ML20151X763

From kanterella
Jump to navigation Jump to search

Forwards RAI Re Plant,Units 1 & 2 Integrated Plant Assessment Technical Rept for Component Cooling Sys (5.3). Response Requested within 30 Days of Receipt of Ltr
ML20151X763
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/27/1998
From: Dave Solorio
NRC (Affiliation Not Assigned)
To: Cruse C
BALTIMORE GAS & ELECTRIC CO.
References
TAC-M99205, TAC-M99583, TAC-M99584, NUDOCS 9809170241
Download: ML20151X763 (4)


Text

Mr. Chrrl:s H. Crusa, Vice Pr sid:nt August 27, 1998 Nuclear Energy Division J' Baltimore Gas & Electric Company 1

1650 Calvert Cliffs Parkway Lusby, MD 20657-47027 l

l

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 COMPONENT COOLING SYSTEM (TAC NOS. M99583, M99584 AND M99205) '

Dear Mr. Cruse:

By letter dated July 30,1997, Baltimore Gas and Electric Company (BGE) submitted for review the Component Cooling System (5.3) 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 Component Cooling System (5.3) integrated plant assessment technical report 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 the Component Cooling System (5.3) integrated plant assessment technical report against the requirements of 10 CFR 54.21(a)(1) and 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). By letter dated August 1,1998, the NRC forwarded requests for additional information to BGE in order to give BGE additional time to prepare its responses while the staff was continuing its review of the subject report. Based on the continued review of Section 5.3 of BGE's license renewal application, the staff has identified in the enclosure additional areas beyond those outlined in the August 1,1998 letter where information 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 additional information.

Sincerely, ad L Wo, Ned Manager 9809170241 980827 PDR ADOCK 05000317 License Renewal Project Directorate P PDR Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket Nos. 50-317,50-318 I

Enclosure:

As stated cc w/ enclosure: See next page DISTRIBUTION:

See next page

  • } g g % h
  • See previous concurrence DOCUMENT NAME G3 WORKING \SOLORIO\CCS_RAl2 LTR / ( y m\

OFFICE \

LA-PDI-1 PDLR/DRPM

%R/DRP)(ASC PDLR/DRPM:D l NAME Slittle DSolorio BPra% CGrimes[h DATE 8/26/98* 8/26/98* / 8/ /k 8/Z798 W

'i G J

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

l President Mr. Joseph H. Walter, Chief Engineer l Calvert County Board of Public Service Commission of Commissioners Maryland 175 Main Street Engineering Division Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806 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 l 2300 N Street, NW Co-Director i 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 ist Floor Lusby, Maryland 20657 y g . , - . . _ - . ..m*, -

m-** , . , .

s i Distribution:

HARD COPY M%%

PUBLIC PDLR R/F MEl Zeftawy DISTRIBUTION: . E-MAIL:

FMiraglia (FJM)

JRoe (JWR)

DMatthews (DBM)

CG'imes (CIG)

TEssig (THE)

GLainas (GCL)

JStrosnider (JRS2)

GHolahan (GMH)

SNewberry (SFN)

GBagchi(GXB1)

RRothman (RLR)

JBrammer (HLB)

CGratton (CXG1)

JMoore (JEM)

MZobier/RWeisman (MLZ/RMW)

SBajwa/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)

DSolorio (DLS2)

PDLR Staff WLefave (WTL1)

L GGeorgiev (GBG) l JRajan(JRR) l KParczewskl(KIP)

Slittle (SLL) l

A l

.o REQUEST FOR ADDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NOS.1 & 2 COMPONENT COOLING SYSTFJ8 INTEGRATED PLANT ASSESSMENT. SECTION 5.3 DOCKET NOS. 50 317 AND 50 318 4

Section 5.3.2 Aging Management

1. The potential age related degradation mechanisms for the Component Cooling System (CCS) have been identified in Table 5.3-3 of Section 5.3 of the license renewal application. The components of the CCS were judged not to be susceptible to low cycle fatigue or corrosion fatigue. Describe the justification and any specific criteria used to make this determination for the piping, check valves, control valves and the pump / driver assemblies of the CCS.

1 Carbon steel piping bends, elbows and nozzles are vulnerable to erosion corrosion which has been identif;cd as an age related degradation mechanism for the CCS piping.

General wall thinning is anticipated as a result of erosion corrosion. Describe the specific evaluations which have been performed (or will be performed) to ensure structuralintegrity of the piping due to the effects of cyclic fatigue at locations where wall thinning may occur during the extended period of operation.

3. The rate of corrosien of components in the CCS can be mitigated by proper control of water chemistry. Please, provide specifications for water chemistry in the CCS. Your answer should include target values for individual parameters and their monitoring frequency.
4. In a 1996 summary report referenced in Section 5.3.2, severalincidents which occurred at Calvert Cliffs that resulted in water chemistry parameters exceeding their action levels were mentioned. Baltimore Gas and Electric Company took actions to correct these conditions. Describe these actions, and the experience gained from implementation of these actions with respect to maintaining water chemistry parameters below action levels.

I I

Enclosure i