ML052550307
| ML052550307 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/21/2005 |
| From: | Sean Peters NRC/NRR/DLPM/LPD2 |
| To: | Office of Nuclear Reactor Regulation |
| Peters S, NRR/DLPM, 415-1842 | |
| Shared Package | |
| ML052550313 | List: |
| References | |
| TAC MB7014, TAC MB7015 | |
| Download: ML052550307 (9) | |
Text
September 21, 2005 LICENSEE:
Duke Energy Corporation FACILITY:
Catawba Nuclear Station, Units 1 and 2
SUBJECT:
SUMMARY
- MEETING WITH DUKE ENERGY CORPORATION ON VENTILATION SYSTEMS AMENDMENT (TAC NOS. MB7014 AND MB7015)
Representatives of Duke Energy Corporation (Duke, the licensee) met with members of the Nuclear Regulatory Commission (NRC) staff at NRC Headquarters on July 18, 2005, in Rockville, Maryland. The meeting addressed issues related to a license amendment submitted by the licensee on November 25, 2002 (Agencywide Documents Access Management (ADAMS) No. ML023380432), for Catawba Nuclear Station (Catawba), Units 1 and 2. These issues concerned the treatment of the iodine release in the licensees alternate source term analysis, the treatment of filter bypass in the auxiliary building filtered ventilation exhaust system (ABFVES), and the testing of the ABFVES relative to design basis accident conditions.
A list of attendees is provided in Attachment 1 and the handouts provided in the meeting by Duke are included in Attachment 2.
SUMMARY
OF MEETING The first portion of the meeting pertained to a discussion of Dukes July 8, 2005, response (Adams No. ML052030337) to the following NRC staff questions:
Regarding iodine release (partitioning) from Engineered Safety Features (ESF) systems and Refueling Water Storage Tank (RWST) leakage, the NRC staff structured regulatory positions in Regulatory Guide (RG) 1.183, Appendix A, Section 5 to be deterministic and conservative in order to compensate for the lack of research into iodine release, partitioning and speciation from systems outside the containment, and the uncertainties of applying laboratory data to the postaccident environment of the plant. Regulatory Position 5.5 does state that a smaller flash fraction could be justified based on the actual sump pH history and area ventilation rates. The NRC staff needs additional information to provide justification for Dukes proposed treatment of ESF system and RWST leakage:
a.
What consideration was given to the mass transfer at the surface of the ESF leakage water pool, the possibility of evaporation to dryness, available experiments to justify the assumed chemical forms, and the potential for changing pH in all areas subject to ESF leakage?
b.
How would the iodine partitioning and release be expected to change as the ECCS leakage is sprayed out of a leak, or streams across a floor into a building sump.
c.
For iodine partitioning values less than 10 percent, justification should include an analysis of the impact of any gases generated by flashing along the piping route or within the RWST. This evaluation should consider any flashing along the pipe length, the temperatures of the back-leaked fluid within the pipe and in the RWST. Provide the calculation including the results, methodology used and justified assumptions.
d.
Duke bases the percent release of iodine from the ESF systems and RWST on NUREG/CR-5950, "Iodine Evolution and pH Control." NUREG/CR-5950 provides several fits to experimental data from controlled experiments. The release rates in NUREG/CR-5950 are for very specific laboratory conditions that do not appear to match those for the loss-of-coolant accident (LOCA) condition.
For example, NUREG/CR-5950 does not appear to address the impact of impurities present due to core damage and other chemicals present. The data fit also contains very large errors when compared with the experimental data.
None of this uncertainty appears to be addressed by Duke. Please explain how the uncertainty is addressed in your calculation of the iodine release. Also provide additional information and justification (benchmarked by any experiments as known) for the methodology used to show why the values used from NUREG/CR-5950 are applicable and conservative for postulated LOCA leakage at Catawba. Include the impact of:
i) impurities in the reactor coolant system and RWST fluids on the pH and iodine partitioning, ii) any other applicable operational issues (i.e., differences between the very specific laboratory conditions and actual plant conditions), and iii) the uncertainty within the curve fits of the data.
e.
Address how mixing and stratification of the combined fluids is modeled in the RWST and address how the release point of the back-leaked fluid into the RWST impacts the amount of iodine released. Provide the calculation including the results, methodology used and justified assumptions.
f.
Are there any organic compounds in the RWST or the area around the RWST?
If so, address how these organic compounds may impact the percentage of organic iodine released.
g.
Are there any organic compounds in the area around the ESF system leakage?
If so, address how these organic compounds may impact the percentage of organic iodine released.
The second part of the meeting pertained to the following NRC staff question:
It is the NRC staff position that charcoal filter testing should be done in accordance with the guidance of RG 1.52, Rev. 2, as has been committed to by the Catawba plant. As such, a 2-inch charcoal filter should be tested to a laboratory efficiency of 97.5 percent, thereby, permitting licensee to claim 95 percent efficiency for both organic and elemental iodine in the dose analysis while providing a safety factor of 2, as outlined in Generic Letter (GL) 99-02. See Regulatory Position 6.a in RG 1.52, Rev. 2, and GL 99-02 for further discussion of the NRC staffs position. Considering this discussion on filter testing and assumed filter efficiency in dose analyses, the explanation of how Catawba has accounted for the 1 percent system bypass for the in-place testing by adjusting the filter efficiency is not clear to the NRC staff. Provide a clear explanation of how the allowable bypass is accounted for in your dose analysis.
