ML13330A266
| ML13330A266 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/17/1981 |
| From: | Haynes J SOUTHERN CALIFORNIA EDISON CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 TAC-44128, NUDOCS 8103240359 | |
| Download: ML13330A266 (22) | |
Text
Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 J. G. HAYNES 1Iarch 17, 1981 MANAGEROFNUCLEAROPERATIONS U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement
- 1981 Region V 1990 North California Boulevard Suite 202, Walnut Creek Plaza Walnut Creek, California 94596 Attention:
Mr. R. H. Engelken, Director DOCKET No. 50-206 SAN ONOFRE - UNIT 1
Dear Sir:
Provided herewith as Enclosure (1) to this letter is a listing containing a brief description of design changes completed during 1980.
Submittal is pursuant to directives contained in 10 CFR 50.59(b) and includes a summary of the safety evaluation of each. Enclosure (2) to this letter forwards our report on challenges to relief and safety valves in accordance with Section II.K.3.2 of NUREG-0578. An original and two copies are provided.
Should you have any questions regarding this submittal, please contact me.
- Sincerel, Enclosures cc:
L. Miller (NRC Resident Inspector - San.Onofre Unit 1)
Director, Office of Inspection and Enforcement (40)
D. M. Crutchfield, Branch Chief, DOL, NRR 8108240359
U.S. Nuclear Regulatory Commission Page #2 bcc: L. T. Papay (2)
P, Dietch NARC Members (8)
-OSRC Members (9)
SR.. Kocher/J.A. Beoletto D. R. Pigott, Esq. (Chickering & rgory)
. C. Moody/R. W. Krieger "W. W. Strom G. W. McDonald SE. Nunn/J. D. Dunn J.Willis K Hadley
,Compliance Engineer
-STA S. Valdivia EDM Files 4"
ENCLOSURE (1)
SAN ONOFRE NUCLEAR GENRATING STATION UNIT 1 DESIGN CHANGES APPROVED DURING THE YEAR 1980 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS & ELECTRIC COMPANY DOCKET NO. 50-206 LICENSE NO. DPR-13
Page 1 DESIGN CHANGES -
1980 UNIT 1 The following design changes were approved for implementation by the On Site Review Committee in 1980. Except as noted, the design changes were fully implemented as of the end of the calendar year 1980. This list fulfills the reporting requirements of the 10 CFR 50.59(b) and Environmental Technical Specification 5.6.1.b. With respect to the latter requirement, none of the 1980 changes resulted in a condition which significantly altered the impact of the Station on the environment as described in the NRC Final Environmental Statement and did not involve a change in the Environmental Technical Specifi cations incorporated in the San Onofre Unit 1 Provisional Operating License
'SPR-13.
- 1. DESIGN CHANGE 80-01:
FUEL ASSEMBLY ECN's FOR CYCLE 8 RELOAD (In Progress)
The modifications described within this design change consist of twenty one (21) Engineering Change Notices (ECN's) which have been processed by Westinghouse. The ECN's concern Region 10 fuel assemblies which are scheduled to be loaded in Cycle 8.
- 2. DESIGN CHANGE 80-02:
MODIFICATION 10 VENT VALVE ACTUATORS TO LIMIT OPENING TO 50 This plant modification will Brovide stops to limit the opening of vent valves CV-10 and CV-116 to 50 from the fully closed position as required by the NRC letter of October 23, 1979. This modification was committed to for the January outage in SCE letter of January 15, 1980, to D. L.
Ziemann of the NRC from K. P. Baskin.
(See Page 3 of letter.)
The reason for this change is to satisfy NRC requirements as stated in NRC letter of october 23, 1979, to "limit the valves t6 be no more than 30 to 500 open.
DESIGN CHANGES-1980 (continued)
Page 2
- 3.
DESIGN CHANGE 80-03:
FEEDWATER FLOW STRAIGHTENER MODIFICATIONS This desi-gn change involves modifications to the feedwater flow straightener vanes and associated feedwater piping. The material and structural modifications are as follows:
Flow Straightener Vanes:
Th'e flow straightener vanes will be fabricated from 321 stainless steel tubing. The tubing shall be 1-7/8" 0.D. with a.095" wall thickness. Each tube will be attached to adjacent tubes with end welding and longitudinal welding.. (The previous design required end welding only.).
