ML13309A178
| ML13309A178 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 02/05/1992 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | Ray H Southern California Edison Co |
| References | |
| NUDOCS 9202100559 | |
| Download: ML13309A178 (7) | |
Text
February 5, 1992 Docket Nos. 50-206, 50-361 and 50-362 Mr. Harold B. Ray Senior Vice President Southern California Edison Company 23 Parker Street Irvine, California 92718
Dear Mr. Ray:
SUBJECT:
EMERGENCY RESPONSE DATA SYSTEM IMPLEMENTATION On October 22, 1991, the Southern California Edison Company forwarded to the U.S. Nuclear Regulatory Commission (NRC) Data Point Libraries for use in the Emergency Response Data System (ERDS) at San Onofre Units 2 and 3. The NRC staff reviewed the ERDS submittal and generated comments that are included in the enclosure to this letter.
As noted by our comments, your ERDS data does not include main steam line radiation monitors. Although these data points were not available for computer transmission at the time that the ERDS design was presented during the NRC site visit on January 25, 1991, discussions with your staff indicate that these data points were subsequently added to the plant computer.
Per the requirements of 10 CFR 50 Appendix E, VI.2.a, the main steam line radiation monitors should be added to the Data Point Library.
Please note that 10 CFR 50, Appendix E requires the ERDS implementation to be completed by February 13, 1993. If you have any questions concerning this letter or any other aspect of ERDS implementation, please contact me at (301) 504-1367 or Mr. John Jolicoeur, the ERDS Project Manager, at (301) 492-4155.
Sincerely, Original signa by George Kalman, Senior Project Manager Project Directorate V Division of Reactor Projects-III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
DISTRIBUTION As stated Docket File NRC & LPDRs PDV r/f BBoger MVirgilio TQuay cc w/enclosures:
DFoster ELJordan GKalman See next page ACRS (10)
RZimmerman, RV OGC DFRoss DOA r/f GGZech JRJolicoeur IRB r/f RFPriebe MTaylor, EDO
- See previous concurrence OFC:
LA:PDV:DRPW
,PE:PDV:DRPW PM:
DRPW
- IRB:DOA:AEOD D:PDV:DRPW NAME:
OFoster J
te 3 amn,.pm JRJolicoeur TQuay DATE:
2 /3 /92 3/ /92
///92 01/30/92 L-/ 5/92 OFFICIAL RECORD COPY Document Name:
ROSENBLU 9202100559 920205 PDR ADOCK 05000206 P
_L
Docket Nos. 50-206, 50-361 and 50-362 Mr. Harold B. Ray Senior Vice President Southern California Edison Company 23 Parker Street Irvine, California 92718
Dear Mr. Ray:
SUBJECT:
EMERGENCY RESPONSE DATA SYSTEM IMPLEMENTATION On October 22, 1991, the Southern California Edison Compa forwarded to the U.S. Nuclear Regulatory Commission (NRC) Data Point Libr ries for use in the Emergency Response Data System (ERDS) at San Onofre Un s 2 and 3. The NRC staff reviewed the ERDS submittal and generated comm ts that are included in the enclosure to this letter.
As noted by our comments, your ERDS data does no include main steam line radiation monitors. Although these data point were not available for computer transmission at the time that the ER S design was presented during the NRC site visit on January 25, 1991, di ussions with your staff indicate that these data points were subsequently a'ded to the plant computer.
Addition of the main steam line radiatio monitors to the Data Point Library would upgrade the San Onofre ERDS and w recommend that you incorporate this feature into your design.
Please note that 10 CFR 50 Appendix requires the ERDS implementation to be completed by February 13, 1993. I you have any questions concerning this letter or any other aspect of ER implementation, please contact me at (301) 504-1367 or Mr. John Jolicoeur, he ERDS project manager, at (301) 492-4155.
