ML020250145
| ML020250145 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 01/31/2002 |
| From: | Pastis H Office of Nuclear Reactor Regulation |
| To: | Kingsley O Exelon Generation Co |
| Pastis H, NRR/DLPM, 415-1261 | |
| References | |
| TAC MB2958 | |
| Download: ML020250145 (5) | |
Text
January 31, 2002 Mr. Oliver D. Kingsley, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION ON TORUS-TO-DRYWELL VACUUM BREAKERS (TAC NO. MB2958)
Dear Mr. Kingsley:
In reviewing your September 19, 2001, submittal, the U.S. Nuclear Regulatory Commission staff has determined that it will need additional information to continue its review. The request for additional information (RAI) is enclosed. Because of your interest in receiving this proposed amendment, please respond to this RAI as soon as it is convenient for you.
If you have any questions regarding this correspondence, please contact me at (301) 415-1261.
Sincerely,
/RA/
Helen N. Pastis, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
As stated cc w/encl: See next page
January 31, 2002 Mr. Oliver D. Kingsley, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION - REQUEST FOR ADDITIONAL INFORMATION ON TORUS-TO-DRYWELL VACUUM BREAKERS (TAC NO. MB2958)
Dear Mr. Kingsley:
In reviewing your September 19, 2001, submittal, the U.S. Nuclear Regulatory Commission staff has determined that it will need additional information to continue its review. The request for additional information (RAI) is enclosed. Because of your interest in receiving this proposed amendment, please respond to this RAI as soon as it is convenient for you.
If you have any questions regarding this correspondence, please contact me at (301) 415-1261.
Sincerely,
/RA/
Helen N. Pastis, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC PDI-1 R/F JMunday RHagar, SPLB SLittle HPastis RLobel, SPLB ACRS BPlatchek, RI OGC Accession Number: ML020250145 NRR-088 OFC PDI-1/PM PDI-1/LA DSSA/SPLB PDI-1/ASC NAME HPastis:as SLittle RHagar JMunday DATE 1/29/02 1/28/02 1/29/02 1/29/02 OFFICIAL RECORD COPY
Enclosure REQUEST FOR ADDITIONAL INFORMATION TORUS-TO-DRYWELL VACUUM BREAKERS OYSTER CREEK NUCLEAR GENERATING STATION FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 1.
Please provide a brief description of the analytical methods of NEDE 24802. In particular, describe any empirical correlations and how they were derived and discuss any comparisons with experimental data and the methods of NEDE 24802.
2.
Why is it assumed that only one train of containment spray is activated for Case1:
Inadvertent drywell spray activation during normal operation? Explain why two drywell spray trains can not be inadvertently actuated? What would be the effect? Would it be more limiting than the drywell spray actuation after a loss-of-coolant accident?
3.
What is the basis for the 45 F spray water temperature for Case 1? What would the expected water temperature be? How can the suppression pool temperature be 95 F and the spray temperature be 45 F? Isnt the water source for drywell spray the suppression pool?
4.
What is the basis for 6.75-ft in the torus to prevent water from being drawn into the vent header. What is the consequence of water in the vent header?
5.
The discussion for Case 1 states that the initial drywell air temperature is assumed to be 150 F which is the design maximum for normal operation. It further states that "the code input initial drywell temperature and pressure conditions were determined to be 115 F and 15.6 psia, respectively." Please explain the two initial drywell temperatures.
6.
Describe how the 115 F and 15.6 psia values referred to in Question 5 were determined.
7.
For Case 2, why is the analysis done for both a single loop and two loops of drywell spray? Isnt the two-loop case always limiting?
8.
What is the basis for the assumption of a suppression pool water temperature following blowdown of 105 F. Why is this conservative?
9.
For the three cases considered, provide results of calculations showing the wetwell to drywell pressure as a function of the number of operable vacuum breakers and the peak vent water level as a function of the number of vacuum breakers.
Also provide the results of calculations for eight vacuum breakers, showing the drywell and wetwell temperature versus time, the drywell and wetwell pressure versus time, the differential pressure between the wetwell and the drywell as a function of time and vent water level as a function of time.
10.
Page 4/9: The description for Case 3 states that "a spray effect is assumed when the reactor vessel is reflooded with emergency core cooling injection until the injection flows out the break." Shouldnt this be after the injection flows out the break?
11.
Page 4/9: Why is the assumption of a single failure beyond the existing licensing basis?
12.
Page 2/9: If Bodega Bay tests, which "established the Oyster Creek design," are the basis for requiring 12 vacuum breakers to be operable, justify the validity of calculations that predict that the differential pressure and downcomer level criteria can be satisfied with six vacuum breakers.
Oyster Creek Nuclear Generating Station cc:
John Skolds Chief Operating Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 William Bohkle Senior Vice President Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 John B. Cotton Senior Vice President - Operations Support Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Joseph J. Hagan Senior Vice President -
Mid Atlantic Regional Operating Group Exelon Generation Company, LLC 200 Exelon Way, Suite 305 Kennett Square, PA 19348 Kevin P. Gallen, Esquire Morgan, Lewis, & Bockius LLP 1800 M Street, NW Washington, DC 20036-5869 Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Jeffrey A. Benjamin Vice President -
Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Ronald J. DeGregorio Vice President Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC PO Box 388 Forked River, NJ 08731 H. J. Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Michael P. Gallagher Director - Licensing Exelon Generation Company, LLC Correspondence Control Desk P.O. Box 160 Kennett Square, PA 19348 Ernest J. Harkness Plant Manager Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Manager Regulatory Assurance Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Edward J. Cullen, Jr., Esquire Vice President, General Counsel and Secretary Exelon Generation Company, LLC 300 Exelon Way Kennett Square, PA 19348 J. Rogge, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415