ML20246D844

1988 Rept of Facility Changes,Tests & Experiments. W/

ML20246D844
Person / Time
Site:	Beaver Valley
Issue date:	12/31/1988
From:	Sieber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8905110070
Download: ML20246D844 (43)

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1988 Report of Facility Changes, Tests and Experiments TABLE OF CONTENTS P_ ace (s)

Facility Changes . . . . . . . . . . . . . . . . . . . 1 - 28 Operating Procedures . . . . . . . . . . . . . . . . . 29 - 38 Radiation Control Procedures . . . . . . . . . . . . . 39 - 40 UFSAR Change . . . . . . . . . . . . . . . . . . . . . 41 I

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) . BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 l l

TACILITY CHANGES Page 1 ,

I SAFETY EVALUATION NO.87-222  :

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. CHANGE TITLE Addition of Exciter Field Resistor )

J DESCRIPTION OF CHANGE  !

i During Hot Functional Testing, Generator Voltage Rise was I sluggish. A 250 OHM, 100 watt resistor was added in parallel to j the three existing exciter field starting resistors to correct the ]

problem. 1 i

SUMMARY

OF SAFETY EVALUATION l 1

The vendor verified and agreed with this change. The use of multiple 250 OUM resistors is recommended by vendor. This component (Main Turbine Generator) is classified as non-nuclear safety and is not required to operate during accident conditions.

SAFETY EVALUATION NO.87-228 CHANGE TITLE Add Insulation to Heater Drains Stand Pipe DESCRIPTION OF CHANGE Insulate stand pipes from moisture separator drain receiver tants 2HDH-TK22A,B,C,&D and reheater drain receiver tanks 2HDH-TK23A,B,C, & D for personnel protection. These pipes are l located near walkways and will be between 400' F and 500* F during operation.

SUMMARY

OF SAFETY EVALUATION Insulation, for this balance of plant system, is not safety related and was not evaluated in the Updated Final Safety Analysis Report. This modification does not involve a system design change j but merely insulates hot piping for personnel protection. There j is no impact on any safety related component or structure.

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FACILITY CHANGES Page 2 j l

' SAFETY EVALUATION NO.87-230 CHANGE TITLE Security A-C Distribution Panels DESCRIPTION OF CHANGE Circuits and Breakers were exchanged within the security distribution panels to balance the electrical loads.

SUMMARY

OF SAFETY EVALUATION These circuit reassignments have no affect on any safety related

. equipment. Security panels are classified as non-nuclear safety and have no impact on the accident analysis.

SAEETY EVALUATION NO.87-238 CHANGE TITLE Replacement of Transmitters DESCRIPTION OF CHANGE Replace existing 0 to 20 psig gauge transmitter with an absolute pressure transmitter to allow better computer input during vacuum service.

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SUMMARY

OF SAFETY EVALUATION .

The Extraction Steam System has no safety function and this modification will not affect safety related equipment. This modification merely replaces the installed transmitter with one better suited for vacuum service.

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% b BVPS-3 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 3 FAFETY EVALUATION NO.87-242 CHANGE TITLE Addition of Ground Connections for Digital Radiation Monitoring System (DRMS)

DESCRIPTION OF CHANGE Add a ground wire from the gas detector photo-multiplier tube for seventeen radiation monitors to the instrument bus ground. This modification was made to reduce noise on the gas channels.

SUMMARY

OF SAFETY EVALUATION This modification will not affect operation of the detectors. It is to reduce the possibility of erroneous alarms. The equipment will. operate in the same manner as described in the design basis and safety analysis documents. The environmental and seismic qualification are unchanged by this modification.

SAFETY EVALUATION NO.87-246 CHANGE TITLE Control Power To Solid Waste Control Panel DESCRIPTION OF CHANGE Add jumpers to solid waste panel to prevent spurious trip of control power on loss of instrument air or demineralized water pressure. This modification will enhance operation of the solid I waste controls.

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SUMMARY

OF SAFETY EVALUATION Solid Waste System is classified as QA Category II, non-nuclear safety. None of the affected equipment is required for safe shutdown. There is no affect on the accident- analysis, i

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- BVPS-2 Annual Raport of Facility Changes, Tests and Experiments for 1988 j FACILITY CHANGES Page 4 SAFETY EVALUATION NO.87-255 CHANGE TITLE Seal Opening OP-5G9 DESCRIPTION OF CHANG _E Seal opening OP-569 between the Auxiliary Building and Health Physics Building at el. 793' 3 3/4" and fire wrap the ductwork from the damper to the opening. This is required to meet 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire barrier requirements.

SUMMARY

OF SAFETY EVALUATION Modification will provide the required fire barrier between Aux.

Building and Health Physics Building at OP-569. Associated ducting is not safety related, fire wrap will not affect system operation; therefore, there is no unreviewed safety question. The Updated Final Safety Analysis Report will be revised to indicate that the fire wrapped ductwork deviates from Standard Review Plan Section 9.5.1.

I SAFETY EVALUATION NO.87-268 CHANGE TITLE Isolation Valve in Demineralized Water System DESCRIPTION OF CHANGE Add an isolation valve to provide the capability to isolate the condensate polishing building from the demineralized water system.

SUMMARY

OF SAFETY EVALUATION Demineralized Water System is Quality Assurance Category II, Non-nuclear Safety and does not affect essential systems or conponents necessary for safe shutdown.

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[ - BVPS-2 Annual R port of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 5 SAFETY EVALUATION NO.87-270 CHANGE TITLE Replace Condensate Polishing Bypass Valve DESCRIPTION OF CHANGE Replace existing valve with a new valve, old valve was damaged. l l

SUMMARY

OF SAFETY EVALUATIO_1{

This system is not safety related. This change will no' affect system operation as described in Updated Final Safety Analysis Report Section 10.4.7 or valve failure position as shown on Figure 10.4-7. Pipe supports have been evaluated and are adequate.

There is no unreviewed safety question.

L SAFETY EVALUATION NO.87-275 CHANGE TITLE Sealing of Spare Sleeves DESCRIPTION OF CHANGE Install seals in spare floor sleeves in the Safeguards Building to minimize tripping hazard and to contain spills.

SUMMARY

OF SAFETY EVALUATION l Subject sleeves are spares and are not required during any mode of I operation, and do not affect any system function; therefore, there is no unreviewed safety question.

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, BVPS-2 Annual Raport of Facility Changes, l Tests and Exp6riments for 1988 j FACILITY CHANGES Page 6 SAFETY EVALUATION NO.87-276 CHANGE TITLE control Room Clock DESCRIPTION OF CHANGE I Add a receptacle powered from an existing circuit and a digital clock to the control room wall outside shift supervisor's office.

SUMMARY

OF SAFETY EVALUATION This modification consists entirely of Quality Assurance (CA)

Category II non-nuclear safety components. The clock is not seismically qualified but it has been reviewed and a seismic failure will not impact any QA Category I components.

SAFETY EVALUATION NO.87-28P, CHANGE TITLE Replacement of Feedwater Flow Transmitter DESCRIPTION OF CHANGE Replace failed Barton transmitters with available spare Rosemount transmitter, j

SUMMARY

OF SAFETY EVALUATION 1

This modification is Quality Assurance (QA) Category I. The replacement transmitter will meet all requirements and functions of the original transmitters as discussed in Updated Final Safety Analysis Report Section 10.4.7; therefore, there is no unreviewed safety question.

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,' . BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 EACILITY CHANGES Page 7 SAFETY EVALUATION NO.87-298 CHANGE TITLE Addition of Diaphragm Seal to Solid Waste System Fluidizing Tank (WSS)

DESCRIPTION OF CHANGE Replace existing pressure switch which directly senses air pressure in the solid waste (WSS) fluidizing tank with a diaphragm seal and capillary system to minimize clogging of the sensing line.

