ML13305A887
| ML13305A887 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/09/1986 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | Baskin K, Holcombe J San Diego Gas & Electric Co, Southern California Edison Co |
| References | |
| NUDOCS 8609180065 | |
| Download: ML13305A887 (7) | |
Text
SEP 9 198 Docket Nos.: 50-361 and 50-362.
Mr. Kenneth P. Baskin Mr. James C. Holcombe Vice President Vice President -
Power Supply Southern Carolina Edison Company San Diego Gas & Electric Company 2244 Walnut Grove Avenue 101 Ash Street Post Office Box 800 Post Office Box 1831 Rosemead, California 91770*
San Diego, California 92112 Gentlemen:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION During the course of our review of the San Onofre 2 and 3 Safety Parameter Display System (SPDS), we find that additional information is needed to com plete our review. The additional information is defined in Enclosure 1.
Further, in our review of the San Onofre 2 and 3 Inservice Testing program, we find that we need to review selected P&I drawings. The P&ID numbers are given in Enclosure 2. To facilitate our review of these areas, we request that you provide a response to the questions in Enclosure 1, and that you provide two sets of each of the drawings listed Enclosure 2. If you have any questions regarding this request please contact me.
Sincerely, Harry Rood, Senior Project Manager PWR Project Directorate #7 Division of PWR Licensing-B
Enclosures:
As stated DISTRIBUTION:
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Mr. Kenneth P. Baskin San Onofre Nuclear Generating Station Southern California Edison Company Units 2 and 3 cc:
Mr. James C. Holcombe Mr. Hans Kaspar, Executive Director Vice President Power Supply Marine Review Committee, Inc.
San Diego Gas & Electric Company 531 Encinitas Boulevard, Suite 105 101 Ash Street Encinitas, California 92024 Post Office Box 1831 San Diego, California 92112 Charles R. Kocher, Esq.
Mr. Mark Medford James A. Beoletto, Esq.
Southern California Edison Company Southern California Edison Company 2244 Walnut Grove Avenue 2244 Walnut Grove Avenue P. 0. Box 800 P. 0. box 800 Rosemead, California 91770 Rosemead, California 91770 Mr. Stephen B. Alman Manager, Nuclear Department Orrick, Herrington & Sutcliffe San Diego Gas & Electric Company ATTN:
David R. Pigott, Esq.
P. 0. Box 1831 600 Montgomery Street San Diego, California 92112 San Francisco, California 94111 Richard J. Wharton, Esq.
University of San Diego School of Alan R. Watts, Esq.
Law Rourke & Woodruff Environmental Law Clinic Suite 1020 San Diego, California 92110 1055 North Main Street Santa Ana, California, 92701 Charles E. McClung, Jr., Esq.
Attorney at Law Mr. S. McClusky 24012 Calle de la Plaza/Suite 330 Bechtel Power Corporation Laguna Hills, California 92653 P. 0. Box 60860, Terminal Annex Los Angeles, California 90060 Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. C. B. Brinkman 1450 Maria Lane/Suite 210 Combustion Engineering, Inc.
Walnut Creek, California 94596 7910 Woodmont Avenue, Suite 1310 Bethesda, Maryland 20814 Resident Inspector, San Onofre NPS c/o U. S. Nuclear Regulatory Commission Mr. Dennis F. Kirsh Post Office Box 4329 U.S. Nuclear Regulatory Commission San Clemente, California 92672 Region V 1450 Maria Lane,.Suite 210 Walnut Creek, California 94596
ENCLOSURE 1 REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE SAN ONOFRE UNITS 2 & 3 SAFETY PARAMETER.DISPLAY SYSTEM Each operating reactor shall be provided with a Safety Parameter Display System (SPDS). The Commission approved requirements for an SPDS are defined in NUREG-0737, Supplement 1. In the Regional Workshops on Generic Letter 82-33 held during March 1983, the NRC discussed these requirements and the staff's review of the SPDS.
The staff reviewed the SPDS Safety Analysis Report (Ref. 1) submitted by the Southern California Edis-on Company. Although our review noted many positive features in the design, we were unable to complete our evaluation because of insufficient information. The following additional information is required to continue and complete our review:
1.0 Isolation Devices (covered in previous R.A.I) 2.0 Data Validation 2.1 Unvalid and Invalid Data The licensee's safety analysis contained information on our of range data, unvalidated data, and invalid data. However, it was unclear how these data.were related to each other, if at all.
Provide a description of the methods used to define valid data, invalid data, and unvalid data. Furthermore, describe how each type of data is coded for display, and how the data is used by operators.
3.0 Human Factors Program 3.1 Density of Displayed Data The licensee's safety analysis states that the density of displayed data is not greater than 40%. For rapid and reliable communication of data, human factor guidelines call for a denity of 25% or less.
Define the number of display formats that have a data density greater than 25% and provide data to justify them.
3.2 Data Concentration The safety analysis described seven critical functions and identified variables for each function. However, We were unable to determine if the variables needed to evaluate a critical function were all presented on one page or spread over several pages.
For each critical function, define the location of each variable needed to evaluate the function.