Feedwater Piping:
A flanged connection consisting of two 600# 10" flanges for schedule 80 piping will be installed upstream of the flow straightener vanes.
At the downstream edge of each flow straightener vane a retaining ring will be welded to the internal circumference of the feedwater piping.
- 4. DESIGN CHANGE 80-04:
THE INSTALLATION OF CONTAINMENT HYDROGEN RECOMBINERS (TMI)
(In Progress)
This plant modification consists of the addition of necessary supports for redundant safety related quality class hydrogen recombiners inside the containment sphere to deal with the long-term post LOCA generation of hydrogen.
The recombiners scheduled to be installed during a projected January 1981 outage will be mounted on steel platforms extended from the A&C steam generator enclosure structures at elevation 53'-6".
Access ladders will be provided from the operation deck (el. 42'-0") to the platform for required normal maintenance.
DESIGN CHANGES-1980 (continued)
Page 3
- 5.
DESIGN CHANGE 80-04 (Addendum I):
THE INSTALLATION OF CONTAINMENT HYDROGEN RECOMBINERS (In Progress)
Included in this Addendum I to Design Change 80-04 will be supports for conduit runs between the recombiners, the D. G. Building and the main Control Room..The recombiner's heaters will be powered from 480 volt Motor Control Centers 1B and 2B.
Power for instrumentation and controls will come from the 120 V ac vital buses.
Each system will consist of one recombiner unit, including thermocouples, a control panel and a power supply panel.
The control panels will be located in the MCR. Power supply panels will be installed in the D.. G.
Building.
- 6. DESIGN CHANGE 80-05:
MODIFICATIONS TO ACCOMMODATE PRESSURIZER HEATERS EMERGENCY POWER (TMI) (In Progress)
This design change provides the following modifications:
- 1)
Feedwater Pump Recirculation Valves - The interlock design of these
.valves will be modified such that, depending on the status of HV-853 A &
B, appropriate circulation to the feedwater pumps is assured.
- 2) Reactor Coolant System Letdown - The function of the letdown line control valves CV-202, CV-203 and CV-204 will be modified so that on SIS they will be closed and can then be opened only by manual action subsequent to sequence reset.
- 3)
Safety Injection and Feedwater Pumps - (a) Removal of automatic engagement of overload protection circuits for the pumps upon sequence reset, and (b) Addition ofan undervoltage trip feature for the S.I. pumps.
- 4)
Charging Pump - Modifications will be made to the control circuits for the pumps to retain the following interlock upon sequence reset:
Capability during SIS mode, to retain one charging pump connected to the same train power source as MOV-1100C running while the other charging pump is blocked by an interlock.
- 5)
Containment Spray Actuation System (CSAS) Auto Initiation - The CSAS control circuit will be modified to seal in auto initiation following sequencer reset until it is defeated by operation action.
DESIGN CHANGES -
1980 (continued)
Page 4
- 7.
DESIGN CHANGE 80-05 (Addendum I):
MODIFICATIONS TO ACCOMMODATE PRESSURIZER HEATERS EMERGENCY POWER (TMI)
(In Progress)
This design change addendum provides two modifications as a result of IE Bulletin 80-06. This bulletin essentially requires assurance that all safety related equipment remains in its emergency mode upon reset of SIS.
- 1. Feedwater Bypass Valves Modifications of the control scheme for these valves provides a latching type control on initiation of the safety injection signal such that on sequencer reset these valves can be controlled only by deliberate operator action.
- 2. Diesel Generator Electrical Trips On sequencer (SIS)-reset, the bypassed electrical trips are automatically placed in service even though the diesel generator is operating under emergency conditions.
The modification for this condition involves providing a latched signal to the electrical trips so that they are blocked until operation action.
- 8. DESIGN CHANGE 80-07:
ADDITION OF MECHANICAL PENETRATIONS (In Progress)
This plant modification consists of the addition of containment penetrations only, for sampling lines for obtaining samples of the reactor coolant and of the containment atmosphere. The sampling lines and associated systems will be incorporated by a future design change to be prepared later in 1981.
