ML20101F070
| ML20101F070 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/16/1992 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-92-01, GL-92-1, ULNRC-2649, NUDOCS 9206240249 | |
| Download: ML20101F070 (7) | |
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Donald F. Schnell ON
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53 June 16,.1992 U.S. Nuclear Regulatory Commission
-ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
ULNRC-2649 CALLAWAY PLANT DOCKET NUMBER 50-483 REACTOR VESSEL STRUCTURAL INTEGRITY, 10 CFR 50,54 (f)
Reference:
NRC Generic Letter 92-01, Revision 1, dated March 6,1992 Attached please find Union Electric's response to NRC Generic Letter 92-01.
This response provides information which will enable NRC to verify.that Union Electric is complying with the current licensing basis regarding reactor vessel fracture toughness and material surveillance for the reactor coolant pressure boundary.
If you have any questions concerning this information, please contact us.
t' Very truly yours, t4 4
Donald F. Sc nell l$_fiD l
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STATE OF MISSOURI )
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t Donald F.
Schnell, of lawful age, being first duly sworn upon oath says that he is Senior Vice President-Nuc] ear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facta therein stated are true and correct to the best of his knowledge, information and belief.
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Schnell Senior Vice President Nuclear SUBS _CRIBED and sworn to before me this /MY day of dz/4 c 1992.
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!abl AEf PUHilC, SIAIE ~ Of MIMOVRI Mf COMMi%!0*' O.MRIS APFIL 22. 1993 ST. LOU;S COUhiY s
cc:
T. A.
Baxter, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N.
- Street, N.W.
Washington, D.C.
20037 Dr.
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Cermak CFA, Inc.
18225-A Flower Hill Way Gaithersburg, MD 2089-5334 R.
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' tief, teactor Project Branch 1 U.S.
Nuclear Regulatory Commission I
Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Bartlett Callaway Resident Office U.S.
Nuclear Regulatory Commission RR41 Steedman, Missouri 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 Manager, Electr'; Department Missouri 1unlic Service Commission P.O.
Box 360 Jefferson City, MO 65102 NUMARC Attn:
Kurt Cozens 1776 Eye Street, N.W.
Suite 300 Washington, D.C.
/
20006-2496
Attachment to ULNRC-2M9 UNION EkECTRIC RESPONSE TO CAMERl_C_ LETTER 92 01 Qu3D&Lon.1.
Certain addressees are requested to provide the following iniormation regarding Appendix H to CFR Part 50:
Addressees who do not have a surveillance program meeting ASTM E 185-73,
-79, or -82 and who do not have an integrated surveillance program approved by the NRC are requested to describe actions taken or to be taken to ensure compliance with Appendix H to 10 CFR Part 50.
Addressees who plan to revise the surveillance program to meet Appendix H to 10 CFR Part 50 are requested to indicate when the revised program will be submitted to O
the NRC staff for review.
If the surveillance program is not to be revised to meet Appendix H to 10 CFR Part 50, addressees are requested to indicate when they plan j
to request an exemption from Appendix H to 10 CFR Part 50 under 10 CFR 50.60(b).
Rep.ppnpe:
The radiation surveillance program for the Callaway reactor pressure vessel covers the 40-year vessel design life and was based on ASTM E185-73, " Standard Recommended Practice for Surveillance Tests f or Nuclear Reactor Vessels. "
This program complies with Appendix H to 10 CFR Part 50 as described in NUREG-0830 and NUREG-0830, Supplement 4 (Callaway Safety Evaluation Report and Supplement).
Refer to ULNRC-2537 (dated December 18, 1991) for additional discussion concerning the Callaway reactor vessel radiation surveillance program.
Qugp3 ion 1 Certain addressees are requested to provide the following information regarding.ppendix G to 10 CFR Part 50:
a.
Address 6es of plants for which the Charpy upper shelf energy is predicted to be less than 50 foot-pounds at the end of their licenses using the guidance in Paragraphs C.1.2 or C.2.2 in Regulatory Guide 1.99, Revision 2, are requested to provide to the NRC the Charpy upper shelf energy predicted for December 16, 1991, and for the end of their current license for the limiting beltline weld and the plate or forging and are requested to describe the actions taken pursuant to Paragraphs IV.A.1 or V.C of Appendix G to 10 CFR Part 50.
