ML17059A247
| ML17059A247 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/30/1994 |
| From: | Brinkman D Office of Nuclear Reactor Regulation |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| References | |
| GL-92-01, GL-92-1, TAC-M83486, NUDOCS 9404050195 | |
| Download: ML17059A247 (18) | |
Text
~p,R REGS( 'lp0 p 1~
0 n +y*y4 Docket No. 50-220 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 30, 1994 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Sylvia:
SUBJECT:
GENERIC LETTER (GL) 92-01, REVISION 1, "REACTOR VESSEL STRUCTURAL INTEGRITY," NINE MILE POINT NUCLEAR STATION UNIT NO.
1 (NMP-1)
By letters dated July 2,
- 1992, and October 16,
The NRC staff has completed its review of NMPC's responses.
Based on its review, the NRC staff has determined that NMPC has provided the information requested in-'L 92-01.
The GL is part of the NRC staff's program to evaluate reactor vessel integrity for Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs).
The information provided in response to GL 92-01, including previously docketed information, is being used to confirm that licensees satisfy the requirements and commitments necessary to ensure reactor vessel integrity for their facilities.
A substantial amount of information was provided in response to GL 92-01, Revision 1.
These data have been entered into a computerized data base designated Reactor Vessel Integrity Database (RVID).
The RVID contains the following tables:
A pressure-temperature limit table for BWRs and an upper-shelf energy (USE) table for PWRs and BWR's.
Enclosure 1 provides the pressure-temperature
- table, Enclosure 2 provides the USE table for NMP-1, and Enclosure 3 provides a key for the nomenclature used in the tables.
The tables include the data necessary to perform USE and pressure-temperature limit evaluations.
These data were taken from your responses to GL 92-01 and previously docketed information.
The information in the RVID for NMP-1 will be considered accurate at this point in time and will be used in the NRC staff's assessments related to vessel structural integrity.
References to the specific source of the data are provided in the tables.
We request that you verify the information you have provided for your facility has been accurately entered in the data base.
No response is necessary unless an inconsistency is identified. If no comments are received within 30 days from the date of this letter, the NRC staff will consider your actions related to GL 92-01, Revision 1, to be complete.
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Hr. B. Ralph Sylvia March 30, 1994 The NRC staff's evaluation of NMPC's plant specific equivalent margin analysis is being reported separately to you under TAC No. H86107.
The information requested by this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, "Reactor Vessel Structural Integrity, 10 CFR 50.54(f)."
The estimated average number of burden hours is 200 person hours for each addressee's response.
This estimate pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations.
This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely,
Enclosures:
1.
Pressure-Temperature Limit Table 2.. Upper-Shelf Energy Table 3.
Nomenclature Key cc w/enclosures:
See next page Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Mr. B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Hile Point Nuclear Station Unit No.
1 CC; Mark J. Wetterhahh, Esquire Winston 8 Strawn 1400 L Street, NW Washington, DC 20005-3502 Supervisor Town of Scriba Route 8, Box 382
- Oswego, New York 13126 Vice President - Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 32
- Lycoming, New York 13093 Resident Inspector U.S. Nuclear Regulatory Commission P.O.
Box 126
- Lycoming, New York 13093 Gary D. Wilson, Esquire Niagara Hohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Ms.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Hr. Richard B. Abbott Unit 1 Plant Manager Nine Mile Point Nuclear Station P.O.
Box 32
- Lycoming, New York 13093 Hr. David K. Greene Manager Licensing Niagara Hohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Hr. Paul D.
Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza
- Albany, New York 12223 Mr. Martin J.
McCormick, Jr.
Vice President Nuclear Safety Assessment and Support Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.
Box 63
- Lycoming, New York 13093
0
Enclosure 1
Summary File for Pressure-Temperature Limits Plant Nano Nine Hite Point 1
EOL:
8/22/2009 Betttine ident.
Upper Shell G.307.3 Upper Shell 0.307.4 Upper Shall G.307.10 Lour SheLL G-8-1 Louer SheLL G.8-3 Loser Shell 0.8.4 Louer int.
SheLL Axial Welda 2.564A/C Louer Int./Lour Shell Circ. Meld 3.564 Lower Shell Axial Welda 2 5640/F Neat No, ident.
P2074 P2076 P2091 P2112 P2130 P2130 1248 LO Naut.