02 3.3 Alarm Overload The licensee's SPDS design utilize alarms to highlight an event and obtain the user's attention. However, our review was unable to determine if a method existed to prioritize alarms and prevent overloading the user with information. Describe the features of the design used to prevent information overload.
3.4 Oscillation of Process Variables and Displayed Date Our review of the safety analysis noted that trend graphs of process variables are available from the SPDS. To complete our review, we need information on how the trend data is processed by the SPDS.
Furthermore, the licensee should describe the features of the SPOS design that transmit and display oscillating process variables or limit cycling process variables, which may be symptoms of a severe accident.
4.0 Parameter Selection 4.1 Steam Generator Radiation Our review of the licensee's variables was unable to identify the use of steam generator radiation as a displayed variable. Prior to isolation, steam generator radiation and plant vent stack radiation provide a rapid assessment of radiation status for the most likely radioactive release paths. The licensee's SPDS contains plant vent stack radiation, but does not contain steam generator radiation. Upon isolation of a steam generator, plant vent stack radiation is not a valid indicator of steam generator radiation. The licensee should indicate how radiation in the secondary system (steam generator and steamline) is monitored by the SPDS when the steam generator and/or their steamline are isolated, or provide justification for its exclusion.
4.2 Containment Hydrogen Concentration Containment Sump Water Level is a key indicator of the viability of the ECCS recirculation mode of heat removal. The licensee's SPDS displays Quench Tank Water Level, which is a key indicator to identify leakage from the primary safety valves. However, Quench Tank Water Level is not useful in evaluating the viability of the ECCS recircu lation mode of heat removal.
We recommend the addition of Containment Sump Water Level to the SPDS, or provide justification for its exclusion.
-- 30
-3 REFERENCE
- 1. Letter from: M.E. Medford, Southern California Edison Company, to:
G.W. Knighton, NRC, subject: Safety Parameter Display System Safety Analysis for San Onofre Units 2 and 3, dated November 30, 1984.
ENCLOSURE 2 SAN ONOFRE UNIT 2 SYSTEM VALVE LIST P&ID NO.
Reactor Coolant System...................40111 Safety Injection System, Sheet 1.................40112 Safety Injection System, Sheet 2.................40113 Containment Spray System....
................. 40114 Diesel Fuel Storage System..
.................. 40116 Sumps & Drains Systems..........................40117 Fuel Pool Cooling System........................40122 Reactor Coolant Chemical & Volume Control, Sheet 1...40128 Reactor Coolant Chemical & Volume Control, Sheet 2...40124 Reactor Coolant Chemical & Volume Control, Sheet 3...40125 Component Cooling Water System, Sheet 1...........40126 Component Cooling Water System, Sheet 2...........40127 Nuclear Plant Sampling System..
............... 40128 Coolant Radwaste System.........................40131 Coolant & Boric Acid Recycle System..............40133 Nuclear Plant Sampling System....
.............. 40134 Waste Gas System......................
....40135 Nuclear Service Water System....................40140 Main Steam System..
40141 High Pressure Feedwater System..
.............. 40156 Auxiliary.Feedwater System......................40160 Auxiliary Boiler System..
40169 Containment HV&AC System (Normal) Sheet 1.........40170 Containment HV&AC SYstem (Normal) Sheet 2.........40171 Containment HV&AC System (Emergency)..............40172 Containment HV&AC System (Emergency)..............40172 Fire Protection System..........................4184 Compressed Air System......
....................40191 Auxiliary Gas System.
40192
ENCLOSURE 2 (Cont'd)
SAN ONOFRE UNIT 3 SYSTEM VALVE LIST P&ID No.
Reactor Coolant System..................
.40111S03 Safety Injection System, Sheet 1..........
...... 40112SC3 Safety Injection System, Sheet 2..................40113S03 Containment Spray System...
................... 40114S03 Diesel Fuel Storage System.....
40116S03 Sumps & Drains Systems..........................40117S03 Fuel Pool Cooling System........................40122S03 Reactor Coolant Chemical & Volume Control, Sheet I....40123503 Reactor Coolant Chemical & Volume Control, Sheet 2....
40124503 Reactor Coolant Chemical & Volume Control, Sheet. 3.... 40235S03 Component Cooling Water System, Sheet 1............40126S03 Component Cooling Water System, Sheet 2............40127503 Nuclear Plant Sampling System...............
..40128S03 Coolant Radwaste System..............
........... 40131SO3 Coolant & Boric Acid Recycle System.................40133S03 Nuclear Plant Sampling System.
40134S03 Waste Gas System
...............................40135S03 Nuclear Service Water System.................
&u o
l....40140S03 Main Steam System
.............................. 40141S3 High Pressure Feedwater System.....
............. 40156S03 Auxiliary Feedwater System yte..h....40160S3 Auxiliary Boiler System....ml....
................ 40169S03 Containment HV&AC System (Normal) Sheet 1..........40170S3 Containment HV&AC System (Normal) Sheet 2..........40171S03 Containment HV&AC System (Emergency)..............40172S3 Fire Protection 40189S3 Compressed Air System...........................40191S03 Auxiliary Gas System...........................40192S03