ML20069L675

Forwards Corrected Tables of PTS & Use Info for Callaway Plant,In Response to NRC Concerning Util 920616 Response to GL 92-01 Re Reactor Vessel Structural Integrity

ML20069L675
Person / Time
Site:	Callaway
Issue date:	06/13/1994
From:	Schnell D UNION ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, TAC-M83445, ULNRC-3031, NUDOCS 9406200162
Download: ML20069L675 (4)

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31:: % 1 l%0 June 13, 1994 Eucenue IGN U.S. Nac1 ear Resuiatory Commission Y;

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'] ATTN.: Document Control Desk Mail Station P1-137 Washington, D.C. 20555 ULNRC-3031 TAC No. 83445 Gentlemen:

CALLAWAY PLANT DOCKET NUMBER 50-483 REACTOR VESSEL STRUCTURAL INTEGRITL_10 CFR 5_0_,_5_4_Lfl Ref. 1) Generic Letter 92-01, Revision 1, dated March 6, 1992 2 ) ULNRC- 2 64 9, dated June 16, 1992

3) L. R. Wharton Letter to D. F. Schnell dated May 12, 1994 NRC Generic Letter 92-01 requested that licensees provide information concerning their reactor pressure vessels. This information will be used by NRC to confirm that licensees satisfy the requirements and commitments necessary to ensure reactor vessel integrity at their facilities.

By letter dated May 12, 1994 (Reference 3) the NRC Staff determined that Union Electric had provided the information requested by GL 92-01. This letter also transmitted tables which contain pressurized thermal shock (PTS) and upper-shelf energy (USE) information for Callaway Plant. The staff requested that Union Electric perform an accuracy review of the information contained in the tables.

Enclosed please find the corrected tables of PTS and USE information for Callaway Plant. This data was taken from our response to GL 92-01 and previously docketed information. Please review this information and update your database accordingly.

If you have any questions concerning this information, please contact us.

Very truly yours, l$ ,

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h Donald F. Schnell WEK/kea Enclosures h. [l 9406200162 940613 PDR ADOCK 05000403 p PDR

cc:' T. A. Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge 2300 N. Street, N.W.

Washington, D.C. 20037 M. H. Fletcher CFA, Inc.

18225-A Flower Hill Way Gaithersburg, MD 20879-5334 L. Robert Greger Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 801 Warrenville Road Lisle, IL 60532-4351 Bruce Bartlett Callaway Resident Office U.S. Regulatory Commission RR#1 Steedman, MO 65077 L. R. Wharton (2)

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 f

Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 l.

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_ ENCLOSURE 1 i

Summary File for Pressurised Thermal Shock Plant itettline lleat No. ID Neut. IRTndt niethod Chemistry Method of GCu %Ni 1%me Ident. Ident. Fluence at of Determin. Factor Determin.

EOIAFPY 1RTndt CF Callaway i Int. Shell C4144- 1 2.19E 14 40*F Plant Specific 26 Table 0.04 0.57 R27071 EOL:

10/18/

2024 Int Shell C4381 1 2.39E19 10'F Plant Specifie 31 Table 0.05 0.59 R 2 707-2 Int. Shell C4183-2 2.39 E 10 - 10 F Plant Specifie 37 Table 0.06 0.61 R2707-3 1 ower C4499-2 2.34E l9 50V Plant Specific 26.139 Calculated 0.07 0.59 Shell R 2 708- 1 Lowcr 04472-1 2.39 E 19 10*F Plant Specilie 31 Table 0.05 0.57 Shell R2708-2 1.ower C4499 1 2.39 E l o 20*F Plant Specific 44 Table 0.07 0.59 Shell R2708 3 Int. and 90077 2.39 E 19 -60

• F Plant Specilie 29.7 Table 0.04 0.06 l ower Shell A nal WelJs i G2.01  !

Int. to u0077 2.19E19 _t,0 T Plant Specifie 56.144 Calculated 0.04 0.07 l 1.ou er Shell Circ. Weld l'.3. I 4

!Mr1GEO l Chenucal composition and IRTndt are troin Table A 3 of R. R Lott, et. al. " Analysis of Capsule U Irom the Union Electric Company Callaway Unit i Reactor Vessel Radiation Surseillance Program." WCAP ll374, Revision I, Westinghouse Electric Corporation, i Pittsburgh, PA 15230. June 1987. '

Iluence data are f rom Table 6-14 of WCAP 1294e> and December 18.199 t. Letter from D. F. Schnell (UECo) to USNRC Document Control Desk. subi ect: Revision to Teshmcal Specification 3/4.4.9 Pressure Temperature Limits.

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_ ENCLOSURE 2 Summary File fnr l'pper Shelf Energy Plant Name fieltline ident, lleat No. Material Ty pe 1/4T USE at 1/4T Neutron t'nirrad. Method EOL Fluence at USE of Determin.

EOl. Unirrad. USE Callaway i Int. Shell C4144 1 A 53111-1 62 1.31 E l 9 78 Direct R 2707- 1 I 01.:

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2024 Int. Shell C4181 1 A 53111-1 79 1.31E19 100 Direct R2707-2 Int. Shell C4383-2 A 51311-1 79 1.3lE19 49 Direct R2707 3 l.ower Shell C4499 2 A 53311 1 65 1.31El9 82 Direct R2708-l lower Shell C4472-1 A 513[1 1 83 1.31E19 105 Direct R2708 2 Imwer Shell C4499-1 A 55311 1 80 1.31E19 101 Direct R2708-1 Int. and lower 90077 L inde 0091 113 1.31El9 143 Direct Shell Axial L.ot No, 0842 Welds, G2.03 SAW Int. to I.nw er 90077 Lmde 124, 87 1.31E19 112 Direct Shell Cire. I ot No. 1061 Weld, E3.14 SAW lie111E0W USE data are from Table A-1 of R.G. lett et. al, " Analysis of Capsule il from the Umon Electrie Company Callaway Unit i Reactor Venel Radiation Sur$cillance Program." WCAP-11174. Resiuon I, Westmghouse :lectrie Corporation, Pittsburgh, PA 15230 June 1987.

I'luence data are from Table 6-14 of WCAP-12946 and December 18, 1991, Letter from D. F. Sshnell(UEco) to USNRC Document Control Desk, subiect: Resiuon to Tethmeal Specification 3/4.4.9 Pressure Temperature Limits.

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