ML20210G704
| ML20210G704 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/22/1999 |
| From: | DUQUESNE LIGHT CO. |
| To: | |
| Shared Package | |
| ML20210G694 | List: |
| References | |
| NUDOCS 9908030186 | |
| Download: ML20210G704 (30) | |
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Be ;vir Valley Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Table of Contents Title Paae DCP 2085,125VDC System Breaker Coordination improvements........
............1 DCP 2129, Replacement of Boron Recovery Evaporator Recirculation Pump Pressure Transmitter. 1 DCP 2168, installation of Strainers on Circulating Water Air Release Valves...
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DCP 2275, Non-safety Diesel Generator Fuel Oil Tank Upgrades.................
..............2 DCP 2313, Upgraded Nitrogen Backup Supply for Pressurizer Power Operated Relief Valves........ 3 TER 11701, Parts Changes for Fire Pumps.
.3 TER 11873, Correction of Valve Type and Size for Drain Valve FW-651.
.4 TER 11877, Change to Seal Water Return Filter Specifications........
....4 TER 11958, Reactor Coolant Pump Underfrequency Relay Time Delay Changes.
...5 TER 11991, Setpoint and Procedure Changes Resulting from Revised Hydrogen Control Analysis.. 5 TER 11999, Type Change and Relocation of CO2 Storage Tank Instrument isolation Valves.
....6 TER 12004, Reactor Coolant Pump (RCP) Bus Undervoltage Trip Setpoint Change.....
.. 6 TER 12010, Control Switch Covers for Containment Recirculation Spray Pumps..
.....7 TER 12018, Control Room Carpet Replacement.....
...7 TER 12029, Evaluation of Overpower Delta Temperature (OPDT) Trip.
.8 TER 12081, Addition of Pressure Indicators to Circulating Water System Drawing..
..8 TER 12091, Change to QA Category of Boron Recovery Degasification Subsystem and Piping..
.9 TER 12106, Addition of isolation Valvca for Overhead Gas Compressor Instruments..
..9 TER 12202, Revised Piping Configuration for Boron Recovery and Liquid Waste Tanks Level Instruments.
.10 9909030186 990722 PDR ADOCK 05000334 R
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p BasvIr Vdity Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Table of Contents Title Pggg TER 12233, Addition of a Drain Valve to a Gaseous Waste System Line...............................10 TER 12282, Reactor Coolant Pump Motor Insulation Upgrade................................
..11 Operating Manual Revision, Makeup to Component Cooling Water System.
....... 1 1 Preventive Maintenance Procedure, Periodic inspection Of Fire Doors...............................12 Temporary Modificatbn 1-98-02, Temporary intake Structure Flood Seals.....................................12 Temporary Modification 1-98-10, Temporary Steam Generator Blowdown Sample Cooler.......13 Temporary Modification 1-98-11, Temporary Diesel Driven Air Compressor.............
.. 13 UFSAR Description Changes pertaining to Secondary Plant Chemistry................
...... 14 Chemical and Volume Control System (CVCS) Demineralizer Changes............................14 l
1 Removal of Excessive Secondary Sampling System Details from the UFSAR..........................15 Change of Resin Type for Cesium Removal lon Exchanger............................................. 15 Change of Resin Type for Fuel Pool lon Exchanger........................................................ 16 Deviation from ASME Section lli Pressure Protection Requirements...
.... 16 UFSAR Revision, Control Room Emergency Breathing Air Design Bases Clarification................17 UFSAR Revision, Small Bore Piping and Support Design Criteria....................................... 17 UFSAR Revision, Component Cooling / Recirculation Spray Heat Exchangers River Water Monitor Clarification..................
... 18 UFSAR Revision, Addition of Pressure Indicator on BVPS-2 Demineralized Water Supply Line...18 UFSAR Revision, Depiction of Valve Position for Isolation Valves Associated with Residual Heat Removal System (RHR) Cooling Water Supply.............................
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I Be:v:r Vcliey Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Table of Contents Title Paae UFSAR Revision, QA Classification of Chemical and Volume Control System (CVCS)
Demineralizers.
.........................................19 UFSAR Revision, Change to Flood Door Seals Operability Check Frequency................
.......20 UFSAR Revision, Remote Operation of Battery Charger Breakers.....
........20 UFSAR Revision, Steam Generator Stress Report.........
.............21 UFSAR Revision, Standby Service Water System Information..
.. 21 UFSAR Revision, Backup Cooling Water Supply for Containment Recirculation Air Coolers........... 22 UFSAR Revision, Auxiliary Building Maximum Air Temperature.
.22 UFSAR Revision, Environmental Qualification of Reactor Coolant System Resistance Tempe' Jture Detectors (RTDs) and Steam Line Flow Sensors..
.23 UFSAR Revision, Boric Acid Transfer Pump Reactivity insertion Rate.
