ML13324A927
| ML13324A927 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/28/1986 |
| From: | Medford M Southern California Edison Co |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| TASK-***, TASK-OR NUDOCS 8607300059 | |
| Download: ML13324A927 (7) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M. O. MEDFORD TELEPHONE MANAGER. NUCLEAR LICENSING 1(818) 302-1749 July 28, 1986 Director, Office of Nuclear Reactor Regulation Attention: G. E. Lear, Director PWR Project Directorate No. 1 U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Schedules for Actions Resulting from the Systematic Evaluation Program (SEP)
San Onofre Nuclear Generating Station Unit 1
Reference:
Letter, M. 0. Medford, SCE, to 3. A. Zwolinski, dated October 4, 1985 During the current outage, we were scheduled to provide several submittals regarding the SEP (see referenced letter).
Due to the manpower diverted to address the November 21, 1985 loss of power and water hammer event and other issues addressed during the current outage, we have had to delay a number of these projects. The enclosure to this letter provides a revised summary of remaining actions required as a result of SEP and provides new dates for completion of some of these projects. All changes are indicated by a change bar in the right column.
In addition, our response provided in the referenced letter indicated that for item 4.23.7.2, procedures were in place for isolation of certain steamline valves.
Our further review of the drain lines on the main steam system has identified additional drain valves that may need to be isolated. Revised item 4.23.7.2 in the enclosure reflects this information.
If there are any questions, please contact me.
Very truly yours, Enclosure PDR3ADO 860728 P
C 05000206 PDR
COMPLETION DATES FOR SEP PROJECTS IPSAR Topic Section No.
Title Requirement Completion Date 111-1 4.4 Classification of Perform the following analyses as Per 10 CFR 50.71(e)(3)(ii)
Structures, Systems and practical, otherwise evaluate component Components (Seismic safety significance.
and Quality) 4.4.1 Radiography Requirements Verify that specified components have Per 10 CFR 50.71(e)(3)(ii) been radiographed or volumetrically inspected; otherwise perform volumetric inspection.
4.4.2 Pressure Vessels Show compliance with fatigue analysis Per 10 CFR 50.71(e)(3)(ii) requirements.
4.4.3 Fracture Toughness Evaluate to determine if material Per 10 CFR 50.71(e)(3)(ii) toughness is sufficient to prevent failure.
4.4.4 Piping Assess impact on usage factor of gross Per 10 CFR 50.71(e)(3)(ii) discontinuities in Class 1 piping for cyclic loads.
4.4.5 Valves Verify on sampling basis that Class 1 Per 10 CFR 50.71(e)(3)(ii) valve stress limits meet criteria for body shape and Service Level C conditions; verify pressure-temperature rating of Class 2/3 valves.
4.4.6 Pumps Demonstrate fatigue analysis compliance Per 10 CFR 50.71(e)(3)(ii) for reactor coolant pumps; evaluate design of other pumps.
4.4.7 Storage Tanks Evaluate tanks to determine if Per 10 CFR 50.71(e)(3)(ii) specified stress limits are met.
-2 IPSAR Topic Section No.
Title Requirement Completion Date 111-2 4.5 Wind and Tornado Perform cost-benefit analysis of August 31, 1986 Loadings upgrading at specific windspeeds.
III-3.A 4.6 Effects of High Water Level on Structures 4.6.1 Groundwater Evaluate short-term hydrostatic load September 30, 1986 at grade.
Evaluate and justify lower levels if necessary.
4.6.2 Roof Loadings Demonstrate roofs can withstand ponding Complete 4/26/85 load, or propose corrective measures.
III-3.C 4.7 Inservice Inspection of Revise inspection program in accordance Prior to next inspection Water Control Structures with NRC staff comments.
Provide details of Intake Structure 10/4/85 Surveillance Program Inspect Seawall Complete Cycle IX Outage III-4.A 4.8 Tornado Missiles Perform cost-benefit per 111-2 above.
August 31, 1986 III-5.A 4.9 Effects of Pipe Break Perform fracture mechanics analyses, January 30, 1987 on Structures, Systems systems analyses, etc.
Determine and Components Inside need for change in leak detection Containment system sensitivity.
(Integrate Topic V-5)
III-5.B 4.10 Pipe Break Outside Perform fracture mechanics analyses, January 30, 1987 Containment systems analyses, etc.
111-6 4.11 Seismic Design Complete analysis of remaining safety Complete Cycle IX Outage related piping and implement necessary modifications.
III-7.B 4.12.1 Design Codes, Criteria, Confirm that seismic loads dominate See related topics and Load Combinations tornado loads and that correct combinations were used.
(Integrate with other topics 111-2, III-5.A, III-5.B) To be completed with other SEP topics.
-3 IPSAR Topic Section No.
Title Requirement Completion Date V-5 4.18 Reactor Coolant Pressure Boundary Leakage Detection 4.18.1.1 System Sensitivity See III-5.A.
