ML20086U509

BVPS Unit 1 Rept of Facility Changes,Tests & Experiments 940123-950122

ML20086U509
Person / Time
Site:	Beaver Valley
Issue date:	01/22/1995
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20086U497	List: ML20086U491 ML20086U509
References
NUDOCS 9508040122
Download: ML20086U509 (67)

Text

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, Be v:r Vcil:y Pow:r St: tion Unit 1 Report of Fccility Ching:s, Tests, cnd Experim:nts January 23,1994 - January 22,1995 Table of Contents Utilization / Designation Of The Shippingport Atomic Power Station (SAPS)

Warehouse For The Storage Of Radioactive Tools, Materials, And Equipment While N ot in U s e At Ei the r U nit.................................................................................... 1 Installation of an AudioNideo CCTV System for the Tenth Refueling Outage Surveillance...................................................................................................................2 Installation Of Temporary Lead Blanket Shielding On Fuel Pool Purification Line 4-FC-19-152...................................................................................................................3 Wa s t e H a n d li n g B ul l di n g ........ ... ..... . ... ............... ...... . ..... ........... .. .. ......... ....... .......... . .... 4 Use Of A Storage Building For The Storage of Mixed Hazardous And Radioactive Material..........................................................................................................................5 River Water System Valve Normal Position Changes ............................................... 6 1 TOP-94-2 and 1 TOP-94-5, Operating the "B" and "D" Cooling Tower Pump M o t o rs fo r Te s ti n g . . . . . . . .. . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . ... . . . .. . . . . .. . . . . . . . . . . . . .. ... . . . . . .. . . . . . . . . . . 7 1 TOP-94-3, Dye Check of River Water Pipe................................................................ 8 1 TOP-94-7, Operational Test for DCP-2092, Main Transformer Replacement........ 9 Reactor Coolant System Sample Header Containment isolation Valves Position Change........................................................................................................................10 Locking of River Water Return Header isolation Valve...........................................11 Defeat of Residual Heat Removal (RHR) System Automatic Isolation Function ..12 Temporary Blank Flange on ERF Substation Dampers ..........................................13 1

h Removal of Main Turbine Lube Oil Reservoir Drain Pump (LO.P-1)......................14 Temporary Modification to the Nitrogen Supply Manifold......................................15 9508040122 950727 i PDR ADOCK 0500o334 R PDR

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, B: aver Vallsy Power Stction Unit.1 _

Report of Facility Changas, Tests,' and Expsriments  ;

January 23,1994 - January 22,1995 '

Table of Contents  ;

J Temporary Modification to Change Normal Position of Blowdown isolation '

Valves (IA 166 and IA-167) for Containment Air Compressor Receivers...............16 Leak Repair of "C" Steam Generator Hand-Hole. ....................................................17 Temporary Line to Chemical Waste Hold Tanks (WT-TK-24A, B)..........................18 ,

1 Installation of a Tem,9orary Station Air Compressor...............................................19  ;

i Temporary Modification of Station Air Compressor (SA-C-18) Auto Start Feature.........................................................................................................................20 i

' Leak Repair of Cross-Under Piping Manway Covers .............................................. 21 Installation of Temporary Heaters at the Refueling Water Storage Tank i (RWST)........................................................................................................................22 i Corrosion Control for Recirculation Spray and Diesel Generator Heat Exchangers.................................................................................................................23 ,

i Temporary Modification to Support Safety injection Accumulator Discharge C h e c k Val ve s Full Strok e Te st ....... . ... ...... .. . ..................... . . ...................... ........ ... ...... 24 Installation of a Blind Flange on River Water Chlorine injection Line................... 25  :

Installation of a Blind Flange on River Water Line ...................................................26 Installation of a Blind Flange on River Water Supply Line to the "A" Emergency  ;

~ D i e s e l G e n e ra t o r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Temporary Modification to Remove Solid State Protection System Instrument Bus _ ,

StatusLamp................................................................................................................28  !

Connection of Test Coupon Rack to Raw Water System ....................................... 29 l Tempo ra ry M odific a tio n to A M S AC........................................................................... 30 i

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, B2 aver Valley Pow:r Station Unit 1 i Report of Facility Changes, Tests, and Experiments January 23,1994 - January 22,1995 Table of Contents

' Locking and Deenergizing of Charging Pump Recirculation Line Isolation  :

Valve............................................................................................................................31 l i

Test Frequency Change for Switchgear and Power Transformers........................ 32 DCP-738, Replacement of Boron Recovery System Pressure Transmitters......... 33 DCP-1450, Ventilation Modification to Maintain the Control Room Envelope Pressure......................................................................................................................34 '

DC P-1516, Spent Fuel Pool Capacity Expansion..................................................... 35 DCP-1551, Standby Alarm Interface to Mergellsolate Cabinet ............................... 36 DC P-1913, Outage Communications Upg rade ......................................................... 37 DC P-1915, Dedicated Dial Tone Lines for the N RC ................................................. 38

'DCP-1941, Modification of the Control Circuitry for Control Room Ventilation Dampers......................................................................................................................39 DCP-1960, NRC Emergency Telecommunications (FTS-2000)............................... 40 DCP-1989, Replacement of'dVAC Control Air System Drain Valves ..................... 41 DCP-2003, Test Fittings for Air Operated Valves..................................................... 42  :

DCP-2011, Removal of the Auxiliary Boiler Fuel Oil Tank ...................................... 43 DCP-2012, Replacement of Supplementary Leak Collection and Release .l System Differential Pre ss ure indicators ................................................................... 44 1 DCP-2041, Mechanical Seal Replacement for Ventilation System Pumps ............ 45 f DCP-2075, Gland Steam Extraction Fans Structural Modifications....................... 46 I

I DC P-2076, C o n d uit S u p p o rt B ra cln g ........................................................................ 47 )

1 DCP-2079, Removal of Plastic Liquid Waste Piping................................................ 48  ;

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. , Beaver Valley Power Station Unit 1 ,

, Report of Facility Changes, Tests, and Experiments l January 23,1994 - January 22,1995 Table of Contents DCP-2086, Valve Operator Torque Switch Bypass / Heater Removal...................... 49 i

DC P-2092, M ain Tran sforme r Replac e ment ............................................................. 50  :

i DCP-2096, Remove Reactor Coolant Pump Seal Differential Pressure Indicator. 51 DCP-2110, install Ground at Output Common For isolator TM-RC-433B.............. 52  !

