ML13330A243
| ML13330A243 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/10/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Dietch R Southern California Edison Co |
| References | |
| TASK-05-05, TASK-5-5, TASK-RR LSO5-81-03-011, LSO5-81-3-11, NUDOCS 8103110728 | |
| Download: ML13330A243 (6) | |
Text
March 10, 1981 Docket No. 50-206 LS05-81-03-011 Mr. R. Dietch, Vice President 4
Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Dietch:
RE: SEP TOPIC V-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SAN ONOFRE NUCLEAR GENERATING STATION Enclosed is a copy of our evaluaton of SEP Topic V-5 for the San Onofre Nuclear Generating Station. This assessment compares your facility, as described in Docket No. 50-206, with the criteria currently used by the regulatory staff for licensing new-fatilities.
Please inform us within 30 days if your as-built facility differs from the licensing basis assumed in our assessment-or this topic will be assumed complete.
This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as built conditions at your facility. This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is completed.
In future correspondence regarding this topic, please refer to the topic number in your cover letter.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
SEP Topic V-5 cc w/enclosure:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 10, 1981 ce 1N3
.-206 Mr. R. Dietch, Vice President Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Dietch:
RE: SEP TOPIC V-5, REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SAN ONOFRE NUCLEAR GENERATING STATION Enclosed is a copy of our evaluaton of SEP Topic V-5 for the San Onofre Nuclear Generating Station. This assessment compares your facility, as described in Docket No. 50-206, with the criteria currently used by the regulatory staff for licensing new facilities. Please inform us within 30 days if your as-built facility differs from the licensing basis assumed in our assessment or this topic will be assumed complFete.
This evaluation will be a basic input to the integrated safety assessment for your facility unless you identify changes needed to reflect the as built conditions at your facility. This assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is completed.
In future correspondence regarding this topic, please refer to the topic number in your cover letter.
Sincerely, Dennis M. Crutchfield, ief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
SEP Topic V-5 cc w/enclosure:
See next page
Mr. R. Dietch SAN ONOFRE NUCLEAR GENERATION STATION, UNIT NO. 1 DOCKET NO. 50-206 CC Charles R. Kocher, Assistant Director, Technical Assessment General Counsel Division Southern California Edison Company Office of Radiation Programs Post Office Box 800 (AW-459)
Rosemead, California 91770 U. S. Environmental Protection Agency David R. Pigott Crystal Mall #2 SSamuel B. Casey Arlington, Virginia 20460 Chickering & Gregory Three Embarcadero Center U. S. Environmental Protection Twenty-Third Floor Agency San Francisco, California 94111 Region IX Office ATTN:
EIS COORDINATOR Jack E. Thomas 215 Freemont Street Harry B. Stoehr San Francisco, California 94111 San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector c/o U. S. NRC P. 0. Box AA Oceanside, California 92054 Mission Viejo Branch Library 24851 Chrisanta Drive Mission Viejo, California 92676 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN:
Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814
(1) SAN ONOFRE SYSTEMATIC EVALUATION PROGRAM TOPIC V-5 REACTOR COOLANT PRESSURE BOUNDARY (PCPB) LEAKAGE DETECTION
- 1.
Introduction The safety objective of Topic V-5 is to determine th.e reliability and sensitivity of the leak detection systems which. monitor the reactor coolant pressure boundary to identify primary system leaks at an early stage before failures occur.
II.
Review Criteria ine acceptance criteria for the detection of leakage from the reactor coolant pressure boundary is stated in the General Design Criteria of Appendix A, 10 CFR Part 50.
Criterion 30, "Quality of Reactor Coolant Pressure Boundary", requires that means shall be provided for detecting and, to the extent practical. identifying the location of the source of leakage in the reactor coolant pressure boundary. Criterion 32, "Inspection of Reactor Coolant Pressure Boundary", requires that components which are part of the reactor coolant pressure boundary shall be designed to permit Periodic inspection and testing to assess their structural and leak tight integrity.
III.
Review Guidelines The acceptance criteria are implemented by the Nuclear Regulatory Commission in Section 5.2.5, "Reactor Coolant Pressure Boundary Leakage Detection",
and Section 5.2.4, "Reactor Coolant Pressure Boundary Inservice Inspection and Testing", of the Standard Review Plan.
The areas of the Safety Analysis Report and Technical Specifications are reviewed to establish that informa tion submitted by the licensee is in compliance with Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems", and that the inservice inspection programs are based on the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, "Rules for the Inservice Inspec tion of Nuclear Power Components". Although not a part of th.is review, the consequences of break and crack location in component failures is analyzed and evaluated in Section 3.6.1. "Plant Design for Protection Against Postulated Pioing Failures in Fluid Systems Outside Containment",..and Section 3.6.2, "Determination of Break Locations and Dynamic Effects Associated with Postulated Rupture of Piping", of the Standard Review* Plan.
IV.
Evaluation Safety Topic V-5 was evaluated in this review for compliance of the infor mation submitted by the licensee with Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems".
The information in the Safety Analysis Report and Technical Specifications was substantiated by telephone conversation with the licensee. Reculatory Guide 1.45 requires that at
-2 least three separate detection systems be installed in a nuclear power plant to detect an unidentified leakage from the reactor coolant pressure boundary of one gallon per minute within one hour. Leakage from identified sources must be isolated so that the flow rates may be monitored separately from unidentified leakage. The detection systems should be capable of performing their functions following seismic events and capable of being checked in the control room. Of the three separate leak detection methods required, two of the methods should be (1) sump level and flow monitoring and (2) airborne particulate radioactivity monitoring. The third method may be either monitoring of condensate flow rate from air coolers or monitoring of airborne gaseous radioactivity. Other detection methods, such as humidity, temperature and pressure, should be considered to be alarms or indirect indication of leakage to the containment. The require ments of Regulatory Guide 1.45 and Standard Review Plan 5.2.5 and plant incorporated systems that meet those requirements are tabulated in.
V.
Conclusions Our review indicates that the San Onofre Plant is in compliance with Regulatory Guide 1.45.
ENCLOSURE 1 TABLE 1:
REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION SYSTEM Plant S.R.P. 5.2.5 or Incorporated Reg Guide 1.45 System System Requirement
- 1) Sump Level Monitoring (Inventory)
X Yes, 1 or 2 Mandatory
- 2) Sump Pump Actuations Yes, 1 or 2 Monitoring (Time Meters)
X Mandatory Airborne Particulate Yes Radioactivity Monitoring X
Mandatory
- 4) Airborne Gaseous Yes, 4 or 5 Radioactivity Monitoring x
Mandatory
- 5) Condensated Flow Rate Yes, 4 or 5 from Air Coolers Mandatory
- 6) Containment Atmosohere Yes Pressure Monitoring X
Optional Containment Atmosphere Yes Humidity Monitoring X
Optional
- 8) Containment Atmosphere Yes Temperature Monitoring X
Optional
- 9) CVCS Makeup Flowrate Yes Optional
- 10) Portable Ultrasonic Yes Dete cto rs Optional
- 11) Air Conditioner Coolant No Temperature Rise
- 12) 13)