ML14138A087
| ML14138A087 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/02/1982 |
| From: | Paulson W Office of Nuclear Reactor Regulation |
| To: | Dietch R SOUTHERN CALIFORNIA EDISON CO. |
| Shared Package | |
| ML14079A135 | List: |
| References | |
| TASK-09-05, TASK-9-5, TASK-RR LSO5-82-11-004, LSO5-82-11-4, NUDOCS 8211100350 | |
| Download: ML14138A087 (7) | |
Text
November 2, 1982 Docket No. 50-206 LS05-82-11-004 Mr. R. Dietch, Vice President Nuclear Engineering and Operations Southern Califo nia Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Dietch:
SUBJECT:
SEP TOPIC IX-5, VENTILATION SYSTEMS SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 Enclosed is a copy of a Safety Evaluation Report of Systematic Evaluation Program Topic IX-5, Ventilation Systems. This evaluation is based on our contractor's, the Franklin Research Center, Technical Evaluation Report (TER-C5257-413), and your December 16, 1981 topic assessment.
This evaluation will be a basic input to the Integrated Safety Assessment for your facility. A determination of the need to actually implement modifications will be made during the integrated assessment. This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic is modified before the integrated assessment is completed.
Sincerely, Walt Paulson,,'Project Manager
Enclosure:
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGo :1981-335-960
Mr. R. Dietch cc Charles R. Kocher, Assistant General Counsel James Beoletto, Esquire Southern California Edison Company Post Office Box 800 Rosemead, California 91770 David R. Pigott Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111 Harry B. Stoehr San Diego Gas & Electric Company P. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U. S. NRC P. 0. Box 4329 San Clemente, California 92672 Mayor City of San Clemente 7
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 U. S. Environmental Protection Agency Region IX Office ATTN:
Regional Radiation Representative 215 Freemont Street San Francisco, California 94111 Robert H. Engelken, Regional Administrator Nuclear Regulatory Commission, Region V 1450 Maria Lane Walnut Creek, California 94596
TOPIC IX-5 SEP REVIEW VENTILATION SYSTEMS FOR THE SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1
I.
INTRODUCTION To assure that the ventilation systems have the capability to provide a safe environment for plant personnel and for engineered safety features, it is necessary to review the design and operation of these systems. For example, the function of the spent fuel pool area ventilation system is, to provide ventilation in the spent fuel pool equipment areas, to permit personnel access, and to control airborne radioactivity in the area'during normal operation, anticipated opera tional transients, and following postulated fuel handling accidents.
The function of the engineered safety feature ventilation system is to provide a suitable and controlled environment for engineered safety featu'e components following certain anticipated transients and design basis accidents.
II. REVIEW CRITERIA The current licensing criteria are identified in Section 2 of FRC Report TER-C5257-413, "Review of the Design and Operation of Ventilation Systems for SEP Plants, San Onofre."
III.
RELATED SAFETY TOPICS AND INTERFACES The scope of review for this topic was limited to avoid duplication of effort since some aspects of the review were performed under related topics. The related topics and the subject matter are identified in Section 3 of FRC Report TER-C5257-413.
IV. REVIEW GUIDELINES In determining which systems to evaluate under this topic, the staff used the definition of "systems important to safety" provided in Regulatory Guide 1.105. The definition states that systems important to safety are those necessary to ensure (1) the integrity of the reactor coolant pressure boundary, (2).the capability to shutdown the reactor and maintain it in a safe condition, or (3) the capability to prevent, or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guidelines of 10 CFR Part 100, "Reactor Site Criteria."
This definition was used to determine which systems or portions of systems were "essential."
Systems or portions of systems which perform functions important to safety were considered to be essential.
V, EVALUATION The systems reviewed under the topic are the Control Room Area Ventilation System, Reactor Auxiliary Building Ventilation System, Fuel Storage Building Ventilation System, and Engineered Safety Features Ventilation Systems. While the FRC report addresses the con tainment sphere purging and exhaust system it is beyond the defined scope of this topic.
-2 A. Control Room Area Ventilation System The function of the Control Room Area Ventilation System (CRAVS) is to provide a controlled environment for the comfort and safety of control room personnel and to assure the operability of control room components during normal operating, anticipated operational transient and design basis accident conditions.