TER-5906, Supplementary Leak Collection and Release System Design 4 Reconciliation.............................................................................................................53 l TER-7828, Relocation of Class Break for Containment Vacuum Piping ............... 54 TER-8071, Replacement of River Water Pipe Drain Valve....................................... 55 TER-8484, Reclassification of Portions of BV-1 Raw Water System ..................... 56  ;

i TER-8696, Reconciliation of Safety injection Cyatem VONDs, Flow Diagrams j a n d U F S A R Fi g u re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 7 l i

i TE R-8808, Se t pol n t St ud y C h a ng e s .......................................................................... 58 j TER-8952, Fuel Assembly and Component Drawing Changes............................... 59 l TE R 9289, Steam Gene rator Tu be Sleevin g ............................................................. 60 i

UFSAR Change to Allow Use of Equivalent Materials............................................. 61 l

Exc ayation of River Wate r Lin es ............................................................................... 6 2 l

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.t Updated Evaluation of the Effects of High Energy Breaks Outside  !

Containment................................................................................................................63 i

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, B: aver Valley Power Station Unit 1

. Report of Facility Changes, Tests, and Experiments January 23,1994 - January 22,1995 Page 1 of 63 CHANGE TITLE Utilization / Designation Of The Shippingport Atomic Power Station (SAPS) Warehouse For The Storage Of Radioactive Tools, Materials, And Equipment While Not In Use At Either Unit CHANGE DESCRIPTION This safety evaluation documented the utilization of the SAPS warehouse, which is located on the southwest side of the Beaver Valley Power Station Site (as shown on UFSAR site layout drawings), for the storage of radioactive tools, materials, and equipment when not in use. The reason for this change is to provide additional "under shelter" storage capacity for the plant.

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, Beaver Vellsy Power Station Unit.1' Report of Facility Changas,~ Tosts, and Expsriments l

. January 23,1994 - January 22,1995 l Page 2 of 63 l

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CHANGE TITLE l l

Installation of an AudioNideo CCTV System for - the Tenth Refueling Outage I Surveillance 1

CHANGE DESCRIPTION ,

E This temporary modification installed a closed circuit television system in the Reactor  !

Containment Building for the tenth refueling outage. installation of the system involved ,

the routing of IEEE rated cabling, breaching and restoration of two fire stops and an electrical penetration. Twelve cameras were installed. The modification was made' to i support ALARA dose reduction for supervisory radiological support and radworker personnel.

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l'~ Scavar Vallay Pow:r Station Unit.1

. Report of Facility Chenges, Tests, and Exp rimsnts.  ;

' January 23,1994 - January 22,1995 _;

Page 3 of 63-

' CHANGE TITLE t Installation Of _ Temporary Lead Blanket Shielding On Fuel Pool Purification Line 4-FC- -

.19-152. >

L CHANGE DESCRIPTION t

Temporary lead shielding on line 4-FC-19-152 was installed to reduce high general .

area and contact dose rates attributed to a radioactive hot spot in the line. The l

. shielding installation was effective.in reducing dose rates during repair of a nearby  !

valve.  !

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.. Bscver Vcll:y Pow:r Station Unit 1

.p Report of Fccility Chang s, Tests, and Exp: rim:nts -  ;

January 23,1994 - January 22,1995 Page'4 of 63-

. CHANGE TITLE ,

Waste Handling Building CHANGE DESCRIPTION

• The Waste Handling Building (WHB) is a shielded' facility, constructed during the mid 1980s, for interim storage of compacted and solidified . low-level radioactive waste (LLRW) from Beaver Valley Power Station (BVPS) Units 1 and 2. The. building and ,

associated equipment were designed to meet the spplicable requirements of 10 CFR  ;

50,10 CFR 20, Regulatory Guides 1.21 and 8.8, Branch Technical Position ESTB 11- l 3, and Generic Letter 81-38. >

The WHB design was not changed. However, since the date that the WHB was placed in service, there have been changes in procedures and practices regarding interim storage of LLRW. These changes are described below. -

' The first change affects the type of waste form that is to be stored in the facility. The l WHB liner storage bay was designed primar a for the storage of carbon steel liners that contained evaporator bottoms solidified with cement. The present station practice of using demineralization, in lieu of evaporation, generates LLRW resins and filters which are transferred into liners and dewatered to meet the burial criteria.

' The second change involved implementation of the revised 10 CFR 20, " Standards for Protection Against Radiation," at BVPS.

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L Brv:r Vill:y Power Station Unit 1

.- R: port of Fccility Chang:e, Tests, cnd Experim:nts January 23,1994 - January 22,1995 Page 5 of 63 CHANGE TITLE Use Of A Storage Building For The Storage of Mixed Hazardous And Radioactive Material CHANGE DESCRIPTION The purpose of this safety evaluation was to document the designation of an  ;

acceptable storage facility for the storage of hazardous / radioactive materials referred to as " mixed waste." Mixed waste is low-level radioactive waste (LLRW) that also l contains listed hazardous waste or exhibits one of the four hazardous waste  :

characteristics (i.e., ignitability, corrosivity, reactivity, or toxicity). Both the NRC and EPA regulate the management of mixed waste.- Generators of mixed waste must comply with 40 CFR 262 " Standards Applicable to Generators of Hazardous Waste."

Treatment, storage, and disposal facilities must also comply with the applicable provisions of 40 CFR 264 " Standards For Owners and Operators of Hazardous Waste  !

Treatment, Storage, and Disposal Facilities," and 40 CFR 265 " Interim Status Standards For Owners and Operators of Hazardous Waste Treatment, Storage, and Disposal Facilities."

