ML20151V397

Forwards Request for Addl Info Re Licensee 971217 Submittal of Reactor Coolant Sys Integrated Plant Assessment Technical Rept as Part of License Renewal Application

ML20151V397
Person / Time
Site:	Calvert Cliffs
Issue date:	09/02/1998
From:	Dave Solorio NRC (Affiliation Not Assigned)
To:	Cruse C BALTIMORE GAS & ELECTRIC CO.
References
TAC-M99223, TAC-MA1016, TAC-MA1017, NUDOCS 9809140294
Download: ML20151V397 (4)

Text

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g September 2,1998 I Mr. Chirl;s H. Crusa, Vica Prcsid:nt s Nuclear Energy Division Baltimore Gas and Electric Company 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.1 & 2, INTEGRATED PLANT ASSESSMENT REPORT FOR THE REACTOR COOLANT SYSTEM (TAC NOS. MA1016, MA1017, AND M99223)

Dear Mr. Cruse:

By letter dated December 17,1997, Baltimore Gas and Electric Company (BGE) submitted for review the Reactor Coolant System (4.1) 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 the Reactor Coolant System (4.1) report to determine if this report meets the requirements of 10 CFR 54.21(a)," Contents of application-technicalinformation," 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, BG81 formally submitted its license renewal application.

The NRC staff has reviewed the Reactor Coolant System (4.1) report against the requirements of 10 CFR 54.21(a)(1),10 CFR 54.21(a)(3). By letter dated April 4,1996, the staff approved BGE's methodology for meeting the requirements of 10 CFR 54.21(a)(2). Based on a review of the information submitted, the staff has identified in the enclosure, areas where additional information related to scoping is needed to complete its review. Should the staff have additional information needs related to aging management they will be forwarded under a future correspondence.

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 staff would be willing to meet with BGE prior to the submittal of the responses to provide clarifications of the staff's requests for additional information. ,

1 Sincerely, MMD 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:

Request for Additional Information cc w/ encl: See next page l DISTRIBUTION: '

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See next page > 1 DOCUMENT NAME GiWORKING\SOLORIO\RCS RAl2 LTR / (j l OFFICE PDLR/DRPM LA:PDI-g , %R/DRf61:ASC PDLR/DRPM:D NAME SLittisF DSolori,$ BPra k CGrimesh DATE 9 /d /98 f/ L/98 [/ /9h k /'),, /98" ,

UFFICIAL RECORD COPY ic073 NRC HLE CENTEB CGM 9009140294 980902 PDR ADOCK 05000317 P PDR

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Mr. Charles H. Cruse Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos.1 and 2 cc:

Mr. Joseph H. Walter, Chief Engineer President Public Service Commission of Calvert County Board of Maryland Commissioners Engineering Division 175 Main Street 6 St. Paul Centre Prince Frederick, MD 20678 Baltimore, MD 21202-6806 James P. Bennett, Esquire Kristen A. Burger, Esquire Counsel Maryland People's Counsel Baltimore Gas and Electric Company 6 St. Paul Centre P.O. Box 1475 Suite 2102 Baltimore, MD 21203 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire Patricia T. Birnie, Esquire Shaw, Pittman, Potts, and Trowbridge Co-Director l 2300 N Street, NW Maryland Safe Energy Coalition l Washington, DC 20037 P.O. Box 33111 Baltimore, MD 21218 l Mr. Thomas N. Prichett, Director NRM Mr. Loren F. Donatell Calvert Cliffs Nuclear Power Plant NRC Technical Training Center 1650 Calvert Cliffs Parkway 5700 Brainerd Road Lusby, MD 20657-4702 Chattanooga, TN 37411-4017 Resident Inspector David Lewis i

U.S. Nuclear Regulatory Commission Shaw, Pittman, Potts, and Trowbridge l P.O. Box 287 2300 N Street, NW i St. Leonard, MD 20685 Washington, DC 20037 Mr. Richard I McLean Douglas J. Walters Nuclear Programs Nuclear Energy Institute Power Plant Research Program 1776 l Street, N.W.

Maryland Dept. of Natural Resources Suite 400 Tawes State Office Building, B3 Washington, DC 20006-3708 Annapolis, MD 21401 DJW@NEl ORG Regional Administrator, Region I Barth W. Doroshuk U.S. Nuclear Regulatory Commission Baltimore Gas and Electric Company 475 Allendale Road Calvert Cliffs Nuclear Power Plant King of Prussia, PA 19406 1650 Calvert Cliffs Parkv ay NEF ist Floor Lusby, Maryland 20657 t

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Distribution:

HARD COPY Docket Files PUBLIC PDLR R/F MEl-Zeftawy DISTRIBUTION: E-MAIL:

FMiraglia (FJM)

JRoe (JWR)

DMatthews (DBM)

CGrimes (CIG)

TEssig (THE)

Glainas (GCL)

JStrosnider (JRS2)

GHolahan (GMH) l SNewberry (SFN)

GBagch!(GXB1) l l

RRothman (RLR)

JBrammer (HLB)

CGratton (CXG1)

JMoore (JEM)

MZobler/RWeisman (MLZ/RMW)

SBajwa/ADromerick (SSB1/AXD) l LDoerflein (LTD)

BBores (RJB)

SDroggitis (SCD)

RArchitzel(REA)

CCraig (CMC 1)

LSpessard (RLS)

RCorreia (RPC) 4 RLatta (RML1)

EHackett (EMH1)

AMurphy (AJM1) )

TMartin (TOM 2)

DMartin (DAM 3) l GMeyer (GWM)

WMcDowell (WDM)

SStewart (JSS1)

THiltz (TGH)

SDroggitis (SCD)

DSolorio (DLS2)

PDLR Staff TCollins (TEC)

RCaruso (RXC)

MRazzaque (MMR1)

Slittle (SLL)

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'n REQUEST FOR ADDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NOS.1 & 2 REACTOR COOLANT SYSTF.M

, INTEGRATED PLANT ASSESSMENT. SECTION 4.1 DOCKET NOS. 50-317 AND 50-318

Section 4.1.1 - Scoolna

]

Regarding the structures and components identified as being within the scope of license renewal for the Reactor Coolant System (RCS), the NRC staff has the following questions:

1

! 1. Please explain why the pressurizer spray and auxiliary spray nozzles were not included within the scope of license renewal?  ;

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2. In Table 4.1-2, " Tank (TK)" was listed as a device type requiring aging management  ;

I review (AMR). But, Figure 4.1-1 shows that the Quench Tank No.11 is not within the scope of license renewal. Please clarify this apparent discrepancy.

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. 3. The device type, " Miscellaneous (XL)," listed in Table 4.1-1 has been classified as only i associaied with active functions, and therefore, was excluded from the AMR. Please I j describe the types of components that make up this device type.

i 4. In Table 4.2-2 in Section 4.2, footnotes were used to indicate that "not all components of a device type were affected by the ARDM." This has been interpreted to mean that some components within the device type category are not subject to the effects of the listed plausible aging related degradation mechanism (ARDM). Referring to Table 4.1-3 l

in subsection 4.1.1.2, please clarify whether any subcomponents of the components listed in the table are similarly not subject to the plausible ARDMs shown.

Enclosure