ML19282B133
| ML19282B133 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 02/16/1979 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7903090081 | |
| Download: ML19282B133 (5) | |
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NUCLEAR REGULATORY COMMisslON
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.g WASHING TON. D. C. 20555 FEB 1 G 1979 Docket No: 50-358 Mr. Earl A. Borgmann Vice President - Engineering Cincinnati Gas & Electric Company P. O. Box 960 Cincinnati, Ohio 45201
Dear Mr. Borgmann:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - WM. H. ZIMMER, UNIT N0. 1 In order that we may continue our review of your application for a license to operate the Zimer Nuclear Power Station, Unit No.1, your responses to the enclosed positions (and requests for additional information) are needed.
The positions (and requests) are based upon infonnation contained in your application as amended through Revision 52 and your responses to our previous requests.
We will need your responses to these positions (and requests) by March 15, 1979.
If you cannot meet this date, please advise us within two weeks of receipt of this letter of your date for complete response.
Please contact us if you desire information or clarification regarding the enclosu re.
Sincerely, q&
,i. /
John F. Stolz, Chief tjght Water' Reactors Branch No.1 L
Division of Project Management
Enclosure:
Request for Additional Information cc:
See next page 79030900W/
as FEB 161979 Mr. Earl A. Borgmann cc: Troy B. Conner, Jr., Esq.
David B. Far.khauser, PhD Conner, Moore & Corber 3569 Nine Mile Road 1747 Pennsylvania Avenue, N. W.
Cincinnati, Ohio 45230 Washington, D. C.
20006 Thomas A. Luebbers, Esq.
Mr. William J. Moran Cincinnati City Solicitor General Counsel Room 215, City Hall The Cincinnati Gas and Electric Cincinnati, Ohio 45202 Company P. 0. Box 960 Mr. Stephen Schumacher Cinnati, Ohio 45201 Miami Valley Power Project P. O. Box 252 Mr. William G. Porter, Jr.
Dayton Ohio 45401 Porter, Stanley, Arthur and Platt Ms. Augusta Prince, Chairperson 37 West Broad Street 601 Stanley Avenue Columbus, Ohio 43215 Cincinnati, Ohio 45226 Mr. Peter H. Forster, Vice President Charles Bechhoefer, Esq., Chai rman Energy Resources Atomic Safety & Licensing Board The Dayton Power and Light Panel Company U. S. Nuclear Regulatory Com. mission P. O. Box 1247 Washington, D. C.
20555 Dayton, Ohio 45401 J. Robert Newlin, Counsel The Dayton Power and Light Company P. O. Box 1247 Dayton, Ohio 45401 Mr. James D. Flynn Manager, Licensing Environmental Affairs The Cincinnati Gas and Electric Company P. 0. Box 960 Cincinnati, Ohio 45201 Mr. J. P. Fenstermaker Senior Vi.ce President-Operations Columbus and Southern Ohio Electric Company 215 North Front Street Columbus, Ohio 43215
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ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION WM. H. ZIMMER ROUND-TWO QUESTIONS Introduction This enclosure consists of the twenty-second in a series of positions (and requests for additional information). We will need your response to them in order to complete our safety evaluation of your Zimmer OL application. The position (and requests) are in the area of:
121.0 Materials Engineering It will be helpful to us if your responses are in a " Position and Response" format using the same number designation as the position.
The first number designated the review area and the second (in parentheses) designated the associated section of the FSAR. Of course, your responses should include revision to the FSAR wherever appropriate.
NOTE: We have reviewed the information contained in Revision 52 of your FSAR regarding fracture toughness to determine if you comply with the requirements of 10 CFR, Part 50, Appendices G and H.
We will need adequate response to the enclosed requests for additional infor-mation to determine the degree of compliance to Appendices G and H and to evaluate possible areas of non-compliance with these appendices.
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121-1 121.0 MATERIALS ENGINEERING BRANCH - MATERIALS INTEGRITY SECTICN 121.15 In Amendment No. 83 of the FSAR, a factor of 2'F/ft-lb was used to adjust the longitudinal CVN data to the 50 ft-lb level.
It is stated that this estimation and the 30*F adjustment for specimen orientation was based on data from WRC Bulletin 217
" Properties of Heavy Section Nucle ~ar Reactor Steels," ZPS-1, and other vessel fracture toughness data. State explicitly in the FSAR the procedure used to obtain the 2*F/ft-lb and 30 F estimations from the data. Also provide any data that was used as a basis for these estimates, other than that contained in WRC 217.
121.16 Table 5.2-9, " Appendix G Matrix for Zimmer," indicates that the weld test specimens were not necessarily made from the same heat of base plate as required by Appendix G.
In addition, the FSAR does not indicate the weld wire and flux used in the fabrication of the test specimens. Provide the following information for the weld test specimens:
(1) Material specification, CVN data and heat number for test plate.
(2) Weld wire.
(3) Weld flux.
(4) Welding process.
121.17 For the main steam isolation valves and main steam safety relief valves that were procured to early ASME Codes without fracture toughness requirements, identify the pressure retaining valve materials and estimate the material toughness and the extent of compliance with the requirements of Appendix G.
Provide any available typical data.ind/or representative data from the literature to justify t. e toughness values used.
121.18 The FSAR indicates that the upper shelf energy was not deter-mined for the reactor vessel beltline materials. The response to Question 121.8 in Amendment No. 83 does not contain the required technical justification and data to demonstrate that the material upper shelf fracture toughness complies with the requirements of paragraph IV.B of Appendix G 10 CFR Part 50.
Provide adequate techr.ical data and analyses to demonstrate that the beltline materials will maintain adequate upper shelf fracture toughness through end of life.
m 121-2 121.19 Table 5.2-10. " Appendix H Matrix for Zimmer," indicates that:
(1) The requirements of paragraph II.B of Appendix H are not met in that replacement specimens are not from the limiting beltline material.
(2) The requirements of paragraph II.C.1 of Appendix'H are not met in that specimens may not have been taken from along-side specimens required by Section III of Appendix G and that transverse Charpy V-notch samples may not be employed.
The following information is required for us to evaluate compliance with these sections of Appendix H:
(1) Identify the plate and weld materials contained in the surveillance program.
(2)
Identify the specimen orientations.
(3) Correlate the surveillance samples with the limiting material in the reactor vessel.
121.20 Table 5.2-10 of FSAR Amendment No. 83 indicates that the requirements for the fourth capsule needed for a vessel with an adjusted reference shift less than 200 F at EOL cannot be met.
However, the FSAR also indicates that the limiting beltline plate has an initial RT of 12'F and a predicted conservative RT shift of 73 F.
Tb[wouldresultinanEOLadjusted reNTrence temperature of less than 100*F at EOL. Provide a clarification of this apparent discrepancy and indicate the appropriate number of surveillance capsules for ZPS-l in accordance with Section II.C.3 of Appendix H.
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