ML17317A757

Forwards Request for Addl Info Re Containment Sump Tests. Inter Alia,Seeks Info Re NPSH Margin & Containment Sump Vent Design

ML17317A757
Person / Time
Site:	Cook
Issue date:	11/07/1978
From:	Schwencer A Office of Nuclear Reactor Regulation
To:	Tillinghast J INDIANA MICHIGAN POWER CO.
References
NUDOCS 7811280344
Download: ML17317A757 (21)

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NOV 7 $78

<<I Docket Nos.'0-315

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DISTR BUTION Docket Files 50-315 and 50-316 NRC PDR Local PDR ORBl Rdg V. Stello

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A. Schwencer M. Mlynczak Indiana and Michigan Power Company Indiana and, Michigan Electric Company ATTN:

Mr.. John Tillinghast J'.

Buchanan Yice President

'ACRS (16)

Post Office Box 18 Bowling Green Station New York, New York 10004 l I'<<

l'entl emen:

As a result of our review of your preliminary report and our observation of your August 23, 1978 containment,'s'ump demonstrjtion tests performed at Alden Research Laboratories for the D. C. Cook Nuclear Plant, we have developed the enclosed request for additional information.

Your response is req'uested no later than thirty days from the date of this letter.'incerely, Original Signed BJ

Enclosure:

Request for Additional Information ll cc:

w/enclosure See next. page A. Schwencer, Chief Operating Reactors Branch 1

Division of Operating Reactors

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Indian 5 Michigan Electric Company Indian

& Michigan Power Company cc:

Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman Potts 5 Trowbridge 1800 M Street, NW Washington, D.C.

20036 David Dinsmore Comey Executive Director Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Reston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Donald C.

Cook Nuclear Plant ATTN:

Mr.

D. Shaller Plant Manager P.

0.

Box 458

Bridgman, Michigan 49106

Enclosure 1

Request for Additional Information D.

C.

Cook Nuclear Plant Containment Sump Tests The containment sump vent design must be improved to assure that air trapped under the surface immediately above the outlet pipes is removed.

A more dispersed venting capability is required and the potential for circulation due to submergence of the vent pipe must be removed by extending it to above the maximum postulated water level.

Provide details of an improved. vent design which accommodates this concern.

Air entrainment has not been considered in the tests.

Effluent from ice condenser drains and postulated pipe breaks striking the surface of water in containment can create aeration detrimental to pump performance.

Demonstrate that the design is not susceptible to such conditions.

High pressure breaks in the vicinity of the conditions detrimental to sump performance.

flow patterns conducive to vortex formation ingestion of two-'phase flow.

Void collapse pipe could cause limiting pressure pulses.

breaks i.n the vicinity of the sump will not performance.

sump could create flow Specific concerns include and the direct injection/

in the sump and outlet Demonstrate that pipe adversely affect sump Demonstrate that adequate NPSH margin is available under runout conditions for all pumps drawing from the sump.

This demonstration must utilize entrance losses based on model tests and pipe losses based on measurements taken during in-plant pre-operational tests.

Losses in sections of piping not tested may be calculated.

The required NPSH for each pump is that measured during individual tests of the pumps by the manufacturers.

The margin is to be demonstrated for post-LOCA conditions.

If credit is taken for subcooling of the sump water or containment pressures greater than saturation

pressure, provide the supporting post-LOCA containment analysis to demonstrate a conservative basis for NPSH calculations.

Address possible design improvements which have been suggested from the tests and modifications which may be required to resolve the concerns expressed above.

Me understand that model tests indicated that removal of the horizontal plate placed below the sump suction and replacement with screens in the sump inlets was desirable.

Provide details of plant design changes and the schedule for implementing these modifications.

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ElUGUS1 g P tgyg Docket Hos. 50-315 and 50-316 Indiana and Michigan Electric Company Indiana and Michigan Power Company ATTN:

Mr, John Tillinghast Vice President P. 0. Box 18 Bowling Green Station Hew York, New York 10004 Gentlemen:

As we discussed with Mr. Feinstein of your staff, the HRC requests that you participate in a vital area analysis of the Cook Nuclear Station as part of the 10 CFR 73.55 security plan review.

Mr.

Richard M. Leep and Hr. Donald F.

Cameron of Los Alamos Scientific Laboratory, Los Alamos, Hew Ihxico have scheduled the week of August 28, 1978 for the analysis of the Cook Nuclear Station.

The proposed site visit would obtain information needed for the analysis of vital areas.

Your cooperation in admitting ger.