DESIGN CHANGES-1980 (continued)
Page 5
- 9. DESIGN CHANGE 80-08:
MODIFICATION OF THE RHR PUMP MOTOR SEAL (In Progress)
The work to be accomplished within this design change shall consist of the following modifications to two (2) Residual Heat Removal (RHR) System pump motor seals.
- 1) Replace existing motor seal with qualified Crane motor seal.
- 2)
Install motor seal vent and vent reservoir.
- 3) Provide lube oil lines to motor seal.
- 4) Replace existing lube oil with nonpareil turbine oil, AMOKON No. 32.
- 5)
Install Conax connector to junction box.
- 6)
Install new power cable and conduit, and splice to Conax unit.
- 7) Install lube oil temperature alarms.
- 10. DESIGN CHANGE 80-08 (Addendum I):
MODIFICATION OF THE RHR PUMP MOTOR SEAL (In Progress)
In addition to the work delineated in Design Change 80-08 this Addendum No. 1 incorporates the following additional modification to the RHR system:
- 8) Plug the existing motor enclosure vents.
- 11.
DESIGN CHANGE 80-09:
MODIFICATIONS TO THE SALT WATER COOLING PUMP SUPPORTS This design change describes modifications to be made to the pipe supports (9-415-12 and 9-416-14) that are attached to the Salt Water Cooling Pump Foundations. This design change also modifies the two vertical support legs by routing them to the floor slab and grouting the anchor bolts into the floor at this point. The two horizontal supports are to be routed to the floor with the structural elements also'attached by grouted-in anchor bolts.
DESIGN CHANGES-1980 (continued)
Page 6
- 12. DESIGN CHANGE 80-10:
BORIC ACID SYSTEM AND HEAT TRACING MODIFICATIONS During the 1980 Refueling Outage, certain portions of the Boric Acid
,System piping and all heat tracing and associated controls and power supplies will be replaced. All replacement Boric Acid System material is safety-related and construction will be to the appropriate editions of the same codes as the existing installation. Standards of construction will meet or exceed those of the original installation.
- 13.
DESIGN CHANGE 80-11:. GENERATOR ANTI-MOTORING RELAY MODIFICATION (In Progress)
This design change will simplify the circuit logic and increase the reliability of the individual trip circuits of the anti-motoring relay scheme. This design change actually addresses two modifications to the existing relay scheme.
- 14.
DESIGN CHANGE 80-12:
SALTWATER COOLING SYSTEM PUMP FOUNDATION MODIFICATIONS (In Progress)
This design change describes modifications to be made to the two (2) saltwater cooling pump foundations. During pump maintenance on the south saltwater pump, cracking was found on both concrete pump pedestal foundations.
Both north and south pedestals were found to have a horizontal crack running continuously around the pedestal about 6 inches below the top surface ranging from a hairline to a 1/2-inch in width. This design change will add 2 inches of concrete on all sides so' that sufficient exterior covering exists. Horizontal reinforcing spacing will be reduced to 12 inches.
DESIGN CHANGES -
1980 (continued)
Page 7
- 15.
DESIGN CHANGE 80-13:
MODIFICATIONS TO THE REFUELING WATER AND SAFETY INJECTION RECIRCULATION SYSTEMS (In Progress)
During the 1980 Refueling Outage, certain portions of the Refueling Water and Safety Injection System piping and associated valves will be replaced.
All replacement material is safety-related and construction will be to the appropriate editions of the same codes as the existing installation.
Standards of construction will meet or exceed those ofthe original installation.
- 16.
DESIGN CHANGE 80-13 (Revision 1):
MODIFICATIONS TO THE.REFUELING WATER AND SAFETY INJECTION RECIRCULATION SYSTEMS (In Progress)
This modification consists of replacing certain portions of the Refueling Water and Safety Injection System piping, associated valves, and supports.
All replacement material is safety-related, and construction will be to the appropriate editions of the same codes as the existing installation.
Standards of construction will meet or exceed those of the original installation.
- 17.
DESIGN CHANGE 80-14 (Revision 1):. MODIFICATION OF ANCHORAGE AND SUPPORT OF SAFETY-RELATED ELECTRICAL EQUIPMENT (In Progress)
This plant modification consists of upgrading existing anchorage and support for safety-related electrical equipment. Also included is positive seismic restraint for non-safety-related ancillary items that, in the event of an earthquake, could impact physically on and thereby disrupt operability of IE electrical or other safety-related equipment.
