ML17187A390
| ML17187A390 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, LaSalle |
| Issue date: | 04/04/1996 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| References | |
| TAC-M92914, NUDOCS 9604080322 | |
| Download: ML17187A390 (4) | |
Text
Mr. D. L. Farrar, Manager Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III, Suite 500 1400 OPUS Place Downers Grove, IL 60515 Apri 1 4, 1996
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M92914)
Dear Mr. Farrar:
By letter dated June 26, 1995, Commonwealth Edison Company (ComEd) submitted for NRC review, Topical Report NFSR-0111, Revision 0, "BWR Transient Analysis Methods," for Dresden Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Station, Units 1 and 2.
The staff is currently reviewing this report and has identified additional information needed to continue its evaluation. The enclosed request for additional information (RAI) requests that ComEd provide the staff with some additional bench-marking information relating to the use of the RETRAN code for reload transient analysis.
Docket Nos. 50-237, 50-249, 50-373, 50-374, 50-254, 50-265
Enclosure:
RAI cc w/encl:
See next page Sincerely, Original signed by:
Donna M. Skay, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation DI STR IBUTI ON:
Docket.
PUBLIC PDIII-2 r/f(3)
JRoe (JWR)
RCapra CMoore (3)
JStang RPulsifer DSkay OGC, 015-BlB Ringram ACRS, T2-E26
,,---- _96o:Oao'""'322 A960404 __ ------. BClayton, Riil PHiland, Riil
/rPr:3 I PDR ADOCK 05000237 P
PDR D~:~~:~eTa ~AME:
Gd:o~~~:n~.
9 1~~;a~i~ the box: "C" = Copy witho It enclosures "E" = Copy with enclosures "N" = No copy ~
\\ I '
OFFICE LA: D II-2 e..,,,.. PM:PDill-2 PM:
~II-2
- e. PM:PDllI-2/
D:PDllI-2 c,
NAME C
E DSKAY JS, tJG RPULSIF:>~
RCAPRAtfl.-
OFFICIAL RECORD COPY
D. L. Farrar Commonwealth Edison Company cc:
Phillip P. Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Assistant Attorney General 100 West Randolph Street Suite 12 Chicago, Illinois 60601 U.S. Nuclear Regulatory Commission Resident Inspectors Office LaSalle Station 2605 N. 21st Road Marseilles, Illinois 61341-9756 Chairman LaSalle County Board of Supervisors LaSalle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South Second Street Springfield, Illinois 62701 Chairman Illinois Commerce Commission Leland Building 527 East Capitol Avenue Springfield, Illinois 62706 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351 LaSalle Station Manager LaSalle County Station Rural Route I P.O. Box 220 Marseilles, Illinois 61341 LaSalle County Station Unit Nos. I and 2 Robert Cushing Chief, Public Utilities Division Illinois Attorney General's Office 100 West Randolph Street Chicago, Illinois 60601 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515
D. L. Farrar Commonwealth Edison Company cc:
Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60603 Site Vice President Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 Station Manager Dresden Nuclear Power Station 6500 North Dresden Road Morris, Illinois 60450-9765 U.S. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station 6500 North Dresden Road Morris, Illinois 60450-9766 Richard J. Singer Manager - Nuclear MidAmerican Energy Company 907 Walnut Street P.O. Box 657 Des Moines, Iowa 50303 Brent E. Gale, Esq.
Vice President - Law and Regulatory Affairs MidAmerican Energy Company One RiverCenter Place 106 East Second Street P.O. Box 4350 Davenport, Iowa 52808 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, Illinois 61201 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351 Dresden Nuclear Power Station Unit Nos. 2 and 3 Quad Cities Nuclear Power Station Unit Nos. 1 and 2 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Chairman Grundy County Board Administration Building 1320 Union Street Morris, Illinois 60450 Mr. L. William Pearce Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 U.S. Nuclear Regulatory Commission Quad Cities Resident Inspectors Office 22712 206th Avenue North Cordova, Illinois 61242 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515
I I.
- 2.
REQUEST FOR ADDITIONAL INFORMATION ON BWR TRANSIENT ANALYSIS METHODS In your topical report dated June 1995 for the LaSalle Reactor Water Level Setpoint Change {RWLSC), you state that core power, steam flow rate, and reactor pressure remain relatively constant as expected over the course of the transient {page 4-5).
Provide those results and compare them to the test data, if available.
From the several tests/benchmarks presented in the report, pressure discrepancies between the test data and RETRAN02 results could be observed throughout.
For example, for the LaSalle Pressure Regulator Setpoint Change {PRSC), test data stabilized 1.5 psi higher than the RETRAN02 results; for the Dual Recirculation Pump Trip {DRPT), a 3 psi difference is observed; for the Main Steam Isolation Valve Closure
{MSIVC), the test data stabilized 8 psi lower than the RETRAN02 results;.
and for the Peach Bottom turbine trip test 2, the reactor dome pressure shows a 3 psi difference.
Considering that most of the other parameters plotted show superior agreement, discuss why these pressure differences are observed.
Where is the pressure parameter measured {both for the test data and in the RETRAN02 model)?
- 3.
In the same report, on page 4-51, you state that "the measured data is clearly in error as the power was measured to level off around 10% after the reactor scram".
Discuss/prove that the model results are correct.
- 4.
On page 4-51, you state that the initial rise of the steam flow for the turbine trip with bypass benchmark is not believed to reflect the physical process and represents a temporary error in the flow measurement.
Discuss how/why the test data is wrong and describe the expected physical process.
- 5.
On page 6-6, you include the statement "The results show that the RETRAN model would be more conservative." Discuss how you reached this conclusion from the results presented.
ENCLOSURE l
I