Sincerely, George Kalman, Project Manager Project Directorate V Division of Reactor Projects-III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
DISTRIBUTION As stated Docket File NRC & LPDRs PDV r/f BBoger MVirgilio TQuay cc w/enclosures:
DFoster ELJQrdan GKalman See next page ACRS (10)
RZimmerman, RV OGC DFRoss DOA r/f GGZech JRJolicoeur IRB r/f RFPriebe MTaylor, EDO OFC:
A:PDV:DRPW PE:PDV:DRPW PM:P RPW
- DOA:
OD 0:PDV:DRPW NAME:
DFoster JBradfute G, iM pm JRJoli oeur TQuay DATE:
/
/92
/
/92
'Z,9/92 L/1/92
/
/92 OFFICIAL RECORD COPY Document Name:
ROSENBLU
' ~tREG41 4'
UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555 February 5, 1992 Docket Nos. 50-206, 50-361 and 50-362 Mr. Harold B. Ray Senior Vice President Southern California Edison Company 23 Parker Street Irvine, California 92718
Dear Mr. Ray:
SUBJECT:
EMERGENCY RESPONSE DATA SYSTEM IMPLEMENTATION On October 22, 1991, the Southern California Edison Company forwarded to the U.S. Nuclear Regulatory Commission (NRC) Data Point Libraries for use in the Emergency Response Data System (ERDS) at San Onofre Units 2 and 3. The NRC staff reviewed the ERDS submittal and generated comments that are included in the enclosure to this letter.
As noted by our comments, your ERDS data does not include main steam line radiation monitors. Although these data points were not available for computer transmission at the time that the ERDS design was presented during the NRC site visit on January 25, 1991, discussions with your staff indicate that these data points were subsequently added to the plant computer. Per the requirements of 10 CFR 50 Appendix E, VI.2.a, the main steam line radiation monitors should be added to the Data Point Library.
Please note that 10 CFR 50, Appendix E requires the ERDS implementation to be completed by February 13, 1993.
If you have any questions concerning this letter or any other aspect of ERDS implementation, please contact me at (301) 504-1367 or Mr. John Jolicoeur, the ERDS Project Manager, at (301) 492-4155.
Sincerely, George Kalman, Senior Project Manager Project Directorate V Division of Reactor Projects-III/IV/V Office of Nuclear Reactor Regulation
Enclosure:
As stated cc:
See next page
Mr. Harold B. Ray San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc:
Mr. Phil Johnson Mr. Richard J. Kosiba, Project Manager U.S. Nuclear Regulatory Commission Bechtel Power Corporation Region V 12440 E. Imperial Highway 1450 Maria Lane, Suite 210 Norwalk, California 90650 Walnut Creek, California 94596 Mr. Robert G. Lacy Manager, Nuclear Department San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U.S. Nuclear Regulatory Commission P. 0. Box 4329 San Clemente, California 92674 Mayor City of San Clemente 100 Avenida Presidio San Clemente, California 92672 Chairman, Board of Supervisors County of San Diego 1600 Pacific Highway, Room 335 San Diego, California 92101 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. John Hickman Senior Health Physicist Environmental Radioactive Mgmt. Unit Environmental Management Branch State Department of Health Services 714 P Street, Room 616 Sacramento, California 95814 Mr. Don J. Womeldorf Chief, Environmental Management Branch California Department of Health Services 714 P Street, Room 616 Sacramento, California 95814
Mssrs. Ray and Cotton San Onofre Nuclear Generating Southern California Edison Company Station, Unit Nos. 2 and 3 cc:
James A. Beoletto, Esq.
Mr. Richard J. Kosiba, Project Manager Southern California Edison Company Bechtel Power Corporation Irvine Operations Center 12440 E. Imperial Highway 23 Parker Street Norwalk, California 90650 Irvine, California 92718 Mr. Robert G. Lacy Chairman, Board of Supervisors Manager, Nuclear Department County of San Diego San Diego Gas & Electric Company 1600 Pacific Highway, Room 335 P. 0. Box 1831 San Diego, California 92101 San Diego, California 92112 Alan R. Watts, Esq.
