ML20069H535
| ML20069H535 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/01/1983 |
| From: | Meyer T POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK, WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| References | |
| ISSUANCES-SP, NUDOCS 8304060219 | |
| Download: ML20069H535 (11) | |
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U{UJ3 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 83 APR -5 A'0 :18 ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges:
James P.
Gleason, Chairman Frederick J.
Shon Dr. Oscar H.
Paris
)
In the Matter of
)
)
CONSOLIDATED EDISON COMPANY OF
)
Docket Nos.
NEW YO RK, INC.
)
50-247 SP (Indian Point, Unit No. 2)
)
50-286 SP
)
POWER AUTHORITY OF THE STATE OF
)
April 1, 1983 NEW YORK
)
(Indian Point, Unit No. 3)
)
)
POWER AUTHORITY'S TESTIMONY OF THEODORE A.
MEYER ON BOARD QUESTION 1.4 ATTORNEYS FILING THIS DOCUMENT:
Charles Morgan, Jr.
Paul F.
Colarulli Joseph J.
Levin, Jr.
MORGAN ASSOCIATES, CHARTERED i
l 1899 L Street, N.W.
t Washington, D.C.
20036 l
(202) 466-7000 l
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l l
l l
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8304060219 830401 PDR ADOCK 050002
My name is Theodore A. Meyer.
I am Manager of the Division of Reactor Vessel Integrity Group of the Nuclear Technology Division of Westinghouse Electric Corporation.
A 4
I statement of my professional qualifications is attached.
The purpose of this supplemental testimony is to address the current status of Indian Point Unit 3's fuel management program as it relates to Board Question 1.4.
In November, 1982, the Nuclear Regulatory Commission (NRC) issued a report entitled, "NRC Staff Evaluation of Pressurized Thermal Shock."
This report discussed the NRC screening criteria of 270*F reference temperature, nil-i ductility transition (RTNDT) for longitudinal flaw orientations and 300*F RT for circumferential flaw NDT orientations in the reactor pressure vessel.
The screening criteria and the issue of pressurized thermal shock assumes that there are flaws either detected or undetected in the reactor pressure vessel.
During the service life of the reactor vessel, the i'
RTNDT increases above the initial value of RT because of NDT neutron-irradiation by an amount delta RTNDT which depends t
is on fluetce and materials properties.
The initial RTNDT determitted from materials tests made at the time the vessel is fabricated.
The change, delta RTNDT, is determined from fluence measurements, calculations, and from trend curves, l
based on tests of irradiated specimens that measure the
-.-,.m
,m
- m.. _ __
_2_
effects of neutron irradiation.
Analysis of a surveillance capsule which was removed from the Indian Point Unit 3 pressure vessel during this refueling outage supports the calculated fluence levels used in calculating delta RTNDT.
There are, however, a number of uncertainties in the esti-mation of both initial RTNDT and delta RTNDT.
There fo re,
the NRC Staf f has established a prescribed, conservative method for calculating RTNDT which would be compared to the screening criteria.
The current total RT values calcu-NDT lated using these conservative methods for the longitudinal and circumferential flaw orientations for Unit 3 are both 218'F because a lower vessel shell plate is curently the most limiting location.
Both circumferential and longi-tudinal flaws are postulated in vessel plates.
One important aspect of this issue of which the Board should be aware is the actual risk posed by pressurized thermal shock.
The NRC Staf f has calculated and stated in their testimony on this Board question that when the screen-ing criteria are reached a reactor pressure vessel "would have a frequency of crack extension withcut arrest between 10-3 and 10-6 per reactor-year."
The NRC Staff has also testified "that not all through wall cracks will result in core melt since some crack sizes and crack shapes and crack locations will not preclude ability of the emergency systems to keep the core cooled."
Testimony of Dr. Hugh W.
Woods and Raymond W.
Klecker on Board Question 1.4 at 8.
The Licensees have testified that "[t]he Indian Point Probabilistic Safety Study (IPPSS) evaluated the frequency of a reactor vessel rupture large enough to exceed the cap-ability of the emergency core cooling systems.
That evalu-ation used the same methodology and assumptions as the Reactor Safety Study and yields a mean frequency of 3 x 10-7 per reactor year for all types of vessel failure, which included those failures induced by transients (pres-surized thermal shock (PTS) chain of events) and spurious events."
Licensees' Testimony of Dennis C.
Richardson and Dennis C.
Bley on Board Question 1.4 at 2.
Given this mean frequency, the frequency of core melt resulting from PTS is less than 3 x 10-7 per reactor year.
Calculations performed by the Westinghouse Owners Group on Reactor Vessel Integrity using generic fluence values have shown that the Indian Point Unit 3 reactor pressure vessel, before modification to its present reload fuel core, would not reach the NRC screening criteria for approximately 16.5 effective full power years for the most limiting case.
The Power Authority is currently taking measures to i
reduce the neutron irradiation of the reactor pressure ves-sel.
The current reload fuel core, cycle 4, is a modified low leakage core.