Duke elaborated and clarified its responses to these questions. Furthermore, during the last portion of the meeting, the NRC staff inquired about how the proposed changes to the Technical Specifications (e.g., changing the requirements from testing one train of the ABFVES at 30,000 cfm to testing two trains at 60,000 cfm) would ensure that the ABFVES would be capable of handling design basis accident conditions. Duke provided the enclosed engineering drawings and handouts to aid in its response.
CONCLUSION At the conclusion of the meeting, the NRC staff indicated that it would use the information gathered to aid in the review of the amendment request.
No members of the public attended this meeting. There were no public comments.
Sincerely,
/RA/
Sean E. Peters, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414 Attachments: 1. Attendance List
- 2. to 13. Meeting Handouts cc w/atts: See next page
ML052550307 Package: ML052550313 Meeting Notice: ML051880251 :
ML052570069 0: ML052570070 1: ML052570071 2: ML052570076 3: ML052570078 NRC-001 OFFICE PDII-1/PM PDII-1/LA PDII-1/SC NAME SPeters CHawes EMarinos DATE 9/21/05 9/20/05 9/21/05 ATTENDEES LIST JULY 18, 2005 MEETING WITH DUKE ENERGY CORPORATION NAME ORGANIZATION Sean Peters NRC/NRR/DLPM Kahtan Jabbour NRC/NRR/DLPM Harold Walker NRC/NRR/DSSA Ed Forrest NRC/NRR/DSSA Michelle Hart NRC/NRR/DSSA Ed Hackett NRC/NRR/DLPM John Hayes NRC/NRR/DSSA Leta Brown NRC/NRR/DSSA Angelo Marinos NRC/NRR/DLPM Mike Tschiltz NRC/NRR/DSSA Regis Repko Duke Energy Lee Keller Duke Energy Stephen Schultz Duke Energy Mark Costello Duke Energy Tracy Saville Duke Energy Tom Simril Duke Energy
Catawba Nuclear Station, Units 1 & 2 cc:
Mr. Lee Keller, Manager Regulatory Compliance Duke Energy Corporation 4800 Concord Road York, South Carolina 29745 Ms. Lisa F. Vaughn Duke Energy Corporation 526 South Church Street P. O. Box 1006 Mail Code = EC07H Charlotte, North Carolina 28201-1006 North Carolina Municipal Power Agency Number 1 1427 Meadowwood Boulevard P.O. Box 29513 Raleigh, North Carolina 27626 County Manager of York County York County Courthouse York, South Carolina 29745 Piedmont Municipal Power Agency 121 Village Drive Greer, South Carolina 29651 Ms. Karen E. Long Assistant Attorney General North Carolina Department of Justice P.O. Box 629 Raleigh, North Carolina 27602 NCEM REP Program Manager 4713 Mail Service Center Raleigh, North Carolina 27699-4713 Division of Radiation Protection NC Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Mr. Henry Barron Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006 North Carolina Electric Membership Corp.
P.O. Box 27306 Raleigh, North Carolina 27611 Senior Resident Inspector U.S. Nuclear Regulatory Commission 4830 Concord Road York, South Carolina 29745 Mr. Henry Porter, Assistant Director Division of Waste Management Bureau of Land and Waste Management Dept. of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201-1708 Mr. R.L. Gill, Jr., Manager Nuclear Regulatory Issues and Industry Affairs Duke Energy Corporation 526 South Church Street Mail Stop EC05P Charlotte, North Carolina 28202 Saluda River Electric P.O. Box 929 Laurens, South Carolina 29360 Mr. Peter R. Harden, IV, Vice President Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road 12th Floor Charlotte, North Carolina 28210 Mr. T. Richard Puryear Owners Group (NCEMC)
Duke Energy Corporation 4800 Concord Road York, South Carolina 29745 Diane Curran Harmon, Curran, Spielbergy &
Eisenberg, LLP 1726 M Street, NW Suite 600 Washington, DC 20036
MEETING HANDOUTS CATAWBA NUCLEAR STATION UNITS 1 & 2 VENTILATION SYSTEM DIAGRAMS Attachments 3 - 13 are listed below with their Accession Numbers. They are accessible from the Agencywide Documents Access and Management System's (ADAMS)
Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. : ML052570061 : ML052570063 : ML052570064 : ML052570065 :ML052570067 : ML050270068 : ML052570069 0: ML052570070 1: ML052570071 2: ML052570076 3: ML052570078
SUBJECT:
SUMMARY
- MEETING WITH DUKE ENERGY CORPORATION ON VENTILATION SYSTEMS AMENDMENT (TAC NOS. MB7014 AND MB7015)
Dated:
September 21, 2005 Distribution:
PUBLIC PDII-1 R/F RidsNrrPMSPeters RidsNrrPMKJabbour RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDlpm (LMarsh/CHaney)
RidsNrrDlpmLpdii (EHackett)
RidsNrrDlpmLpdii1 (EMarinos)
RidsNrrLACHawes RidsRgn2MailCenter BWetzel RJasinski HWalker EForrest MHart JHayes LBrown MTschiltz