ML20093M693

1983 Facility Changes

ML20093M693
Person / Time
Site:	San Onofre
Issue date:	12/31/1983
From:	Haynes J SOUTHERN CALIFORNIA EDISON CO.
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 8410230145
Download: ML20093M693 (68)

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3 ATTACHMENT 1 UNIT 2 1983 FACILITY CHANGES TABLE OF CONTENTS FACILITY-CHANGE NO.

TITLE PAGE 2/3-82-073 Post' Accident Sampling System (PASS) - Electrical Modification 1

-2/3-82-184' Additional Motor Control Centers (MCC's) in Emergency Safety Function (ESF) Switchgear Rooms 2

2/3-82-192 Nuclear Water Service Tank Connections 3

2/3-82-276 Addition of a Drain Line to the Reactor Coolant Drain. Tank (RCDT) 4 2/3-82-599 Addition of Containment Isolation Actuation Signal (CIAS) for Component Cooling Water (CCW) Noncritical Loop Valves Inside the Containment 5

2/3-82-611 Addition of Fire Detectors 6

2/3-82-613 Addition of Drain Line for Collection of Reactor-Coolant Leakage 7

2/3-83-015

- Addition of New Air Conditioning System for Control Element Drive Motor (CEDM) Control Cabinet Room 8

2/3-83-039 Steam Generator Blowdown System Bypass Line 9

2/3-83-095 Additional Deluge Fire Protection 10 2/3-83-144 Modification of Control Circuitries 11

'2/3-83-199 Installation of Emergency Lighting 12 2/3-83-220 Modification to Post Accident Monitoring System 13 2/3-83-227 Modification of Turbocharger and Spring Drive Gears on

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Diesel Generator 14 2/3-83-242 Component Cooling Water (CCW) Isolation Valve Interlock Scheme 15 2/3-83-280 Sampler and Flow Totalizer for. the Steam Generator Blowdown Sample System 16 Nft !D

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TABLE OF CONTENTS (Unit 2 Continued) i FACILITY-PAGE F

~ CHANGE NO.

TITLE 2/3-83-291 Nuisance Alarm Elimination - Hot Leg Injection Header 17 2/3-83-294 Rerouting of. Reactor Coolant Pump.(RCP) Vapor Seal Leakoff Line 18

~2/3-83-304 Rerouting of Movable Incore Detector (MICD) Drain 19 2/3-83-331'

~ Control Buildig Emergency Filter Flow Instrumentation 20 2/3-83-394 Temporary ' Air Conditioning for Control Element Drive Motor (CE0M) Control Cabinets in Rooms 308A and 308B 21 i

2/3-83-430 Reactor Vessel and Refueling Cavity Water Level Indication 22 2/3-83-4311 Modification to Accident Monitoring System-Phase II 23 2/3-83-432

-Modification to Accident Monitoring System - Phase III 24 2/3-83-451' Steam Generator Blowdown-Flash Tank Replacement 25 2/3-83-460' Boric Acid Batching Tank Temperature Alarm Relocation 26

'2/3-83-463 Deletion of Remote Shutdown Panel (L-42) " Door Open" Alarm 27 2/3-83-540 Additional Ccmmunications Equipment at the Emergency Plant Parameter Monitoring System (EPPMS) Panel 28

-2/3-83-542

. Installation of Non-1E Uninterruptible Power Supply (UPS) System 29 2/3-83-574 Replacement of Control Room and Local Differential Pressure Scales 30 2/3-83-643 Bypass Line Installation Around Vol,ume Control Tank 31 2/3-83-770 Control Room Status Information of Two Containment Isolation Valves 32 2/3-83-774 Interlocks and Status Lights for Heat Treating Mode of Operation 33 2/3-83-778 Relocation of Radwaste Discharge Line 34 L

'2/3-83-854 Stroke Positioners in Ammonia and Hydrazine Pump Control System 35 t Ol i

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FACILITY ~ CHANGE 2/3-82-073-e

-: TITLE -

Post-Accident Sampling System (PASS)

Electrical Modification-DESCRIPTION

-This facility. change--installed eighteen nonsafety-related cables to the PASS system.

SAFETY EVALUATION This PASS modification was n'onsafety-related.

Review of the change concluded that neither the' probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any

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equipment used as a basis for any accident evaluated in the FSAR.

The Lpossibility of an unevaluated accident was not created since there was no functional change or degradation to any equipment used as a basis for any incident evaluated in the_FSAR. -No margin of safety in the basis for any-Technical Specification.was reduced. Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE ~ 2/3-82-184

-TITLE

- Additional Motor Control Centers (MCC's) in Engineered Safety Features (ESF)

Switchgear Rooms.

DESCRIPTION This modification installed two Class IE (480 Volt) MCC's (2 BRA & 28RB), one for each of the two safety load groups A and B.

The change was to accommodate known and anticipated load additions, including motor operated valves (MOVs)

for. Shutdown Cooling System (SDCS) and Inadequate Core Cooling (ICC) uninterruptible power supply loads.

SAFETY EVALUATION The additional MCC's are safety-related. The FSAR Section 8.3.1.1.3, Table 8.3-2, Table 8.3-1, Figure 8.3-6, and Figure 8.3-7 were modified to include the MCCs cddition to the ESF. Busses 3804 and 3806.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased by this change. The subject design change ensured adequate margin in MCC~ source for adding loads related to SDCS modifications and Class 1E loads. The possibility of an unevaluated accident was not created since.there was no functional change or degradation

-.of any equipment used as a basis for any incident evaluated in the FSAR. No margin of safety in the basis for any Technical Specification was reduced because the addition of two MCC's provided adequate margins to add increasingly expanding Class 1E loads covered in the Technical Specifications. Therefore, there was-no unreviewed safety question associated with this modification.

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FACILITY CHANGE 2/3-82-192 i

TITLE-

Nuclear Water Service Tank (NWST) Connections DESCRIPTION.

This modification installed an automatic level control system for the NWST

.T-104 to increase the efficiency of the system. The new system automatically adds water'whenever needed from the Demineralizer Water Header through a pneumatically operated level control valve controlled by a signal from the NWST Level Transmitter LIT-7900..Previously, the demineralizer or the condensate pump and associated valves required manual aligning.

Revision (1) to.this' facility change deleted the existing connection to the Condensate Storage Tank to reduce the potential for chemical contamination of the NWST.

-SAFETY EVALUATION-The NWST is safety-related. Review of the change concluded-that neither the probability nor the consequences of any previously evaluated accident were inc'reased because this modification increased the efficiency of the system by

the addition of the-automatic refilling capability. The possibility of an unevaluated accident was not created since there was no functional change or

' degradation to any equipment used as a basis for any incident evaluated in the FSAR.' No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore, there was no unreviewed safety question associated with this change.

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E-TITLEJ; IAddition' of a Drain Line tolthe Reactor--Coolant Drain Tank (RCDT)

LDESCRIPTION

!This modification" provided lan.-effective : leak detection system of: the..

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eflexitallic, gasket between the Reactor. Coolant Pump (RCP) casing and the pump

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cover; 1The change'was-implemented on:each of the.four.RCP's.

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addition -of= a drain 11ne to 'RCDT, a pressure-transmitter, a control valve and -

1 Ma pressure? indicator 1with :an~ annunciator in the-control room. This results in early detection of.the gasket failure, and.the preclusions:of-the RCP stud and

bolt corrosion inherent with seal leakage.

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. SAFETY' EVAL'UATION -

-The'modificationsJare nonsafety related.' Review of:the change concluded that-neitherithe-probability nor..the consequences of any previously evaluated accident:were increased because~ the addition of the modification improved previous gasket;1eakage inspection.- In addition; the modification did not

. create (the possibility ~ for'an. accident or. malfunction of a different type = than

any previously1evaluatedLin the.FSAR, nor=was any margin of safety' reduced in:

the basistfor.any Technical Specification. Therefore,:there was-no unreviewed

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safetytquestion associated with this. change.

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FACILITY CHANGE 2/3-82-599 TITLE Addition'of Containment Isolation Actuation Signal (CIAS) for Component Cooling Water (CCW) Noncritical. Loop Valves Inside the Containment DESCRIPTION This modification added (CIAS) to (CCW) noncritical loop supply and return containment isolation valves (3HV-6223~and 3HV-6236) inside the containment.

The change.was made pursuant to the criteria for containment isolation for ropen: loop systems, FSAR Section 6.2.4.1E and General Design Criteria 55 and

56..These modifications ensure that on LOCA or steam line rupture these valves 'will close, reducing'the possibility of releasing radioactive materials-to the atmosphere and maintaining containment integrity.

SAFETY EVALUATION The CCW ' system is safety-related and interfaces with the Reactor Coolant Pumps

.and Engineered Safety Feature Actuation System.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because there is no effect on the response of.the CCW system and these' valves can still be actuated manually at the

. operator's discretion. The possibility of an unevaluated accident was not created since there was no functional change or degradation'to any equipment

used as a basis for any incident evaluated in the FSAR. There was a change to Technical Specification 3.3.2, Tables 3.3-5 and 3.6-1.

This change minimizes the possibility of release of radioactive materials to the atmosphere.

No margin.of safety in the basis for any Technical Specification was reduced by

.this change since it-supports the intent of the basis of the Technical Specifications. Therefore, there was no unreviewed safety question associated with the change.

