ML20151X771

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Forwards RAI Re Plant,Units 1 & 2 Integrated Plant Assessment Rept for Fire Protection Sys (5.10).Response Requested within 30 Days of Receipt of Ltr
ML20151X771
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 09/04/1998
From: Dave Solorio
NRC (Affiliation Not Assigned)
To: Cruse C
BALTIMORE GAS & ELECTRIC CO.
References
TAC-M99214, TAC-MA1445, TAC-MA1446, NUDOCS 9809170245
Download: ML20151X771 (4)


Text

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, September 4, 1998 Mr. Charl;s H. Crust, 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 CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS.1 & 2, INTEGRATED PLANT ASSESSMENT REPORT FOR FIRE PROTECTION SYSTEM (TAC NOS. MA1445, MA1446, AND M99214)

Dear Mr. Cruse:

By letter dated March 27,1998, Baltimore Gas and Electric Company (BGE) submitted for review the Fire Protection System (5.10) 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 Fire Protection System (5.10) integrated plant assessment technical report to determine if the report meets 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 the Fire Protection System (5.10) integrated plant assessment technical 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.

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 additionalinformation.

Sincerely,

&&N 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 Additionalinformation cc w/ encl: See next page DISTRIBUTION:

See next page ,_ }

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  • 9/4/98 [ 9/ /gh W 9//h/98 9/$98 OFFICIAL RECORD COPY
?r:143 9809170245 900904 PDR ADOCK 050003 7 Q(QMM V-

I Mr. CharlIs H. Cruse Calvert Cliffs Nuclear Power Plant l 1 . Baltimore Gas & Electric Company Unit Nos.1 and 2 l

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President . Mr. Joseph H. Walter, Chief Engineer

- Calvert County Board of Public Service Commission of Commissioners Maryland  :

175 Main Street Engineering Division l Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806 l 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 Street, 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. Donatell 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 -

Nuclear Programs Douglas J. Walters Power Plant Research Program Nuclear Energy Institute Maryland Dept. of Natural Resources 1776 i Street, N.W.

Tawes State Office Building, B3 - Suite 400 Annapolis, MD 21401 Washington, DC 20006-3708 DJW@NEl.ORG Regional Administrator, Region i U.S. Nuclear Regulatory Commission Barth W. Doroshuk 475 Allendale Road Baltimore Gas and Electric Company King of Prussia, PA 19406 Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway NEF 1st Floor Lusby, Maryland 20657

LX L Distribution:

l 4 HARD COPY

  • WZ$es 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)

SNewberry (SFN)

GBagchi(GXB1)

RRothman (RLR)

JBrammer (HLB)

CGratton (C"G1)

JMoore (JEM)

MZobler/RWeisman (MLZ/RMW)

GBajwa/ADromerick (SSB1/AXD)

LDoerflein (LTD)

BBores (RJB)

SDroggitis (SCD)

RArchitzel(REA)

CCraig (CMC 1)

LSpessard (RLS)

RCorreia (RPC)

RLatta (RML1)

EHackett (EMH1)

AMurphy (AJM1)

TMartin (TOM 2)

DMartin (DAM 3)

GMeyer (GWM)

WMcDowell(WDM)

SStewart (JSS1)

- THiltz (TGH)

SDroggitis (SCD) i DSolorio (DLS2) l PDLR Staff 1

l SWest (KSW)

CBajwa (CSB1)

TCheng (TMC)

SLittle (SLL)'

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( I REQUEST FOR ADDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NOS.1 & 2 FIRE PROTECTION SYSTEM l INTEGRATED PLANT ASSESSMENT. SECTION 5.10 DOCKET NOS. 50-317 AND 50-318 Sicflon 5.10.1 - Scoolna

1. Section 5.10, " Fire Protection," addresses the fire protection (FP) functions and the safe shutdown function (Appendix R to 10 CFR 50). Describe how the Calvert Cliffs Fire Protection Plan, which is required under 10 CFR 50.48, " Fire Protection," was used in developing the system-level scoping and the integrated plant assessment (including FP and safe shutdown).
2. Summarize the changes to the post-fire safe shutdown analysis and the fire hazards analysis that have been implemented since plant licensing and briefly discuss how the analyses, including changes, were addressed in the system level scoping process.
3. Identify the fire protection components, if any, that have been excluded from the scope of the rule because they are subject to replacement based on qualified life or a specified time period as permitted under 10 CFR 54.21(a)(1)(ii).
4. Describe, in detail, how the post-fire remote or auxiliary shutdown panels were '

addressed in the system level scoping process and the aging management review process.

I i

Enclosure

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