ML20029D910
| ML20029D910 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/09/1994 |
| From: | Labarge D Office of Nuclear Reactor Regulation |
| To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
| References | |
| GL-92-01, GL-92-1, TAC-M83513, TAC-M83514, NUDOCS 9405120234 | |
| Download: ML20029D910 (9) | |
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UNITED STATES
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'b WASHINGTON, D.C. 2055%0001
- j May 9, 1994 l
Docket Nos. 50-327 and 50-328 Mr. Oliver D. Kingsley, Jr.
1 President, TVA Nuclear and Chief Nuclear Officer Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801 I
Dear Mr. Kingsley:
SUBJECT:
GENERIC LETTER 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M83513 AND M83514)
By letters dated July 7, 1992 and September 27, 1993, the Tennessee Valley Authority (TVA) responded to Generic letter (GL) 92-01, Revision 1 for the Sequoyah Nuclear Plant (SQN), Units 1 and 2.
The NRC staff has completed its review of these responses and, based on its review, has determined that TVA has provided the information requested in GL 92-01.
The GL is part of the 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.
This data has been entered into a computerized data base designated the Reactor Vessel Integrity Database (RVID).
The RVID contains the following tables:
a pressurized thermal shock (PTS) table for PWRs, a pressure-temperature limits table for BWRs, and an upper-shelf energy (USE) table for PWRs and BWRs. provides the PTS table, Enclosure 2 provides the USE table for SQN Units 1 and 2, and Enclosure 3 provides a key for the nomenclature used in the tables.
The tables include the data necessary to perform USE and RT evaluations, This data was taken from g
TVA's responses to GL 92-01 and previously docketed information.
References to the specific source of the data are provided in the tables.
We request that you verify that the information you have provided for SQN Units 1 and 2 has been accurately entered in the summary data files.
No response is necessary unless an inconsistency is identified.
If no comments are received within 30 days from the date of this letter, the staff will consider your actions related to GL 92-01, Revision 1, to be complete and the staff will use the information in the tables for future NRC assessments of your reactor pressure vessel.
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9405120234 940509 PDR ADDCK 05000327
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s Mr. Oliver D. Kingsley 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.
This action closes TAC Nos. M83513 and M83514.
Sincerely, Original signed by David E. LaBarge, Sr. Project Manager Project Directorate 11-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
1.
Pressurized Thermal Shock Table 2.
Upper-Shelf Energy Table 3.
Nomenclature Key cc w/ enclosures:
See next page Distribution Docket: File NRC & Local PDRs SQN Reading S. Varga G. Lainas F. Hebdon B. Clayton D. LaBarge ACRS(10)
D. Mcdonald E-7 E. Hackett D-4 J. Johnson, RII M. Lesser, RII J. Jaudon, RII e
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DLaBarge FHebdonN-NAME:
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110009 j
i ENCLOSURE 2 Sumary File for Upper Shelf Energy Plant uene Belttine Neet No.
Meterl4L 1/47 USE 1/4T unirred.
Method of l
Ident.
Tme at E0L Neutron USE Deternin.
Fluence at Unfrred.
EOL Uss SegJoyah 1 Int. shet t,
980807/
A 508 2 53 2.29E19 74
&$1 Forging 09 281489 EOL :
Lowe 900919/
A 508 2 53 2.29E19 72 Otract 9/17/2020 ehelt 28154 7 Forging 04 Cire. weld 25295 SMlf 89, 57 2.29e19 111 Direct SAW Referefree Chemical compoeltlon. LAfst, and fluence dets are from July 7,1992, Letter fras R. M. Shelt (TVA) to USNRC Occument Centrol Desk, s@ ject: Broune Ferry Nucteer Plant, segJoyeh Nucteer Plant, and Wette See Nucteer Plantatesponse to Generle Letter 92 01 (Reector vesset Structural Integrity)
The USE vetues et EOL for Forging 04 and the cireurferential weld are calculated free survelttance date (6 for Forging 04 and 3 for the circueferential weld).
Ptent kone setttlne Noet No.
Meteriet 1/47 Ust 1/47 Unirred.
Method of Ident.
Type at EOL Neutron USE Detenmin.
Fluence at Untrred.
EOL USE Sequoyeh 2 Int, shell 288757/
A $08 2 71 9.96E18 88 Ofroct Forging 05 -
961057 EOL :
Lower 990469/
A 508 2 77 9.96E18 100 65%
9/15/2021 sheLL 293323 i
Forging 04 Cire.