Page 1 of 4
Attachment to ULNRC-2649 b.
Addressees whose reactor vessels were constructed to an ASME Code earlier than tne Summer 1972 Addenda of the 1971 Edition are requested to describe the consideration given to the following material properties in their evaluations perfc.med pursuant to 10 CFR 50.61 and Paragraph III.A of 10 CFR Part 50, Appendix G:
(1) the results from all Charpy and drop weight tests for all unirradiated beltline materials, the unirradiated reference temperature for each beltline material, and the method of determining the unirradiated reference temperature from the Charpy and drop weight test; (2) the--heat treatment received by all beltline and surveillance materials; (3) the heat number for each beltline plate or forging and the heat number of wire and flux lot number used to fabricate each beltline weld; I4) the heat number for each surveillance plate or-forging and the heat number of wire and flux lot number used to faoricate the surveillance weld; (5)
-the chemical composition, in particular the weight
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in percent of copper, nickel, phosphorous, and sulfur for each beltline and surveillance material; and (6) the heat nn=her of the wire used for determining the weld metal chemical composition if different
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than Item (3) above.
Besnonse:
2.a. The Charpy upper shelf energy is predicted to be greater than 50 foot-pounds for the Callaway reactor pressure vessel at the end of the plant licence using the guidance in Regulatory Guide 1.99, Rev. 2, Paragraphs C.1.2 o_ C.2.2.
For the Callaway reactor vessel, the upper shelf energy (USE) of the weld metal and Heat-Affected-Zone (RAZ) metal has decreased the greatest amount (from 112 to 97 ft-lb and from 106 to 91 ft-lb, respectively).
The materials which have the lowest USE are Plate R2708-1 and the HAZ metal (both are 91 ft-lb).
Refer to ULNRC-2537 for additional results from the Cal]away reactor vessel surveillance program.
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Attachment to ULNRC-2649 2.b. The Callaway reactor vessel was constructed to ASME III, 1971 Edition through Winter 1972 Addenda, therefore, Question 2.b is not applicable to Callaway Plant.
OnM110tti:
Addressees are requested to provide the following information regarding commitments made to respond to GL 88-11:
a.
How the embrittlement effects of operating at an irradiation temperature (cold leg or recirculation suction temperature) below 525 *F were considered.
In particular 31censees are requested to describe consideration given to determining the effect of lower irradiation temperature on the reference temperature and on the Charpy upper shelf energy, b.
How-their surveillance results on the predicted amount of embrittlement were considered.
c.
If a measured increase in reference temperature exceeds the mean-plus-two riandard deviations predicted by Regulatory Guide J.)9, Rev'sion 2, or if a measured decrease in Charpy upper snelf energy exceeds the value predicted using the guidance in Paragraph C.1.2 in Regulatory Guide 1.99, Revision 2, the licensee is requested to report the information and describe the effect of the surveillance results on the adjusted reference temperature and Charpy upper shelf energy for each beltline material as predicted for December 16, 1991, and for the end of its current license.
EMAqnn:
3.a. Callaway Plant-Technical Specification 3/4.1.1.4 prohibits criticality below an average temperature of 551*F except for brief periods to perform core physics testing.
Extended plant operation below an average temperature of 551 F would constitute a violation of Technical Specifications and would-be a reportable event.
In addition, plant average temperature is routinely maintained in the programmed band, which by design, limits cold leg temperature to a value greater than 525*F.
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I Attachment to ULNRC-2649 3.b. Callaway Plant utilized the criteria defined in Regulatory Guide 1.99, Revision 2 to determine the credibility of surveillance data, in those cases where surveillance data was used.
Refer to ULNRC-2537 for additional discussion concerning the Callaway reactor vessel radiation surveillance program.
3.c. No data from the Callaway Plant reactor vessel radiation surveillance program have exceeded the mean-plus-two standard deviation bound predicted by Regulatory Guide 1.99, Revision 2.
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