ML061210471: Difference between revisions
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| number = ML061210471 | | number = ML061210471 | ||
| issue date = 05/16/2006 | | issue date = 05/16/2006 | ||
| title = | | title = License Amendment, Request to Change the Reactor Coolant System Leakage Detection Instrumentation Methodology | ||
| author name = Donohew J | | author name = Donohew J | ||
| author affiliation = NRC/NRR/ADRO/DORL | | author affiliation = NRC/NRR/ADRO/DORL | ||
| addressee name = Naslund C | | addressee name = Naslund C | ||
| addressee affiliation = Union Electric Co | | addressee affiliation = Union Electric Co | ||
| docket = 05000483 | | docket = 05000483 |
Revision as of 19:14, 13 July 2019
ML061210471 | |
Person / Time | |
---|---|
Site: | Callaway |
Issue date: | 05/16/2006 |
From: | Donohew J Plant Licensing Branch III-2 |
To: | Naslund C Union Electric Co |
Donohew J N, NRR/DORL, 415-1307 | |
References | |
TAC MC8220 | |
Download: ML061210471 (4) | |
Text
May 16, 2006Mr. Charles D. Naslund Senior Vice President and Chief Nuclear Officer Union Electric Company Post Office Box 620 Fulton, MO 65251
SUBJECT:
CALLAWAY PLANT, UNIT 1 - LICENSE AMENDMENT REQUEST TOCHANGE THE REACTOR COOLANT SYSTEM LEAKAGE DETECTION INSTRUMENTATION METHODOLOGY (TAC NO. MC8220)
Dear Mr. Naslund:
In your license amendment request application dated August 26, 2005 (UL NRC-05197), youproposed to revise your commitment to Regulatory Guide (RG) 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems," dated May 1973, in the Final Safety Analysis Report for the Callaway Plant. This revision would change the plant licensing basis to account for the containment atmosphere gaseous radioactivity monitor in Technical Specification (TS) 3.4.15, "RCS [Reactor Coolant System] Leakage Detection Instrumentation," not beingable to promptly detect a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at the levels of radioactivity that are currently normally present in the RCS. Because TS 3.4.16, "RCS Specific Activity," allowed plant operation at the RCS radioactivity levels where the containment atmosphere gaseousradioactivity monitor would be able to promptly detect a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the radioactivity monitor was not proposed to be removed from TS 3.4.15.On April 13, 2006, the basis for not removing the containment atmosphere gaseousradioactivity monitor (gaseous radmonitor) in TS 3.4.15 was discussed in a conference call with your staff. The other three instrumentations listed in TS 3.4.15, in addition to this monitor, are capable of promptly measuring a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for normal plant conditions and the gaseous radmonitor does not appear to be capable of doing this. This is also stated in your application dated August 26, 2005. Your staff did not explain in the call how the gaseousradioactivity monitor could promptly detect a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for normal plant conditions.RG 1.45 states that "in analyzing the sensitivity of leak detection systems using airborneparticulate or gaseous radioactivity, a realistic primary coolant radioactivity concentration assumption should be used" and a realistic concentration would be that which is currently normally expected to be present in the RCS coolant. Although RG 1.45 also states that thecoolant radioactivity concentration values in the plant environmental report would be acceptable as the realistic primary coolant radioactivity concentration, this statement would no longer be correct if the values in the plant environmental report are significantly higher than the valuesthat would be currently expected in the RCS coolant.It has always been the NRC's position that the instrumentation listed in TS 3.4.15 as a methodfor meeting Part 50, Appendix A, General Design Criterion (GDC) 30 of Title 10 of the Code ofFederal Regulations, "Quality of reactor coolant pressure boundary," should be capable ofdetecting a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for realistic or normal plant conditions. In the NRC C. Naslund- 2 -Standard Review Plan 5.2.5, "Reactor Coolant Pressure Boundary Leakage Detection," it isstated that RG 1.45 is an acceptable method to meet GDC 30 for RCS leak detection, and, in1973, when RG 1.45 was issued, the underlying assumption was that the acceptable detectionmethods would have that detection capability for the normal plant conditions that existed at thattime. The containment atmosphere gaseous radioactivity monitor was listed in RG 1.45 because the normal RCS radioactivity concentrations at that time were such that this monitor could detect a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Now that normal plant conditions have much lower RCS