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FACILITY CHANGE 2/3-82-611 L

TITLE '

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Addition of Fire DetectorsL g

-DESCRIPTION eThis modification insta11ed' additional fire detectors in -Unit 2 Fire Zones 11, 28,: 45, 62, >72 'and ;in Room 248A of the 1 Technical Support. Center. -This c

. facility change was implemented to satisfy a Unit 2 Operating License s

v Jcondition.

SAFETY: EVALUATION' 1The insta11ationfof these additional fire detectors-is nonsafety-related. The change required editorial revisions to -the Technical Specifications, Fire!

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< - Hazard Analysis and the FSAR to include these additional detectors.

Review of (the change concluded that neither'the probability nor the consequences of any previously evaluated accident were increased because this~ addition of fire.

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detectors ensures adequate early warning detection of fires'in the specified areas._;The possibility'of an unevaluated accident.was'not created, since-

.there wa's no functional. change or degradation of equipment used as a' basis for L; any tincident evaluated _in FSAR. (This change required Table 3.3-11 of the Technical Specifications to be updated-to include the added detectors and'

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increases'the number of detectors which 'are ' required to ' demonstrate

operability.oer the. Technical Specification Section 3/4 3.3.7.

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safety.in theLbasisLfor'any Technical Specification'was reduced by this change. ;Therefore,1there was no 'unreviewed safety' questions associated with

.this modification.

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FACILITY-CHANGE'2/3-82-613 TITLE' 1

Addition of Drain.Line for Col nection of Reactor Coolant Leakage DESCRIPTION This modification provided a' tapped hole in each Reactor Coo' ant Pump drive l

mount and installed piping to a gravity drain to remove borated reactor

-coolant which leaks and collects in the drive-mount area.

~ SAFETY EVALUATION The Reactor Coolant Pumps are safety-related.

Review of the change concluded that neither.the probability nor the consequences'of any previously evaluated accident or malfunction of equipment important toL safety were increased Tbecause.the change ensures operation within the design basis of FSAR Sections 5.4.1 and 9.3.3.

The possibility of an unevaluated accident was not c'reated because there was no changes in_the design function of the system. No

< margin offsafety 'in tha basis for any Technical Specification was reduced by this change. -Therefore, there was no unreviewed safety question associated with this modification.

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3 FACILITY-CHANGE 2/3-83-015

. TITLE.

Addition ~of New Air Conditioning System for Control Element Drive Motor (CEDM)

Control-Cabinet Room DESCRIPTION This modification added an'. air conditioning system to the CEDM Control Cabinet Room.- This system maintains a maximum. temperature of 75 F and approximate relative humidity of-50% at the maximum space cooling load. The modification

'added'an air conditioning unit to the CEDM room sized for 50% of the total cooling load.

SAFETY EVALUATION

-The CEDM Control Room cabinets are not safety-related. Review of the change

. concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change did not affect the function of any equipment used as a basis for any accident evaluated in the FSAR. There was a. revision to Section 9.5.1.5.10 of the FSAR to address

- the deviation in fire damper and -fan operation upon sensing a fire; also Sections 3.2 and 9.4.2.11 were changed to reflect the.new design parameters.

The possibility of an unevaluated accident was not created since there was no fun'ctional change or degradation to any equipment used as a basis for any incident evaluated in the FSAR. No margin of safety in the basis for any Technical Specificaton was reduced by this change. Therefore, there was no unreviewed safety question associa ed with this modification.

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! FACILITY CHANGE 2/3-83-039 gj TITLE-Steam Generator Blowdown System Bypass Line

- DESCRIPTION DThe modification odded a_ bypass line to the blowdown system and additional l controls and instrumentation required _for proper monitoring of the blowdown

~ processing system bypass during all modes of operation. The change routes blowdown flow.from the steam generatorsidtrectly to the circulating water

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system discharge and facilitates steam generator-water chemistry control during periods;when the'blowcown processing system is unavailable.

SAFETY EVALUATION'

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TheLSteam Generator Blowdown Bypass System is nonsafety-related. Review of

.the change concluded that neither the probability nor the consequences of any

previously evaluated accident were increased because the system function remains as originally intended and the change ensures compliance with the FSAR design basis. The possibility of an unevaluated accident was not created because-the system is' designed to function identically to the existing blowdown processing system. The Technical Specification 3/4.3 was revised to i include this change' No margin of safety :to the basis for any-Technical Specification is reduced by_this change. Therefore, there was no unreviewed safety question associated with this modification.

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_ FACILITY CHANGE 2/3-83-095 TITLE

-Additional Deluge Fire Protection

. DESCRIPTION The change.added~a Deluge Fire Protection System over the turbine and motor drivers of the Feedwater Pumps (P-504 and P-140). This system utilizes a deluge valve with actuation from heat detectors located in accordance with Section:I.I, Fire Detector Design Basis, of the Fire Hazard Analysis. This system and the_ installation of the lube oil shroud (addressed in a previous facility change) ensured adequate fire protection to the motor driven pump (P-504) from the turbine driven pump's (P-140) lube oil system.

SAFETY EVALUATION-The Deluge Fire P-otection System is nonsafety related. Revisions were made to the safety evrluation for the Fire Protection System in Section 9.5.1.3 Paragraph D, of the FSAR, to include a dry pipe deluge system in the Auxiliary Feedwater Pump hoom and to Table 9.5-2 of the FSAR to add heat detectors inside _the Auxiitary Feed Pump Room. Also revisions were-made to the Technical Specification in Table 3.3-11 to include addition of heat detectors for_ deluge actuation, and to Table 3.7-5 to include the addition of a deluge-system in the' auxiliary feedwater area over the adjacent pump drivers.

Review of the change concluded that neither the probability nor the consequences of p

any previously evaluated accident were increased because the change ensures the' required fire protection is maintained, thus complying with the FSAR design basis. The-possibility of an unevaluated accident was not created

~ ince there are no changes in the design function of the system. No margin of s

safety to the basis for any Technical Specification was reduced by this change, as there was no impact on those parameters or surveillance requirements governed by the existing Technical Specification.

Therefore, there was no unreviewed safety question associated with this modification.

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-Modification-of Control Circuitries DESCRIPTION This modification changed the control circuitry of several devices, to bring the design in compliance with NRC IE Bulletin 80-06. The bulletin recommended Ethat all devices actuated by the Engineered Safety Features Actuation

' System (ESFAS) should remain in the same. status which they were in at the time ESFAS' reset was actuated. The affected componer'.s were:

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Safety Injection Tank Outlet Valves HV-9340, 9350, 9360 and 9370.

Safety-related 2.

Emergency Core Cooling System Pump Mini-Flow Lines Isolation Valves HV-9306, 9307, 9347 and 9348. Safety related 3.'

Spray Chemical Addition Pump Discharge Flow Control Valves FV-0318 and 0328. Safety-related 4.

Onsite Technical Support Center (0TCS) Uninterruptible Power Supply

'. Unit YO10..Nonsafety-related 5.

Pressurizer Back-Up Heaters E-128 and 129. Nonsafety-related 6.

Low Pressure Turbine Emergency Spray Water Pump P-145.

Nonsafety-related 7.

Essential Lighting Transformer LTLP-35. Nonsafety-related SAFETY EVALUATION This modification is both safety-related and nonsafety-related.

Review of the

' change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because none of the changes affect the designed function of the system or prevent the devices from performing their safety function. The possibility of an unevaluated accident or malfunction of a different type.than any previously evaluated in FSAR was not created. No margin of safety in the basis for any Technical Specification was reduced by this change since the equipment affected is neither governed by Technical Specifications nor impacts any existing Limiting Conditions for Operations or Surveillance Requirements. Therefore, there was no unreviewed safety question associated with this change.

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-y FACILITY CHANGE' 2/3-83-199

-TITLE Instaliation of Emergency Lighting DESCRIPTION This modification Linstalled new self-contained sealed beam battery power pack lighting units in the area of the Intake Structure and in specified access and egress-routes. The. change corrected the deficiencies identified in the Emergency Lighting System relative to conformance-to the Fire Hazard Analysis.

SAFETY EVALUATION The Emergency Lighting System is nonsafety-related. R? view of the change concluded that neitherzthe probability nor the consequences of voy previously evaluated accident were increased because no design basis was changed. The possibility of an unevaluated accident of a different type than any previously evaluated in the FSAR was-not created. No_ margin of safety in the basis for any Technical Specification was reduced since the equipment covered by this change is not governed by the Technical' Specifications. Therefore,,there was no unreviewed safety question associated with this change.

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. FACILITY CHANGEL2/3-83-220

-TITLE -

Modification to Post Accident Monitoring (PAM) System

-DESCRIPTION This modification made changes to the PA.i system, to bring the system design in conformance with NRC Regulatory Guide 1.97, Revision 2 requirements. - The existing non-1E qualified transmitters were replaced with IE qualified transmitters. Two existing non-1E qualified _ indicators were replaced by 1E qualified indicators and annunicators werel installed to display the status of pressurizer backup heaters.

SAFETY EVALUATION This modification to the PAM System is safety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because more reliable and qualified instruments were installed.. The possibility of an unevaluated accident of a different type Lthan any previously avaluated in the FSAR was not created. No margin of safety in the basis for any Tcchnical Specification ~was reduced since no change occurred in system' operation or surveillance ~ requirements. Therefore, there was no unreviewed safety' question associated with this change.