..23 UFSAR Revision, Fim Protection System Valve Position Verification Frequency.
.. 24 UFSAR Revision, Er a gency Diesel Generator Fuel Oil Transfer Pump Capacity...
... 24 UFSAR Revision, Testing of the Power Range Channels...
.25 UFSAR Revision, Electronic Supervision of Diesel Generator Room Doors.
..... 2 5 UFSAR Revision, Check of Logic Matrices / Testing of Reactor Trip Breakers...
.26 Licensing Requirements Manual Revision, Addition of Meteorologicalinstrumentation Technical Specifications.,.....................
.. 26 Licensing Requirements Manual Revision, Intermittent Manipulation of Locked or Sealed Containment isolation Valves (CIVs).
.27 UFSAR Description Changes pertaining to Reactor Coolant Hydrogen Content...
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8:: var Vrilsy Pow:r St tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 1 of 27 CHANGE TITLE DCP 2085,125VDC System Breaker Coordination Improvements CHANGE DESCRIPTION This change was implemented to ensure that several DC circuit breakers would be properly coordinated with upstream breakers. As part of this change, the power feeder cable to Panel PNL-DC-4 was replaced with smaller size cable to increase circuit resistance. To protect the smaller cable it was necessary to reduce its upstream breaker size from the value described in the UFSAR.
By providing proper coordination of the DC breakers, trips of local breakers are more likely to prevent upstream breakers from opening and disabling a wider range of components. This change restored the originally intended function of the system. Therefore, it did not involve an unreviewed safety question.
CHANGE TITLE DCP 2129, Replacement of Boron Recovery Evaporator Recirculation Pump Pressure Transmitter QHANGE DESCRIPTION DCP 2129 replaced the discharge pressure transmitter for a boron recovery evaporator recirculation pump with a local indicator, thus eliminating alarm and recorder functions supplied by the origina:
transmitter.
The design change did not introduce the potential for new failures and performance of the system was not affected by elimination of the alarm and recorder functions. This change did not involve an unreviewed s&fety question.
B2avar Vall:y Pow:r St: tion Unit 1 Facility Changes, Tests, and Experiments Januay 23,1998 - Januay 22,1999 Page 2 of 27 CHANGE TITLE DCP 2168, Installation of Strainers on Circulating Water Air Release Valves i
CHANGE DESCRIPTION Air release valves are provided on the 108 inch circulating water lines between the condenser and the cooling tower pump house. This DCP installed strainers upstream of the valves to reduce fouling and L
leakage of the valves.
The circulating watcr system is not safety related. Neither the function nor the failure of the strainers can affect safety-related systems. Therefore, it was determined that the change did not involve an unreviewed safety question.
CHANGE TITLE DCP 2275, Non-safety Diesel Generator Fuel Oil Tank Upgrades i
CHANGE DESCRIPTION This DCP installed an overfill protection device and a spill protection device in the oil storage tank fill piping of the non-safety diesel generator. This reduced the capacity of the tank as described in the UFSAR by 1253 gallons.
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The reduced storage capacity has been evaluated with respect to various load scenarios and has been found to provide seven days' supply (NRC guidance for safety related diesels). The affected diesel generator is not used to mitigate accidents. Therefore, it was determined that the change did l
1 not involve an unreviewed safety question.
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Bnvsr Vclisy Pow:r St tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 3 of 27 CHANGE TITLE DCP 2313, Upgraded Nitrogen Backup Supply for Pressurizer Power Operated Relief Valvos CHANGE DESCRIPTION I
Prior to this change, a nitrogen supply had been provided as a backup to compressed air for two of three pressurizer power operated relief valves. This change added a similar backup supply to the third valve. Various other enhancements were also made, but these were consistent with the existing UFSAR description or licennig commitments and do not constitute changes to the facility as intended by 10 C' R 50.59.
The addition of a backup nitrogen supply imnroved the reliability of the power operated relief valves.
It did not create an unreviewed safety question because it provided additional assurance that the previously existing functions of the valves would be fulfilled if needed.
CHANGE TITLE TER 11701, Parts Changes for Fire Pumps CHANGE DESCRIPTION UFSAR Figure 9.9-3 depicts a dimension from the bottom of the pump strainer to the discharge head flange (near the motor) for fire pumps FP-P-1 and FP-P-2. This technical evaluation report evaluated a slight change in this dimension resulting from a change in vendor supplied parts.
The function of the pumps was not affected because the minimum submergence specification was maintained. Therefore, no unreviewed safety question was involved.
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B;5vsr Vcil;y Power St tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 4 of 27 CHANGE TITLE
' TER 11873, Correction of Valve Type and Size for Drain Valve FW-651 CHANGE DESCRIPTION UFSAR Figure 10.3-5 incorrectly depicts a drain valve on the suction strainer for dedicated auxiliary feedwater pump FW-P-4. It is oepicted as a % inch gate valve rather than a 2 inch globe valve. This evaluation permitted the figure to be corrected.