This is accomplished by placing spent fuel assemblies at select locations around the periphery of the core.
This modified core loading pattern will reduce the peak neutron flux on the limiting vessel shell plate by i
- t a factor of 1.4.
This modification alone will extend the time by which the pressure vessel will reach the NRC screen-ing criteria to approximately 2005.
The expiration of the plant license is 2009.
The Power Authority will be evaluating in the near future oth'er fuel loading patterns which would preclude the Indian Point Unit 3 pressure vessel from ever reaching the NRC screening criteria.
J l
l I
E,V ERIENCE FROFILE - MEYER, THECD0RE A.
EXPERIENCE:
11 years with Westinghouse and 3 years at Atomic Power Ceveicement Associates WESTINGHOUSE ELECTRIC CORPORATION, NUCLEAR TECHNOLOGY DIVISION, STRATEGIC OPERATIONS DIVISION AND PWRSD 1981 - Present: Manager of Reactor Vessel Integrity Programs Grouc - Responsible for identifying and implementing strucutural analysis required by utilities in tne evaluation and resolution of reactor vessel in-tegrity concerns relative to Pressuri:ed Thermal Shock (?TS) and o:ner structural integrity concerns.
These responsibilities in-clude the development of methods anc tne identification and utili-zation of acprocriate technology to evaluate reactor vessel in-tegrity including the identifica:icn and evaluation of benefits cerived from mcdifications aimed at imoroving reactor vessel in-tegrity. These activities include interfacing with the NRC, utilities and numerous other impacted W organizations.
Manage and direct structural integrity engineering analysis efforts performed by members of RVIP and coordination of these efforts with other disciplines and customer /NRC needs.
1975 - 1981:
Senior and Principal Engineer resconsible for identifying, deveico-l ing and implementing structural analyses programs and their associated thermal / hydraulic incuts relative to addressing reactor vessel in-tegrity concerns. These programs included evaluations of Large LOCA, Large Steam Line Break and Small LOCA to determine their impact on vessel integrity as well as test programs to deve1co appropriate boundary conditions (e.g. hea transfer coefficients).
Additional major responsibilities included the design, fabrication, testing and operation of capsules for the purpose of irradiating vessel material specimens in tes reactors.
e gineer resocnsible for thermal / hydraulic evaluation of reactor 1972 - 197:-
ninternals including evaluation of the reactor vessel for emergency and faulted conditions. Resconsibilities included the development of analysis methods, develocment of recuired comcuter programs,
as well as evaluation and testing of varicus reactor internals ccmcenents. The test program resconsibilities included the cevelop-ment of the test program and objectives, design and fabrication of recuired harcware and test facilities, perfor.ance of the recuired tests anc :ne obtaining of data and reduction of that data into useful engineering evaluations.
v4 m
ATOMIC PCWER DEVELOPMENT ASSOCIATES 1969 - 1972:
Co-operative education student engineer and Engineer at Atomic Power Development Associates which was responsible for the design of the Enrico Fermi Breeder Reactor.
Responsibilities covered a wide range of thermal / hydraulic and structural analyses, hardware test programs, methods and computer program development activities as well as on-site operational testing associated with the recovery from a major plant accident testing and operation of the plant.
MILITARY:
1967 - 1969:
ROTC U.S. Air Force EDUCATION:
1967 - 1972:
B.M.E., University of Detroit in Mechanical Engineering 1971 - 1972:
Advanced Degree work in Mechanical Engineering at University of Detroit i
1975 - 1979:
Masters Degree in Engineering Management (MSIE) at University of Pittsburgh 4
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD Before Administrative Judges:
James P.
Gleason, Chairman Frederick J.
Shon Dr. Oscar H.
Paris
)
In the Matter of
)
)
CONSOLIDATED EDISON COMPANY OF
)
Docket Nos.
NEW YORK, INC.
)
50-247 SP (Indian Point, Unit No. 2)
)
50-286 SP
)
POWER AUTHORITY OF THE STATE OF
)
April 1, 1983 NEW YORK
)
(Indian Point, Unit No. 3)
)
)
CERTIFICATE OF SERVICE I hereby certify that on the 1st day of April, 1983, I caused a copy of Power Authority's Testimony of Theodore A.
Meyer on Board Question 1.4, to be served by United States Express Mail Service to Jeffrey Blum, Esquire, and by first i
class mail, postage prepaid on all others:
n
James P.
Gleason, Chairman Charles M. Pratt, Esq.
Administrative Judge Stephen L.
Baum, Esq.
Atomic Safety and Licensing Board Power Authority of the 513 Gilmoure Drive State of New York Silver Spring, Ma ryland 20901 10 Columbus Circle New York, New York 10019 Mr. Frederick J.
Shon Administrative Judge Janice Moore, Esq.
Atomic Safety and Licensing Board Counsel for NRC Staff U.S.
Nuclear Regulatory Office of the Executive Commission Legal Director Washington, D.C.
20555 U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 Dr. Oscar H.
Paris Administrative Judge Brent L.
