ML20205K136

Bvps,Unit 1 Facility Changes,Tests & Experiments for 970123-980122

ML20205K136
Person / Time
Site:	Beaver Valley
Issue date:	01/22/1998
From:	DUQUESNE LIGHT CO.
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ML20205K130	List: ML20205K126 ML20205K136
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NUDOCS 9904120345
Download: ML20205K136 (44)

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Table of Contents 4

Page 1 of 4 DCP 1109, Sand Filter Pumps Discharge Line Material Change.......................................... 1 l

l DCP 2134, Contamment Air Partial Pressure Loops................................................................ 1 l

l DCP 213 8, IPC Upgrade to Include PVC Functions................................................................... 2 l

DCP 2170, AFW Turbine Overspeed Trip Linkage Upgrade.................................................... 2 DCP 2177, Phase 2 - BV-2 Service Water System (SWS) Pump Seal & Filtered Water Pipe i

Replacement.....................................

.................................................3 l

I DCP 2191, Installation of Condensate Drain Lines with Isolation Valves.

.............................3 l

DCP 2209, ARPI Electronic Upgrade.......

.4 DCP 2219, BV-1 Contamment Penetrations Ovcipressure Protection......................

.........4 i

l DCP 2228, in-Mast Sipping....................

..........................................................5 1

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DCP 2253, Installation of Permanent Spool Pieces For Existing Metrex Valves.........

..................5 l

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DCP 2263, Excess Letdown Pipe Support Modification.......................................................... 6 I

l DCP 2298, Additional Small Bore Pipe Supports Upgrade..........................

...................6

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DCP 2300, Charging Pump Miniflow Restricting Orifice Modification..............................................7 DCP 2320, Discharge Line High Point Vent of the Quench Spray System..........

.........7 MISC 16-02, Incorrect Identification of ASME Class of Gaseous Waste Charcoal Delay Bed Vessel inUFSAR...........................................................

......................8 MISC 16-05, Clarification ofIncore Thermocouple Operation......

...........8 1

i MISC 16-06, Clarification on RVLIS Hydraulic Isolators.............................................. 9 MISC 16-07, NSA Change of ICCR-28 from Open to Closed......................................

....9 MISC 16-08, Change NSA of Gaseous Waste Disposal System Valves 1GW-83 and IGW-85....

. 10 MISC 16-15, Service Building Flooding Evaluation..................................

....... 10 MISC 16-16, Change NSA For BR-757 & BR-759 to Open.................

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1 MISC 16-17, NSA Change of AS-979 & AS-983 to Closed....................

............... I 1 MISC 16-18, NSA Change of CN-33 to Closed & CN-52 to Open..............................................12 9904120345 990330 m

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Table of Contents Page 2 of 4 MISC 16-19, NSA of Various CCR Valves.........

..... 12 MISC 16-20, Stroke Time Requirement of MOV-SI-867D...............................

...........13 MISC 16-21, Change Description of Valves QS-94 and QS-95 from Drain to Vent Valves............13 TER 09619, Nitrogen Supply System Modification.

.14 TER 10127, Retirement of Primary Deacrator and Associated Components................................. 14 TER 10284, Replacement Ball Valve for RW-212, RW-213, RW-214, and RW-215......

.15 TER 10424, AMSAC Circuit Modification................

...................................15 TER 10516, Retire in Place Narrow Range H2 Analyzer and Local Panel..............................

... 16 TER 10559, Reconcile Valve BR-739 Location (Rev.1)....

...... 16 TER 10.577, Piping Support Modifications for Containment Pene'ra'. ions.......

...................17 TER 10702, Modify Outlet Piping of WT-1084..............

.. 17 TER 10840, Intake Structure Pump Cubicles Exhaust Vents............................

.18 TER 10855, Sealing ofIntake Structure Pump Cubicles Roof Plugs.....

.. I8 TER 10885, Replacement of Main Steam Check Valves MS-18, MS-19, MS-20..

.19 TER 11012, Replace MOV-SI-863A Valve Body..........

............19 TER 11189, Valves for Switchgear Cooling Condenser Pumps Instruments..

.............................20 TER 11311, Replacement of Valve RC-72..................

... 20 3

TER 11312, Replacement of Vahe IA-91...

. 21 TER 11314, Replacement of SA-15..............

...............................21 TER 11425, Vital Bus 1,2,3, and 4 Setting Changes...........

........ 22 TER 11434, Reactor Core Analysis for Cycle 13...........

...................................22 TER 11464, Evaluation of 17x17 Enhanced Performance RCCAs.

..................................23 i

TER 11711, Assign Floor Penetration Numbers to Intake Structure Curb Boxes..................

. 23 Temporary Modification 1-97-03, Temporary Cribbing to Support Condensate Piping............... 24

I Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments i

January 23,1997 - January 22,1998 Table of Contents Page 3 of 4 Temporary Modification 1-97-04, Steam Generator I A Blowdown Line Isolation Valve Leak Repair... 24 Temporary Modification 1-97-05, High Pressure Turbine, Turbine Chest (West) Leak Repair......... 25 i

Temporary Modification 1-97-06, High Pressure Turbine, Turbine Chest (East) Leak Repair........ 25 1

Temporary Modification 1-97-07, Leak Repair Clamp on 3" Swing Check Valve MS-81............... 26 Temporary Modification 1-97-08, Leak Repair for Condensate Punp.............

.............26 Temporary Modification 1-97-09, Leak Repair to 1" Ball Valve BR-80 to Prevent Boric Acid Leak...... 27 l

Temporary Modification 1-97-10, install Leak Repair in Pipe to Elbow Weld...........

.... 27 l

Temporary Modification 1-97-12, Utilize Service Air to Mix Contents of Clarifier..

.. 28 l

Tempo ary Modification 1-97-13, Drip Pan Installation.........

......... 2 8 Temporary Modification 1-97-14, Temporaiy Modification to FW-P-1B1/lB2 Coupling Guard..

.... 29 Temporary Modification 1-97-15, Temporary Bladder Air Supply For Dampers VS-D-40-1 A, IB, 1C,1D...............................

...............................29 l

l Temporary Modification 1-97-16, Temporary Modification to Cooling Tower Pump House Ventilation Controls........

......................................30 Temporary Modification 1-97-17, Temporary Support of HCV-CH-389 and CH-130 Piping........ 30 Temporary Modification 1-97-18, Install Blank Flange in Joint Downstream of ISA-15.................... 31 Temporary Modification 1-97-19, Install Leak Repair for Valve SD-136...

..... 31 Temporary Modification 1-97-20, RCS Makeup From RWST..

..... 32 Temporary Modification 1-97-21, Addition of Sprinklers To Temporary Outage Structures / Trailers...32 Temporary Modification 1-97-22, Lirks Radiological Access Tracking System......

... 33 Temporary Modification 1-97-29, Installation of Plugs in the Unit 1 Cooling Tower Discharge Drain Lines.

.. 33 Temporary Modification 1-97-30, Temporary Modification for FW-P-1B1 and IB2 Outer Oil Seals...34 Temporary Modification 1-97-31, Temporary Modification for FW-P-1 A1 and 1 A2 Bearing Housings.. 34 Temporary Modification 1-97-32, Magnahelic Gage Addition & Setpoint Change..

.. 35 r

UFSAR Change To Update Containment isolation Valve (CIV) Arrangements Tables..

.35 l

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Table of Contents 4

Page 4 of 4 UFSAR Revision, Refueling Procedure Change For Vessel Stud Tensioning.......

..........................36 UFSAR Revision, Review of Scoping Dose Calculation Results Agamst UFSAR Listed Bounding Dose Values..........

........................................36 UFSAR Revision, Revise Frequency for Testing SI Auto Transfer to Recirculation....................... 37 UFSAR Revision, Changes to Reflect Current Operation of Solid Waste Handling Program.............. 37 UFSAR Revision, Changes to Reflect Current Operation of Liquid and Gaseous Waste Handling Program........................................................

....38 UFS AR Revision, Editorial Change To UFSAR To Clarify Emergency Diesel Generator Design........ 38 UFS AR Revision, 480 V Bus Tie Breakers.................................................

.............39 UFSAR Revision, Breaker Alignment Verification.............

.........................................39 UFSAR Revision, RCCA Misalignment....

.........................................................40

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Beaver Vc.lley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 1 of 40 CHANGE TITLE DCP 1109, Sand Filter Pumps Discharge Line Material Change CHANGE DESCRIPTION This modification replaced the existing 2" carbon steel pipe supplying seal water to the river w3ter pumps with stainless steel pipe. The design function remamed the same and all seismic requirements were unaffected. He carbon pipes were replaced with stainless to reduce the amount of corrosion which exists in the currently installed piping.

This change will not affect the river water system's function to provide sufficient cooling capacity for safety-related equipment. His change will improve the reliability of the system by making it less prone to corrosion which will assist in providing the river water pumps with seal water. This design change will not create the possibility of an accident or malfunction of a different type than previously evaluated, nor will this change increase the likelihood of an accident or the consequences of an accident. This change, therefore, will not create an unreviewed safety question.

DIANGE TITLE DCP 2134, Containment Air Partial Pressure Loops CHANGE DESCRIPTION This change replaced the contamment air partial pressure loop with a containment total air pressure indication. The containment air partial pressure will be hand calculated by control room operators.

