ML20140C723

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Ack Receipt of Informing NRC of Steps Taken to Correct & Prevent Recurrence of 841218 Misalignment of Boric Acid Tank Selector.Implementation of Corrective Actions Will Be Examined During Subsequent Insp
ML20140C723
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 01/15/1986
From: Norelius C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Hintz D
WISCONSIN PUBLIC SERVICE CORP.
References
NUDOCS 8601280390
Download: ML20140C723 (1)


Text

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JAN 15 I!B6 P;

Docket No. 50-305 Wisconsin Public Service Corporation ATTN: Mr. D. C. Hintz Manager Nuclear Power Post Office Box 19002 Green Bay, WI 54307-9002 Gentlemen:

Thank you for your letter dated December 23, 1985, informing us of the updated status of the long-term corrective actions being taken to correct and prevent recurrence of circumstances which resulted in the misalignment of the boric acid tank selector switch on December 18, 1984. We will examine the implementation of your corrective actions during a subsequent inspection.

. Your cooperation in keeping us current on the status of your commitments in regard to this matter is appreciated.

Sincerely, "0,-i; i r '~t  ;;JJ. 3 b' C.Z. t!oreliua" Charles E. Norelius, Director Division of Reactor Projects cc: C. R. Steinhardt, Plant Manager cc w/ltr dtd 12/23/85:

DCS/RSB (RIDS)

Licensing Fee Management Branch Resident Inspector, RIII John J. Duffy, Chief Boiler Section Ness Flores, Chairperson Wisconsin Public Service Commission 8601280390 86011 DR ADOCK 050 S RIII RIII RIII RIII G ner/cs J kiw Ch ssotimos hbs dh \

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NRC-85-184 WISCONSIN PUBLIC SERVICE CORPORATION 4

December 23, 1985 Mr. J. G. Keppler, Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 i

Gentlemen:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Status of Corrective Actions (Boric Acid Tank Selector Switch Misalignment /LER 84-21)

References:

1) Letter from D. C. Hintz (WPSC) to J. G. Keppler (NRC) dated March 13, 1985
2) Letter from P. D. Ziemer (WPSC) to J. G. Keppler (NRC) dated April 12, 1985, responding to Notice of Violation and Inspection Report 50-305/84-23
3) Letter from D. C. Hintz (WPSC) to J. G. Keppler (NRC) dated July 31, 1985
4) Letter from D. C. Hintz (WPSC) to H. L. Thompson (NRC) dated October 31, 1985 '
5) Letter from C. E. Norelius (NRC) to D. C. Hintz (WPSC) dated October 29, 1985 Per the conference call with Messrs. Greenman and Jackiw of NRC Region III on December 6,1985, this letter provides an interim status report concerning i WPSC's remaining long-term corrective actions resulting from the boric acid tank j selector switch misalignment event. Three previous WPSC submittals (references -

1, 2, and 3) described a total of eight long-term corrective ections and 1

l 600 North Adams

  • P.O. Box 19002
  • Green Bay, WI 54307-9002 l DEC 2 61985 ]

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Mr. J. G. Keppler December 23, 1985 Page 2 informed you of the completion of six of these corrective actions. The purpose of this letter is to provide the NRC with the status of the two remaining items.

We recognize the importance of these corrective actions with regard to the pre-vention of the reoccurrence of this specific event and the reduction of the pro-bability of the occurrence of any similar events. We wish to assure you that we are continuing to apply the appropriate resources to this end.

Improvement of the Control Room SI Ready Status Panel Previous status updates (references 1, 2, and 3) informed you of the on-ge;ng evaluation of the KNPP status panels and the tentative recommendations of the evaluation. However, the method of implementing this corrective action has changed somewhat since the July 31, 1985 status update. As you were informed at the January 7, 1985 enforcement conference, the need for this corrective action was previously identified by the Control Room Design Review (CRDR). In August, 1985, the CRDR Implementation Committee was established. The purpose of this committee was described in some detail by WPSC submittal dated October 31, 1985 (reference 4). Basically, this committee will ensure all changes to the control

! room receive adequate operations and human factors review and approval prior to implementation. The preliminary procedure established by the CRDR Implementation Committee does not permit any significant 1986 outage work for the control room status panels due to the time required for the extensive operations and human factors review of this particular modification.

However,inlightofthesignificanceoftheSIReadyStatusPane[andits contribution to the December 18, 1984 switch misalignment, WPSC has expedited the modification of this particular panel. While other portions of the status panel system will be upgraded uader a schedule that will be approved by the CRDR Implementation Committee, it was felt the improvement of this particular panel was of considerable importance and should be completed as soon as possible. The current goal for implementation of this particular panel modification is the 1986 refueling outage. Prior to installation, the proposed modification will receive the applicable operations and human factors review. The critical path item for this project will be the manufacture of the new panel. We are in close contact with the manufacturer and hope to ensure fabrication of the panel in time for installation during the 1986 refueling outage.

Review of All Plant Surveillance Procedures Our July 31, 1985 status update (reference 3) provided you with a staggered implementation schedule for the incorporation of the recommendations of the sur-veillance procedure (SP) review team. Your letter dated October 29, 1985 (reference 5) found this schedule acceptable. However, as discussed in the December 6, 1985 conference call, we are having difficulty meeting one of the staggered implementation dates and would like to point out what has been accomplished to date, why we are having problems meeting the proposed schedule, and what remains to be done. .

As reference 3 informed you, the review of the SPs has been completed. This review involved approximately 280 SPs which are now in the process of being revised to incorporate the recommendations of the review team. Any possible

=

Mr. J. G. Keppler

. December 23, 1985

. Page 3 conflicts with Technical Specifications were identified for further investiga-tion as part of the review. As discussed in reference 3, these possible conflicts have been resolved.

Although we have a number of personnel virtually dedicated to the incorporation of the review team's recommendations, we underestimated the scope of this task.

Furthermore, we feel that the scope of the reviews and the corrective modifica-tions being made to the SPs is above and beyond what was originally projected as corrective actions. Examples are including signoffs for equipment manipulations (not necessarily just operator signoffs), separating existing SPs into more spe-cific individual SPs for each train or channel where appropriate, and including statements of the applicable Technical Specification limiting conditions for operation in the SP.

As a result of the extensive reviews and modifications being made to the SPs, approximately 60 SPs were not issued prior to their December 1, 1985 target date. We are striving to revise and issue the remaining SPs prior to their next performance; however, we must inform you that we do not feel this can be accomplished for all the SPs. In addition, with the 1986 spring refueling outage rapidly approaching, the plant staff will begin to concentrate on outage activities. This will impede the revision process for any remaining SPs, par-ticularly during the outage. Therefore, our best estimate for the complete issuance of the SPs is June 1, 1986. This includes only those SPs not included in the other staggered implementation dates as described in reference 3. Per our December 6, 1985 conference call, this date is acceptable with NRC Region III. .

Upon completion of the remaining long-term corrective actions, WPSC will pro-vide you with a letter closing out this issue. It is not anticipated that any further status updates will be required. However, should any unforeseen cir-cumstances affect the remaining long-term corrective actions, you will be promptly informed.

Sincerely, D. C. Hintz Manager - Nuclear Power KAH/jms cc - Mr. George Lear, US NRC Mr. Robert Nelson, US NRC

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