SUMMARY

OF SAFETY EVALUATION This equipment is Quality Assurance (QA) Category III, non-nuclear safety. This modification will not affect the function or reliability of the pressure switch but will prevent clogging; therefore, there is no unreviewed safety question.

.S_AJJTY EVALUATION NO.87-307 CHANGE TITLE l Reroute Solid Waste System (WSS) Drains DESCRIPTION OF CHANGE Reroute WSS equipment drains from the Condensate Polishing i Building sump to the Waste Handling Building sump. This change l

Will take advantage of the sweep gas in Waste Handling Building sump since the drains may carry high level waste.

SUMMARY

OF SAFETY _gVALUATION This change is QA Category II, non-nuclear safety and results in the relocation of equipment drains, not in their deletion. There is no unreviewed safety question.

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 8 SAFETY EVALUATION NO.87-309 CHANGE TITLE

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Spent Resin Retention Screen Modification DESCRIPTION OF CHANGE Replace existing twenty-four spent resin holding tank retention screens with three vertical retention screens with backflush capability. Existing Gcreens clog easily and cannot be backflushed. Delete relief valve 2WSS-RV140 and add pressure control valve 2WSS-PCV202.

SUMMARY

OF SAFETY EVALUATION This system is Quality Assurance (QA) Category II, non-nuclear safety. Screen modification will enhance Solid Waste System (WSS) operation while reducing frequency of personnel access for maintenance. The Updated Final Safety Analysis Report will be revised to reflect these changes.

SAFETY EVALUATION NO.87-312 CHANGE TITLE Amertap Reinjection Pump Priming Connection DESCRIPTION OF CHANGE Add a valved connection into suction piping of Amertap reinjection pumps to supply a forced prime to these pumps when required.

SUMMARY

OF SAFETY EVALUATION These systems are not safety related, and their failure will not affect safe shutdown. The function of this system is to maintain condenser performance, it has no safety function. The UFSAR will be revised to reflect this change.

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,' - BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 9 SAFETY EVALUATION NO.87-321 CHANGE TITLE Add Backwash Filter to Condensate Demineralized DESCRIPTION OF CHANGE Add an in-line polishing filter between the backwach feed tank and demineralized tanks to reduce the amount of suspended solids recycled to the condensate water.

SUMMARY

OF SAFETY EVALUATION The condensate demineralized system is Quality Assurance (QA)

Category III, non-nuclear safety. This system is not required to be operable by the Updated Final Safety Analysis Report (UFSAR) accident analysis. The UFSAR will be revised to reflect this modification.

SAFETY EVALUATION NO. 88-03 CHANGE TITLE Revise Layout and Wiring of Gaseous Waste Panel DESCRIPTION OF CHANGE Revise Gaseous Waste Storage Tank panel graphic layout and wiring to correct an installation error on the surge tank discharge valve and the header outlet valve.

E.UMMARY OF SAFETY EVALUATION This system is QA Category II non-nuclear safety. Modification will correct the installation error and bring the Gaseous Waste System graphic layout and air cperated valve (AOV) wiring into agreement with the original design intent of the system.

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- BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 10 SAFETY EVALUATION NO. 88-07 l

CHANGE TITLE Temporary Heat Trace For Refueling Water Storage Tank (RWST)

Transmitter l

l DESCRIPTION OF CHANGE Add temporary heat trace and additional insulation for RWST level transmitters 2QSS*LT104A,B,C & D. This modification is to prevent freezing of the sensing lines.

SUMMARY

OF SAFETY EVALUATION The proposed modification is temporary and is in addition to the permanent heat trace and insulation. The temporary heat trace will be energized from a non-Quality Assurance (QA) Category I power supply and will not affect the QA Category I power supply to permanent heat trace. This modification will not affect operation of the level transmitter.

SAFETY EVALUATION NO. 88-08 CHANGE TITLE Temporary heat Trace For RWST Transmitters DESCRIPTION OF CHANGE Add temporary heat trace and additional insulation for RWST level transmitters 2QSS*LT100A&B, 2QSS*LT101A&B, and 2QSS-LT102A&B.

This modification is to prevent freezing of the sensing lines.

SUMMARY

OF SAFETY EVALUATION The proposed modification is temporary and is in addition to the permanent heat trace and insulation. The temporary heat trace will be energized from a non-QA Category I power supply and will not affect the QA Category I power supply to the permanent heat trace. This modification will not affect operation of the level transmitters.

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 11 SAFETY EVALUATION NO. 88-23 CHANGE TITLE Remove Snubber 2RCS-PSSP001A & B DESCRIPTION OF CHANGE Remove and delete snubber trapeze 2RCS-PSSP001A & B, located on the pressurizer surge line. A review of the calculations has determined that this snubber is not required to restrain the surge line during a seismic event.

SUMMARY

OF SAFETY EVALUATION This snubber was initially installed to provide restraint during a seismic event. Based on ASME Code Case N-411 analysis now indicates that it is not required. The technical justification is contained in calculations and documents that there is no unreviewed safety question. The Updated Final Safety Analysis Report (UFSAR) will be revised.

SAFETY EVALUATION NO. 88-25 CHANGE TITLE l Condensate Polishing Valves Trim Change DESCRIPTION OF CHANGE Condensate sludge pump is tripping on high discharge pressure.

The pump discharge valve is a reduced port design. This modification will replace valve trim with a high capacity trim to enable sludge to pass.

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SUMMARY

OF SAFETY EVALUATION Modification involves an internal trim change for two valves in a non-safety related, non-seismic system which has no safety function per UFSAR Section 10.4.6. This change does not constitute an unreviewed safety question.

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DESIGN CHANGE PACKAGE (DCP) NO. 880 CHANGE TITLE Isolation of Pressurizer Relief Water Seal Drains DESCRIPTION OF CHANGE Some of the normally-closed Pressurizer Relief Water Seal Drain Valves (2RCS*60, 61, 62) and the normally-closed Pressurizer Relief Water Seal Drain Header Isolation Valve (2RCS-63) are leaking. Therefore, the water seals upstream of the Pressurizer Safety Relief Valves (2RCS*RV551A, B, C) cannot be maintained.

To solve these problems, the Pressurizer Water Seal Drain Header (2RCS-001-153-4) and supports will be eliminated. The non-safety Drain Header Isolation Valve (2RCS-63), which ties the Drain Header (2RCS-001-153-4) into the Pressurizer Relief Piping (2RCS-012-112-4),

will also be eliminated. The branch connection (2RCS-001-154-4) on the Pressurizer Relief Piping (2RCS-012-112-4) will be capped. The Water Seal Drain Valves (2RCS*60, 61, 62) will be sealed-off by installing non-safety blind flange assemblies immediately downstream of these valves. The safety class 2 drain lines upstream of each of the Water Seal Drain Valves will be reduced in length to provide assurance that the stresses remain within design allowables.

SUMMARY

OF SAFETY EVALUATION The equipment and piping associated with this design change is both l safety and non-safety related. However, the design basis of the Pressurizer Relief Discharge System as described in Updated Final Safety Analysis Report (UFSAR) Section 5.4.11 is unchanged. Therefore, the possibility for an accident or malfunction of a different type than previously evaluated in the UFSAR has not been created.

Equipment and piping associated with this design change is both safety and non-safety related and is used only as a method for disposing of the Reactor Coolant which is drained from the Pressurizer Relief Valve (2RCS*RV551A, B, C) water seals. Based on this and a review of UFSAR Sections 5.1, 5.2, 5.4.10, 5.4.11, and 15.6.1, there will be no increase in the probability of an occurrence or the consequence of an accident or malfunction of equipment important to safety as previously evaluated in the UFSAR.

