ML20107M205
| ML20107M205 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/23/1996 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9604300250 | |
| Download: ML20107M205 (32) | |
Text
-
.e e
a 8
ver Vaney Power Station f
Shippingport. PA 15077-0004 l
SUSHIL C.JAIN (412) 393 6512 DMsaon Vice President Fax (412) 643-8069 April 23, 1996 U. S. Nuclear Regulatory Commission Attention: Documeet Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Report of Facility Changes, Tests and Experiments In accordance with 10 CFR 50.59, the Annual Report of Facility Changes, Tests, and Experiments for the Beaver Valley Power Station, Unit No. 2, is attached. This report provides a brief description of each facility and procedure change and a summary j
of the safety evaluations. The annual report covers the period of November 1,1994, through October 31,1995.
l Each change was evaluated to detennine (1) if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Updated Final Safety Analysis Report may be increased, or (2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the Updated Final Safety Analysis Report may be created, or (3) if the margin of safety as defined in the basis for any technical specification is reduced. In each case, it was determined that the change did not constitute an unreviewed safety question as defined in 10 CFR 50.59.
If you have any questions regarding this report, please contact R. K. Brosi, Manager, Nuclear Safety, at (412) 393-5210.
Sincerely, a
300004 Sushil C. Ja.m Attachment c:
Mr. L. W. Rossbach, Sr. Resident Inspector I O Mr. T. T. Manin, NRC Region 1 Administrator 0UAi1if Mr. D. S. Bd
- man, Sr. Project Manager
]I ENERGY 9604300250 960423 PDR ADOCK 05000412 R
1 i
e
=
Beaver Valley Power Stction Unit 2 e
Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 TABLE OF CONTENTS Title P. nan DCP-868, ELIMINATION OF METEOROLOGICAL TOWER RECORDERS FROM THE UNIT 1 CONTROL ROOM..............................................................,.....,,,...,..,...,,,,,.,,....,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,1 DCP-912, ADD LOCAL INDICATION TO 2SWC-FS107A, B AND C....
................1 DCP-1018, REV,1, ADDITIONAL REAC TOR COOLANT LEVEL INDICATION...................................1 DCP-1126, LARGE BORE PRIMA RY COMPONENT SNUBBER ELIMINATION.......
=2 DCP-1135, SMALL BORE SNUBBER OFTIMIZATION.,........................................................... 3 DCP-1208, REV.1, ADDITION OF SPENT REdIN TRANSFER BOOSTER PUMP PRESSURE INDICATORS i
AND HIC DEWATERING SAMPLE COLLECTION TANK........................................................... 3 DCP-1337, BORIC ACID TO BORIC ACID BLENDER FLOW CONTROL VALVE CONTROL PROBLEMS. 4 DCP-1465, STEAM GENERATOR 2RCS*SG21B TUBE-SHEET ACCESS....................
........4
. DCP-1469, RESISTANCE TEMPERATURE DETECTOR BYPASS MANIFOLD ELIMINATION............... 4 DCP 1658, CONTAINMENT AIR COMPRESSORS 2IAC-C21 A AND B RELIABILITY MODIFICATIONS... 5 DCP-1662, CHIU Pn PUMP CONTROL MODIFICATION............................................................$
DCP-1769, REPLACE SWING DISC CHECK VALVES WITH IN LINE CHECK VALVES.......................... 5 DCP 1815, ADDITION OF VALVES AND GAUGES TO THE UNIT 2 INSTRUMENT AIR COMPRESSORS 2IACC1 A AND B..........
................................................................................6 DCP-1825, LODTRAK RELAY REPLACEMENT...................
........................................................6 DCP-1906, MAIN PLANT CARBON DIOXIDE DISCHARGE HEADER PRESSURE GAUGE................. 6 DCP-1921, ADD HIGH PRESSURE SAMPLE TAPS TO UNIT 2 TURBINE PLANT SAMPLE PANEL FOR CORROSION MONITORS.,
.................................................................................7 DCP-2063, CONDENS ATE PUMP SEAL WATER..................................................................... 7 DCP-2066, RELOCATION OF SEISMIC MONITOR............................................................. 7 DCP-2070, MIDLAND WATER SUPPLY - CONNECTION TO SITE DOMESTIC WATER SYSTEM............. 8 DCP 2077, DELETION OF BYPASS AND INOPERABLE STATUS INDICATION INPUTS Y3553D ANDY5639D................................................................................................................................8 DCP-2087, DOMESTIC WATER TAP IN AUXILIARY BOILER ROOM................................................ 8 DCP-2095, REV.1, NITROGEN TRUCK CONNECTION....................................................
...9
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 TABLE OF CONTENTS Title P. ass DCP-2142, AUXILIARY FEEDWATER LINE PRESSURIZATION.......
.........................................9 DCP-2143, INSTALLATION OF BRANCH LINES ON THE INSTRUMENT AIR AND STATION AIR SYSTEMS................................................................
10 DCP-2144, MODIFICATION OF SECONDARY PLANT COMPONENT COOLING WATER HEAT l
EXCHANGER SERVICE WATER SUPPLY ISOLATION VALVES..............
...... 10 1
DCP-2160, RADIOLOGICAL ACCESS TRACKING SYSTEM..........................................
....... 10 l
TER-7311, BALL VALVE REPLACEMENT FOR DRAIN VALVE 2IAS-422..............
..... 11
.l TER-9040, REPLACE PORTIONS OF THE CARBON STEEL FILTERED WATER LINE INSIDE THE UNIT 2 l
COOLING TOWER PUMP HOUSE WITH STAINLESS STEEL..............................
.11 l
l TER 9314, RETIRE EMERGENCY DIESEL GENERATOR DAY TANK LEVEL INDICATORS.
..............11 TER 9336, REACTOR VESSEL HEAD CLOSURE STUDS STUCK IN THE VESSEL FLANGE...................12 TER-9424, EVALUATE REPLACEMENT ISOLATION VALVES FOR MAIN STEAM DISCHARGE OFF-l LINE RADIATION MONITORS.,..............
... 12 TER-9498, UPDATE OF INTAKE STRUCTURE TEMPERATURE LIMITS AND VENTILATION REQUIREMENTS...........................................................
