ML20211N536
| ML20211N536 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/11/1986 |
| From: | Morgan H SOUTHERN CALIFORNIA EDISON CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| TAC-62092, NUDOCS 8607030140 | |
| Download: ML20211N536 (85) | |
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Southem Califomia Edison Company gg ;.n l 9 pg p sp SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 120 bb SAN CLEMENTE. CALIFORNIA 92672 H E. MORGAN T E LEPHOP!E sr ro~ ~ ~^"'"
June 11, 1986 U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Attention:
Mr. J. B. Martin, Regional Administrator
Dear Sir:
Subject:
Docket Nos. 50-206, 50-361 and 50-362 Facility Change Annual Report San Onofre Nuclear Generating Station, Units 1, 2 and 3 Pursuant to 10 CFR 50.59(b), this submittal provides the required annual report describing facility changes, procedure changes, tests, and experiments for Units 1, 2 and 3.
This report covers the period January 1 through December 31, 1985. Enclosure I contains a description and summary of facility changes which were approved for construction during 1985.
Enclosure II contains a summary statement regarding procedure changer, tests and experiments for the reporting period.
If there are any questions regarding this report, please so advise.
Sincerely, b
f*
Enclosures cc:
F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)
Director of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555 U.S. Nuclear Regulatory Commission, Document Control Desk -
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T ENCLOSURE I SAN ONOFRE NUCLEAR GENERATING STATION UNITS 1, 2 AND 3 1985 FACILITY CHANGES Index Unit 1 Facility Change No.
_ Title Page 1-85-3066.0 Replacement of Environmentally 1
Unqualified Containment Electrical Penetrations and Safety Related Cables 1-85-3066.1 Replacement of Environmentally 2
Unqualified Containment Electrical Penetrations and Safety Related-Cables CF-85-9146.2 Remodeling of the Office Area 3
of the Control-Administration Building in Unit 1 CF-85-9146.9 Modification of the Administration -
4 Operations Building Emergency Egress Lighting CF-85-9177.0 Addition of a Protective Clothing 5
Storage Facility 8098u
Index Unit 2 Facility Change No.
Title Page 2-84-6238.0, Revision 3 Letdown System Modifications 6
2-84-6238.1, Revision 1 Charging Pump Area Modifications 7
2-84-6372 Isolation and Removal of the 8
High Pressure Turbine Flange Warming System 2-85-6012.3, Revision 1 Installation of Backup Capability 9
Between the Plant Monitoring Computer (PMC) and the Core Operating Limit Supervisory System (COLSS) 2-85-6012.4 Addition of Selection Switch 10 for the Core Operating Limit Supervisory System Backup Computer System (CBCS) 2-85-6106 Station Telecommunications and 11 VHF Radio Modification 2-85-6166 Addition of a High Radioactive 12 Storage Area Sprinkler System 2-85-6198.2 Installation of Radiation 13 Monitor Recorders in the Main Control Room and Radwaste Control Room 2-85-6221 Installation of a Spare Mobile 14 Exciter 2-85-6241.1 Addition of Status Indication of 15 the Component Cooling Water System (CCW) Valves 2-85-6251 Addition of Data Communication 16 Circuits 2-85-6277 Replacement of Inadequate 17 Ball Drips 2-85-6345-Addition of Sonic Type Saltwater 18 Cooling Flow Monitoring Instrumentation 8098u
Index Unit 2 (Continued)
Facility Change No.
Title Page 2-85-6379 Modification of the Engineered 19 Safety Feature (ESF) Bypass /
Inoperable Status Indications and Alarm Logics 2-85-6401 Reroute the Waste Gas Surge 20 Tank Outlet Line and the Nitrogen Inlet Line 2-85-6404 Modification of the Containment 21 Purge Isolation System (CPIS),
Control Room Isolation System (CRIS) and Fuel Handling Isolation System (FHIS) Bypass and Status Indication Circuits 2-85-6418 Addition of Data / Communication 22 Circuits to Various Plant Locations 2-85-6420 Addition of a Halon 1301 Fire 23
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Protection System for the Telecommunications Room 2-85-6428 Addition of Condensate Storage 24 Tank Level Controls hy '
8098u O
Index Common Facility Change No.
Title Page 2/3-84-0188 Installation of an Eductor System 25 to Facilitate Degassing of the Reactor Coolant System through the Reactor Head Vent Discharge to the Normal Purge Exhaust -
Unit 3 2/3-84-0220 Addition of Electrical Power for 26 the Refueling Machine Auxiliary Hoist - Unit 2 2/3-84-0221 Addition of Electrical Power for 27 the Refueling Machine Auxiliary Hoist - Unit 3 2/3-84-0257 Containment Sump Inlet Flow 28 Monitoring Modification 7 nit 3 U
2/3-84-6160, Revision 3 Modification of the Source Range 30 Neutron Flux Monitoring System
- Unit 2
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2/3-85-004 Addition of a Shutdown Cooling 32 Heat Exchanger Inlet Temperature Monitor - Unit 3 o
2/3-85-009 Modifications to the Site 33 Emergency Evacuation Siren System 2/3-85-005 Addition of a Full Flow 34 2/3-85-013 Condensate Polishirg 2/3-85-018 Demineralizer System (FFCPD) -
2/3-85-021 Unit 2 2/3-85-024 2/3-85-032 2/3-85-034 2/3-85-050 2/3-85-058 2/3-85-060 i
8098u
Index Common (Continued)
Facility Change No.
Title Page 2/3-84-190, Revision 2 Addition of a Full Flow Condensate 35 2/3-85-022 Polishing Demineralizer System 2/3-85-023 (FFCPD) - Unit 3 2/3-85-030 2/3-85-033 2/3-85-042 2/3-85-052 2/3-85-059 2/3-85-061 2/3-85-066 2/3-85-067 2/3-85-068 2/3-85-070 2/3-85-071 2/3-85-073 2/3.-85-075 2/3-85-080 Modification of the Existing 36 Ventilation System for the Radwaste Control Panel Room 2/3-85-6066 Removal of Existing Chlorinating 37 System and Replacement with an Entirely New Unit 2/3-85-6098.4, Revision 1 Installation of Telecommunication 38 Cables to the Telecommunication Room
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Elevation 70'-0" 2/3-85-6161.7 Auxiliary Building Addition at 39 Elevation 63'-6" 2/3-85-6211 Replacement of the Chemical and 40 i
Volume Control System (CVCS)
Purification Filter Backflush System Electronic Logic Control with a Programmable Logic Controller 2/3-85-6307 Replacement of Fire Doors 41 9
8098u t'V'
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Index Unit 3 Facility Change No.
Title Page 3-85-6012.1-Replacement of Computer Room 42 Ventilation Unit to Support Addition of Backup Computer System 3-85-6012.2, Revision 1 Installation of Core Operating 43 Limit Supervisory System Backup Computer System (CBCS) 3-85-6012.3 Installation of Backup Capability 44 Between the Plant Monitoring Computer (PMC) and the Core Operating Limit Supervisory System (COLSS) 3-85-6012.4, Revision 1 Addition of Selector Switch 45 for the Core Operating Limit Supervisory System Backup Computer System (CBCS) 3-85-6043 Addition of Main Steam Bypass 46 Valve Indication 3-85-6044 Addition of an Automatic Start 47 Capability to the Emergency Chilled Water System 3-85-6090 Addition of a Control Room 48 Indication for the Reactor Coolant System (RCS) Refueling Water Level 3-85-6123 Replacemsat of the Excore Linear 49 Power Sensor Signal with a Excore Log Power Sensor Signal 3-85-6151 Modification of the Low Point 50 Drains in the Waste Gas System 3-85-6160 Upgrade of the Source Range Neutron 52 Flux Monitoring System 3-85-6175 Replacement of the Reactor Coolant 54.
Drain Tank Inlet Flow Monitoring System 3-85-6198.2 Installation of Radiation Monitor 55 Recorders in the Main Control-Room and Radwaste Control Room 8098u
v Index Unit 3 (Continued)
Facility Change No.
Title Page
- 3-85-6218 Installation of a Multiplexer 56 in the Penetration Room and Thermocouples on the Steam Generator Exterior Surface Under the Thermal Shield 3-85-6221 Installation of a Spare Mobile 58 Exciter 3-85-6234 Modification of the Safety 59 Injection Pump Miniflow Isolation Valve Control Circuit 3-85-6238.0 Letdown System Modifications 61 j
3-85-6241 Addition of Status Indication 62 for the Component Cooling Water System (CCW) Valves 2
3-85-6252 Condenser Vacuum Trip Control 63 Modifications 3-85-6277 Replacement of Inadequate Ball 64 Drips 3-85-6299 Chemical and Volume Control 65 I
System (CVCS) Modifications 3-85-6345 Addition of Sonic Type Saltwater 66 Cooling Flow Monitoring Instrumentation 3-85-6354 Addition of Steam Generator 67 Blowdown System Flow Indication to the Plant Monitoring System (PMS)
Computer 3-85-6367 Replacement of Existing Valve 68 Position Transmitters and Positioners on the Steam Generator Feedwater Bypass and' Control Valves 3-85-6372 Isolation and Removal of the 69 High Pressure Turbine Flange Warming System 8098u
O Index Unit 3 (Continued) i Facility Change No.
Title Page 3-85-6379 Modification of the Engineered 70 4
Safety Feature.(ESF) Bypass /
Inoperable Status Indications and Alarm Logic i
3-85-6404 Modification of the Containment 71 Purge Isolation System (CPIS),
Control Room Isolation System (CRIS) and Fuel Handling Isolation System (FHIS) Bypass and Status 2
Indication Circuits 3-85-6428 Addition of Condensate 72 Storage Tank Level Controls 3-85-6574 Emergency Diesel Fuel Oil 73 Transfer Pump Control Modification CF-85-9027 Addition of a Multi purpose 74 Holding Facility i
CF-85-9173 Installation of 800 MHz VHF 75 Radio Consoles i
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i 8098u o
Facility Change 1-85-3066.0 Title Replacement of Environmentally Unqualified Containment Electrical Penetrations and Safety Related Cables Description This modification upgrades two existing containment pressure boundary electrical penetrations and cables for safety related circuits, which have been determined to be inadequate for environmental qualification ~
pursuant to 10 CFR 50.49, by installing qualified Conax Penetrations and Brand Rax Cables that were purchased specifically for the SONGS 1 Environmental Qualification Program.
l Safety Evaluation The function of the containment electrical penetration assemblies is to provide containment pressure integrity and to assure electrical 1
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continuity for safety related circuits penetrating the containment.
The replacement penetrations and cables fulfill the same function as the original penetrations and cables, and are being installed to meet the environmental qualification requirements of 10 CFR 50.49. The Fire Hazards Analysis will be revised to account for the addition of combustibles, but this addition does not increase the fire loading beyond the analyzed maximum permissible loading for the affected fire Zones.
Review of this modification concluded that neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the Final Safety Analyses (FSA) will be increased. This modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSA.
This design change does not impact any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements, and the 4
margin of safety as defined in the basis for any Technical Specification is not reduced.
8098u c..
Facility Change 1-85-3066.1 Title Replacement of Environmentally Unqualified Containment Electrical Penetrations and Safety Related Cables.
Description This modification upgrades two existing containment pressure boundary electrical pene.trations and cables for safety related circuits, which have been determined to be inadequate for environmental qualification pursuant to 10 CFR 50.49, by installing qualified Conax Penetrations and Brand Rax Cables that were purchased specifically for the SONGS 1 Environmental Qualification Program.
Safety Evaluation The function of the containment electrical penetration assemblies is to provide containment pressure integrity and to assure electrical continuity for safety related circuits penetrating the containment.
The replacement penetrations and cables fulfill the same function as the original penetrations and cables and are being installed to meet the environmental qualification requirements of 10 CFR 50.49. The Fire l
Hazards Analysis will be revised to account for the addition of combustibles, but this addition does not increase the fire loading beyond the analyzed maximum permissible loading for the affected fire zones.
Review of this modification concluded that neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSA will be increased. This modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSA.
This design change does not impact any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements and the margin of safety as defined in the basis for any Technical Specification is not reduced.
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l 8098u i
Facility Change CF-85-9146.2 i
Title Remodeling of the Office Area of the Control - Administration Building in Unit 1 Description This modification affects architectural features of the existing 3
Control-Administration Building and has therefore been designed to Quality Class NSR, Seismic Category C per the SONGS 1 Q-List Section 2.2.2.b.
None of the modifications are structural in nature, and therefore, the existing structural analysis for the building remains valid.
This modification does not interfere with or affect any safety related 4
systems or equipment. The design basis for the evaluation of this modification indicates there will be no effect on Safe Shutdown capability, since the battery room barriers are not altered by this i
modification. The Fire Hazards Analysis will be revised to incorporate the new building configuration.
Safety Evaluation Only nonsafety related architectural features, HVAC and electrical systems of the building are affected by this modification. The existing battery room and its perimeter boundaries will remain in their present condition, and the Safe Shutdown capability of the plant will not be decreased as a result of this modification. Consequently, all accident probabilities, consequences and scenarios remain bounded by existing FSA analyses.
r A review of this modification concluded that neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSA will be increased. This modification will not create the possibility for an 1
accident or malfunction of a different type than any previously evaluated in the FSA.
't None of the modifications included in this change package are specifically addressed in the Technical Specifications. Therefore, these changes will not affect the Limiting Conditions for Operation, Surveillance Requirements or other parameters of the Technical i
Specifications. As such, no technical basis or associated margins of safety are affected as a result of this change.
l 8098u "
Facility Change CF-85-9146.9 i
Title Modification of the Administration - Operations Building Emergency Egress Lighting Description This modification removes a temporary emergency light and adds two new emergency lights in the Administration - Operations Building.
