ML20058J793

Affidavit of DE Demoor Re Event Rept E-BRP-82-26 Prepared by F Turski on Safety Concern W/Spent Fuel Transfer Cask. Based Upon Whiting Corp Testimony,Situation Did Not Require Reporting.Rept Retracted.W/Certificate of Svc

ML20058J793
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	08/04/1982
From:	Demoor D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20058J747	List: ML20058J744 ML20058J759 ML20058J793
References
ISSSUANCES-OLA, NUDOCS 8208110211
Download: ML20058J793 (28)

Text

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Attcchment 2 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD i

In the Matter of

)

) Docket No. 50-155-OLA CONSUMERS POWER COMPANY

) (Spent Fuel Pool

) Modification)

(Big Rock Point Nuclear Power Plant)

)

AFFIDAVIT OF DONALD E. DEM00R

)

I, Donald E. DeMoor, of lawful age, being first duly sworn, do state i

as follows:

1.

I am employed as a Technical Engineer by Consumers Power Company at l

Big Rock Point Plant.

I graduated from Tri-State University in 1956 with a Bachelor of Science Degree in Electrical Engineering.

2.

I have been employed by Consumers Power Company for 25 years.

I have w'orked at Big Rock Point for 20 years in several engineering and supervisory positions including Instrument and Control Engineer, Senior-Engineer, Technical Superintendent and presently as Technical Engineer.

I was i

licensed as a senior reactor operator for Big Rock Point from 1967 to 1975.

I am responsible for administering the NRC Licensee Event Reporting requirements set forth in the technical specifications to the operating license for Big Rock Point Plant.

In this capacity, I review and participate in determining whether or not information is reportable to the NRC.

3.

On May 19, 1982, I processed Event Report E-BRP-82-26 (attached as Exhibit A) that had been prepared by Mr. Frank Turski concerning a potential safety concer'n with respect to the use of the spent fuel transfer cask. An I

event report is an internal reporting form used to document problems that have P208110211 820006 PDR ADOCK 05000155 g

PDR

p'.

.. a safety impact or a potential safety impact on plant operation.

On this occasion, I determined that the subject matter required reporting to the NRC as a prompt reportable occurrence under provision 6.9.2.A(9) of the Technical Specifications which reads as follows:

6.9.2 Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence.

In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

A.

Prompt Notification With Written Followup The types of events listed below shall be reported as expeditiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone. id confirmed by telegraph, mailgram, or facsimile t.2nsmission to the Director of the appropriate Regional Office, or his designate no later than the first working day following the event, with a written followup report within two weeks.

The written followup report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

(9) Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety j

analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial j

action or corrective measures to prevent the existence or development of an unsafe condition.

Note: This item is intended to provide for reporting of potentially generic problems.

L

O e

. This specification requires notification by phone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of

~ classification of the event with a written confirmation to be filed no later than the following day. A followup report is required within 14 days.

4.

In accordance with the above requirements, I called, on May 19, 1982, Mr R. Knop of Region III of the NRC office of Inspection and Enforcement and advised him of the contents of the Event Report.

I then prepared a confirming report to be sent to the NRC.

My report was forwarded to Consumers l

Power Company's Nuclear Licensing Department for Telex to the NRC. This report which is attached as Exhibit B, was sent on May 19 to Mr. Keppler of Region III by Mr. VandeWalle.

5.

The potential safety concern described in the attached Event Report 1

was based on calculations by a Whiting Corporation representative and an evaluation of the data by Mr. Turski and his supervisor, Mr. Alexander. The Event Report indicated that load bearing pins "may yield" and load bearing bolts "are inadequate" as related to the proper function of the cask catching equipment.

I believed on May 19 that a failure mechanism had been verified.

Knowing that failure could result in loss of pool water beyond make-up capability, I judged it to be reportable based on the above-mentioned reporting requirement.

l 6.

Prior to the deadline for filing the 14-day Licensee Event Report, I l

received a copy of testimony for the spent fuel storage hearings prepared by Mr. Charles R. Norman, of the Whiting Corporation.