Technical Specification Section 3/4.4, " Reactor Coolant System", and the bases for this section do not discuss the equipment and piping being eliminated / modified by this design change. This design change will help to ensure that a water seal is maintained on the upstream ,

side of the Pressurizer Safety Relief Valves (2RCS*RV551A, B, C) which will aid in preventing steam cutting damage to these valves. Therefore, the margin of safety as defined in the basis for any Technical

. Specification is not reduced. Further, length reduction in safety class 2 drain piping will assure piping is within allowable design stresses.

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FACILITY CHANGES Page 13 l DESIGN CHANGE PACKAGE (DCP) NO. 889 CHANGE TITLE Turbine Supervisory Instruments Casing Expansion / Rotor Position Power Drawer Modification DESCRIPTION OF CHANGE

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i To prevent the possibility of a spurious turbine trip on loss of )

power to the casing expansion / rotor position power drawer by i

' installing a relay across the 120 VAC drawer supply. The relay will act to disable the trip circuitry on loss of power, thus eliminating the potential of' a power decay imbalance within the drawer causing a spurious trip.

SUMMARY

OF SAFETY EVALUATION The probability of occurrence or consequence of an accident j similar to those evaluated in. Updated Final Safety Analysis Report (UFSAR), Section 15.2.3, " Turbine Trip", will not be increased.

The reliability of the turbine trip system is unchanged and the probability of a spurious turbine trip is decreased by this modification. j The function of the turbine casing expansion / rotor position supervisory instruments is not being changed. No Technical Specifications apply to the turbine casing expansion / rotor position supervisory instrument.

DESIGN CHANGE PACKAGE (DCP) NO. 892 .

1 CHANGE TITLE Modifications to Equipment Supports and Pipe Supports DESCRIPTION OF CHANGE This design change combined ten (10) separate changes into a single package. The changes which were combined were all modifications to existing supports or the addition of new supports. The types of modifications included the addition of .

cross-bracing, moving the support, readjusting spring hangers, l changing clamps, etc. These changes were required to reduce vibration, to distribute weight, to correct an interference or to correct other concerns.

SUMMARY

OF SAFEfY EVALUATION These modifications will not alter the integrity or function of I the associated systems. Appropriate calculations were reviewed to i confirm the acceptability of each change. No UFSAR change is required as this level of detail is not included in the UFSAR.

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 l

EACILITY CHANGES Page 14 DESIGN CHANGE PACKAGF (DCP) NO. 894 CHANGE TITLE Pressure Indicators at Overhead Compressors Discharge DESCRIPTION OF CHANGE A permanent method of reading discharge pressure from Gaseous Waste System Overhead Gas Compressors is needed to provide capability for maintenance and testing one (1) compressor while the other compressor is still in service. Provision of a gage and root valve for isolation at the discharge line for each compressor will provide this method and will reduce potential radiation to personnel by making available readily accessible instrumentation for use during maintenance and testing.

SUMMARY

OF SAFETY EVALUATION Piping and components, including instrumentation for the Gaseous Waste System, associated with this design change are non-safety-related. This change will enhance maintainability and operations for overhead gas compressors through provision of discharge line instrumentation. Based on this and review of Updated Final Safety Analysis Report (UFSAR) Section 11.3 and Figure 11.3-1, there is no increase in the probability of an occurrence or the consequence of an accident or malfunction of equipment important to safety as previously evaluated in the UFSAR.

The piping components and instrumentation associated with this design change are non-safety-related and the design basis for the Gaseous Waste System, as described in UFSAR Section 11.3 is unchanged. No new factors or possibilities are initiated by this design change. Therefore, the possibility for an accident or malfunction of a different type than previously evaluated in the UFSAR has not been created.

Technical Specification Section 3/4 11.2, " Gaseous Effluents" and the basis for this section do not discuss pressure instrumentation. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.

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EACILITY CHANGES Page 15

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, DESIGN CHANGE PACKAGE (DCP) NO. 944 CHANGE TITLE i

Modification of Solid Waste System (WSS) Pipe Supports DESCRIPTION OF CHANGE Pipe supports were modified and new supports were added due to excessive piping vibrations experienced during the operation of pumps 2WSS-P23 and 2WSS-P25.

SUMMARY

OF SAFETY EVALUATION -l The solid waste system and the associated pipe supports are Quality Assurance (QA) Category II, non-nuclear safety. The WSS System function remains . unchanged by this modification. No Updated Final Safety. Analysis Report Section 15 accident analysis is impacted by this change, therefore there is no unreviewed safety question.

SAFETY EVALUATION NO. 975.

CHANGE TITLE Missile Shield Rings for-Fans 2HVZ*FN262A&B (Emergency Switchgear Exhaust Fans)

DESCRIPTION OF CHANGE The subject Design Concept is being canceled based on a determination that the missile shields were not required for these fans. This evaluation confirms that elimination of the shields does not create an unreviewed safety question.

Pumps and fans located in areas containing safety-related components have been evaluated for missiles associated with overspeed failures. For axial fans, the typical failure model is the loss of a vane. For fans 2HVZ*FN262A&B, this evaluation concluded that a. failed vane could be ejected through the inlet air flex connection, which is a lighter gauge than the fan housing. The fan housing can contain an internal missile. To protect nearby safety-related electrical components, it was determined that a missile shield was required. The installation of the missile shield was hampered by interference and ultimately delayed. This outstanding installation has been tracked by E&DCR ACN D-0178, SMR 1346, and most recently by DCP 975.

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 16 DCP 975, continued The calculation requiring the missile shield was reviewed as part of the processing of DCP 975. It was noticed that the calculation had conservatism such as a large failure cone and a conservative failure point. (The failure cone predicts the path of a vane missile.) After discussions with the fan vendor, Joy Manufacturing, regarding failure modes, it was determined that the failure mode of this type of fan blade is predictable. This allows using a less conservative (smaller) failure cone.

This smaller failure cone resulted in a smaller impact area for the vane inside the fan housing. This impact area does not now include the inlet air flex connection, thus the blade will not be ejected, and the missile shields are not required.

SAFETY EVALUATION

SUMMARY

The determination to cancel the proposed design change will not involve an unreviewed safety question. It has been established by calculation that a failed vane will not be ejected from the fan housing; therefore, there is no need to provide protection from this postulated internal missile.

The determination to cancel the proposed design change will not require change to the technical specifications. No Technical Specifications apply to these fans.

The determination to cancel the proposed change will require changes to the Updated Final Safety Analysis Report (UFSAR).

UFSAR Table 3.5-12 and Section 3.5.1.1 must be revised to delete reference to these fans having a missile shield. The determination to cancel the proposed change will not involve an Unreviewed Environmental Question or a change in the Environmental Protection Plan because there is no change to effluent releases caused by this change.

The probability of an occurrence of an accident previously evaluated in the safety analysis report will not be increased because there has been no change to the fan or the ventilation system to affect the probability of occurrence. The anticipated frequency of occurrence as defined in UFSAR Section 15.0.1 remains unchanged.

The consequence of an accident previously evaluated in the safety analysis report will not be increased because these fans are located in the Main Steam Cable Vault fan room elevation 780  !

feet. This area contains only ventilation fans and supporting electrical cable, conduit, and associated components. Failure of a fan blade has been shown by calculation not to affect any equipment in this area.

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• BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 17 DCP 975, continued The probability of a malfunction of equipment important to safety as previously evaluated in the safety analysis report will not be increased because the Section 15 accident analysis anticipated frequency of occurrence remains unchanged.

The consequence of a malfunction of equipment important to safety as previously evaluated in the safety analysis report will not be l increased because failure of a fan blade will have no effect on equipment located in the fan room.

l There are no BVPS-2 Section 15 design basis accidents which are potentially impacted by the proposed design change. Failure of axial fans is described in UFSAR Section 3.5.1, but this is not considered a design basis accident.