The failure of the containment total pressure instrumentation will not initiate any currently analyzed design basis accidents, nor will it create r4 new accident. Since total pressure will respond similarly to partial pressure, the possibility of a signi.ficant change in air partial pressure without a corresponding change in total pressure was not considered a credible event. Since the total air pressure instruments will alarm in the control room, response to accibnt scenarios remains the same. The equipment used to monitor total pressure is considered more reliable than that used to measure partial pressure. This change does not involve an unreviewed safety questio t

m Beaver Valley Power Station Unit 1 l

Facility Changes, Tests, and Experiments l

January 23,1997 - January 22,1998 Page 2 of 40 CHANGE TITLE DCP 2138, IPC Upgrade to Include PVC Functions CHANGE DESCRIPTIOE nis DCP removed the existing Unit 1 Plant Variable Computer (PVC) from service due to it being obsolete and having high maintenance costs. All functions of the PVC have been taken over by the In-Plant Process Computer (IPC). The data points that were not currently on the IPC were added by replacing the l

applicable PVC input / output (UO) with the type of FO that was on the IPC. One of the six PVC UO cabinets is being reused with the new IPC UO; the remaming five were retired in place.

The computer systems affected by this change perform no control or protection actions and are intended as I

a monitoring aid. Therefore, this design change and the failure modes associated with this design change do not affect any DBA, nor create a new type of accident. His change does not create an unre,iewed safety question.

CHANGE TITLE DCP 2170, AFW Turbine Overspeed Trip Linkage Upgrade CHANGE DESCRIPTION i

l DCP-2170 changed the overspeed trip mechanism on the steam driver (i.e., the Terry Turbine, FW-T-2) l for the Turbine Driven Steam Generator Auxiliary Feedwater Pump (FW-P-2) from the existing oil trip l

mechanism to a direct mechanical trip linkage. He existing overspeed trip mechanism on the Terry Turbine utilized an oil trip arrangement to prevent overspeeding of the turbine, which could cause turbine j

damage or feedwater system overpressurization. He oil trip is part of the pump and turbine's lube oil l

system.

This design change does not impact the probability of failure of other plant systems. Since the existing arrangement relied upon both hydraulic and mechanical parts to effect a trip, and the new mechanical trip linkage relics on a simpler mechanical linkage, the new mechanical linkage arrangement does not increase the probability of failure of the systems important to safety, ne change will not impact the assumptions, consequences or the probability of occurrences of any DBA and, as such, no unreviewed sat, question is involved.

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Beaver Valley Power Station Unit Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 3 of 40 CHANGE TITLE DCP 2177, Pi.ase 2 - BV-2 Service Water System (SWS) Pump Seal & Filtered Water Pipe Replacement CHANGE DESCRIPTION This is a Beaver Valley Unit 2 (BV-2) design change to replace the existing carbon steel pipe supplying the Seal and Fihered Water to each BV-2 SWS Pump with alloy steel, and replace the carbon steel valves with

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stainless steel ball valves. The Seal and Filtered Water lines had experienced ledage due to degradation J

caused by pipe wall thinning and corrosion. Phase 2 of this design change affected BV-1 by changing the location of the Unit 1IUnit 2 boundary at the Unit 1 Filtered Water tie-in and by changing the pipe material at the Unit 1/ Unit 2 boundary valve.

The installation and testing for this material replacement conform to the original design document, and will therefom have the same effects and failure modes as the original installation; and no new accident condition is created. Since this change replaces existing components that meet the origir' design basis, the consequences of an accident would not be increased as a result of this change. This c_. age, therefore, does not involve an unreviewed safety question.

CHANGE TITLE DCP 2191, Installation of Condensate Drain Lines with Isolation Valves CHANGE DESCRIPTIOR This change added a drain line with an isolation valve to three gaseous waste filters. These drain hnes are seismically supported. The dmin lines were installed to provide a drain path for condensate that collected in the gaseous waste system filter housings which affected the flow of gas through tire filters.

The change does not reduce the effectiveness of the gaseous waste system, or create a condition to prevent the function of the gaseous waste system. The installation will be seismically supported; therefore, the installation does not increase the probability of a pipe break due to a seismic event. This change does not affect the assumptions and radiological consequences of an accidental gaseous selease. An unreviewed safety question is not invoh~ed with this change.

Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1908 Page 4 of 40 CHANGE TITLE DCP 2209, ARPI Electronie Upgrade CHANGE DESCRIPTION DCP 2209 replaced the existing rack mounted electronic equipment for Westinghouse's Analog Rod Position Indication (ARPI) system with ABB Combustion Engineering Rod Position Indication (CERPI) system. The replacement CERPI system uses existing RPI detectors, existing analog meters and rod bottom lights.

CERPI is an electronic replacement upgrade which corrects existing detector design limitations, Therefore, the perfonnance of the RPI system will be improved. None of the identified failure modes associated with this change represents a new unanalyzed type of malfunction. There are no design basis accidents for which failure modes associated with the change can be an initiating event. 'Iherefore, this change does not represent an unreviewed safety question.

l CHANGE TITLE l:

DCP 2219, BV-1 Containment Penetrations Overpressure Protection i

CHANGE DESCRIPTION This DCP installed relief valves on lines connecting certain containment penetrations. These valves are to provide thermal overpressure protection in the event of liquid pressure build-up due to transient temperature conditions inside contamment following a DBA.

The additional piping and valves meets or exceeds the design requirements for the systems in which they are installed. This change does not increase the probability of a contamment penetratica pipe or valve failure because the penetration pressures will be maintained within design limits during all plant operatmg conditions, including a DBA. The new relief valves will provide overpressure protection. This change restores conformance to the original design basis and enhances the system. This change, therefore, does not represent an unreviewed safety question.

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r Beaver Valley Power Station Unit !

Facility Changes, Tests, and Experiments January 23,1997 -January 22,1998 Page 5 of 40 CHANGE TITLE DCP 2228, Ir.-Mast Sipping CHANGE DESCRIPTION This DCP added In-Mast Sipping hardware to the existing refueling crane. The hardware was added to the mast of the refueling crane to permit the injection of air into the bottom of the mast. The air is then collected at the top of the mast and passed through a radiation monitorms system During refueling, the sipping systens is used to identify leaking fuel assemblics by %+3ag fission gases or solid fission products that have escaped from bn: ached irrad= tart fuel rods.

De addition of the In-Mast Sipping hardware and analysis cu...yersts has been evaluated and has no effect on the refueling crane's performance. He probability of occurrence of a fuel handling accident is, therefore, unaffected by this change. This modification is a safety wi.ne.st that does not interfere with the function of any component important to safety. Herefore, this change does not increase the probability of, nor the consequences of, an accident evaluated previously in the UFSAR, and does not involve an unreviewed safety question.

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CHANGE TITLE DCP 2253, Installation of Permanent Spool Pieces For Existing Metres Valves CHANGE DESCRIPTION 1

This DCP converted temporary modifications into permanent modifications for two Turbine Plant River l

Water valves which had been used to control flow through the switchgear chiller condenser. He temporary modifications removed the valve internals, and the river water flow through the switchgear chiller condensers is now manually adjustcd. He valve bodies will remain and function in place of new spool pieces.

No safety systems are affected by this change. His change will ine ease the reliability of the switchgear chillers and decrease the maintenance on cleaning and irpairing con. valves. De proposed change does not increase the probability of occurrence c,f an accident evaluated previously in the UFSAR. Therefore, this chenge does not involve an unreviewed safety question.

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Beaver Wiley Power Station Unit i Facility Changes, Tests, and Experiments Januvy 23,1997 - January 22,1998

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l CilANGE TITLE DCP 2263, Excess Letdown Pipe Support Modification CIIANGE DESCRIPTION This DCP upgraded the excess letdown small bore pipa supports, Individual support modifications consisted of upgrading the existing support, removing the existing support and replacing it with a new support, or a combination of both. This modification will result in a decrease in the probability of failure of the piping systems.

The upgraded pipe supports are designed to withstand piping loads for ah anticipated plant conditions (norrnal and accident). It does not create any new accidents or malfunctions and does not adversely affect the operation of systems, structures or components important to safety. The probability of occurrence of, or consequences of an accident are not increased as a result of this change. Therefore, this change does not represent an unreviewed safety question.

CIIANGE TITLE DCP 2298, Additional Small Bore Pipe Supports Upgrade CIIANGE DESCRIPTION This modification upgraded the small bore pipe supports (Chemical and Volume Control System) which consisted of upgrading the individual support, removing the existing support and replacing it with a new support, or a combination of both.

There was no change that affects the function of these piping systems. The pipe supports are designed to withstand loads imparted on them from the pipe due to all anticipated loading conditions (nonnal, upset, faulted). The proposed change does not increase the probability of occurrence of a malfunction of equipment important to safety evaluated previously in the UFSAR. This change will upgrade the supports on the systems to ensure the piping integrity is maintained, thereby allowing the systems to perform their intended functions during the accident. "Ihe proposed change does not increase the consequences of an accidut evaluated previously in the UFSAR. Therefore, this change does not represent an unreviewed

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safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 7 of 40 CHANGE TITL,E DCP 2300, Charging Pnmp Miniflow Restricting Orifice Modification CHANGE DESCRIPTION DCP-2300 removed the three existing Il-stage miniflow orifices (RO-CH-ORCP-1, RO-CH-ORCP-2 and RO-CH-ORCP-3) and replaced each one with a new 22-stage orifice design. The pipe lines that contain the orifices (2"-CH-77-1503-Q2,2"-CH-78-1503-Q2 and 2"-CH-79-1503-Q2) were modified to accept the longer orifices. A capped branch line downstream of each orifice was removed as a result of the 1

modification. The affected lines are located in the charging pump cubicles, El. 722'-6" of the Auxiliary Building.

The new miniflow orifices and associated piping modifications were designed to provide the required miniflow to preclude damage of the charging /high head safety injection pumps. Replacing existing miniflow orifices does not create any new accidents or malfunctions and does not affect the operation of any existing protection systems. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE DCP 2320, Discharge Line High Point Vent of the Quench Spray System CHANGE DESCRIPTION This DCP installed a 3/4" high point vent line and isolation valve on the discharge line of quench spray pump, QS-P-1 A. He vent valve was added to remove air that is entrapped in the high point to prevent water hammer events.