Fluence at EOL/EFPY 2.21E18 2.21E18 2.21E18 2.21E1d 2.21E18 2.21E18 2.21E18 2.21E18 2.21Eld 28'F 40'F 20'F WF
-3'F
.3'F 50'F
.50'F
-50'F Hethod of Oeterain.
LRT Plant Speci fic Plant Speci fic Plant Speci fic Plant Speci fic Plant Speci fic Plant Specific Generic Generic Cheaiatry Factor 134.6 173.85 148.85 153+95 130.2 130.2 112.0 112.0 Hethod of Oeterain.
CF Table Tabt ~
Tabl ~
Table Table Tabl ~
Table Tabl ~
Table 0.20 0.27 0.22 0.23 0.18 0.18 0.22 0.22 0.22 0.48 0.53 0.51 0.51 0.56 0.56 0.20 0.20 0.20 Reference for Nine Hile Poin
- Fluence, cheaicat coapoaition, and LRT data are fry JuLy 2, 1992, Letter fry C. O. Terry (1NNN:o) to USNRC Docsasent Control Oeatc, aubjectt Generic Letter 92-01, Rwiaion 1, Reactor Veaaet Structural integrity, 10 CFR 50.54(f)
Enclosure 2
Summary File for Upper Shelf Energy Plant Nioe Nine Hile Point 1
EOL:
8/22/2009 Beltlinc ident.
Upper Shell G-307 3 Upper Shell G.307.4 Upper Shell G-307 10 Lour Sh@L L G.8.1 LoNer Sh@L L G.d-3 Lour Shell G.8.4 Liower int.
Shel L Axial Melds 2.564A/C Lour Int./Lover Sh@LL Circ. 'Meld 3.564 Lower Shell Axi~ L
'Maids 2 5640/F Neat No.
P2074 P2076 P2091 P2112 P2130 P2130 1248 NaterIeL Typ A 302B Nod.
A 302$
Nod.
A 302$
Hod.
A 302$
Hod.
A 302B Hod.
A 302$
Nod.
ARCOS $ 5 SAM ARCOS $.5, SAlJ ARCOS $.5, SAM USE at EOL/EFPY 53 50 ENA 53 53 57 57 57 1/4T Neutron Fluence at EOL/EFPY 1.44E18 1.44E1d 1.44E1d 1.44E18 1.44E18 1.44E18 1.44E18 1.44E18 1.44E18 Unirrad.
USE 65 52 53 Hethod of Oeterain.
Unirrad.
USE 65X 65X 65X 65X Direct Direct NRC Generic NRC Generic NRC Generic R
enc frN H
WSEg chef cat coapoei tIon, and fluence data are froe July 2, 1992, Letter frce C. 0. Terry (NOD) to USNRC Doaaent Control Desk, subjects Generic Letter 92.01, Revision 1, Reactor Vessel Structural Lntegrity, 10 CFR 50.54(f)
Notes LRtirradiated USE for Maids are LoMer tao standard deviation value tree the surveillance ueld Plant specific equivalent margins, analysis has been approved by NRC.
Generic value for welds fabricated by Combustion Engineering using Linde
- 1092, 0091 and 123 and Arcos B-5 fluxes (Ref:
Letter from S.
- Bloom, NRR, to T.L. Patterson,
- OPPO, dated Oecember 3, 1993)
Enc)osure 3
Pressure-Temperature Limits Table Column I:
Column 2:
Column 3:
Column 4:
Column 5:
Column 6:
Plant name and date of expiration of license.
Beltline material location identification.
Beltline material heat number; for some welds that a single-wire or tandem-,wire process has been reported, (S) indicates single wire was used in the SAM process, (T) indicates tandem wire was used in the SAM process.
End-of-life (EOL) neutron fluence at vessel inner wall; cited directly from inner diameter (ID) value or calculated by using Regulatory Guide (RG) 1.99, Revision 2 neutron fluence attenuation methodology from the quarter thickness (T/4) value reported in the latest submittal (GL 92-01, PTS, or P/T limits submittals).
Unirradiated reference temperature.
Method of determining unirradiated reference temperature (IRT).
Column 7:
Colum 8:
This indicates that the IRT was determined from tests on material removed from the same heat of the beltline material.
HlU~
This indicates that the unirradiated reference temperature was determined from following HTEB 5-2 guidelines for cases where the IRT was not determined using American Society of Mechanical Engineers Boiler and Pressure Vessel
- Code,Section III, NB-2331, methodology.
9m~
This indicates that the unirradiated reference temperature was determined from the mean value of tests on material of similar types.
Chemistry factor for irradiated reference temperature evaluation.