Mr. John Hickman Rourke & Woodruff Senior Health Physicist 701 S. Parker St. No. 7000 Environmental Radioactive Mgmt. Unit Orange, California 92668-4702 Environmental Management Branch State Department of Health Services Mr. Sherwin Harris 714 P Street, Room 616 Resource Project Manager Sacramento, California 95814 Public Utilities Department City of Riverside Resident Inspector/San Onofre NPS 3900 Main Street c/o U.S. Nuclear Regulatory Commission Riverside, California 92522 Post Office Box 4329 San Clemente, California 92674 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering Nuclear Power Mayor 12300 Twinbrook Parkway, Suite 330 City of San Clemente Rockville, Maryland 20852 100 Avenida Presidio San Clemente, California 92672 Mr. Phil Johnson Regional Administrator, Region V U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Region V 1450 Maria Lane, Suite 210 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Walnut Creek, California 94596 Mr. Don J. Womeldorf Chief, Environmental Managemeot Branch California Department of Health Services 714 P Street, Room 616 Sacramento, California 95814
ENCLOSURE COMMENTS CONCERNING THE SAN ONOFRE UNITS 2 & 3 EMERGENCY RESPONSE DATA SYSTEM (ERDS)
DATA POINT LIBRARIES
- 1.
PRESSURIZER LEVEL
- a. A unit conversion factor is needed (e.g., 1 percent = x inches).
- b. In the unique system description field a level for the top of the pressurizer heater bundle would be appropriate.
- 2.
REACTOR VESSEL LEVEL
- a. The zero reference level is given as UGS support plate for the vessel head level.
This should be described in the unique system description field.
- b. A unit conversion (percent to inches) should be provided.
- 3.
LOW PRESSURE SAFETY INJECTION (LPSI) FLOW RATE Is this a total LPSI flow rate?
- 4.
REACTOR COOLANT FLOW The units for this parameter are given in AMPS. The unique system description should provide some method for deducing a flow rate based on the instrument readings provided to ERDS.
- 5.
STEAM GENERATOR LEVELS
- a. A unit conversion factor is needed (percent to inches).
- b. The location of the top of the U-tubes with respect to this range should be described in the unique system description.
- 6.
The CHARGING FLOW RATE data point was repeated as a high-pressure safety injection (HPSI) data point. The latter should be deleted.
- 7.
No data points were provided for MAIN STEAM LINE RAD levels.
- 8.
VOL CONT TANK LEVEL A unit conversion factor (percent to gallon) or tank capacity should be provided.
- 9.
For the various CONTAINMENT SUMP LEVEL data points a conversion of percent of feet to gallons of liquid should be provided.
- 10.
For the CONTAINMENT RAD data point the term "RED CH AVAIL" should be explained.
-2
- 11.
For COND A/E RAD the second portion of the unique system description needs clarification.
- 12.
For the LO and MED VENT STACK EFF RAD data points the unique system description should describe the multiple flows available. In addition, if there is a method for obtaining flow rate information for this path, it should be described here. For instance, if the flow rate is a computerized point, it should be sent. If it is available as an instrumented reading, the instrument number should be provided.
- 13.
For the CONTAINMENT PURGE VENT STACK PARTICULATE and NOBLE GAS data points does a conversion from CPM to pi/cc or similar units exist?
- 14.
For ATMOSPHERIC STABILITY CLASS it is not clear what you are sending.
Are you sending a stability class? If so, in what format? Note that ERDS requires numerical data inputs, therefore, if you are sending stability class (i.e., A, B, etc.) they need to be converted to numbers for transmission and the description of that translation should appear in the unique system description. If you are sending a temperature differential between two elevations, then your units need to be updated and the elevation between the two points should be provided in the unique system description.