4278 Smit 89, 70 9.96E18 105 Ofrect weld SAW teferexes Chemical compoeltlan, Uutt, and fluence data are frce July 7,1992, letter from R. M. Shell (TVA) to U$htC Occument Controt Desk, s@ ject Browns Ferry Nucteer Plent, segJoyah Nucteer Plant, and Wette Bar Nuclear Plantateoponse to Generic Letter 92 01 (tenctor vessel structuret Integelty) l
ENCLOSURE 1 Sumary File for Pressurized Thermal Shock Plant Beltline Nest No.
ID Neut.
I R T.,,
Method of Chemistry Method of ICu ENI Name Ident.
Ident.
Fluence at Determin.
Factor Determin.
EOL 1 R T.,
CF Sequoyah Int, shell 990807/
3.838E19 40*F Plant 115.6 Table 0.15 0.86 1
Forging 05 281489 specific EOL:
Lower 980919/
3.838E19 T3*F Plant 107.15 Calcuteted 0.13 0.76 9/1F/2020 shett 281587 Specific Forging 04 cire. wid 25295 3.838E19 40*F Plant 158.65 Calculated 0.33 0.17 specific References Chemical composition, IRT, and fluence data are from July 7,1992, letter fran R. M. Shett (TVA) to USNRC Document Control Desk, s@)ect: Browne Ferry Nucteer Plant, Sequoyah Nuclear Plant, and Wetts Bar Nuclear Plant Response to Generic Letter 92 01 (Reactor vesset structural Integrity) 127 values for forgines 05 aruf 04 have been revised to 40*F and 73'F (response to GL 92 01 RAI datcd September 27, 1993). -
The Chemistry Factor for Forging 04 and the circueferentist weld are calculated from surveillance data (6 dets for Forging 04 and 3 data for the circunferentist weld). One of the weld data is not credible per AG 1.99, Rev. 2, but the calculated value is still used because this CF is only 1*F higher than that determined free usire the Table.
Plant Belttine Nest No.
ID Neut.
IRT Method of Cheeletry Method of ICU INI Name Ident.
Ident.
Fluence et Determin.
Factor Determin.
4 E04.
IRT CF sequoyen Int, shett 288757/
1.669t19 10'F Plant 92.373 Calculated 0.13 0.74 3
Forging 05 981057 toecific EOL:
Lower 990469/
1.669t19
-22*F Plant 103.75 Table 0.14 0.75 9/15/2021 shelt 293323 Specific Forging 04 cire.
4278 1.669t19
-4'F Plant 67.9 Tabte 0.13 0.11 weld specific i
Lt!MY.C1 The IRT., vot-Forgirg 04 has been revised to 22'F (response to GL 92 01 RAI dated September 27, 1993).
the Chemistry Factor for Forgine 04 is calculated from surveillvce data (6 deta). The surveillance date for the circurferentist weld how been discounted because two et the three data are not credible.
Chemical compoet tion, IRT.,,, cad fluence data are from July 7,1992, letter fra R. M. shett (TVA) to usNaC Document control Desk, subject: Browns Ferry Nucteer Plant, segJoyah Nucteer Plant, and Watts Bar Nuclear Plant Response to Generic Letter 92 01 (Reactor vessel structurel Integrity)
ENCLOSVRE 3 NOMENCLATURE - PRESSURIZED THERMAL SH0CK TABLE - UPPER-SHELF ENERGY TABLE FOR ALL PRESSURIZED WATER REACTOR PLANTS NOMENCLATURE Pressurized Thermal Shock Table Column 1:
Plant name and date of expiration of license.
Column 2:
Beltline material location identification.
Column 3:
Beltline material heat number; for some welds that.a single-wire or tandem-wire process has been reported, (S) indicates singla wire was used in the SAW process, (T) indicates tandem-wire was used in the SAW process.
Column 4:
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
.i reported in the latest submittal (GL 92-01, PTS, or.P/T limits submittals).
Column 5: Unirradiated reference temperature.
Column 6: Method of determining unirradiated reference temperature (IRT),.
Plant-Soecific This indicates that the IRT was determined from tests on
)
material removed from the same' heat of the beltline material.
MTEB 5-2 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.
Generic j
This indicates that the unirradiated reference temperature was determined from the mean value of tests on material of similar types.
I j
b 2
Column 7: Chemistry factor for irradiated reference temperature evaluation.
Column 8: Method of determining chemistry factor.
Table This indicates that the chemistry factor was determined from the chemistry factor tables in RG 1.99, Revision 2.
Calculated This indicates that the chemistry factor was determined from surveillance data via procedures described in RG 1.99, Revision 2.
Column 9:
Copper content; cited directly from licensee value except when more than one value was reported.
(Staff used the average value in the latter case.)
No Data 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.
Column 10: Nickel content; cited directly from licensee value except when more than one value was reported.