Leep and Mr. Cameron to the Cook site and in providing them the necessary input information for our analysis is necessary to complete the security plan review of the Cook Nuclear Station.

Upon completion of the analysis, we will be pleased to discuss the results with you and your staff.

Thank you for your assistance.

Sincerely, Original Signed by Q. z~h A. Schwencer, Chief Operating Reactors Branch Ho.

1 Division of Operating Reactors cc:

See next page DISTRIBUTION Docket Files 50-315 C. Parrish

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Indian 5 Michigan Electric Company-Indian 5 Michigan Power Company August 17, 1978 cc:

Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire

Shaw, Pittman Potts 8 Trowbridge 1800 M Street, NW Washington, D.C.

20036

, David Dinsmore Comey Executive Director Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Reston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Donald C.

Cook Nuclear Plant ATTN:

Mr.

D. Shaller Plant Manager P. 0.

Box 458

Bridgman, Michigan 49106

Docket Ho. 50-316)316 JUL 81 1978 American E)ectric Pe~er Service Corporation Indiana and ffich)Can Pwer CGBpany ATTN:. Hr. John E. Do1an Senior Executive Vice President, Engineering 2 Broadlfay fleer York, IÃ 10004 Gebnt1enen:

This ackneRedges receipt of your 1etter dated June 15, 1978

~herein you forwarded a check in the atttount of Ten Thousand Oo1'lars

($)0000) in ful) paymnt of the Notice of Proposed Imposition of Civi1 Pena1ties dated Eked 30, 1978.

Your June 16, 1978 1etter also responded to the )tees of noncomp1iance set forth in the tttotice of Vio1ation-dated N@r 30, 1978..

Your planned corrective actions have been reviewed by the staff, and ice have no further questions at this tig80 Sincere'fy~

I Ernst Vo1genau Director Office of Inspection and Enforcement D:IE NRC FORM 318 (9-76) NRCM 0240

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Aaerican Electric Purer Service Corporation ATTt<: f<r. John A. Til'finghast Vice Chaiman EogineeHng an< Construction 2 Broadway Na Yorg, HY 10004 Distribution:

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States of'ichigan, Nev York fm Indiana ACRS (3)

SECY E. Volgenau J.

G. Davis H. D. Thornburg CA (3)

F. Ingram, PA J. P. Murray, ELD J.

Lieberman, ELD fl. Grossman, ELD DOR; E. Reeves, ORB2 3l5 DPN: N. Nlynczak, LHR2 316 Coordinators:

Regions I, II, III, IV, V G. 0. Abston, IA IE Files'entral Files Civil Penalty Book XOOS Reading File EDO Reading File IE Reading File J. Crooks, NIPC tJ. P. Ellis T. M. Brockett F. A. Dreher OPPICE~

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UNITED STATES NUCLEAR R EGULATORY COMMISSION WASHINGTON, D. C. 20555 July 18, 1978 All Power Reactor Licensees and Applicants with Docketed Applications To Construct or Operate a Power Reactor Gentlemen:

This letter and enclosed NUREG/CR-0181 are being sent to all licensees authorized to operate a nuclear power reactor and to all applicants with applications for a license to operate or construct a power reactor.

NUREG/CR-0181 provides basic barrier and penetration data needed for physical security system assessment.

The data provided in the NUREG is being used by NRC during the reactor safeguards review process.

Additional copies of this document can be obtained from the National Technical Information Service, Springfield, Virginia 22161, at current prices.

Sincerely, g-f.'( C.j'.UI James R. Miller, Assistant Director for Reactor Safeguards Division of Operating Reactors

Enclosure:

NUREG/CR-0181 cc Without

Enclosure:

Service List

P fndian

& Michigan Electric Company-Indian

& Michigan Power Company 50-315 cc:

Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman Potts

& Trowbridge 1800 M Street, NW Washington, D.C.

20036 David Dinsmore Comey Executive Director Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Reston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 Donald C.

Cook Nuclear Plant ATTN:

Mr.

D. Shaller Plant Manager P.

0.

Box 458

Bridgman, Michigan 49106

JULY 1 2 1978 UTION Dockets Docket thos.

0-3 and 50-3l6 Indiana 5 Nichigan Electric Company Indiana 8 Michigan Power Company ATTN:

Nr. Qohn Tillinghast Vice President Post Office Box 18 Bo>sling Green Station New York, New York 10004 Gentlemen:.

