ML20056H062
| ML20056H062 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/23/1993 |
| From: | Dromerick A Office of Nuclear Reactor Regulation |
| To: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| References | |
| GL-92-01, GL-92-1, TAC-M83490, NUDOCS 9309080161 | |
| Download: ML20056H062 (4) | |
Text
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i August 23, 1993
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'$ocketNo.50-219 Distribution:
l Docket File CSheng NRC & Local PDRs JFRogge, RI Mr. John J. Barton PD I-4 Plant ACRS (10)
Vice President and Director SVarga l
GPU Nuclear Corporation JCalvo L
Oyster Creek Nuclear Generating Station JStolz Post Office Box 388 SNorris i
Forked River, New Jersey 08731 ADromerick l
OGC I
Dear Mr. Barton:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - OYSTER CREEK NUCLEAR GENERATING STATION, ELASTIC-PLASTIC FRACTURE MECHANICS ASSESSMENT PER GENERIC LETTER 92-01 (TAC NO. M83490)
By letter dated September 22, 1992, GPU Nuclear Corporation submitted a plant specific report entitled "0yster Creek Vessel Fracture Mechanics Analysis for Upper Shelf Energy Requirement," for staff review and approval. This report is intended to demonstrate through _ fracture mechanics analysis that there exist margins of safety against fracture equivalent to those required by l
Appendix G of ASME Code Section III, for beltline materials having Upper-Shelf j
Energy (USE) values below the screening criterion of 50 ft-lb. The staff, with assistance from its contractor, Oak Ridge National Laboratory, is reviewing this report to determine if the information requested in Generic Letter 92-02 has been provided.
Additional information is required from GPU Nuclear Corporation in order for the staff to complete its review. The staff requests that you respond to the l
1 enclosed request for additional information within 30 days of receipt of this l
letter. The short response time is necessary for our contractor to fulfill-its contractual requirements.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under Pub. L. No.96-511.
i Sincerely, f
Original signed by:
Alexander W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page
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wasninctou, o c. roswoooi August 23, 1993 Docket No. 50-219 Mr. John J. Barton Vice President and Director GPU Nuclear Corporation Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Barton:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - OYSTER CREEK NUCLEAR GENERATING STATION, ELASTIC-PLASTIC FRACTURE MECHANICS ASSESSMENT PER GENERIC LETTER 92-01 (TAC NO. M83490)
By letter dated September 22, 1992, GPU Nuclear Corporation submitted a plant specific report entitled "0yster Creek Vessel Fracture Mechanics Analysis for Upper Shelf Energy Requirement," for staff review and approval.
This report is intended to demonstrate through fracture mechanics analysis that there exist margins of safety against fracture equivalent to those required by Appendix G of ASME Code Section III, for beltline materials having Upper-Shelf Energy (USE) values below the screening criterion of 50 ft-lb.
The staff, with assistance from its contractor, Oak Ridge National Laboratory, is reviewing this report to determine if the information requested in Generic t
Letter 92-02 has been provided.
Additional information is required from GPU Nuclear Corporation in order for the staff to complete its review.
The :taff requests that_you respond to the enclosed request for additional information within 30 days of receipt of this letter. The short response time is necessary for our contractor to fulfill its contractual requirements.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under Pub. L. No.96-511.
Sincerely, "O
G
,s Alexander W. Dromerick, Sr. Project Manager Project Directorate I-4 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page
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Mr. John J. Barton Oyster Creek Nuclear GPU Nuclear Corporation Generating Station cc:
Ernest L. Blake, Jr., Esquire Resident Inspector Shaw, Pittman, Potts & Trowbridge c/o U.S. Nuclear Regulatory Commission 2300 N Street, NW.
Post Office Box 445 Washington, DC 20037 Forked River, New Jersey 08731 Regional Administrator, Region I Kent Tesch, Chief U.S. Nuclear Regulatory Commission New Jersey Department of 475 Allendale Road Environmental Protection King of Prussia, Pennsylvania 19406 Bureau of Nuclear Engineering CN 415 Licensing Manager Trenton, New Jersey 08625 GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 j
Licensing Manager Dyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
Post Office Box 388 Forked River, New Jersey 08731
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Enclosure GPU NVCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-212 REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 92-01 I
Oyster Creek Vessel Fracture Mechanics Analysis for Upper Shelf Energy Requirement
(
Reference:
GE-NE-523-70-0692, "0yster Creek Vessel fracture Mechanics Analysis for Upper Shelf Energy Requirement")
i 1.
Provide the effect of cladding on the calculated applied J values for all Service Levels.
2.
Confirm that the method in Regulatory Guide 1.99, Revision 2 was used for calculating fluence at the quarter thickness location.
3.
Supply the operating and clad stress-free temperatures of the vessel for Levels A to D analyses.
i 4.
Sections 1.2 and 3.1 of the GPUN report suggest that A302 modified material car. be treated as A5338 material based on similar nickel content. Justify not considering the detrimental effects of high sulfur content on toughness.
5.
Provide temperatures used to generate J-R curves in Figs. 3-5, 3-6, 4-1 to 4-4, 5-5, and 5-10.
6.
The report indicates that the effects of the range of flaw depths have not been considered.
Provide justification for not analyzing all flaws with depths up to W/10 + clad thickness for Levels C and D loadinos.
7.
Provide the derivation or the reference (indicating the page number) of Equation (5-2).
8.
Supply a complete list of input parameters and conditions for Levels C and D transient thermal analyses. This includes specific heat, thermal conductivity, densiiv, the resulting value of thermal diffusivity, coefficier,
,, thermal expansion, elastic modulus and Poisson's ratio (fo 00th cladding and base metal);
also the relationships needed to determine the insido surface heat transfer coefficient.
Further, provide detailed procedures for calculating K values from the temperature and stress n
distributions obtained above.
9.
Confirm that Levels C and D transients were analyzed from the beginning of the transient to the time at which the metal at the tip of the flaw being ana1{F. zed reaches a temperature equivalent to the adjusted RT, plus 50
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