(Staff used the average value in the latter case.)
No Data 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 1:
Plant name and date of expiration of license.
Column 2:
Beltline material location identification.
Column 3:
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 SAW process.
Column 4: Material type; plate types include A 533B-1, A 3028, A 302B i
Mod., and forging A 508-2; weld types include SAW welds using Linde 80, 0091, 124, 1092, ARCOS-B5 flux, Rotterdam welds using Graw Lo, SMIT 89, LW 320, and SAF 89 flux, and SMAW welds using no flux.
Column 5:
E0L upper-shelf energy (USE) at T/4; calculated by using the E0L fluence and either the cooper value or the surveillance data.
(Both methods are described in RG 1.99,. Revision 2.)
3 EMA This indicates that the USE issue may be covered by either owners group or plant-specific equivalent margins analyses.
Column 6:
E0L 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 reported in the latest submittal (GL 92-01, PTS, or P/T limits submittals).
Column 7:
Unirradiated USE.
EMA l
This indicates that the USE issue may be covered by either R
owners' group or plant-specific cquivalent margins analyses.
Column 8: Method of determining unirradiated USE.
]
Direct
-l For plates, this indicates that the unirr?.diated USE was from a transverse specimen.
For welds, this indicates that the 1
unirradiated USE was from test date.
M This indicates that the unirradiated USE was 65% of the USE from a longitudinal specimen.
Generic This indicates that the unirradiated USE was reported by the licensee from other plants with similar materials to the beltline material.
NRC aeneric This indicates that the unirradiated USE was derived by the staff from other plants with similar materials to the beltline material.
- 10. 30. 40. or 50 *F This indicates that the unirradiated USE was derived from Charpy test conducted at 10, 30, 40, or 50 *F.
Surveillance Weld This indicates that the unirradiated USE was from the surveillance weld having the same weld wire heat number.
i
4 Eouivalent to Surveillance Weld This indicates that the unirradiated USE was from the surveillance weld having different weld wire heat number.
Sister Plant This indicates that the unirradiated USE was derived by using the reported value from other plants with the same weld wire heat number.
Blank Indicates that there is insufficient data to determine the unirradiated USE.
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' 'Mr. Oliver. D. Kingsley, Jr.
SEQUOYAH NUCLEAR PLANT
^
Tennessee Valley Authority cc:
Mr. Craven Crowell, Chairman Mr. B. S. Schofield, Manager Tennessee Valley Authority '
Nuclear Licensing and ET 12A Regulatory Affairs 400 West Summit Hill Drive Tennessee Valley Authority Knoxville, TN -37902 4G Blue Ridge 1101 Market Street Mr. W. H. Kennoy, Director Chattanooga, TN 37402-2801 Tennessee Valley Authority
)
.ET 12A Mr. Ralph H. Shell 400 West Summit Hill Drive Site Licensing Manager Knoxville, TN 37902 Sequoyah Nuclear Plant Tennessee Valley Authority Mr. Johnny H. Hayes, Director P.O. Box 2000 Tennessee Valley Authority Soddy Daisy, TN 37379 ET 12A 400 West Summit Hill Drive Mr. Roger W. Huston Knoxville, TN 37902 Tennessee Valley Authority 11921 Rockville Pike Mr. O. J. Zeringue, Sr. Vice President Suite 402 Nuclear Operations Rockville, MD 20852-j Tennessee Valley Authority 3B Lookout Place Regional Administrator 1101 Market Street U.S. Nuclear Regulatory Commission Chattanooga, TN :37402-2801-
- Region 'II x 101 Marietta Street,.NW., Suite 2900 i
Dr. Mark 0. Medford, Vice President Atlanta, GA 30323 Technical Support Tennessee Valley Authority Mr. William E. Holland' 3B Lookout Placet Senior Resident Inspector 1101 Market Street Sequoyah Nuclear Plant Chattanooga, TN 37402-2801 U.S. Nuclear Regulatory Commission 3
2600 Igou Ferry' Road Mr. D. E. Nunn, Vice President Soddy. Daisy, TN 37379 Nuclear Projects Tennessee Valley Authority Mr. Michael H. Mobley, Director 3B Lookout Place Division of Radiological Health 1101 Market' Street 3rd Floor, L and C Annex-Chattanooga, TN 37402-2801 401 Church Street Nashville, TN 37243-1532 Site Vice President Sequoyah Nuclear Plant County Judge Tennessee Valley Authority Hamilton County Courthouse P.O. Box 2000 Chattanooga, TN 37402 Soddy, Daisy, TN 37379
' General Counsel
~
Tennessee Valley Authority ET 11H 400' West Summit Hill Drive
. Knoxville, TN ~37902 l
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