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FACILITY CHANGE 2/3-83-227

' TITLE Modification of Turbocharger and Spring Drive Gears on Diesel Generators DESCRIPTION sThis modification changed the standard duty turbochargers to heavy-duty turbochargers. The new turbochargers were developed by General Motors (diesel generator manufacturer) specifically for use on emergency diesel generator sets. Spring-drive gears were also changed in accordance with General = Motors recommendations for engines where reliability is high priority.

SAFETY EVALUATION The emergency diesel generators are safety-related. This'changeout is in response to NRC Question 040-72.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment used as a basis for any accident or malfunction evaluated in the FSAR. The possibility' of an unevaluated accident was not created, since there was no functional change or degradation to any equipment used as a basis for any incident evaluated in the FSAR. No margin of safety in the basis for any

- Technical Specification was reduced by this change. 'Therefore, there was no unreviewed safety question associated with this change.

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. FACILITY' CHANGE'2/3-83-242 g

TITLE

. Component Cooling Water (CCW) Isolation Valve Interlock Scheme

. DESCRIPTION' This modification revised the interlock' scheme for the isoittion valves of the (CCW noncritical loop. The change al. lows the closed train isolation valves to

-begin opening while the opened train isolation. valves are being closed.

Also, the setpoints for the CCW Surge Tank Pressure Relief Valves and Surge JTank Nitrogen Regulator Valves are increased slightly to mitigate any mass transfer transient between CCW loops.

-SAFETY EVALUATION This modification is safety-related. System operation as described in Section 9.2.2.2.3.4 of the FSAR has been revised.to incorporate this change.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased. This

' modification reduced the likelihood of Reactor Coolant Pump seal failure by providing continuous Component Cooling Water to the seal coolers. The possibility of an unevaluated accident was not created since there vas no functional change or degradation of any equipment used as a basis for any

' incident evaluated in the FSAR. No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore, no unreviewed

-safety question was. associated with this change.

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- FACILITY CHANGEL2/3-83-2801

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, Sampler and Flow -Totalizer for the -Steam Generator Blowdown Sample

--System (SG8SS)

DESCRIPTION'

' This' change +enh'anced the SGBSS in order to provide proper monitoring ~of the

' Blowdown Processing System Bypass during all'its modes of operation. The-T

-modification also added a flow totalizer and a proportional sampler to the

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existing SGBSS of-each: steam generator.

SAFETY EVALUATION-The Steam Generator-Blowdown Sampling System is nonsafety-related.

Section.10.4.8 of the FSAR has been revised to include the additional controls 1

and instrumentation required by this change. Section 11.5 of the FSAR has

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been revised to include the revised sampling information. Review of the change concluded that neither the probability nor the consequences of any

- previously evaluated accident were increased because the failure modes and

-related;affects are no-different from~that previously analyzed. The

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possibility of an-unevaluated accident was not created since the system is

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' designed to function identically to the'previously existing Blowdown 1 Processing System..Technica1' Specification 3/4.3 was also revised to include

-this modification. ~No margin _of safety in the be. is for any Technical Specification was reduced by this change. Therefore, there was no unreviewed-safety question associated with this modification.

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p FACILITY' CHANGE 2/3-83-291 TITLE Nuisance Alarm Elimination - Hot. Leg Injection Header DESCRIPTION This modification' eliminated a nuisance alarm resulting from small leakages past check valve 1204-3"-156 in the Hot Leg Injection Header No. 1, due to the short-length and small volume of the pipe section between the redundant check valves (1204-3"-156 and 1204-3"-158). lThe nuisance alarm was suppressed by

disconnecting the cable to the high pressure alarm of. loop 9422. The signal to the computer and the Control Room pressure indicator was retained.

SAFETY EVALUATION

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The alarm is nonsafety-related. Review of the change concluded that'neither the probability nor the consequences of any previously evaluated accident were

. increased because the change does not affect the function of any equipment used as basis for any accident. evaluated in the FSAR. The possibility of an unevaluated accident was nct created by this change. No margin of safaty in-the basis for_ any Technical Specification was reduced since the affected alarm is not required by any Technical Specification. Therefore, there was no unreviewed safety question associated with this modification.

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FACIL77v CHANGE 2/3-83-294

' TIT'LE t

Rerouting of Reactor Coolant Pump (RCP) Vapor Seal' Leakoff Line DESCRIPTION This modification provided a gravity flow path for the RCP Vapor Seal Leakoff to the floor drains instead of to the Reactor Coolant Drain Tank. The change was necessary to prevent leakage of reactor coolant from the RCP shaft from spilling onte-the drive mount area. 0perating Procedure S023-3-1.7 and S023-3-5.26 were revised by this change.

SAFETY EVALUATION The rerouting of the RCP Vapor Seal' Leakoff line'is nonsafety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased since the change did not affect operation within the design bases. The possibility of an unevaluated accident was not created because there are no changes in the design functions of the system. No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore, there was no unreviewed safety question associated with this modification.

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..,7 FACILITY CHANGE.2/3-83-304 TITLE Rerouting of Movable Incore Detector (MICD) Drain DESCRIPTION

.This change rerouted the MICD drain lines from the Reactor Coolant Drain Tank to the Containment Sump to prevent water backflow to the MICD transfer box, with the~ potential of ultimately damaging the MICD system. This chtqge assures the proper operation of the MICD and proper drainage of water if leakage occurs in the system.

SAFETY EVALUATION The MICD System is safety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because no functional change has occurred in the moveable in-core detector system. The possibility of an unevaluated accident was not created.since-there was no functional change or degradation to any equipment evaluated in the-FSAR. No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore, there was no unreviewed safety question associated with this modification.

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- FACILITY CHANGE 2/3-83-331 TITLE Control Building Emergency Filter Flow Instrumentation DESCRIPTION This facility change modified the flow measuring instrumentation of the control Building Recirculating Units to indicate the correct flow and to extend the range of the supply unit instrumentation.

- SAFETY EVALUATION

- The Control Room Emergency supply and Recirculation units and associated control panels are safety-related.

There were revisions and impacts to the FSAR as follows:

(a)_

Sections 6.4.2.2.2, 6.4.3.2, 6.4.4.2.1, and 6.4.5.1 are revised to show increased supply unit flow and exemption of the supply units,

~from Reg'ulatory requirements; (b)

Tables 158-5, 6.4-1A, and 9.4-5 are revised to indicate increased supply unit flows and related changes; (c):

Response to NRC Question 312.17 is revised; (d)

Table 9.4-3 is revised to indicate decreased smoke exhaust flow and increased recirculating unit flow; (e)

-Section 9.4.2.2.2.2 and 15B.7 is revised to indicate exemption to Regulatory requirements for the supply units.

There were revisions to Technical Specification Section 4.7.5 to show recirculation unit flow increase, supply unit exemption to Regulatory Guide 1.52 requirement, and HEPA and charcoal exemption to ANSI-N510.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated. accident were increased because the modifications do not

- alter the operation within the design basis. The possibility of an unevaluated accident will not be created because there is no change in the design function of the system. No margin of safety in the basis for any Technical Specification was reduced since there was no effect on existing Limiting Conditions of Operation or Surveillance Requirements governed by existing Technical Specifications.

Therefore, there was no unreviewed safety question associated with the modification.

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FACILITY CHANGE 2/3-83-394 TITLE Temporary Air Conditioning for Control Element Drive Motor (CEDM) Control Cabinets in Rooms 308A and 3088.

DESCRIPTION The modification provided an enclosure around the CEDM cabinets in the CEDM Control Cabinet Rooms (308 and 3088) and thermostatically controlled recirculation type air conditioning units within the enclosures. This was a-

-temporary modification to prevent the actuation of tha CEDM cabinets' high temperature alarms. This modification covers both Units 2 and 3 and was removed upon installation of Facility Changes 2/3-83-15 for-Unit 2 and 2/3-83-16 for Unit 3.

SAFETY EVALUATION The temporary air conditioning for CEDM Control Cabinets is nonsafety-related.

Section 9.5.1.5.10 of the FSAR and Zone 58 of the Fire Hazard Analysis were re' vised to include this change. Review of the change concluded that neither the' probability nor the consequences of any previously evaluated accident were

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increased because the change did not affect the function of any equipment used as a basis for any accident evaluated in the FSAR. The change provided added assurance that the-integrity of the CEDM control would be protected because of the icwered temperature. The possibility of an unevaluated accident was not created, since there was no functional change or degradation to any equipment used as a basis'for any incident evaluated in the FSAR. No margin of safety in the basis for any Technical Specification was reduced. Therefore, there-was no unreviewed safety question associated with this modification.

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-FACILITVCHANGE 2/3-83-430

TITLE ReactorLVessel and Refueling Cavity Water Level Indication 2 DESCRIPTION This change added an upper reactor vessel and refueling cavity' level monitoring system. -The level monitoring' system measures the-water level from the reactor hot leg.up to the~ top of the refueling cavity. This modification

.will assist operations personnel in maintaining Reactor Coolant System water level within. Technical Specification. limits during refueling.

< ' t

--SAFETY EVALUATION The level-indication is nonsafety-related. Review of the change concluded

that neither the probability nor the consequences of any previously evaluated accident were increased since the -change does not. modify any existing FSAR

_ design ' basis.:,The possibility of an unevaluated accident of a different type 4

- than any previously evaluated in the FSAR was not created. No margin of safety in the basis for any Technical Specification was reduced since the change had no_ impact on any Technical Specification.. Therefore, there was no unreviewed: safety question. associated with this modification.