- 12 TER-9540, AIR PILOT VALVE 2TMB-HYV101 VENT CONNECTION.................................................13 i
TER-9601, TURBINE CONTROL SYSTEM CLOSE INTERCEPT VALVE FUNCTION................................13 TER-9851, STROKE ADJUSTMENT FOR DIESEL GENERATOR BUILDING RETURN AIR DAMPERS....13 TER-9866, ISOLATION OF SEAL WATER TO STEAM GENERATOR BLOWDOWN EVAPORATOR FEED PUMPS......................
..........................................................................................14 UFSAR CHANGE TO ALLOW USE OF EQUIVALENT MATERIALS.................................................14
]
REVISE BEAVER VALLEY POWER STATION SWITCHYARD 138 KV BU3 TIE PROTECTION TO ACCOMMODATE SHIPPINGPORT TAP REMOVAL...................................
.................14 DESIGN BASIS CHANGE FOR CABLE VAULT AND ROD CONTROL AREA AIR CONDITIONING UNrrS 2HVR*ACU208A AND B..
...... 15 j
i l
l TEMPORARY MODIFICATION ASSOCIATED WITH EMERGENCY SWITCHGEAR VENTILATION SUPPLY FAN CONTROL CIRCUIT.....
...............................................15 TEMPORARY MODIFICATION FOR ADDITION OF SPRINKLERS TO TEMPORARY OUTAGE STRUCTURES.............................
................15 I
t
Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 i
TABLE OF CONTENTS I.1111 EAgt s
TEMPORARY MODIFICATION OF FLOW ELEMENT FOR AUXILIARY BUILDING AIR CONDITIONING UNIT........................................................................
...........................................16
)
i l
TEMPORARY MODIFICATION TO CONTROL ROOM AIR CONDITIONER STRAIhER 2SWS-STR25.....16 i
TEMPORARY MODIFICATION TO ADD INSTRUMENTATION AND INSULATION TO VARIOUS COMPONENTS ON THE REFUELING WATER STORAGE TANK........
....... 16 TEMPORARY MODIFICATION 'IO PROVIDE TEMPORARY SPRINKLER PROTECTION FOR TEMPORARY TRAILERS AND STRUCTURES ON THE TURBINE DECK......
.. 17 HEAVY LOADS LIFT OVER SAFEGUARDS AREA............
.......... 17 TEMPORARY MODIFICATION 2-95-011, LOCKING LOOP STOP VALVE HANDWHEELS TO MAINI'AIN l
THE VALVE IN THE OPEN POSITION...
.................................................17 j
REMOVAL OF TORQUE SWITCH LIMITER PLATES DURING STATIC TEST OF PRIMARY COMPONENI' COOLING WATER HEADER INSIDE CONI'AINMENT ISOLATION VALVES...................18
\\
l TEMPORARY MODIFICATION TO REPAIR PIPE DOWNSTREAM OF MANUAL DRAIN VALVE 2FWS-277..
......... I 8 i.
i TEMPORARY MODIFICATION TO RELIEF VALVE 2 MSS-RV100..........................................18 l
1 TEMPORARY MODIFICATION TO REPLACE ROAD LIGHTING POWER CABLE..................................19
.h 1
i TER 9713, PERMANENT INCORPORATION OF TEMPORARY MODIFICATION 2-93 7.........................19 i
2OM 30.3.B.1, SERVICE WATER SYSTEM VALVE LIST....................
.......................19 i
TEMPORARY MODIFICATION TO AUXILIARY BUILDING AIR CONDITIONING UNIT I
DAMPER POSITION,.....
...........................................20
.i TEMPORARY MODIFICATION TO PROVIDE EMERGENCY RESPONSE FACILITY 4160 AND 480 VOLT RELAY CONTROL POWER.......
.......................................................................20 i
COOLING WATER SYSTEM MONITORING STATION CONNECTION TO SECONDARY COMPONENT COOLING WATER HEAT EXCHANGER VENT FOR CHEMISTRY PROCEDURE C.M. 2 3.79A............... 20 s
INSTALLATION OF AN AUDIO / VISUAL CCTV SURVEILLANCE SYSTEM DURING THE FIFTH MAINTENANCE AND REFUELING OUI' AGE.................
.........................................21 I
l OFFSITE DOSE CALCULATION MANUAL, APPENDIX C SURVEILLANCE REQUIREMENT CHANGE. 21 4
l OFFSITE DOSE CALCULATION MANUAL APPENDIX C CONTROL 3.3.3.10 CHANGE..................... 21 1
UFSAR SECTION 2.3.3.1 ONSITE hETEOROLOGICAL MEASUREMENT PROGRAM DESCRIPTION.... 22
]
CHANGE TO CRITERIA FOR INTERNAL SEALING OF OPEN ELECTRICAL CONDUlTS.................... 22 i
Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 TABLE OF CONTENTS Title P.Agt CONTAINMENT ISOLATION VALVE TABLE.............
.................................................22 FIRE PROTECTION EVALUATION REPORT CHANGE...........................................................
... 23 UPDATED FINAL SAFETY ANALYSIS REPORT SECTION 9.5.I, " FIRE PROTECTION" AND APPENDIX 9.5 A, " FIRE PROTECTION EVALUATION REPORT" CHANGES....
....... 23 REMOVE UFSAR REQUIREMENT FOR FIRE BOOSTER PUMP AND ASSOCIATED EQUIPMENT......... 23 OPERATING MANUAL CHANGE NOTICE 2OM-34.3.............
............ 24 CORE PHYSICS MONITORING DURING REFUELING...........................................
z24 CHANGE NORMAL SYSTEM ARRANGEMENT OF DECONTAMINATION BUILDING ROOF EXHAUST FANS TO STOP POSITION......................................
=24 2OST 33.13 C, MAIN PLANT CO ZONE PUFF TEST......................................
.............. 2 5 2
2OM-10.4.A, C, RESIDUAL HEAT REMOVAL SYSTEM STARTUP, SHUTDOWN............................... 25 2OM-6.4X, OPERATION OF THE DISC PRESSURIZATION SYSTEM FOR LOOP ISOLATION VALVES USING SAFETY INJECTION ACCUMULATORS.
.................................25 2 TOP-95 02, LOSS OF ALL AC POWER WHEN VESSEL IS DEFUELED...............................
..............26 2 TOP 95 03, DRAIN /REFLOOD THE REFUELING CAVITY TO REPAIR THE FUEL TRANSFER SYSTEM 26 TEMPORARY MODIFICATION 2 95-10, FUEL TRANSFER SYSTEM EMERGENCY PULLOUT CABLE.. 26 2RP-5R-2.10 REFUELING PROCEDURE.................................................................................... 27 2OM 23B, 3.B.I, HIGH PRESSURE HEATER DRAINS VALVE LIST.............................................. 27 2 TOP 95-04, STROKE TEST OF STEAM GENERATOR ATMOSPHERIC STEAM DUMP VALVES DURING MODE 1...