Brandenburg, Esq.
Atomic Safety and Licensing Board Assistant General Counsel U.S.
Nuclear Regulatory Consolidated Edison Company Commission of New York, Inc.
Washington, D.C. 20555 4 Irving Place New York, New York 10003 Docketing and Service Branch Office of the Secretary Ellyn R. Weiss, Esq.
U.S.
Nuclear Regulatory Commission William S. Jordan, III, Esq.
Washington, D.C.
20555 Harmon and Weiss 1725 I Street, N.W.,
Suite 506 Joan Holt, Project Director Washington, D.C.
20006 Indian Point Project New York Public Interest Research Charles A.
Scheiner, Co-Chairperson Group Westchester People's Action 9 Murray Street Coalition, Inc.
Box 488 White Plains, New York 10602 Jeffrey M.
Blum, Esq.
New York University Law School Alan Latman, Esq.
423 Vanderbilt Hall 44 Sunset Drive 40 Washington Square South Croton-On-Hudson, New York 10520 New York, New York 10012 Ezra I.
Bialik, Esq.
Charles J.
Maikish, Esq.
Steve Leipzig, Esq.
Litigation Division Environmental Protection Bureau The Port Authority of New York New York State Attorney l
and New Jersey General's Office One World Trade Center Two World Trade Center New York, New York 10048 New York, New York 10047 Andrew P.
O'Rourke Westchester County Executive
(
148 Martine Avenue White Plains, New York 10601 l
l Andrew S.
Roffe, Esq.
New York State Assembly Albany, New York 12248
Marc L.
Parris, Esq.
Atomic Safety and Licensing Eric Thorsen, Esq.
Board Panel County Attorney U.S.
Nuclear Regulatory Commission County of Rockland Washington, D.C.
20555 11 New Hempstead Road New City, New York 10956 Atomic Safety and Licensing Appeal Board Panel Phyllis Rodriguez, Spokesperson U.S. Nuclear Regulatory Commission Parents Concerned About Indian Washington, D.C.
20555 Point P.O.
Box 125 Honorable Richard L.
Brodsky Croton-on-Hudson, New York 10520 Member of the County Legislature Westchester County Renee Schwartz, Esq.
County Office Building Paul Chessin, Esq.
White Plains, New York 10601 Laurens R.
Schwartz, Esq.
Margaret Oppel, Esq.
Zipporah S.
Fleisher Botein, Hays, Sklar and Hertzberg West Branch Conservation 200 Park Avenue Association New York, New York 10166 443 Buena Vista Road New City, New York 10956 Honorable Ruth W. Me3 singer Member of the Council of the Mayor George V.
Begany City of New York Village of Buchanan District #4 236 Tate Avenue City Hall Buchanan, New York 10511 j
New York, New York 10007 Judith Kessler, Coordinator Greater New York Council Rockland Citizens for Safe Energy on Energy 300 New Hemstead Road c/o Dean R. Corren, Director New City, New York 10956 New York University 26 Stuyvesant Street David H.
Pikus, Esq.
New York, New York 10003 Richard F.
Czaja, Esq.
Shea & Gould Joan Miles 330 Madison Avenue Indian Point Coordinator New York, New York 10017 New York City Audubon Society j
71 West 23rd Street, Suite 1828 Amanda Potterfield, Esq.
New York, New York 10010 New York Public Interest Research Group, Inc.
Richard M. Hartzman, Esq.
9 Murray Street, 3rd Floor l
Lorna Salzman New York, New York 10007 Mid-Atlantic Representative Friends of the Earth, Inc.
David R.
Lewis, Esq.
208 West 13th Street Atomic Safety and New York, New York 10011 Licensing Board Panel l
U.S.
Nuclear Regulatory I
Stanley B.
Klimberg, Esq.
Commission General Counsel Washington, D.C.
20555 New York State Energy Office 2 Rockefeller State Plaza Albany, New York 12223 i
Mr. Donald Davidoff Director, Radiological Emergency Preparedness Group Empire State Plaza Tower Building, Rm. 1750 Albany, New York 12237 Craig Kaplan, Esq.
National Emergency Civil Liberties Committee 175 Fifth Avenue, Suite 712 New York, New York 10010 Michael D.
Diederich, Jr.,
Esq.
Fitgerald, Lynch & Diederich 24 Central Drive Stony Point, New York 10980 Steven C.
Sholly Union of Concerned Scientists 1346 Connecticut Avenue, N.W.
Suite 1101 Washington, D.C.
20036 Spence W.
Perry Office of General Counsel Federal Emergency Management Agency 500 C Street, S.W.
Washington, D.C.
20472 Stewart M. Glass Regional Counsel Room 1349 Federal Emergency Management Agency 26 Federal Plaza New York, New York 10278 Melvin Goldberg Staff Attorney New York Public Interest Research Group 9 Murray Street New York, New York 10007 Jonathan L.
Levine, Esq.
P.
O.
Box 280 New City, New York 10958 l
Paul F.
Colarulli l
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