DESIGN CHANGES-1980 (continued)
Page 8
- 18. DESIGN CHANGE 80-15 (Revision 1):
MODIFICATIONS TO PROVIDE ISOLATION
. 'OF MAIN FEED FLOW BY INITIATING SIAS UPON 2 PSI CONTAINMENT PRESSURE (In Progress)
This design change will incorporate modifications to the safeguard load sequencing system (sequencers) logic to provide an additional signal to initiate safety injection upon 2 psi containment pressure. Sequencer logic will be revised to provide safety injection system actuation upon 2 out of 3 pressurizer low pressure OR 2 out of 3 containment high pressure.
The containment isolation system (IS) will be modified to provide a containment high-pressure signal to each sequencer.
- 19.
DESIGN CHANGE 80-16:
MODIFICATION TO COMPONENT COOLING WATER HEAT EXCHANGER (In Progress)
This design change describes modifications to the cover assemblies of the Component'Cooling Water Heat Exchangers. These heat exchangers are safety-related and the new cover assemblies will be fabricated to the original material specifications, i.e., carbon steel A-285 Grade C.
Design and fabrication will be in accordance withASME Boiler & Pressure Vessel Code, Sections VIII and XI.
- 20. DESIGN CHANGE 80-17:
MODIFICATION TO CONTROL ROOM HVAC SYSTEM DUCTING MEASURE CONTROL ROOM HEAT LOAD (In Progress)
This design change provides test ports in the Control Room HVAC system supply and return ducting to measure the Control Room heat load. This information is required to evaluate the capacity of the existing HVAC system to service the Onsite Technical Support Center (OTSC) to be located in the existing adjacent gallery.
DESIGN CHANGES-1980 (continued)
Page 9
- 21.
DESIGN CHANGE 80-18:
ADD VITAL BUS'SYSTEM STATUS INDICATION ON VERTICAL ELECTRICAL CONTROL BOARD (G12) (In Progress)
This design change describes modifications to the vertical electrical control board (C12) and 120 V ac bus system. A set of five indicating lights are to be installed. These lights will be used to provide status indication for the 120 V ac buses. The 28 V ac lamps are connected to their respective vital bus through a dropping resistor and fuse, as shown.
- 22. DESIGN CHANGE 80-19:
FIRE PROTECTION PROJECT SAFE SHUTDOWN MODIFICATION (In Progress)
This design change incorporates two manually operated isolation switches in the control circuits from the C-38 auxiliary control panel and the steam dump actuating solenoid valves SV-175 and SV-176.
The purpose of his isolation feature is to ensure that fire damage at the auxiliary panel will not impact the normal steam dump control.
- 23. DESIGN CHANGE 80-20 (Revision 1):
REMOVE SOUTH OFFSITE TRIGGER FOR STRONG MOTION ACCELEROGRAPH (In Progress)
Construction of the SONGS 2&3 PMF berm will result in the destruction of the buried section of the conductor to the south offsite trigger. This design change will make the following modifications:
- 1) Remove the Kinemetrics VS-1 south offsite trigger for the SONGS 1 strong motion accelerograph system.
- 2)
Install the VS-1 near the accelerograph recording station as a backup onsite trigger.
- 3) Remove the existing above ground section of the conductor to the south trigger site, including poles.
- 4)
Remove the small concrete slab at the trigger site.
DESIGN CHANGES -
1980 (continued)
Page 10
- 24. DESIGN CHANGE 80-21:
AMERTAP SCREEN -
CONDENSER DISCHARGE VALVE INTERLOCKING ALARM SYSTEM (In Progress)
This plant modification consists of the addition of a local alarm system intended to prevent damage of the Amertap Condenser Tube Cleaning System collector screens.
This design change provides for a local alarm interlocked with screen and valve position to alert the operator to a potentially damaging condition due to operation of the condenser discharge valve.
- 25.
DESIGN CHANGE 80-22:
PROVIDE AN ALARM FOR THE UPS SYSTEM TO BE ANNUNCIATED ON THE SECURITY COMPUTER (In Progress)
This modification will allow the Central Alarm Station operator to know when there is a failure or problem with the inverter feeding the Security computer system.