..............................................27
1 Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments i
November 1,1994 - October 31,1995 Page1of27 CHANGE TITLE DCP-868, Elimination of Meteorological Tower Recorders from the Unit 1 Control Room 1
CHANGE DESCRIPTION l
With the installation of the Atmospheric Radioactive Effluent Release Assessment System (ARERAS) computer, operation of the cuteorological chart recorders located in the Control Room became unnecessary.
This modification disconnected and removed four (4) meteorological strip chart recorders (SDR-MT-200, 201, 202 and XR-MT-600), and the panel they were mounted in (PNL-MET-RECD).
CHANGE TITLE i
DCP-912, Add LocalIndication to 2SWC-FS107A, B and C CHANGE DESCRIPTION Service Water System flow switches 2SWC-FS107A, B and C were modified by adding a faceplate to provide local flow indication. Each flow switch is located in a service water line downstream of a chilled water condenser.
CHANGE TITLE i
DCP-1018, Rev.1, Additional Reactor Coolant LevelIndication l
CHANGE DESCRIPTION The NRC issued Generic Letter No. 88-17 concerning loss of Residual Heat Removal (RHR) while the RCS is partially filled. In response to this letter, the Reactor Coolant System (RCS) mid-loop level indication was upgraded. This design change added a narrow range level transmitter in parallel with existing "C" loop level transmitter 2RCS-LT-102; added a digital indicator (to monitor vessel level) and Control Room annunciator to level transmitter 2RCS-LT102; and added an ultrasonic level transmitter on the "A" loop hot leg. The mounting hardware for the ultrasonic transmitter was permanently installed on the "A" hot leg.
Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments L
November 1,1994 - October 31,1995 3
Page 2 0f 27 i
l CHANGE TITLE 4
DCP-1126, Large Bore Primary Component Snubber Elimination i
i CHANGE DESCRIPTION j
'l Changes to 10 CFR 50 Appendix A, General Design Criterion 4 allow for the exclusion of reactor coolant loop breaks as a design basis. This design change included the following modifications and activities.
- 1. Removed large bore snubbers installed on the steam generator and reactor coolant pump supports. Rigid struts were installed in place of upper steam generator ring snubbers
- 2. Removed snubbers on the reactor coolant loop bypass lines.
}
- 3. Documented elimination of pressurizer surge line snubbers 2RCS-PSSP-001A and 2RCS-PSSP-001B, which were removed during pre-service inspection.
l
- 4. Optimized or eliminated approximately 80% of the snubbers on the following lines:
a) Three safetyinjectionlines
_ b) Two residual heat removallines 4
4 c) Three RTD manifold lines d) Three safety injection accumulator lines
- 5. Replaced snubbers PSA-1/4 and PSA-1/2, which could not be eliminated by analyses, with j
like kind replacements.
- 6. Decontaminated snubbers identified for disposal as needed.
These modifications are expected to reduce plant downtime, man-REM exposure, and maintenance efforts.
j l-j' I
i s
)
i 1
i I
Beaver Valley Power Station Unit 2 i
Report of Facility Changes, Tests, and Experiments i
November 1,1994 - October 31,1995 Page 3 of 27 CHANGE TITLE j
DCP-1135, Small Bore Snubber Optimization CHANGE DESCRIPTION 4
i This design change eliminated snubbers on small bore piping. Using ASME Code Case N-411 damping values, it was determined that the affected snubbers were not required.
These modificatior,s are expected to reduce plant down time, man-FEM exposure, and maintenance efforts.
CHANGE TITLE 1
i DCP-1208, Rev.1, Addition of Spent Resin Transfer Booster Pump Pressure Indicators and HIC Dewatering Sample Collection Tank CHANGE DESCRIPTION
[
This design change:
4 l
- 1. Added pressure indicators to the suction and discharge lines of spent resin transfer booster pump 2WSS-P21. These pressure indicators allow monitoring of the pump's performance without entering the pump cubicle, thereby enhancing overall system operability by allowing early detection of potential pump operating problems.
I
- 2. Installed instrumentation, piping, and a ten gallon HIC dewatering sample tank. The HIC dewatering sample tank (2WSS-TK21) and associated piping were installed in place of temporary hoses and a temporary sample tar.k to improve dewatering operations.
l
- 3. Added Condensate Polishing Building Compressed Air System line 2-SAS-750-948-4 (to i
supply air operated HIC Dewatering Pump 2WSS-P27), and isolation valve 2SAS-1012 (upstream of existing valve 2SAS-902). This permanent equipment replaced a temporary air hose to the pump.
i b
N I
Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 4 of 27 CHANGE TITLE DCP-1337, Boric Acid to Boric Acid Blender Flow Control Valve Control Problems 1
CHANGE DESCRIPTION Due to flow control problems associated with the boric acid to boric acid blender flow control valve (2CHS*FCV113A) wiring changes were made so that two flow control valves (2CHS*FCV113B and 2CHS*FCV114B), located downstream of the boric acid blender, do not close on a boric acid high flow deviation signal. Prior to the change the two flow control valves would close when 2CHS*FCV113 A was opened fully on a demand signal and the flow controller could not stabilize the process within the boric acid high flow deviation signal time delay.
l CHANGE TITLE DCP-1465, Steam Generator 2RCS*SG21B Tube-Sheet Access CHANGE DESCRIPTION This design change installed a two inch diameter inspection opening immediately above the tubesheet of Steam Generator 2RCS*SG21B and attached a removable insulation cover over the opening in the insulation panel. The opening provides access for removal of a foreign object identified by eddy current inspection.
CHANGE TITLE DCP-1469, Resistance Temperature Detector Bypass Manifold Elimination CHANGE DESCRIPTION This design change replaced the Resistance Temperature Detector (RTD) Bypass System with a temperature measurement system using RTDs in thermowells in the reactor coolant loop piping.
This modification is expected to increase reliability, and reduce worker radiation exposure and forced outages as a result of problems associated with maintenance and/or operability of the RTD bypass manifolds and associated components.
i c-.
