ML19275A593

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Summary of 790828 & 29 Meeting W/Util in Berlin,Ct Re Info Requirements to Determine Seismic Resistance Capability of Facility
ML19275A593
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/25/1979
From: James Shea
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TASK-03-06, TASK-3-6, TASK-RR NUDOCS 7910050568
Download: ML19275A593 (56)
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September 25, 1979 Docket No. 50-245 LICENSEE: Northeast Nuclear Eriergy Company (NNECO)

FACILITY: Millstone Nuclear Power Station, Unit 1

SUBJECT:

SUMMARY

OF MEETING HELD ON AUGUST 28-29, 1979 NRC and NNEC0 representatives met at the Millstone site on August 28, and at the NNECO main office in Berlin, Connecticut, on August 29, 1979, to (1) v'iew selected accessible structures such as the main turbine building, condenser circulating water intake structure, the ventilation stack and equipment such as control room instrument panels, the emergency condenser, emergency diesel and gas turbine generators, and (2) to discuss information requirements to determine the seismic resistance capability of the Millstone 1 Facility. The meeting attendees for both days are listed in Attachments 1 and 2.

During the meeting at the Millstone site, NNEC0 reviewed the general plant layout for orientation purposes and provided information (Attachment 3) related to the Safe Shutdown Systems which was the basis for the discussions that followed. After the conducted tour of the accessible plant areas there was a brief continuation of discussion to clarify and answer questions resulting from visual examination of plant components and structures.

The NNEC0 presentation at the main office in Berlin, utilizing the visual aides in Attachments 4, 5, and 6, was a sunniary of the seismic design analysis for Millstone 1.

NRC representatives recited a number of items requiring further evaluation and agreed after a request by NNECO to provide a detailed list of specific additional information requirements,to be addressed by NNECO,as an attachment to the meeting sunmary. Accordingly, the additional information required from NNECO to document the seismic resistance capability of the Millstone 1 Facility is provided as Attachment 7.

910050 1100 284

Northeast Nuclear Energy Company September 25, 1979 NNECO cormiitted to review its resources and inform NRC of the schedule, consistent with the milestones for the SEP Seismic Review of Millstone Unit 1 as presented in Attachment 7, for providing the required infonnation.

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J L' c-J,imes J. She', Project Manager a

'N 0 berating Reactors Branch #2 Division of Operating Reactors Attachments:

As stated cc w/ attachments:

See next page 1100 285

Northeast Nuclear Energy Company September 25, 1979 cc William H. Cuddy, Esquire Day, Berry & Howard Counselors at Law One Constitution Plaza Hartford, Connecticut 06103 Anthony Z. Roisman Natural Resources Defense Council 917 15th Street, N. W.

sashington, D. C.

20005 Northeast Nuclear Energy Company ATTN: Superintendent Millstone Plant P. O. Box 128 Waterford, Connecticut 06385 Mr. James R. Himmelwright Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Nuclear Regulatory Commission, Region I Office of Inspection and Enforcement ATTN: John T. Shediosky 631 Park Avenue King of Prussia, Pennsylvania 19406 Waterford Public Library Rope Ferry Road, Route 156 Waterford, Connecticut 06385 M. W. G. Counsil, Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06101 1100 286

LIST OF ATTENDEES AUGUST 28-29, 1979 NRC EDAC C. Hofmayer D. Wesley W. Hall, Consultant H. Lee P. Chen EG8G J. Shea H. Levin C. Liaw J. Stevenson, Consultant GE NNEC0 A. Armitage K. Thomas W. Romberg KMC, Inc.

NUSCO R. Schaffstall T. Dente W. Walsh LLL L. Davison J. Bibby T. Nelson C. Gladding G. Cornelius R. Artwell Blume & Assoc.

J. Shea

8. Ilberman L. Malik R. Kacich 1100 287

ATTENDANCE LIST NORTHEAST UTILITIES NUSCO NNECO B. Ilberman P. J. Przekop T. J. Dente W. J. Walsh L. D. Davison R. L. McGuinness R. N. Smart J. J. Shes R. N. Artwell C. J. Gladding J. F. Bibby R. M. Kacich NORTHEAST UTILITIES' CONSULTANTS Ebasco General Electric URS Bluzne M. Esich A. L. Armitage R. P. Gallagher D.