Safety Evaluation f
These lights are nonsafety related and their power supply is taken from a nonsafety related panel. The new circuit does not affect any safety
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related system either physically or electrically. The Fire Hazard Analysis will be revised to reflect this modification.
t The purpose of the Emergency Lighting System is to illuminate the egress path from the Control-Administration Building during a postulated outage of the normal lighting system. Since the new emergency lights are added to the new evacuation route based on the existing design criteria, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSA will be increased by this modification.
In addition, this modification ill not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSA.
The Emergency Lighting System is
,t specifically addressed in the Technical Specifications. This modification will not affect the Limiting Conditions for Operation, Surveillance Requirements, or other parameters of the Technical Specifications.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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8098u t
Facility Change C F-85-9177.0 Title Addition of a Protective Clothing Storage Facility Description This modification adds a Protective Clothing Storage Facility consisting of an eight foot wide, twenty foot long steel cargo container within the Vital Area, adjacent to the new Health Physics Building. This modification was designed to Seismic Category C and 100 mph wind criteria, in accordance with SONGS 1 Retrofit General Design Criteria.
Safety Evaluation The Protective Clothing Storage Facility is not in the vicinity of any equipment or systems important to safety except the blowdown trench.
Potential loads resulting from the cargo container during a Design Basis Earthquake will not adversely impact the blowdown trench because the loads will be less than the design loads of the trench covers (H-20 truck wheel loads).
A review of this modification concluded that neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSA will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSA.
The Protective Clothing Storage Facility is not specifically addressed in the Technical Specifications and will not affect the Limiting Conditions for Operation, Surveillance Requirements, or other parameters of the Technical Specifications.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
Since the facility will be located in Fire Zone 1-AB-14-2J, Section 6.0 of the Fire Hazards Analysis (FHA) will be revised.
The addition of this facility will not adversely affect the FHA.
4 4
8098u..
Facility Change 2-84-6238.0, Revision 3 Title Letdown System Modifications Description This modification is to improve the characteristics and control of flow through the Boronometer and Process Radiation Monitor. This modification includes the following changes:
A.
Provides optimum flow of 8 and 5 gpm respectively, for Baronometer and Process Radiation Monitor from downstream of the filter instead of upstream of the filter to avoid crud in the system.
B.
Replaces existing flow indicator downstream of the Boronometer and Process Radiation Monitor with a venturi flow element which includes a flow indicating transmitter.
C.
Adds a control valve in the main letdown line complete with isolation valves, a bypass valve and a spring loaded check valve. Also adds throttle valves downstream of the Boronometer and Process Radiation Monitor to permit flow control through each instrument.
D.
Adds High Flow Annunciation at the main control panel and flow indication to the Critical Function Monitoring System (CFMS) for the sample flow through the Boronometer and Process Radiation Monitor instruments.
Safety Evaluation FSAR Section 9.3.4.1 discusses the design bases for the Chemical and Volume Control System (CVCS).
This modification does require a revision to the FSAR, but it does not adversely affect the operation, functions or design bases of the CVCS. The existing seismic analysis (FSAR 5.4.3.1),
high energy line break analysis (FSAR 3.6.2) and fatigue analysis (FSAR 3.9.'.1) have been reviewed and are not affected by this change and, as such, neither the consequences nor the probability of occurrence of an accidet or malfunction of any equipment important to safety previously evalua>ed in the FSAR will be increased.
In addition, this modification will not create the possibility for an accident or malfunction of a differsnt type than any previously evaluated in the FSAR.
The change has no effect on existing Limiting Conditions for Operation or Surveillance Requirements governed by the existing Technical Specifications.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
The Fire Hazard Analysis (FHA) will be changed to account for the increase of combustibles in the applicable fire zones. This is required due to the percentage fill of three cable trays exceed 30 percent fill. The maximum permissible fire loading is 80,000 Btu /sq. ft.
This addition will only add 0.4 Btu /sq. ft. to the existing' fire loading of 16,440 Btu /sq. ft.
This is far below the maximum permissible and will have no adverse effect on the FHA.
8098u i
Facility Change 2-84-6238.1, Revision-1 Title Charging Pump Area Modifications Description This is a modification to the Charging Pump Area instrumentation of the Chemical and Volume Control System (CVCS) and includes the following changes:
A.
Modifies and relocates the Charging Pump discharge Safety Valve return line and adds a flow venturi in the suction line of the Charging Pump to provide separate and remote pressure and flow indication for each pump.
B.
Relocates Charging Pump Instrumentation to the outside of the Charging Pump room. Adds a pressure tap and an instrument to facilitate pump testing.
C.
Adds charging capability for the suction and discharge accumulators from outside the Charging Pump rooms.
D.
Eliminate piping snubbers from inaccessible and/or high radiation locations by adding new support and/or modifying existing supports as necessary.
o Safety Evaluation FSAR Sections 9.3.4.1 discuss design bases for the CVCS system. This modification will revise the FSAR, but it will not adversely affect operation of the CVCS system, as the system functions remains as originally intended, and the design bases are unaffected. The existing seismic analysis (FSAR 5.4.3.1), high energy line break analysis (FSAR 3.6.2) and fatigue analysis (FSAR 3.9.1.1) have been reviewed and are not affected by this design change and neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, the modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
The change has no effect on existing Limiting Conditions for Operation or Surveillance Requirements governed by the existing Technical Specifications. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
The Fire Hazards Analysis (FHA) will be revised to account for the changes in the fire loading due to this modification, but these changes do not adversely affect the FHA.
8098u Facility Change 2-84-6372 i
Title Isolation and Removal of the High Pressure Turbine Flange Warming System Description This modification isolates the High Pressure (HP) Turbine Flange Warming System from the Condenser to eliminate air in-leakage into the Condenser.
Safety Evaluation Removal, abandonment, and/or isolation of the HP Turbine Flange Warming System will affect the Main Steam Supply System to the extent that main steam to this system is no longer required. As a result, the design basis of the Main Steam Supply System per FSAR Section 10.3.1 will 7
require a change to paragraph H deleting the HP Turbine Flange Warming System as one of the systems to which main steam is supplied.
In addition, FSAR Section 10.3.2.1 will also require changes.
The HP Turbine Flange Warming System is addressed in the FSAR Design Basis for the Main Steam Supply System, FSAR Section 10.3.1.
- However, per FSAR 10.3.3 (H) the Flange Warming System has no nuclear safety relationship or significance. The turbine manufacturer has determined that the Flange Warming System is not required for the HP Turbine at San Onofre given the operating quality and temperature of the steam.
Removal of this system from the Main Steam System will have no impact on Main Steam Supply Sy' stem components important to safety.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
This change has not alter the original Turbine or Main Steam design objectives and system functions. The HP Flange Warming System is not addressed in the Technical Specifications, therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
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8098u -
G Facility Change 2-85-6012.3, Revision 1 Title Installation of Backup Capability Between the Plant Monitoring Computer (PMC) and the Core Operating Limit Supervisory System (COLSS)
Description This modification fixes incore detector field cabling problems at the Auxiliary Protective Cabinet (APC), and provides a spare set of incore detector signals for the new COLSS Backup Computer System.
i Safety Evaluation This change eliminates the current APC Cabinet field cabling problems and provides a spare set of signals to the new COLSS Backup computer system.
It has no impact on any of the functions or design criteria of the incore instrumentation. As such, existing analyses in the FSAR are unaffected by this modification. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
The incore field cabling modification neither affects the functional design nor degrades the performance of the fixed incore detector instrumentation system. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
Fire Hazards Analysis (FHA) Sections 2-AC-30-20B will be revised to account for the increase in fire loading due to the implementation of this modification. The total fire loading, following implementation of the change, will still be below the maximum permissible value and will not adversely affect the FHA.
8098u Facility Change 2-85-6012.4 Title Addition of Selector Switch for the Core Operating Limit Supervisory System Backup Computer System (CBCS)
Description This modification adds a selector switch to enable an operator to select either the Plant Monitoring Computer (PMS) or the new CBCS for display, annunciation and Control Element Assembly (CEA) sequencing control.
Safety Evaluation The addition of a selector switch to improve the availability of the CBCS to facilitate compliance with the requirements of the Technical Specitications, has no impact on any of the functions or design criteria of the Core Operating Limit Supervisory System (COLSS) or CEA sequencing as described in FSAR Section 7.7.1.5.
However, FSAR Chapter 7.7 needs to be updated to reflect the addition of the CBCS.
As a result of this modification, neither the consequences nor the probability of occurrence of an accident or malfunction of any i
equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
This modification has no effect on any Technical Specification, Surveillance Requirements or Limiting Conditions for Operation since the COLSS software and CEA sequencing programs are functionally l
identical to those described in the FSAR. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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i 8098u j
Facility Change 2-85-6106 Title Station Telecommunications and VHF Radio Modification Description This modification accommodates completion of the site-wide tele-communications upgrade and installation of a 800 MHZ Radio System.
Safety Evaluation All changes included in this modification are related to telecommunication and lighting.
The telecommunications system are addressed in FSAR Section 9.52, the lighting systems are addressed in FSAR Section 9.5.3.
Both of these FSAR sections will require a revision, but the changes do not affect safety related equipment.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
This modification has no effect on existing Limiting Conditions for Operation, Surveillance Requirements, or other parameters governed by the existing Technical Specifications.
Therefore, the margin of safety as defined in the basis for any Technical Specifications is not reduced.
The Fire Hazard Analysis will require a revision to account for this modification, but the changes will have no adverse affect.
8098u Facility Change 2-85-6166 Title Additior, of a High Radioactive Storage Area Sprinkler System Description This modification provides for the addition of a Wet Pipe Sprinkler System to the High Radioactive Storage Area. The Sprinkler System is designed and constructed in accordance with NFPA-13 requirements.
Safety Evaluation This modification will require revision to the FSAR Section 9.5.1, but has no effect on systems which perform safety related functions and does not require any modifications to safety related structures, components or systems.
This modification does not increase the probability or conseque1ces of an accident or ma,1 function of equipment important to safety pre /iously evaluated in the FSAR, nor does it create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The changes have no effect on the existing Limiting Conditions for Operation or Surveillance Requirements governed by the existing j
Technical Specification. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
The Fire Hazards Analysis will be revised to account for this modification, but the maximum permissible fire loadings are not exceeded, therefore, there will be no adverse effects from this modification.
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8098u
- Facility Change 2-85-6198.2 Title Installation of Radiation Monitor Recorders in the Main Control Room and Radwaste Control Room Description This modification includes:
A.
Replacing the multipoint scanning recorders located on the radiation monitoring panels with continuous pen recorders.
B.
Relocating various radiation monitoring recorder points to the main control room control panels.
C.
Adding recorders for various redundant radiation monitoring channels which were not previously recorded.
D.
Adding a microprocessor-based multichannel recorder for various radiation monitoring channels to the radwaste control room.
Safety Evaluation The changes involved in this modification affect the Process and Effluent Radiological Monitoring System and the Area Radiation Monitoring System which have safety and nonsafety related design bases in the FSAR. This modification will require revisions to FSAR Sections 7.3.1.1.5, 7.3.1.1.10, 7.3.1.1.11, 11.5 and 12.3.4.. This modification allows the Process and Effluent Radiological Monitoring System and the Area Radiation Monitoring System to continue to function as specified in those design bases and setpoints are not changed.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR.
In addition, these modifications will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The equipment affected by this change is governed by the Technical Specifications, but does not affect any existing Technical Specification Limiting Condition for Operation or surveillance requirement. Therefore, the margin of safety as defined in the basis for any Technical Specification will not be reduced.
The Fire Hazard Analysis (FHA) will be revised to accommodate this modification, but the change does not adversely impact the fire protection system / program or violate the FHA. The additional fire loading due to this modification does not result in exceeding the maximum permissible fire loading.
8098u __
Facility Change 2-85-6221 Title Installation of a Spare Mobile Exciter Description This modification will facilitate the location and hookup of a Mobile Spare Exciter to allow continued operation of the main generator during major repairs of the permanent exciter.
Safety Evaluation The design bases and the safety evaluations for the Turbine-Generator are presented in FSAR Section 10.2.
T5e Turbine Generator has no safety related design basis as defined in the FSAR and no safety related equipment is located in the vicinity of the turbine.
All potential accidents and consequences remain bounded by the existing analyses; therefore, this change neither increase the probability or consequences of an accident or malfunction of any equipment important to safety, nor does it create the possibility of an accident or malfunction of a different type than any previously evaluated in the r
FSAR.
The equipment affected by this change is not governed by the Technical Specifications and any existing Technical Specifications Limiting Conditions for Operation or Surveillance Requirements is not affected.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification will require the revision of the Fire Hazards Analysis (FHA) to accommodate the increase combustible, but this mcdification does not adversely impact the fire protection system / program or violate the FHA.
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I 8098u..
Facility Change 2-85-6241.1 Title Addition of Status Indication of the Component Cooling Water System (CCW) Valves Description This modification brings the four (4) CCW system critical / noncritical loop isolation valve status inputs to the Critical Function Monitoring System (CFMS).
It also ensures the CFMS data base design complies with the regulatory requirements and its display algorithms function as designed.
Safety Evaluation This modification brings the existing limit switch ' contact signals in the Plant Monitoring System (PMS) termination cabinet to the CFMS termination cabinet in accordance with the established control and instrumentation circuit design criteria.
No control circuity or system functional modification is involved in this change and no degradation of IE/non-1E or redundant IE train separation is involved.
