ML19282C698
| ML19282C698 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/09/1979 |
| From: | Wambach T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-06, TASK-3-6, TASK-RR NUDOCS 7903300599 | |
| Download: ML19282C698 (13) | |
Text
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A UNITED S*ATES y
NUCLEAR REGULATORY COMMiss:ON h
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WASHINGTON, D. C. 20555 m
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8 March 9,1979 Docket No. 50-213 i
LICENSEE: Connecticut Yankee Atomic Power Company (CYAPCo)
FACILITY: Haddam Neck Nuclear Plant i
SUBJECT:
SITE VISIT OF SENIOR SEISMIC REVIEW TEAM TO HADDAM NECK NUCLEAR PLANT '
Members of the Nuclear Regulatory Commission (NRC) staff and members of the Senior Seismic Review Team (SSRT) visit'ed the.Haddam Neck Nuclear Plant on Februar 21, 1979, and the Northeast Utilities Service Company (NUSCO) yoffice in Berlin, Connecticut on February 22, 1979.
The attendance lists for both meetings are included as
> to this summary.
At the plant site on the first day, CYAPCo personnel described the plant arrangement and showed the location of the components, systems, and structures identified in the NRC letter to CYAPCo dated February 2, 1979. This was accomplished by viewing slides of piping diagrams and a small scale model of the plant at the Energy Information Center.
In the afternoon a plant tour was conducted so that the NRC and SSRT representatives could observe the structures and the supports for piping, mechanical and electrical components associated with those systems identified in the NRC letter as being required for safe shutdown in the event of a postulated seismic event.
The tour did not include the interior of the Containment Building because of the administrative and protective requirements necessitated by the airborne activity levels associated with the refueling and maintenance work that was in progress.
On February 22, 1979, representatives of NUSCO gave a presentation to partially respond to the NRC request for additional infomation contained in Enclosure 2 of the February 2,1979 letter regarding
-- the seismic design review of Haddam Neck--Nuclear Plant.-The informa-tion discussed is outlined in Attachment 2 to this summary.
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. The NRC staff and the SSRT then discussed with the licensee the additional documentation and information that would be necessary
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to verify the seismic resistance capability of the Haddam Neck Nuclear Plant.
The preliminary list of items developed and discussed during the raeting is given in Attacincnt 3.
The NRC staff identified during the meeting three possible options for generating this required information and analyses. They are:
1.
CYAPCo generates all the information identified by the NRC staff and SSRT; 2.
NRC staff and SSRT generate all additional analyses using input information provided by CYAPCo; and 3.
NRC staff and the SSRT perform limited analyses to generate information sufficient to identify signfficant issues and limit the scope of the analyses and evaluation to be performed by CYAPCo.
The licensee stated that they would like to review this summary of the meeting and the attached list prior to giving their viewpoint as to how to proceed.
k Thomas V. Wambach, Project Manager Operating Reactors Branch #2 Division of Operating Reactors Attachments:
As stated cc w/ attachments:
See next page
& cc Day,/attachentsBerry & Howard w
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Counselors at Law One Constitution Plaza Hartford, Connecticut 06103 u
l Superintendent Haddam Neck Plant RFD #1 Post Office Box 127E East Hampton, Connecticut 06424
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Mr. James R. Himmelwright Northeast Utilities Service Company P. O. Box 270 -
Hartford, Connecticut 06101 Russe.11 Library 119 Broad Street Middletown, Connecticut 06457 t
Mr. W. G. Counsil, Vice President t
Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06101 e
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ATTACHMENT 1 ATTENDANCE LIST HADDAM NECK SSRT SITE VISIT FEBRUARY 21, 1979
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NORTHEAST UTILITIES SERVICE COMPANY NRC J. F. Bibby T. V. Wambach" B. Ilberman H. A. Levin i
B. M. Fox T. M. Cheng L. H. Levy C.:.H. Hofmayer C. J. Gladding K. N. Jabbour L.;J. Nadeau T. A. Shaffer J. Shea Connecticut-Yankee Atomic Power Company M. S. Morris Lawrence Livermore Lab f
R. C. Murray F. J. Tokarz Westinghouse Corporation S. J. Jarecki C. W. Lin F. Loceff Stone & Webster M. B. Stetson D. B. Heard EDAC R. P. Kennedy D. A. Wesley
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JDS - McKee_
J. D. Stevenson NRC Consultant W. J. Hall KMC J. McEwen
.7 ATTACHMENT 1 ATTENDANCE LIST SSRT MEETING - NUSCO 0FFICE FEBRUARY 22, 1979 NORTHEAST UTILITIES SERVICE COMPANY NRC R. N. Smart C. Gladding T. V. Wambach J. F. Bibby H. A. Levin L. H. Levy K. N. Jabbour L J. Nadeau C. H. Hofmayer B. Fox T. M. Cheng E. deBarba L. D. Davison J. Shea Connecticut Yankee Atomic Power Company M. Morris Lawrence Livermore Lab F. J. Tokarz R. Murray Westinghouse Corporation S. Jarecki C. W. Lin E. L. Morris F. Loceff Stone &. Webster M. B. Stetson D. B. Heard EDAC R. P. Kennedy
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D. A. Wesley JDS - McKee J. D. Stevenson NRC Consultant _
W. J. Hall KMC J. McEwen
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ATTACHMENT 2 SAFE SHUT 00WN SYSTEMS SYSTEM / COMPONENT SEISMIC DESIGN Main Steam (up to Isolation Valves)
Piping in Containment
.17g ground acceleration Steam Safety Valves
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(SectionVIII Atmospheri:: Dump Valves 039 ground acceleration with l
Piping Outside Containment J (spectrum analysis Auxiliary Feed Water Auxiliary Feed Pumps - 450 gpm
.17g ground acceleration DWST - 100,000 gal.
