ML20249C339

BVPS Unit 2 Facility Changes,Tests & Experiments for Period 961101-971031

ML20249C339
Person / Time
Site:	Beaver Valley
Issue date:	10/31/1997
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20249C338	List: L-98-122, Forwards BVPS Unit 2 Facility Changes,Tests & Experiments for Period 961101-971031, Per 10CFR50.59.Determination of Changes,Discussed ML20249C339
References
NUDOCS 9806290082
Download: ML20249C339 (65)

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• Br.cver Vril:y Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Table of Contents i i

Ilun P. age

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DCP 857 Addition of ATWS Mitigating System Actuation Circuitry (AMSAC).......... ....1 l DCP 900 Addition of Leak Test Panels to Containment Air Lock and Equipment Hatch.............................................................................................................................1 i DCP 1121 Abandonment of Indicators and Annunciators on Chemical Feed Panel..... 2 DCP 1469 Deletion of RTD Bypass Manifold ............................................................... 2 l DCP 1633 Deletion of Auto Start Signal to Motor-Driven AFW Pumps from Turbine-D ri ven AF W P ump . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 DCP 2025 Addition of Steam Driven Auxiliary Feedwater Pump SI Start Signal ..... . .. 3 l DCP 2040 Retirement of Alternate Miniflow Valves for HHSI/ Charging........................ 4 DCP 2131 Addition of instrumentation for Indication of Containment Sump Pumps TotalFlow......................................................................................................................4 DCP 2152 Addition of Chemical Injection System......................................................... 5 DCP 2156 Diesel Generator Starting Air System Moisture Removal Modifications...... 5 DCP 2164 Turbine Plant Sample Conditioning Modifications ....................................... 6 DCP 2177 Service Water Pump Seal and Filter Water Pipe Material Upgrade............ 6 DCP 2196 Diesel Generator Temperature Indicator Replacement ............................... 7 DCP 2208 Relief Valves for Steam Generator Blowdown Demineralizers................... 7 DCP 2238 Sewage Treatment Plant Replacement................... ................................ .8 DCP 2240 Thermo-Lag Insulation Upgrade for Electrical Conduits........... . ... ............ 8 DCP 2306 Control Room Emergency Air Filtration System Upgrades....................... .. 9 TER 5115, Lengths of Fire Hose Within Turbine Building ...................................... ... .. 9 TER 9349, Removal of Flow Indicator 2GWS-FIT 103 .................................................10 TER 9433 Remove 2 MSS-ARV-100 and 2 MSS-RV-101.............................................10 TER 9721, Replace Unit 2 Degraded Grid Relays, Rev.1...........................................11 w

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BIcyrr Vcil:y Power St tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Table of Contents T.itle Eage TER 10072, Retire Fire Water Booster Pump and Motor 2 FPW-36............................11 1

TER 10127, Retirement of Primary Demerator.............................................................. 12 TER 10322, Removal of Blind Section of Spectacle Flange on Downstream of Relief Valves........................................................................................................................12 TER 10331, Replacement of Drain Lines from Carbon Steel Pipe to Stainless Steel Tubing for 2SAS-C21 A, B, and 2SAS-C22.......... .......... . . ... .. .... ... . ... .... .... ....... . ...... ........ 13 TER 10349, Replacement of 2SAS-221, 222, 223, and 224........................................13 TER 10361, Auxiliary Boiler Propane Supply............................................................... 14 TER 10534, Retirement in Place of Unit 2 Fault Recorder PNL-2FAL-REC ................14 TER 10543, Loose Parts Monitoring System................................................................ 15 TER 10599, Spent Resin Hold Tank Low Level Trip Bypass ..... ................................15 TER 10652, Retirement in Place of 2TMS-PT215........................................................ 16 TER 10664, BV-2 Cycle 7 Reactor Core Reload Analysis ...................... ... ................16 TER 10716, Capping of Seal injection and Leakage Lines to Heater Drain Pumps ....17 TER 10736, Unit 2 UFSAR Appendix 9.5A and FPSSR Updates ................................17 TER 10771, Removal of 2RCS-624 and 2RCSFG200 and Piping...............................18 TER 10772, Unit 2 UFSAR Appendix 9.5A and FPSSR Update for PORV......... ........18 TER 10782, Correction of Discrepancy for 2RCS*SOV200A and B.............................19 I

TER 10809, Removal of Valve Stem Leakoff for Valve 2 MSS-FCV100A......... ....... ...19 TER 10840, intake Structure Pump Cubicles Exhaust Vents..... . ............................... 20 TER 10890, Turbine Lube Oil Reservoir Fire Protection System Corrections ............. 20 TER 10904, Miscellaneous Modifications to Support Security............................. ....... 21 TER 11078, Evaluate Gagging 2CNM-RV109,100,114,115, when isolation Valve Closed.........................................................................~......~....~.~...--..~.~.-21 i L---_------___--------_-----. .- - - _ - - - - - - - - - -- - - -- J

t B:cv:r VallIy Power Strtion Unit 2

. Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Table of Contents Tde P_ age TER 11245, Vital Bus Distribution Panel Drawing Discrepancies..... . .................. ..... 22 TER 11275, QA Classification for Gaseous Waste Disposal..................... ................. 22 TER 11402, Fire Hazards Analysis Records Update .. ...... ..................... ............ ...... 23 TER 11403, Fire Area CV-6 Thermo-Lag Thickness Evaluation... ............................ . 23 TER 11691, EDG Load Step 2 Time Delay Evaluation ................................. ..... ........ 24 Deletion of EDG Load Values from UFSAR Table 8.3-3........ .. .................................. 24 Revise Minimum Service Water Flow for Charging Pump Lubricating Oil Coolers...... 25 Resolution of S S F E Item 97-01 -A02-01 . .... .... . . .. .. . ... .. . . ... ..... .... . .. ... ... . .. . . ... .. . . .. .. . .. . .. . .. 25 Change of Second Level Undervoltage Time Delay Setting in UFSAR ....................... 26 Correction of Emergency Diesel Generator Loading in UFSAR Table 8.3-3............... 26 Updated Final Safety Analysis Report, Correction of UFSAR Table 8.3-3................... 27 )

l Updated Final Safety Analysis Report Section 7.2,15.3.2, IEEE-279 Qualification for Antici patory Tri ps . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .)

Updated Final Safety Analysis Report Section 9.2.1.1.2, Service Water System De scri ption . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Licensing Requirements Manual Table 5.1-1 and Updated Final Safety Analysis

' Report Table 6S-60, Containment Penetrations................................... ...................... 30 Updated Final Safaty Analysis Report Table 6.2-60, Revise Overpressure Protection

' C ol umn I nformation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

l Updated Final Safety Analysis Report Section 11.5/12.5, Radiation Clearance / l Health Physics P rogram . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31l Updated Final Safety Analysis Report Section 1 3.1. 2. 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 l Updated Final Safety Analysis Report Figure 9.2-10, Change NSA of 2CCP-28 from O pen t o C l o sed . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2OM-26-3.B.6,3.C, Change NSA of [2GSS-FN270A, B] and Associated Flowpath ... 33

9 B:cv:r Vell::y Power Stition Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Table of Contents Title .P_ age Licensing Requirements Manual, Table 5.1-1, Updated Final Safety Analysis Report Table 6.2-60, Change Penetrations 14 and 25 MOVs to Remain Locked Shut........... 34 Updated Final Safety Analysis Report Table 8.3-3, Deletion of Load Values in U F S AR Ta ble 8. 3-3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34 Updated Final Safety Analysis Report Table 1.8-1, USNRC Regulatory Guides......... 35 Delete Incorrect Statement in the UFSAR for 4KV Transfer Switches ......................... 35 Updated Final Safety Analysis Report Change for CARF 97 0196-02 . . . . . . . . . . . . . . . . . . . . . . . . . 36 Updated Final Safety Analysis Report Section 8.3.1.1.8 Change................................ 36 2OM-35.3.B.1 and Updated Final Safety Analysis Report 10.2-10, Valve List -

2GMH and UFSAR Figure 10.2-10, respectively......... . . . .. ............................37 Clearances 153343 and 153348, Isolation of Components No Longer in Use........ .... 37

" Retirement in-Place" of 2WWS-TK24 and 2WWS-TK25............................................ 38 10080-RM-422A-1 VCN - 2CNM-620, 636,1026 NSA Change, VOND Main C ondensate S ystem . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 38 Change NSA From OPEN to CLOSE for Containment isolation Valves 2SSR-SOV128A1 & 2,129A1 & 2, and 2SSR-AOV102A1 & A2 ............................................ 39 Updated Final Safety Analysis Report Figure 9.3-11, Post Accident Sampling S y stem , BVP S U n it N o. 2 . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .. . . .. . 3 9 1/2 CMP-75-MONITOR-11, Connecting Monitoring Equipment to Operating Equipment 1/2 CMP-75-MONITOR-11 Procedure Change for Power Monitoring Test Equipment.. 40 Updated Final Safety Analysis Report Change Request on Figure 9.5-6 for 2FPD-AOV202A/B............................................................................................................40 2 TOP-96-11, RCS Head Vent SOV Leak Test . .... ... .......... ............... .............. .... .. 41 j' Unit 1/2 Updated Final Safety Analysis Report Section 11.5/12.5, Personnel Radiation Protection / Health Physics Program........ ........ .... ....... .......... .............. .... 41 2 TOP-97-03, Aligning Temporary Flowpath for Service Water Out of CCS Heat Exchangers.................................................................................................................42

Bxvtr Vcll:y Power Stition Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Table of Contents Iillt ' ESQR 2 TOP-97-04, Operating the [2CWS-P21D] Motor Uncoupled for PMT........................ 42 BVPS-2 Updated Final Safety Analysis Report Sections 1.2.2, 2.1.1.2, 2.1.2.1, Figure 2.1-2..............................................................................................................43 2OM-45.3.D.3, Power Supply and Control Switch List Electric Heat Tracing System.. 43 2 TOP-97-05, Returning Water from the BR Degasifier 21B to the Reactor Coolant System........................................................................................................................44 2GNS-1 NSA Shut, Clearance #153285-2GNS-1 Change NSA Position from Open toShut..........................................................................................................................44 Temporary Modification, install Bronze Swing Check Valve for [2iAC-7)..................... 45 Temporary Modification, Filtered Water Supply Line Condition................................... 45 Temporary Modification, Isolation of Cell #14 from Station Battery 2-1.............. ........ 46 Temporary Modification of 2RCS-P21 A Seal Pot High Level Alarm Indication, Annunciator A2-5D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Leak Repair of Cross Under Piping Manway Flange Gasket....................................... 47 Temporary Modification Installation of 2CHS-FT154A................................................. 47 Temporary Modification - Radiation Monitor 2 MSS-DAU101 A/B/C EMI Modifications .48 Temporary Modification - Block Drain Valves .............................................................. 48 Temporary Modification - Slade Packing in the Condenser Tube Cleaning System.... 49 l l

On Line Leak Repair of 2B DG-463 ... . .. . .... .... . ............... ... ...... ......... ....... . .. .... .............. 49  :

' 2OM-9.4.F - Draining a Recirc Spray Pump Casing or Pump Pit................................. 50 Temporary Modification - Installation of Modified AIM 07 RTD Module in RK-2 CMP-DIN 8............................................................................... .............................50 i

Temporary Modification - Leak Repair of 2HDH-TK22A Manway Flange Gasket....... 51 j Temporary Modification - Leak Repair of 2FWS-H22B Test Connection..... ..... ......... 51 Temporary Modification - Leak Repair of Steam Supply Valve 2 MSS-FCV100A......... 52

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B:sver Vall:y Power St:. tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Table of Contents Title _P_ age

! Temporary Modification - Leak Repair of 2RCS424.... ............................ .................. 52 l Temporary Modification - Blind Flange Installation for 2HVC-CND248..... ................. 53 l

Temporary Modification - Steam Generator Blowdown Filters..................................... 53 20M-53A.1, BV-2 Emergency Operating Procedures (OMCNs)................ ............... 54 EM 114926, Removal of Fire Door [CV47-1] During Outage Activities....................... 54 i

Temporary Modification, install Stainless Steel Swing Check Valve at [21AC-7].......... 55 Temporary Modification, Install Bronze Swing Check Valve for [21AC-7]..................... 56 l 2 TOP-97-06, Flushing Service Water Side of [2CHS*E258] Charging Pump Lube Oil Cooler Supply and Return Low Point Piping........................................................... 57 Temporary Modification - Turbine Governor Valve No. 4 (2TMS-GV4) Valve Stem and Coupling Anti-rotation Collar . . .. . . ....... .. ....... ... . .... . . ...... .. . .. ...... ... .. . . . ........ . ....... .... . . 58 Temporary Modification - Digital Rod Position Indicators F6 and F8 Train l

C orrection Modification . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Disconnect Category 11 Equipment - Remove from Service 2 MSS-PR475....... ........... 59 i

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Braver Vclicy Pow:r Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 1 of 59 DESIGN CHANGES CHANGE TITLE DCP 857 Addition of ATWS Mitigating System Actuation Circuitry (AMSAC)

CHANGE DESCRIPTION DCP 857 was implemented to provide a backup system diverse and independent from the Reactor Protection System which would initiate a turbine trip, and initiate auxiliary feedwater flow. This change was initiated to conform to 10 CFR 50.62 requirements.

This change does not create any new accidents or malfunctions and does not affect the operation of any existing protection systems. This change is considered safe and, therefore, does not represent an unreviewed safety question.