Although the modification will require a revision to the FSAR Sections 9.2.2 and 7.6.1.3 it will not affect the design bases described in these sections. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
Although the operability of the CCW system isolation valves 2HV-6212, 2HV-6213, 2HV-6218 and 2HV-6219 is required by Technical Specification Limiting Condition for Operation Section 3/4.7.3 and 3/4.3.2, this change merely utilizes the existing PMS terminals for CFMS inputs. No existing valve control circuity or the designed function of the valves is affected by this change. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
Minor changes to the computer room combustible loading will require a revision to the Fire Hazards Analysis, but all increases in loading are within the acceptable limits and will have no adverse effect.
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P Facility Change 2-85-6251 Title Addition of Data Communication Circuits Description This modification accomplishes the following:
A.
Enhances and satisfies expanded tool data handling requirements in the Hot Tool Room.
Installs three coaxial cables including two spares, to connect Cathode Ray Tube (CRT) display terminals in the Hot Tool Room (Elev.15' in the Unit 2 Piping Penetration Room) to Communication Room (Elev. 70' in the Control Building).
B., Provides digital data transmission between the Unit 3 Computer Room and the Units 2 & 3 Control Room and the Control Building lobby.
Installs three coaxial cable each to connect the IBM Multiplexer 2/3L569 in Unit 3 Computer Room to:
o Unit 2 Control Room o
Unit 3 Control Room o
Units 2 & 3 Control Building lobby Also two coaxial cables from 2/3L569 are to be installed to connect the hallway utility box outside of Units 2 & 3 Control Room.
Safety Evaluation All changes covered by this modification are related to data communications circuits only. All affected equipment, devices and wiring are Quality Class IV.
Addition of these new circuits will not affect safe shutdown or other safety related equipment; therefore, all accident probabilities, consequences, and scenarios remain bounded by existing analyses.
Neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR i~s increased.
In addition, the modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The new data communication circuits instal'ed by this modification do i
not impact any Technical Specification Limiting Conditions for Operation, parameter, or Surveillance Requirements. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification does not adversely affect the fire protection system / program, but does require a change in the Fire Hazards Analysis (FHA) to account for additional fire barrier penetrations and combustible materials.
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Facility Change 2-85,6277-Title Replacement of Inadequate Ball Drips i
Description i
This modification provides for the replacement of existing ball drip valves in the water spray fire protection systems for charcoal filters in SONGS Unit 2, with high quality ball drips of all metal l~
isolation valve causes the previous ball drips to stick in their closed
-construction. The annual system tests which cycle the upstream position. The replacement ball drips are provided with a plunger type
- device which can be used to clear ball drips should it become stuck.
2 Safety Evaluation This modification does involve a revision to Figure 9.5-1 of the FSAR, but it has no effect on systems which perform safety related functions and does not require any modification to safety related structures, J
components or systems. Therefore, neither the consequences nor the i
probability of an accident or malfunction of any equipment important to safety previously evaluated in FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The changes have no effect on the Limiting Conditions for Operation or i
Surveillance Requirements governed by the existing Technical Specifications. Therefore, the margin of safety as defined in the j
basis for any Technical Specification is not reduced.
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Facility Change 2-85-6345 Title Addition of Sonic Type Saltwater Cooling Flow Monitoring Inctrumentation Description This modification increases accuracy and reliablility in the indication of saltwater cooling flow by installing ultrasonic type flow sensors to the exterior of the system piping. The previous Component Cooling Water Heat Exchanger differential pressure method of determining the flow had not been very reliable.
A reliable flow indication is required for In-Service Inspection Test for the Saltwater Pumps (FSAR Section 9.2.1.4C, Technical Specification Sections 3/4.7.4 and 4.0.5).
The new flow indication will help monitor Saltwater Pump performance on a continuous basis, detect restricted flow through heat exchangers because of sea debris accumulation, and determine the necessity to initiate backflush of the heat exchangers. The addition of an abnormal flow indication and alarm will help detect a major malfunction in the system.
New cables and conduit runs were added from Salt Water Cooling System (SC S) tunnel to the main Control Room.
Safety Evaluation This modification installs ultra-sonic type flow sensors without penetrating or puncturing the flow pipeline, and does not adversely impact the saltwater cooling system. This modification provides monitoring of the system and does not interfere, impede or adversely affect any safety related or nonsafety related equipment and its function or operation.
The mass of the flow sensors on the SWCS pipe has a negligible affect on pipe seismic loads.
Although this modification requires a revision to FSAR Section 9.2, the functional design bases described in this section is not affected.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or n.alfunction of a different type than any previously evaluated in the FSAR.
The equipment and system affected by this change is governed by Technical Specifications, Section 3/4.7.4 and 4.0.5.
This change will not modify or affect any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
All floor and wall penetrations are properly sealed with Bisco seals and the new cables add negligible fire loads, which allows the total fire loading to stay within the maximum allowable fire loads for the affected zone. However, the Fire Hazards Analysis will be revised to account for the additional fire loadings.
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e Facility Change 2-85-6379 Title Modification of the Engineered Safety Feature (ESF) Bypass / Inoperable Status Indications and Alarm Logics Description This modification adds more information to the ESF Bypass / Inoperable Panel, eliminates unnecessary alarms and provides more logical alarm annunciations by rearranging portions of the ESF System's Inoperable Alarm logics based on Technical Specification Limiting Conditions for Operation.
The statuses of vital supporting equipment for the ESF System operations have also been included in the alarm logics to provide more meaningful ESF Inoperable Alarms.
Safety Evaluation All components and cabling added by this change are for status indication and alarming function only.
The quality class and seismic category of the equipment, cables and raceways added are compatible with the affected existing devices and the established design criteria. The ESF System Inoperable Alarm Logic rearrangements are made in such a way that no cross channel wiring connection results from this change and compliance with the requirements of Regulatory Guide 1.47 is maintained. The ESF Bypass / Inoperable Status Panel and its associated alarm annunciation system are strictly for ESF equipment status indication and alarm annunciation only.
No circuits performing control function or system which are needed for safe shutdown of the plant, are affected by this change.
This change neither alters the established design criteria n.or affects the designed function of the Bypass / Inoperable Status Indication and Alarm Systems. As such, neither the plant reliability, operability or maintainability is affected by this change. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunctior of any equipment important to safety previously evaluated in tre FSAR will be increased.
In addition, this modification will net crea:e the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The ESF Bypass / Inoperable Status Indication and Alarm System affected by this change, is neither governed by the Technical Specifications nor impacts the existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification requires a revision to the Fire Hazards Analysis (FHA) to account for the additional fire loading, but it does not adversely affect the FHA.
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Facility Change 2-85-6401 Title Reroute the Waste Gas Surge Tank Outlet Line and the Nitrogen Inlet Line Description This modification makes a change to the Gaseous Radwaste System (GRWS) to exchange the Waste Gas Surge Tank outlet line with the nitrogen inlet line.
It also replaces the existing copper oil tubes / fittings and adds pressure instruments to the Waste Gas Compressors.
Safety Evaluation This modification does require a revision to FSAR Section 11.3, which discusses the Gaseous Radwaste System design bases, but it does not adversely effect the design bases. Neither safety related equipment, structure or system nor the process parameters or pressure boundary integrity of the GRWS are adversely affected.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
Technical Specification 3/4.11.2.4 specifies Limiting Conditions for Operation and Surveillance Requirements for the GRWS. This modification does not impact these Technical Specification requirements (i.e., operability of the GRWS will not be adversely affected),
therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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Facility Change 2-85-6404 Title Modification of the Containment Purge Isolation System (CPIS), Control Room Isolation System (CRIS) and Fuel Handling Isolation System (FHIS) lypass and Status. Indication Circuits Description This modification changes the Containment Purge Isolation System (CPIS), Control Room Isolation System (CRIS) and Fuel Handling Isolation System (FHIS) actuation logics to provide a locking bypass mode, a channel reset feature, a channel actuation and a bypass status annunciation / indicating functions.
This modification will eliminate the potential cause of CPIS, CRIS and FHIS inadvertent or spurious actuation during performance of maintenance or surveillance testing by replacing the existing momentary contact pushbutton bypass switches with keflock switches.
The addition of backlighted momentary contact channel reset switch to each CPIS, CRIS and FHIS allows the operator to reset a channel and check the continuity of the channel relay circuit after resetting.
Safety Evaluation This modification does require revision to FSAR Sections 7.3.1.1.5.4, 7.3.1.1.10.4 and 7.3.1.1.11.4, but it is designed in accordance with the established SONGS 2&3 Engineered Safety Feature Actuation System design criteria, and does not adversely affect the designed functions of the systems affected. All the components added by this change are compatible with the required environmental and seismic qualifications.
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The Design Basis for Accident Analysis in FSAR Chapter 15, Accident and a
Equipment Malfunction Analysis in FSAR Chapter 6 and the High Energy M
Line Break Analysis in FSAR Chapter 3 are not affected by this y
modification.
Therefore, neither the consequences nor the probability i
of occurrence of an accident or malfunction of any equioment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The operability of the CPIS, CRIS and FHIS are governed by Technical Specification 3/4.3.2.
This change provides locking channel bypasses, channel actuation and bypass annunciations, and channel reset functions.
However, the designed safety functions, reliability and operability of CPIS, CRIS and FHIS are not adversely affected by this change. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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Facility Change 2-85-6418 Title Addition of Data / Communication Circuits to Various Plant Locations Description I
This modification installs data and telecommunication circuits between the Control Building and the Radwaste Building l
Safety Evaluation i
1 All changes covered by this modification are related to data /
telecommunications circuits only. All affected equipment, devices and wiring are Quality Class IV.
Addition of these new circuits does not impact and'is not required for safe shutdown, and all accident probabilities, consequences, and scenarios remain bounded by existing analyses.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
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j The new data / telecommunication circuits installed by this modification will not impact any Technical Specification Limiting Conditions for Operation, parameters, or Surveillance Requirements. Therefore, the margin of safety as defined in the basis for any Technical 4
Specification is not reduced.
This modification does not adversely impact the fire protection system /
program, but does require a change in the Fire Hazards Analysis to account for additional fire barrier penetrations and combustible i
materials.
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Facility Change 2-85-6420 Title Addition of a Halon 1301 Fire Protection System for the Telecommunications Room Description This modification orovides an Automatic Fixed Pipe, Total Flooding Halon 1301 Fire Protection System in the Telecommunications Room of the 70' elevation of the Auxiliary Building.
j Safety Evaluation FSAR Section 9.5.1 discusses the basis of the Fire Protection System and this modification ensures that operation is within that design bases. The failure modes and related effects are no different than that previously analyzed in the FSAR.
For the same reason, the results of any potential accident or malfunction are bounded by existing evaluations in the FSAR. There are no changes in the equipment or in the design function of the system, and there are no additional administrative or operational constraints imposed on the affected systems. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will not be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
t This modification has no effect on existing limiting Conditions for i
Operation or Surveillance Requirements goverred by the existing Technical Specifications. Therefore, the marg'n of safety as defined in the basis for any Technical Specification 's not reduced.
The Fire Hazards Analysis (FHA) will be revised to account for this modification. The Halon Fire Protection System serves the fire area 2-AC-70-175. Penetrations for this modification were provided on the east fire wall separating the Telecommunications Room and the Cable 4
Riser Gallery. All penetrations were provided with approved and appropriately rated fire seals. Also, the existing fireproofing applied to the structural support beams was removed to allow installation of the detector conduit between the top portion of the beams and the raised section of the steel decking. The fire proofing was reapplied after the conduit installation with equal or better fire resistance rating. Therefore, the consequences of a design basis fire previously evaluated in the FHA will not be increased by this change.
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Facility Change 2-85-6428 Title Addition of Condensate Storage Tank Level Controls Description This modification completely automates the level controls for both condensate storage tanks T-120 and T-121 with no operator interface.
The addition of these controls and the availalility of 2000 gpm of demineralized water will greatly increase the reliability of this system. The new level transmitters and level controllers will modulate the control valves in order to maintain the desired level in the tanks. The controllers can be set to maintain a constant level in the tanks which is particularly important in the case of T-121 during periods of high Auxiliary Feedwater (AFW) demand. When AFW demand is high, the new level controls are designed to give filling priority to T-121.
Safety Evaluation This modification adds controls to automatically maintain a constant level in the Condensate Storage Tanks.
The automatic level control increases the reliability of the tank level control by removing the human response factor, and increases the reliability of meeting the system Technical Specification requirements.
Tank T-121 is a Quality Class II, Seismic Category I criteria structure and Tank T-120 is a Quality Class III, Seismic Category II structure.
T-120 serves a Quality Class II function by virtue of its emergency service to T-121. Both tanks are housed in Seismic Category I enclosures.
The new level transmitters installed on these tanks are Quality Class III, Seismic Category II devices. All of the instruments and tubina installed in the T-121 building are mounted and supported in accordance with Seismic Category I criteria.
No core drilling was done below the flood level in either tank building, so the tank building water retenti,on capability was not compromised.
This modification does require a revision to the FSAR, but it does not j
adversely affect any safety function as previously reviewed in the FSAR Section 9.2.6 or Technical Specifications 3/4.7.1.3.
No design bases have been changed, and all potential accident scenarios, consequences and probabilities remain bounded by existing analyses. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased as a result of this change.
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addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
The Condensate Storage System is governed by Techn.ical Specifications 3/4.7.1.3.
This modification does not affect any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
8098u Facility Change 2/3 0188 Title Installation of an Eductor System to facilitate degassing of the Reactor Coolant System Through the Reactor Head Vent discharge to the Normal Purge Exhaust - Unit 3.
Description As previously installed, the gasses within the Reactor Coolant System (RCS), is vented into the containment atmosphere when a Reactor Coolant Pump seal or the Reactor Vessel Head is removed.
This leads to airborne activity and a potential for work stoppage until acceptable airborne radiation levels can be achieved.