, Bnv:r V ll:y Powcr Station Unit 1 R: port of Facility Chang:s, Tests, and Exp; rim:nts January 23,1994 - January 22,1995 Page 6 of 63 CHANGE TITLE River Water System Valve Normal Position Changes DESCRIPTION OF CHANGE The nowal system alignment of various River Water System valves were changed to support plant operating needs. The following is a summary of the changes.

. Secondary Plant Component Cooling Hect Exchangers 3A, 3B and 3C Outlet Isolation Valves (1RW-30, 34, 35) will be throttled when the associated heat exchanger is in service and will be closed when the heat exchanger is not in service. This will decrease fouling of heat exchangers not in service.

. Chilled Water Unit Condensers 3A,3B and 3C Outlet Isolation Valves (1RW-49, 50, 51), will be closed when the associated heat exchanger is not in service. This will minimize heat exchanger tube fouling.

. River Water Pump Seal Water Regulating Valve (PCV-1RW-117) Bypass Valve (1RW-86) was opened and its isolation valves (1RW-87, 90, 682) were closed pending its replacement. Raw Water Pumps Bearing Cooling Water Outlet isolation Valves (1RW-671, 674) were throttled to regulate seal water pressure until replacement of the PCV.

. Primary Component Cooling Heat Exchangers 1A,18 and 1C Outlet isolation Valves (1RW-188,189,190) were aligned to have at least two outlet valves throttled (instead of one) to maintain sufficient backpressure while meeting heat load demands.

. Recirculation Spray Heat Exchanger Chemical Treatment Pump (1WR-P-4) Outlet isolation Valve (1RW-202) was closed because the pump was not normally in service. The pump will be aligned to the Reactor Plant River Water System and operated in accordance with procedures. All other valves associated with 1WR-P-4 were already closed.

. Isolation valves for Differential Pressure Indicator PDI-1RW-109 (1RW-216-1, 2) were closed because this PDI cell is normally not in service.

. The inlet valve (1RW-414) and outlet valve (1RW-415) for Duplex Strainer 1WR-S-8 must be properly coordinated to isolate flow through the strainer. This change was to permit the strainer to be normally isolated. The strainer provides river water as a backup to chilled water for containment air cooling.

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Beav:r Valley Pow:r Station Unit 1  !

-. Report of Facility Changes, Tests, and Exp3rimsnts  !

- January 23l 1994 - January 22,1995 Page 7 of 63

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CHANGE TITLE '

1 TOP-94-2 and 1 TOP-94-5, Operating the "B" and "D" Cooling Tower Pump Motors for- i

. Testing l

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DESCRIPTION OF CHANGE  ;

New temporary operating procedures were written to operate Cooling Tower Pump -

(1CT-P-1B,1D) motors,- uncoupled, for post maintenance testing of the motors. The  ;

procedures provided steps for installation and removal of two jumpers and one lifted -  !

- lead to allow the motors to be started (bypassing valve, timer and pressure interlocks). ,

Because the pump motors were uncoupled, thery. was no affect on the function of the  :

Circulating Water System.'

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. Braver Vall:y Power Station Unit 1

, , R port of Fccility Chtng:s, Tests, cnd Exp: rim:nts January 23,1994 - January 22,1995 Page 8 of 63 CHANGE TITLE 1 TOP-94-3, Dye Check of River Water Pipe DESCRIPTION OF CHANGE A new temporary operating procedure was written to confirm a suspected leak in the 6 inch river water supply line for Emergency Fuel Pool Cooling. The procedure provided steps for installation and removal of temporary equipment used for dye injection. This method of leak detection was necessary because the pipe (WR-119) is buried. The river water header supplying the suspect line was considered inoperable during the performance of this test; however the alternate header was fully operable.

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, B:av:r Valley Power Station Unit 1 Report of Facility Changes, Tests, and Exp rim:nts January 23,1994 - January 22,1995 Page 9 of 63 CHANGE TITLE 1 TOP-94-7, Operational Test for DCP-2092, Main Transformer Replacement DESCRIPTION OF CHANGE A new temporary operating procedure was written to verify that the replacement main transformer design and operating characteristics met the intended service requirements. Engineering evaluations confirmed the spare transformer would permit system protection standards to be maintained while providing the capacity to reliably deliver the Unit 1 electrical output to the system grid.

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,  :.. Banver Vallsy Power Station Unit 1 ,

., Report of Facility Ch:ngas, Tests, and Experim:nts -l January 23,1994 - January 22,1995  :

Page 10 of 63 -

i CHANGE TITLE ,

r Reactor Coolant . System Sample Header Containment Isolation Valves Position i Change

' CHANGE DESCRIPTION  ;

Samples obtained via sample valves from various points in the Reactor Coolant System .

(hot leg and cold leg) are fed to one of two headers which exit containment. The

, solenoid operated isolation valves (TV-1SS-102A1,102A2, .105A1,105A2) fc

• these headers were previously maintained open (energized). This change permitad the j valves to be normally deenergized to reduce valve intenance and increase valve  !

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. B::v r Vcilsy Pow:r Stction Unit 1 -

Report of Facility Changts, Tests, and Experim:nts c 0 c.-  ;

' January 23,1994 - January 22,1995 '

Page 11 of 63 '

i CHANGE TITLE '  :

Locking of River Water Return Header Isolation Valve - i F

CHANGE DESCRIPTION ,

. Valve 1RW-646 is an isolation valve in a river water return header which serves the  !

charging pump coolers, and control room air conditioning. ' This change permitted the i valve to be locked, avoiding inadvertent closure which would render all trains of the serviced components inoperable.

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., ' Beaver Valley Powar Station Unit 1

,- _ Report of Facility Changss, Tests, and Expsrimsnts ,  ;

' January 23,1994 - January 22,1995 i

~ Page 12 of 63 .l r- - 3 CHANGE TITLE I

~ Defeat of Residual Heat Removal (RHR; Tystem Automatic Isolation Function 1

CHANGE DESCRIPTION I

The RHR System Operating Procedures (10M-10.4.A, C) were revised to defeat automatic closure of the RHR isolation valves when the system is placed Linto service' )

and to restore the function upon shutdown of the system. This was done to increase- i plant shutdown safety by eliminating the possibility of unexpected RHR isolation.