There are no BVPS-2 safety systems which will be affected by the proposed design change. Safety-related components located in the fan room are limited to ventilation fans and associated electrical support system. The revised calculation indicates that a failed vane will not escape the fan housing; therefore, there is no effect on safety systems.

The possibility for an accident of a different type than previously evaluated in the safety analysis report will not be created because there has been no change to the safety-related equipment. Failure of a vane (not a design basis accident) has been evaluated. No other accident is affected by this change.

The possibility for a malfunction of equipment important to safety of a different type than previously evaluated in the safety analysis report will not be created because there has been no change to the fan or the ventilation system or to any other system in the fan room which could introduce a different type of malfunction.

Failure modes of the proposed design change which were reviewed included failure of a vane which then travels in a trajectory limited to a 25* cone from the point of failure and impacting the fan housing.

The margin of safety as defined in the basis for any Technical Specification will not be reduced because no Technical Specifications apply to the Emergency Switchgear Exhaust Fans.

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1 FACILITY CHANGES Page 18 DESIGN CHANGE PACKAGE (DCP) NO. 982 CHANGE TITLE Addition of Nuclear Construction Department (NCD) Building Accountability Card Readers DESCRIPTION OF CHANGE i l

At the present time, Primary Assembly Areas of the NCD Building require personnel accountability card readers. Three card readers: No. 1 (located on the third floor) and Nos. 2 and 3 (located on the second floor) will be connected to the security computer system, located in the Primary Access Facility. This will provide an immediate account of personnel during an emergency or drill. This design change will add these three card readers, cables, conduits, connection boxes and other miscellaneous components required to interface the new card readers into the existing Security Computer System.

SUMMARY

OF SAFETY EVALUATION The proposed modification does not increase the possibility of an occurrence or the consequence of an accident or malfunction of equipment important to safety referenced in the Updated Finhl Safety Analysis Report (UFSAR) Section 15. The equipment affected by this DCP is not safety related. With the proposed modifications, the plant security system will stay the same. It will improve personnel accountability during an accident or drill.

This modification to install three card readers, cables, conduits, connection boxes and other miscellaneous items in the primary assembly area of the NCD Building will not create an accident or malfunction of different type than previously evaluated in the Updated Final Safety Analysis Report. The equipment affected by this proposed modification is not safety related. It does not impact on the plant security system. The failure of these card readers, etc., will not impact safe plant operation and shutdown, therefore, they will not cause an accident or malfunction of a different type than previously evaluated in the UFSAR.

BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page.19

. DESIGN CHANGE PACKAGE (DCP) NO. 985 CHANGE TITLE Gaseous Waste Decay Tank Sampling DESCRIPTION OF CHANGE The . Gaseous Waste Storage (Decay) Tank Piping System presently requires that potentially radioactive gas be collected by the sweep gas system and discharged to the environment via BVPS Unit

1. 1 cooling tower during the collection of grab samples. This modification provides an addition of high pressure (approximately 60 psig) grab sample capability (valves, flex hoses, and quick disconnects) downstream of the recirculation blower (2GWS-P21) and upstream of the present radiation monitor (2GWS-RQIl04).

Therefore, this modification will eliminate the possible release of potentially radioactive gas during grab sample collections.

SUMMARY

OF SAFETY EVALUATION Piping and components for the Gaseous Waste System, including Gaseous Waste Storage Tank and piping and components associated with this design change are non-safety-related. This design

-change will enhance sampling capability. Based on this and a review of Updated Final Safety Analysis Report (UFSAR) Sections 11.3.1, 11.3.2.1, 11.3.2.3, and Figure 11.3-3, there will be no increase in the probability of an occurrence or the consequence of an accident or malfunction of equipment important to safety as previously evaluated in the UFSAR.

The sample piping and components, associated with this design change, are non-safety-related and the design basis for the Gaseous Waste System, as described in UFSAR Section 11.3.1 is unchanged. No new factors or possibilities are initiated by this design change. Therefore, the possibility for an accident or malfunction of a different type than previously evaluated in the UFSAR has not been created.

Technical Specification Section 3/4.11.2, " Gaseous Effluents" and the. basis for this section do not discuss local sampling capabilities or the piping valves, and other associated equipment. This design change will help to ensure that potential radioactive gas release is reduced and present effluent release controls and criteria are unaffected. Therefore, the margin of safety as defined in the basis for any Technical Specification is not reduced.

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BVPS-2 Annual Report.of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 20 DESIGN CHANGE PACKAGE (DCP) NO. 986_

CHANGE TITLE Replacement Cooling Coils for Air Conditioning Units 2HVR-ACU220 and 221 DESCRIPTION OF CHANGE During fire protection carbon dioxide system testing in the Cable Vault and Rod Control Area of Unit 2, the cooling coils for.

2HVR-ACU220 and 2HVR-ACU221 were damaged beyond repair due to freezing of the chilled water in the coils. This modification will address this situation as follows:

Replace damaged cooling coils with new cooling coils and rework chilled water system connections as required for installation; and install a temperature switch on 2HVR-ACU220 to shut down unit-during CO 2 testing. (Unit 2HVR-ACU221 is already interlocked with the CO 2 discharge circuit, so no modification is necessary for it.)

SUMMARY

OF SAFETY EVALUATION Air conditioning units 2HVR-ACU220 and 2fiVR-ACU221 supplement the primary cable vault air conditioning units for normal operation and are not safety-related units. Their failure will not compromise the ability of the primary units to perform their safety functions as described in Section 9.4.12 of the BVPS-2 Updated Final Safety Analysis Report, nor will their failure jecpardize any other safety-related equipment.

Installation of the temperature switch on 2HVR-ACU220 will not affect any safety-related equipment, but will improve the reliability of 2HVR-ACU220 by preventing future damage to the unit during fire protection system carbon dioxide testing. Replacement of the cooling coils is a direct replacement of existing components and does not create any new accident situations.

.Therefore, no neu accidents are created.

• BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 EA_CILITY CHANGES Page 21 DESIGN CHANGE PACKAGE (DCP) NO. 1017 CHANGE TITLE Non-Regenerative Heat Exchanger Cubicle #3 Entering Air Velocity DESCRIPTION OF CHANGE In order to control and confine airborne contamination, entrance air velocity into an area of potential high airborne activity must be greater than 50 ft/ min to meet the ALARA program requirements.

Actual air entrance velocity in the non-regenerative heat exchanger cubicle #3 of the Unit 2 Auxiliary Building is not sufficient (i.e., less than 50 ft/ min) to confine the airborne contamination resulting from operation of a pressure relief valve.

Partially blocking the doorway opening would result in an increased air entrance velocity. The cubicle entry will be reduced by providing an 18 gage sheet metal cover to the existing radiation : barrier. cage, which will decrease the open area of the doorway to 25% of the present area. This will result in an air velocity of 150 to 200 ft/ min, which will confine the contamination in the cubicle.

SUMMARY

OF SAFETY EVALUATION The failure of the sheet metal would be inconsequential; it will have no effect on the probability of occurrence, or the consequences of, any Updated Final Safety Analysis Report accidents, including Section 15.6.2, " Failure of Small- Lines Carrying Primary Coolant Outside Containment."

The equipment affected by this DCP is not safety related. It is located to preclude interactions, and therefore, the probability of any malfunction of safety related equipment that could be indirectly affected will not be increased.

The equipment affected by this DCP is not safety related. There should be no effect on the consequences of a malfunction of safety related equipment because the equipment affected by this DCP is not relied on to mitigate the consequences of any equipment failures.

Because this DCP is so minor, and the failure of the sheet metal would be inconsequential, it neither changes the failure modes of the equipment involved, nor introduces any new potential hazard which could cause an accident of a different type.

a 4 BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 22 DESIGN CHANGE PACKAGE (DCP) NO. 1022 CHANGE TITLE Installation of Five-Diameter Bend in Cement Station Transfer Line DESCRIPTION OF CHANGE The 2" cement transfer line from the cement silo to the day tank clogs at a 90* bend-tee fitting. This modification replaces the tee with a 5" diameter bend and a lateral upstream for a clean out port.