P.. Jhaveri L. Malik NRC NRC Employees H. W. Lee C. H. Hofmayer H. A. Levin Pei-Ying Chen J. J. Shea NRC CONSULTANTS LLL EDAC T. A. Nelson W. J. Hall D. A. Wesley Woodward-Clyde EG&G J. D. Stevenson C. Y. Liaw KMC YAEC R. E. Schaffstall J. W. Stacey 1100 288 i

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MINIMUM SYSTEMS FOR SAFE SHUTDOWN The following are the minimum systems required for a safe shutdown from full reactor power with loss of off site power but no plant accidents:

1.

Control rods / drives / hydraulic control units / reactor protection system.

2.

Isolation condenser system.

3.

Condensate storage and transfer system.

4.

Shutdown cooling system.

5.

Reactor building closed cooling water system.

6.

Service water system.

7.

Emergency power sources (diesel generator, gas turbine generator battery).

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8.

IC&E for above systems and for monitoring reactor condition.

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A-3 CONTROL ROOM AND TURBINE BUILDING 1. Control Room (Front Panels and Behind) 2. Cable Vault 3, Switchgear Safety Related 4,160 Volt Buses Safety Related 480 Volt Buses 4. Battery Rooms Station 120 VDC Batteries Battery Chargers 5. Diesel Generator Engine and Accessories bl00 298

A-3 OUTSIDE 1. Gas Turbine Building--Engine and Accessories 2. Tank Farm--Fuel Oil Supplies To Diesel Generator And Gas Turbine 3 Transformer Yard 4. Condensate Storage Tank 5. Stack 6. Screenhouse 7. Intake S tructure--Service Water Pumps And Piping 4 1100 299

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~ ,._. p. my..s. ~ m a...-- ~ r ~ 300RORSMR JOHN A. 8LUME & ASSOCIATES, ENGINEERS sin nowano stasar saw esawcasco s. cauroemia 20s340m. 'MILLSTOME PolhJT R P.v. n:c...n 8 2-(6 eu ,C.E. .nc, E 'tSMic ANALve;s ..n B 2 66 c- =

3. MATHEMATICA ActODEL.

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10HN A. BLUME AND ASSOCIATES, ENGINEERS i 111 199A12'Siffff SAR FIARCISCl l MILLSTONE 1 l SOL A TION CONDENSER SE/SMIC ANAL YSIS _GEOME TRIC FIGURE 54'- 4" ~ 49 '-I V4" /4'- 2" = ./_A '- 2.".-.. J2. ' 4 Ve' __ =_ smusw 24 '-0. " ' '.'. 4.,*,'a.*. g, f . - gug m h .i n .s ?,4 N S m t j <'j) T I T hi av_ g - = = :====t:

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_ #wMg _Ma,emagg jp,,.,.pg.,. JCN.Y A. ELUME AND ASSC:/ATES, ENf/ NEE 15 MILLSTONE NUCLEAR f'Q:vER STATIO 125 ACTOR REC /RCULATION LOOP P/to!NG P/ f /O2 QQQQ Q Q Q F/XEC A?,ep t'(7y,9y z y f iE i i. [ A =h )- s t v /2 ".21.sE ( r v. c.) ~R Fy ,7 p 26 ,00.%o N fk'A.i.5 E \\. 27'y5.4O5,z pl 1 a I 1 28 *: o:. :q,o Oil:,;.1.C "- E i ) / N, F/XEO AT \\ AuMA 1.1 O u,, 3 1 4 .s y "S' PUMP JuCTIONf,\\, P2 F/XEO AT PUMP l MC/N OF COORDINATE 5 occ. /w,4 -=- .v nnw, m am 2sc i

MNN A ItUNE ANS AS$1CMEL ENGINEEM ^-4 M/LLSVONE NUCLEAR PooVEA? STAT /ON REACTOR A?EC/2Cl/t AT/QN LOOP PIP /NG PI, LOC 47/ON OF MASSES-. ~ , 5 %.Q.7b] " ~ ~ ~ y 0 Ill '92 y q gy y,z 'in-p pggg 9g y 3o .1,g' V 'N 'N [ &,gy 6 ) 3 M' ts auen nw-ir+ 3C 80, ./+7 .m ,4 H 74 4 g .!49 41 hy *0 ( NE< >M X-RESTRAINT L 't \\ (RADIAL DUt 10