CHANGE TITLE DCP 900 Addition of Leak Test Panels to Containment Air Lock and Equipment Hatch CHANGE DESCRIPTION DCP 900 was implemented to add two seismically mounted test stands, each consisting of instrumentation and associated tubing and valves, near the respective containment penetration. This change was implemented to facilitate requisite periodic leak testing of the doors in accordance with 10 CFR 50, Appendix J.

There is no change in the design or operation of the containment resulting from the addition of these Seismic Category ll test panels. No design basis accident scenarios are impacted by this change. Therefore, this change does not represent an unreviewed safety question.

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- Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 2 of 59 1 CHANGE TITLE {

1 DCP 1121 Abandonment of Indicators and Annunciators on Chemical Feed Panel CHANGE DESCRIPTION ,

f DCP 1121 abandoned five indicators and their associated annunciator inputs from the chemical l feed panel. This change was implemented due to unnecessary duplicate supervisory instrumentation resulting in additional administrative and maintenance burdens on Chemistry j Operations. Changes were verified to comply with NUREG 0700.

The Turt>ine Plant Sample system performs no safety related functions. 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.

CHANGE TITLE DCP 1469 Deletion of RTD Bypass Manifold CHANGE DESCRIPTION DCP 1469 was implemented to delete the RTD Bypass manifold piping and add new RTDs in  !

thermowells as an improved means to measure reactor coolant temperatures. The result of  !

these changes was reduced radiation exposure in the reactor coolant pump cubicles, new RTDs which meet Technical Specif; cation requirements for response time, and elimination of forced outages as a result of maintenance and operability problems associated with the RTD bypass. .

l The possibility of an accident of a different type other than those previously evaluated is not  ;

created as a result of this change. The possibility of a malfunction of equipment important to i safety of a different type than previously evaluated is not created as a result of this change. !

See also Westinghouse WCAP 12478. Therefore, this change does not represent an unreviewed safety question.

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. Be:ver Vciley Power Strtion Unit 2 i Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 3 of 59 I CHANGE TITLE DCP 1633 Deletion of Auto Start Signal to Motor-Driven AFW Pumps from Turbine-Driven AFW Pump.

CHANGE DESCRIPTION DCP 1633 removed the auto start signal to the motor driven Auxiliary Feedwater pumps upon failure of the Turbine Driven Auxiliary Feedwater Pump to achieve 500 psig discharge pressure within 10 seconds. The effect of this change is that the motor driven pumps do not start automatically on failure of the turbine driven pump, but require a Safety injection (SI) signal or 2 steam generator low-low level signals. Technical Specification Amendment #6 removed the requiremord for this auto start.

The proposed change will not increase the probability of occurrence nor increase the consequences of a malfunction of equipment important to safety. The proposed activity will j not create the possibility of an accident or a malfunction of equipment important to safety of a 1 different type than any evaluated previously in the UFSAR. There are no new failure modes of the Auxiliary Feedwater system and therefore no new unanalyzed accidents. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE DCP 2025 Addition of Steam Driven Auxiliary Feedwater Pump SI Start Signal l

l CHANGE DESCRIPTION DCP 2025 was implemented to add a start signal for the steam driven auxiliary feedwater i pump on a SIS signal. This is consistent with the Westinghouse small break LOCA analysis. J The UFSAR small break LOCA analysis is based on auxiliary feedwater flow from one motor driven pump and the steam driven pump. None of the identified failure modes associated with this change represent a new unanalyzed type of malfunction. Therefore, this change does not represent an unreviewed safety question, i

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Be::v:r Vill:y Power St: tion Unit 2 Facility Changes, Tests, and Experiments l

November 1,1996 - October 31,1997 Page 4 of 59 CHANGE TITLE DCP 2040 Retirement of Alternate Miniflow Valves for HHSI/ Charging CHANGE DESCRIPTION l

DCP 2040 was implemented to abandon the attemate miniflow valves in-place. Altemate miniflow was not required since the valves did not, and were not required to close on a SIS signal. Safety injection bypass flow rates were evaluated and found to be acceptable.

The removal from service of the attemate miniflow valves does not create any new failure modes which could be initiating events. The required Si flow is maintained and pump damage due to runout has been addressed. There is no impact on the assumptions and radiological consequences of any accident. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE DCP 2131 Addition of instrumentation for Indication of Containment Sump Pumps Total Flow CHANGE DESCRIPTION DCP 2131 added remote indication of total containment sump pump flow. The purpose of this change was to reduce operator exposure to high radiation levels particularly during performance of various survelliance requirements for the containment sump pumps.

There are no new failure modes which would increase the probability of failure in the assodated instrument loop introduced by this change. This is a non-safety related system and sincts the instrumentation is not relied upon for post accident monitoring, there are no effects on 'h9 postulated accident assumptions. Therefore, this change does not represent an unreviewed safety question.

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• B=v r Vall:y Power Station Unit 2

_ Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 5 of 59 CHANGE TITLE DCP 2152 Addition of Chemical injection System CHANGE DESCRIPTION DCP 2152 installed a Chemical injection System in the intake Structure, which is common to both units. It enables injection of chemicals for treatment of safety related piping in Unit 1 Reactor Plant River Water, and Unit 2 Service Water System. This provides treatment to essentially all piping, and pump casings to inhibit fouling and corrosion mechanisms caused by materials entrained in the river water supply to these systems.

No relevant accidents were identified for which this new Chemical injection System can be an initiating, or mitigating factor. No increase in probability or consequences of a credible failure is introduced with this change. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE l DCP 2156 Diesel Generator Starting Air System Moisture Removal Modifications CHANGE DESCRIPTION DCP 2156 installed a moisture trap with isolation valve and strainer in the common discharge header of the starting air compressors supp!ying each diesel generator. This modification also reconfigure discharge piping resulting in less rust forming in the piping upstream of the air f drying components and more reliable operation of the air compressor discharge check valves due to less condensate formation.

l This change affects the non-safety related portion of the D/G Starting Air system and the identified failure modes are not impacted. There is no impact on the assumptions or radiological consequences of the accidents identified. Therefore, this change does not  !

represent an unreviewed safety question. l l

B= var Vcil:y Power St tion Unit 2 J Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 l Page 6 of 59 I

I CHANGE TITLE DCP 2164 Turbine Plant Sample Conditioning Modifications CHANGE DESCRIPTION DCP 2164 was implemented to resolve sample coolers temperature switches, associated relays, and solenoid valves malfunctions. Existing pressure reducing valves were upgraded facilitating the removal of upstream restriction tubing and filters. A new bypass line was installed which was directed to the recovery header and on to the Aux. Steam Condensate Receiver.

This change applies to non-safety related equipment and there are no additional failtre modes associated. The change does not affect any of the parameters or systems that couid alter the i causes, assumptions, or consequences of an accident and does not affect the probability of occurrence of a design basis accident. Therefore, this change does not represent an  ;

unreviewed safety question. j i

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CHANGE TITLE DCP 2177 Service Water Pump Seal and Filter Water Pipe Material Upgrade CHANGE DESCRIPTION DCP 2177 replaced the Seal and Filtered Water lines to each Service Water Pump which exhibited leakage due to degradation from pipe wall thinning and line obstructions from corrosion products causing flow restrictions. This modification replaced the existing carbon steel pipe supplying the seal and filtered water with stainless steel alloy pipe, and replaced the carbon steel valves with stainless steel ball valves. Pipe flanges were added to allow additional access for mechanical cleaning of the pipe intemally.

This modification and its associated failure modes have no impact on the accident analyses for ,

the Service Water system since the installation and testing conform to the original design.

Therefore, this change does not represent an unreviewed safety question.

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Brv:r Vall:;y Power St-tion Unit 2 Facility Changes, Tests, and Experiments i November 1,1996 - October 31,1997 Page 7 of 59 CHANGE TITLE DCP 2196 Diesel Generator Temperature Indicator Replacement CHANGE DESCRIPTION DCP 2196 replaced the No. 2 Emergency Diesel Generator (EDG) intercooler Jacket water inlet and outlet duplex temperature indicator with two separate single indicators. This modification was implemented due to vendor recommendation and because the original indicator is no longer manufactured.

The failures associated with these temperature indicators are passive, (i.e., no breach of Jacket water system) and the diesel generator can function without them. This modification haa no impact on the results of any accident analyses or their conclusions. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE DCP 2208 Relief Valves for Steam Generator Blowdown Demineralizers CHANGE DESCRIPTION DCP 2208 installed thermal relief valves and associated discharge piping for the Steam Generator Blowdown Domineralizers. The domineralizers were originally a temporary skid mounted type, that are now considered as permanent plant equipment. The relief valves were required to be installed to conform to State of Pennsylvania codes for qualified pressure vessels.

i The Steam Generator Blowdown System is non-safety related and non-seismic. Also, a blowdown piping failure does not initiate nor impact liquid-containing tank failures considered in accident analyses for other plant areas. Therefore, this change does not represent an I unreviewed safety question.

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B :vtr Vdby Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 8 of 59 CHANGE TITLE DCP 2238 Sewage Treatment Plant Replacement CHANGE DESCRIPTION DCP 2238 installed a replacement Sewage Treatment Plant (STP) and included new equipment (valves, pipelines, timers) and several new operating features, due to physical deterioration of the original BVPS-2 STP. The new equipment was not described in the UFSAR but the UFSAR incorrectly implied that all collected (Unit 2) waste is conveyed to the BVPS-1 STP, when, in fact, only a portion of the Unit 2 sanitary waste is conveyed to the BVPS-1 STP.

No safety-related systems or systems important to safety are impacted by this change. There are no new credible failure modes introduced with this change. The existing accident scenarios are not challenged as a result of this change. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE DCP 2240 Thermo-Lag insulation Upgrade for Electrical Conduits CHANGE DESCRIPTION DCP 2240 installed additional fire proofing to various electncal conduits to achieve a 1-hour rating required for post-fire Safe Shutdown circuits. This change was a result of industry testing which determined that some applications of Thermo-Lag insulation, originally rated as

, 1-hour barriers, failed to provide adequate protection. '

i As a result of this change, previously identified design basis events are not affected and no new failure modes have been identified which could be initiating events. The performance of i safety-related systems is not impacted because the passive fire barriers will perform their intended safety function. Therefore, this change does not represent an unreviewed safety question.

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B :ver Vcil y Power Stction Unit 2 Facility Changes, Tests, and Experiments  ;

November 1,1996 - October 31,1997 Page 9 of 59  ;

Cl4ANGE TITLE DCP 2306 Control Room Emergency Air Filtration System Upgrades

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CHANGE DESCRIPTION DCP 2306 was implemented to replace filter fan discharge dampers with non powered back draft dampers and to reposition instrumentation sensor taps to produce more reliable indication. These changes were necessary to correct design deficiencies in the Control Room Emergency Air Filtration System which, if not corrected, could have resulted in a single failure rendering the system ineffective in performing its design safety function, j No radiological consequences of accidents are affected by these changes. There are no design basis accidents for which failure modes associated with these changes can be an initiating event. These changes restore conformance of system design with the current licensing basis and thereby ensure that radiological consequences are not increased for control room habitability. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE TER 5115, Lengths of Fire Hose Within Turbine Building  ;

CHANGE DESCRIPTION The length of fire hose would be reduced from 75 feet to 50 feet in the Unit 2 Turbine Building.

Engineenng has determined that 50 feet of fire hose is acceptable. This change is requested to standardize fire hose lengths throughout the station.

This change does not affect any safety systems and will not impact fire fighting capabilities.

There are no credible failure modes of safety components and no impact on DBA results and, as such, no unreviewed safety question is involved.

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• B::ver V ll y Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 10 of 59 l i l CHANGE TITLE TER 9349, Removal of Flow Indicator 2GWS-FIT 103 CHANGE DESCRIPTION l

This change removed the gaseous waste locai flow indicator (2GWS-FIT 103) from service,

. since it is no longer required as an input to radiation monitor 2GWS-RQl101. Power cable 2GWSNNK500 was spared at both ends and the 8' vendor cable was removed. Also, the flow transmitter and the stainless steel flow tube, which is welded on the gaseous waste disposal line 2GWS-500-49-4, was retired in piace. {

There are no new credible failure modes associated with the removal of local flow indicator and this will also not affect any other system, component or structure. The device is not required to perform any safety function or used for post accident monitoring and has no impact on any DBA result or probability of occurrence and, as such, no unreviewed safety question is involved.

CHANGE TITLE

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TER 9433, Remove 2 MSS-ARV-100 and 2 MSS-RV-101 CHANGE DESCRIPTION Two relief valves were removed from two 24 inch Gate valves. Removal of the two (2) relief valves removed the Gate valve bonnet overpressure protection. However, the application of i

overpressure protection to the Gate valves was always unnecessary, and its absence didn't jeopardize plant operation. 2 MSS-1 and 2 are the manually operated isolation valves for the  !

condenser steam dump valve headers.

Assumptions and radiological consequences of applicable accidents did not change with the removal of 2 MSS-RV-100,101. Ability of Steam System to dump steam into the atmosphere or condenser was not lessened. There were no effects on the performance of safety related

systems, structures, and components, as this TER is entirely non-safety related. This activity l

did not increase the consequences of a malfunction of equipment important to safety l

evaluated previously in the UFSAR. This change, therefore, does not represent an unreviewed safety question.

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9 B=ver Vcil;y Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 11 of 59 l

- CHANGE TITLE TER 9721, Replace Unit 2 Degraded Grid Relays, Rev.1 i

CHANGE DESCRIPTION l This TER replaced the Unit 2 Degraded Grit: undervoltage relays with higher accuracy relays.

The proposed replacement relays have a higner accuracy than the existing relays and would allow the trip and reset setpoints to be lowered.

