ML13330A783
| ML13330A783 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/10/1979 |
| From: | Head J Southern California Edison Co |
| To: | Engelken R NRC Office of Inspection & Enforcement (IE Region V) |
| References | |
| NUDOCS 7910180497 | |
| Download: ML13330A783 (7) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE J. T. HEAD, JR.
ROSEMEAD, CALIFORNIA 91770 TELEPHONE VEn-August 10, 1979 213-5721472 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V
- Sute20, Wal71nut Cr.Eek 'Plaza 1990 N. California Boulevard Walnut Creek, California 94596 Attention:
Mr. R. H. Engelken, Director Docket No. 50-206 San Onofre Unit 1 Your letter dated July 2, 1979 forwarded IE Bulletin No. 79-14, "Seismic Analyses for As-Built Safety-Related Piping Systems."
The Bulletin requires action by licensees to verify that the seismic analysis applies to the actual configuration of safety-related piping systems.
Item 1 of the Bulletin requests that we identify (1) seismic analysis input information to be used in verifying conformance to the actual configuration of safety-related piping systems, and (2) those safety-related piping systems or portions thereof which are planned to be inspected during each sequential inspection identified in Items 2 and 3 of the Bulletin.
Item 2 of the Bulletin requests that we inspect one system in each set of redundant systems and all nonredundant systems which are accessible during normal reactor operation.
Item 3 of the Bulletin requests that we inspect all other systems which are accessible during normal reactor operation and all systems which are inaccessible during normal reactor operation. The objective of the inspections is to verify that the actual as-built configuration conforms to the seismic analysis input information identified in response to Item 1 of the Bulletin.
Submitted herewith as Enclosure 1 is our response to IE Bulletin No. 79-14.
The responses con tained in Enclosure 1 correspond to the item numbers given in the Bulletin.
71910180
-2 If you have any questions, or desire additional information concerning Enclosure 1, please contact me.
Very truly yours, Enclosure cc:
Director, Office of Inspection and Enforcement
ENCLOSURE 1 Responses to IE Bulletin No. 79-14 Seismic Analysis For As-Built Safety-Related Piping Systems San Onofre Nuclear Generating Station Unit 1 ITEM 1 As defined in the San Onofre Unit 1 Final Safety Analysis Report, the following piping systems or portions thereof are considered safety-related:
- 1. Reactor Coolant System-piping required to maintain the reactor poolant system pressure boundary'
- 2. Chemical and Volume Control System-piping associated with reactor coolant system letdown and charging, reactor coolant pump seal water injection and return, boi i
bthigad injection.
- 3.
Auxiliary Coolant System-piping associated with component cooling water, spent fuel pool cooling, residual heat removal
- 4.
Safety Injection System
- 5. Recirculation System
- 6. Containment Spray System
- 7. Hydrazine Additive System
- 8. Radioactivity Waste Disposal System-piping up to and including the first isolation valve to waste gas decay tanks and waste gas surge tank
- 9. Main Steam System-piping from steam generators to upstream side of turbine stop valves, including safety and relief valves
- 10.
Circulating Water System-piping associated with saltwater cooling water, auxiliary saltwater cooling water
- 11.
Miscellaneous Water System-piping associated with service water to saltwater cooling water pumps and turbine driven auxiliary feedwater pump for bearing cooling
- 12.
Feedwater and Condensate System-piping associated with Safety Injection System and Auxiliary Feedwater System
- 13.
Diesel Generator Systems
- 14.
Piping Required to Maintain Containment Penetration Integrity Seismic analyses on the systems described above were performed within the jurisdiction of the NSSS vendor (Westinghouse Electric Corporation), the Architect-Engineer (Bechtel Power Corporation) and the Southern California Edison Company. Following receipt of IE Bulletin No. 79-14, Westinghouse, Bechtel and SCE (engineering organization) were requested to provide the required seismic analysis input information for those systems within their jurisdiction.
-2 Since there were no record retention requirements in effect when San Onofre Unit 1 was designed and constructed, Westinghouse and Bechtel have been able to retrieve seismic analysis design documents for only a limited number of the systems described above.
However, Westinghouse and Bechtel are continuing to review their records in an attempt to locate seismic analysis design documents for the remainder of the systems described above.
In addition, SCE has retrieved the seismic analysis design documents for those systems within its jurisdiction, except for those associated with the diesel generator.lube oil system, the design of which was within the scope of work of the diesel generator manufacturer (DeLaval).
SCE has requested that DeLaval provide the required seismic analysis input information for this system necessary to respond to this item.
Seismic analysis design documents have been located for the following safety-related piping systems:
- 1.
Reactor Coolant System Primary Piping
- 2. Reactor Coolant System Pressurizer Spray Piping o Line 5011-4"1-2501R o Line 5011-3"-2501R o Line 5025-3"-2501R
- 3.
