ML13330A255
| ML13330A255 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/16/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Dietch R Southern California Edison Co |
| References | |
| TASK-07-01.A, TASK-07-02, TASK-07-03, TASK-7-1.A, TASK-7-2, TASK-7-3, TASK-RR LSO5-81-03-030, LSO5-81-3-30, NUDOCS 8103200525 | |
| Download: ML13330A255 (7) | |
Text
Docket No. 50-206 March 16 1981 LS05-81-03-030 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:
SUBJECT:
SEP TOPICS VII-1.A, VII-2 AND VII SAN ONOFRE REQUEST FOR ADDITIONAL INFORMATION The enclosed request for additional information has been prepared as part of our evaluation of the subject topics for San Onofre.
Response within 30 days is requested so that we maintain the present SEP review schedule.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/enclosure:
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UNITED STATES Vo NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 16, 1981 Docket No. 50-206 LS05-81-03-030 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:
SUBJECT:
SEP TOPICS VII-l.A, VII-2 AND VII SAN ONOFRE REQUEST FOR ADDITIONAL INFORMATION The enclosed request for additional information has been prepared as part of our evaluation of the subject topics for San Onofre.
Response within 30 days is requested so that we maintain the present SEP review schedule.
Sincerely, Dennis M, Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
As stated cc w/enclosure:
See next page Sc 8 10 820-0
Mr. R. Dietch 2 -
March 16, 1981 cc w/enclosure:
Charles R. Kocher, Assistant Director, Criteria and Standards General Counsel Division Southern California Edison Company Office of Radiation Programs Post Office Box 800 (ANR-460)
Rosemead, California 91770 U. S. Environmental Protection Agency David R. Pigott Washington, D. C. 20460 Samuel B. Casey Chickering & Gregory U. S. Environmental Protection Three Embarcadero Center Agency Twenty-Third Floor Region IX Office San Francisco, California 94111 ATTN:
EIS COORDINATOR T
215 Freemont Street Jack E. Thomas 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 U.o U. S. NRC P. 0. Box 4329 San Clemente, California 92672 Mission Viejo Branch Library 224851 Chrisanta Drive Mission Viejo, California 92676 Mayor City of San Clemente San Clemente, California 92672 Cha irman 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
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION ON SAN ONOFRE UNIT 1 FOR SEP TOPICS VII-l.A, VII-2 AND VII-3
- 1. The information provided in response to our letter of February 14, 1980 does not adequately address GDC 19 requirements for remote shutdown capability.
Provide responses to the following.requests for additional information:
A. Please provide electrical schematics (including control circuits) and panel layout drawings for the following valves from valve solenoid to power source and, for each valve, state the position assumed by the valve upon loss of air:
(1) SV 84 SV 88 ref. P&ID 568773-13 SV 86 SV 89 SV 87 SV 90 (2) SV 149 SV 151 ref. P&ID 568779-21 SV 150 (Please note SV 150, part of CV 144, and FC 144 appears to be shown as SV 157, but the drawing is not clear).
B. With reference to drawing 5102174-30, describe the functioning of automatic transfer switches upon restoration of the normal power source and provide a detailed schematic for transfer switches 1, 2, 3 and 5.
C. Provide the diesel generator breaker control schematic drawings.
- 2. The drawings enclosed with your letter of February 19, 1981 do not provide sufficient information for an independent review. Accordingly, for each P&ID listed below, provide the schematics and one line drawing for the power and control circuits for the specified equipment:
A.
P&ID 568779-21 (1) Pump Motors: G-lA, 1B, IC, lD, 3A, 3B, 105 (2) Motor Operated Valves:
20, 21, 22, 852A, 852B, 854A, 854B B. P&ID 568776-21 Pump Motors:
G-11, G-11S, 28, 28S
-2 C.
P&ID 568768-15 (1) Pump Motors:
G-14A, 14B, 15A, 15B, Thermal Barrier Emergency Cooling Pump (2) Motor Operated Valves:
720A, 720B, 813, 814, 822A, 822B, 833, 834 (3) Other Valves:
CV-772A, B, C; TCV (YM/TC/TI/TE) 601A&B D. P&ID 568775-22 (1) Pump Motors:
G-13C; G43A,B,C (2) Motor Operated Valves: 9, 10, 11, 12 (3) Other Valves:
POV 3,4,5,6,7,8,11, SV 79,80 E. P&ID 568780-18 (1) Compressor Motors:
Emergency Compressor (2) Valves SV 62, 105, 106, 107, 147, CV/PC-41, CV/SV-125 F. P&ID 568769-14 (1) Pump Motors:
G-8A, B, 27N, 27S, 45A, 45B, 50A, 50B (2) Motor Operated Valves:
18, 19, 356, 357, 358, 850A, 850B, 850C 851A, 851B, 851C, 853A, 853B, 866, 885, LCV-1100B,C,D (3) Other Valves:
CV36, 37, 92, 875A, 875B (4) Instrumentation:
FQ 500, FY 500, FY 501, FQ 501, FIS 520 and 521, RMS 2055, 2056, 2059 G. P&ID 568767-19 (1) Pump Motors:
G-2B, 2BS (2) Other Valves:
CV-202, 203, 204, 287, 288, 291, 304, 305, 406A, 406B, 412, LCV-1102 A, LCV-1105; FCV-1115A,B,C,D,E,F, HCV-1117
-3
- 4. In addition to the above, please provide the following current schematics:
5149454 EID Safety Injection Circuitry 5150623 E/D Reactor Scram Breakers A & B 5150874 E/D Safety Injection Sequencer #1 5150875 E/D Safety Injection Sequencer #2 5150884 Schem. Diag. Nuclear Inst. Power Range Drawer Sh 2 5151820 Permissive Relay Circuits For Scram Breaker Trip 5153972 Sh 1&2 Schematic Diagram Logic/Sequencer Cons. Cont.
N-1541 Sh 1 E/C Turbine
- 5.
The FSAR and available drawings do not contain sufficient information.
lor us to review the degree of isolation between reactor trip systems, engineered safety features, and non-safety control systems. Therefore, please provide the following additional information:
A Describe the isolation buffer devices used in the following cir
-uiStry and how these dev ices satisfy the requirments of.IEEE Standard 279-1968:
(t roIsolation between SIS flow-monitoring channels in flow com parators A-i, A-,
and A-3 (2)
Isolation between the delta temperature channel current loops and the computer, the flow control system, and the RPS pressure channels (3) Isolation between the pressurizer high water level channels and the pressurizer level control circuits (4) Isolation of the steam and feedwater flow mismatch channels between channels, isolation from the cptimac computer, and from the flow control system (5) Isolation between the four power range nuclear channels and the comparator system.
-4 B. Provide current elementary or schematic drawings of the following systems:
(1) Control circuitry for the containment isolation system (2).
One-line diagrams or panel drawings for the 120V ac regula ted and unregulated power to the RPS and ESF systems.
C. Identify the type of relay(s) used in the RPS and ESF for signal isolation by make and model number.