Mr. Norman's testimony contained the same set of calculations as were provided with the Event Report.

Based on the conclusion in the Norman testimony (pages 13 and 14), it is now my judgment that the situation did not require reporting since there was no

7,'

4_

prediction of failure, only some uncertainty about the safety margin and the commitment to increase the safety margin by replacing the bolts and pins.

f/wf (Jhki Consequently, I recommended to the4 Superintendent that the May 19 notification to the NRC be retracted. He agreed.

I prepared a draft letter retracting the prior notification and sent it to Mr. VandeWalle's office for processing.

The retraction letter (attached as Exhibit C) was sent to the NRC on May 28, 1982.

Subsequently, the retraction was discussed with the NRC Resident Inspector at Big Rock Point and he appeared to be satisfied with the retraction judgment.

k Subscribed and sworn to before me this 4th day of August, 1982.

n 11elen I Dempski, Notary PuMic My commission expires December 14, 1983.

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TCBordin2,.P24-608 To hh DPHoffman/DEDeMoor, BRP

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Fnom Consumers 04tc May 26, 1982 POW 8r SuesccT BIG ROCK POINT PLANT -

RETRACTION OF LER PRIOR TO

~

FORMAL SUBMITTAL laicaun Conacsponocuct DED 82-19 CC E-BRP-82-26 Telephone discussion with RKnop of Region III on May 26, 1982 indicated that retraction of a prompt LER (which has been telegrammed to the NRC, but not submitted as a 14 day formal report) is best done via letter to the NRC Region 4

III prior to expiration of the 14 day period.

Based on further review of the subject matter described in DED 82-17 (attached) we request a letter be sent to Region III by 6/1/82 to advise of our retraction and indicate that related information is available for review by the Resident Inspector at Big Rock Point.

Note: A copy of thi retraction letter to NRC Region III should also be sent to J Gallo.

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Analysis by the reactor crane vendor (Whiting Corporation) indicates inadequate design of components in the crane and the 24 ten fuel transfer cask safety sling mechanism for a postulated failure of the crane cable when using the transfer cask.

The transfer cask will not be used until modifications ara ec=plete.

Reportability is based on Technical Specification 6.9.2.A (9).

This' confirms a telephone report to Richard Knop of NRC Region III at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> on 5/19/82 frem DEDeMoor.

Note:

A copy of the telegram to the NRC and the 82-18 LER report should be sent to J Gallo per his request to D?Hoffman.

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1 8 f Aw a p l ?yicin* 40 9a 6'y,m : 6 0,000 .=;c 1 Pia /s Sw'r's c i nry To: Y,4er Dvsissui Los o.: Nt rdo u r Y/El b id G. 1, 4 e

L. c; : _21MiWJW202 L i r. 2 : 1 Hdr: 1 '16' NC ANSWER Exhibit B NO CCNNECTIOt1 C' Time: 12:06 05/19/82 EST Msc : 021M/WJW202 Line: 1 H d r- : 1 6161 ,,3 WU INFOMASTER C CPCO PARN JKN 011075C139 1109EST C ZCZC 076 CONSUr!ERS POWER JACKSON MI 11:40 EST 05-19 ZIP J G KEFPLER REGION III C US NRC l 799 ROOSEVELT ROAD GLEN ELLYN IL 60137 C BT MSG # WJW202 5/19/82 11:52 AM NOTIFICATION OF 24-HOUR PROMPT REPORTABLE LER 82-18 l ANALYSIS BY REACTOR CRANE VENDOR (WHITING CORPORATION) INDICATES INADEQUATE DESIGN OF COMPONENTS IN THE CRANE AND THE 24-TON FUEL TRANSFER CASK SAFETY SLING MECHANISM FOR A POSTULATED FAILURE OF b THE CRANE CABLE WHEN USING THE TRANSFER CASK. THE TRANSFER CASK WILL NOT BE USED UNTIL MODIFICATIONS ARE COMPLETE. b REPORTABILITY IS BASED ON TECHNICAL SPECIFICATION 6.9.2.A (9). THIS CONFIRMS A TELEPHONE REPORT TO RICHARD KNOP OF NRC REGION III AT 0930 HOURS ON 5/19/82 FROM D E DE MOOR. DAVID J VANDE WALLE, NUCLEAR LICENSING CONSUMERS POWER COMPANY JACKSON, MICHIGAN CC D P HOFFMAN, BIG ROCK POINT PLANT D E DE MOOR, BIG ROCK POINT PLANT NNNN END Q, ACCEPTED g 00076 1-PC C G O b' Time: 12:11 05/19/82 EST Connect Time : 187 seconds J