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,_. y. 5 n,. .a:xu.sgexwsa u,=.. JOHN J. ELUME AND ASSCC/MES, ENGINEERS p.4 ML STONE NUCLEA12 POWE2 SI'A T/ON REACTO2 (2EC/2CULATION LOOP P!P!NG P2., t OCAT/oN OF MASSES I, [

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A-4 2. Structures or epipment supported in er en other structures or ~ equijaant shall be designed sinf1mely as in (1) alkNe with the tuo coor- ~ di'. ions of seisuie loading, but shall be ecosidered as appendages of the supporting structures or equipeent, and the complete structumi system [ shall be considered. + A' vertical ace.l.tatice of 0.05g shall be applied to the structure. Essulting stresses of the horizontal and wrtical accelerations st-11 De ecosidered as occurring simultaaecosly. TIGLE II nm~ne axmo=ns so . Item Percent critical Da= ping Beinfarced concrete structures 50 Steel truce structures 2.0 Welded assenhlies 1.0 a Bolted and riveted assenhlies 2.0 T1tal piping systees d.5 Tree II criteria It is recocnended that applicable codes shall be followed in the design of non-critical items. All equi p.nt should be so bolted or cistenedthatitvouldnotbedispiacediffrictiondidnotexist. If ~ seismic design is not cwma in applicable codes, Section 23 of the Uniform Building Code is reecuumerded. ~ liOO 317 1 k e e M

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m v 5 m .5 PIPING STRESS ANALYSIS M c y c= <c -r RECIRC LOOP PIPING: ALL OTHER SEISMIC CATEGORY I PIPING: J. A. BLUME EBASCO SERVICES, INC. RESPONSE SPECTRA METHOD COMPUTERIZED STATIC ANALYSIS PREVIOUS VERSION OF PIPESTRESS 2010 TURBINE BUILDING: REACTOR BUILDING: GENERAL ELECTRIC STATIC COEFFICIENT BASED ON STATIC COEFFICIENT BASED LOAD COMBINATIONS & DESIGN REPORT PEAK OF J. A. BLUME RESPONSE ON AMPLIFIED PEAK AVERAGE. SPECTRA 0F UNSM00THED HORIZONTAL GROUND RESPONSE SPECTRA PIPING: B31.1, 1967 EDITION SUPPORTS: 1963 AISC & MSS-SP-58 VERIFICATION -- 18E BULLETIN 79-1Li "AS-BUILT GE0 METRY OF SEISMIC CATEGORY I PIPING"

REACTOR BUILDING PIPING STRESS ANALYSIS T< A PEAK = AVERAGE OF PEAKS OF UNSM00THED RESPONSE SPECTRA FOR T< 0.25 SEC. A PEAK = 0.63 + 0.56 + 0.54 ' O 50 + 0.43 7 5 o A PEAK = 0.50 CP = A PEAK A GROUND A BUILDING = MAXIMUM ABSOLUTE ACCELERATION DETERMINED BY J. A. BLUME, IIME-HISTORY ANALYSIS OF REACTOR BUILDING cs 9; b ELEVATION A PEAK A GROUND A BUILDING CP ABOVE 90'0" 0.50 0.07 0.13 0.90 <s- \\ s 55'0" TO 90'0" 0.50 0.07 0.10 O.68 BELOW 55'0" 0.50 0.07 0.07 0.50 m O

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P 9 ~ ADDITIONAL INFORMATION REQUIRED TO DOCUMENT THE SEI5MIC RESISTANCE CAPABILITY OF THE MILLSTONE 1 FACILITY The NRC staff and its consultants have completed a review of the Millstone 1 docket for information pertinent to the seismic design bases of the facility and its capability to withstand the effect of potential earthquakes. The information currently on the docket is not sufficiently complete to adequately , quantify such capability. It is anticipated that pertinent information is available from other sources such as the original NSSS, A-E, or plant files. The following information is necessary to proceed with the seismic review; h) wever, at this time it is not required that new information be generated to satisfy this request. (Except Item B.18). A. Seismic Analysis and Design Criteria for Structures and Input to Equipment 1. Building Models - Original mathematical models used to determine seismic response (forces, moments, shears) for the following structures, a. Turbine Building b. Control Building / Rad Waste Building c. Intake Structure Information concerning these models should include: Lumaed mass properties Stiffness properties Details of any consideration of coupling / torsional effects 2. Structural response profiles (forces, moments, shears) actually used in design for the following structures. a. Turbine Building b. Control Building / Rad Waste Building c. Screen House d. Gas Turbine Building 3. Foundation details (drawings) for the following structures, a. Turbine Building b. Control Room / Rad Waste Building c. Reactor Building d. Stack 4 Description of structural interconnection and gaps between Unit 1 buildings and between Units 1 and 2. Simplified sketches showing overall interactions would be berieficial. These sketches should i100 332