Nethod of determining chemistry factor Iahla This indicates that the chemistry factor was determined from the chemistry factor tables in RG 1.99, Revision 2.
C41atl4M This indicates that the chemistry factor was determined from surveillance data via procedures described in RG 1.99, Revision 2.
Column Column 9
~
10:
Copper content; cited directly from licensee value except when more than one value was reported.
(Staff used the average value in the latter case.)
~N~t This indicates that no copper data has been reported and the default value in RG 1.99, Revision 2, will be used by the staff.
Nickel content; cited directly from licensee value except when more than one value was reported.
(Staff used the average value in the latter case.)
This indicates that no nickel data has been reported and the default value in RG 1.99, Revision 2, will be used by the staff.
Upper Shelf Energy Table Column Column Column Column Col umn Colum 1
~
2 ~
3
~
4o 5
~
6:
Plant name and date of expiration of license.
Beltline material location identification.
Beltline material heat number; for some welds that a single-wire or tandem-wire process has been reported, (S) indicates single wire was used in the SAM process.
(T) indicates tandem wire was used in the SAM process.
Material type; plate types include A 533B-1, A 302B, A 302B Hod.,
and forging A 508-2; weld types include SAM welds using Linde 80,
- 0091, 124,
- 1092, ARCOS-B5 flux, Rotterdam welds using Graw Lo, SHIT 89, LM 320,.-and SAF 89 flux, and SHAM welds using no flux.
EOL upper-shelf energy (USE) at T/4; calculated by using the EOL fluence and either the cooper value or the surveillance data.
(Both methods are described in RG 1.99, Revision 2.)
QS This indicates that the USE issue may be covered by the approved equivalent margins analysis in the BMR Owners Group Topical Report:
NE00-32205, Revision 1.
EOL neutron fluence at T/4 from vessel inner wall; cited directly from T/4 value or calculated by using RG 1.99, Revision 2 neutron fluence attenuation methodology from the ID value reorted in the latest submittal (GL 92-01, PTS, or P/T limits submittals).
Column 7:
Unirradiated USE.
QQ This indicates that the USE issue may be covered by the approved equivalent margins analysis in the 8WR Owners Group
.Topical Report:
NE00-32205, Revision l.
Column 8:
Method of determining unirradiated USE QizM For plates, this indicates that the unirradiated USE was from a transverse specimen.
For welds, this indicates that the unirradiated USE was from test date.
~6 This indicates that the unirradiated USE was 65X of the USE from a longitudinal specimen.
~G~i This indicates that the unirradiated USE was reported by the licensee from other plants with similar materials to the beltline material.
JHN~c This indicates that the unirradiated USE was derived by the staff from other plants with similar materials to the beltline material.
This indicates that the unirradiated USE was derived from Charpy test conducted at 10, 30, 40, or 50 'F.
Stgv ~e~l This indicates that the unirradiated USE was from the surveillance weld having the same weld wire heat number.
t v
This indicates that the unirradiated USE was from the surveillance weld having different weld wire heat number.
This indicates that the unirradiated USE was derived by using the reported value from other plants with the same weld wire heat number.
91m'ndicates that there is insufficient data to determine the unirradiated USE.
These licensees will utilize Topical Report NED0-32205, Revision 1 to demonstrate USE compliance to Appendix G, 10 CFR Part 50.
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Hr. B. Ralph Sylvia March 30, 1994 The NRC staff's evaluation of NHPC's plant specific equivalent margin analysis is being reported separately to you under TAC No. H86107.
The information requested by this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, "Reactor Vessel Structural
'ntegrity, 10 CFR 50.54(f)."
The estimated average number of burden hours is 200 person hours for each addressee's response.
This estimate pertains only to the identified response-related matters and does not include the time required to implement actions required by the regulations.
This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely, Original signed by:
Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Pressure-Temperature Limit Table 2.
Upper-Shelf Energy Table 3.
Nomenclature Key cc w/enclosures:
See next page DISTRIBUTION:
Docket File,'DI-1 Reading JCalvo CVogan OGC CCowgill, RGN-I DMcDonald NRC 8 Local PDRs SVarga RACapra DBrinkman ACRS (10)
JStrosnider, 7/D/4 PDI-1: LA PDI-1: PH PDI-1: D HAHE CVo DBrinkman: avl RACa ra DATE 9 4'f 94 3' 940 94 OFFICIAL RECORD COPY F ILENAME:,G: iNMPliNH183486. LTR
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