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. Brav:r Valley Pow:r Station Unit 1

., R: port of Fccility Ch:ing s, Tests, cnd Experim:nts January 23,1994 - January 22,1995 Page 13 of 63 CHANGE TITLE Temporary Blank Flange on ERF Substation Dampers CHANGE DESCRIPTION When not in service, automatic ceiling dampers 1VS-D-121G and H will not close upon ,

fire detection. This can allow the escape of CO2 fire suppressant. This change-permitted installation of a blank flange to prevent CO2 escape.

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.. Beaver Valley Power Station Unit 1 ,

, . Report of Facility Changes, Tests,4cnd Experim:nts i

' January 23,1994 - January 22,1995 - ,

' Page 14 of 63. 1 CHANGE TITLE .

- Removal of Main Turbine Lube Oil Reservoir Drain Pump (LO-P-1) ll l

. CHANGE DESCRIPTION .

t LO-P-1 was removed for use as a replacement elsewhere in the Main Turbine Lube Oil '

System. The function of LO-P-1 can be accomplished using the lube oil purifier

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(LO-FL-1). ,

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B=ver Vcil y Pow r Station Unit 1

. R:: port of Fccility Chang:s, Tests, and Exp rim:nts January 23,1994 - January 22,1995 Page 15 of 63 CHANGE TITLE Temporary Modification to the Nitrogen Supply Manifold CHANGE DESCRIPTION The nitrogen supply manifold was partially removed and replaced with temporary hose and valves to provide access for excavation and replacement of the river water lines supplying the emergency diesel generators.

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Beaver Valley Power Station Unit 1 ,

Report of Facility Changes, Tests, and Experiments ' i January 23,1994 - January 22,1995 l Page 16 of 63'  ;

CHANGE TITLE j r

Temporary Modification to Change Normal Position of Blowdown isolation Valves q (11A-166 and ilA-167) for Containment Air Compressor Receivers .

CHANGE DESCRIPTION - '

I Moisture in the air receivers for the containment air compressors may be removed by two methods, (1) a mechanical condensate trap and (2) automatic solenoid blowdown ,

valves. Valves ilA-166 and 167 are provided to isolate the solenoid blowdown valves.

The normal position for these isolation valves has been changed to closed.  !

Condensate in the system will be removed by mechanical drain traps.

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, (Bodvar Valloy Pow:r. Station Unit 1..

Rcport of Facility Changes,. Tests, and Experim:nts

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. January 23l 1994_- January 22,1995 'l

'Page 17.of 63 q J

CHANGE TITLE ~ .!

' Leak Repair of "C" Steam Generator Hand-Hole.

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. CHANGE DESCRIPTION. i

. l The "C" Steam Generator developed a leak at the number.1 hend-hole. _ Retorquing the  ;

bolts did not stop the leak. This change permitted the hand-hole to be wire wrapped .!

,;.  : and injected with sealant.

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, Beaver Valley Power Station Unit 1 ,

. Report of Facility Chang s, Tests, end Exp; rim:nts January 23,1994 - January 22,1995 Page 18 of 63 CHANGE TITLE ,

Temporary Line to Chemical Waste Hold Tanks (WT-TK-24A,8)

CHANGE DESCRIPTION A temporary hose was installed to bypass a leaking section of 4 inch line to the chemical waste hold tanks. The hold tanks temporarily store byproducts from water treatment plant demineralizer regeneration.

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Be ver Vcil;y Power St: tion Unit 1 -

R: port of Facility Changes, Tcsts, and Experiments .  ;

January 23,1994 - January 22,1995  !

Page 19 of 63 .

CHANGE TITLE Installation of a Temporary Station Air Compressor i

~ CHANGE DESCRIPTION To compensate for diminished air capacity during overhaul of a Station Air Compressor .l (SA-C-1 A), a temporary diesel driven air compressor was connected to the Service Air System.

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,- ' Beaver Valley Power Station Unit 1

). - Report of Facility Changes, Tests, and Expsrimsnts January 23,1994 - January 22,- 1995 i Page 20 of 63 i

CHANGE TITLE'  ;

1 Temporary Modification of Station Air Compressor (SA-C-1B) Auto Start Feature CHANGE DESCRIPTION l The auto start feature of SA-C-18 was defeated when SA-C-1 A was in pull-to-lock (due  !

to overhaul). This was necessary to support operation of a temporary diesel air-  !

compressor which replaced SA-C-1 A.  ;

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, Be:ver Valley Power Station Unit 1

.. Report of Facility Chang s, Tests, and Exp:riments January 23,1994 - January 22,1995 Page 21 of 63 CHANGE TITLE Leak Repair of Cross-Under Piping Manway Covers CHANGE DESCRIPTION 1 Because leaks developed on the manway covers of the cross-under piping leading to the moisture separator reheaters, the manways were injected with sealant through injection capnuts and slotted studs.

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_ Beaver Vallsy Power Str. tion Unit 1 L

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. Report of Facility Ching:s, Tcsts,' and ExperimInts

January 23,1994 - January 22,1995 Page 22 of 63 1 CHANGE TITLE Installation of Temporary Heaters at the Refueling Water Storage Tank (RWST) f CHANGE DESCRIPTION  !

-Two thermostatically controlled heaters were added at the RWST.' In cold weather conditions, these heaters supplement existing heat trace to keep the area free of  :

moisture and maintain RWST piping at the proper temperature.  ;

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R port of Facility Changes, Tests,' and Experim:nts January 23,1994 - January 22,1995

. Page 23'of 63 CHANGE TITLE i Corrosion Control for Recirculation Spray and Diesel Generator Hest Exchangers i

CHANGE DESCRIPTION -

The UFSAR description was changed to allow mo,e flexibCy in the corrosion control method used for the Recirculation Spray Heat Exchangers. This change also evaluated removal of corrosion control loops for the emergency diesel generators.

