ML20212E561
| ML20212E561 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/22/1986 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| SL-1766, NUDOCS 8701050355 | |
| Download: ML20212E561 (3) | |
Text
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Georgia Power Company J
3 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526-6526 Maihng Address:
Post Office Box 4545 Atlanta, Georgia 30302 GeorgiaPower T[h66W" L T. Gucwa Manager Nuclear Safety and Licensing 1006C December 22, 1986 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 INSPECTION REPORT 86-32 Gentlemen:
The following information is submitted in response to the notice of violation cited in NRC Inspection Report Hos.
50-321/86-32 and 50-366/86-32, dated November 20, 1986.
The report concerns the inspection performed by Messrs. J. E. Menning and R.
W.
Newsome from September 29 through October 3,1986, and October 14 through 17, 1986.
NRC NOTICE OF VIOLATION:
"10 CFR Part 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings," require that activities affecting quality shall be prescribed by documented instructions, procedures, or
- drawings, of a
type appropriate to the circumstances and that the activities be accomplished in accordance with these instructions, procedures, or drawings, also Natch Unit 2 Technical Specification 6.8.1.a and paragraph 1.0 of Appendix A to Regulatory Guide 1.33, Revision 3 require that general procedures be implemented for control of Inservice Inspection.
Contrary to the above, an activity affecting quality was not accomplished in accordance with general procedures for control of Inservice Inspection (ISI).
On September 30, 1986, in the Hatch Unit 2 Drywell, at the 156' level, two ISI Liquid Penetrant (PT) examiners were observed mistakenly conducting examinations on two loop "B"
Reactor Recirculation System welds 2B31-1 RCM-12BE-3, Item No. B9.11, Pipe to Safe-End, isometric drawing number A-15 and 2B31-lRCM-28BS-2, Item No. 89.11, Safe-End 'to -
isometric drawing number A-18, which do not require examination
- Elbon, The examiners were unaware that they had incorrectly during this outage.
identified the above walds as Loop "B" Reactor Recirculation System welds 2B31 -1 RC-12BR-E-5, Item No. B5.10, Reactor Yessel Nozzle to Safe-End, isometric drawing number A-15 and 2831-1RC-288-1, Item No. 85.10, Reactor gloso355861222
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s Georgia Power A U. S. Nuclear Regulatory Commission Document Control Desk December 22, 1986 Page 2 Vessel Nozzle to Safe-End, isometric drawing number A-18 which do require examination during this outage.
As a resul t, the welds which require examination would not have been examined but would have been reported as having been examined.
This is a Severity Level IV violation (Supplement I)."
RESPONSE TO NRC NOTICE OF VIOLATION:
Admission or Denial of alleged violation: The event occurred.
Reason for violation:
Two examiners contracted by Southern Company Services, Inc. (SC5) did not properly identify the welds targeted for PT examination.
The violation is attributed to personnel error. Contributing factors were:
1.
The contractor examiners did not avail themselves of the appropriate isometric drawings needed to positively identify / locate the welds.
2.
The welds which were examined in error are located approximately 6 inches from the target welds.
3.
The welds could not be located easily due to flush surface conditions.
Corrective steps which were taken and the results achieved:
Following the event, the two contractor examiners who performed the inspection were removed as team leaders and were designated to assist other Level II or III exaniners for the remainder of the outage.
It should be notad that the two subject welds were the only welds which the two contract examiners inspected independently.
The two welds in question were reexamineJ on September 30 and October 1,1986, by other certified examiners.
SCS and contractor personnel were verbally instructed to carry the isometric drawings during the remaining inspections to ensure accurate weld identification.
Prior to and following the occurrence of the violation, SCS Level II and III personnel performed several spot checks on examination teams to ensure positive weld identification.
The frequency of the spot checks was increased following the violation.
The results of the spot checks were satisfactory.
In addition to the above, the SCS oversight group was counseled on the need for adequate supervision for the performance of the ISI program.
l 1006C i
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Georgia Power A U. S. Nuclear Regulatory Commission Document Control Desk December 22, 1986 Page 3 Corrective steps which will be taken to prevent recurrence:
A training checklist, which will instruct examiners to have the appropriate isometric drawings present during an inspection, is being developed.
In addition, the checklist will instruct examiners to consul t with SCS personnel if any uncertainty regarding examination parameters occurs.
The training checklist will be in place by March 31, 1987, which is prior to the next refueling outage.
Date when full compliance was achieved:
Full compliance was achieved on October 1,1986, when the welds in question were reexamined.
If you have any questions in this regard, please contact this office at any time.
Sincerely, f g
=.
L. T. Gucwa MJB/lc c: Georgia Power Comcany U. S. Nuclear Regulatory Commission Mr.t. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr.
Mr. P. Holmes-Ray, Senior Resident Mr. H. C. Nix, Jr.
Inspector - Hatch GO-NORMS 1006C i
.