The valve is used for flushing and cleaning the strainer and has no effect on postulated accidents or system performance. As a result, the change to its size and type did not constitute an unreviewed safety question.
CHANGE TITLE TER 11877, Change to Seal Water Return Filter Specifications CHANGE DESCRIPTION This TER permitted the use of finer filter media for reactor coolant pump seal water. The finer media was to reduce radiation dose rates and contamination levels of water returned from the pump seals.
l The change had no effect on previously evaluated failure modes, did not affect radiological consequences of accidents, and did not alter equipment performance in a way that could have created a new type of accident. It was determined that improved filter specifications did not constitute an unreviewed safety question.
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Be:vIr Vcil2y Power St: tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 5 of 27 CHANGE TITLE TER 11958, Reactor Coolant Pump Underfrequency Relay Time Delay Changes CHAN.QE DESCRIPTION The UFSAR describes a time delay of up to approximately 0.1 seconds for relays used in tripping the reactor coolant pumps on underfrequency. Because testing revealed an inherent relay time delay that had not been considered in the 0.1 second value, a UFSAR revision was prepared to increase this i
delay to 0.2 seconds. This increased the calculated total channel response time, but the total remained less th.Tn required by technical specifications.
Because no physical changes have been made, the probability of failure is not affected. The time delay increase has not modified system response to the point that a new type of accident needs to be i
considered. In addition, the technical specification limits continue to be satisfied. Based on these considerations, it was found that the additional delay did not constitute an unreviewed safety question.
CHANGE TITLE TER 11991, Setpoint and Procedure Changes Resulting from Revised Hydrogen Control Analysis CHANGE DELRIPTION This change involved a revised containment hydrogen control analysis as well as hydrogen analyzer setpoint changes and procedure changes necessary to satisfy analysis assumptions. Hydrogen recombiner startup must now occur 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following the design basis accident. Previously two days was calculated to be adequate.
The new analysis used conservative assumptions and no hardware changes were required to be implemented due to the analysis. The time required to start up a recombiner was shortened, but there would be ample time to accomplish this task and maintain hydrogen concentration et an acceptable level. Therefore, no adverse system impacts or new failure modes hcve resulted from this change.
No unreviewed safety question was involved.
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B::avsr Vrilsy Powsr Ststion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999
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Page 6 of 27 CHANGE TITLE TER 11999, Type Change and Relocation of CO: Storage Tank Instrument isolation Valves CHANGE DESCRIPTION Due to the need for repair of one of the valves, this TER was prepared to allow replacement of four instrument isolation gate valves with globe valves. The valves are used to isolate pressure and level instruments associated with two CO2 fire suppression storage tanks. The change also would correct UFSAR Figure 9.10-2 that incorrectly shows two of these valves connected to the refrigerant lines for j
the tanks rather than directly to the tanks.
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No new failure modes are created by this change because specifications for the replacement valves exceed service requirements. In addition, the valves (regardless of type) have no effect on the fire suppression function of the system. It was determined that no unreviewed safety question was involved.
CHANGE TITLE TER 12004, Reactor Coolant Pump (RCP) Bus Undervoltage Trip Setpoint Change CHANGE DESCRIPTION This technical evaluation report was prepared to establish administrative controls for the RCP bus undervoltage trip setpoint. Administrative controls were necessary to ensure consistency between RCP bus and emergency bus settings. A license amendment request has been filed to request a conservative change to the setpoint descr: bed in the technical specifications.
The setpoint proposed by the TER was consistent with existing and proposed technical specifications.
This trip is used as a backup to the low reactor coolar,t pump flow trip and was not credited in the accident analyses, it was determined that no unreviewed safety question was involved.
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BssvIr Vtilsy Power St; tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 7 of 27 l
CHANGE TITLE 1
TER 12010, Control Switch Covers for Containment Recirculation Spray Pumps j
i CHANGE DESCRIPTION The UFSAR erroneously indicated that an electrical interlock prevents inadvertet closure of outside recirculation spray pumps' suction valves by an operator while the pumps are running. As an altemative, this TER permitted sealed covers to be installed on the control switches. This altemative would force an operator to break the seal and lift the cover prior to manipulating a valve.
Valve manipulation is not required by any abnormal or emergency operating procedure. Therefore, by j
preventing inadvertent manipulation by an operator, the change ensures that the system will function i
as originally intended. The change also would not prevent operation when required for a valid reason.
- ' Therefore, it was determined that no unreviewed safety question was involved.
L CHANGE TITLE TER 12018, Control Room Carpet Replacement CHANGE DESCRIPTION l
In support of carpet replacement, this TER revised the flame spread testing specification (ASTM E84, identified in the BVPS-1 UFSAR) for control room carpet to be consistent with the current specification (ASTM E648) used by the carpet industry and endorsed by NFPA.