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' FACILITY CHANGE 2/3-83-431 '

L it

' TITLE F

Modification t'o' Accident Monitoring System-Phase'II DESCRIPTION The modification to the Accident-Monitoring System (AMS) included-the following changes:

-1.

The installation and calibration of the Unit 2 Qualified Safety Parameter Display System (QSPDS).

2.

The provision of inputs 1to the~QSPDS.

3.

The deletion of the existing Subcooled Margin Monitors (SMM).

4.

The installation of a Operators Console.

5.

The installation of a CRT and keyboard for Critical Function Monitorin'g System.(CFMS) display.

6.

-The installation of a new Containment Electrical Penetration 1

-Assemblies (CEPA)~into existing containment nozzles.

t' 7.

Upgrading of Incore Instrumentation-System (ICI).

The Phase II. task of the AMS and the upgrading of the ICI system was required to enable the.AMS to function as designed and to comply with NUREG 0737 Item II F.2, NUREG 0696, and portions of Regulatory Guide (R.G.) 1.97.

SAFETY EVALUATION This change is nonsafety-related.

Review.of the change concluded that neither the probability nor'the. consequences of any previously evaluated accident were increased as a~ result of this change. The AMS is solely a data acquisition and display system.

It displays plant parameters important for the operator and the Technical Support Center personnel to assess the degree of unit safety during normal operating condition as well as during and after an accident.

.The possibility of an unevaluated accident was not created by this modification. No margin of safety in the basis for any Technical

~ Specification was reduced since this change upgrades the ICI's and will

. increase the operability and availability of the AMS. Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY' CHANGE 2/3-83-432 U

TITLE

' Modification to Accident Monitoring. System - Phase III L

. DESCRIPTION The implementation of the Phase III task of.the Accident Monitoring System o

. (AMS). included the following changes:

ll

.The Phase III inputs to the Critical Function Monitoring System F

(CFMS) and Qualified Safety Parameter Display System (QSPDS).

'2.

The~QSPDS power failure and. trouble' alarm annunication function.

The Phase III task of the AMS was required to complete the AMS to enable it to function as designed and to comply with NUREG 0737 Item II F.2, NUREG 0696,

'and-portions of Regulatory Guide (R.G.) 1.97.

' SAFETY EVALUATION

. This modification is nonsafety-related. Review of the change concluded that neither the probability nor the consequences of any'previously evaluated accident were increased since the system control display functions or design

'critoria were~not affected by this change. The possibility of an unevaluated accident was not created as a result of this change. No margin of safety in the basis for any Technical Specification was reduced. Therefore, there was no unreviewed safety question associated with.this modification.

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.FACILITI CHANGE 2/3-83-451 t

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-TITLE.

L L

-Steam Generator Blowdown Flash Tank Replacement L

DESCRIPTION

'This change'provided for the replacing of the existing Blowdown Flash Tank with~a larger tank. A steam purifier, modified piping and instrumentation to accommodate the change were also installed.

SAFETY EVALUATION The Blowdown Processing System is nonsafety-related.

Review of the change

, concluded' that neither.the probability nor the' consequences of any previously evaluated accident were increased because the change does not affect the L

-function of any equipment used as a basis for any accident or malfunction evaluated in the FSAR. The possibility of an unevaluated accident was not created, since there was no functional change or degradation of any equipment

-used as a basis.for any incident evaluated in'the FSAR. No margin of safety to the basis for any Technical Specification was reduced by this change because there was no functional change or degradation of any equipment used as a basis for any Technical Specification. Therefore, there was no unreviewed l

safety question associated with this modification.

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FACILITY CHANGE 2/3-83-460 TITLE Boric Acid Batching Tank Temperature Alarm Relocation

-DESCRIPTION

-This change moved the annunciation for the Boric Acid Batching Tank temperature alarm from the Main Control Room Panel to the Radwaste Local Control Panel. This modification eliminated an unnecessary alarm in the

-Control Room and improved the response time to the temperature alarm, making the process more ef ficient.

SAFETY EVALUATION The alarm is nonsafety-related.

Review of the change concluded that neither the_ probability nor:tna consequences of any previously evaluated accident were-increased as a result of this change. The overall function of the annunciator and the process was unchanged by this modification..The possibility of an unevaluated accident-was not created since there was no functional change or degradation to any equipment used as a basis for any incident evaluated in the FSAR. No margin of safety in the basis for any Technical Specification was reduced. :Therefore, there was no unreviewed safety question associated with this modification.

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- FACILITY CHANGE 2/3-83-463 TITLE-Deletion of Remote Shutdown Panel -(L-42) " Door Open" Alarm DESCRIPTION This modif.ication deleted the." Shutdown Panel (L-42) Door Open" alarm and' annunciator window from the Main. Control Room Panel, and deleted the alarm ninitiating switches and circuit from the shutdown 4 panel door. The intrusion

- alarm was-not needed since the shutdown panel was located in an area which is secured by a key. locked door and monitored by the.se:urity system.

SAFETY EVALUATION

-The annunciator system is.nonsafety-related. Review of the change concluded that neither'the probability nor the consequences of any previously evaluated accident were increased as a result.of this change. The possibility of an

~

unevaluated accident was not created because the design function and.

characteristics'of the shutdown panel were not changed or degraded in any

-way.

No margin of safety in.the basis for any Technical Specification was reduced by.this change.

Therefore,-there was no unreviewed safety question associated with this modification.

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x FACILITY CHANGE 2/3-83-540 TITLE Additional Communication. Equipment at the Emergency Plant Parameter Monitoring System (EPPMS) Panel DESCRIPTION This modification provided telephone communication capability between the EPPMS panel area and the Evacuation Shutdown Panel Room which may be used in the event of safe shutdown operation from this latter panel. The installation, consisted of a telephone, and associated cabling consistent with existing communication design.

SAFETY EVALUATION The additional communication equipment is nonsafety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment used as a basis for any incident evaluated in FSAR. This design change did not affect the function of the existing communication system. The possibility of an unevaluated accident was not created by this change. No margin of safety in the basis for any Technical Specification was reduced. Therefore, there was no unreviewed safety question associated with this modification.

28

FACILITY CHANGE 2/3-83-542 TITLE Installation of Non-1E Uninterruptible Power Supply (UPS) System DESCRIPTION This modification installed a UPS system to provide enough alternate power sources and switching capability to ensure continuous power to the non-1E instrumentation power panels during loss of offsite power or other loss of AC power events. The primary power to the UPS is from a Class IE source via an isolation device consistent with FSAR Section 8.1.4.3.14A, with the diesel generator as the backup.

In addition, the UPS system has a battery ride-through capability with an alternate AC power source from a none-1E bus.

SAFETY EVALUATION The UPS is nonsafety-related but interfaces with safety-related systems via an isolation circuit breaker. This change improves the reliability of power to the non-1E instrument power panels per the SCE evaluation of IE Information Notice No. 80-10 as supplemented by the March 1980 NSAC/INPO report.

Isolation circuit breaker 3A0412 will provide proper separation between the existing Quality Class II switchgear and the new Quality Class III UPS.

Although the FSAR response to NRC Question 222.44 was revised, no design bases have been changed.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because this change improves reliability of power to the non-1E instrument power panels. The oossibility of an unevaluated accident of a different type than any previously evaluated in the FSAR was not created. No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore, there was no unreviewed safety question associated with this modification.

29

i FACILITY CHANGE 2/3-83-574 l

TITLE Replacement of Control Room and Local Differential Pressure Scales DESCRIPTION This modification replaced the original 0-15 psid range scale with a 0-25 psid scale.

The affected instruments were 2PDIT-6484 and 2POIT-6485, which monitor

_ pressure drop across the Component Cooling Water (CCW) Heat Exchangers, as well as 2PDI-6484, and 2PDI-6485, which display the differential pressure on t

panel 2CR-64.' This change was required due to a higher than expected rate of s

buildup of saltwater debris coming in through the screens.

SAFETY EVALUATION The CCW system is safety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment

[

'used as a basis for any accident evaluated in the FSAR.

The possibility of an unevaluated accident was not created since there was no functional change or degradation to any equipment used as a basis for any incident evaluated in the FSAR.

No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore, there was no unreviewed safety question associated with this modification.

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l FACILITY CHANGE 2/3-83-643 TITLE Bypass Line Installation Around Volume Control Tank (VCT)

DESCRIPTION This facility change installed a bypass line with a locked-close globe valve around the VCT Gas Discharge Pressure Control Valve (PCV-9210) for use during a cover gas change to vent and purge the tant.

SAFETY EVALUATION The bypass line installation is safety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment used as a basis for any accident evaluated in the FSAR. The change did not alter the functional design of the Chemical and Volume Control System since the bypass valve is locked closed during all system modes except during cover gas change of the VCT. The possibility of an unevaluated accident was not created since there is no functional change or degradation to any equipment whose basis is evaluated in the FSAR. No margin of safety in the basis for any Technical Specification was reduced as a result of this change. Therefore, there was no unreviewed safety question associated with this modification.

1 31

FACILITY CHANGE 2/3-83-770 TITLE Control Room Status Information of Two Containment Isolation Valves i

DESCRIPTION This change modified control circuitries that indicate and alarm inoperable and bypass status of subject valves in the Control Room. The purpose of the change was to provide Control Room indications and alarms of the status of Component Cooling Water (CCW) motor-operated valves, HV-6223 and HV-6236.

SAFETY EVALUATION The subject valves are safety-related. This modification required a revision to Table 7.5.1 and Figure 7.5.2 of the FSAR.