This modification adds an eductor system which will utilize Service Air to remove RCS gasses from the reactor head vent by creating a vacuum and exhausting the gasses to the Containment Normal Purge Erhaust System. This will provide a means for reducing containment airborne radiation levels. The system is interlocked with the exhaust fans to stop the eductor system operation following a high radiation alarm, containment isolation, or exhaust fan failure. The system is
)
interconnected with the Service Air System, the Containment Exhaust System, and the Reactor Coolant System by temporary hose connections.
Hoses and end connections to piping, filtration units, and sample bombs are provided by station as required to facilitate system operation.
Safety Evaluation The eductor system is not discussed in the FSAR since this is a new auxiliary system, however, the FSAR will be revised to include this modification. The modification do not adversely affect cperation of
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the Reactor Coolant, Service Air, or Containment Exhaust Systems in j
that the function of these systems remain as originally intended, and the de:ign bases are unaffected. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety oreviously evaluated in the FSAR will be increased.
In addition, the modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
This modification has no effect on existing Limiting Conditions for Operation or Surveillance Requirements governed by the existing Technical Specifications. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this I
change.
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Facility Change 2/3 0220
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Title Addition of Electrical Power for the Refueling Machine Auxiliary Hoist l
- Unit 2 i
Description This modification provides electrical power to the new auxiliary hoist which has been attached to the Unit 2 Refueling Machine.
Power for the auxiliary hoist will be supplied by tapping into the existing 480 VAC, 3 phase, 60 Hz source at the Refueling Machine. The existing refueling machine controls will be interlocked with the cor.trols of the auxiliary hoist such that either the Refueling Machine or the auxiliary hoist may be operated individually, but not simultaneously.
l Safety Evaluation This modification involves the addition of Quality Class III Seismic Category II/I equipment that is operated only during refueling activities. No design bases have been changed, but FSAR Section 6.2.5 must be revised to reflect fourteen additional pounds of aluminum that forms an integral part of the auxiliary hoist. The Refueling Machine Auxiliary Hoist has been evaluated under the same accident scenarios J
and design criteria as the original refueling machine.
All potential accident probabilities are bounded by existing FSAR analyses; therefore, neither the consequences nor probability of occurrence of an i
accident or malfunction of any equipment important to safety previously I
evaluated in the FSAR will be increased.
In addition, this i
modification will not create the possibility for an accident or i
malfunction of a different type than any previously evaluated in the FSAR.
Technical Specifications 3/4.9.6 defines the function of the refueling machine and establishes its minimum and maximum load capacity. The addition of the auxiliary hoist will not reduce any of the margins of safety established in the Technical Specifications since the operation of the refueling machine components which deal with movement of Control Element Assemblies and Fuel Assemblies is functionally independent from the operation of the auxiliary hoist.
The auxiliary hoist will be procedurally prohibited from use for those functions reserved for the Refueling Machine and Polar Crane Auxiliary Hoist by T/S 3/4.9.6 and its design basis. With these restrictions, this modification does not impact any Technical Specifications Limiting Conditions for Operation, l
parameters, or Surveillance Requirements.
Therefore, the margin of safety as defined in the basis for any Technical Specification will not be reduced.
This modification does add additional combustible material to Fire Zone 2-CO-63-10 and the Fire Hazards Analysis will be revised to account for this addition.
The resultant fire loading remains well below the maximum permissible; therefore, the consequences of a design basis fire previously evaluated in the FHA are acceptable, i
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i Facility Change 2/3 0221 Title Addition of Electrical Power for the Refueling Machine Auxiliary Hoist
- Unit 3 i
Description 1
This modification provides electrical power to the new auxiliary hoist which has been attached to the Unit 3 Refueling Machine.
Power for the auxiliary hoist will be supplied by tapping into the existing 480 VAC, 3 phase, 60 Hz source at the Refueling Machine.
The existing refueling machine controls will be interlocked with the controls of the auxiliary hoist such that either the Refueling nachine or the auxiliary hoist may be operated individually, but not simultaneously, i
Safety Evaluatan This modification involves the addition of Quality Class III Seismic Category II/I equipment that is operated only during refueling i
activities. No design bases have been changed, but FSAR Section 6.2.5 i
must be revised to reflect fourteen additional pounds of aluminum that j
forms an integral part of the auxiliary hoist. The Refueling Machine Auxiliary Hoist has been evaluated under the same accident scenarios and design criteria as the original refueling machine. All potential accident probabilities are bounded by existing FSAR analyses, therefore, neither the consequences nor probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the 1
FSAR.
Technical Specifications 3/4.9.6 defines the function of the refueling l
machine and establishes its minimum and maximum load capacity. The j
addition of tha auxiliary hoist will not reduce any of the margins of safety established in the Technical Specifications since the operation of the refueling machine components which deal with movement of Control Element Assemblies and Fuel Assemblies is functionally independent from the operation of the auxiliary hoist. The auxiliary hoist will be procedurally prohibited from use for those functions reserved for the Refueling Machine and Polar Crane Auxiliary Hoist by T/S 3/4.9.6 and its design basis. With these restrictions, this modification does not impact any Technical Specifications Limiting Conditions for Operation, parameters, or Surveillance Requirements. Therefore, the margin of l
safety as defined in the basis for any Technical Specification will not be reduced.
This modification does add additional combustible material to Fire Zone 3-C0-63-10 and the Fire Hazards Analysis will be revised to accommodate this addition.
The resultant fire loading remains well below the 1
maximum permissible; therefore, the consequences of a design basis fire previously evaluated in the FHA are acceptable.
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Facility Change 2/3 0257 Title Containment Sump Inlet Flow Monitoring Modification - Unit 3 Description This modification abandons in place the present high range and low range flow mcnitoring systems located at the containment sump inlet.
Associated inputs to recorder and plant annunciator are disconnected.
A Containment Sump Level Signal is provided to the Critical Function Monitoring System (CFMS) and the Plant Monitoring System (PMS) from a circuit isolator in a panel located in the Control Building. Computer software is provided to convert level change signals into flow rates, and display and alarm on the Control Room CFMS computer display, when flow rates are one gpm or increased by 0.5 gpm. Also, a one gpm flow rate alarm is provided to a plant annunciator.
Safety Evaluation This modification only changes nonsafety related flow monitoring system hardware and method, to replace inoperable instrumentation.
It reduces operator action and relieves him of additional stress.
It restores the original intent of the monitoring system and enhances plant operation.
The new containment sump inlet flow monitoring modification helps l
detect impending problems with the Reactor Coolant System and related equipment, and does not adversely impact any safety related equipment.
Only one 1E level channel is used for the flow calculation, and this level channel is isolated from non-1E circuits by a comp' uter interface and isolation card in the instrument rack located in the Control Room.
l Changes to FSAR Section 9.3.3 have been initiated to clarify use of CFMS for sump inlet flow monitoring but, the basis for the design, as described in FSAR Section 5.2.5, is not changed or affected by this modification. The flow rate limit for alarm on the plant annunciator is not changed; only the hardware to determine the flow rate is changed. Any potential accidents and consequences are bounded by existing analysis. Therefore, this modification does not increase the l
consequences or the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR. This modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
l The system affected by this change is governed by Technical Specifications Section 3.4.5.2.
This modification does not adversely affect this Technical Specification.
The flow rate alarm set point for identified leak rates will remain within the limits of the Technical Specifications and Regulatory Guide 1.45.
This change will not affect any existing Technical Specifications Limiting Conditions for Operation l
or Surveillance Requirements, therefore, the nargin of safety as defined in the basis for any Technical Specification is not reduced.
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This modification results in some cable trays being filled to greater than 30%. As such this modification will require a revision to the Fire Hazard Analysis (FHA). However, the actual fire load in the affected zones remains within the maximum allowed FHA design fire load and therefore this modification does not adversely impact the FHA.
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Facility Change 2/3 6160, Revision 3 Title Modification of the Source Range Neutron Flux Monitoring System
- Unit 2 Description This modification upgrades the two Startup Sources Range Neutron Flux Monitoring Systems from nonsafety related to safety related and LOCA Qualified Class 1E Wide Range Systems. This includes replacing the existing degraded BF-3 Detector Systems with a more reliable fission chamber detector systems, relocating of amplifiers from inside containment to the outside, and locating the signal processors in the Main Control Room and Emergency Evaluation Shutdown Area separately to attain redundant channel separation requirement for Class 1E operation and fire protection criteria.
Safety Evaluation 4
This modification upgrades the Startup Range Neutron Flux Monitoring Sys t.em.
The new fission chamber detectors, junction boxes, penetrations, amplifiers and signal processors are seismically and environmentally qualified. All circuitry wiring and cable routings are in compliance with the established project electrical and instrument and control system separation criteria.
FSAR Sections 7.5, 7.6, 7.7 and FSAR Table 7.5-1 describe the design basis for this system and these sections are being revised to reflect the new wide range flux monitoring channel data. However, this modification does not adversely affect any of these design bases as described in the FSAR. Therefore, this modification does not increase the consequences or the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in this FSAR.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
Technical Specifications 3/4.9.2 requires two source range channels during refueling operations, and requires periodic channel check and channel functional tests of each monitor.
Continuous visual indication is required in the Control Room for both channels, and at least one channel is required to have audible indication in the Control Room and in the containment.
This modification upgrades the overall qualification of the Startup Source Range Neutron Flux Monitoring System for Class 1E operation by replacing the existing BF-3 detector systems with safety-related and LOCA Qualified Fission Chamber Detector Systems. Both of the new upgraded channels will have continuous visual indication in the Control Room, and either channel can be selected to provide continuous audible indication in the Control Room and in containment.
Channel checks and channel functional tests can be performed as needed to meet Technical Specification 4.9.2 Surveillance Requirements. Therefore, this modification does not affect the existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements. The margin of safety as defined in the basis for any Technical Specification is not reduced.
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The Fire Hazards Analysis (FHA) will be revised to reflect this modification. However, the new cables, amplifiers and signal processors installed by this modification will not adversely affect the results of the Fire Hazards Analysis (FHA). All combustible loadings and safe shutdown separation criteria remain within acceptable limits and the two systems are routed in separate fire zones to preclude loss of flux monitoring due to a fire.
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Facility Change 2/3 004 Title l
Addition of a Shutdown Cooling Heat Exchanger Inlet Temperature Monitor - Unit 3.
Description j
This modification adds a temperature element.at the Shutdown Cooling l
Heat Exchanger (SDCHX) E004 inlet, a signal converter module in f
rack 3L-158, and replaces existing two pen recorder 3TR-0351 A/B with a four pen recorder in the same Control Room location. The new temperature indicating / recording loop is non-1E and is consistent with existing instrumertation for SDCHX E003.
Safety Evaluation This modification does not affect the design basis of the Shutdown Cooling System, the Emergency Core Cooling System or post-accident monitoring instrumentation of other systems, since the nature of the modifications do not impact the function of these systems. This change only upgrades the instrumentation and improves operation of the plant..
All potential accidents and consequences are bounded by existing analysis. Therefore, this modification does not increase the consequences or the probability of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR. This modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The margin of safety as defined in the basis for any Technical Specification is not reduced. The equipment affected by this change is governed by, but does not impact Technical Specifications 3/4-9.8.1, 3/4-9.8.2, 3/4-5.2 and Table 3-8-2.
This change will not affect any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
This change does not adversely impact the function of Safe and Auxiliary Shutdown Systems, and does not violate fire hazard requirements. Although over 30% fill in some cable trays result from this modification, and a revision of the Fire Hazards Analysis (FHA) will be required, the actual fire load in the affected zones remains within the maximum allowed FHA design fire load.
In addition, this change does not adversely impact the FHA.
Separations between IE trains, and between IE and non-1E circuits are maintained.
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8098u Facility Change 2/3 009 Title Modifications to the Site Emergency Evacuation Siren System.
Description I
This modification involves circuit design modification of the plant wide Emergency Evacuation Siren System to fully meet Emergency Preparedness requirements. This modification includes removal of the automatic activation feature of the Site Emergency Siren System which is initiated by receipt of a Safety Injection Actuation System (SIAS) signal.
The revised system is manually activated by station operating personnel from pushbutton switches located in the Control Room.
Furthermore, the operator is able to activate the system selectively as follows:
(1) Unit 2 containment sirens, (2) Unit 3 containment sirens, (3) all sirens, plant wide, (4) the combination of I and 2 above.
Audio amplification is also added to the Public Address Speaker System (P.A.), without revision of the design of the P.A. Speaker System Evacuation Warning Tone.
The addition of audio amplification merely allows the P.A. Warning System to properly serve its original intended function.
This modification also includes the addition of strobe lights in high-noise areas of the containment to enhance personnel awareness of imminent containment evacuation, thus more effectively vacating the area.
Safety Evaluation This modification will require changes to FSAR system description Section 9.5.2.2.1.3 and Table 7.3-2 in order to reflect the revised system design concept.
This modification will only reduce the number of unnecessary evacuation alarm occurrences, and will have no adverse effects on any other system. All potential accidents and consequences are bounded by l
existing analysis. The evacuation alarm sirens do not provide any means for preventing an " accident" or for mitigating its effects. The l
alarm sirens are used strictly for the purpose of warning station personnel that an accident has occurred, and that evacuation of the area is required. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any l
equipment previously important to safety evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
The margin of safety as defined in the basis for any Technical Specification is not reduced. There are no Limiting Conditions for Operations or Surveillance Requirements applicable to the emergency evacuation siren system.
8098u Facility Chan9 q 2/3 005, 2/3 013, 2/3 018, 2/3 021, 2/3 024, 2/3 032, 2/3 034, 2/3 050, 2/3 058, 2/3 060 Title l
Addition of a Full Flow Condensate Polishing Demineralizer System (FFCPD) - Unit 2 i
l Description These modifications form a part in the addition of the Full Flow Condensate Demineralizer System and associated components to Unit 2.
