ML020170490
| ML020170490 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/16/2002 |
| From: | Jack Cushing NRC/NRR/DLPM/LPD4 |
| To: | NRC/NRR/DLPM/LPD4 |
| Cushing J, NRR/DLPM,415-1424 | |
| Shared Package | |
| ml020170498 | List: |
| References | |
| TAC MB3574 | |
| Download: ML020170490 (6) | |
Text
January 16, 2002 LICENSEE:
Energy Northwest FACILITY:
Columbia Generating Station
SUBJECT:
SUMMARY
OF MEETING WITH ENERGY NORTHWEST ON DECEMBER 17, 2001, TO DISCUSS THE ALTERNATE SOURCE TERM LICENSE AMENDMENT REQUEST FOR THE COLUMBIA GENERATING STATION (TAC NO. MB3574)
On December 17, 2001, a public meeting was held at the NRC Headquarters office in Rockville, Maryland, between Energy Northwest and the NRC staff. The list of attendees is enclosed.
The purpose of the meeting was to brief the staff on the alternate source term (AST) license amendment request for the Columbia Generating Station. The slides are available in ADAMS under accession number ML013540048.
Energy Northwest submitted a license amendment request on December 3, 2001, to use an AST for the Columbia Generating Station. Energy Northwest stated that the use of an AST justifies the following changes to the technical specifications (TS) surveillance requirements (SR).
SR 3.6.1.3.10 - Increase secondary containment bypass leakage from.74 standard cubic feet per hour to.04 percent per day.
TS 3.6.1.8 - Delete the main steam line leakage control system.
TS 3.6.4.1 - Delete secondary containment applicability during movement of irradiated fuel and core alterations.
SR 3.6.4.1.1 - Change the requirement to verify secondary containment vacuum.
SR 3.6.4.1.4 - Delete secondary containment drawdown time surveillance.
SR3.6.4.1.5 - Specify that each standby gas treatment subsystem maintain secondary containment vacuum greater than or equal to.25 inches of vacuum water gauge with an in-leakage flow rate of 2240 cubic feet per minute (CFM).
TS 3.6.4.2 - Delete secondary containment isolation valve applicability during movement of irradiated fuel and core alterations.
TS 3.6.4.3 - Delete standby gas treatment system applicability during the movement of irradiated fuel and core alterations.
SR 3.6.4.3 - Add the requirement that the standby gas treatment system reaches greater than or equal to 5000 CFM in less than or equal to 2 minutes.
TS 5.5.7 - Increase standby gas treatment flow rates.
Energy Northwest then discussed their simplified approach. All the accident analyses except the main steam line break (MSLB) conform to Regulatory Guide (RG) 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors."
To assess effluent dispersion in the atmosphere, the MSLB accident analysis uses a buoyant steam bubble model not addressed by RG 1.183. The submittal did not use suppression pool scrubbing, aerosol impaction, enhanced drywell spray credit, enhanced steam line deposition credit, MAAP code containment thermal-hydraulic analysis or reduced iodine release.
The control room dose was calculated using the unfiltered in-leakage based on measured values from a tracer gas test performed at the Columbia Generating Station.
The staff said that it would be helpful to have the following information:
meteorological data used to develop the atmospheric dispersion factors; additional information to support the buoyant steam bubble model; and calculation used for pH control in the suppression pool.
Energy Northwest said that they would submit the information.
The staff said that they would issue requests for additional information by March 2002, with an expected response of 30-60 days depending on the complexity of the questions. Energy Northwest stated that there is a great deal of work to be done after the amendment is approved to fully implement the change. The staff said that the amendment would be effective the date of issuance but the implementation period would be sufficient for Energy Northwest to make the changes.
/RA/
Jack Cushing, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
List of Meeting Attendees cc w/encl: See next page Energy Northwest then discussed their simplified approach. All the accident analyses except the main steam line break (MSLB) conform to Regulatory Guide (RG) 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors."
To assess effluent dispersion in the atmosphere, the MSLB accident analysis uses a buoyant steam bubble model not addressed by RG 1.183. The submittal did not use suppression pool scrubbing, aerosol impaction, enhanced drywell spray credit, enhanced steam line deposition credit, MAAP code containment thermal-hydraulic analysis or reduced iodine release.
The control room dose was calculated using the unfiltered in-leakage based on measured values from a tracer gas test performed at the Columbia Generating Station.
The staff said that it would be helpful to have the following information:
meteorological data used to develop the atmospheric dispersion factors; additional information to support the buoyant steam bubble model; and calculation used for pH control in the suppression pool.
Energy Northwest said that they would submit the information.
The staff said that they would issue requests for additional information by March 2002, with an expected response of 30-60 days depending on the complexity of the questions. Energy Northwest stated that there is a great deal of work to be done after the amendment is approved to fully implement the change. The staff said that the amendment would be effective the date of issuance but the implementation period would be sufficient for Energy Northwest to make the changes.
/RA/
Jack Cushing, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-397
Enclosure:
List of Meeting Attendees cc w/encl: See next page DISTRIBUTION: See attached list ADAMS ACCESSION NO.: ML020170490 NRC-001 MEETING NOTICE: ML013380023 PACKAGE: ML020170498 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME JCushing EPeyton SDembek DATE 1/15/02 1/15/02 1/16/2002 OFFICIAL RECORD COPY
Columbia Generating Station cc:
Mr. Greg O. Smith (Mail Drop 927M)
Vice President, Generation Energy Northwest P. O. Box 968 Richland, WA 99352-0968 Mr. Albert E. Mouncer (Mail Drop 1396)
Chief Counsel Energy Northwest P.O. Box 968 Richland, WA 99352-0968 Ms. Deborah J. Ross, Chairman Energy Facility Site Evaluation Council P. O. Box 43172 Olympia, WA 98504-3172 Mr. D. W. Coleman (Mail Drop PE20)
Manager, Regulatory Affairs Energy Northwest P.O. Box 968 Richland, WA 99352-0968 Mr. Paul Inserra (Mail Drop PE20)
Manager, Licensing Energy Northwest P.O. Box 968 Richland, WA 99352-0968 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavilion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Chairman Benton County Board of Commissioners P.O. Box 69 Prosser, WA 99350-0190 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 69 Richland, WA 99352-0069 Mr. Rodney L. Webring (Mail Drop PE08)
Vice President, Operations Support/PIO Energy Northwest P. O. Box 968 Richland, WA 99352-0968 Thomas C. Poindexter, Esq.
Winston & 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, WA 98504-3113 Ms. Lynn Albin Washington State Department of Health P.O. Box 7827 Olympia, WA 98504-7827 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
LIST OF MEETING ATTENDEES ALTERNATE SOURCE TERM MEETING DECEMBER 17, 2001 ENERGY NORTHWEST Douglas Coleman Rod Webring Bruce Boyum NRC Jack Cushing Paul Shemanski Stephen Dembek Mark Blumberg Kris Parczewski Richard Lobel Leta Brown POLESTAR James Metcalf Fred Hennion
DISTRIBUTION FOR MEETING
SUMMARY
WITH ENERGY NORTHWEST ON DECEMBER 17, 2001 Dated: January 16, 2002 Hard Copy:
PUBLIC PDIV-2 R/F RidsNrrPMJCushing RidsNrrLAEPeyton E-Mail:
RidsNrrDlpm (JZwolinski/TMarsh)
RisNrrDlpmLpdiv (SRichards)
RidsNrrLAEPeyton MBlumberg RLobel LBrown KParczewski PShemanski BJones, RIV RidsOgcRp RidsAcrsAcnwMailCenter DMcCain