ML20034G421
| ML20034G421 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/03/1993 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-M83222, NUDOCS 9303090489 | |
| Download: ML20034G421 (35) | |
Text
{{#Wiki_filter:. j o "c oq}t u. UNITED STATES [ f[ ] NUCLEAR REGULATORY COMMISSION 'l g WASHINGTON, D.C. 2068f4001 / March 3, 1993 ~ Docket Nos. 50-317 and 50-318 ( I LICENSEE: Baltimore Gas and Electric Company (BG&E) FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 l 9
SUBJECT:
MEETING. MINUTES REGARDING THE FEBRUARY 11, 1993, MEETING TO DISCUSS THE MECHANICAL ENGINEERING DESIGN ASPECTS OF THE TWO NEW EMERGENCY DIESEL GENERATORS AND SUPPORT SYSTEMS WHICH ARE TO BE ADDED TO THE I CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2.(TAC NOS. M83222 AND M83223) i BACKGROUND: On July 21,1988, Part 50 of Title 10 of the Code of Federal Regulations was i amended to include a new Section 50.63, entitled, " Loss of All Alternating Current Power," referred to as the station blackout (SB0) rule. The 580 rule ~ requires that each light-water cooled nuclear power plant be able to withstand j and recover from an SB0 of specified duration. The SB0. rule also requires that information defined in the rule be provided to the staff for review. l. BG&E responded to the requirements of the rule and the' staff approved'its response by letter dated February 12, 1992. The staff's approval included the addition of two new safety-related Class-lE emergency diesel generators- ) (EDGs). Three meetings, which are part of a series of meetings, have been a held to discuss: the preliminary design, seismic and structural design,- and 4 the EDG design (including codes, standards, testing and quality assurance). i PURPOSE: 1his meeting focused on the mechanical engineering design aspects of the EDGs, their support systems and the other systems in the new EDG building. These systems included:' the demineralized water systems, compressed air system, heating and ventilation system, and the fire protection system. 1 A list of attendees is attached as Enclosure 1 and the BG&E presentation is i attached as Enclosure 2. 050042
SUMMARY
All of the topics listed in' Enclosure 2 were discussed during the meeting, ' i i The detailed discussions of the EDGs, their support systems and the other . systems in the new EDG building, as identified above, included details on the' applicable codes and standards. This portion of the presentation included: high energy line breaks,- seismic design, piping design codes, stress analysis,- 1 l and environmental qualification. g r9 '" f"I@]c L hh,/ 9303090489 930303 e ~: PDR ADOCK 05000317 Q
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t --l , March 3, 1993 The staff provided several comments during the presentation in areas where additional consideration should be given to assure that the BG&E submittal will include sufficient detail and will address all areas necessary for-staff review. ,a The staff indicated that the preser'ation was informative, facilitated communications, and should assist in a timely review when the EDG modifications are provided for staff review. ~ Daniel G. Mcdonald, Senior Pr ect Manager Project Directorate I-l Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Enclosures:
1. Attendance List 2. Emergency Diesel Generator Addition Project cc w/ enclosures: See next page h [ 6 2 I er, i
t ~ Calvert Cliffs Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos. I and 2 i cc: Mr. Michael Moore, President Mr. Joseph H. Walter Calvert County Board of Engineering Division l Commissioners Public Service Commission of 175 Main Street Maryland Prince Frederick, Maryland 20678 American Building 231 E. Baltimore Street D. A. Brune, Esquire Baltimore, Maryland 21202-3486 General Counsel i Baltimore Gas and Electric Company Kristen A. Burger, Esquire P. O. Box 1475 Maryland People's Counsel Baltimore, Maryland 21203 American Building, 9th Floor 231 E. Baltimore Street Jay E. Silberg, Esquire Baltimore, Maryland 21202 Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW Patricia T. Birnie, Esquire Washington, DC 20037 Co-Director Maryland Safe Energy Coalition Mr. G. L. Detter, Director, NRM P. O. Box 33111 Calvert Cliffs Nuclear Power Plant Baltimore, Maryland 21218 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-4702 Mr. Robert E. Denton Vice President'- Nuclear Energy Resident Inspector Baltimore Gas and Electric Company c/o U.S. Nuclear Regulatory Calvert Cliffs Nuclear Power Plant Commission 1650 Calvert Cliffs Parkway s P. O. Box 287 Lusby, Maryland 20657-4702 St. Leonard, Maryland 20685 Mr. Richard I. McLean Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue Tawes State Office Building B3 Annapolis, Maryland 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406
FEBRUARY 11. 1993 NRC/BG&E MEETING ADDITION OF EMERGENCY DIESEL GENERATORS ATTENDANCE LIST PARTICIPANTS ORGANIZATION Daniel G. Mcdonald, Jr NRR/DRP/PDI-l Mikhail Ratyshny MD PSC Tom Konerth BG&E Charles R. Mahon BG&E/ Diesel Generator Project Philie J. Hebrank BG&E/ Diesel Generator Project Harold J. Mantle Bechtel/M&QS Staff Christy Leskovar Bechtel/DG Mechanical Wayne Smith Bechtel Rena Lee Bechtel Michael Mikolanis Bechtel Arnold Lee NRR/DE/EMEB Mark Hartzman NRR/DE/EMEB Terence Chan NRR/DE/EMEB Daniele Oudinot NRR/DSSA/SPLB Isabel Moghissi Miller NRR/DSSA/SPLB Richard A. Skokowski RI/DRS/EBES Pat furio BG&E Jai Raj Rajan ~ NRR/EMEB .m..
