ML20035F558
| ML20035F558 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/16/1993 |
| From: | Mccoy C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20035F559 | List: |
| References | |
| MSV-01365, MSV-1365, NUDOCS 9304220028 | |
| Download: ML20035F558 (4) | |
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- Georg a Power Company 40 loverness Center Pa*way Post O*fce Box 1295 Bi,eming%m Alabama 35201 Te phone 205 E77-7122 e
h Georgia Power C.K.McCoy Vce Premdent. fJuclear vogue Prosc' April 16, 1993 MSV-01365
- 5068 t
Docket No. 50-425
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U. S. Nuclear Regulatory Commission i
ATTN: Document Control Desk Washington, D. C.
20555 i.
Gentlemen:
V0GTLE ELECTRIC GENERATING PLANT - UNIT-2 j
REVISION 5 TO INSERVICE INSPECTION PROGRAM i
In accordance with the requirements of Technical Specification 4.0.5 concerning surveillance requirements, Georgia Power Company (GPC). submits for NRC review and approval ten copies of Revision 5 to the Vogtle Electric e
Generating Plant, Unit 2 (VEGP-2) Inservice Inspection (ISI) Program, ISI-P-014. The ISI program currently in effect was written to the requirements of the 1983 Edition of the ASME Section XI Code with Addenda through Summer 1983. The enclosed documents supersede portions of the original ISI program document previously submitted to the NRC.. A summary of changes resulting from the revision is provided in the enclosure and precedes the affected document pages.
l The Revision 5 changes to the ISI program includes the following:
I o Revision of existing Relief Request RR-12, o Addition of Relief Request RR-57, o Revision of Line Designation List, and i
j-o Minor editorial changes, e.g., correction of typographical errors.
4 Relief Request RR-12 was previously submitted to the NRC in the original j
ISI program for VEGP-2 and addressed limitations in performing the volumetric examination of pressure-retaining welds associated with the pressurizer. Specifically, Attachment I to the relief request was revised ~
in Revision 5 to the VEGP-2 ISI program to reflect current examination coverage percentages for certain components.
Each of the pressurizer nozzles at VEGP-2 has a ridge which prohibits proper ultrasonic transducer 1
contact for weld examinations. The examinations performed during the preservice inspection (PSI) utilized shear wave transducers. Sub:equently, '
i the NRC recommended.the use of longitudinal wave transducers for the.
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U. S. Nuclear Regulatory Commission MSV-01365 Page Two examination of bimetallic welds such as the pressurizer nozzle-to-safe end welds at VEGP-2.
Because longitudinal waves are significantly affected by uneven outside diameter (OD) part geometry, it was decided to machine the subject welds on selected nozzles. During VEGP-2 Outage 2R2, the four 6" pressurizer safety nozzle-to-safe end welds (Weld Nos. 21201-V6-002-W017 through WO20) were machined using controlled grinding. The intention was to blend the welds to allow better examination coverage.
Utilizing longitudinal wave transducers in lieu of the shear wave transducers does not allow equal examination coverage. As a result, Attachment I was revised to reflect the current percentage of examination coverage obtained resulting from the machining performed and use of the longitudinal wave transducers. Typically, the percentage of examination coverage increased for both the nozzle and safe end sides of the affected welds.
In addition, a footnote was added to the Attachment I table indicating that the surface conditioning performed during VEGP-2 Outage 2R2 and utilization of more effective examination techniques, i.e., use of longitudinal wave transducers, resulted in different examination coverage percentages than those recorded during the PSI. The intent of Relief Request RR-12 remains unchanged as a result of its revision.
Examination methods and techniques are periodically reviewed to enhance our inservice inspections. As a result, other welds in Relief Request RR-12 may be examined using other techniques at a later date during the normal course of inspections and the relief request will be updated at the appropriate time to reflect the percentage of examination coverage achieved using any improved techniques.