Implementing this change provided additional information an equipment status in the Control Room to meet the requirements of NRC Regulatory Guide 1.47. Review of the change concluded that neither the probability nor the consequences of any previously l

evaluated accident were increased since the modification does not affect the function of any equipment used as a basis for any accident evaluated in the FSAR. The possibility of an unevaluated accident was not created by this modification. No margin of safety in the basis for any Technical Specification was reduced. Therefore, there was no unreviewed safety question associated with this modification.

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Y FACILITY CHANGE 2/3-83-174 TITLE l

Interlocks and Status Lights for Heat Treating Mode of Operation OESCRIPTION One change modified the circuits to the main turbine condenser pressure (vacuum) switches.

The other change modiffeo the turbine control logic to l

allow the condenser vacuum trip setpoint to be reset from 4.5" Hg absolute to 6.5" Hg absolute during circulating water heat treatment for more operational flexibility.

The modifications resulted from Startup Problem Reports which identified problems caused by the wide deadband of the main turbinc condenser pressure switches.

SAFETY EVALUATION l

This modification was nonsafety related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated l

accident were increased as a result of this change.

This modification reduces the probability of a turbine trip, and thereby reduces the probability of a reactor scram.

The possibility of an unevaluated accident was not created by this modification.

No margin of safety in the basis for any fechnical Specification was reduced by this change. Therefore, there was no unreviewed safety question associated with this modification.

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I FACILITY CHANGE 2/3-83-778' TITLE -

Relocation of Radwaste Discharge Line DESCRIPTION This facility changa relocated the radwaste discharge line from its eirrent location in the Circulating Water System weir vent structure (an unrestricted area) to a location inside the'Ridiologically Controlled Area. The radviste discharge line was routed to the Saltwater Cooling System on the discharge side of each Component Cooling Water Heat Exchanger.

The associated instruments, proportional samplers and interlocks were also installed.

SAFETY EVALUATION The relocation of the radwaste discharge line is safety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment used as a basis for any accident evaluated in the FSAR. The possibility of an unevaluated accident was not created since there was no functional change or degradation to any equipment used as a basis-for any incident evaluated in the FSAR. No margin of safety in the basis for any Technical. Specification was reduced by this change as no equipment whose basis is discussed in Technical Specification sections was impacted.- Therefore, there was no unreviewed safety question associated with this modification.

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i-FACILITY CHANGE 2/3-83-854 TITLE Stroke Positioners in Ammonia and Hydrazine Pump Control System.

' DESCRIPTION This' change replaced the electropneumatic control system with an electric control system which utilizes an electric stroke length positioner instead of a pneumatic control drive. The modification was necessary because the old system had become. obsolete and replacement parts were no longer available.

. SAFETY EVALUATION

--The replacemen't of an electropneumatic control system is nonsafety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased as a result of this change. -The possibility of an unevaluated accident was not created since there was no functional change or degradation of any equipment evaluated in the FSAR. No margin-of safety in the basis for any Technical Specification was reduced because no equipment used as a_ basis for any Techriical Specification Limiting. Condition of Operation or Surveillance Requirement was functionally changed or degraded. Therefore, there was no unreviewed_ safety m

question associated with this modification.

s 35

s ATTACHMENT 2 UNIT 3-

'1983 FACILITY CHANGES

. TABLE OF CONTENTS FACILITY.

CHANGE NO.

TITLE PAGE 2/3-82-185 Additional Motor Control Centers (MCC's) in Emergency Safety Function (ESF) Switchgear Rooms 1

2/3-82-293 Improvement of Process Sample Operation For Various Plant Systems 2

2/3-82-612 Addition of Drain Line for Collection of Reactor Coolant Leakage 3

~2/3-83-002 Replacement of Safety Injection Actuation Signal (SIAS) by Containment Isolation > Actuation Signal (CIAS) for Component Cooling Water (CCW) Noncritical Loop Valves Outside the Containment 4

- 2/3-83-003'

_ Addition of Containment Isolation Actuation Signal (CIAS) for Component Cooling Water (CCW) Noncritical Loop Valves Inside the Containment 5

~2/3-83-004 Deletion of Automatic Closure of Component Cooling Water (CCW) Valve 6

2/3-83-016.

Addition of New Air Conditioning System for Control Element Drive Motor _(CEDM) Control Cabinet Room 7

2/3-83-030 Installation of a Shutdown Cooling Low-Flow Alarm for Low Pressure Safety Injection Flow 8

2/3-83-040

. Steam Generator Blowdown System Bypass Line 9

~

2/3-83-046 Additional Deluge Fire Protection 10 l2/3-83-049

' Addition of Fire Detectors 11 g

2/3-83-200 Installation of Emergency Lighting 12 2/3-83-228 Mouification of Turbocharger and Spring Drive Gears on Diesel Generators 13 2/3-83-258 Component Cooling Water (CCW) Isolation Valve

. Interlock Scheme 14 2/3-83-281.

Sampler and Flow Totalizer for the Steam Generator Blowdown Sample System (SGBSS) 15

_ t- -

p TABLE OF' CONTENTS

p.

(Unit 3 Continued) n+

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FACILITY

~ CHANGE NO.

TIT'LE PAGE 2/3-83-292 Nuisance Alarm Elimination - Hot Leg Injection Header 16 L2/3-83-305-Rerouting of-Movable Incore Detector-(MICD) Drain 17 2/3-83-429-Reactor. Vessel:and-Refueling Cavity Water Level Indication 18 2/3-83-461 Boric lAcidBatchingTankTemperatureAlarmRelocation 19

~

9 2/3-83-464 Deletion of Remote Shutdown Panel (L-42) " Door Open" Alarm-20 2

-2/3 83-497 Shutdown Cooling System (SDCS), Valve Instrumentation.

21 2/3-83-541 Additional Communications Equipment at the Emergency Plant Parameter' Monitoring System-(EPPMS) Panel 22 2/3-83-543 Installation of Non-1E Uninterruptible Power Supply-(UPS) System 23

~2/3-83-575 Replacement = of ~ Control Room and Local Differential 1

Pressure Scales' 24 l'

2/3-83-644

~ Bypass Line Installation Around Volume Control Tank (VCT) 25 2/3-83-671 Steam Generator Blowdown Flash Tank Replacement 26 2/3-83-771.

Control Room Status Information of Two-Containment

~

Isolation Valves 27 L 2/3-83-874

-Stroke Positioners in Ammonia and Hydrazine Pump Control System 28 Q.(

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FACILITY CHANGE 2/3-82-185 TITLE Additional Motor Control Centers (MCC's) in Engineered Safety Features (ESF)

Switchgear Rooms DESCRIPTION This modification ' installed.two Class 1E (48'O Volt) MCC's (2 BRA & 2BRB), one for each of the two safety load groups A and B.

The change was to accommodate known and anticipated load additions, including motor operated valves MOVs for

. Shutdown Cooling System (SDCS) and Inadequate Core Cooling (ICC)

-Uninterru'ptible Power Supply (UPS) loads.

SAFETY EVALUATION The additional MCC's are safety-related. The FSAR Section 8.3.1.1.3, Table 8.3-2, Table 8.3-1, Figure 8.3-6, and Figure 8.3-7 were modified to include the MCCs addition to the ESF Busses 3804 and 3B06.

Review of the change concluded that neither the probability nor-the consequences of any

.previously evaluated accident were increased by this change. The subject design change ensures adequate margin in MCC source for adding loads related-to SDCS modifications and Class 1E loads. The possibility of an unevaluated accident was not created since there was no functional change or degradation offany equipment'used as a basis for any incident evaluated in the FSAR.. No margin'of. safety in'the basis for any Technical Specification was reduced because the addition of two MCC's provided adequate. margins to add increasingly expanding Class IE loads covered in the Technical Specifications. Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE 2/3-82-293 TITLE.

Improvement of Process Sample Operation For Various Plant Systems DESCRIPTION The purpose of this proposed change is to improve the plant Process Sampling System operations. The changes implemented'by this facility change are as follows:

1'.

-Improved drainage capacity for existing drainage systems as required.

2.

Unique installations as required for boric acid water.

3.

Catch basins for sample points,. routed to the nearest floor drain or sump, are provided where wet floors'would constitute a dangerous condition.

4.

Local gas sample stations modified to obtain pressurized-samples and new station design.

5.

Modification of boric acid-sample points to include heat tracing of pipe or. tubing sample lines.

6.

Feedwater heater sample points designed with portable cooler and vacuum pump for taking samples under process vacuum conditions.

7.

Permanent sample coolers are provided where required.

TSAFETY EVALUATION' Review of the change concluded that neither.the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment used as a basis for any incident evaluated in the FSAR. The new changes constitute an improvement to

'the existing sample system. The possibility of an unevaluated accident was

- not created, since there was no functional change or degradation to any equipment used as a basis ~for any incident evaluated in the FSAR.

No margin of safety in the basis for any Technical Specification was reduced by this change.

Therefore,'there was no unreviewed safety question associated with this modification.

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m FACILITY CHANGE 2/3-82-612

' TITLE TAddition of Drain Line for Collection of Reactor Coolant Leakage

' DESCRIPTION This modification provided a tapped hole in each Reactor Coolant Pump drive mount and installed piping to a gravity drain to remove borated reactor coolant which leaks and collects in the drive-mount area.

SAFETY-EVALUATION

.The Reactor Coolant Pumps are safety-related. Review of the change concluded that neither the probability nor the' consequences of any.previously evaluated accident or malfunction of equipment important to safety were increased

- because the change ensures operation within the design basis of FSAR

-Sections 5.4.1 and 9.3.3.