SUMMARY

OF SAFETY EVALUATION The cement transfer line is Quality Assurance (QA) Category III, non-nuclear safety. This modification only substitutes a lateral and a 5" diameter bend for the existing tee fitting. All new fittings will be of the same material. This modification does not change the intent of the system design nor the systems protective aspects.

BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 23 DESIGN CHANGE PACKAGE (DCP) NO. 1023 CHANGE TITLE Relocate Fire Rose Rack NO. HR-226 and Provide Support DESCRIPTION OF CHANGE Fire hose rack No. 2FPW-HR-226 was relocated 16 feet west of its design location per MWR-885086 to provide better access. This DCP will move the hose rack an additional several feet.

Since Standard NFPA 14 requires hose outlets to be within easy reach of a person standing on the floor and in no case should it be over six feet from the floor, the hose rack must be lowered.

Additional supports are required due to the new piping configuration.

SUMMARY

OF SAFETY EVALUATION Because this DCP is so minor, and all it does is move the hose i rack location about 20 feet and provide supports, it will have no i effect on the probability of occurrence of any Updated Final Safety Analysis Report accidents, inclu61ng fire protection as considered in Sections 9.5.1 and Appendix 9.5A.

The equipment affected by this DCP is not safety related. It is located to preclude interactions, and therefore, the probability l of any malfunction of safety related equipment that could be  !

indirectly affected will not be increased.

t There should be no effect on the consequences of a malfunction of I safety related equipment because the equipment affected by this  !

DCP is not relied on to mitigate the consequences of any safety-related equipment failures.

This equipment is located in the Turbine Building, safety-related equipment will not be affected; therefore, the possibility of a .

malfunction of a different type is not created. .

The integrity of the fire protection system will be maintained, it l neither changes the failure modes of the equipment involved, nor  !

introduces any new potential hazard which could cause an accident of a different type. y I

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 24 DESIGN CHANGE PACKAGE (DCP) NO. 1092 CHANGE TITLE Installation of Additional Tool Storage Brackets in Unit 2 Spent Fuel Pool DESCRIPTION OF CHANGE The purpose of this modification is to install three new tool storage brackets for the Rod Cluster Control (RCC) Thimble Plug Handling Tool, the Portable Rod Cluster Control Assembly (RCCA)

Tool, and the Irradiated Specimen Basket Handling Tool, and to modify the existing Burnable Poison Rod Assembly (BPRA) Handling Tool Bracket to eliminate interference between the BPRA Tool and the Spent Fuel Storage Racks in the Spent Fuel Pool. The reason for this modification is to permit Unit 2 to follow the current industry practice of removing fuel from the reactor vessel and moving it to the Spent Fuel Pool area during refueling outages.

SUMMARY

OF SAFETY EVALUATION The weight of the refueling tools is less than the limit imposed by the Technical Specification. Due to the proposed location of the new brackets, if a bracket should fail and cause the tool that it is holding to fall into the pool the number of fuel rods that could be fractured is substantially less than the number assumed by BVPS-2 Updated Final Safety Analysis Report (UFSAR) Section 15.7.4. Therefore, this scenario is not the bounding case and this modification will not increase the probability of occurrence or consequence of an accident or malfunction previous evaluated.

The new brackets will be located so that they do not interfere with operation of the Fuel Handling System as described in Section 9.1 of the BVPS-2 UFSAR. They will also be seismically installed to prevent their failure during a seismic event. Therefore, no new accident scenarios are created.

The tooling to be stored in the new tool brackets weigh less than 3,000 pounds each, thus does not reduce the margin of safety of Technical Specification 3/4.9.7.

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BVPS-2 Annual Raport of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 25 DESIGN CHANGE PACKAGE (DCP) NO. 1099 CHANGE TITLE Installation of Cooling Water Isolation Valve DESCRIPTION OF CHANGE At the present time, cooling water cannot be isolated on the outlet of the primary sample coolers for maintenance purposes.

This DCP will install an isolation valve on the cooling water outlet of the primary sample conditioning rack. After this modification, the coolers can be maintained to correct improper cooling water connections during plant operation.

SUMMARY

OF SAFETY EVALUATION The proposed modification does not increase the possibility of an occurrence, or the consequence of, an accident or malfunction of equipment important to safety referenced in the Updated Final Safety Analysis Report in Section 15. The affected portion of the component cooling water system is non-safety-related. This modification can correct improper cooling water connections, and the coolers can be maintained during plant operation.

This modification to install a cooling water isolation valve in the cooling water discharge line of the primary sample conditioning rack will not create an accident or malfunction of different type than previously evaluated in the Updated Final Safety Analysis Report. The affected portion of the component cooling water system is non-safety-related. The failure of this isolation valve has no effect on function of the component cooling water system to reduce the pressure and temperature of the steam generator samples.

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• BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 26

. DESIGN CHANGE PACKAGE (DCP) NO. 1113 pHANGE TITLE New Fuel Elevator Carriage Lead-In DESCRIPTION OF CHANGE The new fuel elevator carriage was too narrow to allow fuel handling tool entry into the carriage to reach an inserted fuel assembly. A stainless steel spacer was inserted at the bottom of the carriage so _that an inserted fuel assembly would be raised approximately one-quarter inch above the top of the carriage. The i installation of this spacer provided fuel handling tool access to an inserted fuel assembly, but sacrificed protection and alignment of the fuel handling tools with the fuel assembly.

This modification (DCP 1113) proposes to leave the spacer installed, and attach a new six-inch lead-in collar to the top of the carriage. The collar opening will be large enough to allow fuel handling tool access to an inserted fuel assembly. This will provide the protection and alignment capability requested to enhance fuel handling operations.

SUMMARY

OF SAFETY EVALUATION The probability, of the consequences of, any accident previously evaluated in the Updated Final Safety Analysis Report (UFSAR) will not be increased. This modification serves only to enhance fuel handling operations by providing protection to a fuel assembly that is inserted in the fuel elevator and by providing a means of aligning the fuel handling tools with an inserted assembly. The accident analyses described in UFSAR Sections 15.7.4 and 15.7.5 will not be affected by this modification.

The probability, or consequences of, a malfunction of equipment important to safety will not be increased. Although the new fuel elevator is not safety-related, it is designated as Seismic Category II and is designed so that its failure would not reduce the functioning of any nearby safety-related components (i.e.,

spent fuel storage racks). By designing the carriage collar to these requirements, the functioning of the fuel handling system will actually be enhanced.

The possibility for an accident or malfunction of a different type than previously evaluated in the UFSAR will not be created. No new failure modes or potential hazards will be created by the implementation of this modification.

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 27 DESIGN CHANGE PACKAGE (DCP) NO. 1242 CHANGE TITLE PORV Wiring Modifications DESCRIPTION OF CHANGE The wiring for the pressurizer power operated relief valves (PORVs) is being exposed to temperatures above its qualified rating. This results in a reduced qualified life of the installed cables and could possibly cause cable failure which would render the valves inoperable.

This modification proposes to restore the integrity and qualification of the installation by replacing the vulnerable sections of cable with cable of higher temperature rating. The conduit assemblies will be environmentally sealed; materials with an EYS conduit fitting will be sealed and inspected by BISCO personnel at BISCO's facility. The existing non high temperature environment qualified EPDM gasket at the limit switch housing and its associated bolts will be replaced with a Nuclear Grade TG-264 Union Carbide Grafoil gasket and high strength bolts. Only minor hardware changes are required and no support modifications will be made.

SUMMARY

OF SAFETY EVALUATION The probability of an occurrence of an accident previously evaluated in the safety analysis report will not be increased.