Relief Request RR-57 is being added to the VEGP-2 ISI program in order to comply with a verbal request made by the NRC Vogtle Licensing Project Manager on December 9, 1992.
The relief request addresses the performance of nondestructive examination of the reactor pressure vessel (RPV) outlet nozzle-to-vessel (shell) welds, their inside radius sections, and associated nozzle-to-safe end welds during the second inspection period.
The subject examinations were not performed during the first inspection period for reasons discussed in GPC letter MSV-00821 dated March 17, 1992 to the NRC. Specifically, it was the intent of GPC to re-schedule the RPV outlet nozzle examinations to be done coincident with the examination of the RPV inlet nozzle examinations such that they would all be performed at one time.
It was proposed that such examinations take place during the ISI ten-year outage and would allow savings in contractor costs, critical path time, radiation exposure, and internal manpower requirements. GPC cited an ASME code interpretation and the NRC's approval of a similar re-scheduling plan for another utility as its basis for the planned re-scheduling of the RPV nozzle examinations and their associated components, i.e., safe end welds. Verbal discussions between GPC, Southern Nuclear Operating Company, and NRC staff personnel ensued after the March 17, 1992 submittal to the NRC.
It was indicated to NRC staff personnel that examination of the RPV outlet nozzles and their associated components could not be performed 700776
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GeorgiaPowerd i
U. S. Nuclear Commission MSV-01365 l
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during an outage which was _in progress at the time because of logistical problems and was acknowledged. Subsequent review by the NRC, as documented j
j in its letter to GPC dated July 30, 1992, indicated that the re-scheduling plans were unacceptable and should not be implemented. The examination schedules will be adjusted for the affected components during the next revision of the ISI examination plan document (ISI-P-013) in order to better comply.with the scheduling requirements of the ASME Section XI Code.
4 Since the RPV outlet nozzles and their associated components were not l
j examined during the first inspection period, GPC committed to the NRC to i
perform the necessary examinations during the next regularly scheduled maintenance / refueling outage. That commitment.was made to the NRC in GPC letter MSV-01184 dated November 20, 1992 and is reiterated by this j
submittal and the enclosed relief request.
It shall be noted that the RPV j
outlet nozzles and their associated components have been scheduled to be examined during VEGP-2 Outage 2R3 which is currently scheduled to begin in i
September 1993.
i The Line Designation List was revised to delete certain Reactor Coolant System (RCS) lines as a result of plant modifications.
Specifically, the i
lines associated with the RTD Bypass have been deleted from the Line Designation List.
l The remaining changes in Revision 5 to the VEGP-2 ISI program are editorial in nature.
Please refer to the enclosed Summary of Changes for specific changes to existing relief requests.
Incorporation of the editorial changes does not change the intent of the affected relief requests.
The NRC is requested to review and grant approval of the enclosed ISI program revision in accordance with 10 CFR 50.55a'(g) (6) (1). The subject changes do not affect public health and safety.. Approval of the enclosed-
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revision of the VEGP-2 ISI program is requested by August 31, 1993.
i Should there be any questions in this regard, please contact this office at l
your earliest convenience.
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Sincerely, f
f' C. K. McCoy 3
CKM/ 4 /jae l
Enclosure:
Revision 5 to VEGP-2 ISI Program ISI-P-014 4
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k Georgia Power n U. S. Nuclear Regulatory Commission MSV-01365 Page Four xc: Georaia Power Company l
Mr. S. H. Chesnut (w/o encl.)
l Mr. M. Sheibani (w/o encl.)
Mr. W. B. Shipman (w/ encl.)
NORMS (w/ encl.)
i U. S. Nuclear Reculatory Commission l
Mr. S. D. Ebneter, Regional Administrator (w/ encl.)
Mr. D. S. Hood, Licensing Project Manager, NRR (w/ encl.)
Mr. B. R. Bonser, Senior Resident Inspector, Vogtle (w/ encl.)
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