LOCAL PDR ORB¹l Reading ASchwencer EReeves CParrish OELD OISE(3)

ACRS(16)

TBAbernathy JRBuchanan DEisenhut By letter dated April 5, 1978, you submitted responses to our January 12, 1978 request for information concerning the )'estinghouse Electric Corporation Report,

$1CAP-8887, "Ice Basket Stress Analysis-D. C. Cook, Harch 1977".

Based on our revievr of that submittal

>>e find that additional information is needed to comp'lete our review.

lie request that you respond to the enclosed request for additional information within 30 days of receipt of this letter.

Sincerely, Origtnal signed by A. Schwencer, VChief Operating Reactors Branch ¹1 Division of Operating Reactors Enc'fosu} e:

Request for Additional Information cc w/enc]:

See next page

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UNITEDSTATES NUClEAR REGULATORY COMMISSION WASHINGTON, D. C. 20666 JULY i 3 8y Docket Nos.

50-315 and 50-316 Indiana 8 Michigan Electric Company Indiana-5 Michigan Power Company ATTN:

Mr. John Tillinghast Vice:President Post Office Box 18 Bowling Green Station New York, New York 10004 Gentlemen:

By letter dated April 5, 1978, you submitted responses to our January 12, 1978 request for information concerning the Westinghouse Electric Corporation Report, WCAP-8887, "Ice Basket Stress Analysis-D. C. Cook, March 1977".

Based on our review of that submittal we find that additional information is needed to complete our review.

We request that.

you respond to the enclosed request for additional information I

within 30 days of receipt of this letter.

,Sincerely,

Enclosure:

Request for Additional Information A. Schwencer, Chief Operating Reactors Branch 5'1 Division of Operating Reactors cc w/encl:

See next page

Indian '& Michigan Electric Company Indian

& Michigan Power Company CC:

Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Pow'er Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire

Shaw, Pittman Potts

& Trowbridge 1800 M Street, NW Washington, D.C.

20036 David Dinsmore Comey Executive Director Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Reston Palenske Memorial Eibrary 500 Market Street St. Joseph, Michigan 49085 Donald C.

Cook Nuclear Plant ATTN:

Mr.

D.

Shaller'lant Manager P. 0.

Box 458

Bridgman, Michigan 49106

REQUEST FOR ADDITIONAL INFORMATION ICE BASKET STRESS ANALYSIS D. C.

COOK UNIT NOS.

1 AND 2 DOCKET NOS. 50-315 AND 50-316

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~RPA

~tyt Provide Tables 2 through 7, referred to in ICE-TR-079, page 4, subsection 4.0.

There is still some concern that the test arrangement is not furnishing the most conservative results.

It is correct that the ice has in some cases a stiffening effect. It is however possible to state that for certain buckling shapes the effect of ice pressure on the vertical ligament may make conditions worse.

Discuss this possibility.

Discuss also the adequacy of the.cruciform supports inserts to carry the ice load for which they are not designed.

The response does not include a discussion of the effect of concentrated loads in the hoop direction.

Provide this discussion.

Discuss the effect of the semicircular bracket in the axial direction.

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~ttbA-Include a proof demonstrating that the requirements of General Ice Condenser Design Criteri'a, Section C-6:

Experimental or Test Verification of Design are satisfied.

The concern is that a

2 span beam used as the model does not reproduce the same moment and shear distribution as obtained in the actual multiple span structure.

Your response covered only the end connection.

Cover the condition along the whole length of the structure.

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k lthh "7 lid" btl bdly deformed can still perform its function.

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JUNE 5

197B Docket l

. 50-31 616 n

Indiana l2 Hichigan Electric Company Indiana 8 Michigan Power

Company, ATTN:

Hr. John Tillinghast Vice President Post Office Box

'18 Bowling Green Station New York, Hew York 10004 Gentlemen:

RE tiAHPOHER RE(UIREHENTS FOR OPERATING REACTORS

~D-TR-IBT Docket s R~D, LOCAL PDR ORB¹l Reading ASchwencer TVWambach EReeves CParrish OELD 018 E(3)

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TBAbernathy JRBuchanan DEisenhut VSTe1lo We are enclosing a document entitled, "I'tanpower Requirements for Operating Reactors."

We are using the bases given in this document for allowing the sharing of duties to meet minimum staffing requirements for fire brigades at nuclear power plants.

This is being provided for your guidance in meeting NRC requirements in this area.

Sincerely, priginai signed 4V

Enclosure:

manpower Requirements for Operating Reactors cc w/encl:

See next page Victor Stello, Jr., Director Division of Operating Reactors Office of Huclear Reactor Regulation ORRICC~

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