This n. modification will not affect the function of the PORVs and the qualification of the now installation will be assured by a new environmental qualification review. Therefore, the probability of an inadvertent opening of a pressurizer relief valve, as discussed in Updated Final Safety Analysis Report Section 15.6.1, will not be increased.

The probability of a malfunction of equipment important to safety as previously evaluated in the safety analysis report will not be increased. The function of pressurizer pressure relief system will remain unchanged; therefore, no adverse affects on any safety-related equipment will be created.

The consequence of a malfunction of equipment important to safety as previously evaluated in the safety analysis report will not be increased because no new failure modes or potential hazards will be created by the implementation of this modification.

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- BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 FACILITY CHANGES Page 28 I DCP 1242, continued The possibility for an accident of a different type than previously evaluated in the safety analysis report will not be created. This modification will serve only to provide the PORVs with wiring that is qualified to a higher temperature than the present wiring. The new gasket and bolts installed on the limit switch housing will further assure the PORV's operability under all environment conditions. The function of the PORVs will remain unchanged and no other systems will be affected.

Failure modes of the proposed design change which were reviewed included the failure of the new cables. This would render the affected PORV(s) inoperable, which would revert the PORV(s) to a similar condition to what presently exists. This situation is already addressed in the Technical Specifications (TS). Technical Specification 3.4.11, action statements c and d, explain the requirements to continue power operation with 1, 2 or 3 PORV(s) inoperable due to causes other than excessive seat leakage.

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 OPERATING PROCEDURES Page 29 TEMPORARY OPERATING PROCEDURE (TOP) 2-87-51 CHANGE TITLE Making Up To A Safety Injection Accumulator Using A Temporary Air Operated Pump DESCRIPTION OF CHANGE The TOP was prepared to provide instructions on adding borated l water to the safety injection accumulators in place of the permanent installed pump to ensure the Technical Specification on water level is satisfied.

SUMMARY

OF. SAFETY EVALUATION The pump is required to ensure that the Technical Specification low level limit on the accumulators is not violated in the event of inoperability of the permanent pump. The temporary pump is limited in its discharge pressure; therefore, overpressurization from the pump is minimized. To ensure that the possibility for an accident or malfunction is not increased, the pump is isolated when not in use and manned when in use. The margin of safety is maintained by the availability of a means of water addition to the accumulators. The permanent pump is non-safety related and Updated Final Safety Analysis Report Section 6.3.2.2 does not specify that water addition is limited to the permanent plant pump. No unreviewed safety question exists.

TEMPORARY OPERATING PROCEDURE (TOP) 2-88-002 CHANGE TITLE Venting Of The Idle Charging Pump DESCRIPTION OF CHANGE The TOP was prepared to provide for data gathering and venting of the idle charging pump. The procedure installed vent and sample rigs on the suction and discharge of the pump.

SUMMARY

OF SAFETY EVALUATION Venting of pumps is a normal operating practice and does not affect the operability of the charging pumps because the venting is only done on the idle pumps and no running pump configuration changes are made. No unreviewed safety question exists.

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, a BVPS-2 Annual Report of Facility Changes, l

Tests and Experiments for 1988 OPERATING PROCEDURES Page 30 OPERATIONS SURVEILLANCE TEST (OST) 2.1.7 CHANGE TITLE Manual Reactor Trip Test Issue 1 Rev 3.

DESCRIPTION OF CHANGE The procedure was revised to eliminate taking voltage readings during this test, thereby minimizing the chance of damaging the under voltage (UV) driver card in Solid State Protection System (SSPS).

SUMMARY

OF SAFETY EVALUATION Revising the procedure to use the test panel, eliminated the possibility of damaging the UV driver card in SSPS which could go undetected until the next OST performance. This change provides additional protection to the reactor trip circuitry and does not create or increase the possibility, probability, or consequences of an accident or malfunction. No unreviewed safety question exists.

TEMPORARY OPERATING PROCEDURE (TOP) NO. 2-87-46 CHANGE TITLE Main Generator #2 Neutral Grounding Network Data Gathering DESCRIPTION OF CHANGE This procedure was developed to allow monitoring and. gathering of engineering data (voltage and current) on the main generator neutral grounding network during Unit 2 turbine / generator operation.

SUMMARY

OF SAFETY EVALUATION The system was evaluated and the worst event that could occur would be a generator trip caused by joining the data connections. The system is analyzed for a generator trip and designed to respond to this event; therefore, performance of the TOP does not increase the probability, possibility, or consequences of an accident or malfunction to safety-related equipment. The generator is not safety related. No unreviewed safety question exists.

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- BVPS-2 Annual Report of Facility Changes, )

Tests and Experiments for 1988 i OPERATING PROCEDURES Page 31 TEMPORARY OPERATING PROCEDURE (TOP) 2-88-04 CHANGE TITLE Spent. Resin Hold Tank Transfer To High Integrity Container (HIC)

DESCRIPTION OF CHANGE This procedure was developed to transfer the contents of the spent resin holding tank [2WSS-TK22] to a high integrity container via the decant tank (2WSS-TK23]. This procedure is only applicable to the transfer of non-radioactively contaminated resins.

SUMMARY

OF SAFETY EVALUATION The system is being operated in a manner consistent with the safety evaluation of Design Change Package (DCP) No. 941 which authorized the system changes. There are no radiological concerns because the procedure is only allowed to be performed using non-radioactively contaminated resins and is within the accident analysis of the Updated Final Safety Analysis Report (UFSAR) which assumes that the resin is contaminated. Therefore, no unreviewed safety question exists.

TEMPORARY OPERATING PROCEDURE (TOP) 2-88-05 CHANGE TITLE Flushing Any Group II Ion ' Exchanger To High Integrity Container (HIC).

DESCRIPTION OF CHANGE

, This procedure was developed to remove resin from any Group II ion I

exchanger and convey it in a slurry to a high integrity container.

l This procedure is only applicable to the transfer of non-l radioactively contaminated resins.

SUMMARY

OF SAFETY EVALUATION The system is being operated in a manner consistent with the safety evaluation of DCP-941 and DCP-962 which authorized the system changes. There are no radiological concerns because the procedure is only allowed to be performed using non-radioactively contaminated resins and is within the accident analysis of the Updated Final Safety Analysis Report which assumes that the resin is' contaminated. Therefore, no unreviewed safety question exists.

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- BVPS--2 Annual Report of Facility Changes, Tests and Experiments for 1988 OPERATING PROCEDURES Page 32 OPERATIONS SURVEILLANCE TEST (OST) NO. 2.2.3 CHANGE TITLE Nuclear Source Range Channel Functional Test, Rev. 4 DESCRIPTION OF CHANGE i This procedure was revised to require performance of the surveillance in all modes when below P-6 instead of only when the reactor trip breakers are closed and the control rod drive system is capable of rod withdrawal.

SUMMARY

OF SAFETY EVALUATION The procedure revision corrected an inconsistency between the Technical Specifications, the Licensing basis and the Generic Technical Specification. This ensures that the source range detectors are operable to assist the operator in identifying a reactivity addition while shut down even if the reactor trip I

breakers are open. This will reduce the possibility of an accident or malfunction because the event would be detected sooner. The Technical Specification was revised in Change Request 2A-14 (Amendment Number 8, effective 11/7/88). No unreviewed safety question exists.

CHANGE TITLE Temporary Modification to Install a Drain Hose From the Sample Panel Drain To the Recirculation Tank 2CND-TK21 in the Condensate Polishing System.

l DESCRIPTION OF CHANGE A drain hose was connected from the drain on the condensate l polishing sample panel to the recirculation tank in the condensate polishing building. This will allow for the recovery of clean water instead of processing it as liquid waste.

SUMMARY

OF SAFETY EVALUATION The system is not safety related and provides no safety function.