The replacement of carpet did not increase the probability of a control room fire because no new ignition sources have been introduced. New types of accidents could not be created by the change in carpet specifications. Based on these considerations, it was determined that no unreviewed safety j
question was involved.
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b B :v:r Vcil:y Powtr St1 tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 8 of 27 CHANGE TITLE TER 12029, Evaluation of Overpower Delta Temperature (OPDT) Trip CHANGE DESCRIPTION This TER evaluated accident analyses to determine the extent of reliance on the OPDT trip function in mitigating postulated events. It was determined that the trip was not credited in the accident analyses and that it served only as an enhancement to the overall reliability of the reactor protection system.
UFSAR changes were initiated to ensure that the status of this trip tunction would be clearly understood.
Because this change involved an evaluation of assumptions used in existing accident analyses and did not involve modifications to the design or function of plant systems, it was determined that no unreviewed safety question was involved.
CHANGE TITLE TER 12081, Addition of Pressure Indicators to Circulating Water System Drawing CHANGE DESCRIPTION This TER was prepared to revise UFSAR Figure 10.3.3A to reflect the existence of pressure indicators on each of four 78 inch condenser outlet lines.
The circulating water system has no safety functions and is physically separated from safety-related equipment.
Considering the size of the condenser outlets, potential leakage of the pressure instruments would have a negligible effect on system performance. The potential effects of leakage on other systems and equipment are bounded by a postulated rupture of the condenser expansion joint that has been previously evaluated. Therefore, it was determined that no unreviewed safety question was involved.
B ::vtr VEllsy Powar Stition Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 9 of 27 CHANGE TITLE TER 12091, Change to QA Category of Boron Recovery Degasification Subsystem and Piping CHANGE DESCRIPTION This change permitted the QA category of boron recovery degasification equipment and piping to be changed from Category 1 to Seismic, QA Category 2. The new classification is consistent with the technical specifications, Regulatory Guide 1.26 (9/74) and classification criteria described in the UFSAR.
Regardless of the change in category, failure of the affected components cannot initiate any postulated accident. Therefore, the probability of evaluated accidents was not changed. The change did not alter the assumptions of dose calculations related to failure of the system. As a result, the consequences of a failure were also not changed. New types of accidents could not have been created because no new potential failure modes were introduced by the change. Therefore, it was concluded that no unreviewed safety question was involved.
CHANGE TITLE TER 12106, Addition of isolation Valves for Overhead Gas Compressor instruments CHANGE DESCRIPTION This TER was prepared to allow UFSAR Figure 11.2-1 to be revised showing an additional isolation valve in the lines for each of two pressure switches used to control two overhead (gaseous waste system) gas compressors. The pressure switches sense compressor suction pressure.
There are no design basis accidents that failure of the additional valves could initiate. Therefore, they cannot affect the probability of such an accident. Since existing evaluations of postulated ruptures of gaseous waste system components envelope failure of the valves, consequences of failures were not increased. Introduction of additional valves did not create any new failure mode that could cause a new unanalyzed type of system malfunction. Based on these considerations, it was concluded that no unreviewed safety question was involved.
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. BIcv:r Vcilsy Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 10 of 27 CHANGE TITLE TER 12202, Revised Piping Configuration for Boron Recovery and Liquid Waste Tanks Level Instruments CHANGE DESCRIPTION This TER updated the UFSAR to reflect a variety of design changes made prior to plant licensing.
The changes were associated with instrumentation piping for boron recovery system dsgasifiers, evaporators, distillate accumulators, and test tanks. These vessels are not safety related. Typical changes included mincr &djustment of valve types and/or sizes (3/8 inch socket vs.1/2 inch threaded, for examplQ and deletion of capped vent valves.
The safety evaluation considered potential rupturo of instrument lines and concluded that these ruptures would be bounded by more severe events already analyzed. Therefore, the changes could-not increase the consequences of analyzed accidents. The probability of analyzed accidents was not affected because failure of the boron recovery system could not initiate such accidents. Because j
plant response to boron recovery system malfunctions was not changed, no new types of accidents could be created. Therefore, it was concluded that no unreviewed safety question was involved.
4 CHANGE TITLE TER 12233, Addition of a Drain Valve to a Gaseous Waste System Line CHANGE DESCRIPTION This TER was prepared to document the existence of a drain valve on UFSAR Figure 11.2-2. The valve is located in a non-safety-related portion of the gaseous waste system that is used for discharges to the environment. The figure previously depicted a capped pipe stub at this location.
The change had no effect on existing failure modes or consequences and did not introduce any new failure modes. It was decided that no unreviewed safety question was involved.
Ba;v:r VEll:y Pow;r Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 11 of 27 CHANGE TITLE TER 12202, Reactor Coolant Pump Motor insulation Upgrade CHANGE DESCRIPTION The UFSAR indicates that reactor coolant pump motors contain Class B insulation and six resistance temperature detectors (RTDs). The TER was prepared to evaluate the use of Class F insulation and to add detail to the UFSAR indicating that only one of the RTDs is in service at any particular time.