Alarms will be connected to the Security computer through unction box JB 809N and from there to a spare point in the transponder. The necessary information as to alarm message and type will have to modified in the software to accommodate these alarms.
- 26. DESIGN CHANGE 80-24:
SUB-COOLING MONITORING SYSTEM (In Progress)
This safety analysis has been prepared to evaluate the safety questions associated with installing conduit and cable runs associated with the sub-cooling monitoring system. In order to expedite construction of certain systems while a complete safety analysis of the sub-cooling system is undertaken, construction of the associated conduit and cable runs may progress without affecting other safety systems. This safety analysis, then, is only for cable and conduit installation as required for the sub-cooling monitoring system.
DESIGN CHANGES -
1980 (continued)
Page 11
- 27. DESIGN CHANGE 80-25:
MODIFICATION OF RADIATION SHIELDING FOR SPACES/
SYSTEMS THAT MAY BE USED IN POST-ACCIDENT OPERATIONS (In Progress)
The existing plant radiation shielding will be modified to permit personnel access to vital areas, including the new sampling building, and to protect safety equipment following an accident.
- 28. DESIGN CHANGE 80-25 (Addendum I):
MODIFICATION OF RADIATION SHIELDING FOR SPACES/SYSTEMS THAT MAY BE USED IN POST-ACCIDENT OPERATIONS (In Progress)
This Addendum No. 1 covers the following additional changes associated with the radiation shielding modification covered by Design Change 80-25.
- 1) Relocate blowdown piping to accommodate the shielding modification.
- 2)
Provide removable shielding at the personnel escape lock to permit transfer of equipment through the lock.
- 29.
DESIGN CHANGE 80-26:
REMOTE MANUAL OPERATOR FOR ALTERNATE HOT LEG RECIRCULATION VALVE (In Progress)
This design change consists of providing safety-related, seismic category, a remote manual operation for the alternate hot leg recirculation valve.*
This change will be accomplished in two phases, as follows:
Phase 1. Provide a mechanical linkage from the 2-inch globe valve to a handwheel outside the modified radiation shielding (installed per Design Change 80-25).
Phase 2. Provide a motor-driven valve operator that can be manually actuated from the main Control Room.
DESIGN CHANGES -
1980 (continued)
Page 12
- 30. DESIGN CHANGE 80-27 (Revisioni):
AUTO-INITIATION OF THE AUXILIARY FEEDWATER SYSTEM (In Progress)
The Auxiliary Feedwater System (AFWS) will be modified to include automatic initiation capability of both the turbine and motor-driven pumps, remote flow control capability and redundant pump discharge trains.
- 31.
DESIGN CHANGE 80-28 (Revision 2):
POST-ACCIDENT SAMPLING STATION (In Progress)
The purpose of this design change is to provide a shielded underground sample station which will be constructed to house the Post-Accident Sample System. The underground arrangement will minimize personnel exposure and preserve space or normal station activities.
- 32.
DESIGN CHANGE 80-29:
INCREASED RANGE OF IN-CONTAINMENT RADIATION MONITORS (In Progress)
This design change adds extended range radiation monitoring equipment capable of measuring post-accident in-containment radiation levels to 108 rads per hour with an accuracy of + 20 percent. Two separate and independent systems, each consisting of an in-containment detector with readout units in the main Control Room and the Technical Support Center (TSC), will be installed.
- 33. DESIGN CHANGE 80-30:
INCREASED RANGE OF NOBLE GAS EFFLUENT RADIATION MONITOR (In Progress)
This design change consists of an extended range plant stack effluent radiation monitor that will be capable of measuring post-accidqnt noble gas activ ty, as Xe-133, from concentrations of ALARA (1 x 10 pCi/cc) to 1 x 10 pCi/cc. The system will also provide grab samples for determining the 1-131 release.
DESIGN CHANGES -
1980 (continued)
Page 13
- 34.
DESIGN CHANGE 80-31:
STEAM DUMP AND SAFETY VALVE HEADER RADIATION MONITORS (In Progress)
This design change adds a radiation monitoring system for the two atmospheric steam dump valve and steam safety valve headers. The monitors will be installed at the headers to indirectly monitor the noble gis level by measuring the radiation level of the contained steam to 10 rads per hour with an accuracy of + 20 percent. Readout will be provided in the main Control Room and in the Technical Support Center.