The Updated Final Safety Analysis Report does not address any accident in the condensate polishing system nor does it restrict or stipulate the operation of this portion of the system. The system j is not covered by Technical Specifications. No unreviewed safety question exists.

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 OPERATING PROCEDURES Page 33 I CHANGE TITLE Temporary Modification to Install a Drain Hose From Precoat Header Relief Valves [2CND-RV103] and [2CND-RV107] in the Condensate Polishing System to Recirculation Tank [2CND-TK21].

DESCRIPTION OF CHANGE Isolation valves to the precoat header leak by pressurizing the precoat header and lifting the relief valves. The relief valves discharge to the drain system and have to be processed as liquid waste. This modification minimizes the waste to be processed and directs the relief valve discharge to the recirculation tank where it can be reused. This system is not radioactively contaminated.

SUMMARY

OF SAFETY EVALUATION The system is not safety related and provides no safety function.

The Updated Final Safety Analysis Report (UFSAR) does not address any accident in the condensate polishing system nor does it restrict or specify the operation of this portion of the system.

The system is not covered by Technical Specifications. No unreviewed safety question exists.

CHANGE TITLE BV-2 IST Plan For Pumps and Valves, Rev. 2.

DESCRIPTION OF CHANGE Removed spent fuel pool cooling pumps from IST plan.

SUMMARY

OF SAFETY EVALUATION UFSAR section 9.1.3.4 stated that the fuel pool cooling pumps will be tested to ASME XI. There are no postulated accidents associated with the failure of these pumps and the system is designed to provide for temporary connections and water supplies in the event of a failure. The fuel pool level is important to safety and the design of the pool insures it will be maintained. Since these pumps are not required to perform a specific function in a reactor shutdown or to mitigate the consequences of an accident, they are not required to be tested in accordance with ASME XI. No unreviewed safety question exists.

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BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 OPERATING PROCEDURES Page 34 TEMPORARY OPERATING PROCEDURE (TOP) 2-88-17 CHANGE TITLE Makeup To Safety Injection Accumulator [2 SIS *TK21A, B, C] Using A Temporary Pump DESCRIPTION OF CHANGE This procedure was prepared to provide instructions on adding borated water to the safety injection accumulators using a temporary hydro test pump.

SUMMARY

OF SAFETY EVALUATION The probability or consequences of an accident or malfunction of equipment evaluated in the Updated Final Safety Analysis Report are not increased because the temporary pump, like the permanent hydro test pump, will be isolated during periods of non-use and will be manned when in use. The piping is not nuclear safety related and is already covered in the small break Loss of Coolant Accident outside containment analysis. The pumps relief valve will be set at a similar setting to that of the hydro test pump. The equipment is not covered by Technical Specifications, but the level required in the accumulators is covered by Technical Specifications; therefore, having an available temporary pump will ensure that the 1 Technical Specification is not violated. No unreviewed safety I

question exists.

OPERATING MANUAL CHANGE NOTICE 2-88-249 and 250 CHANGE TITLE Pressurizer Power Operated Relief Valve (PORV) and Relief Valve (RV) Telltale Leakoff Temperature Alarm Setpoint.

DESCRIPTION OF CHANGE This OMCN revised the pressurizer PORV/RV telltale leakoff l temperature alarm setpoint.

SUMMARY

OF SAFETY EVALUATION l The system is designed to provide adequate controls for maintenance and changes in the pressurizer relief tank pressure and level. The alarm serves as a warning to the operator of a potential leaky PORV or relief valve. The new setpoint is still indicative of a potential leak and within the design of the system. The change does not affect any accident analysis nor does it increase the probability of an accident. Therefore, no unreviewed safety question exists.

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BVPS-2 Annual Report or Facility Changes, I

Tests and Experiments for 1988 OPERATING PROCEDURES Page 35 CHANGE TITLE Temporary Modification to Provide Temporary Lights In the Control Room Entrance Vestibule DESCRIPTION OF CHANGE A temporary jumper was installed from the AC lighting panel to the control room vestibule temporary light.

SUMMARY

OF SAFETY EVALUATION The . installation of this temporary light is by current engineering standards and the failure of this light has no seismic or safety concern. The light is located within the Control Room pressure boundary but not near any safety-related equipment that could be damaged by its failure. The cable penetration is resealed and pressure tested SAT, thereby maintaining the control room pressure boundary. The installation does not increase the possibility or probability of a malfunction or accident. No unreviewed safety question exists.

CHANGE TITLE Temporary Modification to Add a Temporary Valve To Blow Down The Air Receiver DESCRIPTION OF CHANGE A new valve was added to the drain line on the instrument air receiver. The permanent plant drain valve leaks through and the air receiver depressurizes.

SUMMARY

OF SAFETY EVALUATION This modification does not increase the chances of a malfunction or failure of the system. It provides a method to blow down any water accumulation in the receiver thereby ensuring that the air system is maintained available for any evolution. This equipment is not safety related and no unreviewed safety questions exists.

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• BVPS-2 Annual Report of Facility Changes,.

Tests and Experiments for 1988 OPERATING PROCEDURES Page 36 CHANGE TITLE

, Temporary Modification to Add a Pressure Gauge DESCRIPTION OF CHANGE A pressure gauge is added to the seal water system (SWS) to provide the operator local pressure indication during auto transfer recovery.

SUMMARY

OF SAFETY EVALUATION The system is still being operated in a manner consistent with the design and does not create anything not previously' analyzed. The gauge provides indication only and has no safety function. No unreviewed safety question exists.

OPERATING MANUAL CHANGE NOTICE (OMCN)

CHANGE TITLE Allowable Steam Generator Level Channel Deviation DESCRIPTION OF CHANGE This OMCN revised the surveillance verification for steam generator levels ,to allow a 17% level deviation per channel. This change will take into account the 13% known bias of the transmitter and allow for 4% transmitter error.

SUMMARY

OF SAFETY EVALUATION The 17% level deviation allowance more accurately reflects plant conditions and permits the surveillance to be properly met. This change does not affFct any auton.A tic safety functions or any previously evaluated accident analysis, and setpoints are unchanged. The new tolerances are indicative of proper calibration and functioning of the transmitters thereby insuring that they will function as designed. No unreviewed safety question exists.

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BVPS-2 Annual-Report of Facility Changes, Tests and Experiments for 1988 L OPERATING PROCEDURES Page 37 l

l CHANGE TITLE Temporary Modification To The Containment Instrument Air Dryer I Drhin Trap and Dew Point Meter DESCRIPTION OF CHANGE The modification will provide a drain path from the dew point meter to the air dryer drain trap, preventing the meter from flooding out; and route dew point sample back to the suction of the air compressors. This modification will reduce the need to bleed containment atmosphere into the compressor room to purge the dew point meter, thus helping to maintain containment pressure. The routing of the drain will minimize the possibility of moisture carryover.

SUMMARY

OF SAFETY EVALUATION The air dryer and dew point meter are not safety related. No modifications are being made to permanent plant equipment such that their operation or safety function would change. the only feasible failure would be for the temporary line to break resulting in a very slow change in containment pressure which is addressed in the Updated Final Safety Analysis Report (USFAR). No Technical Specifications are involved. No unreviewed safety question exists.-

CHANGE TITLE Temporary Modification To The Nitrogen Fill On The Turbine Electro-Hydraulic Control System (EHC) High Pressure Accumulators DESCRIPTION OF CHANGE This modification changes the charging location for the turbine EHC high pressure accumulators from the top of the accumulator pressure gauge to the gauge sensing line.

SUMMARY

OF SAFETY EVALUATION The system is not safety related and not addressed in UFSAR safety analysis. Moving the fill point will reduce the possibility of a malfunction of equipment because it will provide an equivalent Nitrogen charging connection and eliminate the possibility of accidentally breaking tubing conponents on the high pressure EHC accumulators. This system is not covered by Technical Specifications. No unreviewed safety question exists.