The Quench Spray System will not be affected by this change, nor will any other equipment that is required i

to mitigate an accident. System flow will be unaffected by this change. This change will not affect any of the analyzed design basis accidents, nor will the potential for an accident be increased as a result of this change. This change does not involve an unreviewed safety question.

Beaver Vdley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 8 of 40 CIIANGE TITLE MISC 16-02, Incorrect Identification of ASME Class of Gaseous Waste Charcoal Delay Bed Vessel in UFSAR I

CHANGE DESCRIPTION A Condition Report documented that the UFSAR had incorrectly stated that the gaseous waste delay bed vessels were fabricated in compliance with ASMF Section III, Class C. The UFSAR was changed to correctly identify the Gascous Waste Charcoal Delay Bed vessels as being fabricated to ASME Section III Class 3.

The vessels were fabricated to the proper code. He UFSAR change will not affect the performance of safety systems and does not affect the design in the field. Thus, no new failure modes are associated with this change. This revision to the UFSAR does not involve an unreviewed safety question.

CHANGE TITLE MISC 16-05, Clarification ofIncore Thermocouple Operation CHANGE DESCRIPTION A UFSAR change was submitted to clarify that incore thermocouple operation is specified in and controlled by the BV-1 Technical Specifications. It also clarifies that the design has excess capacity to house additional thennocouple instrumentation. Technical Specification Amendment 137, dated March 13,1989, imposed initial requirements on incore thermocouples during Modes 1, 2, and 3. TS Table 3.3-1, was revised to include incore thermocouples with two channels minimum per core quadrant operable out of the total of four channels per core quadrant.

This UFSAR revision introduced no change in actual incore thermocouple instrumentation criteria, only a clarification of current criteria. Since this change was a clarification of information contained in the UFSAR and not a modification to equipment, it introduced no new failure modes. Thus, the margin of safety has not been reduced. This UFSAR revision does not involve an unreviewed safety question.

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e Beaver Valley Power Station Unit 1 Facility Changs, Tests, and Experiments January 23,1997 - January 22,1998 Page 9 of 40 CHANGE TITLE MISC 16-06, ClarificatN on RVLIS Hydraulic Isolators CHANGE DESCRIPTION This item documented a revision needed to BV-1 UFSAR Section 7.8.4 to clarify the operation of the limit switches associated with the RVLIS hydralic isolators. The UFSAR stated that a limit switch will actuate when there is a leak between the hydraulic isolators and the high volume sensor inside the contamment. In fact, the limit switches only respond to a loss of volume or excess volume in the instrument line between the hydraulic isolator and the transmitter.

This change did not involve any physical plant changes, just a clarification to the Unit 1 UFSAR.

Assumptions and radiological consequences are unaffected since the change does not involve any physical modifications. Thus, the change has no effect on the probability of occurrence of design basis accidents and does not involve an unreviewed safety question.

CHANGE TJTLE I

MISC 16-07, NSA Change of ICCR-28 from Open to Closed CHANGE DESCRIPTION This item documented that the normal system arrangement (NSA) position of the chemical addition tank isolation valve was changed from open to closed. Molybdate based corrosion inhibitors, which required the presence of oxygen for effective passivation, were used in the Component Cooling Water (CCR) System until 1996. An NSA change was made previously to leave ICCR-28 open to allow circulation of the system through the surge tank to oxygenate the system. In May 1996 a nitrite component was added to the CCR System to enhance corrosion inhibition properties in localized areas of the system with low dissolved oxygen. Molybdates used with nitrites no longer required the presence of dissolved oxygen for passivation.

Changing the NSA position to closed reduced the susceptibility of system contammation from aerobic microbiological activity caused by continuous flow through the atmospheric surge tank.

This change had no effect on the probability of failure of the CCR System because it only involved changing the NSA of ICCR-28. No new failure modes were created since the original position of the valve I

was closed. There were no design basis accidents that were affected by this change and the susceptibility to contamination from aerobic microbiological activity causod by continuous flow through the atmospheric surge tank was reduced. This change, therefore, does not involve an unreviewed safety question.

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Beaver Valley Power Station Unit 2 Facility Changes, Tests, and Experiments January 23,1997 -January 22,1998 Page 10 of 40 CHANGE TITLE MISC 16-08, Change NSA of Gaseous Waste Disposal System Valves 1GW-83 and 1GW-85 CHANGE DESCRIPTION i

A change to UFSAR Fig. I1.2-2 was submitted to change the NSA of gaseous waste isolation valves from open to shut. This was done to prevent recycling hydrogen and fission product gases from the waste gas i

system to the Volume Control Tank (VCT). A corresponding text change was also submitted for UFSAR Sections 9.2.2,11.2.3.1, and 11.2.3.2 to identify that even though the recycling path for gas reclamation to the VCT is available, it is not normally used.

Here are no design bases accidents which could be initiated as a result of this change. There is no adverse impact on the performance of safety systems (Gaseous Waste Disposal System, Charging and Volume Control System, and Reactor Coolant System) resulting from this change. The proposed change does nct reduce the margin of safety as defmed in the rechnical Specifications. The change will improve the margin of safety by preventing the buildup of fission product gases in the RCS. This change does not represent an unreviewed safety question.

CHANGE TITLE MISC 16-15, Service Building Flooding Evaluation CHANGE DESCRIPTION i

This change revised the BV-1 UFSAR Section 9.7.2 discussion of Service Building Switchgear, Relay Room and Cable Tray Area flooding to reflect a new flow rate from a break in a 1" domestic water line to two battery area safety showers. Normal water supply pressure was reduced to 55 psig from 65 psig; however, calculations resulted in a higher break flow rate.

The original flooding analysis for the non-safety related domestic water system did not postulate a regulating equipment failure concurrent with the postulated break. There is no change in the probability of a failure within the system. Also, even with the higher break flow, adequate time exists for operators to take action against a postulated pipe break. Since the prescribed operator response time to isolate the break remains conservatively set, and flood height remains well below the level that would threaten sital electrical equipment, there is no impact or change to the performance of any safety systems. This change does not involve an unreviewed safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 -January 22,1998 Page 11 of 40 CHANGE TITLE MISC 16-16, Change NSA For BR-757 & BR-759 to Open CHANGE DESCRIPTION This change permits the root isolation valves for Boron Recovery test tank pumps discharge possure gauges to be maintained as normally open versus normally closed. This change supposts the change to the Operating Manual and the UFSAR. The discharge pressure gauge would subsequently be continually available. De test tanks receive distillate from the Boron Recovery Evaporators for sampling. De water is then directed to either the primary water storage tanks or to a high level waste drain tank.

Here are no design basis accidents which will be impacted as a result of the failure of these pressure gauges. Failure of the pressure gauge would result in contamination to the auxiliary building floor only, J

and would not present an accident different from those already analyzed. This change, therefore, does not represent an unreviewed safety question.

CHANGE TITLE MISC 16-17, NSA Change of AS-979 & AS-983 to Closed CHANGE DESCRIPTION Drains from the air ejectors are directed to the steam air ejector tank, which is normally drained to 'the condenser tirough a loop seal connection. An alternate drain path is to the blowdown system flash tank through pump IBD-P-3. His pump has not been used satisfactorily for this purpose and has been isolated j

for an extended time. This change evaluated retiring this pump in place.

Isolating this drain path to the blowdown system has no effect on the probability of failure of any plant equipment. The flow path which is now isolated is an alternate path, and the normal path is not affected by this change. No safety related equipment is affected by this change, and no accident conditions are created by retiring the equipment. No previously evaluated accident conditions rely upon this equipment for accident mitigation; therefore, this change will not affect the consequences of an accident and does not involve an unreviewed safety question.

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4 Beaver VrJley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 -January 22,1998 Page 12 of 40 CHANGE TITLE MISC 16-18, NSA Change of CN-33 to Closed & CN-52 to Open CHANGE DESCRIPTION Previously, Slade packing was installed in the Heater Drain Pumps which permitted pump operation without a seal water supply. When the pumps were ranacked, seal water to the pumps was isolated.

Subsequently, it was requested that the seal water supply be isolated further upstream at the Condensate header. This was accomplished by changing the NSA of several valves in the Candea =*a System.

Here is no change to the operation of the Heater Drain or Condensate Systems. Seal water isolation has j

no impact on safety systems. Here are no failure modes assoc.iated with the seal water isolation, as seal t

water is not required with the replacement style packing. This change does not involve an unreviewed safety question.

CHANGE TITLE MISC 16-19, NSA of Various CCR Valves CHA'NGE DESCRIPTION This change reclassifies Reactor Plant Component Cooling Water (CCR) valves from normal system arrangement (NSA) to a secured in position status. The affected valves were secured in position. His change permitted the removal of these valves from a monthly surveillance based on these valves being in a secured position.

The valves being secured are manual valves which are normally left in the open, closed, or throttled position and are not capable of modulating. nese valves are located in Containment and are not required to be manipulated at power. Herefore, the locking device will r.ot prevent the vaiva.s from performing their l

intended function. This change is for administrative control only, and does not involve an unreviewed safety question.

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Beaver Valley Power Station s it1 Facility Changes, Tests, and Expenments January 23,1997 - January 22,1998 Page 13 of 40 CHANGE TITLE MISC 16-20, Stroke Time Requirement of MOV-SI-867D CHANGE DESCRIPTION

- This change revised BV-1 UFSAR Section 6 concerning the stroke time requirement for valves which must function on a safety injection signal (SIS). This was the result of a replacement of a motor operated valve whose stroke time differed from the original value contained in the UFSAR. The effect of this change was to remove the original stroke time requirement contained in the UFSAR and refer to the Liceram Requirements Manual (LRM) for SIS stroke time requirements.

This change has no effect on the performance of the safety systems The accident calculation of record utilized the limiting value as described by the Technical Specifications (and later relocated to the LRM) to ensure system performance was satiu,, tory during an accident. 'Ihis change does not increase the probability of an accident as described in the UFSAR. There are no credible failure modes associated with this change. The purpose of this change is to clarify a discrepancy between the UFSAR and the LRM.