The possibility of an unevaluated accident was not created because there were no changes in the-design function of the system.

No margin of safety in the basis for:any Technical Specification was reduced by this change. -Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE 2/3-83-002-

- TITLE

- Replacement of Safety Injection Actuation Signal (SIAS) by Containment

' Isolation Actuation Signal (CIAS) for Component Cooling Water (CCW)

Noncritical. Loop Valves Outside the Containment

' DESCRIPTION-This' change 1 removed the SIAS from the CCW noncritical loop containment isolation valves 3HV-6211 and 3HV-6216 and CCW critical / noncritical loop

- isolation valves ~3HV-6212, 3HV-6213, 3HV-6218 and 3HV-6219 and replaced it with CIAS which provided cicsure of these valves upon a high energy event in the containment.

It is desirable to maintain CCW flow during a SIAS so as to minimize damage to the Reactor Coolant Pump (RCP) seals and the Control-Element Drive _ Mechanism (CEDM) windings due to a loss of coolant flow. This

- modification eliminated this unnecessary isolation.

SAFETY EVALUATION

.The CCW system is safety-related and interfaces with the RCP's and Engineered

-Safety ~ Features Actuation System. Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased by this change..The possibility of an unevaluated accident was not created since the change will minimize the cummulative damage caused by interuptions_of CCW which will result in an increase in RCP availability for non-LOCA events and a reduction in the the possibility-of excessive Reactor Coolant System (RCS) leakage resulting from seal failures. There was a change to Technical' Specification 3.3.2 and Table 3.3-5 to include this modification.

- No margin of safety in the basis for any Technical Specification was reduced.

.Therefore, there was no unreviewed safety question associated with this change.

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mFACILITY-CHANGE 2/3-83-003' 3

-TITLE-Addition of: Containment: Isolation' Actuation Signal _ (CIAS);for Component Cocl.ing Water '(CCW). Noncritical' Loop Valves Inside the Containment.

DESCRIPTION

This' modification'ad'ed:(CIAS) to (CCW)l noncritical. loop supplyLand. return d

containment! isolation valves;(3HV-6223 and 3HV-6236)'.inside the containment.

.-The change was made pursuant to _ the criteria -for containment ' isolation for.

11 topeniloop' systems,-FSARLSection-6.2.4.1E:and General. Design Criteria 55:and 56.1These modifications' ensure that on LOCA or steam line rupture these; ivalves will close,(reducing the possibility _of-releasing radioactive materials-Lto'the atmosphere _and maintaining. containment' integrity.

I-2 aSAFETY: EVAL ATION Thi CCWLsystem is safets-related;and. interfaces with the Reactor Coolant Pumps

and Engineered. Safety Feature Actuation System.

Review of the change-(concluded that neitherL the: probability nor the consequences of any previously Levaluated accident were increased because'there is no effect'on the_ response

~

of the CCW system and these valves'can:still be actuated manually at the-Loperator's discretion. LThe Jpossibility.of an.unevaluated accident.was not

~

7 created since there was no functional change or degradation to any. equipment used as a~ basis'for-any incident evaluated in'the:FSAR._ There was'a change:to

['"

c, Technical Specification 3.3;2, tTables: 3.3-5;and 3.6-1.

This change minimizes the' possibility of release of radioactive materials-to the atmosphere. No margin:of-safety:in,the basis for any-Technical Specification was reduced by

.this' change since:it supports-the11ntent of the. basis.of the-Technical

~

?

Specifications. LTherefore, there was_no unreviewed safety question associated jwith the change.

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F FACILITY CHANGE 2/3-83-004 TITLE Deletion of Automatic Closure of Component Cooling Water (CCW) Valve DESCRIPTION This modification provided for opening and closing of the control valve located in the CCW return line, by manual means only. The modification was incorporated to minimize the possibility of the supply of CCW being interrupted to the Reactor Coolant Pump (RCP) Seal Heat Exchanger.

SAFET.' EVALUATION

-The CCW system is safety-related. _ Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment used as a basis for any accident evaluated in the FSAR. This modification makes the system more reliable by protecting the RCP seals from high temperature excursions due to loss of CCW. The possibility of an unevaluated accident was not created, since there was no functional change or degradation to any_ equipment used as a basis for any incident evaluated in the FSAR. No margin of safety in the basis for any Technical Specification was reduced by this. change. -Therefore, there was no unreviewed safety question associated with this change.

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' FACILITY CHANGE' 2/3-83-016 x 1

TITLE Addition of..New Air. Conditioning System for Control Element Drive Motor (CEDM)

~

ControllCabinet Room-

-. DESCRIPTION Tnts modification added an. air conditioning system to the CEDM Control Cabinet

-Room. LThis system' maintain'sia. maximum temperature of 75*F and approximate

- :y.

relative humidity of 50% atlthe maximum space cooling Lload. The modification 3added;an' ' air conditioning unit to the CEDM room sized for. 50% of the total coolingpload.

SAFETY EVALUATION cThe1CEDM Control Room-cabinets are not. safety-related. : Review'of the change 2 concluded that'neitherfthe probability nor the consequences of any previously.

evaluated: accident were increased because the= change did not affect the O

ifunction'of any equipment-used as a basis'for any accident evaluated in the -

s FSAR.

There was-a1 revision to Section 9.5.1.5.10 of the FSAR to address

-the deviation in fire damper and. fan operation upon sensing a fire; also.

Sections 3.2 and 9.4.2.11 were changed to-reflect the new design parameters.

m The'po'ssibilityl~of an unevaluated. accident.was not created since there was no functionalLchange~or degradation to.any equipment used as a basis for any incident evaluated in the. FSAR. No. margin of safety in the basis for any.

/

Technical Specificatonlwas reduced by this change.- Therefore, there.was no

~-

-c unreviewed safety 1 question associated with this modification.

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e FACILITY CHANGE 2/3-83-030 TITLE-

-Installation of a Shutdown Cooling Low-Flow Alarm for Low Pressure Safety Injection Flow DESCRIPTION This modification added a low-flow alarm circuit to the Low Pressure Safety Injection System (LPSI) to monitor the Shutdown Cooling System (SDCS) function of the LPSI. The addition of this alarm was considered necessary to assure prompt _ corrective action on loss of this flow, since the LPSI pumps have their discharges below their impellers and they are susceptible to gas-binding. The new alarm to the-plant's annunciator system assures the SDCS will be properly vented and prevent possible LPSI pump damage.

SAFETY EVALUATION The Low-Flow Alarm is nonsafety-related aut interfaces with the LPSI system, which is safety-related.

Review of the change concluded that neither the probability nor the consequences of-any previously evaluated accident will be increased because the change will not effect the ability of the LPSI pump to

-perform itsrsafety function and will assure prompt corrective action on loss of flow. This change added annunciation capability to the SDC portion of LPSI and will not impact events which require LPSI System operation. The possibility of an unevaluated accident will not be created since there was no functional change or degradation to the LPSI pumps or any interfacing equipment. No margin of safety in the basis for any Technical Specification will be reduced by this change because there is no functional change or degradation of'any equipment used as a basis for any Technical Specification.

This change ensures operators will be made aware of low flow situations during SDCS._ Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE 2/3-83-040 t

? TITLE

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. Steam. Generator Blowdown System Bypass Line DESCRIPTION.

The modification added a' bypass line to the blowdown system and additional controls and. instrumentation required for proper monitoring of the blowdown

. processing' system bypass;during all modes of operation. The change routes blowdown flow from the steam; generators directly'to the circulating water system. discharge and ' facilitates steam -generator water chemistry control

t iduring periods when;the blowdown processing. system is unavailable.

SAFETY EVALUATION The Steam Generator Blowdown Bypass System is nonsafety-related.

Review of

-the change concluded that neither the probability nor the consequences of any

'previously evaluated accident were increased because the system function remains as originally. intended and the-change ensures compliance with the FSAR design-basis.' The possibility of an unevalutated accident'was not created because:the system.is designed to function identically to the existing

. blowdown processing system. The Technical Specification 3/4.3 was revised to

' include.this change.

No margin of-safety to the basis for any Technical LSpecification is reduced by this change.

Therefore, there was no unreviewed

-safety question associated with this modification.

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' FACILITY CHANGE 2/3-83-046 TITLE Additional' Deluge Fire Protection

~ DESCRIPTION The change added a Deluge Fire Protection System over the turbine and motor drivers of the adjacent Feedwater Pumps (P-504 and P-140). This system utilizes a deluge valve with actuation from heat detectors located in

-accordance with_Section I.I, Fire Detector Design Basis, of the Fire Hazard Analysis. This system and the installation of the lube oil shroud (addressed in a previous facility change) ensured adequate fire protection to the motor

-driven pump (P-504) from the turbine driven pump's (P-140) lube oil-system.