Class F insulation exceeds Class B insulation specifications; therefore, the facility as described in the UFSAR has not been changed. The RTD detail was added only to clarify that all six RTDs are not used simultaneously. These clarifications did not involve an unreviewed safety question.
CHANGE TITLE Operating Manual Revision, Makeup to Component Cooling Water System CHANGE DESCRIPTION This operating manual revision permitted manual makeup to the component cooling water system.
The UFSAR originally described makeup as an automatic operation. The ability to manually replenish the system was adopted as an aid in identifying system leakage.
The component cooling water system is not safety related. There were no postulated accidents affected by this change and the probability or consequences of such accidents were not affected.
New types of accidents were not created because the change did not create new failure modes for the system. As a result, it was determined that no unreviewed safety question was involved.
Bravrr Vcilly PowIr Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 12 of 27 QHANGE TITLE L
Preventive Maintenance Procedure, Periodic inspection Of Fire Doors Q_HANGE DESCRIPTION -
A preventive maintenance procedure (PMP) was written to inspect fire doors to verify compliance to NFPA 80 " Fire Doors and Fire Windows" and to assure that these plant components are capable of performing their intended functions as fire barriers. This change allowed a deviation from the clearances specified in NFPA 80 for door-to-frame and door to-floor gaps.
The fire test acceptance criteria of the ASTM test used to qualify BVPS fire doors were reviewed and -
determined to be unaffected by the door-to-frame gap size. An evaluation of the gap deviation from the NFPA 80 criteria used to install the doors determined that the new limits will not affect the fire endurance of the doors and, therefore, this change did not affect the failure modes of the fire doors.
No design basis acciden'.s were affected since the Standard Review Plan states that fires need not be postulated concurrent with non-fire related accidents. This change did not represent an unreviewed safety question.
CHANGE TITLE Temporary Modification 1-98-02, Temporary intake Structure Flood Seals CHANGE DESCRIPTION This change permitted pipe caps to be used as flood seals for two penetrations in separate intake structure pump cubicles. The configuration consists of threaded pipe caps on stuffing boxes reserved for possible future valve operators.
It was determined that this change was not an unreviewed safety question because flood seals only provide a passive mitigation function and possible leakage past the threads would be negligible.
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Bagvtr Vdisy Pow:r St1 tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 13 of 27
. CHANGE TITLE Temporary Modification 1-98-10, Temporary Steam Generator Blowdown Sample Cooler CHANGE DESCRIPTION A leak in a steam generator sample line inside containment could not be repaired with the plant in
. operation. This change permitted a temporary sample cooler to be connected to a drain valve in the turbine building so that the secondary plant (via the steam generator blowdown system) could be periodically sampled for specific activity. Cooling water-was provided by the demineralized water system. Systems involved were non safety related.
Operation of affected systems remained the same following the change. Therefore, the probability of
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analyzed accidents was not changed. No new types of accidents or malfunctions were created because no safety systems or equipment are affected. The consequences of postulated accidents such as a steam generator tube rupture are not increased because the temporary sampling provision will not be used when monitors indicate high activity in the secondary system. This change did not constitute an unreviewed safety question.
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Temporary Modification 1-98-11, Temporary Diesel Driven Air Compressor CHANGE DESCRIPTION This modification provided a full capacity diesel powered air compressor connected to the non-safety related station air system while one of the two electric powered compressors was out of service for maintenance. The other electric compressor was maintained in standby (automatic start mode), as usual. A check valve was provided at the connection point to prevent air system depressurization in the event of a supply line failure.
The safety evaluation for this change determined that no postulated accidents were impacted by the use of a temporary compressor and that probabilities or consequences of these accidents would not be affected.
New accidents could not be created because failure modes of the temporary replacement are the same as for the permanent compressor. The compressor was located outdoors and special precautions were taken for fuel spillage. No unreviewed safety question was involved.
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B::vIr Vcil:y Power Station Unit 1 Facility Changes, Tests, and Experiments
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January 23,1998 - January 22,1999 Page 14 of 27 CHANGE TITLE UFSAR Description Changes pertaining to Secondary Plant Chemistry CHANGE DESCRIPTION The UFSAR describes specific secondary plant sample locations, types of sample analyses and a specific chemical (hydrazine) used for oxygen scavenging. The change revised the UFSAR by (1) replacing the sample point locations with more general references to the specific process fluids being sampled, (2) removing the identification of analyses performed on the samples and (3) replacement of the term "hydrazine" with " oxygen scavenger." Prior to the change, the UFSAR already contained an external reference to the BVPS Chemistry Manual describing analysis procedures and schedules.
This change did not affect potential failure modes of the involved systems and no changes were made that would affect radiological consequences of a postulated accident. It was determined that no unreviewed safety question was involved.