This change does not represent an unreviewed safety question.

CHANGE TITLE MISC 16-21, Change Description of Valves QS-94 and QS-95 from Drain to Vent Valves CHANGE DESCRIPTION Several Quench Spray drain valves were identified as being vent valves based on their orientation and elevation on associated piping. UFSAR Figure 6.4-1A identifies these valves as " drain valves." This i

change corrected the Quench Spray valves' nomenclature, corrected the description on the operatmg drawings to "vc.nts" instead of" drains," and initiated a revision to correct UFSAR Figure 6.4-1 A.

The change is administrative as it only changed valve descriptions fro.n " drain" to " vent." No equipment is being modifi:d or operated differently resulting from this change. Since no equipment is being modified or operated differently, there are no credible failure modes associated with this change. The Quench Spray System will not operate differently and design basis accidents are not affected by this change. This change does not represent an unreviewed safety question.

Beaver Valley Power Station Unit 1 Facility changes, Tests, and Expa..csts January 23,1997 -January 22,1998 Page 14 of 40 CHANGE TITLE TER 09619, Nitrogen Supply System Modification CHANGE DESCRIPTION This change replaced the original nitrogen supply manifold, which used nitrogen bottles and temporary piping and components, with a permanent truck supply fill connection. Nitrogen supplies the steam generator supply system and is backup to instrument air for PORY operation. Nitrogen also supplies the safety injection accumulators to maintain pressure. Additionally, nitrogen is used to purge the Volume Control Tank during shutdown and to purge gascous waste when oxygen is 22% during system startup.

1 No new accident scenarios were created by this change. He installation has no potential for creating a new type of accident. No equipment important to safety is associated with this change, and this change is to the non-safety related portion of the system. He proposed change does not increase the consequences of an accident evaluated previously in the UFSAR. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE TER 10127, Retirement of Primary Deserator and Associated Components CHANGE DESCRIPTION The primary grade make-up water deaeration equipment presently installed at Unit I was retired in place.

His included the Primary Water Make-Up Demerator and associated g- ;==.a. The system was retired by placing pipe caps in the pipelines to isolate the system. Valves adjacent to the pipelme isolation points were also placed in the shut position, if they were not shut already.

This TER a& cts the non-safety related portion of the Boron Recoveiy and Primary Makeup Systems. The

. new pipe caps were installed per approved methods and were tested for leaks. Any adjacent valves to the pipe caps will also have their NSA changed to shut if their current NSA is otherwise. His TER also affects the Reactor Coolant System, in that free oxygen would no longer be removed by the deaerator which may increase corrosion-product deposits on the fuel. However, it was concluded that this would not be of any consequence since there was evidence that there are indiscernible differences between plants which operate with demerated makeup water from those that operate with much higher concentrations. This change will not affect any equipment from performing its intended safe shutdown function and does not involve any unreviewed safew question.

r Beaver Vcliev Nwer Station Unit 1 Facility Changes, Tests, and Expenments

- January 23, 3997 - January 22,1998 l

Page 15 of 40 CHANGE TITLE TER 10284, Replacement Ball Valve for RW-212, RW-213, RW-214, and RW-215 CHANGE DESCRIPTION Four degraded 1/2" River Water drain valves [RW-212, 213, 214 and 215] servicing 14" River Water piping [WR-63, 65, 86 and 88] were replaced with 1/2" & Jess steel full port ball valves. Identical replacement drain valves were not available. The new ball valves are an easier component to maintah, and provide a longer expected service life. Successful ball valve replacement of River Water drain v Uv.s ha previously bien demonstrated. The 14" pipes are the River Water supply to the Recirculation Sprs, Le Exchangers.

This change will not affect the function of the system since the new valves will provide a similar function The river water supply to the recirculation spray heat exchangers will not be affected by this~ change, nor will any equipment required for safe shutdown of the plant. De change in valve type will not create any new types of accidents or increase the probability of an accident and will perform the same function as those they are replacing. This change does not involve an unreviewed safety question.

CHANGE TITLE TER 10424, AMSAC Circuit Modification CHANGE DESCRIPTIO~N i

This TER was involved with changing the AMSAC circuitry to allow a biasing and re-scaling of the main feedwater flow channels so that the AMSAC circuitry could more accurately determine when a channel has failed. With the present circuitry, there is very little difference between a flow channel properly readmg a

'zero' flow condition and AMSAC interpreting the flow signal as " failed." This TER will increase that difference by providing a signal input margin sufficient to ensure the failed and no-flow conditions can be differentiated by AMSAC under static and dynamic conditions. This circuitry change will require the flow j

channels to be re-scaled so that the present AMSAC setpoints are maintained Proper scaling and calibration ofinput cards will ensure compatibility with the AMSAC control cards. Changes are limited to i

the AMSAC system with no changes to its inputs or outputs.

His change will not affect the ability of AMSAC to perform its intended function, nor will it prevent any equipment, structures, or components from performing its intended function during an AMSAC event or any other analyzed event. De change in input margin will not create a new type of accident or increase the consequences of an accident already analyzed. His change does not involve an unresiewed safety question.

Beaver Vr.lley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 16 of 40 CHANGE TITLE TER 10516, Retire in Place Narrow Range H2 Analyzer and Local Panel.

CHANGE DESCRIPTION The Unit I narrow range hydrogen analyzers have been retired in place based on the use of the wide range hydrogen analyzers in lieu of the narrow range hydrogen analyzers.

The narrow range hydrogen analyzer measured hydrogen concentration across the hydrogen recombiner, but the wide range analyzer does not; therefore, the ef ficiency of the recombiner can no longer be measured.

However, the hydrogen concentration in contamment can be measured. The ability of the hydrogen recombiner to perform its safety func. ion will not be affected. Containment integrity will not be affected during normal or design basis accident conditions with respect to the removal of sensing lines. There are no credible failure modes associa.d with the retirement of the narrow range hydrogen analyzers nor are there any effects which inercase the probability of the design basis accidents. His change does not involve an unreviewtxi safety question.

CHANGE TITLE TER 10559, Reconcile Valve BR-739 Location (Rev.1)

CHANGE DESCRIPTION This TER evaluated the existing Boric Acid Hold Tank recirculation line piping configuration against the design configuration shown in UFSAR Figure 9.2-3. This TER documented the present configuration as equivalent to the design configuration shown in the UFSAR and updated plant documents to show the present configuration. This change does not affect the performance of the Boron Recovery System since tank storage c.apacity has not been changed.

There is no change in the probability of occurrence of an accidental release of waste liquid since this change oes not change the Boric Acid Hold Tank building sump configuration. Tb: proposed change does not incease the consequences of an accident evaluated previously in the UFSAR. Therefore, this change does not represent an unreviewed safety question.

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4 Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 17 of 40 l

CHANGE TITLE TER 10577, Piping Support Modifications for Containment Penetrations CHANGE DESCRIPTION A review of the piping support configurations identified that several containment penetration piping supports would exceed the allowable stress values during accident conditions. This TER was generated to add or modify pipe supports on the Reactor Vents and Drains System and the Component Cooling Water System. This change involved containment penetrations 26,29, an.d 38.

This change will ensure calculated stresses of the piping will remain within the allowable design loadmg limits. The addition of these supports will not alter the ability of the systems to perform their design function during normal or accide conditions. This change will not affect the plant's response to an accident nor cause any new accidents. The supports are of a material and construction used throughout BV-1; therefore, there are no new accidents or malfunctions created due to the materials used in this change. This change does not involve an unreviewed safety question.

CHANGE TITLE TER 10702, Modify Outlet Piping of WT-1084 CHANGE DESCRIPTION The purpcse of this TER was to approve, provide instructions and identify materials to be used to install a drain line on the outlet of valve WT-1084 to an adjacent dramage pit. Valve WT-1084 is used to drain the Turbine Plant Demineralized Water Tank. The valve is open ended (6" weld neck flange) allowing the water to drain to the ground in the North Yard. The new 3" drain line is connected via a 6" x 3" eccentric reducing fitting and a 3" weld neck flange.

This evaluation provided the fit, form and function requirements of piping on the outlet of the Demineralized Water Tank routed to a drain pit. The drain pipe has no effect on the condensate system, nor will it affect its performance. The reduction in pipe size was determined to have no effect on system operation. There are no accidents affected by this change, nor are any new accidents or failure mechanisms created as a result of this change. This change does not involve an unreviewed safety question.

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1 Beaver Valley Power Station Unit 1 Facility Changes, Testr, and Exp,riments January 23,1997 - January 22,1998

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Page 18 of 40 CHANGE TITLE TER 10840, Intake Structure Pump Cubicles Exhaust Vents i

l CHANGE DESCRIPTION The four Intake Structure pump cubicles (which house safety related River Water pumps) each have a roof opening for exhaust ventilation. He UFSAR states that these opemngs remain open during normal operation and are covered with 7' high exhaust stacks and cover plates when preparmg for flood conditions, ne exhaust vent stacks and cover plates act as passive devices to raise the flood proofed elevation of the intake structure pump cubicles. However, the vent stacks and cover plates are normally installed at all times and this TER allows for their continued use during normal operation.

The permanent installatior. of the exhaust stacks and cover plates results in the pump cubicles being capable of withstanding the probable maximum flood with wave action. Failure of the stack cannot initiate any design basis accident or create any new type of accident. He stacks and cover plates are available to perform their intended function and do not adversely affect normal plant operation, and the ventilation is not diminished. Additionally, no new failure mechanisms which would impact the operation of the River Water pM.s are created his change does not involve an unreviewed safety question.

CHANGE TITLE 1

TER 10855, Sealing ofIntake Structure Pump Cubicles Roof Plugs

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CHANGE DESCRIPTION Original plant requirements established a need to seal the Intake Structure cubicles' roof plugs with gaskets when preparing for flooding conditions. Two chemical storage tanks are now located on the cubicle roof.