SAFETY EVALUATION The Deluge Fire Protection System is nonsafety-related. Revisions were made to the safety evaluation for the Fire Protection System in Section 9.5.1.3 Paragraph D, of the FSAR, to include a dry pipe deluge system in the Auxiliary Feedwater Pump Room and to Table 9.5-2 of the FSAR to add heat detectors inside the Auxiliary Feedwater Pump Room. Also revisions were made to the Technical Specification in Table 3.3-11 to include addition of heat detectors for deluge actuation, and to Table 3.7-5 to include the addition of a deluge system in the auxiliary feedwater area over the adjacent pump drivers.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change ensures' the required fire protection is maintained, thus complying with the FSAR design basis. The possibility of an unevaluated accident was not created since there are no changes in the design function of the system. No margin of safety to the basis for any Technical Specification was reduced by this change, as there was no impact on those parameters or surveillance requirements governed by the existing Technical Spe'cification. Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE' 2/3-83-049' TITLE Addition of Fire Detectors

' DESCRIPTION =

~This modification installed additional fire detectors in Unit 3 Fire' Zones 11, 28, 45, 62, 72'and in Room 248A of the Technical Support Center. This facility change was implemented to _ satisfy Unit 3 Operating License condition.

SAF TY EVALUATION

The: installation of these addiE1onal fire detectors.is nonsafety-related. The change l required editorial revisions to the Technical Specifications, Fire Hazard Analysis and the FSAR to include these additional detectors.

Review of

-the' change concluded that neither the probability nor the consequences of any previously evaluated accident were-increased because this addition of ffre detectors ensure adequate early warning detection of fires in the specified~

areas..The possibility _of-an unevaluated accident was not created, since there was no functional change or degradation of equipment used as a basis for any. incident evaluated in FSAR. This change required Table 3.3-11 of the Technical Specifications'to be-updated to include the added detectors and -

' increases the number of detectors which are required to demonstrate coperability per'the Technical Specification Section 3/4.3.3.7.

No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore, there was no unreviewed safety questions associated with this modification.

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FACILITY CHANGE-2/3-83-200 TITLE

-Installation of Emergency Lighting DESCRIPTION Ihis modification installed new self-contained sealed beam battery power pack lighting units in_the area of.the Intake Structure and in specified access and egress. routes. The change corrected the deficiencies identified in the Emergency Lighting System _ relative to conformance to the Fire Hazard Analysis.

SAFETY EVALUATION The Emergency Lighting System is nonsafety-related. Review of the change concluded

that neither the probability nor the consequences of any previously evaluated accident were increased because no design basis was changed.

The possibility of an unevaluated accident of a different type than any previously evaluated in the FSAR was not created.

No margin of safety in.the basis for any_ Technical Specification

'was reduced since the equipment covered by this change is not governed by.the Technical Specifications. Therefore, there was no unreviewed safety question-associated with this change.

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FACILITY-CHANGET2/3-83-228.

- ' TITLE

' Modification of' Turbocharger and Spring Drive Gears on Diesel Generators 1 DESCRIPTION {

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7This modificatiot changed the standard. duty turbochargers to heavy-duty turbochargers.- lThe new turbochargers were developed by General Motors l(diesel generator manufacturer) specifically for use on emergency diesel

generator sets and tincorporate stronger. drive gears. Also, spring-drive gears were changed in accordance with General. Motors recommendations for engines a

'where. reliability is high~ priority.

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SAFETY EVALUATION LThe emergency diesel generators-are safety-related. This changeout is in

. response.to-NRC Question ~040-72.

Review of. the change concluded that neither the probability nor the consequences of any previously evaluated accident were

. increased _because the change does not affect the function of any equipment used as a basis for any accident or malfunction evaluated in the FSAR.~ The possibility of'an'unevaluated accident was.not created, since there was no

- functional change or degradation to any equipment used as.a basis for any-incident:evaluatedLin~the.FSAR. No margin.of. safety in the basis for any

, Technical Specification was reduced by this change. Therefore, there was no

unreviewed safety question associated with this. change.

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FACILITY CHANGE 2/3-83-258 TITLE

- Component Cool-ing Water '(CCW) Isolation Valve Interlock Scheme DESCRIPTION This modification revised the interlock scheme for the isolation valves of the CCW noncritical loop. The change allows the closed train isolation valves to begin opening while the opened train isolation valves are being closed.

Also, the setpoints for the CCW Surge Tank Pressure Relief Valves and Surge Tank Nitrogen Regulator Valves are increased slightly to mitigate any mass transfer transient between CCW loops.

SAFETY EVALUATION This modification is safety-related. System operation as described in Section 9.2.2.2.3.4 of the FSAR has been revised to incorporate this change.

Review of the change concluded _that neither the probability nor the consequences of any previously evaluated accident were increased.

This modification reduced the likelihood of Reactor Coolant Pump seal failure by providing continuous Component Cooling Water to the seal coolers. The possibility of an unevaluated accident was not created since there was no functional change or degradation of any equipment used as a basis for any incident evaluated in'the FSAR.

No margin of _ safety in the basis for any Technical' Specification was reduced by this change. Therefore, no unreviewed safety question was associated with this change.

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FACILIT CHANGE-2/3-83-281 TITLE

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_ Sampler and Flow Totalizer for the Steam Generator Blowdown Sample

' System (SGBSS)i

DESCRIPTION This' change enhanced the SGBSS in order to provide proper monitoring of the BlowdownLProcessing System bypass during all its modes of operation. The modification.also added a' flow totalizer and a proportional sampler to the

'existingLSGBSS of each steam generator.

" SAFETY' EVALUATION The! Steam Generator Blowdown Sampling System is nonsafety-related.

Section 10.4.8 of the FSAR has been revised to include the additional controls and. instrumentation required by this. change.

Section 11.5 of the FSAR has-been revised to. include the revised sampling information.

Review of-the.

O change concluded that neither the probability nor the consequences of any previously ' evaluated accident were increased because the failure modes and

.related affe~ cts are no different from that previously analyzed. The possibility of an unevaluated. accident was not created since the system is designed to function identically to the previously existing Blowdown f

Processing System. Technical Specification 3/4.3 was also revised-to include'

' this modification. No margin of-safety in the basis for any-Technical

=

LSpecification was reduced by this change..Therefore, there was no unreviewed

safety question associated with this modification.

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'FNCILITY CHANGE 2/3-83-292 TITLE; Nuisance Alarm. Elimination. Hot Leg Injection Header DESCRIPTION This modification eliminated a nuisance a' arm resulting from small.. leakages past check valve 1204-3"-156 in the Hot Leg Injection Header No. 1,.due to.the short-length and small volume of the pipe-section between the redundant check

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valve's (1204-3"-156 and 1204-3"-158).. The nuisance alarm was suppressed by

- ; disconnecting the cable to the high pressure alarm of loop 9422..The signal Lto the computer.and the-Control Room pressure indicator was retained.

SAFETY EVALUATION

'lhe alarm is nonsafety-related. Review of the change concluded that neither

.the probability nor the consequences of any previously evaluated accident were increa' sed because the change does not affect the function of'any' equipment-

'used as basis for any accident evaluated in the FSAR. The possibility of an unevaluated accident was not created by this change. No margin of safety in

-the basis-for any Technical Specification was reduced since the affected alarm is not required by any Technical Specification. Therefore, there was no F,

Junreviewed safety question associated with-this modification.

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' FACILITY CHANGE 2/3-83-305

. TITLE Rerouting of Movable Incore Detector (MICD) Drain DESCRIPTION.

This change. rerouted the MICD drain lines from1the Reactor Coolant Drain Tank

'to'.the Containment Sump to prevent water backflow to the MICD transfer box, with the' potential of ultimately ~ damaging the MICD system. This change assures.'the proper operation of. the MICD and proper drainage ~ of water if -

leakage occurs'in the' system.

-SAFETY-EVALUATION The MICD System is safety-related.

Review of the change concluded that

-neither the probability'nor the consequences of any previously evaluated accident-were increased because no functional change has occurred in the moveable in-core _ detector system. The possibility of an unevaluated accident swas not created since there was no functional change or degradation to any equipment evaluated in the FSAR.. No margin of' safety in the basis for any Technical Specification was-reduced by this change. Therefore, there was no unreviewed: safety question. associated with this modification.

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. FACILITY CHANGE 2/3-83-429 TITLE Re' actor Vessel and Refueling Cavity Water Level Indication DESCRIPTION This' change added an upper reactor' vessel and refueling cavity level monitoring system. The level monitoring system measures the water level from the reactor hot _ leg up;to the' top of the refueling cavity. This modification will assist operations personnel in. maintaining Reacor Coolant System water

-level within Technical Specification limits during refueling.

SAFETY EVALUATION

'The level indication is nonsafety-related.. Review of the change concluded that neither the probability _nor the consequences of any previously. evaluated accident were increased since the change does not modify any existing FSAR

. design. basis. ;The pessibility of an unevaluated accident of a different type than any previously evaluated in the FSAR was'not created. No margin of safety in the basis for any Technical Specification was reduced since the change.had no impact on any Technical Specification. Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE 2/3-83-461 TITLE-Boric Acid Batching Tank Temperature Alarm Relocation DESCRIPTION

.This change l moved the annunciation for the Boric Acid Batching Tank

.tempsrature alarm from the Main Control Room Panel to the Radwaste Local Control Panel. This modification eliminated an uneccessary alarm in the

Control Room and improved the response time to the temperature alarm making s

-the' process more efficient.

SAFETY EVALUATION The_ alarm is nonsafety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased as a result of this change. -The overall function of the annunciator -

Land the process was unchanged by this modification. The possibility of an unevaluated accident'was not created since there was no functional change or

. degradation to any equipment used as a basis.for any incident evaluated in the FSAR. -No margin of safety in the basis for any Technical Specification was

_.re uce. Therefore, there was no unreviewed safety question associated with d

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L FACILITY CHANGE 2/3-83-464 I

TITLE Deletion of Remote Shutdown Panel (L-42) " Door Open" Alarm DESCRIPTION This modification deleted the " Shutdown Panel (L-42) Door Open" alarm arid annunciator window from the main Control Room Panel, and deleted th. alarm initiating switches and circuit from the shutdown panel door. The intrusion alarm was not needed since the shutdown panel was located in an area which is secured by a key locked door that is also monitored by the security system.

