith "known" or " assumed" ligament cracks (as defined 1
report, blocks in the FaAA repo t) shall be inspected at each refueling outage e or not cracks have initiated on the top surface to determine whet al of two or more cylinder heads. This process exposed by the shall be repeated o r several refueling outages until the entire -
Liquid-cenetrant testing or a block too has been in oected.
similarly sensitive no estructive testing technique shall be used i
to detect cracking, and dy current shall be used as appropriate to detennine the death o ny cracks discovered.
c.
If inspection reveals crack in the cylinder blocks between stud holes of adjacent cylinders tud-to-stud" cracks) or " stud-to-end" cracks, this' condition shall b reported oromptly to the NRC staf f and the affected engine shall be considered inoperable. The engine 1
shall not be restored to "operabl " status until the proposed disposition and/or corrective acti s have been approved by the NRC staff.
4 The following air roll test shall be perfo d as specified below, except when the plant is already in an Action State nt of Technical Soccification 3/4.8.1, " Electric Power Systems A.C. Sources ':
The engines shall be rolled over with the'airsta system and with the cylinder stoccocks open orior to each planned star. 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 s 11 also be rolled over with the airstart system and with the cylinder s pcocks open after and then rolled 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but not more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutd (In the event 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 shutd
. the rolling an engine is removed from service for any reason other th periods over procedure prior to expiration of the 8-hour.or 24-hou noted above, that engine nesd not be rolled over while it is out of stoccocks service. The licensee shall cir roll the engine over with th open at the time it is returned to service).
The origin of an water i
This recort was transmitted to H. Denton, NRC, from C. L. Ray, Jr.,
l Owners Group, by letter dated December 11, 1984 c
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T detected in the cylinder must be determined and any cylinder head which eaks due to a crack shall be replaced. The above air roll test may be-1 continued following the first refueling outage subject to the fo owing conditions:
,,X a.
A cylinder heads are Grouc !!!' heads (i.e., cast after September 19 b.
Qualit revalidation inspections, as identified in the Design Review /
lity Revalidation report, have been completed for all cylinder ads.
c.
Group III he s continue to demonstrate leek-free oerformance.
This should be onfirmed with TDI prior to deleting air roll tests..
v 5.
Periodic inspections the turbochargers shall include the followino:
a.
The turbocharger thru bearings shall be visually inspected for excessive wear after 40 on-prelubed starts since the previous visual inspection.
ance shal' be measured at each 1
b.
Turbocharger rotor axial cle refueling outage to verify c iance with TDI/Elliott specifications.
In addition, th st bearing measurements shall be-g comoared with measurements taken a viously to determine a need for,,
further inspection or corrective ac on.
c.
Spectrographic engine oil and ferrograp c engine oil (wear) analysis shall be performed quarterly to provide e ly evidence of bearing.
degradation.
Particular attention shall b aid ta cooper level and particulate size which could signify th
't bearing degradation.
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