ML20151Y153

Forwards Request for Addl Info for Review of Units 1 & 2 Integrated Plant Assessment Rept Containment Spray Sys

ML20151Y153
Person / Time
Site:	Calvert Cliffs
Issue date:	09/03/1998
From:	Dave Solorio NRC (Affiliation Not Assigned)
To:	Cruse C BALTIMORE GAS & ELECTRIC CO.
References
TAC-M99221, TAC-MA1038, TAC-MA1039, NUDOCS 9809180126
Download: ML20151Y153 (4)

Text

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, September 3,1998 Mr. Chrrl::s H. Crusa, Vice Presid:nt Nuclear Energy Division Baltimore Gas & Electric Company 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE I I

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.1 & 2, INTEGRATED PLANT ASSESSMENT REPORT CONTAINMENT SPRAY l SYSTEM (TAC NOS. MA1038, MA1039, AND M99221)

Dear Mr. Cruse:

By letter dated January 21,1998, Baltimore Gas and Electric Company (BGE) submitted for review the Containment Spray System (5.6) integrated plant assessment technical report as attached to the

• Request for Review and Approval of System and Commodity Reports for License Renewal." BGE requested that the Nuclear Regulatory Commission (NRC) staff review report 5.6 to determine if the report meet the requirements of 10 CFR 54.21(a), " Contents of application-technical information," and the demonstration required by 10 CFR 54.29(a)(1),

" Standards for issuance of a renewed license," to support an application for license renewal if BGE applied in the future. By letter dated April 8,1998, BGE formally submitted its license renewal application.

The NRC staff has reviewed report 5.6 against the requirements of 10 CFR 54.21(a)(1), and 10 CFR 54.21(a)(3). By letter dated April 4,1996, the NRC staff approved BGE's methcdology for meeting the requirements of 10 CFR 54.21(a)(2). Based on a review of the information submitted, the NRC staff has identified in the enclosure, areas where additionalinformation is needed to complete its review.

I Please provide a schedule by letter or telephonically for the submittal of your responses within 30 days of the receipt of this letter. Additionally, the NRC staff would be willing to meet with BGE prior to the submittal of the responses to provide clarifications of the staff's requests for additionalinformation.

Sincerely, M By David L. Solorio, Project Manager License Renewal Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosure:

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Mr. Charles H. Cruse Calvert Cliffs Nuclear Power Plant

' Baltimore Gas & Electric Company Unit Nos.1 and 2 cc:

i President Mr. Joseph H. Wciter, Chief Engineer Calvert County Board of Public Service Commission of 1 Commissioners Maryland 175 Main Street Engineering Division Prince Frederick, MD 20678. 6 St. Paul Centre l Baltimore, MD 21202-6806 I James P. Bennett, Esquire Counsel - Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2102 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge Patricia T. Birnie, Esquire 2300 N Streat, NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Thomas N. Prichett, Director Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donatelt 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road Chattanooga, TN 37411-4017 Resident inspector U.S. Nuclear Regulatory Commission David Lewis P.O. Box 287 Shaw, Pittman, Potts, and Trowbridge St. Leonard, MD 20685 2300 N Street, NW Washington, DC 20037 Mr, Richard I. McLean j Nuclear Programs Douglas J. Walters Power Plant Research Program Nuclear Energy Institute Maryland Dept. of Natural Resources 1776 l Street, N.W.

Tawes State Office Building, B3 Suite 400 Annapolis, MD 21401 Washington, DC 20006-3708 DJW@NEl.ORG Regional Administrator, Region 1

-- U.S. Nuclear Regulatory Commission Barth W. Doroshuk 475 Allendale Road Baltimore Gas and Electric Company King of Prussia, PA 19406 Catvert Cliffs Nuclear Power Plant i' 1650 Calvert Cliffs Parkway NEF ist Floor Lusby, Maryland 20657

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l- BE.QUESI.f QR.ADQlIlQNAL.lNE.QBIBAIlON l-CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NOS.1 fd j CONTAINMENT SPRAY SYSTEM l lNTEGRATED PLANT ASSESSMENT. SECTION 5.6  !

l DOCKET NOS. 50-317 AND 50-318 l

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Section 5.8.2 - Aoing Management

1. Section 5.6.2 states that some components in the shutdown cooling (SDC) flowpath  ;

experienced significant thermal transients during SDC operations. Please identify these l components and characterize the extent of the thermal transients they experienced.

Identify the parameters and specific criteria that are used to monitor and manage j- thermal cyclic fatigue for these components, j l 2. Section 5.6.2 indicates that core spray (CS) system components in the SDC flowpath, l namely SDC heat exchangers, the associated piping, temperature instrurr5nts and l l valves, have fatigue usage factors which are bounded by the fatigue usage of the SDC l L and safety injection (SI) nozzles that connect the SI system piping to tne reactor coolant i l system (RCS). Clarify the technicaljustification for this conclusion. Also, describe the I fatigue criteria uesd in the design of the CS system components in the SDC flowpath l and justify the applicabiWy of tilat criteria to the period of extended operation.

l l 3. Section 5.6.2 indicantes that based on inservice inspections and additional examinations, i it was concluded that ths Negii:/ of welds in the CS pump discharge piping and the I

{ high pressure safety injection (11 PSI) piping from the SDC heat exchanger discharge, l have not been affected by the service environment and residual stresses that have induced pipe cracking elsewhere in the industry. It is further stated that, since these portions of the CS system rr.ay not have any flow due to flushing or performance testing for periods of at least 30 days during normal reactor operation, they were recognized as portions of the CS system which has a high likelihood of containing stagnant oxygenated borated water, an environmental condition which has induced cracks in welds elsewhere in the industry. On the bases of this information, justify the conclusion that similar cracking of welds due to reddual stresses and fatigue will not occur in this portion of the l CS system during the period of extended operation.

4. Section 5.6.2 indicates that the SDC'and Si nozzles that connect the Si system piping to the RCS are among the 11 fatigue-critical locations selected for monitoring under the Calvert Cliffs Nuclear Power Plant fatigue monitoring program (FMP). Describe the specific criteria used for selecting these nozzles for the FMP and indicate the reason the FMP calls for an engineering evaluation of these nozzles.

5. It is stated in the license renewal application that the FMP monitors and tracks low-cycle i

fatigue usage for the selected components of the Nuclear Steam Supply System and the steam generators. Describe the parameters that are monitored by the FMP that are l applicable to the SDC and Si nozzles in the CS system. Also describe how the

monitored parameters are compared to the fatigue analysis of record, and the criteria

) used to initiate corrective action.

4 l Enclosure t

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