The proposed change does not increase the consequences of a malfunction of equipment l

important to safety previously evaluated in the UFSAR. Further, the proposed change did not increase the consequences of an accident previously evaluated in the UFSAR. Wdh this change, the performance of safety systems were improved. There were no effects on assumptions and radiological consequences for the Loss of Offsite Power accident or any l accident which generated a CIB. This change does not represent an unreviewed safety question.

CHANGE TITLE TER 10072, Retire Fire Water Booster Pump and Motor 2 FPW-36 CHANGE DESCRIPTION This TER involved the retirement of the Fire Water Booster Pump. This decisian was based on the results of an assessment of fire protection requirements.

Wdh this activity, the assumptions and consequences associated with the design basis event remain bounded. This change was completely independent of the primary water suppression loop and had no effect on its ability to mitigate the consequences of a fire. NUREG 1057 Section 9.5.1.5 did not identify the fire booster pump in its discussion of the fire protection water supply system and assumed no credit for its function. This change, therefore, does not represent an unreviewed safety question.

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B=v:rVall y Power St tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 12 of 59 CHANGE TITLE TER 10127, Retirement of Primary Demerator CHANGE DESCRIPTION This TER involved retiring installed primary grade make-up water deseration equipment presently installed. This category 11 and lli equipment had a history of operat'onal and maintenance difficulties. A position statement based on a Report Summary from EPRI was developed for retiring this equipment in place.

There were no design basis accidents contained in BVPS Unit 1 or BVPS Unit 2 UFSARs that would be impacted by this change. Further, this change was found to have no impact on the performance of safety systems in the plant. An EPRI study found "inditscemible differences" between plants which operated with deaerated make-up water from those that operated at much higher concentrations (1-2 ppm). Further, the change did not increase the consequences of an accident evaluated previously in the UFSAR. This change, therefore, does not represent an unreviewed safety question.

t CHANGE TITLE TER 10322, Removal of Blind Section of Spectacle Flange on Downstream of Relief Valves CHANGE DESCRIPTION This TER involved the removal of a spectacle flange blind side, downstream of a relief valve.

An ISEG review of the BVPS-System designs in response to Westinghouse NSAL 94-009, ASME Code Compliance for Relief Systems, "it was determined that a spectacle flange was installed in a 6 inch relief line downstream of the relief valves for RHS Suction, Seal Water Retum, Letdown Relief, and the Regenerative Heat Exchanger. This relief line drained to the Pressurizer Relief Tank. The installation of an isolation device in a relief line was not l

acceptable to the ASME Ill Code. Engineering recommended removing the spectacle blind from the spectacle flange.

There were no design basis accidents impacted by this change. Removing the blind face of the spectacle flange did not have any effect on the performance of the system since the blind face of the spectacle flange did not have any operational function duing plant operation.

Completion of this change did not increase the probability of a malfunction of systems, structures, or components important to safety. This change, therefore, does not represent an

(- unreviewed safety question, l

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B;cv:r Vsil:y Power StItion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 13 of 59 CHANGE TITLE TER 10331, Replacement of Drain Lines from Carbon Steel Pipe to Stainless Steel Tubing for 2SAS-C21 A, B, and 2SAS-C22 CHANGE DESCRIPTION This evaluation involved the replacement of carbon steel pipe used for drain lines with stainless steel tubing for Station Air Compressors and Condensate Polishing Air Compressor after coolers The current carbon steel installation had exhibited corrosion and the lines got plugged with corrosion products. This TER also replaced carbon steel globe valves with stainless steel ball valves.

Changing to alloy tubing from carbon steel piping did not impact the probability of system failure. The replacement material . increased resistance to erosion / corrosion. Galvanic ,

corrosion between the existing carbon steel and new stainless steel, which present, was not considered significant since t% affected piping is a drain line leading to a floor drain, and this change is being made to a Category 2 system. This change also did not impact the performance of systems important to safety. The above change, therefore, does r ot represent an unreviewed safety question.

CHANGE TITLE TER 10349, Replacement of 2SAS-221,222,223, and 224 TER 10349 involved replacing of existing Walworth globe and gate valves with Whitey ball valves. The existing globe and gate valves leaked due to seat fouling caused by steel pipe scale. The replacement ball valves, by design, would be less susceptible to this type of failure.

Changing from globe and gate valves to ball valves did not impact the probability of system failure. The failure mode for this change, valve seat fouling, did not represent a new unanalyzed type of malfunction. Further, this proposed change also did not increase the consequences of malfunction of equipment important to safety previously evaluated in the UFSAR. The replacement valves in this change increased resistance to seat fouling and did not create the probability of an accident different than any evaluated previously in the UFSAR.

This change, therefore, does not represent an unreviewed safety question.

. B:cvar Vcliny Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 14 of 59 CHANGE TITLE TER 10361, Auxiliary Boiler Propane Supply CHANGE DESCRIPTION This TER evaluated the replacement of weather damaged gauges with weather, dust, and corrosion resistant gauges. These changes were intended to improve the Auxiliary Boiler Propane Ignition Piping.

The Auxiliary Propane Supply is a non-safety related/non-seismic system. The above changes had no impact on design basis accidents described in the Unit 2 UFSAR nor did it have any impact on the operation of safety systems in the plant. This change, therefore, does not represent an unreviewed safety question.

- CHANGE TITLE TER 10534, Retirement in Place of Unit 2 Fault Recorder PNL-2FAL-REC CHANGE DESCRIPTION This change involved the retirement of a non-functioning fault recorder. This fault recorder has been non-functional since 1987. It was originally installed to monitor and record various electrical distribution system parameters and provide a record of various power line conditions prior to and during faults or line disturbances.

This change had no impact on the performance of safety systems, nor did it have any impact on the systems whose parameters it monitored. The fault recorder had no control or protection function; it only monitored and recorded various parameters. There were no design basis acc6 dents that were impacted by this change and there were, therefore, no effects on the probability of occurrence of a design basis accident. Therefore, this change does not represent an unreviewed safety question.

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- B2:vtr Vcilsy Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 15 of 59 CHANGE TITLE TER 10543, Loose Parts Monitoring System CHANGE DESCRIPTION TER 10543 documented the modification of the Loose Parts Monitoring System. The accelerometers were eliminated. The control room annunciator and its associated computer points.were deleted. The remaining sensors which monitored the steam generators were maintained. A determination was made that this system was no longer a part of the design basis.

The LPMS was independent of other systems that affect plant operation and had no impact on the performance of safety systems. It provided no actuation or control functions, it obtained input by simply " listening" to sound emanating from the RCS. The retirement of this system did not introduce new failure modes because the LPMS did not interact with any other plant systems. This change did not increase the probability of occurrence of an accident previously evaluated in the UFSAR. Further, it did not create the possibility of a malfunction equipment important to safety of a different type than any evaluated in the UFSAR. This change, therefore, does not involve an unreviewed safety question.

CHANGE TITLE TER 10599, Spent Resin Hold Tank Low Level Trip Bypass CHANGE DESCRIPTION Spurious spent resin hold tank low level trips initiated by a level transmitter have caused the spent resin transfer pump to trip off curing resin transfer. These trips caused plugging in the resin transfer lines resul ting in high exposures to personnel. This TER deleted the low level trip signal to the pump by modifying the intemal wiring of the pump's control circuit cabinet. All

- other signals from the transmitter remained unchanged The performance of safety systems were not impacted by this change. Operation of the spent resin transfer pump was not impacted. The pump would still be protected from operating at too low of a suction head. No new failure modes or potential hazards were created by this modification. The consequences of a malfunchon of equipment important to safety were not increased. This change had no impact on design basis accidents evaluated in the UFSAR.

This change, therefore, does not represent an unreviewed safety question.

Braver Vallsy Powcr Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 16 of 59 CHANGE TITLE TER 10652, Retirement in Place of 2TMS-FT215 CHANGE DESCRIPTION TER 10652 evaluated retiring a turbine steam chest pressure transmitter in place, and capping its root isolation valve so that the existing downstream test connection remained available, yet no pressure could enter the transmitter. Retirement of this transmitter did not change its function, since it never had one and it would have no effect on the plant. The NSA of the isolation valve was changed from open to closed. This transmitter was included originally in the plant design and was partially installed but was never electrically wired in and placed in service.

The proposed change is to the non-safety related portion of the Turbine Main Steam System.

It has no impact on safety systems; this transmitter was never placed in service. The proposed change will not increase the consequences of a malfunction of equipment important to safety evaluated previously in the UFSAR. The retirement of this transmitter did not impact design basis accidents evaluated in the UFSAR. This change does not represent an unreviewed safety question.

CHANGE TITLE TER 10664, BV-2 Cycle 7 Reactor Core Reload Analysis CHANGE DESCRIPTION This evaluation documented the reactor core reload for BVPS-2 Cycle 7. Sixty-five fuel assemblies from Cycle 6 were replaced with 64 new feed assemblies. One region 58 fuel assembly from the spent fuel pool was placed in the center core location.

This change did not adversely affect the Reactor Core, Reactor Coolant System, Main Steam System, and the Fuel Pool Cooling System. It did not adversely impact the performance of safety system. The mechanical design did not increase the probability of occurrence of an accident previously evaluated in the UFSAR. The probability of a different accident than any previously evaluated in the UFSAR had not been created. The Cycle 7 reload core design met all applicable design criteria and ensured that all pertinent licensing basis criteria were met.

This change, th?rofore, did not create an unreviewed safety question.

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- Bcsver Vallsy Power Stction Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 17 of 59 CHANGE TITLE TER 10716, Capping of Seal Injection and Leakage Lines to Heater Drain Pumps CHANGE DESCRIPTION This TER involved the capping of seal injection and leakage lines to the Heater Drain Pumps.

Flexhoses on certain lines of the Hester Drain System were disconnected and Swageloks were installed in the vicinity of affected valves.

This change did not increase the probability of a pipe failure because the pressure would be l maintained below the design limits during all plant operatinlj conditions, including a DBA. This change also did not affect the performs.nce of the Heater Drain System. The removal of the seal injection and leakoff lines do not affect pump operation. Further, the change did not I

increase the consequences of an accdont evaluated previously in the UFSAR. The tubing caps and plugs met or exceeded the original design requirements for the system. This change, therefore, does not represent an unreviewed safety question.

CHANGE TITLE t

TER 10736, Unit 2 UFSAR Appendix 9.5A and FPSSR Updates CHANGE DESCRIPTION This activity involved the revision of the Safe Shutdown Report and the UFSAR to incorporate the results of the latest Fire Hazards analysis and to reflect an analysis that evaluated the lack of fire dampers between areas.

There was no change to the performance of any system. The probability of failure of safety systems was not increased because of the fire hazards analysis. The analyses demonstrated that fire barriers would perform adequately to prevent the spread of fire. This activity does not represent an unreviewed safety question.

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- Brav:r Vdisy Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 18 of 59 CHANGE TITLE TER 10771, Removal of 2RCS-624 and 2RCSFG200 and Piping CHANGE DESCRIPTION This TER cut and capped an RCS line, removed a valve, sight glass and blind flange. It also installed a pipe spool with a cap. These changes were made to the Reactor Vessel Head Vent System (RVHVS).

The performance of safety systems were not affected because the reactor vessel head vent system will function as designed. The piping to be installed by this TER was of the same quality and pressure rating as the existing pipe. This activity did not increase the probability of occurrence of a malfunction of equipment important to safety evaluated previously in the UFSAR. It did not impact the assumptions and radiological consequences of the accident (s) identified in the UFSAR. This change does not represent an unreviewed safety question.

CHANGE TITLE TER 10772, Unit 2 UFSAR Appendix 9.5A and FPSSR Update for PORV CHANGE DESCRIPTION TER 10772 evaluated a revision of the Fire Protection Safe Shutdown Report and UFSAR to delete steps which refer to removing fuses for Pressurizer PORVS and replace with steps to open circuit breakers.

There was no change to the performance of any system. This change only affected post-fire operating procedures for de-energizing the PORVS. Further, it had no impact on the assumptions or radiological consequences of design basis accidents. This change, therefore, does not represent an unreviewed safety question.

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. Be ver Vrilsy Power StEtion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 19 of 59 l J CHANGE TITLE TER 10782, Correction of Discrepancy for 2RCS*SOV200A and B CHANGE DESCRIPTION This evaluation was involved with the updating of BVPS Unit 2 UFSAR Figure 5.4-8 to correctly reflect the posebon of Reactor Vessel Head Vent System as being all normally closed and de-energized. The figure showed one of the two valves in series in each flowpath as being normally opened. The Normal System Arrangement of all four of these valves was normally de-energized, normally closed.

The purpose of this evaluation was only to update the UFSAR to correctly reflect actual plant design. There was no increased probability of failure of the systems identified, because the ,

Reactor Coolant System / Reactor Vessel Head Vent System design was not being changed in l any way and the system would continue to operate as designed. This activity does not involve an unreviewed safety question.

1 CHANGE TITLE TER 10809, Removal of Valve Stem Leakoff for Valve 2 MSS-FCV100A CHANGE DESCRIPTION {

This change removed the Valve Stem Leak Off (VSLO) Line from 2 MSS-FCV100A, and installed a welded pipe plug in existing VSLO tap. /also, portions of the VSLO line were removed and the balance of remaining pipe was capped. This system was already functionally deleted prior to startup.

This activity had no effect on the performance of the safety systems. The functions of the Main Steam System and 2 MSS-FCV100A were unaffected. The activity did not create the i

possibility of a malfunction of equipment important to safety of a different type than any evaluated previously in the UFSAR. The VSLO system was functionally deleted prior to start up, and removing the VSLO connechon from the valve only precludes the possibility of a leak path from 2 MSS-FCV100A. This change, therefore, does not represent an unreviewed safety question.