To prevent possible chemical leakage into the cubicles due to a passive failure of a tank, the roof plug gaps have been sealed. The silicone based caulking used is compatible with the chemicals stored in the new tanks.' His TER incorporates the use of a permanent caulked seal rather than installing a gasket m preparation for flood conditions.

The permanent seals provide for continued protection, and failure of a caulk seal will have identical consequences of a failed gasket. Use of a permanent seal is beneficial since it will reduce the amount of work required when preparing for flood conditions. He plugs will not prevent the River Water /Senice Water Systems from supplying sufficient cooling water to required components. The plugs will not affect cubicle ventilation or create any type of new accident, nor will they increase the consequences of a design basis accident. His change, therefore, does not involve an unreviewed safety question.

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e Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 19 of 40 CHANGE TITLE TER 10885, Replacement of Main Steam Check Valves MS-18, MS-19, MS-20 CHANGE DESCRIPTION This TER documented that the swing check valves used in the steam lines to the Terry Turbine (the driver for the auxiliary feedwater pump) were replaced with flanged end in-line nozzle check valves. The new design does not have a separate seat ring that might come loose under extreme thermal transients.

The probability of occurrence of any UFSAR design basis accident is not changed. The pressure boundary of replacement in-line check valves is designed to the same criteria as the existing swing check valves. The probability of damage to any downstream component or other portions of the Main Steam System shall actually be lowered as the internal structure of the in-line check valves is less likely to be subject to stress than a swing check valve due to the short stroke of the in-line valve. The probability of failure within a steam line due to a pressure boundary failum of the in-line check valves remains unchanged. Thus, no new failure modes were created as a result of this change. Therefore, this change does not involve an unreviewed safety question.

CHANGE TITLE TER 11012, Repe

,10V-SI-863A Valve Body CHANGE DESCRIPTION This change replaced the valve body, bonnet, and trim of the low head safety injection pump discharge I

valve to the high head safety injection pump suction header isolation valve. The valve operator was not replaced. The present valve is a 6-inch stainless steel, butt welded, clus 150 solid wedge gate valve with a typical 30 second stroke. It was replaced with a stainless steel parallel disc gate valve.

This change enhances the mechanical strength of the valve and provides for better performance relative to i

leakage concerns. No additional failare mechanisms are created by this change. This change does not affect plant response to an accident. The design of the valve, to stroke open during the safety injxtion transfer from injection phase to recirculation phase, will not be changed. Valve stroke time is estimated to increase; however, this is not a critical characteristic as there is no stroke time limit for the accident conditions. No new accident conditions are created by this change, nor would any accident consequences be increased. This change does not involve an unreviewed safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 20 of 40 CHANGE TITI E TER 11189, Valves for Switchgear Cooling Condenser Pumps Instruments CHANGE DESCRIPTION Valves for the isolation of instruments associated with the Switchgear Cooling condenser p: imps were added when the pump skid was installed by a previous design change. However, plant design documents were not updated at that time to show these valves. The six valves are hand operated valves which are normally open. This TER updates the plant documents, including the UFSAR.

This change alTects the Switchgear Cooling System and the Turbine Plant River Water System, neither of which are required for safe shutdown of the plant. No new accident conditions are created by this change, nor are any accident consequences increased. This change does not involve an unreviewed safety question.

CHANGE TITLE TER 11311 Replacement of Valve RC-72 l

CH ANGE DESCRIPTION This TER documented the replacement of a simple check valve with a spring loaded check valve. The valve is an inside Containment Isolation Valve for penetration 45. The valve is located in containment between the crane wall and the containment liner. The replacement valve is rated for the design pressure and temperature of the system. This change was made to comply with the UFSAR criteria regarding inside containment isolation check valves.

This check valve functions as a Containment isolation Valve. The probability of failure of the Containment Isolation System is not increased because the change conforms with UFSAR Section 5.3, with respect to containment isolation arrangements. The failure mode associated with the replacement valve is the same failure mode that was associated with the original valve. The impact of the change is that the valve will perform as described in the UFSAR and in accordance with the Technical Specification surveillance test. Thus, a new type of accident has not been created. This change, therefore, does not represent an unreviewed safety question.

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R Beaver Vt.lley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 21 of 40 CHANGE TITL_li TER 11312, Replacement of Valve IA-91

. CHANGE DESCRIPTION His TER documented the replacement of a simple check valve with a spring ! tod check valve. The valve is an inside Contamment Isolation Valve for penetration 47. De valve is located in contamment between the crane wall and the containment liner. The replacement valve is rated for the design pressure and temperature of the system. This change was made to comply with the UFSAR criteria agarding inside containment isolation check valves.

His check valve functions as a Containment Isolation Valve. He probability of failure of the Containment Isolation System is not increased because the change conforms with UFSAR Section 5.3, with respect to containment isolation arrangements. The failure mode associated with the replacement valve is the same failure mode that was associated with the original valve. He impact of the change is that the valve will perform as described in the UFSAR and in accordance with the Technical Specification surveillance test. Rus, a new type of accident has not been created. This change, therefore, does not represent an unreviewed safety question.

CHANGE TITLE TER 11314, Replacement of SA-15 CHANGE DESCRIPTION nis TER documented the replacement of a 2-1/2" simple check valve made of carbon steel with a 2" stainless steel spring loaded check valve. The valve is an inside Containment Isolation Valve for penetration 42. The valve is located in containment between the crane wall and the containment liner. The replacement valve is rated for the design pressure and temperature of the system. This change was made to comply with the UFSAR. criteria regarding inside containment isolation check valves. The differences conceming replacement valve size and material were evaluated via this TER and found to be acceptable.

This check valve functions as a Containment Isolation Valve. The probability of failure of the Containment Isolation System is not increased because the change conforms with UFSAR Section 5.3, with respect to containment isolation arrangements. The failure mode associated with the replacement valve is the same failure mode that was associated with the original valve. The impact of the change is that the valve will perform as described in the UFSAR and in accordance with the Tochnical Specification surveillance test. Thus, a new type of accident has not been created. This change, therefore, does not represent an unreviewed safety question.

e Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 22 of 40 CHANGE TITLE TER 11425, Vital Bus 1,2,3, and 4 Setting Changes CHANGE DESCRIPTION Cutler Hammer relays have replaced existing Westinghouse AR440AR latchmg relays. The new relays have a higher inrush and steady state load which results in a higher voltage drop and consequently will not meet the minimum voltage requirements recc...wded by the vendor. This TER raised the output voltage at the inverters and regulating transformers and associated settings.

The performance of the safety system will remain nachanged. Dese changes will assure that the new relays being added to the system and future loads added will receive the required minimum voltage. The proposed change does not increase the consequences of a previously evaluated accident. De proposed activity does not create the possibility of a malfunction of equipment important to safety of a different type than any evaluated previously in the safety analysis report. Herefore, this change does not represent an unreviewed l

safety question.

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CHANGE TITLE i

TER 11434, Reactor Core Analysis for Cycle 13 CHANGE DESCRIPTION This TER documented the effects of the changes to the BV-1 reactor core for Cycle 13 operation. The Cycle 13 core configuration features a low-leakage loading pattern designed to meet a cycle length of 481 Effectiw Full Power Days (EFPD) or 17560 MWD /MTU burnup. The feed region will consist of 64 ihsh Westinghouse Performance + fuel assemblies (40 at 4.2 w/o U235 and 24 at 4.6 w/o U235). The mechanical design of the Region 15 feed fuel represents the introduction of Westinghouse's Performance +

fuel assemblics.

This change will not adversely affect the Reactor Core, Reactor Coolant System, Main Steam System, and Fuel Pool Cooling System since all design and performance criteria would continue to be met. He change would not increase the consequences of an accident evaluated previously in the UFSAR; the clad integrity is maintained and the structural integrity of the fuel rods, fuel assemblies, and core are not affected. ' %is change would also not increase the probability of occurrence of an accident evaluated previously in the UFSAR. Therefore, this change does not represent an unresiewed safety question.

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Be:ver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 23 of 40 CHANGE TITLE TER 11464, Evaluation of 17 17 Enhanced Performance RCCAs i

CHANGE DESCRIPTION l

his TER documented the effects of utilizing hh-M Performance - Rod Cluster Control Assemblies (EP-RCCA) at BV-1. EP-RCCAs are being used in place of the original RCCAs due to wear concerns of existing RCCAs. EP-RCCAs incorporate three features for extended service when compared to the standard RCCAs. These new features will extend the life of the EP-RCCAs by increasing rodlet corrosion resistance; accommodating possible swelling of the absorber material; and providing additional wear resistance.

This change does not adversely affect the Reactor Core, Reactor Coolant, or Fuel Pool Cooling Systems.

All design and performance criteria would continue to be met. The changes identified increase corrosion resistance and wear of the EP-RCCA, resulting in an increase in the mechanical integrity of the EP-RCCAs. The probability of occurrence of a design basis accident does not increase due to the mechanical design changes associated with the EP-RCCAs. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE TER 11711, Assign Floor Penetration Numbers to Intake Structure Curb Boxes CHANGE DESCRIPTION This change assigned seal numbers to floor penetrations in the Intake Structure B & C pump cubicles, so that they may be identified and controlled as flood seals. The TER also identified and corrected a discrepancy conceming the configuration of these penetrations as described on a design drawing and in the UFSAR. Pipe caps had been installed to prevent in-leakage through thene penetrations during high river water conditions; however, they were not shown as flood scais on the drawings. Also, fire barriers for the Intake Structure cubicles were not consistently depicted on figures in the UFSAR and fire protection documents; this change made them consistent.

The pipe cap closures are passive components which do not interact with any plant equipment. There is no effect due to the revised flood seal configuration. The administrative changes reflected in the fire barrier boundaries do not change tha exi: ting plant configuration and will not affect plant operating conditions.