Reactor Coolant Pump Seal Water Injection and Return Piping o Line 2108-3"-2502R o Line 2014-3"-151R
- 4. Component Cooling Water Piping o Line 3090-8"-152N o Line 5056-2"-S2 o Line 8030-2"-S1 o Line 3122-2"-S1 o Line 3007-2"-A o Line 3009-2"-A o Line 3043-2"-A o Line 3044-2"-A o Line 3133-1"-HH6 o Line 3134-1"-HH6
- 5.
Residual Heat Removal Piping o Line 1990-3/4"-A o Line 1991-3/4"1-A
- 6.
--Safety Injection/Feedwater Pump Recirculation Piping
- 7.
Recirculation Piping o Line 737-8"1-HP o Line 6018-6 11-152R o Line 6018-6"1-HH2 o Line 6019-6"-152R
o Line 6019-6"-HH2 o Line 8050-4"-HH2
- 8. Containment Spray Piping
- 9. Main Steam Piping o Line 1-24"-EG o Line 6-24"-EG
- 10.
Feedwater and Condensate'Piping o Line 326-10"-EG o Line 329-10"-EG
- 11.
Containment Penetration Piping o Line 341-2"1-EG o Line 342-2"-EG o Line 343-2"-EG o Line 743-8"-KN o Line 756-8"-KN o Line 892-4"-KN o Line 2008-2"-2502R o Line 6016-4"-301R
- 12.
Diesel Generator Piping o Diesel Generator Fuel Oil Supply/Return (Day Tank To/From Diesel Generator) o Diesel Generator Cooling Water (From/To Heat Exchanger To/From Diesel Generator) o Diesel Generator Intake Air From Air Filter to Diesel Generator o Diesel Generator Starting Air o Diesel Generator Exhaust
- 13.
Reactor Overpressure Instrument Air/Nitrogen Piping o Line Instrument Air From Main Header to N2 Lines 2532-3/4n1-HM2 and 2533-3/4"-HM2 o Line N2 2532-3/4"-HM2 o Line N2 2533-3/4"-HM2
- 14.
Feedwater Pump Lube Oil Cooling Piping o Line 1995-1"-A-3ACB o Line 1996-1"-A-3ACB In addition to the continuing efforts to retrieve the remainder of the seismic analysis design documents., Westinghouse, Bechtel and SCE are reviewing the available design documents described above in order to identify the inspection elements to be used to verify that the seismic analysis input information
-4I conforms to the actual configuration of the safety-related piping systems.
It is expected that a list of design documents, including the inspection elements, will be submitted by August 31, 1979.
As discussed above, the record search for additional seismic analysis design documents is continuing and may be completed before that date. The list, which will be submitted, will identify all design documents, including inspection elements, which have been retrieved.
Since additional time is required to identify the design documents and inspection elements, the inspections required by Item 2 of the Bulletin are scheduled for completion by October 1, 1979 (within 90 days of the date of the Bulletin rather than the 60 days specified therein).
The inspections required by Item 3 of the Bulletin are scheduled for completion within the 120 days specified in the Bulletin.
The systems, or portions thereof, which are planned to be inspected during each sequential inspection identified in Items 2 and 3 the Bulletin are described below.
As part of the Seismic Reevaluation Program at San Onofre Unit 1, which has now been integrated into the Systematic Evaluation Program, a number of certified, as-built drawings of safety-related piping systems were prepared.
A comparison against these drawings will be made to the extent possible, as the method to verify that the seismic analysis input information conforms to the actual configuration of safety-related systems. A review of station documentation is under way to confirm that modifications to the systems have not been made since the certified as-built drawings were prepared.
ITEM 2 The systems, or portions thereof, which are accessible during reactor operation include:
- 1. Chemical and Volume Control System-piping outside containment and not located in a high radiation area
- 2. Auxiliary Coolant System-piping outside containment
- 3.
Safety Injection System-piping outside containment
- 4.
Recirculation System-piping outside containment
- 5. Containment Spray System-Hydrazine Additive System-piping outside containment
- 6. Radioactive Waste Disposal System-piping is accessible but tanks are located in a high radiation area
- 7.
Main Steam System-piping outside containment
- 8.
-Circulating Water System
- 9.
Miscellaneous Water System
- 10.
Feedwater and Condensate System-piping outside containment
- 11.
Diesel Generator Systems
- 12.
Containment Penetration Piping-piping outside containment ITEM 3 The systems, or portions thereof, which are inaccessible during reactor operation include:
- 2. Chemical and Volume Control System-piping inside containment and piping outside containment which is in a high radiation area
- 3.
Auxiliary Coolant System-piping inside containment
- 4.
Safety Injection System-piping inside containment
- 5.
Recirculation System-piping inside containment
- 6.
Containment Spray System-Hydrazine Additive System-piping inside containment
- 7. Radioactive Waste Disposal System-piping adjacent to the tanks
- 8. Main Steam System-piping inside containment
- 9. Feedwater and Condensate System-piping inside containment
- 10.
Containment Penetration Piping-piping inside containment