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.. Beaver Valley Power Station [ Unit 1

, e ' Report of Facility Changas, Tests, and Experiments -j

-January 23,1994 - January 22,1995 i Page 24 of 63 ,

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^ CHANGE TITLE j L Temporary Modification to Support Safety injection Accumulator Discharge- Check-

- Valves Full Stroke Test

. .j CHANGE DESCRIPTION -i Level transmitters, a pressure transmitter, a recorder,.and wiring to connect these j instruments were temporarily installed to support testing of safety injection accumulator  ;

check valves. The test was completed and the modification was removed.

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.. Beaver Valloy Powar Station Unit 1

. .R: port of Facility Changas, Tests, and Exp riments

-January 23,1994 - January 22,1995 -

Page 25 of 63-

' CHANGE TITLE-g installation of a Blind Flange on River Water Chlorine injection Line CHANGE DESCRIPTION To permit repair'of a pinhole sized. leak, a 3 inch blind flange was installed in river

,1 water chlorine injection line WR-232-151-03. This temporarily disabled chlorination of the "A" River Water header. Repairs were made and the temporary modification was removed.

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. Brav:r Vall y Pow:r Station Unit 1

, R: port of Facility Chang:s, Tests, and Exp; rim:nts January 23,1994 - January 22,1995 Page 26 of 63 CHANGE TITLE installation of a Blind Flange on River Water Line CHANGE DESCRIPTION A 24 inch blind flange was temporarily installed in place of an expansion joint (REJ-RW-25R) on River Water Line WR-29-151-03. This was necessary to permit construction work and hydrostatic testing on part of the system without affecting the remainder. The work was completed and the temporary modification was removed.

i Braver Valley Pow:r Station Unit 1 Report of Facility Chang s, Tests, cnd Exp riments January 23,1994 - January 22,1995 ,

Page 27 of 63 CHANGE TITLE installation of a Blind Flange on River Water Supply Line to the "A" Emergency Diesel l Generator i

CHANGE DESCRIPTION A 4 inch blind flange was temporarily installed in place of an expansion joint (REJ-RW-9A) on one of two "A" emergency diesel generator river water supply lines (WR-597-151-03). This enabled construction work to be performed on the river water supply without affecting operability of the "A" diesel generator. The work was completed and the temporary modification was removed.

Braver Valley Pow :r Station Unit 1

, - R: port of Facility Chang:s, Tests, and Exp:riments January 23,1994 - January 22,1995 Page 28 of 63 CHANGE TITLE Temporary Modification to Remove Solid State Protection System Instrument Bus Status Lamp CHANGE DESCRIPTION This change permitted the status lamp, which indicates the presence of power to the instrument bus, to be removed from its damaged socket pending replacement of the socket. Permanent repairs subsequently restored this function.

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'Brnver Vallsy Pow r Station Unit 1

,- R port of Fccility Chang:s, Tests, cnd Exp:: rim:nts January 23,1994 - January 22,1995 Page 29 of 60 CHANGE TITLE Connection of Test Coupon Rack to Raw Water System CHANGE DESCRIPTION A test coupon rack was installed as a branch in the Raw Water System. This provided an experimental environment for testing sample piping materials and anti-corrosion treatments. Corrosion rates and water chemistry conditions can be monitored under experimental operating conditions. t l

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/ c Berver Vr.II:y Power Station Unit 1

, R: port of Facility Changes, Tcsts, and Experiments January 23,1994 - January 22,1995 Page 30 of 63 '

. CHANGE TITLE Temporary Modification to AMSAC. 1 CHANGE DESCRIPTION This safety evaluation was prepared to permit temporary modification of the ATWS.

Mitigating System Actuation Circuitry (AMSAC) upon failure of a feedwater flow channel. In the event of failure of one of three feedwater flow signals which are inputs to AMSAC, it is necessary to change from "2 of 3" logic to "1 of 2" logic to actuate AMSAC. To accomplish this, the temporary modification (which was prepared for future ,

use, only when needed) provided for a simulated low feedwater flow signal as a replacement to the failed feedwater flow channel input to AMSAC.

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c B::v:r Valley Power Station Unit 1 R: port of Facility Chang;s, Tcsts, cnd Exp riments .

January 23,1994 - January 22,1995  ;

Page 31 of 63 CHANGE TITLE Locking and Deenergizing of Charging Pump Recirculation Line Isolation Valve CHANGE DESCRIPTION Valve MOV-1CH-373 provides isolation of a charging pump recirculation line which serves multiple charging pumps. Because spurious closure of this valve can affect operability of more than one of these pumps, administrative controls have been changed to maintain it in a normally locked open and deenergized condition.

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BaaverValicy Powcr Station Unit 1 1, Report of Facility Changes l Tests, and Experim:nts ~

January 23,1994 - January 22,1995 Page 32 of 63'

.s CHANGE TITLE-Test Frequency Change for.Switchgear and Power Transformers . <

CHANGE DESCRIPTION' The testing frequencies provided in Table 8.6-1'of the UFSAR have been changed to 36 months for switchgear and power transformers.- Affected switchgear included 4kV -

'and 480 VAC- circuit breakers. The change in frequency did not affect reliability lof -

these components.

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c Beaver Valley Power Station Unit 1 ,

,- Report of Facility Changes, Tests, and Experim::nts

, January 23,1994 - January 22,1995 Page 33 of 63 CHANGE TITLE DCP-738, ' Replacement of Boron Recovery System Pressure Transmitters l

9 CHANGE DESCRIPTION The purpose of this modification was to replace a boron evaporator circulation pump  ;

4 pressure transmitter and an evaporator bottoms pump pressure transmitter with local pressure indicators (PI-BR-102B, PI-BR-111). -The transmitters' control room indicators 4

and annunciators were'also removed because the local indicators are sufficient. The transmitters were replaced because limited space made maintenance activities ,,

unreasonably difficult.-

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B::vIr Vall:y Power Station Unit 1-Rsport of Fecility Chang:s, Tests, end Exptrim:nts January 23,1994 - January 22,1995 Page 34 of 63 ~

CHANGE TITLE DCP-1450, Ventilation Modification to Maintain the Control Room Envelope Pressure CHANGE DESCRIPTION in order for the Unit 1 and Unit 2 Contrni Building pressures to be properly balanced, modifications to various pieces of ventilation equipment were necessary. When properly balanced, the Control Room envelope pressure is maintained at 1/8 inch W.G.

or greater with respect to atmosphere and positive with respect to adjacent areas.