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. B::cyrr Vall:y Power St tion Unit 2 l I

Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 l Page 20 of 59 CHANGE TITLE TER 10840, Intake Structure Pump Cubicles Exhaust Vents 1

i CHANGE DESCRIPTION 1

This TER corrected a discrepancy contained on design drawings regarding the installation of vent stacks and cover plates over pump cubicle openings. Design drawings and the UFSAR

! indicated that vent stacks and coverings were placed when preparing for flooding conditions.

Originally, the intake Structure Pump Cubicles exhaust vents and cover plates were specified to be installed in preparation for flooding conditions. Contrary to this, the vent stacks and cover plates were normally installed during plant operation. Design Drawings and the UFSAR were updated to reflect this.

Installing vent stacks and cover plates during normal operation would not diminish their ability to protect against flooding. This, change also did not increase the consequences of a malfunction of equipment important to safety evaluated previously in the UFSAR. Further, this change had no effect on the probability of occurrence of any design basis accident. This change, therefore, does not represent an unreviewed safety question.

CHANGE TITLE TER 10890, Turbine Lube Oil Reservoir Fire Protection System Corrections CHANGE DESCRIPTION This TER involved correcting various drawing discrepancies that were not corrected for the .

Turbine Lube Oil Purifier Upgrades. Various drawings contained discrepancies because they had not been updated to incorporate system design changes resulting from DCP 2169, )

" Turbine Lube Oil Purifier Upgrades".

This change had no effect on the performance of safety systems. It did not modify the design basis for the control of siphoning and draining of the lube oil reservoir contents. There was no :

new accident created with this design change. This change did not increase the consequences of an accident previously evaluated in the UFSAR. This change, therefore, does not involve an unreviewed safety question.

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- B;cv;r Vall:y Power Station Unit 2 j Facility Changes, Tests, and Experiments  !

November 1,1996 - October 31,1997 Page 21 of 59 l

CHANGE TITLE -

TER 10904, Miscellaneous Modifications to Support Security CHANGE DESCRIPTION This change involved installing various modifications for Nuclear Security. Some of these modifications included installing surface mounted door locks and razor wire.

These modifications have no effect on the operations of systems, structures or components important to safety. They also do not increase the consequences of a malfunction of equipment important to safety evaluated in the UFSAR. This change, therefore, does not represent an unreviewed safety question.

CHANGE TITLE TER 11078, Evaluate Gagging 2CNM-RV109,100,114,115, when Isolation Valve Closed CHANGE DESCRIPTION TER 11078 evaluated gagging of certain bonnet valves during the period of time when their respective main valves were in the open position. The gags would be removed when the associated valvd Store cimd. Bonnet Relief Valves had been installed in response to ANSI B 31.11973 esMon. Gagging the Bonnet Relief Valves while the parent valve was open and removing the gag while the parent valve was closed, meets the requirements of the Code.

This change did not impact the performance any safety system, The change impacted the non-safety related Main Condensate System and non-safety related portions of Steam Generator Feedwater. Further, this change did not impact the probability of occurrence of a feedwater accident. This change, therefore, does not represent an unreviewed safety question.

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. Becv:r Vall::y Power St2 tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 22 of 59 CHANGE TITLE l TER 11245, Vital Bus Distribution Panel Drawing Discrepancies I

CHANGE DESCRIPTION This TER resolved discrepancies between wiring diagrams and one-line drawings for a vital bus distribution panel. The discrepancy involved a main panel breaker, whether or not it was an automatic breaker or molded case switch. The main panel breakers were determined to be non automatic molded case switches. This configuration issue was resolved and drawings were updated accordingly.

Resolution of the drawing discrepancies had no effects on the performance of safety systems.

There . wore no design basis accidents impacted by this change. Selective breaker coordination was not affected; this change had no impact on design basis accidents. This change, therefore, does not represent an unreviewed safety question.

CHANGE TITLE TER 11275, QA Classification for Gaseous Waste Disposal CHANGE DESCRIPTION This TER provided the basis for upgrading the QA classification from QA Category 3 to QA Category 2 for Gaseous Waste Disposal System equipment. This change will upgrade the QA classification so that system items are consistently classified per regulatory guidelines.

This activity was an administrative change that would have no effect on the performance of safety systems. This change had no effect on the probability of occurrence of the design basis accidents evaluated in the UFSAR. The QA category upgrade was an administrative change that did not create a new unanalyzed type of malfunction. This change does not represent an unreviewed safety question.

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o Beaver Vdlay Power St; tion Unit 2 l Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 23 of 59 ,

CHANGE TITLE TER 11402, Fire Hazards Analysis Records Update CHANGE DESCRIPTION The periodic updating of the Unit 2 Fire Hazards Analysis resulted in related updates to both the Unit 2 Fire Protection Safe Shutdown Report and the Unit 2 UFSAR. Some of the updates were attributed to the newly identified combustible materials that were transient in nature and were not part of permanent plant installations. Other updates related to previously approved design changes or technical evaluation reports.

There was no effect regarding the probability of occurrence of a design basis acodent resulting from this change. The fire barriers would still be capable of protecting equipment and cabling required for achieving safe shutdown in the event of a fire. The performance of safety >

I systems was not affected because fire barriers will perform their intended safety functioi< to

. maintain integrity and prevent fire propagation. This change did not create the possibility of an accident of a different type than those analyzed in the UFSAR. This change, therefore, does not represent an unreviewed safety question.

TER 11403, Fire Area CV 6 Thermo-Lag Thickness Evaluation CHANGE DESCRIPTION This TER evaluated the acceptability of revising the rating of the fire barrier between fire areas CV-3 and CV-6. The rating of the fire barrier was changed from 3 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to reflect the actual qualified rating. The fire barrier between these two areas included Thermo-Lag Panels.

An assessment of Thermo-Lag panels demonstrated the acceptability of the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> fire barrier.

This change was reflected on Hazards Boundary Drawings, concrete drawing, Unit 2 UFSAR, l and in the Unit 2 Fire Protection Safe Shutdown Report.

l Revision of the fire barrier rating had no impact on the performance of safety systems. Fire barriers would still continue to perform their intended safety function and maintain its integrity and prevent fire propagation. There was no change in the probability of fire barrier failure resulting from this fire barrier rating change. This change did not create a new type of accident

.as documented in the UFSAR or Fire Protechon Safe Shutdown Report. Changing the fire rating did not reduce the margin of safety as defined in the Technical Specifications. This change does not represent an untsviewed safety question.

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- Besv:r Vcll y Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 24 of 59 CHANGE TITLE TER 11691, EDG Load Step 2 Time Delay Evaluation CHANGE DESCRIPTION TER 11691 evaluated the required load step 2 setting time to accommodate the tolerance required by Technical Specification Section (TSS) 4.8.1.1.2b7 and provide adequate margin for load step 2 Ic~ts to accelerate to full speed before starting load step 3. The EDG sequencer timer for load step 2 was revised from i second to 0.90 second to comply with the above TSS requirement.

This change did not have an effect on the performance of safety systems. It was intended to meet the Technical Specification guidelines set for the sequence timer tolerance range.

Changing the EDG load sequencer time setting did not increase or decrease the probability of the occurrence of a design basis accident. This change did not reduce the margin of safety as defined in the Technical Specifications. This change, therefore, does not represent an unreviewed safety question.

MISCELLANEOUS ACTIVITIES CHANGE TITLE Deletion of EDG Load Values from UFSAR Table 8.3-3 CHANGE DESCRIPTION This change was implemented to remove the ' Running Load' and ' Inrush Load' columns from UFSAR Table 8.3-3. This load data is maintained current in Analyses / Calculations, and is updated with each minor change whicn results in conflicts with the UFSAR values. Thus, the data will now be maintained only in the analyses / calculations such that each calculation change will not require a corresponding UFSAR change.

This change does not affect any operating or design parameters of any system. All associated equipment will continue to perform the intended design safety function as a result of this change. This change does not impact any design basis accidents in the UFSAR. Therefore, this change does not represent an unreviewed safety question.

- Besv;r Villay Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 25 of 59 CHANGE TITLE Revise Minimum Service Water Flow for Charging Pump Lubricating Oil Coolers CHANGE DESCRIPTION t

This change revised the minimum Service Water flow required for the Charging Pump Lubricating Oil Coolers from 25 gpm to 20 gpm. This reduced flow rate was found to be acceptable for design basis requirements due to the performance of the heat exchangers at a lower design maximum Service Water temperature (g5 dog F vs. 90 deg F).

This change has no impact on the probability of failure of any structure, system, or component.

No change exists for the consequences or radiological assumptions in the UFSAR accidents.

The Service Water and Safety injection Systems capability to perform their intended safety

- functions is not impaired as a result of this change. Therefore, this change does not represent an unreviewed safety question.

CHANGE TITLE Resolution of SSFE Item 97-01-A02-01

!. CHANGE DESCRIPTION l

This change was implemented to correct the UFSAR description of raceway and conduit routing associated with the transfer switches for emergency busses. This statement was technically incorrect and deleted as there was no need to include this specific design information in the UFSAR.

l There are no failure modes associated with this change. The performance of the safety

. functions for the Class 1E power system remain unchanged. There are no design basis accidents impacted by this change. Therefore, this change does not represent an unreviewed safety question.

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. B::vsr Vellsy Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 26 of 59 CHANGE TITLE Change of Second Level Undervoltage Time Delay Setting in UFSAR {

CHANGE DESCRIPTION This change was implemented to correct the UFSAR description of the Class 1E, second level .

, bus undervoltage time celay relay setpoint. This resulted in the UFSAR description of a setpoint value which complies with recommendations in NRC Information Notice (IN) dated l 8/08/96, relay setpoint calculations, and Technical Specifications.

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There is no physical change involved and there is no credible failure mode associated with this change. The reactor coolant pump trip on sustained undervoltage (and eventual reactor trip) transient is not impacted by this change. This change does not represent an initiating event and does not create any new failure modes. Therefore, this change does not represent an unreviewed safety question. j CHANGE TITLE Correction of Emergency Diesel Generator Loading in UFSAR Table 8.3-3 j

'CPANGE DESCRIPTION This change was implemented as a result of incorrect information in UFSAR Table 8.3-3 for the Centrifugal Charging Pumps (CCP) and Residual Heat Removal (RHR) pumps availability )

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for a Containment isolation Phase B (CIB) signal. These pumps are not required to operate )

l during a CIB signal in accordance with the Safety Evaluation Report (SER) and thus the

! applicable data was removed from the UFSAR.

This change does not affect any operating or design parameters of any system. All associated )

equipment will continue to perform the intended design safety function as a result of this l l

change. This change does not impact any design basis accidents in the UFSAR. Therefore, this change does not represent an unreviewed safety question.

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. B:cv:r Vall y Pow:r Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 27 of 59 CHANGE TITLF.

Updated Final Safety Analysis Report, Correction of UFSAR Table 8.3-3 CHANGE DESCRIPTION This safety evaluation is prepared to revise the UFSAR Table 8.3-3 (pages 1 and 10) to remove the automatic start action for the CCP pumps and starting of the RHR pumps during CIB signal.

SSFE inspection question number 97-01-A01-013 identified discrepancies between UFSAR Table 8.3-3 and training department hand out for operation of CCP pumps during CIB signal.

The UFSAR states that the CCP pumps operate in response to a CIB signal. EDG loading analysis 10080-E-48 Revision 10, BV-2 UFSAR Section 9.2.2.1.5 and associated schematic diagrams show that the CCP pumps are tripped and blocked from starting on a CIB signal.

Also deleted "0" from the time delay column and "6" from the load step column.

Further UFSAR review revealed that there are discrepancies between UFSAR Table 8.3-3 and Analysis 10080-E-48 Revision 10 for the operation of RHR pumps during a CIB signal. The RHR pumps are not required to operate during a CIB signal per Unit 2 SER section 5.4.7 and associated schematic drawings. Since none of the RHR pumps operate during a CIB signal, the 240 minutes time delay and "TD" from the load step are also removed from the UFSAR Table 8.3-3.

There are no physical modifications to the facility or credible failure modes associated with this change. This change does not impact any DBA results or assumptions and, as such, no unreviewed safety question is involved.

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. B:cv:r Vril y Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 28 of 59 CHANGE TITLE Updated Final Safety Analysis Report Section 7.2,15.3.2, IEEE-279 Qualification for Anticipatory Trips CHANGE DESCRIPTION The Unit 2 UFSAR and SER identify that the Reactor Protection System is qualified under IEEE-279,1971. As part of the extent of condition review for Condition Report 971117, a UFSAR change is required for clarifying the qualification of non-seismic grade components in the Reactor Protection System trip circuits. This change wiH revise UFSAR Section 7.2 and Chapter 15 to distinguish the trips that are not considered to function by the Accident Analysis and hence will be designated "non-credited." These non-credited trips are the RCP UV, UF and breaker position trips.

A similar change was made to the Unit 1 UFSAR. Unit 2 is similar except that the reactor trip on turbine trip is already described as an " anticipatory" trip, and Unit 2 does not have the feed flow / steam flow mismatch trip. The change to the wording of the UFSAR does not diminish the commitment to IEEE-279, but clarifies the extent that this standard applies to the non-credited trips and their qualification. This is done by performing a circuit failure evaluation for ensuring that seismic or other environmental effects do not prevent the RPS from performing the functions required by the Accident Analysis. The results of the circuit evaluation show that none of the trips will degrade the RPS from performing the required functions of the Chapter 15 accident analysis. The P13 permissive of the RPS which gets its signal from the first stage turbine impulse pressure is dispositioned by the same circuit analysis and does not degrade the RPS capability.