s A-7. be supplemented with sufficient structural framing details to permit dynamic modeling of the buildings as a system including the effects of all pertinent interconnections and interactions. 5. Original stress computations showing the design of i.ne reactor building wall for the design forces, moments and shears at elevation 14'-0. 6. Stuctural design calculations for drywell. 7. Detailed description of how forces, moments, shears were distributed in turbine building for the design of areas which house Category I Equipment, including the rationale for the following structural modifications: a. vertical braced frames b. reinforced block walls in the battery rooms. 8. Condesate storage tank analysis plus arrangement drawings showing anchorage details. B. Seismic Qualification of Mechanical and Electrical Equipment and Fluid and Electric Distribution Systems Seismic qualification documentation based upon analysis or testing of actual equipment or similar equipment to that installed at the Millstone 1 facility for the following equipment is required. In addition, provide-any other reports that document the results of seismic tests or detailed analyses taat may have been parformed on either mechanical or electrical equipment. 1. Please provide a list of mechanical and electrical equipment required for safe shutdown, ECCS and Engineered Safeguards as previously requested in a letter from D. Ziemann to W. Counsil dated may 30, 1979. An example of the necessary format is included. (Enclosure 3). Mechanical Comoonents 2. Reactor pressure vessel support system - analytical techniques (including dynamic model and methodology) used to evaluate the overall RPV support system and the original design computations (including responses and/or stresses due to pipe break). 3. Reactor pressure vessel internals support design report. 4 Control rod drive hydraulic control units, a. Computations addressing the lateral support of tubing. b. Anchorage criteria for the CRD modules including supporting computations. I100 333

s A-7 - 5. Heat Exchangers - arrangement drawings including support and qualification data for the following HXs: a. Isolation condenser b. Reactor building closed cooling water HX c. Shutdown HX 6. Recirculation Pump Support - details of seismic analysis and arrangement drawings (including response due to pipe break). 7. Oil Storage Day Tank - arrangement drawings including support and anchorage details and/or calculations. 8. Service Water Pumps - arrangement drawings including support and anchorage details and qualification data. 9. Small motor operated valves - identification of safety related MOVs on 1" to 4" diameter lines - effect of accentric mass on pipe stress. Fluid Distribution Systems

10. Piping isometric drawings including support locations, support stiffnesses (or necessary drawings of supports to enable a determination of support stiffnesses), valve locations, valve masses and center of gravity and other pertinent details as noted in Enclosure 2 needed to independently verify and audit the seismic capability of the following piping systems, a.

Underground lines to oil storage day tank and from day tank to diesel generator, compressed air inlet line to diesel. b. Feedwater line inside containment. c. Condesate transfer line (portions run above isolation condenser) from reactor building penetration to the isolation condenser. d. Shutdown cooling line (portion summarized in Table 12.1.2.8-3 of the FSAR).

11. Piping analyses of the following lines, a.

Recirculation loop. b. Main steam line inside containment. Electrical Comoonents

12. 4160 - 480 Volt Transformers.
13. Battery racks.

~1100 334

A-7 , 14. Criteria for anchorage of electri:al equipment - anchorage of cabinets and equipment mounted inside (e.g. motor control centers,switchgear,controlpanels,instrumentpanels,etc.). 15. Sketches showing arrangement and anchorage details including mass distribution of typical electrical components as listed above and/or supporting calculations to demonstrate adequate seismic resistance capability. The sample may include: a. Remote control board for diesel generator. b. Motor control center (single unit) on pedestal in diesel generator room. c. Battery chargers (if safety related), d. Motor control centers or switch gear with large height to depth ratios (single and multiple connected units). I

16. Confirmation that design modifications recommended in memo l

from G.E. to NUSCO dated December 18, 1970 were made. Description of Millstone 1 plant specific modifications. Copy of Field Disnosition Instructions referenced in subject memo. Electrical Distribution System

