ML17292B674
| ML17292B674 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/28/1999 |
| From: | Jack Cushing NRC (Affiliation Not Assigned) |
| To: | Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| TAC-M96928, NUDOCS 9906040055 | |
| Download: ML17292B674 (5) | |
Text
Hay 28, 1999 Mr. J. V. Parrish Chief Executive Officer Washington Public Power Supply System P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONALINFORMATION(RAI) FOR THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 (WNP-2) (TAC NO. M96928)
Dear Mr. Parrish:
The NRC staff has reviewed your amendment request pertaining to secondary containment and standby gas treatment drawdown time dated October 15, 1996, and supplemented by letters dated December 4, 1997, and April 12, 1999. As a result of the review, the staff has determined that additional information is needed to complete the review. The information needed is detailed in the enclosure.
The enclosed request was discussed with Mr. Arbuckle of your staff on May 20, 1999. A mutually agreeable target date of July 16, 1999, was established for responding to the RAI.
Ifcircumstances result in the need to revise the target date, please call me at your earliest opportunity at (301) 415-1424.
Sincerely, is/
Jack vushing, Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
Supplemental Request for Additional Information cc w/encl: See next page DISTRIBUTION:
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i Mr. J. V. Parrish Chief Executive Officer Washington Public Power Supply System P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968 May 28, 1999
SUBJECT:
SUPPLEMENTAL REQUEST FOR ADDITIONALINFORMATION(RAI) FOR THE WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 (WNP-2) (TAC NO. M96928)
Dear Mr. Parrish:
The enclosed request was discussed with Mr. Arbuckle of your staff on May 20, 1999. A mutually agreeable target date of July 16, 1999, was established for responding to the RAI.
Ifcircumstances result in the need to revise the target date, please call me at your earliest opportunity at (301) 415-1424.
Sincerely, The NRC staff has reviewed your amendment request pertaining to secondary containment and standby gas treatment drawdown time dated October 15, 1996, and supplemented by letters dated December 4, 1997, and April 12, 1999. As a result of the review, the staff has determined that additional information is needed to complete the review. The information needed is detailed in the enclosure.
Docket No. 50-397
Enclosure:
Supplemental Request for Additional Information ccw/encl: See next page Jack Cushing, Project Manager, Section 2 Project Directorate IV& Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation
Nuclear Project No. 2 CC:
Mr. Greg O. Smith (Mail Drop 927M)
Vice President, Generation Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352-0968 Mr. Albert E. Mouncer (Mail Drop 1396)
Chief Counsel Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352-0968 Ms. Deborah J. Ross, Chairman Energy Facility Site Evaluation Council P. O. Box 43172 Olympia, Washington 98504-3172 Mr. D. W. Coleman (Mail Drop PE20)
Regulatory Affairs Manager Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352-0968 Mr. Paul Inserra (Mail Drop PE20)
Manager, Licensing Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower 8 Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Chairman Benton County Board of Commissioners P.O. Box 69 Prosser, Washington 99350-0190 Senior Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 69 Richland, Washington 99352-0968 Mr. Rodney L. Webring (Mail Drop PE08)
Vice President, Operations Support/PIO Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352 Perry D. Robinson, Esq.
Winston 8 Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Mr. Bob Nichols Executive Policy Division Office of the Governor P.O. Box 43113 Olympia, Washington 98504-3113
SUPPLEMENTAL RE VEST FOR ADDITIONALINFORMATION WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO. 2 NP-2 DOCKET NO. 50-397 What atmospheric dispersion factors used in this review have been previously reviewed and approved by the NRC? Ifthese dispersion factors have been previously reviewed and approved, please identify or provide the documents that approved them. Ifthey have not been reviewed and approved, please provide the calculations or the data and assumptions used to calculate these values.
Provide more detail of the radiological modeling of the standby gas treatment system.
Is the following table an accurate description of your model? Ifso, please provide the basis for this model. Ifthis is not an accurate description please provide the timing, filter efficiency and flow rates assumed and the bases for this model.
Time 0-20 minutes 20 min-720 hr 0
98.7%
5014'cfm 5014 cfm Filter Efficienc Assumed Flow Rate Provide more detail of the modeling of the secondary containment bypass in your radiological model for the loss-of-coolant accident (LOCA). The WNP-2 containment bypass leakage rates are specified in terms of standard cubic feet per hour. To model these activity releases under design basis accident LOCA conditions, these leakage rates are typically adjusted to account for the post-accident pressure and temperature conditions inside the drywell and wetwell ~ Please describe how your model does or does not address this.
The impact of the proposed increased containment drawdown time and secondary containment bypass leakage has been incorporated in the LOCA accident dose analysis presented in the submittal.
Please address the impact of these changes on your other design basis radiological accidents.
Provide adequate justification for only addressing the LOCA. Please address both the control room and offsite doses.
ENCLOSURE