Air conditioning and filter unit in-leakage, damper bypass leakage, and in-leakage through closed return air registers had caused difficulties with the proper balancing of control room ventilation. Temporary mooifications were performed in order to satisfy test acceptance criteria. This desigrh change made permanent modifications to limit in-leakage through the ventilation equipment.

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Beaver V lley Power Station Unit 1..

R: port of Facility Changes, Tcsts,'and Experiments

' January 23,1994 '- January 22,1995 Page 35 of 63 CHANGE TITLE DCP-1516, Spent Fuel Pool Capacity Expansion

- CHANGE DESCRIPTION Because Beaver Valley Power Station Unit 1 would have insufficient fuel pool storage capacity within the n3xt few fuel cycles, capacity was increased by replacing the storage racks with high density racks, increasing capacity to 1627 fuel assemblies.

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Bcavar Valley Powcr Station Unit 1 Report of Facility Changes, Tests, and Experiments I

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January 23,1994 - January 22,1995

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CHANGE TITLE l DCP-1551, Standby Alarm Interface to Merge / Isolate Cabinet 1

.. 5 CHANGE DESCRIPTION -  !

The Unit 1 and Unit 2 Page Party Systems are to be merged in the event of a' standby .

! alarm at either Unit. Unit 2 automatically merges the Page Party Systems v. hen the  :

standby alarm is activated. This Design Change incorporated a similar function for Unit l 1.

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Report of Fccility Ch

ngas, Tests, cnd Exp:rimsnts- ,

January 23,1994 - January 22,1995 -

Page 37 of 63 .;

CHANGE TITLE- 5 DCP-1913, Outage Communications Upgrade l l

CHANGE DESCRIPTION- r This design change relocated phones and installed additional phones, facsimile;  !

machines, and printers in the outage complex; installed network equipment and-personal computers in the south office shops building; installed a communication rack, network equipment and fiber optics in the Unit 1 relay room; installed. network i Lequipment and personal computers in the control' room; connected control. room equipment to the site computer network asing under carpet cable with polyvinyl chloride -

insulation; installed phone jacks outside containment at both units; installed network '

equipment in the Unit 1 computer room; and connected the Unit 1 office area personal ,

computers and printers to the site network computer. ' A communication link was_ also  ;

established between the Unit 1 relay room and warehouse addition. .l These changes were made to improve clearance coordination and the accuracy of. -

information transferred between the outage complex and control room, and among the  :

I various site organizations.

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, Report of Facility Changes, Tests, and Experiments January 23,1994 - January 22,1995 Page 38 of 63 CHANGE TITLE DCP-1915, Dedicated Dial Tone Lines for the NRC i l

l CHANGE DESCRIPTION l

This design change was to install a 25 pair telephone cable, five telephone jacks, and i five telephones in the Emergency Response Facility (ERF). The installation provided l dedicated emergency dial tone lines for the NRC Emergency Office in the ERF. The  ;

dedicated emergency dial tone lines were part of the NRC Emergency Notification System, FTS 2000.

Brever Vall y Power Station Unit 1 Report of Fecility Changes, Tests, cnd Experiments January 23,1994 - January 22,1995 Page 39 of 63 CHANGE TITLE DCP-1941, Modification of the Control Circuitry for Control Room Ventilation Dampers CHANGE DESCRIPTION This change made provisions for remote manual closure of control room ventilation dampers VS-D-40-1 A,1B,1C and 1D. Previously it was necessary to override control logic by removing damper power and manually cranking the damper shut. Power removal resulted in loss of position indication. The new configuration improves safety by reducing the possibility for error.

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'- _B:cvar Valloy Power Station Unit 1 Report of Facility Changas, Tests, and Exp:riments {

January 23,1994 -~ January 22,1995 -l Page 40 of 63 CHANGE TITLE DCP-1960, NRC Emergency Telecommunications (FTS-2000)

CHANGE DESCRIPTION This safety evaluation permitted installation of the FTS 2000 Telephone System replacing the existing Emergency Notification System (ENS) and Health Physics Network (HPN). The new communications system provides the following services: 1 (1) Reactor Safety Counterpart Link (RSCL), (2) Protective Measure Counterpart Link (PMCL), (3) Emergency Response Data System (ERDS), (4) Management Counterpart Link (MCL), and (5) Local Area Network (LAN).

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B;av:r Valby Power Station Unit 1 i l Report of Fecility Changes, Tests, and Exp2 rim:nts January 23,1994 - January 22,1995 Page 41 of 63 CHANGE TITLE DCP-1989, Replacement of HVAC Control Air System Drain Valves i CHANGE DESCRIPTION L Automatic Drain Valves 1CVS-206,207,208 and 209 for the HVAC Control Air System l were replaced by manual valves. The change is expected to increase reliability and

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1 simplify procurement of replacement parts.

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. Bsever Valloy Powcr Stetion Unit 1 Report of Facility Changos', Tests, and Exp:riments January 23,1994.- January 22,1995 Page 42 of 63 g

CHANGE TITLE DCP-2003, Test Fittings for Air Operated Valves i

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CHANGE DESCRIPTION L ~

- Air operated valve testing equipment requires pressure sensing ports at' various locations on the instrument tubing for AOV actuators. This change added test ports for-nonsafety related AOVs in the Heater Drains and Feedwater Systems. 1 L

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~; R: port of Facility Changss, Tcsts, and Exp: rim:nts January 23,1994 - January 22,1995 Page 43 of 63 CHANGE TITLE DCP-2011, Removal of the Auxiliary Boiler Fuel Oil Tank CHANGE DESCRIPTION

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The Auxiliary Boiler Fuel Oil Tank was retired in place by DCP-1543. This change subsequently removed the tank and eliminated the need to maintain and test the Fire Protection Foam System for the tank.

