ML17324B191

Summary of 861211 Meeting W/Whitting Corp,Bechtel,S&A,Util, Westinghouse,Shaw,Pittman,Potts & Trowbridge & PASNY Re Steam Generator Repair Program.List of Attendees & Viewgraphs Encl

ML17324B191
Person / Time
Site:	Cook
Issue date:	12/29/1986
From:	Wigginton D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8701050341
Download: ML17324B191 (44)

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Docket Nos.:

50-315 and 50-316 OEG 39 $8S LICENSEE:

FACILITY:

SUBJECT:

Indiana and Michigan Electric Company Donald C.

Cook Nuclear Plant, Units I and 2

SUMMARY

OF MEETING HELD ON DECEMBER ll, 1986 REGARDING THE STEAM GENERATOR REPAIR PROGRAM AND AUXILIARY BUILDING CRANE The staff met with the licensee in Bethesda, Maryland to discuss the review areas associated with the steam generator repair (or replacement) program and the crane replacement and special lifting rig for the auxiliary building.

The list of attendees is attached as Enclosure 1.

as "The introductory remarks were made by the NRR staff on each of the review eas for the steam generator repair program.

The licensee indicated that ch of the information is contained in the Steam Generator Repair Report submitted by the licensee's letter dated November 7, 1986.

The licensee was informed that a license condition is planned in order to provide a clear basis for program compliance during the period that will be required to per-form the replacement.

It is expected that the approved Steam Generator Repair Report will evolve from the NRR review and will be referenced in the license condition.

The licensee will provide additional information as in-serts to the Repair Report and propose a license condition.

This additional submittal and the November 7, 1986 letter will be the basis for a significant hazards determination and NRRs initiation of the review.

The licensee's presentation was made from viewgraphs attached as Enclosure 2.

The auxiliary building crane will be upgraded to single-failure-proof status as a first step.

The subsequent upgrading will provide the special lift rig needed for the replacement program.

The viewgraphs and discussions provided preliminary information on each upgrading.

In general, the staff believes the licensee is aware of requirements and is proceeding in a reasonable direction with the program.

The specific review will follow the licensees formal submittals.

8701050341 861229 PDR

• DOCK 05000315

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P PDR

Enclosures:

As stated cc:

See next page Dave Wigginton, Project Manager PWR Project Directorate g4 Division of PWR Licensing-A PWRI /DPWR-A DWigginton/mac 12/yR /86 PWR BJYo 12

'I

-A od

MEETING

SUMMARY

DISTRIBUTION DEC 2 g 1986 Dncket File NRC PDR L PDR NSIC PRC System PWR4'4 Reading File Project Manager D,

Wi inton M. Duncan OGC/Bethesda J.

Partlow E. Jordan B. Grimes ACRS (IO)

NRC Participants egg n on W. Brooks H. Brammer J.

Shapaker C. Tinkler R. Ballard F. Rinaldi N.

Romney A. Singh G. Bagchi R.

Kazmar C. Willis T. Sullivan T.

Ouay OTHERS bcc:

Licensee 8 Service List

~~R RECI 0

Cy 0O 0

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DEC 2 g 1986 Duckei. Kos.:

50-315 and 50-316 LICENSEE:

FACILITY:

SUBJECT:

Indiana and Michigan Electric Company Donald C.

Cool< Nuclear Plant, Units 1 and 2

SUt~iMARY OF MEETING HELD ON DECEMBER 11, 1986 REGARDING THE STEAM GENERATOR REPAIR PROGRAM AND AUXILIARY BUILDING CRANE The staff met with the licensee in Bethesda, Maryland to discuss the review areas associated with the steam generator repair (or replacement) program and the c~ane replacement and special lifting rig for the auxiliary building.

Tl e 1'.st of attendees is attached as Enclosure 1.

The introductory remarks were made by the NRR staff on each of the review areas for the steam generator repair program.

The licensee indicated that much of the information is contained in the Steam Generator Repair Report as subrittec by the licensee's letter dated November 7, 1986.