The equipment is located in the FFCPD Building at the north side of the Turbine Building.
Safety Evaluation These modifications will be included in a revision to the FSAR which will incorporate the FFCPD. The FFCPD does not have a safe shutdown or safety related design bases.
These modifications are remote from safety related equipment, structures or systems.
Further, these changes do not affect pressure boundary integrity or seismic integrity of any nonsafety related system. Any potential accident scenarios and consequences remain bounded by the existing analyses.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, these modifications will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
These changes have no effect on the existing Limiting Conditions for Operation or Surveillance Requirements governed by the existing Technical Specifications. The margin of safety as defined in the basis for any Technical Specification is not reduced by these modifications.
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L Facility Changes 2/3 190, Revision 2, 2/3 022, 2/3 023, l
2/3 030, 2/3 033, 2/3 042, 2/3 --85-052, 2/3 059, 2/3 061, 2/3 066, 2/3 067, 2/3 068, 2/3 070, 2/3 071, 2/3 073, 2/3 075 Title Addition of a Full Flow Condensate Polishing Demineralizer System (FFCPD) - Unit 3 Description These modifications form a part of the addition of the Full Flow Condensate Polishing Demineralizer System and associated components to Unit 3.
The equipment is located in the FFCPD Building at the south side of the Turbine Building.
Safety Evaluation These modifications will be included in a revision to the FSAR which will incorporate the FFCPD. The FFCPD does not have a safe shutdown or safety related design bases. These modifications are remote from safety related equipment, structures or systems.
Further, these l
changes do not affect pressure boundary integrity or seismic integrity of any nonsafety related system. Any potential accident scenarios and consequences remain bounded by the existing analyses. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, these modifications will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
These changes have no effect on the existing Limiting Conditions for Operation or Surveillance Requirements governed by the existing Technical Specifications. The margin of safety as defined in the basis for any Technical Specification is not reduced by these modifications.
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Facility Change 2/3 080 Title Modification of the Existing Ventilation System for the Radwaste Control Panel Room.
Description This modification involves the ventilation system for the Radwaste Control Panel Room, which is part of the Radwaste Building Ventilation System. A new and completely independent air conditioning system is provided for the Radwaste Control Panel Room consisting of an air cooled condensing unit located on the roof at El. 85'-0" and a fan-coil unit inside the Control Panel Room.
The new system is complete with temperature control and safety interlocks.
Existing exhaust ducts are extended from the Control Panel Room to Valve Room No. 505C.
Safety Evaluation This modification will require a revision to the FSAR, but all potential accidents and consequences remain bounded by the existing analyses; therefore, this change does not increase the possibility or consequences of an accident or malfunction of any equipment important to safety, nor does it create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR, the Fire Hazards Analysis (FHA) and the Flooding Hazards Analysis.
The margin of safety as defined in the basis for any Technical Specification is not reduced by this change. The change has no effect on Limiting Conditions for Operation or Surveillance Requirements governed by the existing Technical Specifications, i
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N Facility Change 2/3 6066 Title Removal of Existing Chlorinating System and Replacement With an Entirely New Unit.
Description This modification installs a new Sodium Hypochlorite Chlorinating System for treating the intake structure of Units 2 and 3.
The principal elements of this system comprise four new variable speed injection pumps, two distribution manifolds, a local control panel and the existing storage tank.
The system is arranged so that two injection pumps (one a standby) normally serve Unit 2 and the other two pumps serve Unit 3.
Crossover piping allows the pumps to serve the other unit.
The presently installed sodium hypochlorite system has been experiencing continuing problems and is being removed and replaced by the unit described in this Facility Change.
Safety Evaluation I
This modification will not increase the consequences or thc probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR because it only replaces the existing chlorination system with one of a different manufacturer.
This change will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR. There is no change to the design basis or function of the saltwater cooling system as a result of this change (reference FSAR j
Section 9.2.1).
Therefore, this change has no impact on any FSAR safety analysis or FSAR accident analysis. The change to the FSAR which is required by this modification only reflects the new injection point into the Circulating Water System Intake Structure, and identifies how the operation of the system is administratively controlled.
This change has no impact on the original design objectives and system functions.
In addition, the change has no impact on any Limiting Conditions for Operation or Surveillance Requirements of any existing Technical Specifications.
The margin of safety as defined in the basis for any Technical Specification will not be reduced by this change.
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Facility Change 2/3 6098.4, Revision 1 Title Installation of Telecommunication Cables to the Telecommunications Room at Elevation 70'-0".
Description This modification provides a raceway for telecommunications capability by constructing a_ conduit and tray system from the existing underground ducts at the east side of the Radwaste Building to the Telecommun-ications Room at Elevation 70', and by constructing a conduit system from the Telecommunications Room at Elevation 70' to the Unit 3 Computer Room at Elevation 30'.
Safety Evaluation This modification provides a raceway system to be used for telecommunication cables only. There is no interface with safety related or nonsafety related plant equipment, thus this modification will not adversely affect the process parameters, seismic integrity, electrical integrity or design function of any safety related or nonsafety related systems.
The conduit does not provide a flooding path between elevations. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any i
previously evaluated in the FSAR.
This modification does not affect existing Technical Specifications Limiting Conditions for Operation or Surveillance Requirements; therefore, the margin of safety as defined in the basis for any Technical Specification will not be reduced.
This modification requires the revision of the Fire Hazards Analysis (FHA) to account for the additional fire loading, which remains within the maximum allowed fire loading for the affected zone.
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8098u Facility Change 2/3 6161.7 Title Auxiliary Building Addition at Elevation 63'-6".
Description This modification involves the addition of an elevated slab on top of the Radwaste Storage Tank Area of the Auxiliary Building at elevation 63'-5".
A pre engineered building will be supported on this elevated slab and will house laundry facilities, respirator cleaning area, repairing and storage areas, a contaminated equipment storage area, locker rooms, and men's and women's restrooms.
Safety Evaluation This addition does not adversely affect the structural integrity of the existing building or safety related systems. The effect of this 1
addition on the seismic characteristics of the existing Auxiliary Building is negligible and FSAR Section 3.7 will be modified to account 1
for this addition. The missile barrier provided within the pre-engineered building will effectively protect all safety related equipment or systems in the Penetration Areas from tornade missiles.
The existing plant systems that will supply all the utility requirements of the pre-engineered building have been evaluated and j
found to be adequate. All accident probabilities, consequences and scenarios remain bounded by existing analysis. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased as a result of this modification.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The margin of safety as defined in the basis for any Technical Specification is not reduced. The change has no impact on the existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
This modification will require a revision to the Fire Hazards Analysis (FHA) to reflect these changes; however, these changes do not adversely impact the fire protection system or violate the FHA.
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Facility CnanSe 2/3 6211 Title Replacement of the Chemical and Volume Control System (CVCS)
Purification Filter Backflush System Electronic Logic Control With a Programmable Logic Controller.
Description This modification replaces the two electronic logic systems used for CVCS backflush control, with a Programmable Logic Controller (PLC).
One PLC for each Unit 2 and Unit 3 are housed in a single new cabinet.
Space for six additional PLCs is provided in the new cabinet for future use when replacement of the remaining six controllers are approved.
The existing electronic logic system cabinet remains in place and will be used as the marshalling cabinet for the field and the new PLC connections. Wiring between the new and the marshalling cabinet is run in new cable trays.
The replacement system consists of PLC and other equipment which are reliable, easily available and replaceable. The PLC will reduce the 3
number of eiectronic components and will increase interchangeability of components. The PLC will increase maintainability and reliability of the system, which subsequently decreases downtime of the system.
Overall plant reliability is improved by this modification.
Safety Evaluation The probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR Section 9.3.4 will not be increased as a result of this change.
This modification will not affect the design basis of the CVCS or any other safety related system. All potential accidents and consequences are bounded by existing analysis. As such, this change does not increase the possibility or consequences of an accident or malfunction of any i
equipment important to safety previously evaluated in the FSAR, nor does it create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The margin of safety as defined in the basis for any Technical Specification is not reduced by this change. The equipment affected by this change is not governed by Technical Specifications. This change will not affect any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
The Fire Hazards Analysis will require revision to reflect the additional cable routing resulting'from this modification. The additional fire loading will not exceed the permissible limits previously analyzed, therefore, this modification does not adversely impact the fire protection system / program or violate the Fire Hazards Analysis.
8098u Facility Change 2/3 6307 Title Replacement of Fire Doors.
Description This modification involves replacement of a number of existing fire doors with new 14 gauge, heavy duty fire doors.
This will deter the past excessive repairs and replacement problems.
Safety Evaluation i
Neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously i
evaluated in the FSAR will be increased as a result of this change.
The new fire doors meet the fire protection requirements and are labeled Class A (3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) Fire Resistance Rated.
Fire doors in the areas covered in this modification do not have a safety related function. This modification does not adversely affect performance of the personnel working within the respective area, or any safety related or nonsafety related system, equipment or structure. All accident scenarios, probabilities, consequences remain bounded by the existing analysis.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
i The margin of safety as defined in the basis for any Technical Specification is not reduced. The equipment affected by this change is governed by the Technical Specification 3/4.7.9 and is not adversely affected.
The Fire Hazards Analysis (FHA) will require revision to reflect the replacement of these doors. This modification does not adversely impact the fire protection system and/or violate the FHA.
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Title Replacement of Computer Room Ventilation Unit to Support Addition of Backup Computer System Description This modification replaces the existing Computer Room Ventilation Unit with a larger capacity unit due to the addition of the Core Operating Limit Supervisory System Backup Computer System (CBCS).
Safety Evaluation This modification installs additional cooling capacity to provide for increased heat load from the addition of the CBCS computer.
It has no impact on any of the functions or design criteria of the ventilation system as described in FSAR Section 9.4.
As such, the existing analyses in the FSAR are unaffected by this modification, and all i
accident scenarios, probabilities, and consequences remain bounded by the existing analyses.
However, FSAR Chapter 9.4, Table 9.4-5 needs to be updated to reflect modified Performance Parameters.
The computer room ventilation unit takes suction from and discharge into the computer room. The unit is provided to lower design temperature only in the nonsafety related computer room, during normal operation. Operation of this ventilation unit does not affect the operation of either the control building normal ventilation system in safety related areas of the control building or the control building emergency ventilation system. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any
. equipment important to safety previously evaluated in the FSAR will be t
increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
The computer room ventilation unit provides ambient cooling for computers and equipment in the computer room.
However, this change has no effect on any Technical Specification Surveillance Requirements or i
Limiting Conditions for Oparation.
These ventilation modifications neither affect the functional design nor degrade performance of the computer room ventilation system. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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Facility Change 3-85-6012.2, Revision 1 Title Installation of Core Operating Limit Supervisory System Backup Computer System (CBCS)
Description This modification installs the redundant CBCS. The existing Plant Monitoring System (PMS) in which the Core Operating Limit Supervisory System (COLSS) program is executed, has been determined to be obsolete and its reliability is highly suspect.
Having a redundant COLSS backup computer significantly improves the availability of these parameters.
Safety Evaluation The COLSS is-not required for plant safety since it does not initiate any direct safety function during anticipated operational occurrence or postulated accidents (FSAR 7.7.1.5).
It is only used to enable operation of the plant at maximum power level. The addition of the CBCS will not impact any safety related equipment required for shutdown and, all probabilities, consequences, and scenarios remain bounded by the existing analysis.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
The margin of safety is unaffected by the installation of the CBCS because it only provides an alternate source of COLSS parameters for optimal plant operation. The enhanced availability of these parameters improves the probability of plant operation within Technical-Specification limits. No Technical Specification Limiting Conditions for Operation or Surveillance Requirements is affected.
This modification will require the revision of the Fire Hazards Analysis (FHA) to account for the additional fire loads, but this modification does not adversely impact the fire protection system / program or violate the FHA.
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J Facility Change 3-85-6012.3 Title Installation of Backup Capability Between the Plant Monitoring Computer (PMC) and the Core Operating Limit Supervisory System (COLSS)
Description This modification fixes incore detector field cabling problems at the Auxiliary Protective Cabinet (APC), and provides a spare set of incore detector signals for the new COLSS Backup Computer System.
Safety Evaluation This change eliminates the current APC Cabinet field cabling problems and provides a spare set of signals to the new COLSS Backup computer system.
It has no impact on any of the functions or design criteria of the incore instrumentation. As such, existing analyses in the FSAR are unaffected by this modification. Therefore, neither the consequences nor the probabi'ity of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be j
increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any j
previously evaluated in the FSAR.
The incore field cabling modification neither affects the functional design nor degrades the performance of the fixed incore detector instrumentation system.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
Fire Hazards Analysis (FHA) Sections 3-AC-30-20B will be revised to account for the increase fire loaling due to the implementation of this modification. The total fire loading, following implementation of the change remains below the maximum permissible value and will not adversely affect the FHA.
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Facility Change 3-85-6012.4, Revision 1 Title Addition of Selector Switch for the Core Operating Limit Supervisory System Backup Computer System (CBCS)
Description This modification adds i selector switch to enable an operator'to select either the Plant Monitoring Computer (PMS) or the new CBCS for display, annunciation and Control Element Assembly (CEA) sequencing control.
Safety Evaluation The addition of a selector switch to improve the availability of the CBCS to facilitate compliance with the requirements of the Technical Specification, has nc ~~ pact on any of the functions or design crite;la of the Core Operating mit Supervisory System (COLSS) or CEA sequencing as described in FSAR Section 7.7.1.5.
However, FSAR Chapter 7.7 needs to be updated to reflect the addition of the CBCS.