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. Report of Facility Changes, Tests, and Experiments ,

January 23,1994 - January 22,1995 i Page 44 of 63 l i

~ CHANGE TITLE .

t DCP-2012, Replacement .of Supplementary Leak Collection and Release System Differential Pressure Indicators 3

CHANGE DESCRIPTION Differential Pressure Indicators (PDI-VS-104-1 through 12 and 14) which were intended  !

to show the air pressure in areas served by the Supplementary Leak Collection and Release System have been replaced by Test Connections. The replacement was  :

made because the instruments, which lacked sufficient accuracy for testing purposes, were periodically being disconnected to attach test instrumentation which is used for ,

system performance verification. The instruments lacked provisions for calibration and j

were not useful to plant operators.

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Report of Facility Changes, Tests, and Exp: rim:nts .  !

i January 23,1994 - January 22,1995 Page 45 of 63 1

CHANGE TITLE DCP-2041, Mechanical Seal Replacement for Ventilation System Pumps CHANGE DESCRIPTION This minor DCP replaced the existing stuffing box seal on the control room air conditioning water circulation pumps (VS-P-3A, B) with a split ring type mechanical seal. This new seal acts to limit the water leakage to less than the stuffing box seal !

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R: port of Facility Changes, Tests, and Exp:riments January 23,1994 - January 22,1995 Page 46 of 63 CHANGE TITLE DCP-2075, Gland Steam Extraction Fans Structural Modifications CHANGE DESCRIPTION This change allowed the inlet spool piece to Gland Steam Exhausters CN-SC-2A and 2B to be cut and fitted with a shock absorbing splice of ethylene propylene as a means to reduce operational vibration. The splice was to be attached with stainless steel clamps, making a tight connection with each section of the spool piece.

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' Beaver Valloy Power Station Unit 1 Report of Facility Changes, Tests, and Experimnnts .

January 23,1994L- January 22,1995 -

Page 47 of 63 -

m CHANGE TITLE DCP-2076,- Conduit Support Bracing

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CHANGE DESCRIPTION This modification entailed adding a separate brace to each of two conduit supports -

located in the "C" Charging Pump Cubicle. One support was for conduits 1CX717NA9,-

1CX707NF3 and a 1/2" instrument air line.: The~ other support was for conduits 1CX707NF5 and 1CX707NF4. The addition of these' support braces was to ensure the supports would be capable of withstanding the anticipated loading caused by a seismic event.

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n Report of Facility Changes, Tests, and Expariments -

January 23,1994.- January 22,1995 Page 48 of 63 t .

s CHANGE TITLE DCP-2079, Removal of Plastic Liquid Waste Piping h CHANGE DESCRIPTION k

This safety evaluation ' applied to removal of a plastic.1-1/2 inch liquid waste pipe.

between valves 1LW-400 and 1LW-408. The valves were to be closed and capped.

This line was used for processing liquid waste from steam generator drain tanks LW-TK-7A and 78 through liquid waste demineralizer LW-l-1. It was'noinonger used because liquid waste was being processed via another demineralizer.

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Beaver Valloy Powcr Station Unit 1 7 Report of Facility Changes, Tests, and Experiments i January 23,1994 January 22,1995 Page 49 of 63 CHANGE TITLE DCP-2086, Valve Operator Torque Switch Bypass / Heater Removal CHANGE DESCRIPTION

~ This change permitted 98 MOVs to have a limit switch adjustment made so that the open torque switch will be bypassed for 90% of the valve open cycle rather than 5% to 20% of the open cycle. The limit switch adjustment reduces the amount of time .

required to perform valve testing. Most of these MOVs fall under the scope of Generic Letter 89-10.

Electric heaters, located in the limit switch compartments of eight Limitorque operators, were de-energized and removed. Heater removal was intended to avoid the possibilityi of a heater failure affecting the Class 1E power supply. The heater's only function was to minimize moisture related degradation during storage of these operators.

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Beaver Valley Power Station Unit 1 l '

Report of Facility Changes, Tests, and Experiments l , January 23,1994 - Ja'.iuary 22,1995

(- Page 50 of 63

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CHANGE TITLE DCP-2092, Main Transformer Replacement CHANGE DESCRIPTION This design change replaced the Unit 1 Main Transformer with a transformer ha approximately one half the impedance. To accommoda contribution of the offsite power network to the short circuit current (faults) that Uni Unit 2 may experience.

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Rcport of Facility Changes, Tests, and Experiments  !

January 23,1994 - January 22,1995 Page 51 of 63 i

CHANGE TITLE DCP-2096, Remove Reactor Coolant Pump Seal Differential Pressure Indicator l t

CHANGE DESCRIPTION Thermal Barrier Labyrinth Seal Differential Pressure Indicator PDI-CH-125 and its root isolation valves were permanently removed from flanged taps on Reactor Coolant Pump 1C. Blind flanges were used to seal off the lines. This change was intended to -

eliminate potential sources of leakage.

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Report of Facility Changes, Tests, and Experim:nts January 23,1994 - January 22,1995 Page 52 of 63 CHANGE TITLE DCP-2110, Install Ground at Output Common For isolator TM-RC-4338 CHANGE DESCRIPTION The modification placed a ground on the negative 4-20 ma' signal between isolators TM-RC-433B and TM-RC-433C. Installation of the ground was intended to eliminate noise which interfered with calibration of Comparator TC-RC-433. Comparator TC-RC-433 provides an interlock for opening cold leg loop stop valve MOV-1RC-595.

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Report of Facility Changes. Tests, and Experiments

January 23,1994 - January 22,1995 i Page 53 of 63

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CHANGE TITLE- l l TER-5906, Supplementary Leak Collection and Release System Design  ;

Reconciliation  ;

i CHANGE DESCRIPTION  :

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These safety evaluations were performed because changes to the UFSAR resulted {

from reconciliation of.various Supplementary Leak Collection and Release System ,

(SLCRS) _ design _ documents. No physical changes to ' the plant- were involved.

