ML20056C913

Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 70-1257/92-08

ML20056C913
Person / Time
Site:	Framatome ANP Richland
Issue date:	07/01/1993
From:	Reese J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Maas L SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER
References
NUDOCS 9307260142
Download: ML20056C913 (2)

Text

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,4 001.-1195rd Docket No. 70-1257 License No. SNM-1227 Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130 Richland, Washington 99352-0130 Attention: Mr. L. J. Maas, Manager Regulatory Compliance

Subject:

RESPONSE TO NOTICE OF VIOLATION CONTAINED IN NRC INSPECTION REPORT NO. 70-1257/93-04 Thank you for your letter dated June 16, 1993, in response to our Notice of Violation and Inspection Report No. 70-1257/92-08,' dated May 19, 1993, informing us of the steps you have taken to correct the item which we brought to your attention.

Your corrective actions appear to resolve our concerns regarding the violation referenced in the subject report.

Your corrective actions will be reviewed during a future inspection.

Your cooperation with us is appreciated.

Sincerely, James H. Reese, Chief Facilities Radiological Protection.

Branch cc:

State of Washington bec w/ copy of letter dated June 16, 1993 Inspection File M. Adams, NMSS G. Cook B. Faulkenberry D. Proulx, WNP-2 cc w/o copy of letter dated June 16, 1993 M. Smith REGION V CHooke

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~JUL - 1 1993 00cket No. 70-1257 License No. SNM-1227 Siemens Power Corporation 2101 Horn Rapids Road P. O. Box 130

-Richland, Washington 99352-0130 Attention: Mr. L. J. Maas, Manager Regulatory Compliance

Subject:

RESPONSE TU NOTICE OF VIOLATION CONTAINED IN NRC INSPECTION REPORT NO. 70-1257/93-04 Thack you for your letter dated June 16, 1993, in response to our Notice of Violation and Inspection Report No. 70-1257/92-0 dated May 19, 1993, informing us of.the steps you have taken to corri.

the item which we brought to your attention.

Your corrective actions appear to resolve our concerns regarding the violation referenced in the subject report.

Your corrective actions will. be reviewed during a future inspection.

Your cooperation with us is appreciated.

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ief a ilities Radio ogical Protection Branch cc:

State of Washington W

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" SIEMENS sh lr,+3 r " r. _.... i D. r 5 c'

.s June 16,1993 U.S. Nuclear Regulatory Commission l

Attn: Document Control Desk Washington, DC 20555

Subject:

Reply to Notice of Violation

-1 Letter, J. H. Reese to Siemens Power Corporation, " Notice of Violation (NRC -

Reference:

Inspection Report No. 70-1257/93-04)," dated May 19,1993.-

Gentlemen:

Enclosed is Siemens Power Corporation's reply to the Notice of Violation transmitted to SPC3 0

by the refere?,ced letter. -If you have an).luestions regarding this reply, please contact me at 509-375-8537.

V Very truly yours, i

L ti.fu t

Loren J. Maas, Manager Fogulatory Compliance I

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Mr. B. H. Faulkenberry 13egion V Admin"trator i

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Siemens Power Corporation Nuclear Divson - Engineering and Manufacturing FaciMy

-2101 Horn Rapcs Road. PO Box 130. Richland WA 99352 0130 Tet 1509) 375 8100 Fax! (509) 375 8402-i

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USNRC Document Control Desk June 16,1993 Siemens Power Corporation (SPC) Reply to Notice of Violation Dated May 19,1993 (NRC Inspection Report No. 701257/93 04)

Statement of Violation Criticality Safety Analysis (CSA) U-4.2 "U 0 Tray Loading, Furnaces, and Tray Unloading 3s Hoods" Rev. 3, Part 11"Umits and Controls to Assure Critica'ity Safety" and Criticality Safety

- Umit Card P90,052 Revision 0 require in part:

6.

Fumace Tray Stack Dimensions Tray Stack:

Five trays high with.75" edge-to-edge vertical separation between trays.

Contrary to the above, on March 5,1993,4 stacks of trays containing UO Pellets in the U O 2

3g facility in the furnace area were stacked 5 high without maintaining the required.75 inch edge-to-edge vertical separation.

This is a Severity Level IV violation. (Supplement VI).

SPC Response to Violation Reason for Violation This violation resulted from the failure of Operations personnel to adequately report and address an equipment problem that prevented consistent como4nce with a secondary criticality safety limit.

The.U O fumace trays are equipped with supports which pr./ idea s '8" edge-to-edge vertical separation. Primary controls in the cited CSA are bassyr e -chment and ag moderation, however the 0.75" spacing was incorporated into the CS/. e a secondary limit.

After repetitive exposures to heating and cooling cycles over time, many d the trays would i warp such that the supports were' ineffective in maintaining the required spacing. Operations personnel periodically acquired new trays to replace warped trays but the periodic

replacement efforts were inadequate to maintain an acceptable inventory of suitable trays.

The result was that the 0.75" separation requirement was not consistently met.

immediate Corrective Steps Immediately upon discovery the technician rearranged the trays to restore the requiredI.

spacing. The Criticality Safety Specialist (CSS) reviewed the CSA and determined that the operation was adequately controlled via the primary limits called for in the CSA and that the-secondary spacing limit was unnecessary. The CSA was addended on the same day to remove the spacing requirement.

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USNRC Document Control Desk June 16,1993 f

. C arrective Steps Taken to Avoid Further Violations As stated above, the CSA has been addended to remove the 0.75" spacing requirement. An event critique is being provided to all Chemical Operations pe'rsonnel which reviews this particular violation and re-emphasizes SPC procedures which require immediate reporting of all abnormal criticality safety-related conditions. The last of these sessions was completed on June 16.

1 Date to be in Full Compilance

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