CHANGE TITLE Chemical and Volume Control System (CVCS) Demineralizer Changes CHANGE DESCRIPTION The UFSAR describes specific functions of several CVCS demineralizers that are used to treat reactor coolant. By allowing each demineralizer to be charged with a wider variety of resins and to be employed for altemate purposes, this change provided more flexibility in accommodating varying plant conditions.
The use of altemate resins in particular demineralizers did not create new plant failure modes and did not change the probability of failures. The change provided additional flexibility in maintaining plant chemistry within specified limits. Therefore, no unreviewed safety question was involved.
B3 v;r Vall;y Pow:r Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 15 of 27 CHANGE TITLE Removal of Excessive Secondary Sampling System Details from the UFSAR CHANGE DESCRIPTION This change removed references to several secondary system chemistry parameters that are sampled and analyzed by continuous monitoring equipment. Following the change, the UFSAR describes continuous sampling, but did not list the parameters analyzed. This unnecessary detail had been added to the UFSAR as the result of a plant design change and is not part of the licensing basis.
The change has not altered plant specifications and no physical plant changes resulted from this change. No unreviewed safety question was involved.
CHANGE TITLE Change of Resin Type for Cesium Removallon Exchanger CHANGE DESCRIPTION This change allowed cation or mixed bed resins to be used in the cesium removal ion exchangers.
This provided flexibility to remove a broader range of fission and corrosion products than the previous cation or mono bed resins provided.
No unreviewed safety question was involved because no changes to plant design were made and the function of the ion exchangers has been enhanced.
Botver Vcllsy Pow:r Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 16 of 27 CHANGE TITLE Change of Resin Type for Fuel Poollon Exchanger CHANGE DESCRIPTION This change allowed cation resins, anion resins or charcoal to be used in the fuel pool ion exchangers. This provided flexibility to remove a broader range of impurities than the previous mixed bed resins provided.
No unreviewed safety question was involved because no changes to plant design were made and the function of the ion exchangers has been enhanced.
CHANGE TITLE Deviation from ASME Section til Pressure Protection Requirements CHANGE DESCR!PTION The UFSAR cited ASME Section ill as the design code for the volume control tank and various gaseous waste tanks. The change would permit the UFSAR to be changed to allow a deviation from this code by permitting administratively contrciled maintenance isolation valves in the pressure relief lines for the tanks. ASME Ill requires positive interlocks.
The use of administrative controls in lieu of positive interlocks was not considered an unreviewed safety question. No new accident was created because rupture of the tanks has already been evaluated in the UFSAR. In addition, due to the manner in which the administrative controls would be applied, it was not considered credible that the administrative control would fait coincident with an overpressure event. Therefore, probability of failure has not been increased.
4 Buv;r Vcll:;y Pow r St: tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 17 of 27 CHANGE TITLE UFSAR Revision, Control Room Emergency Breathing Air Design Bases Clarification CHANGE DESCRIPTION This change eliminated discussion in the UFSAR which credited the Control Room Emergency Breathing Air System (CREBAS) manifold and masks as the means of providing air to Control Room personnel after a radioactive release event. Redundant plant systems are available for this purpose.
l The UFSAR was also updated to describe the quantity of portable self-contained breathing apparatus (SCBA) units available to protect against a toxic gas release.
These UFSAR revisions describe how BVPS adequately meets the provisions of the regulatory guides in the licensing basis. The provision of portable SCBA units is the method by which BVPS meets toxic gas protection requirements, and the UFSAR revision comprehensively documents this compliance.
No physical modifications result from this clarification of the licensing basis in the UFSAR and no new failure modes are introduced. No technical specifications are affected. This UFSAR change did not result in an unreviewed safety question.
CHANGE TITLE UFSAR Revision, Small Bore Piping and Support Design Criteria CHANGE DESCRIPTION This change revised UFSAR Appendix B.2 to add specific description of small bore (2 inch or less) piping and support design criteria. The appendix previously had been written only to reflect large bore piping.
It was concluded that the proposed UFSAR changes did not constitute an unreviewed safety question.
The revision clarified existing text and added detail pertaining to small bore piping design. Newly described methodology was consistent with other existing UFSAR descriptions as well as with criteria for large bore piping. Basic analytical methods have been reviewed by the NRC.
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7 BEvzr Vcliey Power Station Unit 1 Facility Changes, Tests, and Experiments January 23.1998 - January 22,1999 Page 18 of 27 CHANGE TITLE UFSAR Revision, Component Cooling / Recirculation Spray Heat Exchangers River Water Monitor Clerification CHANGE DESCRIPTION The UFSAR describes the component cooling / recirculation spray heat exchangers river water radiation monitor as " redundant" to (1) the component cooling river water radiation monitor and (2) the recirculation spray heat exchanger river water radiation monitors. Because the terrn " redundant" may not be interpreted in a generic sense as intended, the UFSAR was revised to use clearer terminology showing that this monitor, being downstream of the others, can be used as an altemate means of detecting leaks in the component cooling and recirculation spray systems.
