ML20101J250
| ML20101J250 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/23/1992 |
| From: | Rhodes F WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ET-92-0128, ET-92-128, GL-92-01, GL-92-1, NUDOCS 9207010029 | |
| Download: ML20101J250 (5) | |
Text
{{#Wiki_filter:. / WeLF CREEK ~ NUCLEAR OPERATING CORPORATION Forrest T. Rhodes. Vice President : Engineering & TechnicaI 5ervtces June 23, 1992 ET 92 0128 U. S. hur sar Regulatory Commission ATTN: Document Control Desk 1 Mail Station Pl-137 Washington, D. C. 20555
Subject:
Docket No. 50-*82: Respon=e to Gencric Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity" Gentlemen:. The purpose of this letter is to tranemit Wolf Creek Nuclear Operating i Corporation's (WCNOC) response to Generic Letter 92-01, Revision 1. This Generic ~ Letter requested information to determine if licensees are meeting commitments and license conditions regarding 10 CFR 50. 60, 10 CFR 50.61, and Generic Letter 88-11. The attachment to this letter provides the requested information on the Wolf Creek Generating Station (WCGS) reactor vessel and material surveillance program. If you have any questions concernin3 this matter, please contact me or Mr. S. G. Widemarr of my s ta f f. Very truly yours, Y f I. Forrest T. Rhodes -Vice President-Engineering & Technical Services FTR/aem i Attachment- .cci A. T. Howell (NRC), w/a l
- R. D. Martin-(NRC), w/a--
l G. A. Pick (NRC), w/a l W. D. Reckley (NRC), w/a N A 0 u bl} Uf-{tf-9207010029 920623 .O Box 411 i Burlington.' KS 66839 i Phone:(316) 364 8831 $/ NU U
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o 4 STATE OF KANSAS } } SS COUNTY OF COF m ) Forrest T. Rhodes, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering and Technical Services of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows toe content thereof; that he has executed that same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are
- ue and correct to the best of his knowledge, information and belief.
f', fj y} l A b#~ I"% / By Forrest T. Rhedes Vice President Engineering & Technical Services SUBSCRIBED and sworn to before me this 23 day of w
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-. -. ~ - - Attachment to ET 92-0128 Page i of 3 Wolf Creek CeneratinR Station Response to Generic Letter 92-01 Rev. 1 a Ovestion 1: Certain addressees are requested to provide the following information regarding Appendix H to 10 CFR Part 50: Addresseen 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 (see Enclosure 2), are requested to describe actionc taWn or to be taken to ensure compliance with Appendix.H to 10 C'/R Part 50. Addressees who plan to revise the surveillance. program to meet Appendia H to 10 CFR Part 50 are requested to indicate when-the revised. program will be submitted to 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 to request an exemption from Appendix H to 10 CFR Part 50 under 10 CFR 50.60(b). , Response: 1. The Wolf Creek Cenerating Station (WCGS) surveillance program is designed to cover-the 40-year design life of the reactor vessel. The surveillance program is based on ASTM E-185-79 which complies with Appendix H to 10 CFR Part 50 Letter KMLNRC 82-235 (Reference - 1) transmitted WCAP 10015 to the NRC and provides a description of the surveillance program, a description of the material
- involved, the specimen and capsule design and fabrication, and the preirradiated test results.
guestior. 2: Certain addressees are requested to provide the following information regarding Appendix G to 10.CFR Iart 50: a. Addressees 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 4 Legulatory Guide 1.99.-Ravision 2, are requested to provide to the NRC the Charpy upper sh ut energy predicted for Decemoer 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. b. Addressees whose reactor vessels were constructed-to an ASME Code eerlier than the Summer 1972 Addenda of - the 1971 Edition are i requested to describe the consideratien given to the follcwing !~ material properties in their evaluations performed pursuant to 10 ( CFR 50.61 and Paragraph III.A of 10 CFR Part 50, Appendix G: 1 ( :-. i _., ~, s- =d
m Attachment to'ET 92-0128 l Page 2 of 3 (1) - th e results from all Charpy and drop weight tests fcr all unirradiated beltline materials, the unirradiated reference temperature for each beltline material, and the method of determining the unirradiated reference temperature f rom 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; (4) the heat number for each surveillance plate or forging and the-heat number of wire and flux lot number used to fabricate the surveillance veld; the chemical com in particular the weight in percent of copper, position, (5)
- nickel, phosphorous, and sulfur for each beltline and surveillance material; and
- (6) the heat number of the wire used for determining the weld metal-chemical composition if different than Item (3) above.