January 30, 1987 4.18.1.2 Operability Requirements Provide Technical Specifications for November 14, 1986 surveillance regarding operability of leak detection systems.
4.18.1.3 Seismic Qualification Provide procedures or qualify one leak November 14, 1986 detection system.
V-11.B 4.21 Residual Heat Removal System Interlocks Requirements 4.21.2 Overpressurization Provide Technical Specifications for November 14, 1986 Protection of RHR System operability of Overpressure Mitigation System when necessary to protect RHR system.
VI-1 4.22 Organic Materials and Institute periodic inspection program.
Complete Post-Accident Chemistry Program to be done with Type A testing and will be visual inspection.
VI-4 4.23 Containment Isolation System 4.23.1.2 Key Control and Control Provide procedures for control panel Complete Panel Access Procedures access.
for Sequencer Door 4.23.4 Valve Location Seismically qualify lines.
Complete Cycle IX Outage 4.23.5 Isolation of Closed Seismically qualify lines.
Complete Cycle IX Outage Systems Isolation of Closed Develop procedures to identify when November 14, 1986 Systems CCW valves need to be closed for containment integrity.
-4 IPSAR Topic Section No.
Title Requirement Completion Date 4.23.6 Isolation of Air Seismically qualify lines.
Complete Cycle IX Outage Handling Unit Cooling Lines 4.23.7 Isolation of Branch Lines 4.23.7.1 Refueling Water Supply Provide administrative procedures and/or Complete Line locking devices for refueling water line.
Refueling Water Return Evaluate when to close valves in refueling November 14, 1986 Line water return line and incorporate in procedures as necessary.
4.23.7.2 Main Steamlines Develop procedures to isolate main November 14, 1986 steamline branch lines and drain taps.
VI-7.B 4.24 Engineered Safety Feature Provide automatic termination of To be determined in Switchover from Injection injection and a backup to the refueling accordance with ILS to Recirculation Mode water storage tank level indicator; (Automatic Emergency Core review procedures and training.
Cooling System Realignment)
VI-7.C.2 4.25 Failure Mode Analysis 4.25.4 Other Modifications Evaluate benefits of incorporating September 30, 1986 recommended modifications.
VI-10.A 4.26 Testing of Reactor Trip System and Engineered Safety Features, Including Response-Time Testing 4.26.1 Response Time Testing of Include testing now done by procedures November 14, 1986 Reactor Protection System into Technical Specifications.
4.26.2 Testing of Engineered Include test for Containment Spray November 14, 1986 Safety Features Actuation System in T.S.
IPSAR Topic Section No.
Title Requirement Completion Date VII-3 4.28 Systems Required for Safe Shutdown 4.28.3 TMI Task Action Plan Integrate into topics III-1, 111-2, Third pump installed Cycle IX.
Item III.E.1.1 "Auxiliary III-4.A, III-5.A, III-5.B, 111-6, VIII-3 Upgrade scheduled for Cycle.X Feedwater System and XV-2. Upgrade third train of refueling.
Evaluation" auxiliary feedwater.
VIII-l.A 4.29 Potential Equipment Implement modifications and Technical To be determined in Failures Associated Specification for undervoltage accordance with ILS with Degraded Grid protection.
Voltage Provide voltage monitoring program for Complete by letters tap settings.
December 4, 1985 and June 19, 1986 VIII-4 4.31 Electrical Penetrations No modifications are required;
- however, Complete Cycle IX Outage of Reactor Containment penetrations of concern were replaced as part of Environmental Qualification Program.
IX-3 4.32 Station Service and Cooling Water Systems 4.32.3 Component Cooling Water Install Dedicated Shutdown System.
Complete Cycle IX Outage System Passive Failures Develop procedures for use in event of November 14, 1986 CCW passive failure.
4.32.5 Independence of Saltwater See VI-7.C.2.
September 30, 1986 Cooling System Components 4.32.7 Saltwater Cooling System Perform reliability evaluation of August 31, 1986 Reliability saltwater cooling system.
-6 IPSAR Topic Section No.
Title Requirement Completion Date IX-5 4.33 Ventilation Systems 4.33.2 Switchgear, Cable Implement temperature monitoring program Complete by letter Spreading and 480-V and procedures.
January 17, 1986 Switchgear Rooms 4.33.3 Administration Building Develop a procedure for room Complete (Battery and Inverter hydrogen dispersion.
Room)
IX-6 4.34 Fire Protection Provide dedicated system.
Complete Cycle IX Outage XV-1 4.35 Decrease in Feedwater Determine corrective measures.
November 14, 1986 Temperature, Increase in Feedwater Flow, Increase in System Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve XV-2 4.36 Spectrum of Steam System Install additional train of motor-Third pump installed Cycle IX.
Piping Failures Inside driven auxiliary feedwater.
Upgrade scheduled for Cycle X and Outside Containment refueling.
GEH:6961F