ML20237A823

Forwards Request for Addl Info for Review of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 Re Integrated Plant Assessment Rept for Component Cooling Sys

ML20237A823
Person / Time
Site:	Calvert Cliffs
Issue date:	08/11/1998
From:	Dave Solorio NRC (Affiliation Not Assigned)
To:	Cruse C BALTIMORE GAS & ELECTRIC CO.
References
TAC-M99205, TAC-M99583, TAC-M99584, NUDOCS 9808170163
Download: ML20237A823 (5)

Text

. - _ _ - _ _ - . ._

^

August 11, 1998

. Mr. Chiries H. Cruse, Vica Presid:nt Nuciar Energy Division -

l Baltimore Gas & Electric Company .

1650 Calvert Cliffs Parkway Lusby, Maryland 20657-47027

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 & 2, INTEGRATED PLANT ASSESSMENT REPORT FOR THE COMPONENT COOLING SYSTEM (TAC NOS. M99583, M99584, M99205)

Dear Mr. Cruse:

By letter dated July 30,1997, Baltimore Gas and Electric (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 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 staff has reviewed the Component Cooling System (5.3) integrated plant assessment L 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 sta*f 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 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 staffs requests for additional

- information.

Sincerely,

! Original signed by

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

Enclosure:

As stated

l. cc w/ enclosure: See next page DISTRIBUTION. .

l. i bb I See next page

. DOCUMENT NAME:G:\ WORKING \SOLORIO\CCS_RAI LTR k OFFICE PDLR/Q PDLR/DRPM:ASC PDLR/DRPM:D - I NAME DSolosin30 SLeel%.-

f CGrimes[ h' DATE-8{ /98 8////98 8/ll/98 ~l OFFICIAL RECORD COPY 9808170163 980811 PDR ADOCK 05000217 P PDR

. s

]

i

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

President .

Mr. Joseph H. Walter, Chief Engineer

. 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. Bimie, Esquire 2300 N Street, NW Co-Director Washington, DC 20037 - Marylana 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 Centar 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 l Street, N.W.

. Tawes State Office Building, B3 Suite 400 Annapolis, MD 21401 Washington, DC 20006-3708 Regional Administrator, Region I

! U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 i . . _ _ - .-__ _ __ - _ _-_-________________ _ _ _ - _

Distribution:

HARD COPY r H OEDO Rlli 0-16B18 '

PUBLIC l

DISTRIBUTION: E-MAIL-FMiraglia (FJM) ]

1 JRoe (JWR) l l DMatthews (DBM)

CGrimes (CIG)

)

TEssig (THE)

GLainas (GCL) i JStrosnider (JRS2)

GHolahan (GMH)

SNewberry (SFN)

GBagchi(GXB1) l RRothman (RLD)

JBrammer (HLB) ,

CGratton (CXG1)

JMoore (JEM)

MZobler/RWeisman (MLZ/RMW) l SBajwa, (SSB1)

' ADromerick(AXD)

LDoerflein (LTD)

BBores (RJB)

SDroggitis (SCD)

MMalloy (MXM)

CCraig (CMC 1)

LSpessard (RLS)

RCorreia (RPC) -

RLatta (RML1) l DMartin (DAM 3)

WMcDowell (WDM)

DSolorio (DLS2)

SStewart (JSS1)

PDLR Staff WLefave (WTL1)  !

- GGeorgiev (GBG) j i,

t

a a s Enclosure REQUEST FOR ADDITIONAL INFORMATION

' CALVERT CLIFFS UNITS 1 AND 2 COMPONENT COOLING SYSTEM INTEGRATED PLANT ASSESSMENT. SECTION 5.3 DOCKET NOS. 50-317/S0-318 Section 5.3.1 Sconina

1. In Subsection 5.3.1.1 under Interfacing Systems the report lists interfacing systems with the CC system. Additionally, the report states that "the CC system at the interface may not be within the scope of license renewal. . ." For the CC system piping at the interfaces identified to be outside the scope of license renewal identify the components at the interfaces that maintain the pressure boundary function.

2. Section 5.4 of the compressed air system report identifies that certain air-operated components used with particular systems will be included (i.e., pressure retaining functions) within the kdividual system and not the compressed air system. Based on our review we could not determine how the pressure retaining functions of air-operated components were addressed in the CC system. As there are a number of air-operated components within the CC system, for example valves CV-3840, and CV-3825 shown in the CC system piping and instrument drawing 8307210017-26 (obtained from the Calvert Cliffs Update Final Safety Analysis Report), please explain your process for how air-operated components within the CC system were addressed in the license renewal application (LRA) (and if the process used is the same for other applicable systems indicate that also). Additionally, for other air-operated components that are within systems other than compressed air system please provide a cross reference to where these components are addressed in the LRA or provide justification for their exclusion

, with special emphasis given to why a faliure of the compressed air pressure boundary that these components maintain will not affect any safety related functions of the systems in which they reside or the compressed air system.

Section 5.3.2 Aging Management -

3. Are there any parts of the systems, structures and components that are inaccessible for inspection? If so, describe what aging management program will be relied upon to maintain the integrity of the inacesssible areas. If the aging management program for the inaccessible areas is an evaluation of the acceptability of inaccessible areas based on conditions found in surrounding accessible areas, please provide information to show that conditions would exist in accessible areas that would indicate the presence of or result in degradation to such inaccessible areas. If different aging effects or aging management techniques are needed for the inaccessible areas, please provide a

. summary to address the following elements for the inaccessible areas

(1) Preventive

' actions that will mitigate or prevent aging degradation. (2) Parameters monitored or inspected relative to degradation of specific structure and component intended functions. (3) Detection of aging effects before loss of structure and component intended 94 l

e functions. (4) Monitoring, trending, inspection, testing frequency, and sample size to ensure timely detection of aging effects and corrective actions. (5) Acceptance criteria

' to ensure structure and component intended functions. (6) Operating experience that provides objective evidence to demonstrate that the effects of aging will be adequately

managed.

['

9 1

i l

l i