The licensee was informed that a license condition is planned in order tc Drovide a clear basis for oroaram compliance during the period that will be required to per-form the replacement.

It is expected that the approved Steam Generator Repair Report will evolve from the NRR review and will be referenced in the license condition.

The licensee will provide additional information as in-serts to the Repair Report and propose a license condition.

This additional submittal and the November 7, 1986 letter will be the basis for a significant hazards determinatior and NRRs initiation of the review.

The licensee's presentation was made from viewgraphs attached as Enclosure 2.

The auxiliary building crane will be upgraded to single-failure-proof status as a first step.

The subsequent uparading will provide the special lift rig needed for the replacement program.

The viewgraphs and discussions provided preliminary information on each upgrading.

In general, the staff believes the licensee is aware of requirements and is proceeding in a reasonable direction Ivith the program.

The specific review will follow the licensees formal submittals.

Enclosures:

As stated cc:

See next page Dave Wi nton, Project Manager PWR Project Directorate P4 Division of PWR Licensing-A

Mr. John Dolan Indiana and Michigan Electric Company Donald C.

Cook Nuclear Plant cc Mr. M. P. Alexich Vice President Nuclear Operations American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43215 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgeman, Michigan 49106 W.

G. Smith, Jr., Plant Manager Donald C.

Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.

Washington, DC 20037 Mayor, City of Bridgeman Post Office Box 366 Bridgeman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909

~ s Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 The Honorable John E. Grotberg United States House of Representatives Washington, DC 20515 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen El lyn, Illinois 60137 J. Feinstein American Electric Power Service Corporation 1 Riverside Plaza

Columbus, Ohio 43216

ENCLOSURE I PARTICIPANTS NRC D. Wigginton W. Brooks H. Bramer Shapaker C. Tinkler R. Ballard F. Rinaldi N.

Romney A. Singh G. Bagchi R.

Kazmar C. Will)s T. Sullivan T. quay WHITING CORPORATION J.

Poradzis" J.

Luszyk BECHTEL S.

Routh S&A J.

Stevenson D.

C.

CGGK PLANT L. Gibson AMERICAN ELECTRIC POWER SERVICES CORPORATION M. Alexich T. Harshbarger R. Stringer S.

Brewer R. Kroeger K. Johnson J. Feinstein S.

Heinecke W. Modry T. Satyan-Sharma D. Hafer WESTINGHOUSE Scapellato A. Ball, Jr.

J.

Echols SHAW, PITTtiAN, POTTS 8

TROWBRIDGE J. O'eill N.

Y.

POWER AUTHORITY P.

Kokolakis-

ENCLOSURE 2

I PRE-OUTAGE CONSTRUCTION UPGRADING THE EXISTING AUXILIARYBUILDING BRIDGE CRANE TO SINGLE-FAILURE-PROOF STATUS SPECIAL OVERHEAD HANDLING SYSTEM

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Pre Outage Construction Upgrade of Ezisting Roads and Parking Lots Construction.of the'ite Access Control Building Construction of the Fabrication Shop~ Warehouse Construction of the Containment Access Building Construction oi the Temporary OnSite Steam Generator.,

Lower Assembly Storage Facility

LINREVIEWED ENVIRONMENTAL QLIESTIONS SIGNIFICANT INCREASE IN ANY ADVERSE ENVIRONMENTAL IMPACT PREVIOUSLY EVALUATED.