This change will not introduce any new failure mechanisms or create an accident not already analyzed.

Nor would these changes increase the consequences of an accident or increase the likelihood of an accident.

This change does not represent an unreviewed safety question.

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Beaver Vt.lley Powei station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 24 of 40 CHANGE TITLE Temporary Modification 1-97-03, Temporary Cribbing to Support Condensate Piping CHANGE DESCRIPTION His change permitted the installation of wood cribbing around C*=*a System pipe WCPS-1-121.

He cribbing will prevent damage to WCPS-1-121 and to pipe support WCPS-R-3 which was found to have two of six baseplate anchor bolts broken.

The cribbing material is made of fire retardant material and is mounted such that shifting of the cribbing is not probable. %c loss of normal feedwater accident was determined to be the only event which could result from the failure of this cribbing and it has already been analyzed. However, the possibility of cribbing failure is small due to installation methods herefore, the probability of an accident has not been increased. The temporary modification does not affect the plant response to an accident due to its location and construction. A fire is unlikely in the area; however, fire retardant material is to be used and a sprinkler is located directly over the installation. This change does not represent an unreviewed safety quee. ion.

CHANGE TITLE Temporary Modification 1-97-04, Steam Generator 1 A Blowdown Line Isolation Valve Leak Repair CHANGE DESCRIPTION The body to bonnet joint BD-4 was wrapped with wire to enclose the bonnet seal leak for sealant injection.

Also,50% of the bonnet nuts were replaced with cap nuts to provide an injection path.

BD-4 is not a safety related valve and its performance or function will not be changed by this leak repair.

Installation of this leak repair does not affect the valve function, and will not affect the safety related portions of the blowdown system since it is located in the non-safety related portion of the blowdown system. Failure of the leak repair will not create a new type of accident. A credible accident is the failure of the valve; however, the loss of feedwater is an analyzed condition. Introduction of sealant material was considered highly unlikely due to sealing methodology and meticulous flow path. His change does not represent an unreviewed safety question.

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. Beaver Valley Power Station Unit 1 l

Facility Changes, Tests, and Experiments l

January 23,1997 - January 22,1998 l

l Page 25 of 40 CHANGE TITLE Teniporary Modification 1-97-05, High Pressure Turbine, Turbine Chest (West) Leak Repair CHANGE DESCRIPTION l

%e high pressure turbine outer casing west end balance plane access hole cover was leakmg steam through its gasket seal. With this change, bolting wm replaced with studs and cap nuts, and scalant wm injected to fill the void under and around the cover. De turbine casing was pcened around the cover to prevent sealant tirom escaping.

The peening will not affect the pressure retaining function of the cover due to the small localized area.

Also, the access cover is not part of an isolation buffer. Scalant migration is considered unlikely because of the scaling =*hmialogy, volume monitoring, and high pressure casing flow path. He leak repair will not a&ct the plant's response to an accident, nor modify the plant or operator response such that a new type of accident could be created. He leak repair will not create a new unanalyzed malfunction of safety related equipment and does not a&ct any safety related equipment. His change does not represent an unreviewed safety question.

CHANGE TITLE j

f Tempo 3 y Modification 1-97-06, High Pressure Turbine, Turbine Chest (East) Leak Repair CHANGE DESCRIPTION l

%e high pressure turbine outer casing cast end balance plane access hole cover was leaking steam through its gasket seal. With this change, bolting was replaced with studs and cap nuts, a:xt scalant was injected to l

fill the void under and around the cover. The turbine casing was peened arourd the cover to prevent l

sealant from escaping.

i The peenmg will not affect the pressure retaining function of the cover due to the small localized area.

Also, the access cover is not part of an isolation buffer. Sealant migration is considered unlikely because i

of the sealing methodology, vohune monitoring, and high pressure casing flow path. The leak repair will l

not affect the plant's response to an accident, nor modify the plant or operator response such that a new type of accident could be created. The leak repair will not create a new unanalyzed malfunction of safety related equipment and does not affect any safety related equipment. His change does not represent an unreviewed safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 26 of 40 CHANGE TITLE Temporary Modification 1-97-07, Leak Repair Clamp on 3" Swing Check Valve MS-81 CHANGE DESCRIPTION One of the hinge pin plugs on the three inch,600 pound swing check valve MS-81 was leaking steam past its threads. A clamp was bolted across the valve, and sealant was injected into the void created around the leaking plug.

He leak repair clamp is not used as an extension of the valve pressure boundary, but only as a container for the scalant. The threads of the leaking hinge pin plug create a labyrinth which prevents sealant ingress.

Failure of the seal would not incapacitate the Main Steam System. He leak repair will not affect the Main Steam System and a main steam line break has already been analyzed; however, this leak repair will not increase the likelihood of any analyzed accident. This change does not involve an unrevit J safety question.

CHANGE TITLE Temporary Modification 1-97-08, Leak Repair for Condensate Pump CHANGE DESCRIPTION Pressure indicator CN-105A is located at the discharge of condensate pump CN-P-1A. The %" line connecting it to the pump discharge was leaking condensate at the threaded joint to the pump discharge.

This joint was enclosed in a clamp device and the cavity created was filled with sealant.

Neither the condensate pump nor the pressure indication will be affected by this leak repair. Introduction of sealant material was controlled such that sealant leakage into the Condensate System would be highly unlikely. Failure of the %" pipe joint leak repair will not create a new type of accident or any new unanalyzed type of malfunction. The Condensate System is not a safety related system and does not interact with any safe shutdown equipment. His change does not involve an unreviewed safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 27 of 40 CHANGE TITLE Temporary Modification 1-97-09, Leak Repair to 1" Ball Valve BR-80 to Prevent Boric Acid Leak CHANGE DESCRIPTION Boric acid solution was leaking through the body to end piece flange joint seal of 1" ball valve BR-80, located in the primary grade water make-up line to boric acid hold tank BR-TK-7, A clamp device was installed to enclose BR-80, creating a cavity that was injected with a leak repair sealant.

The clamp will seal it in the closed position. The valve is a normally closed valve and an alternate source of primary grade makeup water to BR-TK-7 is available. BR-80 and the portion of the system in which it is located are not safety related, nor will the implementation of this modification affect any safety related equipment. The addition of the clamping device will not affect the associated equipment. The installation of this modification will not affect the ability to inject boric acid solution into the Reactor Coolant System, nor will it prevent the function of the Boron Recovery and Primary Makeup System He use of the sealant material was also evaluated and determined that it would not affect the system or any safe shutdown equipment. Therefore, this change does not represent an unresiewed safety question.

CHANGE TITL_F Temporary Modification 1-97-10. Install Leak Repair in Pipe to Elbow Weld CHANGE DESCRIPTION A 2" carbon steel pipe SLPD-70 of the Auxiliary Steam System had a condensate leak at an elbow-to-pipe joint in the vicinity of the AS-TK-1 receiver tank. The leaking joint was enclosed in an enclosure clamp and the clamp filled with scalant.

Neither the scalant injection process nor the as-left state of the pipe after its injection modify any plant response. A secondary system pipe break is already an analyzed condition, and this modification will not create any new accident scenarios. Failure of the related piping will not cause a malfunction of any safety related equipment nor interfere with its ability to perform during a design basis accident. He leak repair will be placed on only non-safety related portions of piping. The pipe and its system does not interact with safe shutdown equipment. This change does net represent an unreviewed safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiir. cats January 23,1997 - January 22,1998 Page 28 of 40 CHANGE TITLE Temporary Modification 1-97-12, Utilize Service Air to Mix Contents of Clarifier CHANGE DESCRIPTION As a result of this temporary modification, a %" pressure reducing valve and %" air hose was ennw~I from service air isolation valve SA-62 and routed to the clarifier (WT-FL-1). The NSA of SA-62 was then changed to open. 'Ihis change will permit using service air to mix the contents of the clarifier instead of the mechanical mixer, This temporary modification will not change the plant response to any accident, and a failure of this temporary modification will not cause any new accident. Also, complete failure of this modification would not increase the probability of loss of service air. This change will not affect the assumptions or consequences of any previously analyzed accidents. This change does not involve an unreviewed safety question.

CHANGE TITLE Temporary Modification 1-97-13, Drip Pan lastallation CHANGE DESCRIPTION l

As a result of this temporary modification, a stainless steel drip collector was fabricated for Safety l

Injection System relief valve RV-SI-894 and installed to catch boric acid drips and allow the drips to evaporate without contacting any carbon steel components.

There are no failure modes which can be an initiating event since the drip collector is seismically anchored.

j The drip collector has been bolted to the outlet flange of relief valve RV-SI-894. Installing the drip collector does not change the likelihood of a DBA; therefore, the possibility of an accident of a different type than evaluated in the UFSAR is not increased This change does not increase the consequences of a malfunction of equipment important to safety evaluated previously in the UFSAR. This temporary modification does not involve an unreviewed safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 -January 22,1998 Page 29 of 40 CHANGE TITLE Temporary Modification 1-97-14, Temporary Modification to FW P-1Bl/1B2 Coupling Guc ed CHANGE DESCRIPTION This temporary modification installed strips of clear plastic on both ends of the motor-to-motor coupling guard for the 'B' Main Feedwater Pump motors. His modification would deflect any oil that would be I

flung out by the shaft at the beanns housings. Oil leakage from the motor seals would be deflected to the skid, climinating oil residue on the nearby walkway.

This change did not affect operatmg or design parameters. Further, it does not impact any design basis accidents described in the UFSAR nor does it impact any safety systems Installing the adhesive strips has no effect on the probability of failure of the main feedwater system. The proposed change does not increase the probability of occurrence of a malfunction of equipment important to safety.

The consequences of a malfunction of equipment important to safety previously evaluated in the UFSAR are not increased. This change does not represent an unresiewed safety question.

