ML20069E725
| ML20069E725 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 06/03/1994 |
| From: | Mims D ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 1CAN069401, 1CAN69401, GL-92-01, GL-92-1, NUDOCS 9406080004 | |
| Download: ML20069E725 (5) | |
Text
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-:==- Entcr9Y Entergy opsrations,Inc.
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June 3,1994 2CAN069401 U. S. Nuclear Regulatory Commission Document Control Desk Mail Station PI-137 Washington, DC 20555
Subject:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Request for Verification ofInformation Regarding Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity" Gentlemen:
By letter dated May 4,1994 (2CNA059401), the NRC requested that Entergy Operations verify that the infonnation provided in its response to Generic Letter 92-01 has been accurately entered in the NRC's summary data file. Comments were requested within 30 days of the date of the letter.
Arkansas Nuclear One (ANO) technical personnel reviewed the information contained in the NRC letter and noted several discrepancies from the data which ANO had previously submitted. The data contained in the June 13,1978, letter referenced in Enclosure 2, was prepared by the reactor vendor from source documents and thus is believed to be correct.
Corrections are annotated (in handwriting) on the attached markup of Enclosure 1,
" Summary File for Pressurized Thermal Shock" and Enclosure 2, " Summary File for Upper Shelf Energy" from the May 4,1994, letter. During the course of this review it was found that the data ANO had submitted on June 13,1978 (Letter 2-068-10), regarding pressure vessel fracture toughness, is in conflict with information in safety analysis report table 5.2-5.
A review is in progress with the reactor vessel supplier to resolve this discrepancy. The reactor vessel supplier is compiling the original source documentation.
Once received, this documentation will be used to verify the docketed information on reactor vessel material propenies. When this effort is completed, the appropriate licensing basis documents will be updated as necessary.
Should you have any questions regarding this submittal, please contact me.
o 07GCIS 9406080004 940603 PDR ADOCK 05000368 P
PDR I
. 'U. S. NRC
. June 3,1994 2CAN069401 Page 2 Very truly yours, kt>hlllC~~/)$J Dwight C. Mims Director, Licensing DCM/jrh Attachment To the best of my knowledge and belief, the statements contained in this submittal 1
are true.
1 I
.{UBSCRIBED AND SWORN TO before me, a Notary Puglic in and for F@
County and the State of Arkansas, this J _ day of Ch4_.
i 1994.
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l "M. M1 bidbb Notary Pu$c MgCommission Expires 4-dt-200a >
r M JANE DAVIDSON No;ory PubtlC POPE COUNTY, ARKANSAS Commission Expros 4-24-2002 j
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U. S. NRC June 3,1994 2CAN069401 Page 3 cc:
Mr. Leonard J. Callan Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. George Kalman NRR Project Manager Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-11-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike Rockville, MD 20852
Summary File for Pressurized Th:rmal Shock Plant Battline Neet me.
It neut.
187 Itethod of Chemistry mothed of Eu Mi came Ident.
Ident.
Fluarte et Detersin.
Facter
- Deterein, j
EOL/tFPY
!RT.,
CF Arktnses int. Shett C8161-3 5.2H19 26*F wita 5 2 83.65 Table 0.12 0.63 2
C 8009-1 ECt:
Int. thett C8161 1 5.2M19 0'F NTER 5 2 51 Tette 0.08 0.59 T/17/2018 C 8009 2 Int. Shell C8182 2 5.2M19 0'F Plant 51 febte 0.08 0.60 C 8009 3 Specific Lowe C8161 2 5.26(19 12*r itTES 5 2 51 febte 0.08 0.59 Shett C 8010 1 Lower 82545 1 5.2M19 2A'F isits 5 2 4
Table 0.07 0.66 Shett l
l C 8010 2 Lower 82545 2 5.2M19 30'r NTES 5 2 64 febte 0.07 0.65 shell C 8010 3 Int, to 83650 5.2M19 10*F Plant 35.2 febte 0.05 0.08 4
Lower Specific l
Shell Cire. Weld 9 203 Lower 10120 5.2M19 56*F Generic 4.7 febte 0.05 0.18 shett Amlet Wetde 3 203A/C Int. Shell 10120 5.26E 19 54*F Generic
- 4. 7 Table 0.05 0.14 I
Asial l
Wolde 2 203A/C i
l Upper to 1.52t18 54'r Generic 115.6 Table 0.23 0.1A int. shott lo/37
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8 203 I
eese m e Chemical coruroeition and laf date are from July 1,1992, letter from J. J. Fielcaro (EC) to usutC Demannt Contrst Gesk, s4jects response to Generic tetter 92 01, Revielen 1, =teactor veseal structuret Intetrity" Fluence date, chemical composition and Itf., for 8 203 weld are reported in a Juis 18, 1991 letter free J.W. Tetworten I
(EC) to U$utC.
l Summary File for Upper Shelf Energy Plent Meme seitLine Weet to.
feeteriet 1/47 USE 1/67
- thfrred, leethod of Ident.
Type et EOL Neutron USE
'Determin.
i Fluence et thirred.
M M
Arkeneen 2 Int. h t!
C8161 3 A 5334 1
-M---
2.
- i7 - 65 1 C s009 1
(,;,6
.f.l BI/9 9/
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EOL:
Int. Shett C8161 1 A 5333 1
-M-
-ErF5W49-65 1
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7/17/2018 C 8009 2 6.,2 3.28 8/9 82 Int. shet t C8182 2 A 5338 1
-tH.
- 2. 5 t"* -
126 Ofroct C 8009 3 95"
- 3. 2BE/9 Louer C3161 2
/. 5334 1
-de--
2.5 ?"" - 651 47
- 3. 2BE19 81 sheit C 8010.,
Lover 32545 1 A 5334 1
-P1--
2.C";"? -
-M-651 49 3.2Sfl9 %
shett C 8010 2 tower 82545 2 A 5333 1
-P6-2."t:57 - -
651 e $0 3 71 3.2 arte 94 Int. to 83650 Lires -
- 2. " ' ' ? -
125 Direct Lower 0091, SAW f4 3.38El9 shatt Circ. Wold 9 203 Lower 10120 Linde
+
2."it t" -
122 Direct shett 0091, SAW U-3.28 Elf An'et WeLde 3 203A/c Int. Shett 10120 Linde -
2."*:17 109 Direct Astet 0091, SAW 82 3.3BE/9
- te 2 203A/C upper to 10137 Linds
-4E-9.&tE17
-405--
10'F 79
/OI Uf3 neforences uust date for ptetes are reported in febtes 5.2 5 and 5.2-16 of Ado 2 FsAs LEtst date for Int. Shett and Lower sheLL Amlet Walde are reported in a July 22, 1991 tetter from J.J. Fisicaro (50) to U5meC.
LAJst date for 9 203 erui 5 255 Cire. Walde are reported in e Jme 13, 1975 tetter free D.s.
Wittiens (APLC) to usuaC.
Fluence detus le from Jm e 18, 1991, letter from J. W. Yetverton (EC) to Usuec.
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