r ~ Exhibit C ~ e f \\ COnSum8tS iQ' POW 8r ii H Company b ['N oeneral offices: 212 West Michigen Avenue, Jackson, MI 49201 * (517) 788 4550 May 28, 1982 l l [ James G Keppler, Administrator ( Region III l US Nuclear Regulatory Commission 799 Roosevelt Road l Glen Ellyn, IL 60137 i DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - RETRACTION OF LER PRIOR TO FORMAL SUBMITTAL - CRANE ANALYSIS Notification of 24-hour Prompt Reportable, tentatively identified as LER 82-18 was provided by telephone report to Richard Knop of NRC Region III at 0930 l hours on May 19, 1982. A follow-up confirmation was made by telecopy at l 11:52 am on May 19, 1982. l Based on further review of the reactor crane analysis, Concumers Power Company has determined that the concerns identified by the analysis are not reportable by Technical Specification 6.9.2.A(9). Related information is available for review by the Resident Inspector at the Big Rock Point Plant. Thomas C Bordine (Signed) l Thomas C Bordine Staff Licensing Engineer l CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector-Big Rock Point l oc0582-0021a142 l l L

< s .~ t UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC _ SAFETY AND LICENSING BOARD In the Matter of ) i ) Docket No. 50-155-OLA CONSUMERS POWER COMPANY ) (Spent Fuel Pool ) Modification) (Big Rock Point Nuclear Power Plant) ) t CERTIFICATE OF SERVICE I hereby certify that copies of CONSUMERS POWER j COMPANY'S REPLY TO MOTION TO RECPEN HEARING RECORD were served on Judges Bloch, Paris and Shon by hand delivery and on all other persons listed below by deposit in the United States mail, first-class postage prepaid, this 6th day of August, 1982. Peter B. Bloch, Esquire Atomic Safety and Licensing Administrative Judge Board Panel Atomic Safety and Licensing U. S. Nuclear Regulatory Board Panel Commission l U. S. Nuclear Regulatory Washington, D. C. 20555 i Commission Washington, D. C. 20555 Atomic Safety and Licensing Appeal Board Panel Dr. Oscar H. Paris U. S. Nuclear Regulatory l Administrative Judge Commission l Atomic Safety and Licensing Washington, D. C. 20555 Board Panel U. S. Nuclear Regulatory Docketing and Service Section Commission Office of the Secretary Washington, D. C. 20555 U. S. Nuclear Regulatory Commission Mr. Frederick J. Shon Washington, D.C. 20555 Administrative Judge Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 l

o O 0 0 ' Richard J. Goddard, Esquire Judd Bacon, Esquire Counsel for NRC Staff Consumers Power Company U. S. Nuclear Regulatory 212 West Michigan Avenue Commission Jackson, Michigan 49201 Washington, D. C. 20555 Ms. Christa-Maria Richard G. Bachmann, Esquire Route 2, Box 108C Counsel for NRC Staff Charlevoix, Michigan 49720 U. S. Nuclear Regulatory Commission Mr. Jim Mills Washington, D. C. 20555 Route 2, Box 108 Charlevoix, Michigan 49720 Herbert Semmel, Esquire Urban Law Institute Ms. JoAnne Bier Antioch School of Law 204 Clinton 2633 16th Street, N.W. Charlevoix, Michigan 49720 Washington, D. C. 20555 Mr. John O'Neill, II Route 2, Box 44 Maple City, Michigan 49664 QG f Q&.A l Sylvia P. Adricula l i I I ( . -.,}}