- 35. DESIGN CHANGE 80-32:
ONSITE TECHNICAL SUPPORT CENTER (TMI) (In Progress)
This plant modification consists of the addition of an Onsite Technical Support Center (TSC) located adjacent to the main Control Room in the existing visitors viewing area and a mechanical equipment room on the southeast corner of the administration and control building. The TSC will contain equipment capable of monitoring plant critical functions, and files containing current plant drawings and documents. Operations data will be stored in a moving head disc system.
- 36.
DESIGN CHANGE 80-33:
CONTAINMENT PRESSURE INDICATION (In Progress)
Provided by this design change will be new, separate, and redundant containment pressure indicators. The new.transducers will tap from the same line as the existing pressure transducers.
Each system will consist of the following components:
Pressure transmitter Signal converter (I/V)
Control Room panel indicating instrument Instrument tubing and valves
DESIGN CHANGES -
1980 (continued)
Page 14 Z7. DESIGN CHANGE 80-34:
CONTAINMENT HYDROGEN MONITORING SYSTEM (In Progress)
A new Containment Hydrogen Monitoring System will be installed to provide redundant hydrogen sensing, analysis, indication and recording.
All instrumentation and controls for each.train will be separate and independent.
- 38. DESIGN CHANGE 80-35:
WIDE AND NARROW RANGE CONTAINMENT LEVEL INDICATION (In Progress)
This design change will provide for continuous indication of containment water level.
A narrow range instrument shall be provided to cover the range from the bottom to the top of the containment sump. A wide range instrument shall also be provided and cover the range from the bottom of the containment to the elevation equivalent to a 600,000-gallon capacity.
- 39.
DESIGN CHANGE 80-36:
REACTOR COOLANT SYSTEM VENTING (In Progress)
This design change consists of a remotely operated system for venting the reactor coolant system during post-accident situations when large quantities of non-condensible gases may collect in reactor coolant system high points. The venting system will utilize existing maintenance vent line stubs.
DESIGN CHANGES -
1980 (continued)
Page 15
- 40. DESIGN CHANGE 80-38:
AUXILIARY SALT WATLER COOLING PUMP PRIMING SYSTEM MODIFICATION (In Progress)
This design change describes modifications to be made on Auxiliary Salt Water Cooling Pump ASWCP) priming system. The following improvements will be made:
- 1) The ASWCP shaft packing with flush water will be replaced with a mechanical shaft seal, using the same flush water for boundary fluid injection.
- 2) The existing vacuum pipe between the pump and vacuum tank will be replaced by a standpipe approximately 25' high with a sight glass near the pump to give a quick visual indication of the prime water level.
- 3) An alarm to indicate the presence of water in the vacuum tank will be installed.
- 4)
An alarm to indicate insufficient vacuum will be installed.
- 5) Packless type valves will be installed.
- 6) Valves will be installed above and below the vacuum tank sight glass to allow it to be flushed out if it should become dirty or clogged.
- 41.
DESIGN CHANGE 80-39:
GMS, STAIRS, SRC DATA SYSTEMS (In Progress)
This design change covers the Bechtel scope of work for the following data systems:
- 1) Generation Maintenance System (GMS) is a computer system used to schedule plant maintenance and overhaul activities.
- 2)
Storage and Information Retrieval System (STAIRS) is a computer system used to retrieve documents from the EDMS master file.
- 3) SONGS Radiation Control (SRC) is a computer system used for monitoring and controlling personnel in and out of the Unit 1 facility.
DESIGN CHANGES -
1980 (continued)
Page 16
- 42. DESIGN CHANGE 80-40:
ADDITION OF LOSS OF POWER MONITOR AND. 125V DC INPUT DISCONNECT FUSES TO SEQUENCER (In Progress)
The sequencer system is also modified to include a 125V dc fused power disconnect switch assembly to the neon indicator panel.
This design change identifies work completed during the April 1980 outage, consisting of the addition of a sequencer neon indicator panel breaker subpanel.