As a result of this modification, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
This modificat*on has no effect on any Technical Specification Surveillance Requirements or Limiting Conditions for Operation since the COLSS software and CEA sequencing programs are functionally identical to those described in the FSAR. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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Facility Change 3 6043 Title Addition of Main Steam Bypass Valve Indication.
Description This modification adds instrumentation, circuitry, wiring and computer software for 0-100 percent indication on the Critical Function Monitoring System (CFMS) computer display and the Plant Monitoring System (PMS) computer for four main steam bypass valves (HV-8423, HV-8424, HV-8425 and HV-8426).
Safety Evaluation This modification adds instrumentation to a nonsafety related system.
The steam bypass system and instrumentation as described in FSAR Sections 10.4.4 and 7.7.1.4.1 is not changed and no safety related equipment is impacted by this change.
The additional indicators and circuits do not adversely affect the seismic qualification of the main control boards or the separation of redundant IE systems and the probability of a steam bypass control system malfunction.
All potential accidents and consequences are bounded by existing analysis. Therefore, this change does not increase the consequences or probability of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR. This change will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The margin of safety as defined in the basis for any Technical Specification is not reduced. The equipment affected by this change is not governed by and the change does not modify any Technical Specification. This change will not affect any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
This modification does not adversely impact the Fire Protection System / Program or violate the Fire Hazards Analysis (FHA), however it requires a revision to the FHA to account for the additional fire loading.
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Facility Change 3 6044 Title Addition of an Automatic Start Capability to the Emergency Chilled Water System.
Description This modification provides the controls to interlock the Emergency j
Chillers and the Component Cooling Water (CCW) Pumps. This interlock will provide an auto start of the CCW pumps when a chiller is started, and eliminates the potential for a pump / chiller lineup that can render the Emergency Chiller inoperable.
Safety Evaluation Neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased as a result of this modification. The nature of the modifications does not impact the capability of the system to perform its intended function in accordance with the design basis as specified in FSAR Section 9.4.2.2.
However, a revision to the FSAR is required to reflect this modification.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
- t The change has no affect on the existing Limiting Conditions for i
Operation or Surveillance Requirements governed by the existing i
Technical. Specification. The margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification will require a revision to the Fire Hazards Analysis (FHA) to account for the additional fire loading.
Cables are added to cable trays with greater than 30% fill; however, the additional fire loading is within the limits of FHA design base fire load for that zone, and will not adversely affect the FHA.
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Facility Change 3 6090 Title Addition of a Control Room Indication for the Reactor Coolant System (RCS) Refueling Water Level.
Description The previous design of Refueling Water Level Indication (RWLI) did not have the capability for control room monitoring of RCS level during draining to mid-loop, RCS fill from mid-loop and Refueling Cavity level fill for refueling operations.
It provided a local indication only.
This modification adds level transmitters, indicators, alarms, etc., to achieve accurate RCS level indication in the Control Room for both partial draining and refueling conditions. Two ranges are provided: a narrow range for mid-loop operations, and a wide range for refueling operations. All portions are permanently installed, except for flexible sections of the sensing line, which are used to connect to the drain (sensing) and vent (reference) lines.
Safety Evaluation Neither the consequences nor the probability of occurrence of an 1
accident or malfunction of any equipment important to safety previously evaluated in the FSAR Section 9.1.4.2.2.12 will be increased as a result of this modification. However, the FSAR will be revised to reflect this change. This modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The new RWLI system is a nonsafety related, non-1E system.
It is installed in accordance with established project criteria to maintain separation from safety related IE systems.
In addition, portions of the RWLI system in proximity to safety related systems whose failure could affect the safety related system, are supported to Seismic Category II/I criteria.
5 The margin of safety as defined in the basis for any Technical Specification is not red'uced. The RCS water level in Modes 5 and 6 is governed by Technical Specification Sections 3/4.4.1.4, 3/4.9.8 and 3/4.9.10, and has no adverse effect to the RCS or any other system important to safety.
In addition, this change does not adversely impact any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
i This modification does require a revision to the Fire Hazards Analysis to account for the increased fire loading, but these additional fire loading will not affect the results of the fire hazards analysis because all previous combustible loading analysis and the safe shutdown separation criteria remain valid.
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1 Facility Change 3 6123 Title Replacement of the Excore Linear Power Sensor Signal with a Excore Log Power Sensor Signal.
Description This modification substitutes an Excore Log Power Sensor Signal for the existing Excore Linear Power Sensor Signal as input to the Critical Function Monitoring System (CFMS).
The Excore Log Power Sensor Signal is needed by the CFMS to properly determine loss of reactivity control.
Safety Evaluation The effect of this modification is limited to enabling the CFMS to i
function as designed. The Plant Protection System (PPS) Channel C Excore Log Power Sensor is wired to the CFMS through an isolator, therefore, the operation of the PPS is unaffected.
Per FSAR Section 7.6, the CFMS is used to aid operators in the event of an accident and is not required to actuate or influence safety systems involved in accident mitigation.
Based on the above, this modification does not increase the consequences or the probability of occurrence of an accident or the malfunction of any equipment previously evaluated in the FSAR. The margin of safety as defined in the basis for any Technical Specification is not reduced.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
The Fire Hazards Analysis (FHA) will be revised to account for the additional cables in the cable spreading room. The additional combustible loads however, do not exceed the analyzed maximum allowable loading in the FHA and will have no adverse effect.
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Facility Change 3 6151 Title Modification of the Low Point Drains in the Waste Gas System.
Description In the past, draining of Waste Gas Sampling System low points into open l
flow drains has had the potential to cause airborne radioactive contamination. This modification provides for the low point drains in the Waste Gas Sampling System downstream of the Air Dryer Moisture Separators E0-681 and E0-682 to drain into a common header.
This common head is routed to the Volume Control Tank Pressure Safety Relief Valve (PSV-9220) discharge line that connects to the Miscellaneous Liquid Radwaste Tank (MLWS).
Safety Evaluation FSAR Section 11.2 discusses the Radioactive Liquid Waste System operation and capacity.
FSAR Sections 9.3.4 and 5.2.5 discuss the Chemical and Volume Control System and detection of reactor coolant system leakage, respectively.
The minor drain flow into the PSV-9220 discharge line to the MLWS will not adversely affect MLWS capacity or processing capability, nor will the PSV-9220 discharge capacity be significantly affected. Because Chemical and Volume Control System (CVCS) leakage can appear to be Reactor Coolant System (RCS) leakage per FSAR 5.2.5 (the systems are operated as a combined system), significant flow through the new drain connection could mask PSV-9220 flow.
However, the nature of the drain flow (condensation from gas sampling flow), expected drain temperature and distance from the PSV-9220 tail pipe (approx. 2') make it unlikely that such a situation could occur.
The drain flow is low pressure; therefore, HELBA considerations do not apply.
In addition, core drilled piping penetrations are sealed with Bisco foam to provide a flooding barrier.
Based on the above, this modification does not increase the probability or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR.
In addition, this modification will not create the possibility of accident or malfunction of a different type other than any previously evaluated in the FSAR.
Technical Specification 3/4.4.5.2 governs RCS leakage. As discussed above, this modification could adversely affect the ability to discriminate between RCS and CVCS leakage, potentially causing entry to the actions of 3/4.4.5.2 and difficulty in meeting the Surveillance Requirements; however, this is considered an unlikely occurrence.
Technical Specifications 3/4.11.1 and 3/4.11.2 (gaseous and liquid effluents) will not be adversely affected because no new effluent paths or releases are created.
In addition, no other existing Technical Specifications apply. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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4 This modification will require a revision to the Fire Hazards Analysis (FHA) to account for the additional small bore penetrations with Bisco seals, however these penetrations have no adverse effect on the FHA.
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Facility Change 3 6160 Title Upgrade of the Source Range Neutron Flux Monitoring System.
Description This modification upgrades the.two Startup Source Range Neutron Flux Monitoring Systems from nonsafety related to safety related and LOCA Qualified Class 1E Wide Range Systems. - This includes replacing the existing BF-3 Detector Systems with more reliable fission chamber detector systems, relocating amplifiers from inside containment to the outside and locating the signal processors in Main Control Room and Emergency Evaluation Shutdown Area separately to attain redundant channel separation requirement for Class IE operation and fire protection criteria.
Safety Evaluation This modification upgraded the Startup Range Neutron Flux Monitoring System. The new fission chamber detectors, junction boxes, penetrations, amplifiers and signal processors are seismically and environmentally qualified. All circuitry wiring and cable routings are in compliance with the established project electrical and instrument and control system separation criteria.
FSAR Sections 7.5, 7.6, 7.7 t
and FSAR Table 7.5-1 describe the design basis for this system and these sections are being revised to reflect the new Wide Range Flux Monitoring Channel data.
However, this modification does not adversely affect any of these design bases as described in the FSAR. Therefore, this modification does not increase the consequences or the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previcusly evaluated in the FSAR.
Technical Specification 3/4.9.2 requires two source range flux monitors during refueling operations, and requires periodic channel check and i
channel functional tests of each monitor. Continuous visual indication is required in the Control Room for both channels, and at least one channel is required to have audible indication in the Control Room and in the containment. This modification upgraded the overall qualification of the Startup Source Range Neutron Flux Monitoring System for Class IE operation. Both of the'new upgraded channels will have continuous visual indication in the Control Room, and either channel can be selected to provide continuous audible indication in the Control Room and in the containment.
Channel checks and channel functional tests can be performed as needed to meet Technical Specification 4.9.2 Surveillance Requirements.
Therefore, this modification does not affect the existing Technical Specification Limiting Conditions for Operation or the Surveillance Requirements.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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The new cables, amplifiers and signal processors installed as a result of this change will not. adversely affect the results of the Fire Hazards Analysis (FHA), because.all combustible loadings and safe shutdown separation criteria remain within acceptable limits. The two upgraded channels are also routed in separate fire zones to preclude loss of flux monitoring due to fire, in accordance with FHA commitments. The FHA will require a revision to accommodate this modification, but these changes will not adversely affect it.
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F;cility Change 3-85-6175 Title Replacement of the Reactor Coolant Drain Tank Inlet Flow Monitoring System.
Description T'his modification replaces the existing inoperative Reactor Coolant System Drain Tank Inlet Flow Monitoring System. By utilizing level changes in the drain tank and computer calculations to convert these levels into flow rates, the new system is able to comply with Technical Specification 3.4.5.2 requirements of monitoring identified leakage which limits flow rate to 10 gpm. (Identified leakage is normally 4-5 gpm due to Reactor Coolant Pump controlled bleed off. A flow to the drain tank of greater than 5 gpm would indicate total identified leakage possibly exceeding of the Technical Specification limits.)
Safety Evaluation This modification changes flow monitoring system hardware and methods, deletes inoperable instrumentation, and adds computer software to the Critical Function Monitoring System (CFMS) portion of the safety parameter display system.
Basis for the design as described in FSAR Section 5.2.5.1.9 is not changed or affected by this modification. The flow rate limit for alarm on the plant annunciator has been changed from 1 gpm to 5 gpm to avoid spurious alarms and remains within the Technical Specification, Section 3.4.5.2 requirement of 10 gpm identified flow rate.
The performance of the reactor coolant system inventory balance, pursuant to Technical Specification Surveillance Requirement 4.4.5.2.1c, every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ensures that the probability of occurrence of an accident or malfunction of equipment important to safety is unaffected by the change.
All potential accidents and consequences are bounded by existing analysis.
Therefore, this change does not increase the consequences or the probability of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR to be increased.
In addition, this change will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The system affected by this change is governed by Technical Specification Section 3.4.5.2, but the modification does not adversely affect it.
The flow rate alarm set point for identified leakage is increased but will remain within the limits of the above Technical Specifications and 1
This change will not adversely affect any existing Surveillance Requirements. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification results in 31.1% fill in some cable trays, and will require a revision to the Fire Hazard Analysis (FHA); however actual fire load in the affected zones remains within the maximum allowed FHA design fire loads and the affected penetrations through fire rateo walls are sealed with Bisco seals. Therefore, the FHA will not be adversely affected.
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Facility Change 3-85-6198.2 Title Installation of Radiation Monitor Recorders in the Main Control Room and Radwaste Control Room Description This modification includes:
A.
Replacing the multipoint scanning recorders located on the radiation monitoring panels with continuous pen recorders.
B.
Relocating various radiation monitoring recorder points to the main control room control panels.
C.
Adding recorders for various redundant radiation monitoring channels which were not previously recorded.
D.
Adding a microprocessor-based multichannel recorder for various radiation monitoring channels to the radwaste control room.
Safety Evaluation The changes involved in this modification affect the Process and.
Effluent Radiological Monitoring System and the Area Radiation Monitoring System which have safety and nonsafety related design bases in the FSAR. These modifications will require revisions to FSAR Sections 7.3.1.1.5, 7.3.1.1.10, 7.3.1.1.11, 11.5 and 12.3.4.
This modification allows the Process and Effluent Radiological Monitoring System and the Area Radiation Monitoring System to continue to function as specified in those design bases and setpoints are not changed.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR.
In addition, these modifications will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The equipment affected by this change is governed by the Technical Specifications, but the change does not not affect any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirement. Therefore, tne margin of safety as defined in the basis for any Technical Specification will not be reduced.
The Fire Hazard Analysis (FHA) will be revised to reflect this modification, but the change does not adversely impact the Fire Protection System / Program or violate the FHA. The additional fire loading due to this modification does not result in exceeding the maximum permissible fire loading.
8098u Facility Change 3-85-6218 Title Installation of a Multiplexer in the Penetration Room and Thermocouples on the Steam Generator Exterior Surface Under the Thermal Shield.
Description This change involves installation of a Multiplexer Data Gathering System (MDGS) in the penetration room at 45' elevation, and two Type-K dual thermocouples on each steam generator exterior surface under the thermal shield with their associated cabling to the MDGS.
