View source for HL-5257, Responds to NRC Re Violations Noted in Insp Rept 50-321/96-11.Involved Gpc Personnel Were Counseled Regarding This Event & Its Consequences

{{Adams
| number = ML20129J497
| issue date = 10/30/1996
| title = Responds to NRC Re Violations Noted in Insp Rept 50-321/96-11.Involved Gpc Personnel Were Counseled Regarding This Event & Its Consequences
| author name = Beckham J
| author affiliation = GEORGIA POWER CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000321
| license number = 
| contact person = 
| document report number = HL-5257, NUDOCS 9611060298
| title reference date = 10-11-1996
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 3
}}

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Georgia Power Company s''   40 inverness Center Parkway -
Post Office Box 1295 Birmingham, Alabama 35201 Telephone (205) 877-7279 l
ice es den 4 clear                                                         GeorgiaPower October 30, 1996
                                                                                       % ,    d 8$
Docket No. 50-321                                                                HL-5257 I
U. S. Nuclear Regulatory Commission                                                          i ATTN: Document Control Desk                                                                  :
Washington, D. C. 20555 Edwin I. Hatch Nuclear Plant - Unit 1 Reply to a Notice of Violation
.          Gentlemen:
In response to your {{letter dated|date=October 11, 1996|text=letter dated October 11,1996}}, and according to the requirements of       .
10 CFR 2.201, Georgia Power Company (GPC) is providing the enclosed response to the
                                                                                                        )
Notice of Violation associated with Inspection Report 96-11. In the enclosure, a             l transcription of the NRC violation precedes GPC's response.                                  j i
Sincerely,                                     i
[               Y J. T. Beckham, Jr.
r%
DLM/eb

==Enclosure:==
Violation 96-11-02 and GPC Response cc: Georgia Power Companv Mr. H. L. Sumner, Jr., Nuclear Plant General Manager NORMS U. S. Nuclear Regulatory Commission. Washington. D. C.
Mr. K. Jabbour, Licensing Project Manager - Hatch U. S. Nuclear Reentatorv Commission. Region][L Mr. S. D. Ebneter, Regional Administrator Mr. B.- L. Holbrook, Senior Resident Inspector - Hatch                         -  I 9611060298 961030
                                                                                                 $E   l, PDR     ADOCK 05000321 G                          PDR 060085

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Enclosure l
Edwin I. Hatch Nuclear Plant Violation 96-11-02 and GPC Response i
VIOLATION 96-11-02 10 CFR 50.55a, Codes and Standards, Paragraph (g), Inservice Inspection Requirements, requires that inspection and testing be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. ASME Section XI                    )
IWA-4600(A) requires a re-examination following a repair by machining.
Unit 1 Technical Surveillance Requirement 3.4.2.1 of the Technical Requirements Manual states, in part, to perform required inspection and testing in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g), as modified by approved relief.
Contrary to the above:
Between April 14,1996, and May 1,1996, while implementing Design Change Request 94-033 on valve IE41-F006, High Pressure Coolant Injection Valve, gouges in the bonnet          l at the gasket seating area were removed by machining and a VT-3 reinspection was not            !
completed. As a result, an inspection required by section XI of the ASME Boiler and Pressure Vessel Code was not performed.
This is a Severity Level IV Violation (Supplement I).
RESPONSE TO VIOLATION 96-11-02 Reason for the violation:
The violation was the result of personnel error. Responsible personnel failed to re.:ognize a VT-3 inspection was required following the completion of repair work on valvo IE41-F006. As a result, the valve was reassembled without the inspection having been performed.
A Quality Control Inspection Report was initiated subsequent to the discovery of the gouge in the bonnet at the gasket seating area. A Quality Control hold point was assigned to ensure the Quality Control Inspection Report was resolved prior to the valve being reassembled; however, the report was not resolved adequately. A GPC engineer signed the Quality Control Inspection Report as resclved after the gouge was repaired. Similarly, a GPC Quality Control Specialist signed the Quality Control Inspection Report and released the hold point after repair work was completed. Neither individual recognized a HL-5257                                               E-1
* Enclosure 0
* Violation 96-11-02 and GPC Response i
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VT-3 reinspection of the repaired area was necessary; consequently, the hold point was i
released and the valve was reassembled without performing the inspection required by the l                             ASME Code and the Technical Requirements Manual.
l l                             Corrective steos which have been taken and the results achieved:
As a result of this event, the following corrective actions were taken:
1                             1. Involved GPC personnel were counseled regarding this event and its consequences.
:                             2. An operability and structural integrity assessment for valve 1E41-F006 was l                                   performed concluding the valve is operable and structurally intact. This conclusion                       t
!                                   is based upon successful completion of stroke time, local leak rate, and Generic
{                                   Letter 89-10 testing along with successful completion of a VT-2 leakage inspection
;                                   of this valve during the vessel hydrostatic test. The assessment is documented in l                                   detail in the response to Significant Occurrence Report C09603642.
l                             3. Maintenance Work Order 1-96-2647 was written to disassemble and perform a l                                   VT-3 inspection of the bonnet of valve IE41-F006. This inspection will be
!                                   performed during the next Unit I refueling outage currently scheduled to begin in
!                                   October of 1997.
Corrective steps which will be taken to avoid further violations:
.                             No additional corrective actions to prevent further violations are necessary at this time.
1 Date when full comoliance will be achieved:
Full compliance with Technical Requirements Manual and ASME Code requirements will                               l be achieved when the bonnet of valve IE41-F006 is inspected during the next Unit I refueling outage.                                                                                               '
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