radioactivity concentrations, the monitor cannot meet this criterion. Therefore, the RCS detection instrumentation in TS 3.4.15 should be capable of promptly detecting RCSleakage for the current plant conditions.Because TS 3.4.15 defines the RCS leakage detection instrumentation being relied upon tomeet the criterion of detecting a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for normal plant conditions, we are requesting that you either provide justification that the containment gaseous radioactivitymonitor can meet this criterion or revise your amendment request dated August 26, 2005, to remove the containment gaseous radioactivity monitor from TS 3.4.15. We also request that you submit your response no later than June 30, 2006, so that we can complete our review in a timely manner.If you have any questions concerning this letter, you may contact me at (301) 415-1307, or viathe internet at jnd@nrc.gov
.Sincerely,/RA/Jack Donohew Senior Project ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-483 cc: See next page C. Naslund- 2 -Standard Review Plan 5.2.5, "Reactor Coolant Pressure Boundary Leakage Detection," it isstated that RG 1.45 is an acceptable method to meet GDC 30 for RCS leak detection, and, in1973, when RG 1.45 was issued, the underlying assumption was that the acceptable detectionmethods would have that detection capability for the normal plant conditions that existed at thattime. The containment atmosphere gaseous radioactivity monitor was listed in RG 1.45 because the normal RCS radioactivity concentrations at that time were such that this monitor could detect a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Now that normal plant conditions have much lower RCS radioactivity concentrations, the monitor cannot meet this criterion. Therefore, the RCS detection instrumentation in TS 3.4.15 should be capable of promptly detecting RCSleakage for the current plant conditions.Because TS 3.4.15 defines the RCS leakage detection instrumentation being relied upon tomeet the criterion of detecting a 1 gpm RCS leakrate in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for normal plant conditions, we are requesting that you either provide justification that the containment gaseous radioactivitymonitor can meet this criterion or revise your amendment request dated August 26, 2005, to remove the containment gaseous radioactivity monitor from TS 3.4.15. We also request that you submit your response no later than June 30, 2006, so that we can complete our review in a timely manner.If you have any questions concerning this letter, you may contact me at (301) 415-1307, or viathe internet at jnd@nrc.gov
.Sincerely,/RA/Jack Donohew Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-483cc: See next pageDISTRIBUTION:PUBLICLPLIV r/f RidsNrrDorl (CHaney/CHolden)RidsNrrDorlLpl4 (DTerao)
RidsNrrPMJDonohewRidsNrrDorlDpr RidsNrrLALFeizollahiRidsOgcRp RidsAcrsAcnwMailCenterRidsRegion4MailCenter (BJones)RidsNrrDssSsib (DSolorio)ACCESSION NO.: OFFICENRR/LPL4/PMNRR/LPL4/LA SBPB/BCNRR/LPL4/BCNAMEJDonohewLFeizollahiDSolorioDTerao DATE5/16/0605/15/200605/12/20065/16/06OFFICIAL RECORD COPY Callaway Plant, Unit 1 cc:Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855John O'Neill, Esq.Pillsbury Winthrop Shaw Pittman LLP 2300 N. Street, N.W.
Washington, D.C. 20037Mr. Mark A. Reidmeyer, RegionalRegulatory Affairs Supervisor Regulatory Affairs AmerenUE P.O. Box 620 Fulton, MO 65251U.S. Nuclear Regulatory CommissionResident Inspector Office
8201 NRC RoadSteedman, MO 65077-1302Mr. Les H. KanuckelManager, Quality Assurance AmerenUE P.O. Box 620 Fulton, MO 65251Missouri Public Service CommissionGovernor Office Building 200 Madison Street Jefferson City, MO 65102-0360Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Mr. H. Floyd GilzowDeputy Director for Policy Missouri Department of Natural Resources
P. O. Box 176 Jefferson City, MO 65102-0176Mr. Rick A. MuenchPresident and Chief Executive Officer Wolf Creek Nuclear Operating Corporation
P.O. Box 411 Burlington, KA 66839Mr. Dan I. Bolef, PresidentKay Drey, Representative Board of Directors Coalition for the Environment 6267 Delmar Boulevard University City, MO 63130Mr. Lee Fritz, Presiding CommissionerCallaway County Court House 10 East Fifth Street Fulton, MO 65151Mr. David E. Shafer Superintendent, Licensing Regulatory Affairs AmerenUE P.O. Box 66149, MC 470 St. Louis, MO 63166-6149Mr. Keith D. YoungManager, Regulatory Affairs AmerenUE P.O. Box 620 Fulton, MO 65251Mr. Keith G. Henke, PlannerDivision of Community and Public Health Office of Emergency Coordination 930 Wildwood P.O. Box 570 Jefferson City, MO 65102Certrec Corporation4200 South Hulen, Suite 630 Fort Worth, TX 76109Director, Missouri State Emergency Management Agency
P.O. Box 116 Jefferson City, MO 65102-0116