Safety Evaluation This modification eliminates the necessity of individual cabling from the containment penetration room to the computer room for each input addition to Critical Function Monitoring System (CFMS), providing convenience and cost savings for future addition of process inputs originating from inside containment to the CFMS, and providing the necessary steam generator secondary temperature instrumentation to support compliance of Technical Specification 3/4.7.2 and the Reactor Coolant Pump (RCP) starting procedure. With the exception of the Component Cooling Water (CCW) i containment isolation valve position status, the systems affected by this change are Quality Class III non-1E systems which do not perform any control functions, safety related parameter indication, or annunciation function. The CCW valve is Quality Class II and its position status is providing input to the CFMS for the Safety Parameters Display System monitoring of containment isolation.
The MDGS cabinet and its mounting, and the conduits located inside containment are designed to Seismic Category I criteria. As such, no safety related equipment located in the vicinity of the devices installed by this change will be affected.
Neither the design criteria nor the designed function of any system will be affected by this change. Thereforc, this change will not increase the probability of occurrence or consequences of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
Although this change provides steam generator secondary temperature information which will be displayed on CFMS CRTs on demand to support compliance with Technical Specification 3/4.7.2 and RCP starting procedure during shutdown conditions, the circuits between the MDGS and inside containment do not require containment penetration conductor overcurrent protection devices. Therefore, the containment penetration conductor overcurrent devices shown on Table 3.8-1, Section 3/4.8.4 of the Technical Specification are not affected. As such, this change neither affect the Technical Specifications, nor is it governed by the Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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This modification will require a revision to the Fire Hazards Analysis (FHA) to account for the increase in fire loading. However, these changes do not exceed maximum permissible fire loads and will not adversely affect the FHA.
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Facility Change 3-85-6221 Title Installation of a Spare Mobile Exciter Description This modification will facilitate the location and hookup of a Mobile Spare Exciter to allow continued operation of the main generator during major repairs of the permanent exciter.
Safety Evaluation The design bases and the safety evaluation for the Turbine Generator are presented in FSAR Section 10.2.
The Turbine Generator has no safety related design basis as defined in the FSAR and no safety related equipment is located in the vicinity of the turbine.
All potential accidents and consequences remain bounded by the existing analyses. Therefore, this change does not increase the consequences or the probability or of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR.
This change will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The equipment affected by this change is neither governed by the Technical Specifications nor does it impact any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification will require the revision of the Fire Hazards Analysis (FHA) to account for the increase combustibles, however, this modification does not adversely impact the Fire Protection System /
Program or violate the FHA.
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Facility Change 3-85-6234 Title Modification of the Safety Injection Pump Miniflow Isolation Valve Control Circuit Description This modification provides for the closing of the Safety Injection Pump Miniflow Recirculation Isolation Valves with a permissive from a Containment Emergency Sump level high signal eliminating operator action to close the miniflow valves manually upon Emergency Core Cooling System (ECCS) operational mode transfer from safety injection to recirculation following a Loss of Coolant Accident (LOCA).
The intent of this modification is to avoid High Pressure Safety Injection (HPSI) pump damage in the event of inadvertent simultaneous Safety Injection Actuation System (SIAS) and Recirculation Actuation System (RAS) actuation. The operation of the ECCS miniflow valves is also l
modified such that on " reset" of RAS, the valves do not reopen automatically.
Description This modification will allow for the ECCS miniflow isolation valves
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closing with receipt of an emergency sump high permissive logic signal. The sump level high permissive setpoint is maintained below the minimum post-LOCA flood level so that, including the effects of instrument errors, the miniflow permissive will be enabled prior to opening of the recirculation sump valves on RAS. Thus isolation of the miniflow path will occur when required under design basis events. A failure mode and effect analysis has been performed which verifies that the modified system will perform its intended function given any single active failure consistent with the original system design.
In addition, this change complies with the recommendation of IE Bulletin 80-06 and precludes reopening of the miniflow valves upon RAS reset. Therefore, neither the consequence nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The equipment affected by this modification is governed by Technical Specification Table 3.3-5 (Engineered Safety Function response times),
Technical Specification 3/4.3.3.6 (Post Accident Monitoring), and Technical Specification 3/4.5.2 (ECCS-T avg. > 350 F).
This modification does not modify existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements for the ECCS pump miniflow valves; however, Technical Specification change NPF-10/15-189 has been submitted the pertinent Limiting Conditions for Operation and Surveillance Requirements of the modified system. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
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This modification does require a revision to the Fire Hazards Analysis (FHA), to account for the 9 pound increase in combustibles. However, the increase does not adversely affect the Fire Protection System / Program or violate the FHA because the change do not cause the total fire loading in the affected zone to exceed the maximum permissible fire loading in that zone. The total loading remains below the barrier rating, and fire seals are used to preserve the barrier.
Therefore, the evaluations for the FHA remain valid.
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Facility Change 3-85-6238.0 Title Letdown System Modifications Description This modification improves the charas. eristics and control of flow through the boronometer and process radiation monitor.
This modification includes the following changes:
A.
Provides optimum flow of 8 and 5 gpm, respectively, for boronometer and process radiation monitor from downstream of the filter instead of upstream of the filter to avoid crud in the system.
B.
Replaces the existing flow indicator downstream of the boronometer and the process radiation monitor with a venturi flow element complete with a flow indicating transmitter.
C.
Adds a control valve in the main letdown line complete with isolation valves, a bypass valve and a spring loaded check valve.
It also adds throttle valves downstream of the baronometer and the process radiation monitor, to permit flow control through each instrument.
D.
Adds High Flow Annunciation at the main control panel and flow indication to the Critical Function Monitoring system (CFMS) for the sample flow through the boronometer and the process radiation monitor instruments.
Safety Evaluation FSAR Section 9.3.4.1 discusses the design bases for the Chemical and Volume Control System (CVCS). This modification does require a revision to the FSAR, but it does not adversely affect the operation, function or design bases of the CVCS.
The existing seismic analysis (FSAR 5.4.3.1), high energy line break analysis (FSAR 3.6.2) and fatigue. analysis (FSAR 3.9.1.1) have been reviewed and are not affected by this change. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
The change has no effect on existing Limiting Conditions for Operation or Surveillance Requirements governed by the existing Technical Specifications. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
The Fire Hczard Analysis (FHA) will be changed to account for the additional combustibles in the applicable fire zones.
However, this added fire loading does not exceed the maximum permissible loading and will have no adverse affect on the FHA.
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Facility Change 3-85-6241 Title Addition of Status Indication for the Component Cooling Water System (CCW) Valves Description This modification brings the CCW system's two containment isolation valve and four critical /non-critical loop isolation valve status indication inputs to the Critical Function Monitoring System (CFMS).
It also ensures the CFMS data base design complies with the regulatory requirements and its display algorithms function as designed.
i Safety Evaluation This modification brings the existing limit switch spare contact signals through the existing multiplexer as well as cables from the Plant Monitoring System (PMS) to the CFMS, in accordance with the established control and instrumentation circuit design criteria.
No device other than cables and conduits is added by this change. No control circuitry or system functional modification is involved in this change. Therefore, neither the consequence nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunctioa of a different type than any previously evaluated in the FSAR.
Although the operability of the six CCW System Isolation Valves 3HV-6223, 3HV-6236, 3HV-6212, 3HV-6213, 3HV-6218 and 3HV-6219 is required by Technical Specification Limiting Conditions for Operating Section 3/4.6.3 and 3/4.7.3, this change merely utilizes the existing limit switch spare contacts for CFMS inputs which are wired through a multiplexer and the PMS with separate cables. No existing valve control circuitry or designed function is affected by this change.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
Minor changes to the Computer Room combustible loading will require a revision to the Fire Hazards Analysis, but all increases in loading are within the acceptable limits and will have no adverse effect on the FHA.
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Facility Change 3-85-6252 i
Title Condenser Vacuum Trip Control Modifications Description This modification allows an overriding automat'c return of the condenser i
vacuum trip setpoint to a lower value on a falling power level during i
heat treatment of circulating water intake and discharge conduits.
This capability is provided to preclude plant trip due to turbine power excursions during heat treatment. Adequate administrative procedures will be enforced to ensure that this override capability is used only when necessary, since operating the turbine at low power (<70%) and i
high back pressure (>41/2" Hg) for extended period may result in last stage blade " Buffeting" and consequent damage.
The override action is logged in the computer to keeptrecords of the times for which override l
was in effect.
l Safety Evaluation A revision to the Fire Hazard Analysis (FHA) was necessitated by this modification due to a greater than 30% fill of cable tray caused by adding new cables to an existing tray. A 30% fill is assumed for all cable trays, and combustibles are calculated on this percentage fill in the FHA. When 30*.' fill is exceeded, actual value of combustibles and resultant Btu is shown in FHA.
It should be noted that an FHA revision was required only due to the higher than assumed cable tray fill. The actual increase in combustible is negligible.
Neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased as a result of this change.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The equipment affected by this change is not governed by a Technical i
Specification and this change does not impact any existing Technical Specifications. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
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Facility Change 3-85-6277 Title Replacement of Inadequate Ball Drips Description This modification provides for the replacement of existing ball drip valves in the water spray fire protection systems for charcoal filters in SONGS Unit 3, with high quality ball drips of all metal construction. The annual system tests which cycle the upstream isolation valve causes the previous ball drips to stick in their closed position. The replacement ball drips are provided with a plunger type device which can be used to clear ball drips should it become stuck.
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Safety Evaluation This modification does involve a revision to Figure 9.5-1 of the FSAR, but it has no effect on systems which perform safety related functions and does not require any modification to safety related structures, components or systems. Therefore, neither the consequences nor the probability of an accident or malfunction of any equipment important to safety previously evaluated in FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a differeat type than any previously evaluated in the FSAR.
The changes have no effect on the Limiting Conditions for Operation or Surveillance Requirements governed by the existing Technical Specification. Therefore, the margin of safety as defined in the basis for any Technical Specifications is not reduced, i
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Facility Change 3-85-6299 Title Chemical and Volume Control System (CVCS) Modifications Description Quality Class II instruments and IE circuits for Charging Pump Discharge Transmitters 3FT-0212 and 3PT-0212 and for Boric Acid Makeup Tanks Transmitters 3LT-0206 and 3LT-0208 were installed as a result of SCE's response to NUREG-0588 and position on Regulatory Guide 1.97.
SCE's commitment, however, was only to provide IE qualified field transmitters in some areas outside containment which had been classified as harsh environments.
IE circuits and 1E qualified electrically isolated control room indicators are not required for these instruments and were installed in error.
This modification abandons the 1E circuits and removes the unnecessary Quality Class II instrumentation with the exception of the four required IE qualified field transmitters which will remain installed.
These transmitters will be reconnected to the original non-1E circuits and will be powered from the Uninterruptible Power Supply bus.
The affected portions of the control panel will be reconfigured to match the Unit 2 panel.
Safety Evaluation Restoration of this system to its original non-1E configuration has no effect on the Reactor Coolant System operation. This modification requires a revision to the FSAR, but there is no change in the CVCS function or configuration as defined in FSAR Subsection 9.3.4.
All potential accidents and consequences remain bounded by existing analyses. Therefore, this change does not increase the probability or consequences of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR.
This change will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The abandonment of IE grade transmitters has no effect on the Reactor Coolant System or the Chemical and Volume Control System. No Technical Specification Limiting Conditions for Operation or Surveillance Requirement is affected; therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification will have no adverse affect, but will require revision of the Fire Hazards Analysis to account for the removal of combustibles.
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Facility Change 3-85-6345 Title Addition of Sonic Type Saltwater Cooling Flow Monitoring Instrumentation Description This modification increases the accuracy and reliablity in the indication of saltwater cooling flow by installing ultrasonic type flow sensors to the exterior of the system piping. The previous Component Cooling Water Heat Exchanger differential pressure method of determining the flow had not been very reliable.
A reliable flow indication is required for In-Service Inspection Test for the Saltwater Pumps (FSAR Section 9.2.1.4C, Technical Specification Sections 3/4.7.4 and 4.0.5).
The new flow indication will help monitor Saltwater Pump performance on a continuous basis, detect restricted flow through heat exchangar s because of sea debris accumulation, and determine the necessity to in-fate backflush of the heat exchangers. The addition of an abncrmal flow indication and alarm will help detect a major malfunction in the system.
New cables and conduit runs were added from Salt Water Cooling System (SWCS) tunnel to the main Control Room.
Safety Evaluation This modification installs ultra-sonic type flow sensors without penetrating or puncturing the flow pipeline, and does not adversely impact the saltwater cooling system.
This modification provides monitoring of the system and does not interfere, impede or adversely affect any safety related or nonsafety related equipment and its function or operation. The mass of the flow sensors on the SWCS pipe has a negligible affect on pipe seismic loads.
Although this modification requires a revision to FSAR Section 9.2, the functional design bases described in this section is not affected.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The equipment and system affected by this change is governed by Technical Specifications, Section 3/4.7.4 and 4.0.5.
This change will not modify or affect any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
All floor and wall penetrations will be properly sealed with Bisco seals and the additional fire load resulting from the new cables are negligible. The total fire loading of the affected zone remains within I
the maximum allowed for the affected zone. Therefore the change does not adversely affect the FHA, however, the FHA will be revised to account for this additional fire loading.
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Facility Change 3-85-6354 Title Addition of Steam Generator Blowdown System Flow Indication to the Plant Monitoring System (PMS) Computer Description This modification provides inputs for indication of Steam Generator Blowdown System flow to the PMS Computer from Flow Transmitters 3FT-4055 and 3FT-4056. Two 2-conductor cables (3xC51631 and 3xC51632) will be installed between the PMS Computer Cabinet 3LO81, and the FoxBoro Instrument Panel 3L-158 (which are located in Elevation 30' of the Control Building) to provide the blowdown inputs to PMS computer.
