ML20054J484
| ML20054J484 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/23/1982 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Crouse R TOLEDO EDISON CO. |
| References | |
| NRR-821920, TAC-48349, NUDOCS 8206290083 | |
| Download: ML20054J484 (4) | |
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L PDR AE0D ORB #4 Rdg IE Docket No. 50-346 DEisenhut ACRS-10 ADe Agazio Gray File RIngram Tfornstein EBlackwood fir. Richard P. Crouse TNovak Vice President, Nuclear WJohnston Toledo Edison Company JKnight Program Support Branch NRR-821920 Edison Plaza 300 fladison Avenue Toledo, Ohio 43652
Dear Mr. Crouse:
SUBJECT:
AUXILIARY FEEDWATER HEADER REPAIR - REQUEST FOR ADDITIONAL INFORMATION As a result of certain in-service inspections at the Davis-Besse facility, damage to the auxiliary feedwater headers in both once-through stean generators was discovered. Toledo Edison Company reported the nature of the damage and general plans for repair in Licensee Event Report No.82-019 Revision 1.
Toledo Edison Company also net with the Commission staff on May 21, 1982 to discuss the results of inspections and plans for repair.
Uo have reviewed the information contained in the above referenced LER along J
with that presented in the meeting on May 21, 1982 and find that additional information is required for us to complete our review. Therefore, pursuant to 10 CFR 50.54(f), we request that you provide us your responses to the following itens, no later thsa 10 days prior to scheduled restart.
Your responses must be submitted to the NRC, signed under oath or affirnation, to enable the Connission to detemine whether or not your license shall be rodified, suspended, or revoked.
1.
Provide a detailed description of the repairs and modifications to the auxiliary feedwater systen. Describe how the as modified system compares to the auxiliary feedwater design used previously in other operating Bf.W plants. Conpare the expected performance of the modified design to that of the original design and of earlier B&W units.
2.
Describe the program to identify and recover loose parts resulting froa previous damage and those that may be produced during repair. Describe your loose parts nonitoring system (s) and discuss detection capability partic-ularly with reference to any known or potential loose parts.
If loose parts will exist after operation, evaluate the safety consequences.
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Mr. Richard P. Crouse 3.
Describe the types of pre-repair inspections performed on the steam generator shell, shroud and header and discuss the results. Supply a drawing or drawings which show the limits of each inspection performed.
Identify the criteria used to evaluate the soundness of the header and discuss, where applicable, the ability of the renote visual inspections to detect flaws with respect to the acceptance criteria.
4.
Describe the original criteria for mininum acceptable clearances titween the AFW header and supports and the peripheral tubes, and relate this to the clearances that will exist after repairs are completed. If clearances af ter repair are less than the minimum acceptable for the original design, provide the necessary analyses to justify operation under normal, transient, and accident conditions.
5.
Discuss your criteria and procedures for plugging and stabilizing of peripheral tubes.
6.
Provide an analysis which demonstrates acceptable results when maximum expected forces are applied to the stabilized header considering normal, transient, and accident conditions.
7.
Describe your acceptance criteria for all welds used to stabilize or reinforce the header. Describe in detail the inspection progran to be followed.
8.
What inspections will be performed following the stabilization of the header to ensure that distortion from welding does not reduce clearances between tubes and the header below the mininun acceptable?
9.
Provide an analysis of AFW flow induced tube vibration for the modified AFV design.
- 10. Describe your plans for revision of the ISI/IST program to include steam cenerator internals on the steam side.
- 11. Describe the post-repair startup test and inspection progran, including water hamer tests, to be conducted prior to the resumption of power operations.
Since your proposed repairs include changes in the facility, which involve an un-reviewed safety question, HRC approval will be required prior to facility operation.
The reporting requirements contained in this letter affect fewer than ten respondents; therefore, 0t16 clearance is not required under P.L.96-511.
Sincerely,,.
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fir. Richard P. Crouse.
4 3.
Present, in detail, the types of pre-repair inspections perfomed on the stean generator shell, shroud and header and discuss the results. Supply a drawing or drawings which show the limits of each inspection performed.
Identify the criteria used to evaluate the soundness of the header and discuss, where applicable, the ability of the remote visual inspections to detect flaws with respect to the acceptance criteria.
f 4.
Provide the original minimum acceptable clearances between the AFW header and su:) ports cad the peripheral tubes and relate this to the clearances that will exist after repairs are completed.
If clearances after repair are less than the minimum acceptable for the original design, provide the necessary analyses to justify operation under normal, transient, and accident conditions.
5.
Discuss your plans for plugging and stabfif zing of peripheral tubes including details of how any tube. stabilization will be acconplished.
l 6.
Provide an analysis of the r'aximun forces on the stabilized header considering nomal, transient, and accident conditions.
7.
Describe your acceptance criteria for all welds used to stabilize or reinforce the header. Describe in detail the inspection progran to be followed.
8.
What inspections will be perforced following the stabilization of the header to ensure that clearances betseen tubes and the header have not i
bacn reduced below the mininua acceptable due additional distortation f roa uel ai ng.
9.
Provide an analysis of Anf flow induced tube vibration for the nodified ARI design.
- 10. Describe your plans for revision of the ISI/IST program to include steam generator internals on the steam side.
l
- 11. Describe your plans for conducting water hamer tests on the modified AFW
- systen, i
The reporting requirements centained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Carrell G. Eisenhut, Director Division of Licensing
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' Toledo Edison Company cc w/ enclosure (s):
Mr. Donald H. Hauser Esq.
U.S. Nuclear Regulatory Comission The Cleveland Electric Resident Inspector's Office Illuminating Company 5503 N. State Route 2 P. O. Box 5000 Oak Harbor, Ohio 43449 Cleveland, Ohio 44101 Mrs. Julia Baldwin, Libr'arian Gerald Charnoff, Esq.
Government Documents Collection Shaw, Pittman, Potts William Carlson Library and Trowbridge University of Toledo 1800 M Street, N.W.
2801 W. Bancroft Avenue Washington, D. C.
20036 Toledo, Ohio 43606 Paul M. Smart, Esq.
Fuller & Henry 30011adison Avenue P. O. Box 2083 Regional Radiation Representative Toledo, Ohio 43603 EPA Reaion V 230 South Dearborn Street Mr. Robert B. Borsum Chicago, Illinois 60604 Babcock & Wilcox Nuclear Power Generation Division 7910 Woodmont Avenue, Suite 220 Bethesda,11aryl and 20814 Ohio Department of Health ATTN:
Radiological Health Program Director P. O. Box 118 President, Board of County Columbus, Ohio 43216 Commissioners of Ottawa County Port Clinton, Ohio 43452 Attorney General Department of Attorney General 30 East Broad Street l
Columbus, Ohio 43215 Harold Kahn, Staff Scientist l
Power Siting Commission 361 East Broad Street Columbus, Ohio 43216 Mr. James G. Keppler, Regional Administrator U. S. Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Ted Myers Manager, Nuclear Licensing Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652