There is no change in the probability of failure of any systems because of this change nor any change in performance. There are no adjustments or physical alterations made to the response of the RPS as a result of this. The DBAs do not take credit for the "non-credited" trips and there is no impact on results or assumptions and, as such, no unreviewed safety j question is involved.

B=v r Vril:y Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 29 of 59 i

CHANGE TITLE Updated Final Safety Analysis Report Section 9.2.1.1.2, Service Water System l Description l

CHANGE DESCRIPTION Seal water for cooling, lubricating, and sealing the service water pumps is cuirently described as normally being provided by the BVPS filtered water system. The description of service water pump seal water is revised so that seal water for the service water pumps can be

. provided by either the non-safety related BVPS-1 filtered water system or by the discharge of the service water pumps via self cleaning strainers located in the intake structure. A safety injection signal automatically transfers seal water from the BVPS-1 filtered water system to the discharge of the service water pumps, thus seal water is available from the discharge of the service water pump for any design basis accident. This change will allow seal water to be normally supplied from either the discharge of the service water pumps via strainers, or BVPS-1 filtered water. If the filtered water system is used as the normal supply, the supply from the discharge of the service wr'ar pumps must be available in the event of an SI signal.

This change does not affect failure probability or performance of the service water system.

There is no impact to any DBA result or assumptions and no new type of accident created and, as such, no unreviewed safety question is involved.

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. Beav:r Vcil:y Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 30 of 59 CHANGE TITLE Licensing Requirements Manual Table 5.1-1 and Updated Final Safety Analysis Report Table 6.2-60, Containment Penetrations i

CHANGE DESCRIPTION l

! The Containment Penetrations Table, Table 5.1-1, of the Licensing Requirements Manual l (LRM) was evaluated for consistency and accuracy against the Containment isolation Features

(Table 6.2-60) in the UFSAR. Attachment A and B identify the proposed editorial changes to f enhance these tables. The effect of the editorial changes are:

l 1) Revising the Penetration Numbers to agree with the equipment identification numbers (EINs) listed in the MEL.

2) Addin0 descriptive information in areas where it was previously blank.

3) Correct piping line number errors.

4) Enhance table information for consistency.

5) Correct format and spacing errors.

6). Correct UFSAR section referances in table.

I These editorial changes have no credible failure modes associated with them. There is no effect on performance of safety related systems and no impact on DBA results and, as such, no unreviewed safety question is involved.

CHANGE TITLE Updated Final Safety Analysis Report Table 6.2-60, Revise Overpressure Protection Column Information CHANGE DESCRIPTION This evaluation will provide clarification of the overpressure projections criteria for several penetrations. There are numerous non-intent changes to enhance and clarify UFSAR Table 6.2-80 by avoiding potential misinterpretations of the requirements on these valves. One change alters the overpressure criteria on the three steam generator blowdown penetrations from taking credit for the main steam safety valves to an analysis which shows acceptable post-DBA overpressure conditions via the heat transfer through the existing insulation. This is consistent with the BVPS-2 Containment Penetrations Overpressure Protection l Analysis / Review Report, dated October 28,1996, which was conducted to verify adequacy of l the BVPS-2 penetration overpressure design.

There are no credible failure modes associated with this change. Also this change does not j impact any DBA results or probability of occurrence and, as such, no unreviewed safety question is involved.

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e Bravar Vclisy Pow:r St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 31 of 59 CHANGE TITLE Updated Final Safety Analysis Report Section 11.5/12.5, Radiation Clearance / Health Physics Program CHANGE DESCRIPTION The Health Physics Program was revised to delete the use of designated radiation clearances  !

and to replace their use with established administrative controls. Currently, the UFSAR discusses high radiation areas resulting from plant operations and states, " Access to any of these areas is prohibited unless a Radiation Clearance is authorized and issued for the particular area or continuous radiological monitoring is provided." Subsequent to this change, the Health Physics Manual will continue to define the specific access and monitoring requirements for these areas. In place of the Radiation Clearance, the Radiological Work Permit (RWP) will continue to be utilized to authonze entry into a Radiation Area, High Radiation Area or Very High Radiation Area. The RWP procedure will require authorization of the Nuclear Shift Supervisor of the applicable unit prior to the issuance of an RWP for access to the Reactor Containment Building and Volume Control Tank Area during reactor operations.

If additional administrative control of specific plant components and equipment is prescribed by the RWP, then the Operations Clearance (Tagout) Program described in NPDAP 3.4, Clearance Procedure, may be utilized to implement these controls. This change eliminates a redundant administrative process.

The UFSAR states that all specified steps of a radiation clearance will be verified if the clearance is used. This change removes this statement from the description contained in the UFSAR since the change eliminates the clearance as a control measure.

This change also reduces the level of authorization for the above access to the Reactor Containment Building and Volume Control Tank Area during reactor operation from the Station Manager or designee, to the Nuclear Shift Supervisor, who has historically been the appointed ,

designee. l l

There are no credible failure modes associated with this change and no effect on any safety i

- systems or systems important to safety. This change does not impact any DBA results or probability of occurrence and, as such, no unreviewed safety question is involved.

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-. Beav:r Vdi:y Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 32 of 59 l

CHANGE TITLE Updated Final Safety Analysis Report Section 13.1.2.3 CHANGE DESCRIPTION Eliminate the reference to trending of non-conforming conditions under the Quality Services inspection & Examination (Section 13.1.2.3) of the Beaver Valley Power Station Unit 2 UFSAR. QSIE identifies and documents non-conformances on Condition Reports. The trending of Condition Report data and corrective action effectiveness reviews are performed by the Nuclear Safety and Licensing Department per NPDAP 5.6. This change is consistent with

! OP-13, revision 7, which recognizes the condition report as the vehicle for reporting non-conforming conditions. The trending of non-conforming conditions is not addressed by the QA Program. This change does not represent a reduction in quality requirements.

This change is administrative only and does not impact any plant systems and has no credible failure modes associated with it. There is no impact on DBA results and, as such, no

! unreviewed safety question is involved.

l CHANGE TITLE Updated Final Safety Analysis Report Figure 9.2-10, Change NSA of 2CCP-28 from l Open to Closed  !

f- CHANGE DESCRIPTION l

The NSA position of 2CCP-28 will be changed from open to closed. Molybdate based corrosion inhibitors which require the presence of oxygen for effective passivation were used .

I in the CCP system until April /May of 1996. An NSA change was made years ago to leave l

2CCP-28 open to allow circulation of the system through the surge tank to oxygenate the l system. In May 1996 a nitrite component was added to the CCP system to enhance corrosion l inhibition properties in localized areas of the system with low dissolved oxygen. Molybdates l used with nitritos no longer require the presence of dissolved oxygen for passivation.

Therefore, the need to continuously recirculate the CCP through the surge tank is no longer necessary. The chemical addition tank isolation valve 2CCP-28 should be retumed to NSA closed. This change will also reduce the susceptibility of system contamination from aerobic microbiological activity caused by continuous flow through the atmospheric surge tank.

There are no credible failure modes associated with the change. There is also no impact on DBA results or probability of occurrence and, as such, no unreviewed safety question is involved.

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. Bcavar Valley Power Station Unit 2 Facility Changes Tests, and Experiments November 1.1996 - October 31,1997 Page 33 of 59 CHANGE TITLE 2OM-26-3.B.6,3.C, Change NSA of[2GSS-FN270A, B] and Associated Flowpath CHANGE DESCRIPTION

1) It is desired to change the NSA of the [2GSS-FN270A, B] Gland Steam Filter Exhaust Fans from one ON and one OFF to both OFF AND both flowpaths in service (Change NSA of

[2GSS-26, DMP22A, B] from Throttled to Open and [2GSS-27] from Closed to Open).

Troubleshooting of system operation has shown that this configuration has little effect on system operation (it actually provides more vacuum in the Gland Steam Condenser and runs the [2GSS-FN21A(B)], Gland Steam Condenser Exhausters at a slightly higher current). Per the cognizant SPED Engineer, the component characteristics remain within existing limits.

2) This configuration is recommended due to the degraded condition of the gland steam filter exhaust fans. In 1992, Temporary Modification 2-92-21 removed all of the filter elements from the gland steam exhaust filter housings.

There are no credible failure modes associated with this change, nor are there any safety related systems affected. There is no impact on any DBA result and, as such, no unreviewed safety question is involved.

. B=v:r Valley Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 34 of 59 CHANGE TITLE Licensing Requirements Manual, Table 5.1-1, Updated Final Safety Analysis Report Table 6.2-60, Change Penetrations 14 and 25 MOVs to Remain Locked Shut CHANGE DESCRIPTION Operation of MOVs on Containment Penetrations 14 and 25 are not needed during Modes 1, 2,3 and 4. Therefore, these valves will be locked shut during these Modes. This will ensure that these containment isolation valves continue to perform their function by remaining in their safety related position, i.e., closed. Operating with isolation valves locked shut is consistent with General Design Criteria for containment isolation valves. The valves will continue to receive a CIB actuation signal as previously designed. However, no credit will be taken for the CIB actuation signal to close these containment isolation valves since they will remain locked shut during those modes where containment isolation is required by Technical Specification 3.6.3.1. This design change was implemented per TER 8369. This evaluation will support changes to the Containment Isolation Valve Table in the UFSAR and Licensing Requirements Mar; tal indicating that the Penetration 14 and 25 MOVs will remain locked shut during Modes 1, 2, 3 and 4.

There are no credible failure modes associated with this change, nor is there any change in the containment isolation system's capacity to perform its intended function. There is no impact on any DBA results and, as such, no unreviewed safety question is involved.

CHANGE TITLE Updated Final Safety Analysis Report Table 8.3-3, Deletion of Load Values in UFSAR Table 8.3-3 CHANGE DESCRIPTION The Electrical Distribution System Functional inspection (EDSFI) resulted in testing and analyses to demonstrate acceptability of load carrying capabilities of the emergency diesel generators (EDG). As a part of this review, additional information was developed with respect to the loading of the emergency diesel generator during load sequencing. The transient analysis program was used to analyze the transient loading capabilities of the EDGs and the major motor loads. Results of this new analysis are that the EDGs continue to perform their intended safety function. The load values on Unit 2 UFSAR Table 8.3-3 are being deleted per this change request. The list of the loads, nameplate data, starting and operating times will still be maintained in the UFSAR.

There are no physical modifications to the facility and no credible failure modes associated with this change. This does not impact any DBA results or frequency of occurrence and, as such, no unreviewed safety question is involved.

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. B=ver Vall y Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 35 of 59 CHANGE TITLE Updated Final Safety Analysis Report Table 1.8-1, USNRC Regulatory Guides CHANGE DESCRIPTION Unit 2 Updated Final Safety Analysis Report (UFSAR) Table 1.8-1, "USNRC Regulatory Guides," currently references Regulatory Guide 1.16 (Rev. 4), " Reporting of Operating Information - Appendix A Technical Specifications (August 1975)," which states that Unit 2 will follow the guidance of this regulatory guide for reposting operating information for BVPS-2 as required by UFSAR Reference Chapter 16, " Technical Specifications," Administrative Controls Section 6.9.1.6, " Monthly Operating Report." This change will delete this requirement from UFSAR Table 1.8-1; however, Section 6.9.1.6 of the Technical Specifications will remain unchanged. Instead, the content of the Monthly Operating Report (MOR) will be revised in accordance with NRC Generic Letter No. 97-02, " Revised Contents of the Monthly Operating Report," and will no longer be reported in accordance with Regulatory Guide 1.16 (Rev. 4).

This change does not, in itself, postulate the failure of any component nor does it affect any safety related system. This does not impact any DBA result and, as such, no unreviewed safety question is involved.

CHANGE TITLE Delete Incorrect Statement in the UFSAR for 4KV Transfer Switches CHANGE DESCRIPTION l SSFE ltem 97-01-A02-1 in October 1997 indicated an incorrect statement in the UFSAR l concoming the 4KV transfer switches rdtt.d to the emergency busses 2AE and 2DF. (The Mark number of the switches are 2SW3*TRS-P21C, 2CHS*TRS-P21C, and 2CCP*TRS-P21C). A sentence in the UFSAR Section 8.3.1.1.4 Page 8.3-8a Rev.1 states that " Raceways l - to and from the transfer switch consist of conduit embedded in concrete." This is an incorrect statement. There is a cable coming out of the bottom of each 4KV transfer switch cabinet which is in conduit embedded in concrete. There are also cables coming out of the top of the j transfer switch cabinets which go into air and then into conduit and tray, it is recommended 1 l

that the incorrect statement be deleted from the UFSAR. The need for independent routing of all the cables is mentioned in the last paragraph of Sechon 8.3.1.1.4. That paragraph also refers you to Sections 8.3.1.3 and 8.3.1.4 for a detailed description of identification and l

- routing. There is no need to include this specific design information in the UFSAR.

There are no credible failure modes associated with this change and no effect on any safety system. The change does not impact any DBA results and, as such, no unreviewed safety question is involved.

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. Berv:r Vallry Power St:tien Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 36 of 59 CHANGE TITLE Updated Final Safety Analysis Report Change for CARF 970196-02 CHANGE DESCRIPTION' Revise the BV-2_ Updated Final Safety Analysis Report to address the following items:

1) Clarify the design basis for the Turbine By-Pass System (TBS).

2) Correct the description of the power level that results in an automatic reactor trip following a turbine trip event to be consistent with the P-9 Setpoint specified by the BV-2 Plant Technical Specifications. The UFSAR states that a reactor trip occurs directly following a turbine trip for reactor power levels above 70% This is in conflict with Technical Specification 3.3.1.1 and Technical Specification Table 2.2-1 which has an allowable value of 49% for the P-9 setpoint. The P-9 permissive causes direct reactor trips to occur if the reactor power is greater than its setpoint.