l I j EMERGENCY DIESEL 'i GENERATOR s ADDITION PROJECT l i I i i MECHANICAL 1 i ENGINEERING MEETING l FEBRUARY 11,1993 l l l
MECHANICAL ENGINEERING MEETING I. INTRODUCTION i 11. SYSTEM DESCRIPTION A. DIESEL GENERATOR AND SUPPORT SYSTEMS B. DEMINERALIZED WATER SYSTEM C. COMPRESSED AIR SYSTEM D. BUILDING HEATING AND VENTILATION SYSTEM E. FIRE PROTECTION SYSTEM 111. CODES AND STANDARDS A. HIGH ENERGY LINE BREAK B. SEISMIC DESIGN C. PIPING DESIGN CODES D. STRESS ANALYSIS E. ENVIRONMENTAL QUALIFICATION IV. OUESTIONS
k i i I INTRODUCTION l r h LICENSING PROCESS SCHEDULED MEETINGS CURRENT PROJECT STATUS i [ h e t h E
I EDG DESIGN MEETINGS WITH NRC p civil / SEISMIC DESIGN MAY 1992 l \\ EDG DESIGN OCTOBER 1992 i MECHANICAEDESIGNLn. mm mmw3ysym;mys~:ymm;c--vvc3ggynm;wernynnm is ' iFEBRUAR%19 38 mui a.m;.. A a; L F % h issassM C samma ELECTRICAL DESIGN MARCH 1993 l l&C DESIGN MAY 1993 i 1 1
DIESEL GENERATOR 1 AND i l SUPPORT SYSTEMS 9 DESCRIPTION l d 4 j 2 ~ l I l ) I
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t I i 1 i 1 i r W r 1 MECHANICAL i i e i h SYSTEM I .6 DESCRIPTIONS n i I i i i i i k 2 i
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~ i e o DEMINERALIZED WATER SYSTEM SAFETY DESIGN BASIS 1 i PROVIDES WATER FOR MAKEUP TO HIGH L TEMPERATURE AND LOW TEMPERATURE COOLING SYSTEMS i i NOT RELIED UPON TO PERFORM ANY SAFETY FUNCTION I t i L 3 i i i l l i f q
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COMPRESSED AIR SYSTEM i i SAFETY DESIGN BASIS i PROVIDES A SOURCE OF FILTERED, OlL-FREE COMPRESSED AIR NONE OF THE SAFETY-RELATED EQUIPMENT RELIES UPON THE COMPRESSED AIR SYSTEM TO PERFORM ITS SAFETY FUNCTION t p -up<, i
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DESIGN INTERIOR TEMPERATURE RANGES FOR THE DIESEL GENERATOR BUILDINGS AREA MAXIMUM TEMPERATURE MINIMUM TEMPERATURE BATTERY Room 104*F 69"F IE SWITCHGEAR Room 104*F 50*F DIESEL GENERATOR BLDG 104*F 50*F CONTROL ROOM ALL OTHER ROOMS 120*F 50*F I ~... -.....,. -
1 l FIRE PROTECTION SYSTEM SAFETY DESIGN BASIS LOSS OF POWER OR SYSTEM TROUBLE WILL NOT CAUSE THE AUTOMATIC RELEASE OF WATER OR CAUSE j A TRIPPED DELUGE VALVE TO CLOSE l A PIPE CRACK WILL NOT ACTUATE A DELUGE VALVE OR CAUSE FLOODING OF THE BUILDING FAILURE OF ONE SMOKE OR HEAT DETECTOR WILL NOT ADVERSELY AFFECT THE REST OF THE SYSTEM i i i I i a l [
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s l HIGH ENERGY LINE BREAK ONLY HIGH ENERGY SYSTEM IS THE STARTING AIR SYSTEM ALL STARTING AIR PIPE IS 1-INCH OR LESS IN DIAMETER e THEREFORE: CIRCUMFERENTIAL OR LONGITUDINAL PIPE BREAKS DO NOT HAVE TO BE POSTULATED PER SRP 3.6.2 l l
SEISMIC DESIGN / ANALYSIS METHODS PIPING SYSTEMS ARE ANALYZED USING THE MODAL RESPONSE SPECTRUM ANALYSIS METHOD MASSES AND MODES ARE ESTABLISHED USING SRP 3.7.2 MODAL AND DIRECTIONAL RESPONSES ARE COMBINED IN ACCORDANCE WiTH REG. GUIDE 1.92, REVISION 1 DYNAMIC ANALYSIS DONE USING EITHER LUMPED MASS OR FINITE ELEMENT MODELING DAMPING - EITHER CODE CASE N-411 OR REG. GUIDE 1.61, REVISION 0 WAS USED EFFECTS OF CLOSELY SPACED MODES WAS CONSIDERED USING NRC GROUP METHOD (REG. GUIDE 1.92, REVISION 1)
