ML17059A248
| ML17059A248 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/30/1994 |
| From: | Menning J Office of Nuclear Reactor Regulation |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| References | |
| GL-92-01, GL-92-1, TAC-M83487, NUDOCS 9404050213 | |
| Download: ML17059A248 (18) | |
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Docket No. 50-410 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 2 (TAC NO. M83487)
By letter dated July 2,
The NRC staff has completed its revieq-of your response.
Based on its review, the staff has determined that NMPC hqs provided the information requested in GL 92-01.
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'C The GL is part of the staff's program to evaluate reactor vessel integrity for
'ressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs).
The information provided in response to GL 92-01, including previouslydocketed 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 BWRs.
Enclosure 1 provides the pressure-temperature
- table, Enclosure 2 provides the USE table for your facility, 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 response to GL 92-01 and previously docketed information.
The information in the RVID for your facility will. be considered accurate at this point in time and will be used in the: staff's assessments related to vessel structural integrity.
References to the'pecific source of data are provided in the tables.
We request that NMPC verify that the information 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 NMPC's actions related to GL 92-01, Revision 1, to be complete.
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Mr. B. Ralph Sylvia March 30, 1994 The information requested by this letter is within the scope of the 'overall burden estimated in GL 92-01; Revision 1, "Reactor Vessel'tructural Integrity, 10 CFR 50.54(f)." 'he estimated averag'e number of burden'ours 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.'incerely,
Enclosures:
1.
Pressure-Temperature Limit Table 2.
Upper-Shelf Energy Table 3.
Nomenclature Key cc w/enclosures:
See next page John E. Menning, Project Manager Project Directorate I-l Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
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Hr. B. Ralph Sylvia Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Unit 2 CC:
Hark J. Wetterhahn, Esquire Winston E Strawn 1400 L Street, NW.
Washington, DC 20005-3502 Mr. Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus
- Syracuse, New York 12223 Resident Inspector Nine Mile Point Nuclear Station P.O.
Box 126
- Lycoming, New York 13093 Gary D. Wilson, Esquire
. Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Mr. David K. Greene Manager Licensing Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Ms. Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Super visor Town of Scriba Route 8, Box 382-
- Oswego, New York 13126 Regional Administrator, Region I U. S': Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 L 'k Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Hr. Richard M. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue
- Albany, New York 12210 Hr. John H. Hueller Plant'anager",- Unit 2::"
Nine Mile'Poirit Nuclear Station Niagara Mohawk Power Corporation P.O.
Box 32
- Lycoming, New York 13093 Vice President - Nuclear Generation Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P.O.
Box 32 Lycomin'g, New York 13093'*
Mr. Martin J. HcCormick, Jr.
Vice':Pr esi'dent Nuclear Safety Assessmenf" and Support Niagara Mohawk Power Corporation Nine-Mile Point Nuclear Station P.O.
Box 63
- Lycoming, New York 13093
Enclosure 1
Suffifary File for Pressure-Temperature Limits Plant Nano Nine Hite Point 2 EOL:
10/
21/2026 Beltline Ident.
<<2 Shell Ri
<<2 Shell Rfng
<<2 SheLL Ri
<<1 Shell Ri
<<1 SheLL Ri
<<1 Shell Ring
<<2 Shell Axial Melda BD/BF
<<2 Shell Axial Maids BO/BF
<<1 Shell AxiaL Molds BA/BC
<<1 Shell Axial Metda BA/BC Heat No.
ident.
C3065.1 C3121 2
C3147-1 C3147-2 C3066 2 C3065.2 5P5657 5P5657 5P6214$
5P6214B 1D Naut.
Fluence at EOL/EFPY 1.72E1d 1.72E18 1.72E18 1.72E18 1.72E18 1.72E'id 1.72E18 1.72E18 1.72E1d 1.72E18
-10'F O'
OsF O'
-20'F 10'F
.60'F
.60'F 50'F
.40'F Nethod of Determin.
LRT Plantific Plant S
if ic Plant S
ific PLant S
ific Plant S
ific PLant S
ific Plant Speci fic Plant Speci ffc Plant Speci fic Plant Speci fic Chemi atry Factor 37 58 74.45 74.45 37 27 20 Nethod of Oetermfn.
CF TabLe Table Table Table Table Table Table Table Table Table 0.06 0.09 0.11 0.11 0.07 0.06 0.07 0.04 0.02 0.01 0.63 0.65 0.63 0.63 0.64 0.63 0.71 0.89 0.82 0.70 Circ. Meld 4P7465 (S)
Cfrc. Meld 4P7465 (T)
Circ. Meld 4P7216 (S)
Circ. Meld 4P7216 (T) 1.72E18 1.72E18 1.72E1d 1 72E1d 60'F
.60'F
.50'F
.80'F Plantific Plant S
iffc Plant S
ific Plant S
ific 27 27 82 Table Table Table Table 0.02 0.02 0.06 0.04 0.82 0.80 0.85 0.83 Reference f r N Nile P
- Fluence, chemical composftfon, and lRT data are fran July 2, 1992, Letter from C. D. Terry (NHPCo) to USNRC Doc@nant Control Desk, aubJectt generic Latter 92-01, Reviafon 1, Reactor Vessel Structural integrity, 10 CFR 50.54(f)
NOTEt Nine Nile Point 2 haa a margin that ia specially calculated:
N ~ 2 aqrt[(CF ff/u)*+ 100]
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CIIC I Ob UI"8 Sufmary File for Upper Shelf Energy Plant Nme Seltline Heat No.
ident.