Changes to the UFSAR include SLCRS flow rates to serviced areas, normal damper  ;

positions and clarification of operating practices.

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Beaver Valley Power Station Unit 1  ;

Report of Facility Changes, Tests, and Experiments January 23,1994 - January 22,1995 Page 54 of 63 CHANGE TITLE l TER-7828, Relocation of Class Break for Containment Vacuum Piping CHANGE DESCRIPTION

=I Because DCP-621 removed the internals of inside containment check valves in containment vacuum lines CV-1 and CV-2, the Safety Class Break located at each

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check valve was no longer appropriate. TER 7828 permitted relocation of the class breaks to the respective containment penetration for each check valve.

3 8:nv:r Vclicy Powar Station Unit 1 R: port of Facility Changes, Tcsts, and Experim::nts January 23,1994 - January 22,1995

' Page 55 of 63 CHANGE TITLE TER-8071, Replacement of River Water Pipe Drain Valve I

CHANGE DESCRIPTION A carbon steel globe valve low point drain for the river water pump (WR-P-1A) discharge pipe (WR-1-151-03) was replaced with a stainless steel (with carbon steel end pieces) ball valve. The ball valve design is much less likely to clog or corrode than the globe valve.

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Beaver Valley Powcr Station Unit 1 -

Report of Facility Changes, Tests,.and Expnriments January 23,1994 - January 22,1995 Page 56 of 63 CHANGE TITLE TER-8484, ' Reclassification of Portions of BV-1 Raw Water System

' CHANGE DESCRIPTION This TER changed the OA Category of select piping and components in the Raw Water System from OA Category I to Category ll, Seismic Category ll. ; The new classification is a more accurate reflection of the components' safety functions and was implemented to improve testing program efficiency.

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Beaver Valley Power Station Unit 1  ;

Report of Facility Changes, Tests, and Experiments l January 23,1994 - January 22,1995 Page 57 of 63 i CHANGE TITLE TER-8696, Reconciliation of Safety Injection System VONDs, Flow Diagrams and UFSAR Figures CHANGE DESCRIPTION The Valve Operating Number Diagram (VOND), Flow Diagram and UFSAR Figures for the Safety injection System were being incorporated into a CAD drawing that replaces all of these. Because the drawings being replaced did not always show the same normal valve positions for some valves, the position shown in the UFSAR was sometimes changed to achieve consistency. The safety evaluation for this TER considered each of these instances. No physical changes to the plant resulted.

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Beaver Valley Power Station Unit 1 Report of Facility Changes, Tests, and Exp;riments January 23,1994 - January 22,1995 Page 58 of 63

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CHANGE TITLE TER-8808, Setpoint Study Changes CHANGE DESCRIPTION The results of a Westinghouse analysis documented in WCAP 11419, Revision 1, .

. provided revised design information concerning reactor trip and ESF setpoints. The safety evaluation for this TER permitted the UFSAR to be revised to reflect this analysis. No physical plant changes were made.

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,"- Besvar Vallsy Powcr Station Unit 1' Report of Facility Changes, Tests, and Exparimsnts January 23,1994 - January 22,1995 i F ->

Page 59 of 63 i

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. CHANGE TITLE -

TER-8952, Fuel Assembly and Component Drawing Changes ]

'iP CHANGE DESCRIPTION ' -

t The purpose of this TER was to evaluate several vendor drawings of fuel assemblies,-  ;

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fuel rods, vibration damping assemblies and part-length power suppression assemblies planned for use in Cycle 11. Various UFSAR changes resulted.-

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~ Report of Facility Changes, Tests, and Experimsnts '

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• January 23,1994 - January 22,1995 Page 60 of 63

' CHANGE TITLE .

TER-9289, Steam Generator Tube Sleeving l

CHANGE DESCRIPTION 1 1

This TER initiated UFSAR changes to allow. steam generator tube repair.. by laser -

welded sleeving. This methodology was described in a report (WCAP-13483) which ,

.was approved for use at BVPS-1 by the NRC.

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Page 61 of 63 ';

CHANGE TITLE {

,UFSAR Change to Allow Use of Equivalent Materials i

ICHANGE DESCRIPTION The UFSAR' was changed to eliminate the_ need t'o update the UFSAR .when a ,

component /part material is replaced with an alternative which is determined to be ,

equivalent. This UFSAR change allows specific materials to be. replaced with  ;

equivalents while maintaining the baseline material documentation in the UFSAR. A ~ ,

section (1.8.2) was added to the UFSAR to explain the concept of equivalency and its -;

application to materials found in the UFSAR.  :

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Baaver Valley Power Station Unit'1 - i

/*-  : Report of Facility Changss, Tests, and Expsrimants' '~

' January 23,1994 - January 22,1995 l Page 62 of 63 i

CHANGE TITLE ~

Excavation of River Water Lines CHANGE DESCRIPTION l Safety evaluations were prepared to accommodate immediate temporary repairs and' subsequent permanent repairs (DCP 2104) to buried river water lines serving the - ,

emergency diesel generators. Because the normally buried lines were to be exposed during various. shutdown and operating modes, potential hazards to the piping were evaluated.

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• Beaver Valley Power Station Unit 1

.x,,< i- ' Report of Facility Changes, Tests, and Experiments

• ' Januarj' 23,1994 - January 22,1995

', Page 63 of 63 I

- CHANGE TITLE l Updated Evaluation of the Effects of High Energy Breaks Outside Containment  !

I CHANGE DESCRIPTION i

UFSAR Appendix D provides a report of the effects of line breaks outside containment. -

'!t was interded to be maintained as a historical document describing analyses and j assumptions wh'f were used at the time of p'. ant licensing. This safety evaluation was i i performed to incorporate more recent information which reflects the current licensing l basis in the appendix. Current information includes such topics as changes to periodic  !

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visual leak checking practices, changes to testing practices for devices which detect l' breaks, changes to operator actions in response to breaks, changes to the design

. basis, and changes which reflect currently instal!ed mitigation features.

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