-t PIPING DESIGN CODES / CATEGORY I PIPING - ASME 111, SUBSECTIONS NCA, ND, NF,1986 CATEGORY 11 PIPING - ASME B31.1,1989 CATE ;ORY ll/l PIPE SUPPORTS - ASME B31.1,1989 STRES'. ANALYSIS INCLUDES: DEADWEIGHT THERMAL SEISMIC l DESIGN PRESSURE l MAXIMUM OPERATING PRESSURE h
DIESEL GENERATOR PROJECT-MECilANICAL CODE BOUNDARIES FUEL Olt STORAGE TANK I FUEL Oll OD DAY TANK FUEL DIL TRANSFER PUMP A A EXNAUST l I EXNAUST 3 - - ( S I L E NC E R j - ~ ~ ~ ~ ~ - - - ', [-- -- ~ ~ ~ -- ~ { S ILENCER j - ' s LUBE Olt i p---] l DAY TANK l --g AUXILIARY s AUXlLIARY I DESK l-- l I d DESK L___J l l___J m m i e i r -~ ~ ~ " ~ ' -- 1 r '--~~ "~~~-- i G c. m m c._._. i i i i m m COMPRESSOR'J l ENGINE CW GENERA 10R I} ENGINE CCW l b {l
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a l L____J7 i = .._._.__.._..__.._._g_._..___.___.. [ ._. J L_. ... J t._...J l._ > m m M i S m m ,...s.. LUBE Dil h0WilSil0NAIRl I,* DRAIN TANK 'I .ICOWUSTIONAIRl m 2 [ FILTER /SILENCERJ _'-' " -- -- - --[ F l L T E R / S I L EN r ~ -" -- ' -~ ~ ~{ Lf _ \\'- ' '- ~ -- ' 7 ' -- ""' ' T ' -- - '- ~ r ~ -'- ~ ~- ~ -{ _ \\f 7 EXPANSION EXPANSION j EXPANSION EXPAHSION TANK TANK TANK TANK I I LEGEND (-- 9 ulx i ASME D I .e .i ! TANK .i ' '- " j ASME VTTI -~-"-"-"-"-' s RADIATOR i RADIATOR i i !___..__.T'-'---, j MFG. STD.------ 8 .i ,.. 1..._. % 8...._.........i NON-ASME - - - - - -- RADIATOR I,JRAINTAN } ASME D3/N-253-6-----.
NON-ASME Ill COMPONENTS INSTALLED IN SAFETY-RELATED SYSTEMS 'l 1 f 5 FLEX 1BLE HOSES AUXILIARY DESK 4 AMOT VALVES i RADIATORS INTAKE FILTERS & SILENCERS t i t to
f PIPING INSTALLATION CODES / PIPING INSTALLED IN ACCORDANCE WITH APPROPRIATE CODE ASME Ill PIPING INSTALLED IN ACCORDANCE WITH ASME 111 REQUIREMENTS EXCEPT INSTALLATION (NA) STAMP + THIRD PARTY INSPECTORS I 1 4 %=
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- G ENVIRONMENTAL QUALIFICATION DIESEL GENERATOR BUILDING IS A MILD ENVIRONMENT RADIATION LEVELS ARE NEGLIGIBLE FOR TORNADO CONDITIONS, SAFETY-RELATED SSCS ARE QUALIFIED TO NEGATIVE PRESSURE DIFFERENTIAL OF 3 PSI
6- ! March 3, 1993 l The staff provided several comments during the presentation in areas where additional consideration should be given to assure that the BG&E submittal will include sufficient detail and will address all areas necessary for staff review. The staff indicated that the presentation was informative, facilitated i communications, and should assist in a timely review when.the EDG modifications are provided for staff review. Original signed by: l 4 i Daniel G. Mcdonald, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1. Attendance List 2. Emergency Diesel Generator Addition Project cc w/ enclosures: See next page Distribution: Docket file w/ handouts Alee, 7/E/23 NRC & Local PDRs w/ handouts MHartzman, 7/E/23 l PDI-l Reading w/ handouts TChan, 7/E/23 TMurley/FMiraglia,12/G/18 D0udinot, 8/C/14 1 JPartlow,12/G/18 IMoghissi-Miller, 8/D/1 SVarga RSkokowski, RGN-I JCalvo JRajan, 7/E/23 RACapra ACRS (10) DMcDonald w/ handouts VMcCree 17/G/21 CVogan CCowgill, RGN-I w/ handouts OGC EJordan, MNBB 3701 i f PDI-1:PM7thM3JPDI-1:D f PDI-1:LA CVogan Ok DMcDonalksmm RACapra f b 3/h/93 o3/03/93 03/o3/93 / / / / / / OFFICIAL RECORD COPY FILENAME: CC83222.MTS i i .-.}}