ML17264A153
| ML17264A153 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 09/11/1995 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17264A154 | List: |
| References | |
| TAC-M86500, NUDOCS 9509140197 | |
| Download: ML17264A153 (4) | |
Text
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~O Wp*y4 UNITED STATES NUCLEAR REGULATORY COMMilSSION WASHINGTON, D.C. 2055&0001 September 11, 1995 Dr. Robert C. Hecredy Vice President, Nuclear Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649
SUBJECT:
R.
E.
GINNA NUCLEAR POMER STATION REQUEST TO USE ALTERNATIVE MATERIALS (ALLOY 690 TYPE MELD HETALS) IN THE FABRICATION AND INSTALLATION OF REPLACEHENT STEAH GENERATORS (TAC NO. H86500)
Dear Dr. Hecredy:
By letter dated December 5,
- 1994, you requested approval for the incorporation of two American Society of Hechanical Engineers Boiler and Pressure Vessel Code (ASHE Code)
- Cases, 2142 and 2143, into the Section XI Program.
These cases will allow the use of Alloy 690 type weld material in the fabrication of the replacement steam generator (SG) for the R.
E. Ginna Nuclear Power Plant;-
This relief request is made in accordance with the provisions of 10 CFR 50.55a(a)(3).
- Also, ASHE Code Case N-474-1, as approved by Regulatory Guide 1.85, Rev.
29, July 1993, will be incorporated into the Section XI Program.
This case will allow the use of Alloy 690 for use as a construction material for the replacement SGs.
The NRC staff reviewed the subject request to use ASHE Code Cases 2142 and 2143 under the provisions of 10 CFR 50.55a(a)(3)(i) in the enclosed Safety Evaluation and concluded that the use of ASHE Code Gases 2142 aIId 2143 is authorized under 10 CFR 50.55a(a)(3)(i) for the fabrication and installation of replacement SGs at the Ginna Plant.
Due to the fact this would be a "first use" for these weld metals, the NRC staff recommends that the licensee either use one heat of each type of weld metal or maintain detailed records of individual heat usage locations for this project.
Sincerely, Docket No. 50-244
Enclosure:
Safety Evaluation cc w/encl:
See next page 4hLedyard B. Harsh, Director Project Directorate I-1 Division of Reactor., Projects I/II Office of Nuclear Reactor Regulation 9509140i97 9509ii PDR ADOCK 05000244 P
Ã2Q RtLll Kali'E~ CIEPV I
Dr. Robert C. Hecredy R.E.
Ginna Nuclear Power Plant CC:
Thomas A. Hoslak, Senior Resident Inspector R.E.
Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road
- Ontario, NY 14519 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Hs.
Donna Ross New York State
- Energy, Research, and Development Authority 2 Empire State Plaza Suite 1901
- Albany, NY 12223-1253 Charlie Donaldson, Esq.
Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Nicholas S. Reynolds Minston
& Strawn 1400 L St.
N.M.
Mashington, DC 20005-3502 Hs.
Thelma Mideman
- Director, Mayne County Emergency Hanagement Office Mayne County Emergency Operations Center 7336 Route 31
- Lyons, NY 14489 Hs. Hary Louise Heisenzahl Administrator, Honroe County
'ffice of Emergency Preparedness 111 Mest Fall Road, Room ll Rochester, NY 14620
, Septenber 11, 1995 ~
Dr. Robert C. Mecred~
Vice President, Nucl 'ear Production Rochester Gas and Electric Corporation 89 East Avenue Rochester,,
NY 14649 1
SUBJECT:
R:,. E.!'GINNA NUCLEAR'OWER STATION,RE(VEST TO USE ALTERNATIVE
',MATERIALS (ALLOY 690TYPE WEL'D METALS) IN THE FABRICATION AND INSTALLATION OF REPLACEMENT STEAM. GENERATORS (TAC NO. H86500) ll
Dear Dr. Hecredy:
By letter dated December 5,
1994, you requested approval for the incorporation of two American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASHE Code)
- Cases, 2142 and 2143 into the Section XI Program.
These cases will allow the use of Alloy 690 type weld material in the fabrication of the replacement steam generator (SG) for the R.
E. Ginna Nuclear Power Plant.
This relief request is made in accordance with the provisions of 10 CFR 50.55a(a)(3).
- Also, ASHE Code Case N-474-1, as approved by Regulatory Guide 1.85, Rev.
29, July 1993, will be incorporated into the Section XI Program.
This case will allow the use of Alloy 690 for use as a construction material for the replacement SGs.
The NRC staff reviewed the subject request to use ASME Code Cases 2142 and 2143 under the provisions of 10 CFR 50.55a(a)(3)(i) in the enclosed Safety Evaluation and concluded that the use of ASHE Code Cases 2142 and 2143 is authorized under 10 CFR 50.55a(a)(3)(i) for the fabrication and installation of replacement SGs at the Ginna Plant.
Due to the fact this would be a "first use" for these weld metals, the NRC staff recommends that the licensee either use one heat of each type of weld metal or maintain detailed records of individual heat usage locations for this project.
Sincerely, Original signed by:
Ledyard B. Harsh, Director Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
Safety Evaluation cc w/encl:
See next page Distribution:
~ Docket File To receive e copy of this document, indicate in the box:
C" ~
S.
PUBLIC J.
PDI-1 Reading L.
W. Russell/F. Hirag]ia S.
R.
Zimmerman K.
R. Spessard A.
J.
Lieberman G.
,1 DOCUMENT NAME:
G: iGINNAiGI86500.LTR, Varga Zwolinski Harsh Little Cotton Johnson Hornseth
- See previous concurr c
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95 08/16/95 FF CI'AL RECORD'COPY
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