As a result of TMI this system is being reviewed generically (TMI Item IIID.3.4, Control Room Habitability) to assure compliance with Criterion 19, "Control Room" of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50. Therefore, the CRAVS was not reviewed under this topic.
B. Fuel Storage Building Ventilation System The function of the Fuel Storage Building Ventilation System (FSBVS) is to maintain ventilation in the spent fuel pool equipment areas, to permit personnel access, and to control airborne radioactivity in the area during normal operation, anticipated operational transients, and following postulated fuel handling accidents. Based on the results of Franklin Research Center evaluation, we have determined that this is non-essential as defined in Section IV.
C. Reactor Auxiliary Building Ventilat.ion_.System The function of the Reactor Auxiliary Building Ventilation System (RABVS) is to provide ventilation during normal operation for areas within the reactor auxiliary building, including the liquid radwaste hold up tank rooms,.the demineralizer area, the spent resin cubicle,.the liquid radwaste processing area, the gaseous radwaste processing and decay area, the charging pump room, and the boric acid control area.
Of the equipment ventilated-only the charging pumps are considered essential.
For a detailed description of this ventilation system see Section 4.4 of the Franklin Report. As indicated in the Franklin Report this ventilation system is subject to disabling single failures. The licensee should either demonstrate that ventilation of the charging pumps is unnecessary or propose a corrective action. In addition, if ventilation is required, the licensee should provide procedures which would assure ventilation will be manually initiated in a timely manner.
-3 D. Engineered Safety Features Ventilation This section reviews the ventilation of safety-related systems and components necessary for safe shutdown and post-accident operation that were not reviewed above under the topics of major building ventilation systems.
- 1. Diesel Generator Building Ventilation System The Diesel Generator Building houses the diesel generators and their auxiliaries, station batteries and hydrogen recombiner control panels. A description of this buildings ventilation system is provided in Section 4.7.1 of the Franklin Report, Based on the information provided in that report the staff has determined that all acceptable criteria relative to this ventilation system are satisfied.
- 2. Switchgear and Cable Spreading Room Ventilation The room,'located in the Administration Building, contains the 4160V switchgear, 480V switchgear No. 1 and cables,all of which are considered essential.
Ventilation consists of a single fan which fails to meet single failure criteria. The licensee should either demonstrate that ventilation of this equipment is unnecessary or propose a corrective.actior.
- 3. 480V Switchgear Room Ventilation The 480V Switchgear Room is located the Fuel Storage Building.
The room houses the 480V switchgear and cabling,both of which are considered essential.
Ventilation of this room consists of a single fan, which fails to meet single !failure criteria.
The licensee.should either demonstrate that ventilation of his equipment is unnecessary or propose a corrective action.
- 4. Administration Building Ventilation System The function of the Administration Building, Ventilation System is to provide a controlled environment in the administra tion building for the comfort of the personnel.
This building also contains the battery room, the radiochemical laboratory, the sample station, and the chemical control room.
Only the battery and inverter rooms are considered essential.
Since this ventilation system fails to meet single failure criteria, the licensee should either demonstrate that ventila tion of this equipment is unnecessary or propose a corrective
- action,
-4
- 5. Turbine Building The Turbine Building houses the following essential equipment:
instrument air compressors, auxiliary feedwater pumps, invertor battery, battery charger for valve MOV850C, motor control center No. 3 and portions of the emergency core cooling system, Because a major portion of the turbine building is open to the outside atmosphere an active ventilation system was not included in the design of this building.
VI.
CONCLUSION The following area ventilation systems at the San Onofre Nuclear Generating Station, Unit 1 were found not to be in conformance with current licensing criteria:
Reactor Auxiliary Building Switchgear and Cable Spreading 480V Switchgear Administration Bui ding For each of the above area ventilation systems the licensee should either demonstrate that ventilation is-unnecessary or-propose corrective measures.
Each item will be resolved as part of this plant's integrated assessment, VII.
REFERENCES 1,
Letter from R. Krieger (SCE) to D. Crutchfield (NRC), "Safety Assessment Report for SEP Topic IX-5," dated December 16, 1981.
- 2. Franklin Research Center Report C5257-413, Review-of the Design and Operation of Ventilation Systems for SEP Plants, San Onofre, Unit 1, dated August 24, 1982.