17. Cable trays including lateral supports - original supporting criteria and/or later qualification testing data.

Interaction Problems

18. Develop procedures and/or required modifications to positively anchor dollys, gas bottles, block and tackle or other misc.

items which could potentially impact safety related equipment. The seismic review team recommends that items in the vicinity of the CRD hydraulic modules be addressed. I g

19. Provide the criteria adopted in the design of non-Category I items to assure that they would not fall or become dislodged and damage Category I equipment. Demonstrate how these criteria

{. were applied to assure that: l (a) air handling ducts above service water pumps would not tevere pump electrical power cables if they should fall during an earthquake; (b) water coolers above RBCCW heat exchanger valves would not damage these valves if they should fall during an earthquake. C. Reports Identified During Site Visit and Engineering Discussions The following reports by the J. Blume organization are requested: 1100 335

L A-7 1. Pressure suppression chamber analysis. 2. Suppression chamber suction header an51ysis. 3. Isolation condenser analysis. 4. Reactor pressure vessel analysis. 5. Earthquake design criteria. 6. Radwaste buildir.g analysis. 7. Gas turbint building analysis. 8. Recirculation loop analysis. 9. Ventilation stack analysis.

A-7 MILESTONES FOR THE SEP SEISMIC REVIEW OF MILL 5 TONE Unit NO. I 1. Site visit - August 28, 1979. 2. Request for information - August 29, 1979. 3. Informatic. recieved by NRC from licensee - Octob:1 15, 1979. 4. NRC Review Plan complete (methodology, models developed) - November 26, 1979. 5. Meeting with licensee to discuss review progress, obtain additional information - December 18, 1979. 6. NRC confirmatory analyses complete - January 7, 1980. 7. Structural / mechanical evaluations to;plete - January 31, 1980. 8. Draft Final Report from NRC consultants - February 24, 1980. 9. NRC request of licensee to complete evaluations of outstanding items - March 1, 1980.

10. Licensee evaluation complete - May 1, 1980.
11. NRC review of outstanding items complete - August 1, 1980.

1100 337

s ~A-7 CLOSURE 2 EN PIPING SYSTEM ENGINEERING DATA The folicwing engineering data are required for ASME Class 2, 3, and ANSI B31.1 piping analyses. 1. List of design and operating temperatures anc pressures 2. List of load cases and their associated operating conditions [ normal and upset (Level A and B), emergency (Level C), or faulted (Level D)] 3. Detailed piping drawings and/or isometrics indicating the geometry of the piping system alcng with all necessa y dimensions and weld locations 4 List of nominal pipe sizes, schedules, weights, and materials 5. List of pipe support types, locations, stiffnesses, and preloads 6. List of valve locations, weights, and eccentricities (center of gravity locations) 7. List of any anchor movements (thermal, seismic, etc.) anc locations 5. Response spectra, static acceleration levels, or time iiistory in-formation for dynamic analyses 9. Descriotion of any special fittings or comocnents present on the piping system 10. If acclicable, any imposed forces and moments due to relief valve ciscnarge, connected lines and components, etc. 11. The design specification. It is recognized that the design spec-ification would include some of the above data. Unless otherwise directed the following assumptions will be made: 1. All comoonents are butt welded (fl.ush) and forged '(no longitudinal components). Weld specifications would be needed if verificaticn of tnis assumction is recuired. 2. Ali comocnents meet ANS. 516.9 anc ANSI 516.2S standarcs. 3. The -ecuirements of ASME Coce, Section III, Subsubarticle NC-3640 are satisfied. his lis is nct necessarily all inclusive; thus, variaticns may result due to 5:ecial recuirements mace by certain projects or crograms. 1100 338 E 1 1

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MEETING

SUMMARY

DISTRIBUTION: e Docket 50-245 NRC PDR Local PDR ORB #2 Reading NRR Reading H. R. Denton E. G. Case D. Eisenhut R. Vollmer B. Grimes W. Gammill J. Miller L. Shao T. Carter D. Crutchfield D. Ziemann V. Noonan Seismic Review Group A. Schwencer T. Ippolito R. Reid G. Lainas P. Check F. Pagano G..Knighton J. Shea OELD OI&E(3) H. Smith R. Fraley, ACRS(16) C. Hofmayer W. Hall, Consultant H. Lee P. Chen H. Levin J. Stevenson, Consultant J. R. Buchanan (W 1100 340}}

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