ML17251A870
| ML17251A870 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/17/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17251A869 | List: |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR NUDOCS 8611260151 | |
| Download: ML17251A870 (9) | |
Text
i UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING PROJECTED VALUES OF YIATERIAL PROPERTIES FOR FRACTURE TOUGHNESS REOUIRENENTS FOR PROTECTION AGAINST PRESSURIZED THERYiAL SHOCK EVENTS ROCHESTER GAS AND ELECTRIC CONPAI'Y R.
E.
GINNA NUCLEAR POMER PLANT DOCKET NO. 50-244 INTRODUCTION As required by 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock" (PTS Rule) which was published in the Federal Register July 23, 1985, the licensee for each operating pressurized water reactor "...shall submit projected values of RT S (at the inner vessel surface) of reactor vessel beltlioe materials by givilPvalues from the time of submittal to the expiration date of the operating license.
The assessment must specify the bases for the projection includino the assumptions regarding core. loading patterns.
This assessment must be submitted by January 23,
- 1986, and must be updated whenever changes in core loadings, surveillance measurements or other information indicate a significant change in projected values."
By letter dated January 13, 1986, the Rochester Gas and Electric Company licensee for the R.
E.
Ginna plant, submitted information on the material properties and the fast neutron fluence (E ~ 1.0 NeV) of the reactor pressure vessel in compliance with the requirements of 10 CFR 50.61 (Reference 1).
The staff reviewed the pressure vessel material properties and found the controlling beltline material from the standpoint of PTS susceptibility was identified to be the circumferential weld, intermediate to lower shell, weld MR-19 (weld wire heat number 61782).
1 The material properties of the controllirig material and the associated margin and chemistry factor were reported to be:
Cu (copper content, 5)
Ni (nickel content, 1o)
I (Initial RTNDT, 'F)
N (Nargin, 'F)
Utilit Submittal
- 0. 25
- 0. 55 59 Staff Evaluation 0.25
PD~R'55.6 I
The controlling material has been properly identified.
The justifications given for the copper and nickel contents and the initial RTN~ are acceptable.
The margin has been derived from consideration o
the bases
'fear these values, following the PTS Rule, Section 50.61 of 10 CFR Part 50.
The following evaluation deals with the estimation of the fluence to the pressure vessel to the end of the current license and for 32 effective full power years of operation and the corresponding values of the RTPTS.
The methodology of the fluence calculation was basec on the discrete ordinates code DOT with an ENDF/B-IV based cross section set.
The scattering is treated with a P: approximation and plant specific sources were used for cycles lA to 14.
Cycle 13 and 14 power distribution was used for the extrapolation to the end of the operating license (April 25, 2006).
The extrapolation was also carried to 32 effective full power years of operation, i.e.,
40 calendar years of operation at 80;. load factor.
The code has been benchmarked by Westinghouse.
Its predictions for the surveillance capsule locations are within ~15K of the measured values.
An S
Angular quadrature was used.
The intermediate to lower shell circumferential weld WR19 has beer identified as the controlling material, which we find acceptable
- and, therefore, the applicable value of the fluence is the peak of the azimuthal distribution.
The fluence estimate is conservative.
Future low leakage core loadings were assumed.
The methodology, the cross sections, and the approximations used are acceptable.
The equation specified in 10 CFR 50.61, as applicable for the R.
E. Ginna plant is:
RTP TS
= I+M+( 10+470 x Cu+350 x Cu x Ni ) x f0.27 where:
I
= Initial RTNDT M = Uncertainty Margin O'
59'F Cu
= w/o Copper in circumferential weld WR19
=
0.25 Ni
= w/o Nickel in circumferential weld WR19
=
0.55 f = Peak Azimuthal Fluence (E ~ 1.0 MeV) circumferential weld WR19 in units of 10 n/cm
= 3.38 19 For 32 effective full power years of operation:
RTP TS 59+ (
10<470 x 0 25+350 x 0 25 x 0 55 ) x 3 380.27
= 59+155.6 x 1.389
= 275 F which is lower than 300'F the applicable PTS rule screening criterion and is acceptable.
In view of:
a.
the Pressure-Temperature updating requirements for the fracture toughness of the beltline material in 10 CFR Part 50, Appendix 6, b.
the fact that the RT value is readily available from the calculation of the Pf4sure-Temperature limits, and c.
the staff desire to be informed on the current value of the RTPT>
for all
- PVRs, we reauest that the licensee submit a reevaluation of the RT>>~ and a
comparison to the prediction of Reference 1 along with the fbtbre Pressure-Temperature operating limits which are required by 10 CFR Part 50, Appendix G.* It should be noted that this reevaluation is a requirement by 10 CFR 50.61, whenever core loadings, surveillance measurements, or other information indicate a significant change in projected values.
ss request or snformation is covered under ONB clearance No. 315G-0011.
Contributors L. Lois N. Randall Date:
I I'
Reference Letter from R.
lJ. Kober, Rochester Gas and Electric Company to Director, NRR dated January 13, 1986.
Distribution Copies:
+Docket Files.,
NRC PDR Local PDR PADS'1 r/f PADII1 p/f TNovak, Actg.
DD NThompson, DHFT OGC-Bethesda EJordan BGrimes JPartlow GLear PShuttleworth DDiIanni ACRS-(10)
LFNB (TAC859956)
November 14, 1986 DOCKET NO(S).50-244 Hr. Roger M. Kober Vice President Electric and Steam Production Rochester Gas 8 Electric Corporation 89 East Avenue nglILaptt.r, Neo York 14649 R. E. GINNA NUCLEAR-POWER PLANT DISTRIBUTION:
gDocket File w/o Encl.g PADS'1 r/f w/o Encl.,
PShuttleworth w/Encl.
DDiIanni w/Encl.
The following documents concerning our review of the subject facility are transmitted for your information.
D Notice of Receipt of Application, dated D Draft/Final Environmental Statment, dated D Notice of Availabilityof Draft/Final Environmental Statement, dated D Safety Evaluation Report, or Supplement No.
, dated D Notice of Hearing on Application for Construction Permit, dated D Notice of Consideration of Issuance of Facility Operating License, dated D Monthly Notice; Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated D Application and Safety Analysi's Report, Volume D Amendment No.
to Application/SAR dated D Construction Permit No. CPPR-
, Amendment No dated D Facility Operating License No.
, Amendment No.
D Order Extending Construction Completion Date, dated g3 Other (Specify)
, dated
Enclosures:
As stated Division of Pl/R Licensing-A Office of Nuclear Reactor Regulation cc: See Next Page OFFICE~
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SURNAME+
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NRC FORM 318 (1/84) NRCM 0240
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Nr. Roger W. Kober Rochester Gas and Electric Corporation R.
E. Ginna Nuclear Power Plant CC:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and YiacRae 1333 New Hampshire
- Avenue, N.W.
Suite 1100 Washington, D.C.
20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E.
Ginna Plant c/o U.S.
NRC 1503 Lake Road
- Ontario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road
- Ontario, New York 14519 Jay Dunkleberger Division of Policy Analysis
& Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223