- 43. DESIGN CHANGE 80-41:
TELECOMMUNICATIONS MODIFICATIONS (In Progress)
This design change provides for upgrading the telecommunications system for SONGS 1.
I/
- 44. DESIGN CHANGE 80-42:
SITE SECURITY SYSTEMS INTERFACE WITH SONGS 2 AND 3 (In Progress)
This plant modification consists of providing an uninterruptable power supply (UPS) connection to SONGS 2 & 3 for completion of its site Security System. In addition, the SONGS 2 & 3 Secondary Alarm Station (SAS) is being installed in the Site Security Building (located within the SONGS 1 site boundary).
- 45.
DESIGN CHANGE 80-44:
METEOROLOGICAL TOWER MODIFICATIONS (In Progress)
This modification consists of moving the majority of the signal conditioning and recording equipment associated with the meteorological monitoring system from its present location in a room adjacent to the SONGS 1 Control Room to a climate-controlled instrument shelter to be located near the Bluff Meteorological Tower.
- g 0
DESIGN CHANGES -
1980 (continued)
Page 17
- 46. DESIGN CHANGE 80-47:
STEAM GENERATOR TUBE SLEEVING (In Progress)
A large percentage of the tubes in all three steam generators show indication of circumferential degradation at the top of the tubesheet.
This design change justifies the use of a sleeve inserted within the tube replacing the tube as the pressure retaining boundary.
- 47. DESIGN CHANGE 80-48:
ADDITION OF SONGS 1 CONSTRUCTION POWER (In Progress)
This design change provides a 12kV/480V construction power load center for Unit 1. The existing 12kV source is on the backup circuit pole near the station auxiliary transformer.
- 48. DESIGN CHANGE 80-49:
SEQUENCER MODIFICATIONS TO ACCOMMODATE SMALL BREAK LOCA (In Progress)
This design change modifies the safeguard load sequencing to accommodate small break loss of coolant accidents.
- 1) Following SI, when pressurizer pressure and containment pressure have both returned to normal (as safety injection continues), a LOP occurs.
The sequencer will not operate as if a SIS/LOP has occurred. The D.G.'s will be automatically connected to the buses and the safety injection loads will be sequentially reinitiated.reinitiated.
- 2) In instances of safety injection followed by placing the block switch in the "block" position and subsequent LOP, the sequencers will operate as if a SIS/LOP has occurred. The block switch will be ignored, the D.G.'s will be connected to the buses and the safety injection loads will be sequentially reinitiated.
DESIGN CHANGES -
1980 (continued)
Page 18
- 49. DESIGN CHANGE 80-50:
REACTOR COOLANT PUMP LUBE OIL COLLECTION SYSTEM (In Progress)
A Tube oil drain system will be installed from the existing drain pans on the three reactor coolant pumps to a new lube oil drain tank. A flame arrestor will be included on the tank. The tank is of sufficient volume to hold approximately 400 gallons and should be checked periodically.
- 50. DESIGN CHANGE 80-52:
FUEL OIL TRANSFER PUMP DRAINAGE (In Progress)
This design change provides a drainage system (see Figure 1) for the fuel oil transfer pump vaults adequate for the removal of water resulting from any storm, up to and including the PMF, sufficiently rapid to limit the maximum depth of water in the vault to below the fuel oil transfer pump motor coupling. Check valves will be provided in the drain lines to prevent backflow. Curbing at grade will be improved to prevent flood runoff from entering the vaults.
- 51.
DESIGN CHANGE 80-53:
SONGS 2 AND 3 SECURITY INTERFACE WITH EXISTING SONGS 1 TOWER (In Progress)
This modification consists of:
(1) installing Security System annunciators in Guard Tower No. 2 for a portion of the Unit 2 boundary Security fence, and (2) installing an E-field on the Unit 2 Security fence adjacent to the south side of the SPF Building.
ENCLOSURE (2)
CHALLENGES TO RELIEF AND SAFETY VALVES This letter documents all challenges to the Relief and Safety Valves on Unit 1 for the year 1980.
Challenges to Relief Valves:
0 Challenges to Safety Valves:
0 This letter is responsive to a committment by Southern California Edison to the Nuclear Regulatory Commission, June 13, 1980, to include this list of challenges in this annual report.