SAFETY EVALUATION

-The annunciator system is nonsafety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased as a result of this change. The possibility of an unevaluated accident was not created because the design function and characteristics of the shutdown panel were not changed er degraded in any way. No margin of safety in the basis for any Technical Specification v.ts reduced by this change. Therefore, there was no unreviewed safety question associated with this modification.

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ny FACILITY CHANGE 2/3-83-497

. TITLE.

Shutdown Cooling System (SOCS) Valve Instrumentation DESCRIPTION This modification provided a continuous valve position indication for SOCS l

-Valves ~3HV-8150 and 3HV-8151 at the main Control Room, and valve. status inputs to the Critical Function Monitoring System (CFMS) for Valves 3HV-0396,

'3HV-8160 and.3HV-8161. The. change was necessitated to provide adequate valve status information to the operator to preclude the potential risk of excessive

.heatup or cooldown of the Reactor Coolant System resulting from lack of adequate SCCS valve status information.

SAFETY EVALUATION The SOCS.is safety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased as a result of this change. No control function or safety-related display function was involved. The possibility of an unevaluated accident was not created'due to this modification. No margin of safety in the basis for any Technical Specification was reduced because there was no functional change or. degradation of-any equipment used as a basis for any Technical Specification. Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE'2/3-83-541.

TITLE.

1 Additional Communication Equipment at the Emergency Plant Parameter Monitoring System.(EPPMS) Panel DESCRIPTION

.This modification provided telephone _ communication capability between the

'EPPMS~ panel area 1and the Evacuation Shutdown Panel Room which may be used in the event of-safe shutdown _ operation _from this latter panel. The installation consisted of a telephone, and associated cabling consistent with existing

. communication design.

SAFETY EVALUATION The additional-communication equipment is nonsafety-related. Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not

-affect'the function of any equipment used as a basis for any incident evaluated in FSAR. _This design change did not affect the function of the

' existing communication system.

The possibility of an unevaluated accident was not created by this charge. No margin of safety in the basis for any Technical Specification-was reduced. Therefore, there was no unreviewed

' safety question associated with'this modification.

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l FACILITY CHANGE 2/3-83-543 TITLE Installation of Non-1E Uninterruptible Power Supply (UPS) System DESCRIPTION

~

This modification installed a UPS system to provide enough alternate power

. sources and switching capability to ensure continuous power to the non-1E instrumentation power panels during loss of offsite power or other loss of

'AC power events.

The primary power to the UPS is from a Class 1E source via an isolation device consistent with FSAR Section 8.1.4.3.14A, with the diesel generator as the backup.

In addition the UPS system has a battery ride-through capability with an alternate AC power source from a none-1E bus.

SAFETY EVALUATION The UPS is nonsafety-related but interfaces with safety-related systems via an isolation circuit breaker. This change improves the reliability of power to the non-1E instrument power panels per the SCE evaluation of IE Information Notice No. 80-10 as supplemented by the March 1980 NSAC/INPO report.

Isolation circuit breaker 3A0412 will provide proper separation between the existing Quality Class II switchgear and the new Quality Class III UPS.

-Although the FSAR response to NRC Question 222.44 was revised, no design bases have been changed. Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because this change improves reliability of power to the non-1E instrument power panels. The possibility of an unevaluated accident of a different type than any previously evaluated in the FSAR was not created. No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore, there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE 2/3-83-575-TITLE Replacement of ' Control Room and Local Differential Pressure Scales DESCRIPTION' This modification replaced the original 0-15 psid range scale with a 0-25 psid scale. The affected instruments were 2PDIT-6484 and 2PDIT-6485, which monitor pressure drop across the Component Cooling Water (CCW) Heat Exchangers, as well as 2PDI-6484,'and 2PDI-6485, which display the differential pressure on panel 2CR-64. This change was required due to a higher than expected rate of buildup of saltwater _ debris coming in through the screens.

-SAFETY EVALUATION The CCW system is quality class 2, safety-related. Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment used as a basis for any accident evaluated in the FSAR. The possibility of an unevaluated accident was not. created since.there was no functional change or degradation to any equipment used as a basis for any incident evaluated in the FSAR. No margin of safety in the basis for any Technical Specification was reduced by this change. Therefore there was no unreviewed safety question associated with this modification.

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FACILITY CHANGE 2/3-83-644 TITLE Bypass Line Installation Around Volume Control Tank (VCT)

DESCRIPTION This facility change installed a bypass line with a locked-close globe valve around the VCT Gas Discharge Pressure Control Valve (PCV-9210) for use during a cover gas change to vent and purge the tank.

SAFETY EVALUATION The Bypass Line Installation is safety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the function of any equipment used as a basis for any accident evaluated in the FSAR. The change did not alter the functional design of the Chemical and Volume Control System since the bypass valve is locked closed during all system modes cxcept during cover gas change of the VCT. The possibility of an unevaluated accident was not created since there is no functional change or degradation to any equipment whose basis is evaluated in the FSAR. No margin of safety in the basis for any Technical Specification was reduced as a result of this change. Therefore, there was no unreviewed safety question associated with this modification.

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1 FACILIThCHANGE 2/3-83-671-sTITLE-

Steam Generator Blowdown Flash ~ Tank Replacement

. DESCRIPTION-JThis change provided for the replacing'of the existing Steam Generator Blowdown: Flash Tank:with a larger tank. A steam purifier and modified piping and instrumentation to accommodate the change'were also installed.

e TSAFETY EVALUATION

- The Blowdown. Processing Syst'em is nonsafety-related.

Review of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased because the change does not affect the

' function of any equipment used as a basis for any accident or malfunction

-evaluated in the FSAR. The possibility of an~unevaluated accident was not Jereated,isince there wasino functional change or degradation of any equipment used:as a basis for an'y incident evaluated in'the FSAR. No margin of safety to the basis for any. Technical-Specification was reduced by:this change-7 because there was no functional change or degradation of any equipment as a

' basis for any Technical Specification. Therefore, there was no unreviewed Esafety question ~ associated with.this modification.

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--FACILITY C'HANGE 2/3-83-771 Y

TITLE-Contril' Room Status Information of Two Containment Isolation Valves DESCRIPTION This change modified control circuitries that indicate and.11 arm inoperable-xN and bypass status of subject valves.in the Control Room. The purpose of the

".; change was to provide Control-Room indications and alarms of the status of Component Cooling Water (CCW) motor-operated. valves, HV-6223 and HV-6236.

CAFETY EVALUATION

..The' subject valves are' safety-related.

This modification required a revision

'to Table 7.5.1_and Figure 7.5.2 of the FSAR.

Implementing this change provided' additional information an equipment status in the Control Room to

, meet the requirements of NRC Regulatory Guide 1.47.

Review of the change

-concluded that neither the probability nor the consequences of any previously P

evaluated acciderit were increased since the modification does not affect the function of any equipment used as a-basis for any accident evaluated in the FSAR. The possibility of an unevaluated accident was not created by this modification. No margin of safety in the basis for any Technical kSpecification was reduced.

Therefore, there was no unreviewed safety question

' associated with this modification.

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FACILITY'CHANGEI 2/3-83-874

~ TITLE Stroke Positioners in Ammonia _and Hydrazine Pump Control System.

iDESCRIPTION-1This change replaced the electropneumatic control system with an electric control system which utilizes an electric ctroke length positioner instead of a pneumatic control drive. The modification.was necessary because the old

. system had become obsolete and' replacement parts were no longer available.

SAFETY EVALUATION The replacement of an electropneumatic control _ system is nonsafety-related.

1 Review.of the change concluded that neither the probability nor the consequences of any previously evaluated accident were increased as a result of this change..The possibility of an unevaluated accident was not created-since there was no functional change or_ degradation of-any equipment evaluated

.inithe FSAR. lNo margin of safety in the basis for any Technical Specification was. reduced because no equipment used as a basis for any Technical Specification Limiting Condition of Operation or. Surveillance Requirement was functionally changed or degraded. Therefore, there was no unreviewed safety question associated with this~ modification.

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Southern California Edison Company WU S AN ONOFRE NUCLE AR GENER ATING ST ATION P.O. BO X 12 8 S AN CLEMENTE. C ALtFORNI A 92672

., J. G. H AY N ES vetapwoms

$7ATION M AN AGER (714) 492 7F00 September 24, 1984 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

Subject:

Docket Nos. 50-361 and~50-362 Facility Change Annual Report San Onofre Nuclear Generating Station,. Units 2 and 3 1

Pursu' ant to 10 CFR 50.59(b), this submittal provides the original and 39 copies of the required annual report describing facility changes at Units 2

.and 3.

This report covers the period January 1, 1983 to December 31, 1983, and is submitted in two parts; Attachment (1)

" Unit 2, 1983 Facility Change" and Attachment (2)

" Unit 3,1983 Facility Changes."

-If there are any questions regarding this report, please so advise.

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Enclo'sures cc:

-A.-E. Chaffee (USNRC Senior Resident Inspector, Units 1, 2 and 3)

J. P. Stewart (USNRC Resident Inspector, Units 2 and 3) q USNRC Document Control Oesk g6

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