The proposed change was a clarification intended to eliminate possible confusion. Design or function of the system was not changed. Therefore, it was concluded that the proposed UFSAR changes did not constitute an unreviewed safety question.
CHANGE TITLE UFSAR Revision, Addition of Pressure Indicator on BVPS-2 Domineralized Water Supply Line CHANGE DESCRIPTION This change added a pressure indicator and associated components to a BVPS-1 demineralized water system line that supplies BVPS-2.
This change was not sa unreviewed safety question because operation of the water supply and treatment system is not required for safety and because failure of the added components (3/4 inch or less nominal size) could not produce a large enough leak to affect safety-related equipment.
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B: v:r V:ll:y Pou:r St tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 19 of 27 CHANGE TITLE UFSAR Revision, Depiction of Valve Position for Isolation Valves Associated with Residual Heat Removal System (RHR) Cooling Water Supply CHANGE DESCRIPTION The RHR heat exchangers and seal coolers for the RHR pumps are located inside containment and are chilled by component cooling water. Separate supply and retum lines servicing each of two trains of RHR contain a manual (outside) and a motor operated (inside) containment isolation valve in each line. This change revised UFSAR Figure 9.4-4 to depict these valves as closed. The figure also shows two refueling water refrigeration units that are supplied by component cooling water. The figure was changed to show the flow control valve for one refrigeration unit in the closed position.
This is because normally only one unit is necessary to be in operation.
The component cooling water system is not used for accident mitigation t iu is not an engineered safety features system. Tha newly depicted containment isolation valve positions are consistent with l
other informaUon in the UFSAR describing isolation arrangements. There are no accidents that wou!c l
be adversely affected by the change and no new failure modes were introduced. Therefore, it was concluded that no unreviewed safety question was involved.
CHANGE TITLE J
l UFSAR Revision, QA Classification of Chemical and Volume Control System (CVCS) l Demineralizers CHANGE DESCRIPTION UFSAR Section 6.2 included the CVCS system in the scope of piping Class 111 equipment. Piping Class lit equipment is safety-related (QA Catagory 1). This change removed portions of CVCS that may be classified QA Category 2 from the scope of Class Ill equipment. In this case, QA Category 2
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would be assigned if the equipment does not prevent or mitigate accidents, but contains radioactive materialin excess of specified limits. The change also revised the UFSAR to reflect a QA Category 2 classification for the mixed bed and cation demineralizers in the CVCS. These changes were consistent with other sections of the UFSAR that relate to classification of equipment and piping.
i Safety-related portions of CVCS were not involved in this change and failures of the non-safety related portions of CVCS would not present a hazard to the safety-relateci portions. Therefore, no new accidents or increased probability of accidents was created. Because the bounding dose analysis for the system was not changed, the consequences of a malfunction were not increased.
Therefore, it was concluded that no unreviewed safety question was involved.
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1 B:1v:r Vril:y Pow:r Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 20 of 27 CHANGE TITLE UFSAR Revision, Change to Flood Door Seals Operability Check Frequency
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CHANGE DESCRIPTION This change permitted an annual test of flood door seals to be conducted on a refueling cycle frequency instead of annually. The test confirmc integrity of intake structure pump cubicle doors that protect against extemal flooding.
In order to perform the test, it is necessary to open doors connecting adjacent pump cubicles, making redundant equipment temporarily vulnerable to flooding from a single intemal source. The change in frequency allowed the test to be performed during periods when the potentially affected systems are not required to be available per technical 1
specifications.
A change in testing frequency can only affect the probability of an undetected failure of the flood door seals. Based on previous testing experience and failure rates, it was determined that the change in testing frequency would not increase the probability of malfunction of the affected systems and that no unreviewed safety question was involved.
CHANGE TITLE UFSAR Revision, Remote Operation of Battery Charger Breakers CHANGE DESCRIPTION This change removed a statement indicating that 480V breakers supplying plant battery chargers can be operated from the control room.
The breakers are not potential accident initiators and are not relied upon to mitigate any analyzed accident. As a result, it was determined that no unreviewed safety question was involved.
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Buv:r Vcil:y Power St: tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 i
Page 21 of 27 CHANGE TITLE UFSAR Revision, Steam Generator Stress Report CHANGE DESCRIPTION This revision changed steam generator differential pressures and stress values to make them consistent with those found in the nuclear steam system supplier's stress report.
The changes did not affect operation of the steam generators nor did they affect any steam generator related failure modes or accidents. As a result, they did not constitute an unreviewed safety question.