This change has no physical impact on operation and performance of safety systems and also does not affect any failure probability. There is no credit taken for this trip and the change does not impact any DBA result or probability of occurrence and, as such, no unreviewed safety question is involved.

CHANGE TITLE Updated Final Safety Analysis Report Section 8.3.1.1.8 Change CHANGE DESCRIPTION Unit 2 Updated Final Safety Analysis Report Section 8.3.1.1.8 states that "The second level detects a degraded voltage condition which, if not improved within 1 minute, initiates control actions described previously." This one minute refers to the degraded voltage time delay relay time which is actually set at 90 seconds per the setting sheets. The Tech. Spec. Table 3.3-4 also verifies 90 seconds as correct time delay.- This UFSAR change corrects the degraded bus voltage time delay time to 90 seconds in UFSAR Secten 8.3.1.1.8 There is no credible failure mode associated with this change and the 4160V electric power system performance is not affected. There is no impact on any DBA result and, as such, no unreviewed safety question is involved.

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. Bnvar Vdisy Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 37 of 59 CHANGE TITLE 2OM-35.3.B.1 and Updated Final Safety Analysis Report 10.2-10, Valve List - 2GMH and UFSAR Figure 10.2-10, respectively CHANGE DESCRIPTION Change the configuration of the Bulk Hydrogen Storage Facility in the Operating Manual,2OM-35, and the UFSAR, Figure 10.2-10, such that:

1. The nomenclature for all eight cylinder isolation valves is identical, with respect to each cylinder.

2. No reference to " leak" or " reserve" with respect to any one cylinder.

3. The NSA configuration of [2GMH-204), Isol for [2GMH-TK21A], is "Open"; the NSA configuration for all other tank isolation valves (7) is "Close."

i 4. The NSA configuration for [2GMH-202), Makeup Header Cross Connect, is "Open."

This change has no effect on the performance of the safety functions of the CVCS and there are no impacts on any DBA results or probability of occurrence. Hydrogen will continue to be supplied as usual and there is no new accident created and, as such, no unreviewed safety question is involved.

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' CHANGE TITLE Clearances 153343 and 153348, Isolation of Components No Longer in Use CHANGE DESCRIPTI,0N Clearances 153343 and 153348 isolate certain components within the Steam Generator Water Cleanup Sub-System (SGC) that are no longer in use. These components are located downstream of the Steam Generator Blowdown Hold Tanks. Many of the clearance positions noted are contrary to the NSA positions shown in UFSAR figures. The purpose of this safety evaluation is to determine the impact on the design and licensing bases resulting from these clearances. ,

l There are no safety systems affected or failure probability increases associated with this

. change. Also, there is no impact on any DBA result or probability of occurrence and, as such, no unreviewed safety question is involved.

Bc:v:r Vall::y Power Strtion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 38 of 59 CHANGE TITLE

" Retirement in-Place" of 2WWS-TK24 and 2WWS-TK25 CHANGE DESCRIPTION i

Two components of the Unit #2 Solid Waste System were 'cotired in place' by Operations using the equipment tagging system: 2WSS-TK24, the caustic buffering tank, and 2WSS-TK25, the i Cement Storage Silo. 2WSS-TK24 is no longer needed because !! quid waste evaporator i bottoms are no longer process,ed as solid waste at Unit #2. 2WSS-TK25 is no longer needed since cement solidification of waste is no longer performed at Unit #2.

There are no credible failure modes associated with this change or any effect on safety system performance. There is no impact on any DBA results and, as such, no unreviewed safety question is involved. .

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CHANGE TITLE 10080-RM-422A-1 VCN - 2CNM-620,636,1026 NSA Change, VOND Main Condensate System CHANGE DESCRIPTION Piping downstream of [2CNM-636] - According to the Separator Drain Pump vendor tech manual, the Gland Quench Water supply is an optional connection used to preclude packing leakage flashing to steam. Valves [2HDH-1152(1151) and 1150(1149)], Gland Cooling inlet (Outlet) To 2HDH P22A,B, are shown NSA open on UFSAR Figures 10.4-17 and 18, indicating that the supply is in service. However, the valves are NSA closed on VONDs 10080-RM-423B-1 A and 18, and the valves are maintained closed in the field. Operating experience with Slade packing demonstrates that the packing leakage that exists will not flash, and the amount of leakage can be effectively controlled th ough packing adjustments if necessary. Therefore, the configuration maintained in the fiad currently is the desired option. The Long Term Equipment isolation project has now determined that these seal water supplies should be isolated further upstream at the Condensate header. Changing the NSA [2CNM-620(636)(1026)] will accomplish this. There will be no change to the operation of the Heater Drain or Condensate Systems, as there has been no flow through these lines since the pumps were repacked with Slade packing.

There are no credible failure modes associated with this change and also no effect on any safety systems. There is no impact on DBA results and, as such, no unreviewed safety )

question is involved. j 1

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. Bxver Vcil y Power St"_ tion Unit 2 i Facility Changes, Tests, and Experiments I November 1,1996 - October 31,1997 Page 39 of 59 CHANGE TITLE Change NSA From OPEN to CLOSE for Containment isolation Valves 2SSR-SOV128A1 & 2,129A1 & 2, and 2SSR-AOV102A1 & A2 CHANGE DESCRIPTION This SER is written to address changing the NSA for Sample System Containment isolation Valves 2SSR-SOV128A1 & A2,129A1 & A2, and 2SSR-AOV102A1 & A2 from OPEN to CLOSED. The NSA of these valves is being changed to prevent the possibility of a higher pressure Hot or Cold Leg Sample from overpressurizing the lower pressure RHS Sample piping.

There are no new credible failure modes associated with this change and the performance of the valves will not be changed. There is no impact on DBA results or probability of occurrence i and, as such, no unreviewed safety question is involved.

l CHANGE TITLE Updated Final Safety Analysis Report Figure 9.3-11, Post Accident Sampling System, BVPS Unit No. 2 CHANGE DESCRIPTION Change UFSAR Figure 9.3-11 to show all valves open. Add the following note: " Actual valve positions will vary with plant operations." The con'rol of valves on Figure 9.3-11 is identified in existing, approved Chemistry and Operations procedures.

This change does not create any credible failure modes or affect any safety systems. There is no impact on DBA results and, as such, no unreviewed safety question is involved.

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Bs ver Vcil:y Pow:r Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 40 of 59 CHANGE TITLE 1/2 CMP-75-MONITOR-11, Cont ecting Monitoring Equipment to Operating Equipment 1/2 CMP-75-MONITOR-il Procedure Change for Power Monitoring Test Equipment CHANGE DESCRIPTION This Safety Evaluation reviews a change to the Procedure by adding additional test equipment to the Pre-Apprcved step Vll.B.4., and does not involve a change to the facility or procedures as described in the UFSAR. Maintenance Procedures for Plant Equipment are described in the Tech Specs reference Reg. Guide 1.33. UFSAR Section 8, Electrical Systems states the following: "The electrical systems include the equipment and systems necessary to generate power and deliver it to the high voltage switchyard." This change is in accordance with the UFSAR Section 8 Table 8.5-3 Single Failure Analysis and BV-2 Section 8.3.1.1.11.7 for Blown Pot Fuse Protection (not mentioned for BV-1) and has no adverse effects.

There are no new credible failure modes or increase in present failure modes associated with this change. There is no effect on safety system performance and no impact on any DBA resulta end, as such, no unreviewed safety question is involved.

CHANGE TITLE Updated Final Safety Analysis Report Change Request on Figure 9.5-6 for 2FPD-AOV202A/B CHANGE DESCRIPTION Fire Protection System CO2 Discharge Isolation Valves 2FPD-AOV202A & 2FPD-AOV202B are depicted on UFSAR Figuro 9.5-6 as gate valves. These two valves are actually butterfly valves. A butterfly valve can perform the necessary function in this system, which is to act as a tank discharge master isolation valve. The UFSAR figure will be revised to show the current plant configuration.

This change makes no physical change to any plant component and has no credible failure modes. There is no impact on any DBA results or assumptions and, as such, no unreviewed safety question is involved.

. Bnv:r Vcilty Power Strtion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - Octobor 31,1997 l , ,

Page 41 of 59 CHANGE TITLE 2 TOP-96-11, RCS Head Vent SOV Leak Test l CHANGE DESCRIPTION This Temporary Operating Procedure will be employed to stroke the Reactor System head vent valves,2RCS-SOV200A/B and 2RCS-SOV201A/B in order to ascertain that the leakage passing through the valves is less than the Technical Specification (TS), 3.4.6.2 limit of 10 gpm IDENTIFIED laakage. This value, normally established at full power RCS pressure of 2235 l psig, will be adjusted for the actual conditions of the TOP. The RCS temperature at which the test will be performed is 400 F and approximately 1200 psig.

This change does not create any new credible failure modes and present failure probability of systems is unchanged. There is no impact on DBA assumptions or results and, as such, no i unreviewed safety question is involved.

CHANGE TITLE-Unit 1/2 Updated Final Safety Analysis Report Section 11.5/12.5, Personnel Radiation Protection / Health Physics Program CHANGE DESCRIPTION The Health Physics Program was revised to delete the use of designated radiation area zones for posting purposes and to replace with informational posting. This administrative change is in accordance with 10 CFR 20 radiological posting requirements and will provide an enhancement to the current posting program. This change to the administration of radiation area posting will not affect the current radiological controls program which is also in accordance with 10 CFR 20. - The UFSAR discussion related to posted " occupancy requirements" will be deleted and replaced with a reference to the Health Physics Manual as j these requirements are part of the Health Physics Program.

l There are no credible failure modes associated with this change and no effect on any safety 1 I

related systems. The change does not impact any DBA results and, as such, no unreviewed safety question is involved.

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. Briv:r Villiy Power Staticn Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 42 of 59 CHANGE TITLE 2 TOP-97-03, Aligning Temporary Flowpath for Service Water Out of CCS Heat Exchangers CHANGE DESCRIPTION The service water discharge from the Component Cooling System (CCS) heat exchanger (s) is isolated from the cooling tower basin. In order to align a temporary flow path for service water, a fire hose will be connected to the drain line(s) out of the CCS heat exchanger (s). The fire hose w4 os routed to the storm sewer. This will enable cooling of the CCS water for servicing minor turt>ine plant heat loads while in this configuration in Modes 5 or 6.

This change does not affect any system failure mode or create any new credible failure er. odes. Also it does not affect performance of the service water system or impact any DBA results and, as such, no unroviewed safety question is involved.

CHANGE TITLE 1

2 TOP-97-04, Operating the [2CWS-P21 D) Motor Uncoupled for PMT CHANGE DESCRIPTION l

This TOP provides steps for installation and removal of two jumpers and one lifted lead, to facilitate operation of the cooling tower pump motor in an uncoupled condition. The temporary.

modification allows the motor to be started having the following interlocks bypassed: the pump suction and discharge isolation valve interlocks, the 2 minute delay start timers, and the pump seal cooling water supply pressure interlock. The control room benchboard pump control switch will also be bypassed since pump motor control will be at the 4KV Bus 2D Cubicle 2D8 Test Switch. Pump motor protection relays shall be operational during this TOP. This TOP provides instruchons for operating the [2CWS-P21D], Cooling Tower Pump motor uncoupled, for supporting post-maintenance testing of the motor.

This change will not affect the circulating water system performance or failure probability.

There is no impact on any DBA results and no creation of any new malfunction and, as such, no unreviewed safety question is involved.

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- B:cvar Vril:y Power St: tion Unit 2  ;

Facility Changes, Tests, and Experiments  !

November 1,1996 - October 31,1997 j Page 43 of 59  !

CHANGE TITLE BVPS-2 Updated Final Safety Analysis Report Sections 1.2.2, 2.1.1.2, 2.1.2.1, Figure 2.1-2 CHANGE DESCRIPTION i The site area has been' reduced due to the recent sale of approximately 46 acres of the site property and the ownership of Phillis Island has recently changed. There will be no effect on the plant from this sale. Although approximately 7 acres that were sold are within the i exclusion area boundary (EAB), the EAB will remain the same and BVPS will still maintain the j authonty to restrict the use of the land in the event of an emergency at BVPS.  !

There are no systems affected and no failure probabilities associated with this change. There is no impact on any DBA results or assumptions and, as a;uch, no unreviewed safety question is involved. l l

l CHANGE TITLE 2OM-45.3.D.3, Power Supply and Control Switch List Electric Hea:t Tracing System )

CHANGE DESCRIPTION This Safety Evaluation reviews a change to the Power Supply and Control Switch List, Electric Heat Tracing System, and does not involve a change to the facility or procedures as described in the UFSAR. Power Supply Circuit Breakers for Heat Tracing System 45 are being aligned as described in UFSAR Section 8.3.1.1.3.2 to provide a single train power source. UFSAR Section 8.3.1.1.3.2 states the following: "Only one circuit is energized at a time. The redundant circuits are electrically isolated from their supply to provide required independence of safety trains." This change is in accordance with the UFSAR and will have no adverse effects.

There are no new credible failure modes associated with this change and no effect on present failure modes. This change does not affect any safety system performance and does not impact any DBA results and, as such, no unreviewed safety question is involved.

. B:svar Vcilsy Power St; tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 44 of 59

- CHANGE TITLE 2 TOP-97-05, Returning Water from the BR Degasifier 218 to the Reactor Coolant System CHANGE DESCRIPTION New procedure to permit using the 21B Boron Recovery Degasifier to process water from the Primary Drains Transfer Tank 21 and retum the processed water to the Reactor Coolant System by way of the Chemical and Volume Control System. This procedure will be used when a Reactor Coolant Loop (s) is isolated to recover water leaking into the isolated loop and accumulating in the (2DGS-TK21), Primary Drains Transfer Tank.