CHANGE TITLE i

Temporary Modification 197-15, Temporary Bladder Air Supply For Dampers VS-D-40-1A, IB,

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CHANGE DESCRIPTION This temporary modification enn-M a nitrogen bottle (set to 60 psig) to the test connection valve of each Control Room ventilation damper. This provided a source of air to inflate the damper bladder while changing out the bladder's solenoid operating valve (SOV). This temporary modification enabled the SOV replacement to be perfonned with a ventilation configuration that did not result in the dampers being inoperable.

This change has no effect on the dampers' ability to perform their safety function of isolating the control room. De change has no effect on the probability of failure of the dampers. Further, it has no effect on the assumptions and radiological consequences of the accidents identified in the UFSAR. This change, therefore, does not represent an unreviewed safety question.

Beaver Valley Power S.

' i nit 1 Facility Changes, Tests, ano. apenments January 23,1997 - January 22,1998 Page 30 of 40 CHANGE TITLE Temporary Modification 1-97-16, Temporary Modification to Cooling Towec Pump House Ventilation Controls CHANGE DESCRIPTIOE his temporary modification involved bypassing the temperature controller for dampers associated with Cooling Tower Pump House fan VS-F-54B to keep the recirculation dampers closed and the intake dampers open. The modification was performed because the controller could not put out a full signal because of a small air leak on one of the air motors and the failure of the temperature sensor.

There is no safety related equipment associated with this change, and this change has no effect on the performance of safety systems. & temporary modification does not, therefore, increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the UFSAR. There are no design basis accidents that could be caused by this change. Based on this, the temporary modification will not increase the probability of occurrence of an accident previously evaluated in the UFSAR. This change does not represent an unreviewed safety question.

CHANGE TITLE Temporary Modification 1-97-17, Temporary Support of HCV-CH-389 and CH-130 Piping QtANGE DESCRIPTION A

e rary modification added supports adjacent to valve HCV-CH-389 on the non-safety related portion of -

M-130 line to meet the requirements set forth in Basis for Continued Operation (BCO) 1-97-2. The va..e nonnally directs Chemical and Volume Control System letdown flow to the Volume Control Tank.

One support was situated directly adjacent to valve HCV-CH-389 while the other support was located further downstream These supports were necessary to restore system operability.

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i A hilure of the line or the supports does not modify the plant response to the point where it can be considered a new type of accident. W existing small break LOCA analysis bounds a failure of the system. The plant res,xmse to a small break LOCA is not changed. There are no failure modes of equipment important to safety associated with the change that represents a new unanalyzed type of malfunction. The supports are designed such that they are qualified to maintain their integrity while ensuring the pipe is also supported to resist failure when exposed to these conditions. This temporary modification does not represent an unreviewed safety question.

Beaver Valley Pcwer Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 h e 31 of 40 3

CHANGE TITLE Temporary Modification 1-97-18, Install Blank Flange in Joint Downstream of ISA-15 CHANGE DESCRIPTION A temporary modification was installed on the station air supply lir.: to the Containment. This penetration is for station air service used only during refueling outages when the Cn=+Aa==t is open. A blank flange was iratalled on a mechanicaljoint downstream of a check valve to provide positive isolation during normal plant operations.

The system affected by this temporary modification is not important to safety. 'Ihe line involved supplies air to the Containment during refueling outages. 'Ihe temporary modification has no effect on the performance of safety systems and is installed on a system which is not in service durhg plant operations.

Further, it does not increase the probability of occerence of a malfunction of equipment important to safety.

Failure of this change cannot be an initiating event for a design basis accident. This change, therefore, does not represent an unreviewed safety question.

CHANGE TITLE Temporary Modification 1-97-19, Install Leak Repair for Valve SD-136 CHANGE DESCRIPTION A packmg scalant injection valve was installed into the stuffing box of valve SD-136 to stop a stem packing leak. Valve SD-136 is the inlet isolation valve for steam trap T-SD-60 it. the Main Turbine and Condenser Sy; tem. 'Ihe injected sealant was contamed within the stuffing box and performed a normal stem packing function without affectmg valve operation in its normally open position. However, the valve now cannot be op-rated to a closed position to isolate trap T-SD-60 from the Terry Turbine steam supply for maintenance, or to initiate trap bypass flow. Upstream valve SD-139 can, however, be used as the trap inlet isolation. The injection valve remains attached to SD-136 as a tempora y modification.

Valve SD-136 and steam trap T-SD-60 are not safety related so that failure of the SD-136 leak repair does not represent a new unanalyzed type of malfunction. Any resumed valve stem packing leakage is bounded by the existing DBA analyses. Failure of the leak repair does n% affect the SD-136 function in its a

normally open position. "Ihe structural integrity and function of SD 136 in its normally open pesuion are maintained, as well as for the connecting pipe and attached steam trap T-SD-60. 'Ihis change does not involve an unreviewed question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 32 of 40 CHANGE TITLE Temporary Modification 1-97-20, RCS Makeup From RWST CHANGE DESCRIPTION Valve AS-352 is a 4" normally open manual bolted bonnet gate valve and is the inlet isolation to the Boron Recovery Degasifier Steam Heater. His valve is located in the Unit 1 Primary Auxiliary Building at elevation 7?5' and performs a manual isolation function. It had a steam leak at the Ny to bonnet joint.

The valve body to bonnet joint was wire wrapped and 4 of the 8 bonnet nuts wei M. iced with cap nuts.

One stud near the leak will be replaced with a slo'ted stud to guarantee a sealant pathway to the leak.

j Sealant was injected through the cap nuts into the void created by the wire wrap to stop the leak.

This change will not adversely aiYect any safety related component or system since all design and performance criteria would continue to be met. The change would not increase the consequences of a",

accident evaluated previously in the UFSAR. He leak repair will not prevent the valve from operating.

This change would also not increase the probability of occurrence of an accident evaluated previously in the UFSAR. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE Temporary Modification 1-97-21, Addition of Sprinklers To Temporary Outage Structures / Trailers fHANGE DESCRIPTION A temporary fire protection system was installed to protect outage trailers and structures during the Unit 1 Twelfth Refueling Outage. The temporary sp:inkler protection system provided acceptable fire protection to protect plant structures and componunts by protectmg the temporary trailers and structures.

Dere are no safety systems that are affected by this temporary modification. This change enhances the Fire Protection System. The water source for the sprinklers is the Fire Protection System which is not i

safety related. The Fire Protection Water System does not contain any failure modes which can be an mitiating event for a design basis accident. He change does not represent an unreviewed safety question.

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6 Beaver Vclicy Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 33 of 40 CHANGE TITLE Temporary Modification 1-97-22, Links Radiological Access Tracking System CHANGE DESCRIPTION This temporary mocification provided cables and connections to link four additional Radiological Access Tracking System (RATS) readers to the RATS server. These reader stations are similar to the stations located in Unit I and Unit 2 which were installed under DCP-2160. System operation is unchanged with this temporary modification.

This temporary modification does not interface with any safety system. It will not alter the response of the plant during any design basis accident and could not create a new type of accident. No equipment important to safety is being modified. This modification provides electronic communication to four additional RATS reader stations via spare telephone cables and spare contamment penetration wiring. No new failure mode is associated with this change, and it is not an unreviewed safety question.

l GLA_NGE TITLE Temporary Modification 1-97-29, Installation of Plugs in the Unit 1 Cooling Tower Discharge Drain f

Lines CHANGE DESCRIPTION l

The Circulating Water piping from the Cooling Tower to the Main Unit Condenser has 10" drain lines which were leaking. Both lines are located approximately 20 to 40 feet underground. These lines lead from the Circulating Water lines to a alve pit. This temporary modification installed 10" plugs on these two lines to prevent water leakage from the system.

The Circo' Ec Water System is not safety related and is independent of emergency core cooling I

requiremew. A failure of the plug is not probable since it meets the design parameters of the system. In the event of a failure, no site flooding hazard is presented, due to the location of these lines. Also, it was determined that a failed or loose plug would not have any effect on operating equipment. Since the modification meets the system design parameters, the probability of occurrence cf a turbine trip DBA is not l

increased and there is no unreviewed safety question.

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c Beaver Vt.lley Power Station Unit 1 Facility Changes, Tests, and Experiments knuary 23,1997 - January 22,1998 Page 34 of 40 CHANGE TITLE Temporary Modification 1-97-30, Temporary Modification for FW-P-1B1 and 1B2 Outer Oil Seals CHANGE DESCRIPTION He existing design c. :he 13 Main Feedwater Pump motor beanng seals permits excess oilleakage outside of the motor housing. ite +emporary modification modified the outer oil seal to redirect the dmmage back to the oil sump.

Here are no safety systems affected by this change since the pump is located in a non-safety related l

portion of the Feedwater System. Directmg the seal drain to the oil sump does not affect the probability of a failure of the system nor create a new accident. The installation of this modification does not change the probability of occurrence of any DBA. A loss of the modified pump and subsequent noss of feedwater flow remains bounded by UFSAR analyses; therefore, the chaage does not represent a new unanalyzed type of malfunction. This change does not involve an unreviewed safety question.

CHANGE TITLE Temporary Modification 1-97-31, Temporary Modification for FW-P-1A1 and 1A2 Bearing Housings CHANGE DESCRIPTION his temporary modification enkmW the ventmg capability of the bearing housings on ese 1A Main Feedwater Pumps by the addition of a breather to each bearing housing where currently a pipe plug is installed. His was done to reduce oil leakage by eliminating the air flow through the oil drain piping.