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 5 of 27 CHANGE TITLE DCP-1658, Containment Air Compressors 2IAC-C21 A and B Reliability Modifications CHANGE DESCRIPTION This design change replaced ten check valves associated with the Containment Air Compressors (2IAC-C21A and B). The new check valves use a soft seating surface to help maintain a tighter seal and reduce compressed air leakage. Also, a drains trap was installed on compressor air dryer 2IAC-DRY 21. This permanent drains trap replaced temporary drains trap components installed to handle moisture removed by the dryer.
l CHANGE TITLE DCP-1662, Chiller Pump Control Modification CHANGE DESCRIPTION The Chilled Water System uses three pumps t.nd three chillers to service the chilled water loads.
An interlock which shuts down the chiller circulation pumps was removed so the pumps will remain on after a chiller cycles off. The pumps will only be stopped by operator action. The change allows the chillers to automatically cycle on and off as load requirements demand.
CHANGE TITLE DCP-1769, Replace Swing Disc Check Valves with In-Line Check Valves l
CHANGE DESCRIPTION This design change replaced main steam residual heat release swing check valves 2SVS-80, 81, and 82 with in-line check valves. The in-line check valves are better suited to the steam l
en'/.ronment at the valve locations.
l I
i
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 6 of 27 CHANGE TITLE i
DCP-1815, Addition of Valves and Gauges to the Unit 2 Instrument Air Compressors 2IAC-C21 A and B CHANGE DESCRIPTION I
This design change added a ball valve and two pressure gauges to the skid mounted instrument air compressors located in the Main Steam Cable Vault. The valve is upstream of the air unload J
solenoid, and the gauges are on the " low pressure switch" line, and on the air return from the heat exchanger.
l These modifications provide the ability to isolate the bypass solenoid, and monitor pressures to ensure proper compressor operation.
CHANGE TITLE i
DCP-1825, LODTRAK Relay Replacement i
CHANGE DESCRIPTION l
Relays providing overcurrent and overtemperature protection on 4160V motors were replaced to enhance reliability and reduce the number of unwanted plant trips. In addition, interposing relays were installed to elimir. ate the possibility of an electrical surge on the 600 feet of cable to the l
supervisory centact:. of the hot loop overcurrent relays, i
i CHANGE TITLE j
DCP-1906, Main Plant Carbon Dioxide Discharge Header Pressure Gauge i
CHANGE DESCRIPTION i
A local pressure gauge with associated root isolation valve was added to the Carbon Dioxide 4
(CO2) discharge header from CO2 Tanks 2FPO-TK-22, 23 and 24. Local header pressure readings may be used as an aid in detecting a leaking CO2 master valve (s) after routine testing of the CO2 Fire Protection System.
4
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 7 of 27
)
CHANGE TITLE DCP-1921, Add High Pressure Sample Taps to Unit 2 Turbine Plant Sample Panel for Corrosion Monitors CHANGE DESCRIPTION This design change installed 1/4 inch taps to provide high pressure secondary side samples for corrosion products monitors at the Turbine Plant Sample Panel. Integrated corrosion products sampling may be used to assess the secondary Chemistry Control Program.
CHANGE TITLE DCP-2063, Condensate Pump Seal Water CHANGE DESCRIPTION Temporary Modification 02-91-07 installed 3/4 inch tubing from the demineralized water pumps to the Condensate Pump Seal Water Supply Valve 2CNM-PRV120 discharge. The tubing provides a reliable supply of condensate pump seal water, since valve 2CNM-PRV120 could not operate reliably due to a large pressure drop across the valve.
The tubing between the demineralized water pumps and the condenser centerline was made permanent by DCP 1549, Condenser Tube Cleaning Modification. This design change (DCP-2063) permanently installed the remaining portion of tubing.
j Q&'OE TITLE DCP-2066, Relocation of Seismic Monitor GANGE DESCRIPTION The electronics portion of self contained triaxial time history accelerograph 2ERS-RRA-1 was relocated from the steam generator support cubicle to outside the crane wall to prevent failure due to high radiation dose rates. The accelerometer sensors are located on a steam generator support.
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 8 of 27 CHANGE TITLE DCP-2070, Midland Water Supply - Connection to Site Domestic Water System CHANGE DESCRIPTION A water meter pit was installed in the Site Engineering Building (SEB) parking lot, and the Borough of Midland water supply was connected to the ' Site" Domestic Water System. The Borough ofMidland supplies potable water to the site for drinking and sanitary purposes.
CHANGE TITLE DCP-2077, Deletion ofBypass and Inoperable Status Indication Inputs Y5553D and YS639D CHANGE DESCRIPTION The Bypass and Inoperable Status Indication (BISI) circuitry was designed for continuous diesel generator rocker arm pre-lube pump operation.
However, the pre-lube pumps are run periodically in accordance with plant procedures. When the pre-lube pump control switch was in the OFF position, the diesel generator support systems BISI alarm initiated.
This design change removed BISI inputs, initiated by diesel generator rocker arm pre-lube pump control circuits, from the diesel generator support systems logic. Relays and isolators associated with the electric rocker arm pre-lube pump status were retired / spared in place.
CHANGE TITLE i
DCP-2087, Domestic Water Tap in Auxiliary Boiler Room CHANGE DESCRIPTION This change provided a domestic water supply in the Unit 2 Auxiliary Boiler Room by installing a tee fitting, valve and hose bib in pipeline 2DWS-150-907-4. Domestic water may be used as a cooling water supply to the Auxiliary Boiler sample coolers.
}
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 9 of 27 CHANGE TITLE DCP-2095, Rev.1, Nitrogen Truck Connection CHANGE DESCRIPTION This design change made the following modificationsfunprovements to the Unit 2 Nitrogen Supply System. Relief Valve 2GNS-RV115 was relocated from inside the Condensate Polishing Building to the building exterior at the nitrogen truck connection. Pressure Control Valve 2GNS-PCV846 was removed from service. Small bore piping was installed at the location of the removed valves. The instrument air line was removed and a plug installed in the block valve l
upstream of valve operator 2GNS-PCV846. Check valve 2GNS-940, vent valve 2GNS-941, f
pressure regulator valve 2GNS-PRV-115, pressure indicator 2GNS-PIl15, associated small bore i
' pipe and fittings, and a weather hood were installed on the building exterior at the truck connection. Support 2GNS-PSR163T was modified and a new support 2GNS-PSR629 was l
installed. The line class break was relocated upstream of valve 2GNS-100.