SIGNIFICANT CHANGE IN EFFLUENTS OR POWER LEVEL MATTER NOT PREVIOUSLY REVIEWED WHICH MAY HAVE SIGNIFICANT ADVERSE ENVIRONMENTAL IMPACT

UPGRADING THE EXISTING AUXILIARY BUILDING BRIDGE CRANE TO SINGLEFAILUREPROOF STATUS e BENEFITS OF UPGRADING THE AUXILIARYBUILDING BRIDGE CRANE SINGLEFAILUREPROOF CRITERIA

+ LICENSING'CTIVITIES TO ALLOW OPERATION OF THE UPGRADED SINGLEFAILUREPROOF CRAi'IE

+ ASPECTS OF THE UPGRADE OF THE EXISTING CRANE TO SINGLEFAILUREPROOF CRITERIA

BENEFITS OF UPGRADING THE AUXILIARY BUILDING BRIDGE CRANE

• MAKES PLANT OPERATION/MAINTENANCE EASIER

+ REMOVES THE 15' O'ESTRICTION NEAR THE SPENT FUEL POOL.

• WILL ALSO BENEFIT THE STEAM GENERATOR REPAIR ACTIVITIES.

0 SINGLEFAILUREPROOF CRITERIA NUREG0554, SINGLEFAtLUREPROOF CRANES FOR NUCLEAR POWER PLANTS.

APPLICABLE SECTIONS OF NUREG0612 "CONTROL OF HEAVY LOADS AT NUCLEAR POWER PLANTS

SINGLEFA!LUREPROOF HANDLING SYSTEM EVALUATION PROVIDE A DETAILED EVALUATION OF THE OVERHEAD HANDLING SYSTEM.

THIS EVALUATION MUST INCLUDE A POINTBYPOINT COMPARISON FOR EACH SECTION OF NUREG0554, AND APPENDIX "C", NUREG0612 AS APPLICABLE PROVIDE AN EVALUATION OF THE LIFTING DEVICES FOR EACH SINGLEFAILUREPROOF HANDLING SYSTEM WITH RESPECT TO THE GUIDELINES OF NUREG0612, SECTION 5.1.6 PROVIDE AN EVALUATION OF THE INTERFACING LIFT POINTS WITH RESPECT TO THE GUIDELINES OF NUREG-0612, SECTION 5.1.6.

0 MODIFICATION TO THE EXISTING CRANE TO MAKE IT SINGLEFAILUREPROOF o

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The allowable stress limits should be identified and be conservative enough to prevent permanent deformation of the individual structural members when exposed to maximum load lifts.

The minimum operating temperature of the crane shall be determined from the toughness properties of the structural materials that are stressed by the lifting of the load.

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The crane should be capable of stopping and holding the load during a

seismic event equal to a

SSE applicable to that facility.

I Automatic controls and limiting devices should be designed so that component or system malfunction will not prevent the crane from stopping and holding the load safely.

Design of the wire rope reeving system should include dual wire ropes.

Sensing devices should be included in the hoisting system to detect such items as overspeed,

overload, and overtravel and cause the hoisting action to stop when limits are exceeded.

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The hoisting drum(s) should be protected against dropping should its shafts or bearings fail.

Safety devices such as limit switches provided to reduce the likelihood of a malfunction should be in addition to those normally provided for control of maloperation or operator error.

The crane system should be given a cold proof test if material toughness properties are not known.

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+ UPPER AND LOWER ASSEMBLY REMOVAL PROCEDURE AND PATHWAY

+ ASPECTS OF THE SPECIAL OVERHEAD HANDLING SYSTEM THAT MAKES IT SINGLEFAILUREPROOF

+ AUXILIARYBUILDING STRUCTURAL ANALYSIS

+ LICENSING ACTIVITIES TO ALLOW OPERATION OF THE SPECIAL OVERHEAD HANDLING SYSTEM

TURBINE BUILDING AUX BUILDING UNIT 2

0 WHAT MAKES THE SPECIAL OVERHEAD HANDLING SYSTEM SINGLEFAILUREPROOF~

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EVALUATION OF THE SPECIAL OVERHEAD HANDLING SYSTEM Provide a detailed evaluation of the special overhead handling system.

This evaluation must include a pointbypoint comparison for each section of NUREG0554 and the guidelines of NUREG0612, Section 5.1.6.

+

Provide an evaluation of the interfacing iift points with respect to the guidelines of NUREG0612, Section 5.1.6.