ML20196J217
| ML20196J217 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/04/1988 |
| From: | Martin R Office of Nuclear Reactor Regulation |
| To: | Bauer E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8803140185 | |
| Download: ML20196J217 (4) | |
Text
o Docket Nos.:
50-277/278 March 4, 1988 Mr. Edward G. Bauer, Jr.
Vice President and General Counsel Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101
Dear Mr. Bauer:
SUBJECT:
PECO REPORT FMS-004 "METHODS FOR PERFORMING BWR SYSTEMS TRANSIENT ANALYSES" l
As a result of the staff consultant's review at International Technical Services (ITS) we find that the following additional information is needed to facilitate the review of the PECo report FMS-004, "Methods for Performing BWR Systems Transient Analyses," as identified in the enclosure.
P Sincerely,
/S/
Robert E. Martin, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Enclosure cc:
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p WASHINGTON, D. C. 20555 March 4, 1988 Docket Nos.:
50-277/278 Mr. Edward G. Bauer, Jr.
Vice President and General Counsel Philadelphia Electric Company 2301 Market Street i
Philadelphia, Pennsylvania 19101
Dear Mr. Bauer:
SUBJECT:
PEC0 REPORT FMS-004 "METHODS FOR PERFORMING BWR SYSTEMS TRANSIENT ANALYSES" As a result of the staff consultant's review at International Technical Services (ITS) wt find that the following additional information is needed to facilitate the review of the PECo report FMS-004, "Methods for Performing BWR Systems Transient Analyses," as identified in the enclosure.
Sincerely, V
d Robert E. Martin, Project Manager l
Project Directorate I-2 Division of Reactor Projects I/II Enclosure l
cc: See next page
t j PE0 VEST FOR ADDITIONAL INFORMATION DHil.ADELPHIA ELECTRIC COPPANY TOPICAL REPORT PECO-FMS-004 1.
Model cualification neans a thorouch demonstration that the PETpAN model (nodalization and selection of built-in models) accurately represents the plant that the computer code is being used within its rance of applicability, and that the user can correctly interpret the output from the code analysis.
In addition, use of the RETPAN computer code is subject to certain limitations which are delineated in the staff SER i
applicable to the code.
Therefore, to cualify the PETRAN models for use in Peach Pettom reload applications, provide the following for the j
intended use:
i (a) justify the nodalization on a transient-by-transient basis by parametric studies and by comparison to available test data; (b) justify the selection of RETRAN built-in models on a transient-by-transient basis by parametric studies and by comparison to available data, and by demonstratino that all such models ere used within their ranges of validity; j
(c) demonstrate that all limitations on code use specified in the RETRAN SER are satisfied for each analysis submitted.
2.
In conjunction with the basic model cualification in Ouestion 1, in order to ensure that no unexpected anomalies occur in the use of PECo's version
{
of RETRAN-02, provide a listing of the important sources of uncertainty in the code for the intended reload analyses.
Cersideration should be civen to the reactor core model, recirculation systen model, and steam line model. The key parameters which should be vrried through the rance of potential BWR transient conditions are screm time, void reactivity coefficient, void distribution, jet pump losses, flow rate and distribution, core pressure drop, stop valve closure time, separator i
model, bubble rise (er slip model), MSIV closure time (for pressuriration transients), core exit pressure, specific heat ratio, etc.
Estimate the 95% probability limits for these uncertainties and detemine the corresponding delta-CPR/ICPR for each uncertainty for turbine trip without bypass transient.
Detemine the corresponding delta-pressure (%) for each of these uncertainties for the MSIV closure event with positior switch scram failure. Also provide an estimate of the correspoadino themal-hydraulic stability decay ratio.
i
.s Mr. E. G. Bauer, Jr.
Peach Bottom Atomic Power Station, Philadelphia Electric Company Units 2 and 3 cc:
Mr. J. S. Kemper, Senior Vice President Mr. R. A. Heiss, Coordinator Philadelphia Electric Company Pennsylvania State Clearinghouse 2301 Market Street Governor's Office of State Planning Philadelphia, Pennsylvania 19101 and Development P. O. Box 1323 Troy B. Conner, Jr., Esq.
Harrisburg, Pennsylvania 17120 1747 Pennsylvania Avenue, N.W.
Washington, D.C. 20006 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Philadelphia Electric Company Pennsylvania Department of ATTN: Mr. D. M. Smith, Vice President Environmental Resources Peach Bottom Atomic Power Station P. O. Box 2063 Route 1. Box 208 Harrisburg, Pennsylvania 17120 Delta, Pennsylvania 17314 Mr. Albert R. Steel, Chairman Mr. W. M. Alden Roard of Supervisors Engineer-In-Charge-Licensing Peach Bottom Township Philadelphia Electric Company R. D. !1 2301 Market Street Delta, Pennsylvania 17314 Philadelphia, Pennsylvania 19101 Mr. Gary Mock Morgan J. Morris, III P. O. Box 09181 General Manager - Operating Services Columbus, Ohio 43209 Atlantic Electric P. O. Box 1500 Mr. Jack Urban 1199 Black Horse Pike General Manager, Production Pleasantville, New Jersey 08232 Delmarva Power and Light Company 800 King Street Resident Inspector Wilmington, Delaware 19899 U. S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station Mr. Tom Magette P. O. Box 399 Power Plant Research Program Delta, Pennsylvania 17314 Department of Natural Resources B-3 Regional Administrator, Region I Tawes State Office Building U. S. Nuclear Regulatory Comission Annapolis, Maryland 21401 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Roland Fletcher Department of Environment 201 West Preston Street Baltimore, Maryland 21201