The. TOP shall be used only in Medes 5 and 6 and will have no effect on safety related systems. There is no effect on any DBA assumptions or results or probability of occurrence and, as such, no unreviewed safety question is involved.

CHANGE TITLE 2GNS-1 NSA Shut, Clearance #153285-2GNS-1 Change NSA Position from Open to Shut CHANGE DESCRIPTION 2GNS-1 NSA position is open. NSA position should be shut due to steam generator nitrogen blanket system use for steam generator is for dry layup conditions during shutdown conditions only. This valve closure only isolated 2GNS-PCV103 on the inlet side. The outlet side of the PCV is essentially isolated by the use of NSA shut manual valves and AOVs. The PCV is only used for dry layup of the Steam Generators (S/G).

This change does not generate any new credible failure modes and does not change present failure modes. This does not affect performance of safety systems and does not impact any DBA results or probability of occurrence and, as such, no unreviewed safety question is involved.

. Brcvtr Vall y Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 45 of 59 CHANGE TITLE Temporary Modification, install Bronze Swing Check Valve for [21AC-7]

CHANGE DESCRIPTION To support troubleshooting of the unreliable performance of 2 LAC-C21A, replace the current stainless steel ball check valve (approved under TER 11222) installed for [21AC-7], compressor cone seal water supply to [2lAC-C21A), with William-Powell Figure 596 bronze swing check valve (approved under TER 9132). The original bronze swing check was replaced with the SS ball check because the former was degrading after apprvAmately 3 to 4 weeks of operation causing the compressor not to load properly. After installation of the SS ball check valve, the compressor would not property load within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of operation. The proposed bronze swing check valve is being installed TEMPORARILY and less than its 3 week expected lifetime to see if an extended run can be maintained. If the compressor runs for a week in this condition, then a suitable replacement will be pursued.

This change does not affect the performance or failure probability of any safety related system nor does it affect any parameters, assumptions or results of any DBA and, as such, no unreviewed safety question is involved.

. CHANGE TITLE Temporary Modification biltered Water Supply Line Condition CHANGE DESCRIPTION Several leak repair clamps and red rubber patches exist on the filtered water supply line

(?-WTF-003-001-4) located in the PAB 718' elevation (pipe tunnel). This temporary modification evaluates this installation until the piping is permanently repaired or retired.

This change does not affect the performance of any safety related system and there is no impact on any DBA result or probability of occurrence and, as such, no unreviewed safety question is involved.

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Braver Vcilsy Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 46 of 59 CHANGE TITLE Temporary Modification, Isolation of Cell #14 from Station Battery 2-1 CHANGE DESCRIPTION During the performance of 2MSP-39.01-E " Battery No. 2-1 Test and Inspection" the voltage for Cell #14 was found to be 2.061 VDC. The voltage for Cell #14 recovered after equalization charge. Based on vendor (Exide) input and solicitation of industry experience, Cell #14 is potentially developing a plate to plate fault. To maintain a high degree of reliability for Station Battery 2-1, Cell #14 will be electrically isolated from the battery set. Station Battery 2-1 has adequate capacity to remove one cell from service, as supported by Engineering Calculation 10080-E-201-1 and Engineering Memorandum 114475.

This change will not affect the failure probability of Station Battery 2-1. Also, this change will not impact any DBA result or probability of occurrence and since plant response is not impacted, no new type of accident is created and, as such, no unreviewed safety question is involved.

CHANGE TITLE Temporary Modification of 2RCS-P21 A Seal Pot High Level Alarm Indication, Annunciator A2-5D CHANGE DESCRIPTION Change the 21A Reactor Coolant Pump seal pot high level alarm so that annunciator window A2-5D is dark when the level is HIGH and lit when the level is NOT HIGH by changing the annunciator input type selector switch from "normally closed" to "normally open." The reason for this change is to cause the annunciator window to be dark until the high level condition is resolved during the seventh refueling outage but still allow the alarm to annunciate if the high level switch changes state.

This change does not create any new failure modes or alter any existing failure modes; also the performance of the annunciator system is unaffected. There is no impact on any DBA results or probability of occurrence and, as such, no unreviewed safety question is involved.

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l . B:cv:r VElliy Power Stition Unit 2 Facility Changes, Tests, and Experiments

! November 1,1996 - October 31,1997 l , ,

Page 47 of 59 i CHANGE TITLE Leak Repair of Cross Under Piping Manway Flange Gasket CHANGE DESCRIPTION l

During power operation, a manway flange on the cross-under piping between the Unit 2 high pressure turbine (2TMS-T) and the moisture separator reheater (2 MSS-H218) developed a gasket leak that requires repair. On-line leak repair has been selected as the preferred repair.

To perform this repair, Temp. Mod. 2-97-10 replaced the original fasteners with regular studs and seal injection cap nuts. The Temp. Mod. also included installation of a cable tensioning device on the outside of the flange and the allowance of an injected controlled volume of sealant into the annulus between the stud and gasket. Later, Temp. Mod. 2-97-11 replaced the 24 studs with slotted studs to enhance sealant flow to the leak area. The change to this current arrangement replaces the 2X* sealant with a sealant mixture of 2X* and 2W Liquid

• to further enhance sealant flow to the leak ares due to tight tolerances. This combination of hardware and sealant shall block the steam path and prevent further degradation of the

( flanged manway coverjoint.

l The failure of the leak repair would only retum the system to its current state; therefore, the failure probability of the main turbine and condenser system is unchanged. The change does not impact any DBA results or probability of occurrence and no new type of malfunction is created and, as such, no unreviewed safety question is involved.

CHANGE TITLE l

l Temporary Modification installation of 2CHS-FT154A CHANGE DESCRIPTION L

2CHS-FT154A supplies a signal to provide indication and alarm functions for RCP Seal Leak-off flow. The transmitter is a Barton Model 752. Transmitter currently supplies a 0-6 gpm indication to the control room. Due to degrading conditions, it is desirable to increase indicated range to 0-8 gpm. A Barton Model 764 will be installed. This will allow for 0-8 gpm indication.

Alarm will continue to function as it presently does. This change will not detrimentally affect system performance. This change will provide the ability to monitor increased seal leak-off flow should that become necessary.

There are no new failure modes associated with this change and no safety related systems are affected. The change does not impact any DBA results or probability of occurrence and, as i such, no unreviewed safety question is involved.

9 B::v:r Vril3y Pow:r St; tion Unit 2 Facility Changes, Tests, and Experiments

!- November 1,1996 - October 31,1997 Page 48 of 59 CHANGE TITLE Temporary Modification - Radiation Monitor 2 MSS-DAU101NB/C EMI Modifications CHANGE DESCRIPTION Radiation Monitors,2 MSS-DAU101A, B & C function to monitor the Main Steam discharge piping high range radiation levels. The radiation monitors monitor the discharge paths to the environment associated with the BV-2 Main Steam lines for the Power Operated Dump Valves and Main Steam Safety Valves. These radiation monitors have been a long-standing problem in the plant relating to spurious alarms. Upon investigation of the field equipment and monitor L history, it was recommended that EMI modifications be installed to eliminate the potential for a spurious alarm to be caused by the effects of Electromagnetic Interference (EMI).

l Electromagnetic Interference (EMI) Modifications are as follows:

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1. Install a braided grounding strap on Signal Cable BNC connector shell at the RM-80 Monitor.

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2. Install 4 Ferrite Beads on each Detector High Voltage and Signal Cable in the Customer i interface Junction Box (CUB) as near to where the cable enters the box as possible.

! 3. Terminate to ground spare conductors in the ClJB.

l These changes will not affect system accuracy, function, and/or performance. This change is intended to improve the reliability of the system and reduce nuisance alarms. These changes l will not cause any new failure modes and will not affect performance of the Digital Radiation Monitoring System nor will it impact any DBA results or probability of occurrence and, as such, l no unreviewed safety question is involved.

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Temporary Modification - Block Drain Valves CHANGE MSCRIPTION l This Temporary Modification blocks the drain lines for 2-CWS-108-7-4 and 2-CWS-108-8-4 which are the main circulating water lines from the cooling tower to the main condene er inlet waterboxes by installing welded steel plating to the respective pipe connection for line 2-CWS-01044-4 and line 2-CWS-010-65-4. Circulating water drain piping line 2-CWS-010-64-4 or line 2-CWS-010-65-4 is leaking. Both lines are located approximately 18 feet below ground level with one line connected to 2-CWS-108-7-4 and the other line connected to line 2-CWS-108-8-4.

There are no credible failure modes associated with this change and no effect on any safety related system. There is no impact on any DBA results and, as such, no unreviewed safety question is involved.

.. Bssv:r Vcll:y Pow:r Stntion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 49 of 59 CHANGE TITLE Temporary Modification - Slade Packing in the Condenser Tube Cleaning System CHANGE DESCRIPTION This Temporary Modification will install Slade Packing in the Condenser Tube Cleaning System (Amettap) Reinjechon Pump ([2 CWA-P21A) on a trial basis. This packing configuration is being used to evaluate if Slade Packing is an acceptable option to eliminate the problems on the seal water portion of this system. This modificabon will install the packing and isolate the seal water supply to the pump.

The circulating water system is not safety related and failure of the packing will not increase failure probability of the CWS. There is no effect on any safety related system or DBA results or probability of occurrence and, as such, no unreviewed safety question is involved.

CHANGE TITLE On Line Leak Repair of 2BDG-463 CHANGE DESCRIPTION The Safety Evaluation evaluates the effucts of placing a Temporary Modification (TM) on steam generator blowdown sample isolation valve 2BDG-463. This 2-inch manual gate valve normally supplies blowdown from 2RCS-SG21C to the Primary Sample Panel. This valve is Safety Related and ASME Section lil, Class 2. The valve had a packing (steam) leak. The TM shall stop the steam leak by drilling and tapping the stuffing box, installing an injection valve in the stuffing box of the valve and then injecting a packing type sealant into the stuffing box.

The sealant shall block the steam exhaust path and prevent degradation of the valve pressure boundary.

The failum of the on-line leak repair will not initiate a failure of the blowdown system. Also this does not affect any safety related system or impact any DBA results or probability of

! occurrence and, as such, no unreviewed safety question is involved.

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. Bnv r Vallsy Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 50 of 59 CHANGE . TITLE l

I 2OM-9.4.F - Draining a Recire Spray Pump Casing or Pump Pit CHANGE DESCRIPTION I I

l The procedure is being revised to install a temporary sump pump and hose to the suction of the Recirculation Drain Pump. The temporary sump pump will be lowered into the recirculation

! spray pump pit and operated to supply water to the suction of the recirculation drain pump. q The recirculation drain pump cannot self-prime due to the elevation difference. The recirculatxm drain pump has connections to connect a hose to pump the recirculation spray l pump lower cubicle. The temporary sump pump and hose will be disconnected after the pit is

pumped out. The recirc drains pump will pump the water to the North Safeguards Sump.

I The temporary equipment will not be overpressurized and there will be no increase in failure {

l . probability of the systems. There is no impact on DBA results or probability of occurrence and, as such, no unreviewed safety question is involved.

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Temporary Modification - Installation of Modified AIM 07 RTD Module in RK-2 CMP-DIN 8 l

CHANGE DESCRIPTION installation and use of RTD Analog input Module AIM 07, in RK-2 CMP-DIN 8 slot 16 with modified RTD bridge circuits. AIM 07 module bridge circuits will be modified to reduce i temperature indication drift of 10 Ohm RTD inputs on Plant Computer System.

l This temporary modification does not introduce any new credible failure modes nor does it l affect any safety sys'em performance or failure probability. There is no impact on any DBA results and, as such, no unreviewed safety question is involved.

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e B*zver VEll:y Pow:r Strtion Unit 2 l Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 51 of 59 CHANGE TITLE  ;

Temporary Modification - Leak Repair of 2HDH-TK22A Manway Flange Gasket CHANGE DESCRIPTION During power operation, the manway flange on tank 2HDH-TK22A developed a gasket leak .

that requires repair. On-line leak repair was selected as the preferred repair. This repair consists of removing the existing manway hinge, replacing every other existing stud and blind l flange side nut with a leak repair slotted stud and injechon capnut, replacing the remainder of the blind flange side nuts with injechon capnuts, installation of a stop gap measure inboard of the studs'at the leak location to reduce or eliminate the possible intrusion of sealant into the system, wire wrap of the studs, cable tensioning and injection of a controlled volume of the sealant into the annulus between the wire wrap and gasket. The combination of hardware and sealant shall block the steam path and prevent further degradation of the flanged manway coverjoint.

This change does not affect the failure probability of the heater drains system or impact performance of any safety related system. There is no impact on any DBA result or probability of occurrence and no new accident or malfunction is created and, as such, no unroviewed safety question is involved.

l CHANGE TITLE l Temporary Modification - Leak Repair of 2FWS-H22B Test Connection CHANGE DESCRIPTION A threaded test connection on the Condensate Line 2-CNM-018-35-4 was leaking, and required repair. Injection leak repair was used to stop the leak. The leak repair consisted of i the installation of a clamp and the injection of a known quantity of sealant into the clamp, thus stopping the leak.

The failure of the leak repair would only retum the condensate system to its current condition and, therefore, does not affect probability of failure of the system. This change has no impact on DBA results and does not modify the plant such that a new accident scenario must be considered. No new credible failure modes are created and, as such, no unreviewed safety question is involved.  !