PWST - 150,000 gal.
.17g ground acceleration
.03g. ground acceleration P. Water Transfer Pumps - 200 gpm
.03g ground acceleration Auxiliary Feed Pump Discharge Piping
.179 ground acceleration Service Water Service Water Pumps - 6000 gpm
.4g applied at center of g Service Water Piping
.179 ground acceleration -
CVCS - Charging and Boration Charging Pumps - 360 gpn
.179 horizontal direction
.12g vertical direction Boric Acid Tank - 20,000 gal.
.5g horizontal,.17g vertical Boric Acid Pumps - 80 gpm
.179 horizontal.12g vertical RWST - 260,000 gal.
.5g horizontal,.17g vertical CVCS Piping and Supports
.179 ground acceleration Residual Heat Removal
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RHR Pumps - 2,200 gpm
.179 horizontal,.12p vertical RH Exchanger
.279 horizontal,.179 vertical RHR Piping
.17g ground acceleration February, 1979
r-Shutdown Systems (Cont'd) 2-Emeroency Power Systems Emergency Diesel Generator
.179 ground acceleration 42,000 gal. Fuel Oil Tank
.5g horizontal,.179 vertical 5,000 gal. underground tanks
.03g ground acceleration Diesel oil transfer pumps - 20 gpm
.03g ground acceleration 9
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MECHANICAL SYSTEM / COMPONENT SEISMIC DESIGN METHODS General Description of Methods Used for Seismic Evaluation Discussion of Seismic Criteria Examples of Specific Calculations -
RHR Piping RWST Pressurizer Supports __
February, 1979
e STRUCTURAL SEISMIC DESIGN METHODS Design Criteria of Category I Structures Critical Damping Factors Horizontal Acceleration Basis (0.03 g or 0.17 g)
Seismic Coefficients Used Development of Design Criteria
~ConsTiferatfoi~oFGorden State Park Spectrum Use of Housner Spectrum Contaimnent Design Design Criteria Determination of Natural Period Application of Rayleigh Method by Hansen, Holly, arid Biggs Development of Participation Factor Seismic Coeffic'ient Used February,1979
DESIGN CRITERIA OF SELECTED STRUCTURES
% Critical Criteria Seismic Structure ~
Material (s)
Damping
- O.03g 0.17g Coeff.
Reactor Containment Concrete 7.0 X
0.37*
(Incl. Foundation Mat)
Bolted Steel 2.5 X
0.36 Concrete (Internal) 7.0 X
0.23 Concrete (Cable Vault, 5.0 X
0.26 Hatch Shielding)
Primary Auxiliary Bldg.
Concrete 5.0 X
0.26 Steel Bolted 2.5 X
0.36 New and Spent Fuel Sidg.
Concrete 5.0 X
0.26 (Incl. Refuel Ca'rity)
Steel Bolted 2.5 X
0.36 Steel Welded 1.0 X
0.50 Turbine Bldg.
Eteel Welded 1.0 X
0.089 Steel Bolted 2.5 X
0.064 Concrete Turbine Supp.
5.0 X
0.046 Concrete Floors 5.0 X
0.046 Steel Bolted (Floors) 2.5 X
0.064 Office Bldg.
Concrete 5.0 X
0.046
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Steel Bolted 2.5 X
0.064 Screenwell Concrete 5.0 X
0.26 Steel Bolted 2.5 X
0.36 Ion Exchange Bldg.
Concrete 5.0 X
0.26 Steel Bolted 2.5 X
0.36 Service Bldgs Control Bldg.
Concrete 5.0 X
0.26 Steel Bolted 2.5 X
O.36 Service Bldg., Auxiliary Concrete 5.0 X
0.046 Bay, Warehouse, Service Steel Bolted 2.5.
X 0.064 Boiler Room Diesel Generator Bldg.