1 j
CHANGE TITLE DCP-2142, Auxiliary Feedwater Line Pressurization CHANGE DESCRIPTION I
This design change modified the pipe restraint design for auxiliary feedwater lines inside containment to permit the lines to be maintained pressurized during normal plant operation. Pipe
~
supports were modified to be capable of withstanding new pipe rupture loading conditions.
I Crush bumper supports were installed in strategic areas to minimize pipe deflections following a l
postulated pipe rupture.
i r
g-
--wr-e
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 10 of 27 l
CHANGE TITLE DCP-2143, Installation of Branch Lines on the Instrument Air and Station Air Systems CHANGE DESCRIPTION One branch line was connected to the Instmment Air System and another was connected to the Station Air System. Each installation included a tee, piping, an isolation gate valve, appropriate i
fittings and supports. The end of each branch line has a threaded fitting that permits temporary l
connection of hoses to cross connect the two systems. The change provides a means to remove l
Instrument Air System components from service (for maintenance) while maintaining Instrument l
Air System capability.
CHANGE TITLE DCP-2144, Modification of Secondary Plant Component Cooling Water Heat Exchanger Service Water Supply Isolation Valves CHANGE DESCRIPTION The change removed the automatic closure on low service water header pressure of service water supply isolation valves (2SWS*MOV107B and C). These valves are in the lines that provide cooling water to Secondary Plant Component Cooling Water System (CCS) heat exchangers.
Before the change, low pressure in either service water header would automatically isolate both headers from the CCS. When cooling water is isolated to the CCS, the main turbine must be tripped manually within five minutes to prevent damage. The control circuitry was revised so that only the header experiencing low pressure will be isolated. The proposed cht.nge is expected to reduce the potential for damage to the main turbine.
i CHANGE TITLE DCP-2160, Radiological Access Tracking System CHANGE DESCRIPTION This design change replaced the self reading chamber type pocket dosimeters with an electronic
{
alarming type dosimeter. Alarming electronic dosimeter readers and associated ' fonnation m
handling equipment were also installed.
Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 l
Page 11 of 27 l
CHANGE TITLE l
TER-7311, Bali Valve Replacement for Drain Valve 2IAS-422 l
CHANGE DESCRIPTION l
A one inch bronze globe valve (2IAS-422) in the Station Instrument Air Receiver Tank drain line l
was replaced with a one inch brass ball valve. The ball valve has better isolation capabilities due to a flexing seat design.
CHANGE TITLE TER-9040, Replace Portions of the Carbon Steel Filtered Water Line Inside the Unit 2 Cooling Tower Pump House with Stainless Steel l
CHA'NGE DESCRIPTION I
Carbon steel piping, tubing, fittings and valves were replaced with stainless steel components.
The components are associated with four branch lines that carry filtered water from a common 11 inch header to each of the four cooling tower pumps.
CHANGE TITLE TER-9314, Retire Emergency Diesel Generator Day Tank Level Indicators CHANGE DESCRIPTION Emergency diesel generator day tank level indicators 2EGF-LI202A and B were retired in place by cutting and capping the sensing line at the indicator location. These indicators provided backup level indication for each day tank.
i
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 12 of 27 CHANGE TITLE TER-9336, Reactor Vessel Head Closure Studs Stuck in the Vessel Flange CHANGE DESCRIPTION This Technical Evaluation Report (TER) evaluated and found acceptable the condition of studs numbered 25,37 and 51. Each stud is bound in a vessel flange stud hole turned out 21, 2.0, and
} inch respectively from the normal position. Flat washers were placed under the existing closure
[
washer for the studs, raising the nuts sufficiently to engage the drive sleeve and accommodate a stud tensioning tool.
1 CHANGE TITLE l
i TER-9424, Evaluate Replacement Isolation Valves for Main Steam Discharge Off-line Radiation Monitors L
CHANGE DESCRIPTION Three isolation valves for main steam discharge off-line radiation monitors (2 MSS-RQ101 A, B, j
and C) were replaced. One inch gate valves were replaced with one inch globe valves. The
_ globe valves provide improved isolation capability when maintenance of the radiation monitors is required.
CHANGE TITLE i
TER-9498, Update ofIntake Stmeture Temperature Limits and Ventilation Requirements CHANGE DESCRIPTION This Technical Evaluation Report (TER) updated the UFSAR and engineering documents based on a re-evaluation of heat loads and temperature limits in the river water intake structure.
3 i
i 4
4 x
j o
l Beaver Valley Power Station Unit 2 i
l Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 t
Page 13 of 27 i
CHANGE TITI,E TER-9540,' Air Pilot Valve 2TMB-HYV101 Vent Connection CHANGE DESCRIPTION l
A 3/8 inch stainless steel tube was added from the Air Pilot Valve 2TMB-HYV101 hydraulic l
actuator vent port to a turbine electro-hydraulic (EH) system vented drain line. The modification returns the small amount ofEH fluid discharged from the vent port to the EH reservoir.
l CHANGE TITLE TER-9601, Turbine Control System Close Intercept Valve Function l
CHANGE DESCRIPTION The Turbine Control System was originally supplied with the Close Intercept Valve (CIV) function inhibited. This Technical Evaluation Report (TER) evaluated this condition and determined that it was acceptable to inhibit the CIV function.
CHANGE TITLE TER-9851, Stroke Adjustment for Diesel Generator Building Return Air Dampers CHANGE DESCRIPTION The closed limit of diesel generator building return air dampers (2HVD* MOD 22A and 22B) was adjusted to allow the dampers to be slightly open. The change permits sufficient infiltration to reduce the differential pressure across diesel generator room doors and to enable diesel generator building exhaust fans (2HVD*FN222A and B) to remove heat and fuel oil vapors.
l l
t
\\
l Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments i
November 1,1994 - October 31,1995 Page 14 of 27 CHANGE TITLE TER-9866, Isolation of Seal Water to Steam Generator Blowdown Evaporator Feed Pumps i
CHANGE DESCRIPTION i
This Technical Evaluation Report (TER) evaluated isolation of seal water to the steam generator i
blowdown evaporator feed pumps (2SGC-P22A and B). The normal system alignment of valve 2PGS-127 (located in the common seal water supply line to both feed pumps) was changed to i
closed. In addition, downstream solenoid valves (2PGS-SOV105A and B) located in seal water i
supply lines to each feed pump were electrically disconnected and retired in place.