Response
2.a. The Charpy upper shelf energy for WCGS's reactor vessel is predicted to be greater than 50 foot-pound at the end of WCGS 's-operating license using the guidance in Paragraph C.1.2 or C.2,9 in Proposed Revisicn 2 to - Regulatory Guide 1.99, dated February 10, 1986. This conclusion was based on WCGS's first material - specimen analysis results (capsule "U"). Analysis of capsule "U" utilized the. guidance of Proposed Revision 2 to Regulatory Guide 1.99. Letter ET 87-0346 ' (Reference 2) submitted the results of this analysis to the NRC. In response to Generic Letter 88-11, letter WM 88-0290 (Reference
- 3) submitted the results of a comparisan of Proposed Revision 2 to Revision 2 of Regulatory Guide 1 S.
It was concluded that - Proposed Revision 2.was more conse~ ative when calculating DRT due to a change in attenuation f c when compared to Revision T ND 2 to Regulatory Guide 1.99. Surveillance capsule "Y" was the second capsule removed f rom the WCGS reactor vessel, and was trmoved November 5, 1991 duting Refueling Outage V. 10 CFR 50 A!pendix H.III.A requires-WCNOC to-submit the results of capsule "Y to the NRC by November 5, 1992. - Analysis of capsule "Y" will r:111ze the guidance contained in Revision 2 to Regulatory Gutt.e 1.99 as was committed to in Reference 3. 2.b. The WCGS reactor vessel was manufactured to the 1971 Edition with Addenda through Winter 1972. Reactor vessel material and preirradiation material properties are identified in WCAP-10015 which was transmitted to the NRC by Reference 1. l i l 1 W 4-gn -- p a w w m-T'--- Y-T T-'
i Attachment to ET 92-0128 Page 3 of 3 -Question 3: . 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.ecirculation suction temperature) below 525 F were considered. In particular licensees are requested to describe consideration given to de t t. c mining 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 standard deviations predicted by Regulatory -Guide 1.99, Revision 2, or if a measured decrease in Charpy upper shelf energy exceeds the value predicted using the guidance in Paragraph C.1.2 in Regulatory Guide 1.99, Revision 1, the licensee is requested to report the information and describe the effect of the surveillance results on the - ad justed reference temperature and Charpy upper shelf energy for each beltline material as predicted fot-December 16, 1991, and for the end of its current license. Resnonse 3.a. WCGS Technical Specifications prohibit the reactor coolant system operating loop temperature to fall below 551 F, except during the performance of physics tests. At 02 reactor power the teactor coolant temperature T and Tcold are identical-at 557'F. As ot power is increased, hot rises to 618.2*F and Tcold rises to 558.8 F. 3.b, WCMOC utilized Proposed Revision 2 to Regulatory Guide 1.99 to perform the analysis of capsule "U". Analysis of capsule "Y" and future analyses will utilize the guidance of Revision 2 to Regulatory Guide 1.99, as was committed to in Reference 3. 3.c. No data from the WCGS surveillance program have exceeded the mean-plus-two standard deviation bound predicted by Proposed Revision 2 to Regulatory Guide 1.99. Test results are within the values predicted by the Proposed Regulatory Guide.
References:
1, 1) Letter KFiLNRC 82-235, dated August 11, 1982 f rom G. L. Koester (KG&E) to H. R. Denton (NRC) 2) . Le t t e r _ ET E7-0346, dated November 4, 1987 from J. A. Bailey (WCNOC) to NRC 3) Letter WM 88-0290, dated November 7, 1988 from 5. D. Withers (WCNOC) to NRC m _.,,}}