Safety Evaluation The FSAR Section 10.4.8 covers the Steam Generator Blowdown System and the flow control subsystem. Providing the capability in the PMS Computer to monitor the nonsafety related Steam Generator Blowdown System flow rate will not affect the associated safety related containment isolation devices or any other safety related equipment required to mitigate the consequences of a design basis event.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The portion of the Steam Generator Blowdown System flow ' control circuit affected by this change will not cause an operation or parameter set point change.
Therefore, this change does not impact any existing Technical Specification Limiting Conditions for Operation, parameters or Surveillance Requirements. Therefore the margin of safety as defined in the basis for any Technical Specification is not reduced by i
j this change.
The additional wires within the steel automatic control cabinet 3L-158 between existing terminal blocks and components will not adversely affect the existing seismic or fire hazards analysis.
However, the Fire Hazards Analysis will require a revision to account for this additional fire loading in the affected zone.
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Facility Change 3-85-6367 Title Replacement of Existing Valve Position Transmitters and Positioners on the Steam Generator Feedwater Bypass and Control Valves Description This modification replaces the existing valve position transmitters and valve positioners with new Baily type "RQ" Electronic Valve Position Transmitters and "AP4" Characterizable Pneumatic Positioners.
Safety Evaluation This modification neither increases the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR, Section 7.7.1.3.
The modification does not affect the design basis cf the Steam Generator Feedwater System since the nature of the modification does not impact the function of the system.
The backup feedwater isolation function of the Feedwater Bypass Valves is also unaffected.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The_ margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
The equipment affected by this change is not governed by and the change does not modify any Technical Specifications. The backup feedwater isolation function of the Feedwater Bypass Valves is governed by Technical Specification 3/4.3.2, however, this modification does not affect Feedwater Bypass Valve closure on a Containment Isolation Actuation System signal, and does not affect any other existing Technical Specification Limiting Conditions for Operation or Surveillance Requirement.
This modification will require a revision to the Fire Hazards Analysis (FHA) to account for the addition of cables to cable trays with greater than 30% fill, however the change is within the limits of FHA design base fire load for these zones. This change does not adversely impact the Fire Protection System / Program or violate the FHA.
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Facility Change 3-85-6372 l
Title Isolation and Removal of the High Pressure Turbine Flange Warming System 1
Description This modification isolates the High Pressure (HP) Turbine Flange Warming System from the Condenser, to eliminate air in-leakage into the Condenser.
Safety Evaluation Removal, abandonment, and/or isolation of the HP Turbine Flange Warming System will affect the Main Steam System to the extent that main steam to this system is no longer required. As a result, the design basis of the Main Steam Supply System per FSAR Section 10.3.1 will require a change to paragraph H deleting the HP Turoine Flange Warming System as one of the systems to which main steam is supplied.
In addition, FSAR Section 10.3.2.1 will also require changes.
The HP Turbine Flange Warming System is addressed in the FSAR Design Basis for the Main Steam Supply System, FSAR Section 10.3.1.
- However, per FSAR Section 10.3.3 (H), the Flange Warming System has no safety relationship or significance. The turbine manufacturer has determined that the Flange Warming System is not required for the HP Turbine at San Onofre given the operating quality and temperature of the steam.
Removal of this system from the Main Steam Supply System will have no impact on Main Steam Supply System components important to safety.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
This change has no negative impact on the original Turbine or Main Steam design objectivas and system functions. The HP Flange Warming System is not addressed in the Technical Specifications. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
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i Facility Change 3-85-6379 Title Modification of the Engineered Safety Feature (ESF) Bypass / Inoperable Status Indications and Alarm Logics Description This modification adds more information to the ESF Bypass / Inoperable Panel, eliminates unnecessary alarms and provides more logical alarm annunciations by rearranging portions of the ESF Systems Inoperable Alarm logics based on Technical Specification Limiting Conditions for Operation. The status of vital supporting equipment for the ESF System operations have also been included in the alarm logics to provide more meaningful ESF Inoperable Alarms.
Safety Evaluation All components and cabling added by this change are for status indication and alarming function only.
The quality class and sei:mic category of the equipment, cables and raceways added are compatible with the affected existing devices and the established design criteria. The ESF System Inoperable Alarm Logic rearrangements are made in such a way that no cross channel wiring connection results from this change and compliance with the requirements of Regulatory Guide 1.47 is maintained. The ESF Bypass / Inoperable Status Panel and
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its associated alarm annunciation system are strictly for ESF equipment status indication and alarm annunciation only. No circuits performing control function or system which are needed for safe shutdown of the plant are affected by this change.
This change neither alters the established design criteria nor affects the designed function of the Bypass / Inoperable Status Indication and Alarm Systems. As such, neither the plant reliability, operability or maintainability is affected by this change. Therefore, neither the consequence nor the i
probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
The ESF Bypass / Inoperable Status Indication and Alarm System, which is affected by this change, is neither governed by the Technical Specifications nor impacts the existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification requires a revision to the Fire Hazards Analysis (FHA) to account for the additional fire loading, but it does not adversely effect the FHA.
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Facility Change 3-85-6404 Title Modification of the Containment Purge Isolation System (CPIS), Control Room Isolation System (CRIS) and Fuel Handling Isolation System (FHIS)
Bypass and Status Indication Circuits Description-This modification changes the Containment Purge Isolation System (CPIS), Control Room Isolation System (CRIS) and Fuel Handling Isolation System (FHIS) actuation logics to provide a locking bypass mode, a channel reset feature, channel actuation and a bypass status annunciation / indicating functions.
This modification will eliminate the potential cause of CPIS, CRIS and FHIS inadvertent or spurious actuation during performance of maintenance or surveillance testing by replacing the existing momentary contact pushbutton bypass switches with keylock switches.
The addition of backlighted momentary contact channel reset switch to each CPIS, CRIS and FHIS allows the operator to reset a channel and check the continuity of the channel relay circuit after resetting.
Scfety Evaluation This modification does require revision to FSAR Sections 7.3.1.1.5.4, 7.3.1.1.10.4 and 7.3.1.1.11.4, but it is designed in accordance with the established SONGS 2&3 Engineered Safety Feature Actuation System design criteria, and does not adversely affect the designed functions of the systems affected. All the components added by this change are compatible with the required environmental and seismic qualifications.
The Design Basis for Accident Analysis in FSAR Chapter 15, Accident and Equipment Malfunction Analysis in FSAR Chapter 6 and the High Energy Line Break Analysis in FSAR Chapter 3 are not affected by this modification. Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of eny equipment important to safety previously evaluated in the FSAR will not be increased.
In addition, this modification will not create the possibility of an accident or malfunction of a different type t.ian any previously evaluated in the FSAR.
The operability of the CPIS, CRIS and FHIS are governed by Technical Specification 3/4.3.2. This change provides locking channel bypasses, channel actuation and bypass annunciations, and channel reset functions.
However, the designed safety functions, reliability, and operability of CPIS, CRIS and FHIS are not adversely affected by this change.
Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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Facility Change 3-85-6428 Title Addition of Condensate Storage Tank Level Controls Description This modification completely automates the level controls for both Condensate Storage Tanks T-120 and T-121 with no operator interface.
The addition of these controls and the availability of 2000 gpm of demineralized water will greatly increase the reliability of this system. The new level transmitters and level controllers will modulate the control valves in order to maintain the desired level in the tanks. The controllers can be set to maintain a constant level in the tanks which is particularly important in the case of T-121 during periods of high Auxiliary Feedwater (AFW) demand. When AFW demand is high, the new level controls are designed to give filling priority to T-121.
Safety Evaluation This modification adds controls to automatically maintain a constant level in the Condensate Storage Tanks. The automatic level control increases the reliability of the tank level control by removing the human response iactor, and increases the reliability of meeting the system Technical Specification requirements.
Tank T-121 is a Quality Class II, Seismic Category I criteria structure and Tank T-120 is a Quality Class III, Seismic Category II structure.
T-120 serves a Quality Class II function by virtue of its emergency service to T-121. Both tanks are housed in Seismic Category I enclosures. The new level transmitters installed on these tanks are Quality Class III, Seismic Category II devices. All of the instruments and tubing installed in the T-121 building are mounted and supported in accordance with Seismic Category I Criteria.
No core drilling was done below the flood level in either tank building, so the tank building water retention capability was not be compromised.
This modification does require a revision to the FSAR, but it does not adversely affect any safety function as previously reviewed in the FSAR Section 9.2.6 or Technical Specification 3/4.7.1.3.
No design bases have been changed, and all potential accident scenarios, consequences and probabilities remain bounded by existing analyses.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased as a result of this change.
In addition, this modification will not create the possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR.
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The Condensate Storage System is governed by Technical Specification 3/4.7.1.3.
This modification does not impact any existing Technical Specification Limiting Conditions for Operation or Surveillance Requirements. Therefore, the margin of safety as (! fined in the basis for any Technical Specification is not reduced.
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Facility Change 3-85-6574 Title Emergency Diesel Fuel Oil Transfer Pump Control Modification Description This modification is necessary to ensure that the Emergency Diesel Generators can provide power to shutdown and maintain the plant in a safe condition in the event that a design basis fire, concurrent with a loss of offsite power, were to occur.
Hot shorts (line to line faults), open circuits, or faults to ground caused by an exposure fire in the Control Room will not prevent operation of the Fuel Oil Transfer Pumps.
Safety Evaluation This modification does not involve a functional change to the operation of the Emergency Diesel Generator Fyel Oil System as described in the FSAR, but it will require a revision of the FSAR. This modification assures that the original design objectives and system functions in FSAR Section 9.5.4.2.2 are met. All accident scenarios and consequences remain bounded by existing analysis in the FSAR.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased as a result of this change.
In addition, this change will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
This modification has no effect on existing Limiting Conditions for Operation, Surveillance Requirements or parameters governed by the existing Technical Specifications. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced by this change.
8098u Facility Change CF-85-9027 Title Addition of a Multi-Purpose Holding Facility Description This modification provides a new Multi-Purpose Holding Facility (MPHF) for the interim-storage of radwaste generated at Units 1, 2&3. The MPHF is needed for holding of radwaste containers prior to their shipment to a permanent burial site. The MPHF will be located near the southeast corner of the SONGS site and within the limits of Parking Lot No. 1.
Dry Active Waste (DAW) can also be retained in this facility.
The facility will have a Miscellaneous Waste Holding (MWS) area, High Specific Waste Holding (HSWS) area, a truck bay, a truck ramp, a maintenance area and a pre-engineered office building that will house the control room, an office area, an equipment storage room,.restrooms ahd locker rooms.
Safety Evaluation Neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased as a result of this modification. This addition is not in the protected area arid it does not share or affect any system in the plant.
The MPHF retains radioactive waste until shipments are made to the permanent burial sites. No processing of waste will occur in the MPHF.
This modification does not adversely impact the fire protection system / program or violate the Fire Hazards Analysis (FHA), but will require a revision to the FHA.
The fire protection system for the MPHF has been designed per applicable NFPA codes.
The ventilation system will be shutoff during activation of alarms. The building is constructed of noncombustible materials and is located near the plant southern boundary which is distant from other structures or systems important to safety. The FSAR will be revised to accommodate this addition, but it will not adversely affect the FSAR.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
This modification has no impact on the existing Technical Specifications Limiting Conditions for Operation or Surveillance Requirements; therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
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Facility Change CF-85-9173 Title Installation of 800 MHz UHF Radic Consoles Description This modification is required to support the upgrading of the site-wide 800 MHz. VHF Radio System which is installed for Units 1, 2 and 3.
These changes are an essential part of commitments to improve site operations and maintenance. This modification covers the upgrading and replacement of existing channel controllers for the VHF Radio System, the addition of channel controllers at existing channel control locations, and the addition of 800 MHz Radio Control Stations in the Microwave Building and the Secondary Alarm Station Communication closet.
Safety Evaluation All changes included in this modification are related to telecommunication systems and related electrical feeders. The affected equipment, devices, and wiring are Quality Class IV. The telecommunication system is addressed in FSAR Vol. 17, Section 9.5.2.
l The changes included in this modification do not impact safe shutdown or other safety related equipment. All accident probabilities, consequences, and scenarios remain bounded by existing analysis.
Therefore, neither the consequences nor the probability of occurrence of an accident or malfunction of any equipment important to safety previously evaluated in the FSAR will be increased as a result of this change.
In addition, this modification will not create the possibility of an accident or malfunction of a different type than any previously evaluated in the FSAR.
This modification does not impact any Technical Specifications Limiting Conditions for Operation, parameters, or Surveillance Requirements; therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.
This modification will require the revision of the Fire Hazards Analysis (FHA) to account for the increase of equipment and fire loading, but this increase will have no adverse impact.
8098u Enclosure II San Onofre Nuclear Generating Station Units 1, 2 and 3 1985 Procedure Changes, Tests and Experiments i
All procedure changes in 1985 applicable to San Onofre Nuclear Generating Station, Units 1, 2 and 3 received a safety evaluation pursuant to 10 CFR 50.59. The safety evaluation concluded that none of the procedure changes involved an unreviewed safety question. The safety evaluations were reviewed and approved by the appropriate personnel as required by the 3
Technical Specifications.
For each change, the respective review concluded that the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report-was not increased, the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report was not increased, and the margin of safety as defined in the basis for any Technical Specification was not reduced.
l All tests and experiments conducted in 1985 for Units 1, 2 and 3 were considered described and bounded by the safety analysis report.
Therefore, there were no tests and experiments conducted in 1985 applicable to 4
10 CFR 50.59 reporting requirements.
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