ML062760502
| ML062760502 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/04/2006 |
| From: | Wang A NRC/NRR/ADRO/DORL/LPLIV |
| To: | Ridenoure R Omaha Public Power District |
| Wang A, DORL/LPLIV, 415-1445 | |
| References | |
| TAC MD2864 | |
| Download: ML062760502 (4) | |
Text
October 4, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1: REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REPLACEMENT OF TRISODIUM PHOSPHATE (TAC NO. MD2864)
Dear Mr. Ridenoure:
By letter dated August 21, 2006, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit No. 1, Technical Specification Section 2.3(4), Trisodium Phosphate (TSP). The proposed change will replace the reactor containment building sump buffering agent from TSP to sodium tetraborate.
The U.S. Nuclear Regulatory Commission staff has reviewed OPPDs submittal and has determined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Matthews of your staff on October 2, 2006, and it was agreed that a response would be provided within 7 days of receipt of this letter.
If you have any questions, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
RAI cc w/encl: See next page
October 4, 2006 Mr. R. T. Ridenoure Vice President - Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 550 Fort Calhoun, NE 68023-0550
SUBJECT:
FORT CALHOUN STATION, UNIT NO. 1: REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REPLACEMENT OF TRISODIUM PHOSPHATE (TAC NO. MD2864)
Dear Mr. Ridenoure:
By letter dated August 21, 2006, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit No. 1, Technical Specification Section 2.3(4), Trisodium Phosphate (TSP). The proposed change will replace the reactor containment building sump buffering agent from TSP to sodium tetraborate.
The U.S. Nuclear Regulatory Commission staff has reviewed OPPDs submittal and has determined that additional information is needed to complete our review. A request for additional information (RAI) is enclosed. This request was discussed with Thomas Matthews of your staff on October 2, 2006, and it was agreed that a response would be provided within 7 days of receipt of this letter.
If you have any questions, please contact me at (301) 415-1445.
Sincerely,
/RA/
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
PUBLIC LPLIV R/F RidsRgn4MailCenter RidsOgcRp RidsNrrLALFeizollahi RidsNrrPMAWang RidsAcrsAcnwMailCenter RidsNrrDorlLpl4 ADAMS ACCESSION NO.: ML062760502 OFFICE LPL4/PM LPL4/LA DCI/CSGB/BC LPL4/BC NAME AWang LFeizollahi AHiser DTerao DATE 10/4/06 10/3/06 10/4/06 4/14/00 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION REGARDING CORE OPERATING LIMITS REPORT REFERENCES OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NUMBER 50-285 By letter dated August 21, 2006, Omaha Public Power District (OPPD) submitted an amendment request to revise the Fort Calhoun Station, Unit No. 1 (FCS), Technical Specification Section 2.3(4), Trisodium Phosphate (TSP). The proposed change will replace the reactor containment building sump buffering agent from TSP to sodium tetraborate.
The NRC staff has reviewed OPPDs submittal and has determined that the following additional information is needed to complete our review.
1.
Provide an electronic copy of the Pressurized-Water Reactor (PWR) Owners Group (PWROG) chemical model spreadsheet for FCS that shows the precipitates formed with the TSP buffer and the sodium tetraborate buffer.
2.
Page 3 of 8 of the summary report, Testing of Alternate Buffering Agents for Fort Calhoun Station, indicates that the corrosion rate of aluminum in solution buffered with sodium tetraborate is significantly higher than the corrosion rate in solution buffered with TSP. Table 1 in the summary report provides the PWROG chemical model predictions that show an equal amount of NaAlSi3O8 precipitate is predicted at FCS with sodium tetraborate and TSP buffered environments. Discuss why the predicted amount of aluminum-based precipitate is equal in these environments when the amount of dissolved aluminum in the containment pool would presumably be much greater with sodium tetraborate.
April 2006 Ft. Calhoun Station, Unit 1 cc:
Winston & Strawn ATTN: James R. Curtiss, Esq.
1700 K Street, N.W.
Washington, DC 20006-3817 Chairman Washington County Board of Supervisors P.O. Box 466 Blair, NE 68008 Mr. John Hanna, Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 310 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Ms. Julia Schmitt, Manager Radiation Control Program Nebraska Health & Human Services R & L Public Health Assurance 301 Centennial Mall, South P.O. Box 95007 Lincoln, NE 68509-5007 Mr. David J. Bannister, Manager Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Joe L. McManis Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
P.O. Box 550 Fort Calhoun, NE 68023-0550 Mr. Daniel K. McGhee Bureau of Radiological Health Iowa Department of Public Health Lucas State Office Building, 5th Floor 321 East 12th Street Des Moines, IA 50319