CHANGE TITLE f
UFSAR Change to Allow Use ofEquivalent Materials l
CHANGE DESCRIPTION 1
The UFSAR was changed to eliminate the need to update the UFSAR when a component /part j
material is replaced with an alternative which is determined to be equivalent. This UFSAR i
change allows specific materials to be replaced with equivalents while maintaining the baseline l
material documentation in the UFSAR. A section (1.12) was added to the UFSAR to explain the l
concept of equivalency and its application to materials found in the UFSAR.
l I
CHANGE TITLE i
Revise Beaver VCley Power Station Switchyard 138 KV Bus Tie Protection to Accommodate Shippingport Tap Removal CHANGE DESCRIPTION Switchyard 138 KV Bus tie protection was modified to accommodate the de-energization of the Shippingport Atomic Power Station (SAPS) and remm! of the SAPS 138 KV tap.
m
Beaver Valley Power Station Unit 2
]
Report ofFacility Changes, Tests, and Experiments l
November 1,1994 - October 31,1995 Page 15 of 27 i
CHANGE TITLE 4
Design Basis Change for Cable Vault and Rod Control Area Air Conditioning Units 2HVR*ACU208A and B I
CHANGE DESCRIPTION The changes reflect the use of Supplemental Leak Collection and Release System (SLCRS) ventilation flow as a substitute for cooling previously provided by service water cooling coils.
l This includes cooling of ventilation flow in the rod control and cable vault areas.
1 j
CHANGE TITLE l
- Temporary Modification Associated W Emergency Switchgear Ventilation Supply Fan Control i
Circuit CHANGE DESCRIPTION i
Temporary modification of the Train B emergency switchgear ventilation supply fan white indicating light circuit allowed trouble shooting of the supply fan control circuit.
CHANGE TITLE Temporary Modification for Addition of Sprinklers to Temporary Outage Structures CHANGE DESCRIPTION A temporary water sprinkler fire protection system was installed to protect two temporary outage structures.
Beaver Valley Power St-tion Unit 2 Report of Facility Changes, Tests, and Experiments l
November 1,1994 - October 31,1995 Page 16 of 27 CHANGE TITLE Temporary Modification of Flow Element for Auxiliary Building Air Conditioning Unit CHANGE DESCRIPTION This temporary modification installed a pitot tube in the ventilation ductwork upstream of malfunctioning flow element 2HVP-FE211A. The pitot tube provided differential pressure to flow transmitter 2HVP-FT211A and flow indicator 2HVP-F1211A until flow element 2HVP-
- FE211A could be repaired. Flow element 2HVP-FE211A provides information about flow c..nditions downstream of Auxiliary Building Air Conditioning Unit 2HVP-ACU211A. The matfunctioning flow element supplied a lower than expected differential pressure signal to flow transmitter 2HVP-FT211 A which resulted in a low flow alarm.
CHANGE TITLE Temporary Modification to Control Room Air Conditioner Strainer 2SWS-STR25 CHANGE DESCRIPTION This temporary modification replaced a 20 mesh strainer element with a 60 mesh element. The change is expected to reduce clogging of the downstream temperature control valve (2SWS-TCV101 A) for a control room air conditioning unit.
CHANGEN eTLE Temporary Modification to Add Instmmentation and Insulation to Various Components on the Refueling Water Storage Tank CHANGE DESCRIPTION This temporary modification installed an electric heater and air ducts to provide supplemental heat to sensing lines for Refueling Water Storage Tank Level Transmitters 2QSS-LT104A, B, C, l
and D.
l l
\\
i l
Beaver Valley Power Station Unit 2 j
Report ofFacility Changes, Tests, and Experiments j
November 1,1994 - October 31,1995 Page 17 of 27 CHANGE TITLE Temporary Modification to Provide Temporary Sprinkler Protection for Temporary Trailers and Structures on the Turbine Deck CHANGE DESCRIPTION A temporary sprinkler system was installed to provide fire protection for temporary outage j
trailers and structures during the fifth refueling outage.
i CHANGE TITLE Heavy Loads Lift Over Safeguards Area CHANGE DESCRIPTION Six heavy load lifts over the Safeguards Building were required for repair of Recirculation Spray Pump 2RSS-P21A. Three lifts occurred during disassembly, and three lifts occurred during reassembly of the pump. The heavy loads included a Safeguards Duilding roof plug, the pump motor, and the pump bowl assembly.
CHANGE TITLE Temporary Modification 2-95-011, Locking Loop Stop Valve Handwheels to Maintain the Valve in the Open Position CHANGE DESCRIPTION The reactor coolant loop stop valve handwheels were chained to secure the valves in the open position. A 10 CFR 21 report indicated that torque switches could fail disabling the switch or preventing the switch from de-energizing the motor.
i L
1
s Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 18 of 27 CHANGE TITLE Removal of Torque Switch Limiter Plates During Static Test of Primary Component Cooling i
Water Header Inside Containment Isolation Valves CHANGE DESCRIPTION i
Corrective Maintenance Procedure CMPl/2-75-BARTS-1E required removal of the torque l
switch limiter plates from primary component cooling water supply and retum header inside-containment isolation valves (2CCP-MOV151-2 and 2CCP-MOV157-2, respectively). Removal of the limiter plate was necessary to obtain the torque setting value specified in the Master j
Equipment List. The limiter plate was not replaced.
i CHANGE TITLE i
4 Temporary Modification to Repair Pipe Downstream of Manual Drain Valve 2FWS-277 I
CHANGE DESCRIPTION Valve 2FWS-277 is a manual drain valve on the "C" main feedwater line. This valve had a small j
leak through its seat and downstream pipe cap. The leak was stopped by filling the downstream pipe and cap with leak repair sealant.
CHANGE TITLE Temporary Modification to Relief Valve 2 MSS-RV100 CHANGE DESCRIPTI')H Relief valve 2 MSS-RV100 is located on the bonnet of manually operated isolation gate valve 2 MSS-1 for the condene steam dump valve header. The relief valve was leaking. In order to stop the leak, piping downstream of the relief valve was cut and capped and filled with sealant.