Rater fel Type USE at EOL/EFPY 1/4T
'eutron FLuence at EOI./EFPY Unfrrad.
USK Nethod of Oeterafn.
Unfrrad.
USE Nine Nile Point 2 EOLt 10/21/2026
¹2 Shell Rf
¹2 Shell C3121-2 Rfna
¹2 Shell C3147-1 Rf
¹1 SheLL C3147-2 Rfng 533$ -1 533$
1 533$ -1 A 533$ -1 76 1.1881d 1.18E18 ~
1 ~ 18E18 1.18E1d 71 Dfrect Direct Direct Direct
¹1 Shell Rf C3066 2 A 533$.1 1.18E1d Direct
¹1 Shell C3065-2 Rfno
¹2 ShelL 5P5657 Axial Melda SD/SF
¹2 SheLL SP5657 Axial Melda SD/SF
¹1 Shell 5P6214$
Axial Melda SA/SC
¹1 SheLL 5P6214$
Axf~ L Melda BA/SC Circ. Meld 4P7465 (S)
Circ. Meld 4P7465 (T)
A 53381 Lfnde 124, SAM Linda 124, SAM Linda 124, SAM Linda 124, SAM Lfnde 124, SAM Linda 124,
'74 1.18K18 1 ~ 18Efd 1.1881d 1.18E1d
'1.18E18 1.18K18 1.18E18 102 110 Direct Direct Direct Direct Direct Direct Direct Circ. Meld 4P7216 (S)
Cfrco Meld 4P7216 (T)
Lfnde 124, SAM Linda 124, SALI 1 ~ 18E1d 1.18K18 Direct Direct WSK, cheaIfcaL coapoaftfon, and fluence data are free July 2, 1992, Letter fry C. D. Terry (Neo) to USNRC Docent Control Desk, a&jectt Generic Letter 92-01, Reviaicn 1, Reactor Veaael Structural integrity, 10 CFR 50.54(f)
Enclosure 3
PR T TA S
ND U
P A
S Pressure-Temperature Limits Table
.Column 1:
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).
This indicates that the IRT was determined from tests on material removed from the same heat of the beltline material Column 7:
Column 8:
HIHL~
This indicates that the unirradiated reference temperature was determined from following MTEB 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.
ReneM 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.
Method of determining chemistry factor Isbn This indicates that the chemistry factor was determined from the chemistry factor tables in RG 1.99, Revision 2.
Q~lai!ui This indicates that the chemistry factor was determined from surveillance data via procedures described in RG 1.99, Revision 2.
Column Column 9
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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.)
JhJhia 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 Column Column 1'
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4
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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 SAW process.
(T) indicates tandem wire was used in the SAM process.
Haterial 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, Lll 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.)
9$
This indicates that the USE issue may be covered by the approved equivalent margins analysis in the BNR Owners Group Topical. Report:
NED0-32205, 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).
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Column 7:
Unirradiated USE.
9$
This indicates that the USE issue may be covered by the approved equivalent margins analysis in the BWR Owners Group Topical Report:
NED0-32205, Revision 1.
Column 8:
Method of determining unirradiated USE
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LLeM For plates, this indicates that the univradiated USE was from a transverse specimen.
For welds, this indicates that the unirradiated USE was from test date.
QX This indicates that the unirradiated USE was 65K of the USE from a longitudinal specimen.
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This indicates that the unirradiated USE was reported by the.
licensee from other plants with similar materials to the beltline material.
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.
2,z~ehi This indicates that the unirradiated USE was from the surveillance weld having the same weld wire heat number.
This indicates that the unirradiated USE was from the surveillance weld having different weld wire heat number.
w This indicates that the unirradiated USE was derived by using the reported value from other plants with the same weld wire heat number.
Mnk indicates that there is insufficient data to determine the unirradiated USE.
These licensees will utilize Topical Report NE00-32205, 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 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
'equired to implement actions required by the regulations.
This action is covered by the Office of Hanagem'ent and Budget Clearance Number 3150-0011, which expires June 30, 1994.
n Sincerely,
Enclosures:
II 1.
Pressure-Temperature Limit Table 2.
Upper-Shelf Energy Table 3.
Nomenclature Key cc w/enclosures:
See next page Original signed by:
John E. Henning, Project Manager
'roject Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation DISTRIBUTION:)
Docket File NRC 8 Local PDRs PDI-1 Reading SVarga JCalvo DMcDonald CCowgill, RGN-I RACapra-CVogan JHenning OGC ACRS (10)
- SSheng, 7/D/4 DATE PDI-1: LA CVo an Sg 94 PDI-1: PH JHennin 3g 94 PDI-1: D RACa ra yo 94 OFFICIAL RECORD COPY FILENAHE: G: iNMP2 iI,NM283487. LTR
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