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• BVPS-2 Annual Report of Facility Changes, J Tests and Experiments for 1988 OPERATING PROCEDURES Page 38 )

TEMPORARY OPERATING PROCEDURE (TOP) 2-88-20

j. CHANGE TITLE Transfer Of Steam Generator Slowdown Evaporator [2SGC-EV21A]

To The Evaporator Bottoms Hold Tank [2SGC-TK25] or Liquid Waste Drain Tank [2LWS-TK21A or B].

DESCRIPTION OF CHANGE This TOP was developed to transfer evaporator contents by bypassing the system blockage in the normal transfer path.

SUMMARY

OF SAFETY EVALUATION The TOP provides controls for a temporary bypass around system blockage. Any leakage of the hose will be collected via the plant L

designed floor drains. No offsite release path is utilized in this procedure. The overall intent of the transfer is the same as designed, the only difference is that a temporary hose is used. The probability or consequences of an accident is unchanged. The probability or consequences of a malfunction is reduced because we are providing a method to bypass blockage in the system to provide transfer capabilities. The equipment is not covered by Technical Specifications. No unreviewed safety question exists.

IEMPORARY OPERATING PROCEDURE (TOP) 2-88-22 CHANGE TITLE Recirculation Spray System (RSS) Heat Exchanger -

Service Water System (SWS) Flush DESCRIPTION OF CHANGE This procedure was developed to troubleshoot and flush the seat of valve [2SWS*MOV103B], which leaks by when closed. The procedure flushes under the valve seat to remove any debris which may have been trapped there.

SUMMARY

OF SAFETY EVALUATION The probability or consequences of an accident is unchanged. One train will remain operable with an operator stationed locally to manually restore the second train. The probability or consequences of a malfunction are unchanged because the valves will be operated as designed. One train will always be available for safe shutdown; therefore, the possibility of an accident or malfunction of a different type is not changed. The service water and recirculation spray system Technical Specification basis are consistent with the assumptions used in the accident analysis, that is, one train is operable. No unreviewed safety question exists.

i h . __ _ _ _ - _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ , . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________]

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• BVPS-2 Annual Report of Facility Changes, Tests and Experiments for 1988 RAD CON PROCEDURES Page 39 TEMPORARY RADCON PROCEDURE (TRP) NO. 87-1 CHANGE TITLE Gaseous Waste Surge Tank Transfer Line Sample DESCRIPTION OF CHANGE This temporary procedure was prepared to provide a means of obtaining a non-routine ' sample from the transfer line between the Gas . Surge Tank and process radiation monitor 2GWS-RQ-101.- This sample was use.d to evalauate the response of the monitor in support of IST-2.43.01- Blanked test connections in this transfer line,

.provided for u;h ]r purposes, were used to collect.the sample. A safety- evalualtion was performed since this procedure represented a temporary change to a site facility and involved a radioactive

' waste syctem (refer to I.E. Circular 80-18).

SUMMARY

OF SAFETY EVALUATION The procedure involved temporarily connecting a low pressure sample collection rig to an existing, unused test connection. A connection .to the test fitting will not increase the probability of a gaseous waste system failure as analyzed in the Updated Final Safety Analysis Report.

The pressure and temperature of the gas in the transfer line, and hence the sampling rig, is low and is incapable of causing damage to adjacent safety related equipment.

There are no BVPS-2 Technical Specifications affected by this procedure.

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. BVPS-2 Annual Report of Facility Changes,

, Tests and Experiments for 1988 RAD CON PROCEDURES Page 40 i

CHANGE TITLE BVPS-2 Digital Radiaiton Monitoring System (DRMS) - Database Change j Forms88-110, 88-111 for Radiation Monitor 2HVS-RQ109B 1 DESCRIPTION OF CHANGE During the performance of a maintenance surveillance procedure ] '

(MSP) , it was discovered that two database items that affect the response of this category 1E monitor operability required by technical specificaitons) were improperly set during system  !

startup. Database change forms88-110 and 88-111 reset these two parameters to the values originally documented by the system vendor. The database items being modified are used in controlling sample flow if the release stream flow changes such that automatic isokinetic sampling control is beyond range. The safety evaluation was performed to evaluate the safety of the reset values since system performance is changed.

SUMMARY

OF SYSTEM EVALUATION This monitor is used to assess the effluent releases caused by an accident, and in itself, canont increase the probability or consequences of an analyzed accident as the monitor is not considered in any analysis. The change will return the instrument response to its design state.

This monitor is used to assess the effluent release caused by an accident, once the accident has occurred. The monitor has no automatic control functions, and no manual operation actions are initiated by this monitor. Therefore, there is no increase in the probability or consequence of an accident or malfunction.

The monitor was restored to-operable status within the restoration period allowed by the Technical Specification. Thus, there is no reduction in the margin of safety,

>n s e ,4 = a

• BVPS-2 Annual Report of Facility Changes,

, Tests and Experiments for 1988 UFSAR CHANGE Page 41 1

CHANGE TITLE I FSAR Table 5.2.5, Reactor Coolant System (RCS) Lithium Specification DESCRIPTION OF CHANGE The RCS Lithium concentration specified in the Updated Final Safety Analysis Report will be revised to be variable from 0.7 to 2.2 ppm as a function of Boron concentration. This change is based on Westinghouse recommendations as discussed below.

SUMMARY

OF SAFETY EVALUATION The probability of an accident previously evaluated in the Safety Analysis Report will not be increased because:

a) below 1200 ppm Boron the Lithium is maintained within original Westinghouse design.

b) in the short time the plant is operated above 1200 ppm Boron (Unit 1 cycle 7 beginning of cycle boron concentration is 1283 ppm), the Lithium will be maintained as recommended by Westinghouse in the attachment to Standard Information Package SIPS-1 Rev. 4 for operation above 1200 ppm.

Westinghouse has determined that no appreciable Zircaloy cladding corrosion will occur with this regime. Also, since Beaver Valley Unit 1 has seen little evidence of pressurized water stress corrosion crrcking (PWSCC) thus far in operation and since Unit 1 previously opt sted during cycle 1 and 2 with similar high pH chemistry, the probability of increased corrosion of pre-initiated PWSCC is low. In addition, 100% eddy current is planned for the steam generators in the future and PWSCC levels will be specifically evaluated. Based on those findings, the chemistry regime in use will be reevaluated.

Reference Westinghouse Technical Bulletin NSID-TB-88-03.

The consequences of an accident previously evaluated will not be increased because the plant was designed and evaluated for the use of Lithium in the RCS. The probability of a malfunction of equipment important to safety will not be increased because the plant was designed to operate using Lithium and the Lithium concentrations will be kept within recommended guidelines (NSID-TB-88-03). The consequences of a malfunction of equipment important to safety will not be increased and should be decreased due to reduced ex-core radiation fields. The possibility of an accident of a different type than any previously analyzed will not be created because the Lithium will be kept within Westinghouse guidelines (NSID-TB-88-03). The possibility of a malfunction of a different type than any previously evaluated will not be created.

h Beaver Wuey Power Staten Shippingport. PA 15077@04 sc Ps s en Nuclear Group 44121 643 6256 April 27, 1989 U. .. Nuclear Regulatory Commission Attr : Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 1988 Report of Facility Changes, Tests and Experiments Gentlemen:

Th's letter forwards the 1988 Annual Report of Facility Changes, Tests and Experiments, in accordance with 10 CFR 50.59.

The report covers the period November 1, 1987 through October 31, 1988 to coincide with the annual FSAR update. A brief description of each facility and procedure change is provided with a brief summary of the safety evaluation for each change.

Very truly yours,

'), Lk D. Sieber

[J.Vice President Nuclear Group cc: Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Sr. Project Manager Director, Safety Evaluation & Control (VEPCC)

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