ML20215C882

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Forwards Insp Rept 99900403/86-03 on 860811 & 12 & Notice of Nonconformance.Insp Conducted as Result of 860614 Unusual Control Rod Movement Due to Use of Refurbishment Scram Solenoid Pilot Valve Kits
ML20215C882
Person / Time
Issue date: 10/02/1986
From: Heishman R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Bruggeman W
GENERAL ELECTRIC CO.
Shared Package
ML20215C884 List:
References
REF-QA-99900403 NUDOCS 8610100511
Download: ML20215C882 (3)


Text

. ..

UNITED STATES

,d,f NUCLEAR REGULATORY COMMISSION

g
. ;j WASHINGTON D. C. 20555

\...../ October 2, 1986 Docket No. 99900403/86-03 General Electric Company Nuclear Energy Business Operations ATTN: Mr. W. H. Bruggeman, Vice President and General Manager 175 Curtner Avenue San Jose, California 95125 Gentlemen:

This refers to the inspection conducted by K. R. Naidu and E. Yachimiak of this office on August 11 and 12,1986, of your facility at San Jose, California and to the discussions of our findings with Mr. J. J. Fox and members of your staff at the conclusion of the inspection.

This inspection was made as a result of an event on June 14, 1986 at the Vermont Yankee Nuclear Power Plant, when unusual control rod movement was experienced which was subsequently determined to be due to the use of refurbishment scram solenoid pilot valve (SSPV) kits supplied by you and manufactured by Automatic Switch Company (ASCO) located in Florham Park, New Jersey. Areas examined during the inspection and our findings are discussed in the enclosed report.

Within these areas, the inspection censisted of an examination of procedures and representative records, interviews with personnel, and observations by the inspectors.

During the inspection it was fcund that the implementation of your QA program failed to meet certain NRC requirements. Specifically, you failed to implement your established procedure to reconcile the discrepancy that you supplied 200 SSPV refurbishnent kits to the Vermont Yankee Nuclear Power Plant which were not safety-related, even though their purchase order to you required you to supply 200 sofety-related kits. Subsequent inspections of these kits by ASCO identified several nonconforming components which may have been detected by ASCO prior to shipment to you, had your procurement documents to ASCO identified them as safety related kits. The specific findings and references to the pertinent requirements are identified in the enclosures to this letter.

Please provide us within 30 days from the date of this letter a written statement containing: (1) a description of steps that have been or will be taken to correct this item; (2) a description of steps that have been or will be taken to prevent recurrence; and (3) the dates your corrective actions and preventive measures were or will be completed. Consideration may be given to extending your response time for good cause shown.

0 8610100611 861002 i PDR GA999 EMVGENE 99900403 PDR g

General Electric Company October 2, 1986 Additionally, there is an unresolved item dealing with your apparent failure to adequately review the event which occurred on June 14, 1986 at the Vermont Yankee Nuclear Power Plant in accordance with the requirements of 10 CFR Part 21 when one control rod failed to scram and five others hesitated to scram during single rod scram time testing. This item is to be treated as unresolved for two reasons.

First, no attempt was made by GE personnel to bring forth documentation concerning this issue when the NRC inspectors were at GE's San Jose facility. Second, when asked to supply information which would adequately summarize the findings of GE's Part 21 evaluation, documentation was made available "only for review." This information was reviewed by the NRC inspector at GE's Bethesda, Maryland office on September 10, 1986, but the NRC inspector was asked not to take any notes since the information was proprietary. The NRC can and will protect any infor-mation that is proprietary. Because the inspectors' preliminary review of the information made available resulted in concerns regarding the adequacy of the evaluation, you are requested to provide us within 30 days of the date of this letter the basis for your determination that the failure of the ASCO scram solenoid valves which caused this event and were supplied by you to Vermont Yankee and other BWR facilities could not create a substantial safety hazard. If this information is considered proprietary, please mark it as such.

The responses requested by this letter are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.

In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room.

Should you have any questions concerning this inspection, we will be pleased to discuss them with you.

Sincerely,

/ f)

. 44d

' Robert F. Heishman, Chief Vendor Program Branch i

Division of Quality Assurance, Vendor I_

and Technical Training Center Programs Office of Inspection and Enforcerrent l

Enclosures:

1. Appendix A-Notice of Nonconformance
2. Appendix B-Inspection Report No. 99900403/86-03 l

4 General Electric Company October'2, 1986 DISIi>IBUTION:

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  • see previous or c currence VPB:DQAVT* BC/VPB:DQAVT R KNaidu:tt off RHeishman mes 9/26/86 9/e1/86 9 /86 /( /86 63th

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