This temporary modification rendered the relief valve inoperable.
t
I Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 19 of 27 1
j CHANGE TITLE Temporary Modification to Replace Road Lighting Power Cable i
CHANGE DESCRIPTION This temporary modification replaced defective power cable between two light poles with a i
temporary electricaljumper. The temporary electrical jumper ensured continued availability of l
security lighting during replacement of defective power cable.
i CHANGE TITLE l
TER 9713, Permanent Incorporation of Temporary Modification 2-93-7 l
CHANGE DESCRIPTION l
This evaluation determined acceptable, permanent incorporation of Temporary Modification 2-93-7. The temporary modification installed nylon strainer nets on the cooling tower discharge flume.
t k
. CHANGE TITLE i
j 20M-30.3.B.1, Service Water System Valve List j
CHANGy. DESCRIPTION i
i Unit 2 Operation Manual Service Water System (SWS) Valve List (20M-30.3.B.1) was changed to show tha normal system alignment of safeguards area air conditioning unit outlet valves (2SWS-717 and 718) " sealed throttled" instead of " sealed open." The change is expected to reduce flow velocity induced erosion of heat exchanger tubes.
)
Beaver Valley Power Stati:n Unit 2 Report ofFacility Changes, Tests, and Experiments j
November 1,1994 - October 31,1995 i
Page 20 of 27 CHANGE TITLE Temporary Modification to Auxiliary Building Air Conditioring Unit Damper Position CHANGE DESCRIPTION This temporary modification installed a regulator and tubing to bypass flow controller 2HVP-FC211B and vortex damper 2HVP-AOD21B positioner. With this modification the damper (2HVP-AOD21B) will no longer automatically modulate but will be manually controlled by a 4
regulator. The vortex damper 2HVP-AOD21B had failed open causing excess air flow through the cooling coils of the auxiliary building air conditioning unit.
i CHANGE TITLE Temporary Modification to Provide Emergency Response Facility 4160 ad 480 Volt Relay Control Power j
CHANGE DESCRIPTION j
This temporary modification provided a 48 Volt DC power source for Emergency Response Facility (ERF) 4160 and 480 volt bus 1 and bus 2 relays. The modification permitted ERF battery cell replacement while maintaining ERF relay control power.
CHANGE TITLE Cooling Water System Monitoring Station connection to Secondary Component Cooling Water Heat Exchanger Vent for Chemistry Procedure C.M. 2-3.79A
)
I CHANGE DESCRIPTION j
i Chemistry procedure C. M. 2-3.79A was revised to provide for installation of a cooling water monitoring station in parallel with non-safety related service water flow through the secondary component cooling water heat exchangers. The monitoring station will be used to observe the j
effects of chemical treatments and corrosion rates.
i i
i i
l l
l l
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experimer,ts November 1,1994 - October 31,1995 t
d Page 21 of 27 j
i CHANGE TITLE Installation of an Audio / Visual CCTV Surveillance System During the Fifth Maintenance and Refueling Outage CHANGE DESCRIPTION This temporary modification installed a closed circuit television surveillance system in the Reactor Containment Building for the Unit 2 maintenance and refueling outage. Installation of j
this system involves the routing ofIEEE rated cable which affects five fire stops and an eledrical penetration. Twelve surveillance camera subsystems were installed. This modification was made to reduce personnel exposure by applying ALARA principles.
I CHANGE TIILE Offsite Dose Calculation Manual, Appendix C Surveillance Requirement Change i
CHANGE DESCRIPTION Appendix C of the Offsite Dose Calculation Manual (ODCM) was revised to indicate that Turbine Building Sump sampling is to begin when primary to secondary leakage rate exceeds a specified value. Previously sampling was initiated when the gross beta gamma concentration in the secondary coolant exceeded a specified value. The change is consistent with the purpose of the ODCM requirement to identify actions necessary (e.g., sampling) when primary to secondary leakage is identified by other means.
CHANGE TITLE Offsite Dose Calculation Manual Appendix C Control 3.3.3.10 Change CHANGE DESCRIPTION Appendix C of the Offsite Dose Calculation Manual (ODCM) was revised to permit the use of special particulate, iodine, noble gas monitors (RM-VS-110, RM-VS-109, and RM-GW-109) as alt::rnate instruments for monitoring certain radioactive gaseous effluent ventilation pathways when the primary instruments (FR-VS-112, FR-VS-101, or FR-GW-108, respectively) are out-of-service for routine maintenance.
\\
e l
Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 22 of 27 CHANGE TITLE l
l UFSAR Section 2.3.3.1 Onsite Meteorological Measurement Program Description l
CHANGE DESCRIPTION The change removed the detailed description of two Atmospheric Radioactive Efflucnt Release Assessment System (ARERAS) accident dose assessment models. The UFSAR text continues to l
state that the system meets the intent of the real-time plume trajectory and dispersion calculation i
requirements in Appendix 2 of NUREG-0654 (which was the basis of applicable portions of the ARERAS design). Reference to daily review of meteorological data was revised to indicate that the data will be reviewed perbdically. The data are reviewed to identify anomalous conditions or h
instrumentation problems. l'.eview of data collected on Saturday, Sunday, and holidays is performed on the next busine s day.
CHANGE TITLE l
Change to Criteria for Internal Sealing of Open Electrical Conduits CHANGE DESCRIPTION This change revised the criteria for internal sealing of open electrical conduits found in the Beaver Valley Power Station (BVPS) Unit 2, Updated Final Safety Analysis Report (UFSAR).
Recent fire tests prod.ded the technical data to re-evaluate and revise the internal conduit scaling criteria. When the new criteria are applied, a fire protection engineering evaluation will be performed (following the guidance of NRC Generic Letter 86-10) to ensure the specific interrX conduit sealing configuration complies with the new criteria.
CHANGE TITLE Containment Isolation Valve Table CHANGE DESCRIPTION This change added Note 6 to the Containment Isolation Valve Table and applied it to auxiliary feedwater check valves 2FWE-42A,42B,43A,43B,44A,44B,99,100, and 101. Note 6 stater j
"Not subject to tb cquirements of Specifications 3/4.6.1 and 3/4.6.3." The note eliminates test requirements associated with the referenced Technical Specifications.
i s
Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 23 of 27 CHANGE TITLE Fire Protection Evaluation Report Change CHANGE DESCRIPTION This change revised UFSAR Section 9.5A, " Fire Protection Evaluation Report," criteria for fire l
l' barriers protecting certain equipment in fire area PA-3 (Auxiliary Building). The revised criteria i
ensure protection is provided commensurate with the fire hazards of the area as dermed in the fire hazards analysis for Unit 2 and the " Fire Protection Safe Shutdown Report."