There are no safety systems affected by this change since the pump is located in a non-safety related l

portion of the Feedwater System. Adding breathers to the motor beanng housings does not affect the j

probability of a failure of the system or create a new accident. The installation of this modification does l

not change the probability of occurrence of any DBA. A loss of the modified pump and subsequent loss of l

feedwater flow remains bounded by UFSAR analyses; therefore, the change does not represent a new unanalyzed type of malfunction. His change does not involve an unreviewed safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 l

Page 35 of 40 CHANGE TITLE l

Temporary Modification 1-97-32, MagnJudic Gage Addition & Setpoint Change CHANGE DESCRIPTION i

l Temporary Modification 1-97-32 and the correspondmg procedure changes allowed Ucit I to consider all three of the emergency ventilation subsystems operable as defined in BV-1 Technical Specification l

3/4.7.7.1, following operational acceptance of DCP 2306. He three emergency ventilation subsystems are comprised of the Unit 2 "A" subsystem, Unit 2 "B" subsystem, and the (sole) Unit I subsystem. The temporary modification revised the setpoint for the Unit 2 Emergency Air low flow alarm, and added a temporary control room AP gauge.

There is no increase in the probability of failure of the Unit 1 emergency ventilation since at least two separate and redundant subsystems are available with adequate ability to detect an active failure in the primary subsystems. His temporary modification does not affect the performance requirements of the control room habitability system, nor does it increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the UFSAR. This change does not represent an unreviewed safety question.

CHANGE TITLE UFSAR Change To Update Containment Isolation Valve (CIV) Arrangements Tables CHANGE DESCRIPTION l

his item documented several revisions to Unit 1 UFSAR Tables 5.3-1 and 5.3-1A made by UFSAR Change Notices 1-15-11 through 1-15-19. He revi-ions documented the current inside and outside power supply arrangement used by the associated inside and outside CIVs, reflected the current CIV positions, revised wording to be consistent with the Licensing Requirements Manual, made changes to be consistent with the GDC 57 exemption, removed valves from this table not credited with a contamment isolation i

function, and included editorial changes for consistency within the UFSAR.

He UFSAR revisions were editorial in nature. Hey did not impact systems, structures, or components important to safety. Further, they did not affect any design basis accidents discussed in the safety analysis i

report. He changes made to the CIV tables reflect the current CIV positions and make the UFSAR consistent with other design basis hments. He changes documented by the UFSAR change requests do not represent an unreviewed safety question.

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Facility Changes, Tests, and Experiments l

January 23,1997 - January 22,1998 Page 36 of 40 1

CHANGE TITLE I

UFSAR Revision, Refueling Procedure Change For Vessel Stud Tensioning l

l CHANGE DESCRIPTION The refueling procedure was revised to tension fewer sets of studs by optimization of the tensioning pressures to realize a more uniform initial tension than that which was achieved with the existing i

procedure. A UFSAR revision, Change Notice 1-15-41, was initiated to reflect this procedural change.

Changing the procedure on how the vessel studs are tensioned and detensioned will not create the possibility of a new design basis accident. The tensioning procedures and elongation measurements provided by the vendor utilize the same minimum preloads as current procedures with the same minimum forces applied.

This change will not affect the assumptions or the radiological consequences of design basis accidents discussed in the UFSAR. The revised procedure will not result in an increase in the probability of failure ef safety systems. This change does not represent an unreviewed safety question.

CHANGE TITLE UFSAR Revision, Review of Scoping Dose Calculation Results Against UFSAR Listed Bounding Dose Values CHANGE DESCRIPTION nis item documented the re-evaluation of BVPS control room dose calculations which resulted from issues concerning control room habitability. The control room re-evaluation only addressed design basis accidents (DBA) and their associated control room doses which credited isolation of the control room during the DBA since the issue was limited to control room emergency pressurization and filtration system fan flow I

rate. UFSAR pages that describe analysis assumptions will be revised via UFSAR Change Notice l

l-15-67.

l The revised dose calculation results show that calculated control room doses remain less than the values currently listed in the UFSAR. Thus, there has been no reduction in the margin of safety with respect to j

control room dose. The changes do not increase the probability of the occurrence of a malfunction of equipment. They more accurately show that the design for the current control room pressurization and filtration system continues to operate to meet the design basis that the control room is prosided adequate radiation protection. This item does not represent an unreviewed safety question.

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j Braver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 37 of 40 CHANGE TITLE UFSAR Revision, Revise Frequency for Testing SI Auto Transfer to Recirculation CHANGE DESCRIPTION UFSAR Sections 7.3.2.1.5,1.3.3.22, and 7.2.2 were revised to address test frequency issues concerning the automatic transfer from safety injection to recirculation feature of the Safety Injection System. These revisions clarify that the actuators for this auto transfer feature are not tested at power. This made the UFSAR consistent with Technical Specification 4.5.2.f.2. which requires the surveillance to be conducted on a refueling frequency, rather than at power. De UFSAR revisions were documented in UFSAR Change Notice 1-15-68.

This change affects the automatic changeover from safety injection to recirculation feature for the Safety Injection System. It only affects the testing frequency and does not affect the probability of failure of safety systems No plant design changes are being made and no design basis accidents are affected by this change. His change was made in conformance with the test frequency requirements of Safety Guide 22. It does not represent an unreviewed safety question.

CHANGE TITLE UFSAR Revision Changes to Reflect Current Operation of Solid Waste Handling Program

~ CHANGE DESCRIPTION His item documented minor changes and enhanc-ents to the wording in UFSAR Section 11 to more clearly reflect the current operation of the solid wast: handling program These changes resulted from inconsistencies noted during a program self-assessment and during an NRC inspection. The wording revisions to the UFSAR are contained in UFSAR Change Notice 1-15-71.

De performance of safety systems is not affected by the editorial wording changes. No physical modification of the system occurred. Solid wastes will continue to be processed in accordance with the Operating License and Process Control Program. There are no design basis accidents that were affected by these editorial cht.nges. Descriptive wording changes to the UFSAR could not be an initiating event or create any new failure modes ne editorial changes to the UFSAR do not represent an unresiewed safety question.

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,1 Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 38 of 40 CHANGE TITLE UFSAR Revision, Changes to Reflect Current Operation of Liquid and Gaseous Waste Handling Program CHANGE DESCRIPTION This item documerged minor changes to the Unit 1 Liquid and Gaseous Waste programs described in UFSAR Section 11. The changes were made to more clearly reflect the current operation of the liquid and gaseous waste handling program. Some of these UFSAR changes were the result of recent procedure and Technical Specification changes. He revisions to the UFSAR are contained in UFSAR Change Notice 1-15-72.

The performance of safety systems is not affected by these editorial wording changes. No physical modification of the system occurred. Liquid and gaseous waste will continue to be processed in accordance with the Operating License and the Offsite Dose Calculation Manual. There are no design basis accidents that were affected by these editorial changes. Descriptive wording changes to the UFSAR could not be an initiating event or create any new failure modes. These changes to the UFSAR do not represent an unreviewed safety question.

CHANGE TITLE

' UFSAR Revision, Editorial Change To UFSAR To Clarify Emergency Diesel Generator Design CHANGE DESCRIPTION This item documented a wording change to UFSAR Section 8 to clarify the emergency diesel generator (EDG) design limitations while in the test mode. The wording revision states that the EDG is incapable of responding to an emergency signal while in the test mode. The revised wording to the UFSAR is contained in UFSAR Change Notice 1-15-82.

De performance of safety.,ystems is not affected by this wording change. No physical changes were made to the EDG as a result of this UFSAR change. There are no systems that are affected by this change.

Here are no design basis accidents that were affected by this change. A descriptive wording change to the UFSAR could not be an initiating event or create any new failure modes and does not represent an unreviewed safety question.

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.I Facility Changes, Tests, and Experiments i

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January 23,1997 - January 22,1998 Page 39 of 40 CHANGE TITLE UFSAR Revision,480 V Bus Tie Breakers l

l CHANGE DESCRIPTION This item documented a wording change to UFSAR Section 8 regarding the 480V substations. The change revising the wording in Section 8.4.3 was intended to clarify statements about the closing of the 480 V bus tie breakers. He revised wording is contained in UFSAR Change Notice 1-15-85.

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nis text change clarifies when the tie breakers are used and why it is acceptable to tie the busses together temporarily. The perform >nce of safety systems is not affected by this wording change. No physical changes were made as a result of this UFSAR change. His wording change has no effect on the probability of failure of systems important to safety and does not represent an unreviewed safety question.

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UFSAR Revision, Breaker Alignment Verification CHANGE DESCRIPTION As a result of a procedure revision regarding breaker alignment verification, the applicable section of the UFSAR, Section 8 was revised. The change involved the allowance of an empty breaker cubicle in the load center, and defining the correct position for locking a breaker. The UFSAR Change Notice 1-15-86 will ensure consistency between the documents regarding the performance of weekly breaker alignment verification.

He performance of safety systems will remain unchanged as a result of the revision to the UFSAR. The equipment will still continue to operate as designed. Having a 480 V load center breaker in the disconnect position or having an empty cubicle in the load center will have no effect on the performance of safety systems. The UFSAR change was required so the 480 V swing breakers can be positioned as required to perform the breaker alignment verification procedure. This change does not represent an unreviewed safety question.

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Beaver Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1997 - January 22,1998 Page 40 of 40 CHANGE TITLE UFSAR Revision, RCCA Misalignment CHANGE DESCRIPTION i

A revision was made to UFSAR Section 14 to delete the requirement that core exit thermocouples be used to determine the alignment of control rods with inoperable rod position indicators. Incore movable detectors will be used in accordance with Technical Specification 3.1.3.2. Core exit thermocouples will be used as a back-up to the movable incore detectors for gross rod misaligiunent (i.e., dropped rod). This update was included as UFSAR Change Notice 1-15-91.

4 There is no effect on the performance of safety systems. The UFSAR was resised to reflect information contained in Technical Specification 3.1.3.2.

He incore movable detectors are more accurate in determining the relative position of control rods than the core exit thermocouples. His change does not alter the assumptions or radiological consequences of a control rod misalignment No design basis accident could be initiated by this change since it does not affect actual rod movement or otherwise involve any system that has been identified as having a potential for a design basis accident initiation. This item does not represent an unreviewed safety question.

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