Concrete 5.0 X
0.26 Steel Bolton 2.5 X
0.36 Station Forvice Trans-Concrete 5.0 X
O.26 formers and Switchgear Steel Bolted 2.5 X
0.36 Yard Crane-supporting Steel Bolted 2.5 X
0.36 Structure f
Switchyard Concrete 5.0 X
0.26 y
i Steel Bolted 2.5 X
0.36 96 G
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- Acceleration at crown based on a conputed period of vibration.
ATTACHMENT 3 PRELIMINARY ASSESSMENT OF PERTINENT 1NFORMATION REQUIRED TO DOCUMENT THE SEISMIC RESISTANCE CAPABILITY OF THE HADDAM NECK FACILITY The NRC staff and its consultants, the Senior Seismic Review Team (SSRT), have completed a review of the Haddam Neck docket for information pertinent to the seismic design bases of the facility and its capability to withstand the effects of potential earthquakes.
The infomation currently on the docket is not sufficiently complete to adequately quantify such capability. The following items require further considera-tion.
It is anticipated that some of the information required for documentation maybe available but not on the docket; however, other items will require the generation of substantial new infomation.
The development of this additional documentation should focus on the integrity of the reactor coolant pressure boundary and the capability of essential systems and components required to safely shutdown the reactor and mainta1n it in a safe shutdown condition during and after a postulated seismic disturbance.
The following is a preliminary list of the specific information required to document the seismic resistance capability of the Haddam Neck facility:
I. -Seismic Analysis and Design Criteria for Structures and Input to Equipnent A.. Building Models - Mathematical models to determine response (forces, moments, shears, deflections) to ground motion for the following structures:
Primary Auxiliary Building Service Building / Control Room Screen House Containment Building, including internal structures '
Fuel Storage Building Information concerning these models should include:
1.
Lumped mass properties' development 2.
Stiffness properties' development 3.
Consideration of coupling between buildings / torsional effects 4.
Consideration of load path 5.
Interaction with Non-Category I structures NOTE:
Drawings showing structural framing details, foundation deta11s, and reinforcement details including material properties data and equiprent mass data are required.
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B.
Development of Floor Response Spectra - Input for tire analysis of mechanical and electrical equipment and fluid and electrical distribution systems C.
Miscellaneous Design and Analysis Topics 1.
Treatment of the effects of tangential shears (Containment wall) 2.
Design of liner plate and its anchorage system / liner plate - Helson stud testing program 3.
Design of Primary Water Storage Tank, Demineralized Water Storage Tank, Refueling Water Storage Tank 4.
Spent Fuel Pool integrity / leakage 5.
Penetration design / capability of buried piping to withstand relative motion - Information on the foundation of buried piping and penetration details is required.
6.
Design of structural masonry walls / reinforcement details - Information is required to assess the load carrying capability of such walls and to assess the integrity of attached conduit and cable tray supports.
II. Seismic Qualification of Mechanical and Electric 1 Equipment and Fluid and Electric Distribution Systems Seismic qualification documentation based upon analysis or testing of actual equipment or similar equipraent to that installed at the Haddam Neck facility for the following equipment related to safe shutdown is required.
A.
Mechanical Components 1.
Centrol rod drive mechanism (CRDM) - (housing integrity and CRDM functionability) 2.
Steam generator (including support integrity / reactor pressure boundary integrity)
Reactor coolant pump (including support integrity
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3.
reactor pressure boundary integrity )
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4.
Pressurizer (including support integrity / reactor pressure boundary integrity) 5.
Boric acid tank 6.
Residual heat removal (RRR). heat exchanger 7.
One safety injection (SP) pump-motor component (i.e.,HPSI,LPSI, charging)
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Service water pump 9.
Typical motor operated valves a.
one greater than 8" diameter b.
one less than 4" diameter 10.
Steam drive auxiliary feedwater pump and turbine IL Electrical Components 1.
Control room panels (operability of individual components, stresses in panels and support welds / bolting) 2.
AC-DC motor control centers (operability and support integrity) 3.
4160-480V transfomers (operability and support integrity) 4.. AC-DC inventers (operability and support integrity)
C.
Fluid Distribution Systems 1.
Reactor coolant loop including pressurizer surge line E.-
Auxiliary feedwater piping (~100 feet) 3.
Service water piping (~100 feet including buried section and connection to building structure) 4.
RHR piping (~100 feet)
D.
Electrical Distribution Systems 1.
Cable trays including lateral supports 2.
Conduit attached to block walls E.
Special Components 1.
Battery racks 2.
Air tanks used to start diesels
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