l l
CHANGE TITLE l
l Updated Final Safety Analysis Report Section 9.5.1, " Fire Protection" and Appendix 9.5A, " Fire j
Protection Evaluation Report" Changes l
l CHANGE DESCRIPTION l
\\
\\
l This change affected the criteria for fire protection wrap of cables and associated safe shutdown l
components located in various fire areas. The criteria are identified in UFSAR Section 9.5.1 and Appendix 9.5A. The criteria for one hour barriers as applied to fire wrap protection was revised to credit fire rated material which provides protection commensurate with the hazards of the area.
l CHANGE TITLE Remove UFSAR Requirement for Fire Booster Pump ard Associated Equipment l
CHANGE DESCRIPTION The UFSAR was revised to eliminate references to the fire booster pump (2FPW-P36) and associated equipment. The booster pump was intended to address a postulated loss of function j
of both sprinkler and hose standpipe systems in an cea protected by primary and backup systems. It was determined that the single failure design cf the fire protection pumps and the
[
system configuration preclude such an event, without the need for a fire booster pump.
k I
]
i l
2
j Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 24 of 27 L
CHANGE TITLE '
Operating Manual Change Notice 2OM-34.3 CHANGE DESCRIPTION The normal system arrangement position of a 1" isolation valve (2IAS-607) was dianged from open to shut. The valve is located on a capped pipe line in the compressed air system.
CHANGE TITLE Core Physics Monitoring During Refueling CHANGE DESCRIPTION Reactor Surveillance Procedure 1/2RST-49.1, " Core Physics Monitoring During Refueling," is performed to monitor the source range detectors (i.e., reactivity of the reactor core) during core reload activities. This procedure was revised to allow the high flux at shutdown alarm and containment evacuation alarm for both source range channels to be blocked during the insertion of the first two fuel assemblies (i.e., the source bearing assemblies). This revision was necessary to prevent the alarms from continuously sounding in the containment during insertion of the source bearing assemblies.
CHANGR TITLE Change Normal System Arrangement ofDecontamination Building Roof Exhaust Fans to Stop Position CHANGE DESCRIPTION The Normal System Arrangement (NSA) of controls for the Decontamination Building roof exhaust fans (2HVQ-FN219A,B) was changed from the automatic (AUTO) to the stop (STOP) position. When fan controls are placed in the AUTO position, the fans will automatically start when high temperature is sensed in the Decontamination Building. 'With the new NSA, the fans may be started manually ifneeded.
~
m,
w Beaver Valley Power Station Unit 2 a
Report ofFr.cility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 25 of 27 I
CHANGE TITLE i
2OST 33.13C, Main Plant CO2 Zone PuffTest 4
l CHANGE DESCRIPTION l
Unit 2 Operations Surveillance Test (OST) 33.13C includes an operational test of CO2 actuated fire dampers. Fire damper 2HVS*DMPF231 closes when the CO header pressurizes during a 2
CO2 discharge in any of three CO2 protected zones. To minimize the effects of closing damper 2HVS*DMPF231, the OST was revised to trip the damper closed only during the testing of one zone.
k CHANGE TITLE i
j
' 20M-10.4.A, C, Residual Heat Removal System Startup, Shutdown l
CHANGE DESCRIPTION i-The Residual Heat Removal System (RHR) startup procedure was revised to defeat the autoclosure inte6cks on the RHR inlet and return isolation valves. This prevents the valves from automatically closing inadvertently.
The RHR shutdown procedures reinstate the interlocks.
}
l CHANGE TITLE 20M-6.4X, Operation of the Disc Pressurization System for Loop Isolation Valves Using Safety Injection Accumulators CHANGE DESCRIPTION This procedure was revised to allow the Nuclear Shift Supervisor (NSS)/ Assistant NSS to determine on a case by case basis if disc pressurization of closed loop isolation valves is required.
Placing the disc pressurization system in service requires added outage time and results in additional radiation dose to operators.
u, o
Beaver Valley Power Station Unit 2 Report ofFacility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 26 of 27 j
CHANGE TITLE
+
2 TOP-95-02, Loss of All AC Power When Vesselis Defueled CHANGE DESCRIPTION New Temporary Operating Procedure (TOP) 95-02 provides shutdown contingency actions to j
mitigate total loss of AC power while all fuel is ofBoaded into the spent fuel pool. Unit I and the switchyard are assumed to remain energized and available. The TOP provides guidance on how l
to use the Unit 1 - Unit 2 electrical cross-tie to power the spent fuel pool cooling system and support systems.
CHANGE TITLE 1
2 TOP 95M3, Drain /Reflood the Refueling Cavity to Repair the Fuel Transfer System i
CHANGE DESCRIPTION l
This Temporary Operating Procedure (TOP) was developed to drain the refueling cavity one foot l
below the reactor vessel flange. This allowed repair of the fuel transfer system in the refueling l
cavity. Continuation of the fuel ofDoad to the spent fuel pool could not continue until the repair was completed.
l CHANGE TITLE
)
Temporary Modification 2-95-10, Fuel Transfer System Emergency Pullout Cable CHANGE DESCRIPTION i
The Fuel Transfer System emergency pullout cable was damaged during refueling. The normal shear pin bracket and channel for the cable were damaged. Temporary modifications were made to allow fuel transfer cart travel and to allow the emergency pullout system to be operable.
l 1
l
v Beaver Valley Power Station Unit 2 Report of Facility Changes, Tests, and Experiments November 1,1994 - October 31,1995 Page 27 of 27 CHANGE TITLE l
2RP-5R-2.10 Refueling Procedure l
CHANGE DESCRIPTION The refueling procedure was revised to provide actions to address stuck reactor vessel studs and to install and tension the remaining studs.
l CHANGE TITLE l'
2OM-23B, 3.B.1, High Pressure Heater Drains Valve List CHANGE DESCRIPTION l
This change affected Unit 2 Operating Manual Chapter 23B, Section 3.B.1, high pressure heater drains (HDH) valve list. The normal system arrangement of heater drain pump seal water i
isolation valves (2HDH-618, -619, -1308, and -1309) was changed from open to closed.
Operating data indicates that the pumps car. operate without a seal water supply.
CHANGE TITL_E 2 TOP 95-04, Stroke Test of Steam Generator Atmospheric Steam Dump Valves During Mode 1 CHANGE DESCRIPTION This Temporary Operating Procedure (TOP) provides instmetions for partial or full stroke testing of each steam generator atmospheric dump valve during Mode 1.
The TOP was developed for the purpose of post maintenance testing.
i 4
4}