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. Bi vtr Vill y Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 52 of 59 CHANGE TITLE Temporary Modification - Leak Repair of Steam Supply Valve 2 MSS-FCV100A CHANGE DESCRIPTION j i'

This Temporary Modification is on the steam supply isolation valve 2 MSS-FCV100A. This 10-inch air operated globe valve normally supplies steam to the Units A and C moisture separator

- reheaters during plant operation. The valve has a bonnet to body steam leak. The Temporary Modification shall stop the steam leak by installing several leak repair enclosures about the valve body and then injecting these enclosures with a suitable sealant. The combination of enclosures and sealant shall block the present steam exhaust path and thus prevent degradation of the valve pressure boundary.

Leak repair of this valve does not affect any safety system and there is no impact on any DBA resu;ts or probability of occurrence. This TM does not cause any new accident or unanalyzed  !

malfunction and, as such, no unreviewed safety question is involved.

i CHANGE TITLE j l Temporary Modification - Leak Repair of 2RCS-624 CHANGE DESCRIPTION 2RCS-624, NSA closed, is the 1" inlet isolation valve for reactor vessel head vent flow Site Glass 2RCS-FG-200, whose discharge is capped with a 150 lb. blind flange. Leakage past the seat of 2RCS-624 is exiting the RCS through this flange joint. Sealant shall be injected through the inlet side pressure boundary of 2RCS-624 to stop the leak, making it inoperable.

l 2RCS-624 performs no safety function and will be kept closed in accordance with its current NSA. Leakage or loss of the sealant effects are bounded by existing small break LOCA analysis. The probability of occurrence of the DBA remains unchanged and there are no new l unanalyzed accidents or malfunctions and, as such, no new unreviewed safety question is involved.

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• B !ver Vill:y Power St: tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 53 of 59 CHANGE TITLE Temporary Modification - Blind Flange Installation for 2HVC-CND24B CHANGE DESCRIPTION

! The service water spool pieces for the control room air conditioning unit condensers are in i need of replacement. The spool piece for the inlet to 2HVC-CND24B on service water pipe 2-SWS-003-050-3 will be removed and sent to a vendor for fabncation of new spool pieces.

Since the fabrication of new spool pieces will take longer than 7 days, this Temporary Modification will install a blind flange on the inlet side of the service water piping to the condensers to allow the backup air cooling capability and 2HVC-ACU201B to remain available for service.

The installation of the blind flange will meet or exceed the design requirements of the' system and there are no credible modes identified with it. This will not increase the failure probability of the control room ventilation or service water system or affect their performance. There is no

- impact on any DBA results and, as such, no unreviewed safety question is involved.

l CHANGE TITLE Temporary Modification - Steam Generator Blowdown Filters i

CHANGE DESCRIPTION 1

! This modification will remove the filter cartridges from the Steam Generator Blowdown Filters

[2BDG-FLT21A). This change is being implemented due to the low flow condition resulting from fouling of the filters. In addition, replacement filter cartridges are not available at this time. By removing the filter media, a slight increase in me volume of Low Level Radioactive Waste (LLRW) will be generated due to the inability to prevent radioactive particulate from contaminating the domineralizer resin. l There are no credible failure modes associated with this change and it will not affect probability of failure or performance of the steam generator blowdown system. There is no impact on any safety systems or DBA results and, as such, no unreviewed safety question is involved.

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. Bev:r Vellsy Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 54 of 59 l

CHANGE TITLE 2OM-53A.1, BV-2 Emergency Operating Procedures (OMCNs)

CHANGE DESCRIPTION The Emergency Operating Procedures are being revised to delete starting and stopping Recire Spray Pumps and use an attemate method to maintain Containment Pressure between -2 and l

-5 psig. The EOPs will provide dirschon to start and stop Service Water flow to the Recirc

Spray Heat Exchangers by electrically operating 2SWS-MOV105A,B, from the control room.

This reduced Service Water flow will effectively increase the temperature of the Recirc Spray l water and raise containment absolute pressure without compromising other DBA Service Water loads. Valve manipulation in lieu of RSS Pump starts and stops is the preferred method to control Recirc Spray temperature / containment pressure and to minimize transient effects on RSS System Piping. The A and B Recire Spray Heat Exchangers have been chosen to be isolated versus the C and D Heat Exchangers to preclude any effect on the Switchover to Recirc of the accident.

l This change has no adverse effect on the Service Water System or Recirculation Spray

Systems and does not change the ability of the RSS System to mitigate effects of elevated containment pressure. This change will not impact any DBA results or probability of occurrence or create any new malfunction and, as such, no unreviewed safety question is involved.

CHANGE TITLE l EM 114926, Removal of Fire Door (CV-67-1) During Outage Activities l

CHANGE DESCRIPTION l

f During Unit 2 outages, while the plant is in Mode 5 and 6, fire door [CV-67-1] between PA-5

( (773' PAB) and CV-5 (Cable Vault and Rod Control Building 767' 10") is removed for easier i access between the PAB and containment. Removing fire door [CV-67-1] will connect fire areas PA-5 (773' PAB), CV-5 (Cable Vault and Rod Control Building 767' 10"), and RC-1 (Containment Building) when the air lock is open. A fire watch will be established for the area j while the door is removed as required by NPDAP 3.5. The door is located in a wall which has a barrier classification of fire, hydrostatic pressure and air pressure per drawing 10080-RM-301E. No compensatory measures are required for the hydrostatic or air pressure boundary with the plant in Mode 5 and Mode 6.

Removal of the fire door does not introduce any additional failure modes for the hazards barrier and the Fire Protection System, nor does it increase the probability of a fire since no additional fire loading is being introduced. There is no impact on any DBA results or probability of occurrence and no new unanalyzed accident and, as such, no unreviewed safety question is involved.

. Beever Valley Power Stction Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 55 of 59 CHANGE TITLE Temporary Modification, Install Stainless Steel Swing Check Valve at [2lAC-7]

CHANGE DESCRIPTION To correct unreliable operation of [21AC-C21 A), replace the current check valve with a stainless steel swing check valve at location [2lAC-7], compressor cone seal water supply to [21AC-C21A]. It has been demonstrated both in the Nash compressor shop and through implementation of Temporary Modification 2-97-013 that the ball check valve specified and installed under TER 11222 was the cause of the unreliable operation. Use of a swing check valve is necessary in location [2 LAC-7]. The proposed replacement valve is a Wm-Powell Figure 1847Y stainless steel swing check valve,200# class, threaded ends and 1/2" size. The design of this check valve is similar to the bronze version approved under TER 9132 which has been operating successfully for up to three weeks under Temporary Modification 2-97-013.

The only difference is that the stainless steel material will provide for a more rugged and robust design. The purpose of this Temporary Modification is to perform a confidence run of [21AC-C21A] with this valve at (2iAC-7) for approximately one week. Should the confidence run be successful, then a TER will be issued to make the replacement valve permanent.

No operating or design parameters or systems are affected by this change. There is no effect on any safety related system since the containment 1A system is not safety related and no DBAs are impacted by this change. There is no new unanalyzed malfunction or accident and, as such, no unreviewed safety question is involved.

. Bnvrr Vcliny Power Station Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 56 of 59 CHANGE TITLE Temporary Modification, install Bronze Swing Check Valve for [2lAC-7]

CHANGE DESCRIPTION To support troubleshooting of the unreliable performance of 2lAC-C21A, replace the current stainless steel ball check valve (approved under TER 11222) installed for [2lAC-7], compressor cone seal water supply to [2lAC-C21A], with William-Powell Figure 5g6 bronze twing check valve (approved under TER 9132). The original bronze swing check was replaced with the SS ball check because tne former was degrading after approximately 3 to 4 weeks of operation {

causing the compressor not to load properly. After installation of the SS ball check valve, the compressor would not property load within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of operation (i.e., would not even last the three weeks as oefore). Much troubleshooting has been done to determine what is causing I I

the compressor not to load. Although it is acknowledged that the proposed bronze swing check valve is a known problem, it is being installed TEMPORARILY and less than its 3 week expected lifetime to see if an extended run can be maintained. If the compressor runs for a

- week in this condition, then a suitable replacement will be pursued.

The performance or failure probability of any safety related or important to safety system is not affected by this change. This does not impact any DBA results or probabihty of occurrence and no new unanalyzed accident is created and, as such, no unreviewed safety question is involved.

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. B=v;r Vill;y Power St tion Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 57 of 59 CHANGE TITLE 2 TOP-97-06, Flushing Service Water Side of [2CHS*E25B] Charging Pump Lube Oil Cooler Supply and Return Low Point Piping CHANGE DESCRIPTION This TOP provides a method to flush the service water side of [2CHS*E25B) Charging Pump Lube Oil Cooler supply and retum low point piping. Low flow has been experienced on

[2SWS*Fl111B] Charging Pump B Lube Oil Cooler Outlet and is believed to be caused by accumulated debris in the low point piping. A tygon hose will be connected to the service water side of [2CHS*E25B] low point drains and routed to the Fire Sump. Drain point will be moved to ensure all the low point piping has been completely flushed. The flush will begin with using the service water from the 'A' header to remove any debris that may have accumulated in the low point piping. Then service water from the 'B' header will be used. Prior to the flushes, the service water flow to the standby or running Charging Pump Lube Oil Cooler will be raised to 30 gpm for the cooler that is aligned to the same header. An additional operator will continuously monitor the standby or running Charging Pump Lube Oil Cooler flow to ensure at least 26 gpm is maintained. If flow should happen to drop below 25 gpm, the service water supply valve used to flush [2SWS*E25B] will be immediately throttled closed to raise flow in the respective inservice cooler above 25 gpm.

This will not change the performance or failure probability of the charging pumps or service water system and there are no DBAs identified with this change. There is no unanalyzed accident or malfunction created and, as such, no unreviewed safety question is involved.

.f B3tv:r Villay Power Stition Unit 2 Facility Changes, Tests, and Experiments November 1,1996 - October 31,1997 Page 58 of 59 CHANGE TITLE Temporary Modification - Turbine Governor Valve No. 4 (2TMS-GV4) Valve Stem and Coupling Anti-rotation Collar CHANGE DESCRIPTION On August 19,1997, during the performance of Turbine Valve Freedom Testing (20ST-26.1),

the Operator at the Turbine noted that the #4 govemor valve (2TMS-GV4) was not fully closed and the LVDT core rod was bent. It was later determined that the limit switch linkage rod i became unthreaded from the coupling. This rod also serves as the valve anti-rotation device.

i Without the anti-rotation rod attached, the valve stem rotated approximately 60 degrees until the LVDT linkage contacted the spring housing preventing any further movement. Attempts to l

reposition the valve in the original alignment were unsuccessful. While trying to rotate the l coupling back into its original position the coupling rotated approximately 1/8" without corresponding movement of the valve stem. It is e.ssumed that the 1/2" coupling shear pin is l

~ damaged and the valve stem is no longer fully engaged in the coupling. A collar will be  ?

l machined to attach to the valve coupling utilizing the original limit switch rod mounting location on the coupling (1" x 8 TPI bore). New limit switch and LVDT rods will also be machined to a slightly shorter length that correspond to the new alignment lengths based on the collar thickness and actual field requirements. Yhe valve stem is captured around the flats located directly below the coupling to prevent any potential valve stem rotation inside the coup!ing while the valve is operating.

The turbine throttle valves and turbine hydraulic trip system are not affected by this temporary change and there is no impact on the turbine trip accident analysis or probability of occurrence. .

I This does not cause any unanalyzed accident or malfunction and, as such, no unreviewed safety question is invosved.

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B::cv:r Vallsy Power Station Unit 2 j

Facility Changes, Tests, and Experiments j f November 1,1996 - October 31,1997 i

. , Page 59 of 59 CHANGE TITLE

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Temporary Modification - Digital Rod Position Indicators F6 and F8 Train Correction Modification CM?NGE DESCRIPTION "The change consists of providing a temporary modification to correct reversed train connections for rod position indicators F6.(C/B-D) and F8 (C/B-C). The train reversal, pret amed to be located at the detector assembly connection below the missile shield, shall be corrected for by exchanging the two train connections located at the connection plate near the Rt. actor Ref..eling Cavity, operating dock (elevation 767'-10"). This action, commonly referred to as a double-roll, will temporarily restore the system to its Normal System Arrangement (electrica'ty). TP.e %o trains being exchanged in this manner ara electrically and mechanically

, equivalent with the exception of the detector coil arrangement; each DRPI detector contains 42 identical coils,21 coils per train, attached to the assembly body length at 6-step intervals in a train-staggered arrangement. The modification will allow these coils to receive power from and l report position to the correct train Data Cabinet thereby eliminating the miswiring electrically.

Note that without the modification, the design of the DRPl system allows DRPI to property l Indicate position in its present state provided the system is operated normally (two train mode).

I No plant components are added or removed by this temporary modification and performance l of safety systems remains unchanged. The DRPI System is not safety related and the l temporary modification will not impact any DBA result or probability of occurrence and, as

! such, no unreviewed safety question is involved.

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CHANGE TITLE l l Disconnect Category ll Equipment - Remove from Service 2 MSS-PR475 CHANGE DESCRIPTION l

The QA Category 11 Steam Line Pressure recorder 2 MSS-PR475 will be temporarily disconnected until the seventh refueling outage 2R07. The purpose for this temporary

modification is to decrease the effects of an electrical fault from affecting protection rack RK-2PRI-SEC-3. The existing electrical configuration is such that a 1E circuit is electrically connected to a non-1E circuit with no isolation in between.

There are no credible failure modes associated with this change and since the equipment and computer points are never relied upon to mitigate any DBA, there is no impact on results or

, probability of occurrence. There is no type of unanalyzed accident or malfunction created and, as such, no unreviewed safety question is involved.

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