CHANGE TITLE UFSAR Revision, Standby Service Water System Information 1
CHANGE DESCRIPTION This UFSAR revision provicied clarification to the current UFSAR text concerning the original licensing basis for the standby service water system (SSWS), and the attemate intake structure. These are only required to operate following a postulated gasoline barge impact wit: the intake structure which disables both trains of the safety related service water system.
These UFSAR revisions did not alter the licensing basis for the SSWS. These revisions were meant
.only to clarify the original licensing basis in such a manner that the UFSAR will be read and i
l understood in a clear and consistent manner. There is no requirement to operate the SSWS during a UFSAR-described design basis accident. These UFSAR revisions are not an unresiewed safety 4
question since there were no changes to the current design basis or licensing basis for the SSWS.
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B: v:r Vcil:y Pow:r St: tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 22 of 27 CHANGE TITLE l
UFSAR Revision, Backup Cooling Water Supply for Containment Recirculation Air Coolers CHANGE DESCRIPTION The UFSAR previously stated that the river water system would be used as the backup to cool the containment recirculation air coolers when chilled water is not available. Because the wording could be interpreted as requiring the use of river water as the only option, the UFSAR was revised to allow the possibility of cther attematives to chilled water.
This change did not constitute an unreviewed safety question. It expanded the possible set of solutions to a loss of chilled water. As a result, it had no effect on equipment performance and no impact on plant response to postulated accidents.
CHANGE TITLE UFSAR Revision, Auxiliary Building Maximum Air Temperature QHANGE DESCRIPTION As part of the ventilation system description for the auxiliary building, the UFSA.R stated that maximum air temperature limits (in areas where motors are located) were designed to be 104 degrees. The UFSAR also described a minimum temperature for personnel comfort. The UFSAR was changed to provide a general statement that area temperatures keep motor winding temperatures within the insulation ratings of the motor windings.
A potential change in ambient air temperature exceeding 104 degrees would not represent a challenge to the affected motors because temperatures would be consistent with insulation ratings.
Because equipment function was unchanged, no unreviewed safety questica was involved.
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Bnv:r V;ll:;y Pow:r Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 23 of 27 CHANGE TITLE UFSAR Revision, Environmental Qualification of Reactor Coolant System Resistance Temperature Detectors (RTDs) and Steam Line Flow Sensors CHANGE DEJQRIPTIQN This revision changed the UFSAR to state that RTDs used for T y measurement and steam line flow sensors used to detect steam line breaks are qualified to operate in an accident environment.
Previously the UFSAR indicated that the RTDs were not qualified and did not indicate whether the steam line flow sensors were qualified.
It was determined that revision of the UFSAR to reflect greater qualification requirements for the affected instruments had no effect on plant functions that would involve an unreviewed safety question.
CHANGE TITLE UFSAR Revision, Boric Acid Transfer Pump Reactivity Insertion Rate i
CHANGE DESCRIPTION j
As part of the reactor shutdown capabilities description, the UFSAR stated that a single boron transfer pump could inject boren at a specific reactivity insertion rate that would shut down the reactor (with no rods inserted) in 45 minutes. The specific insertion rate described was appropriate only for the first fuel cycle. Because the specific insertion rate vanu depending on differential boron worth, the insertion rate was deleted in favor of the more general criterion of shutting down the reactor in 45 minutes. The 45 minute criterion was not obtained from a technical specification or accident analysis, but is merely a way of describing capacity
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Because the change did not modify plant equipment and did not affect a system with potential to initiate an accident, the probability of malfunctions or accidents was not affected and no new types of accidents could have been created. No unreviewed safety question was involved.
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Brv;r Vciley Pow:r St tion Unit 1 Facility Changes, Tests, and Experiments l
January 23,1998 - January 22,1999 Page 24 of 27 CHANGE TITLE UFSAR Revision, Fire Protection System Valve Position Verification Frequency CHANGE DESCRIPTION This change allowed monthly valve position verifications of fire protection water supply sectionalizing valves which are chained, locked or sealed. The UFSAR contained an indirect commitment to NFPA 26 which recommends a weekly check.
The change was not an unreviewed safety question because the monthly surveillance frequency is the same frequency included in the plant license via BVPS-1 fire suppression water system technical specifications. The NRC subsequently allowed these specifications to be removed from the license and incorporated in plant administrative procedures.
CHANGE TITLE UFSAR Revision, Emergency Diesel Generator Fuel Oil Transfer Pump Capacity CHANGE DESCRIPTION Fuel oil transfer pumps move fuel from the main storage tanks to the day tank for consumption by a diesel generator. The UFSAR described two 100 percent capacity pumps capable of 10 gpm flow.
This change deleted the 10 gpm flow specification in favor of the 100 percent capacity terminology because 10 gpm is much in excess of the maximum flow needed to sustain diesel operation (less than 4 gpm).
The safety evaluation for this change demonstrated that no unreviewed safety question was involved based upon the diesel generators remaining fuliy capable of responding to accident conditions assuming a transfer pump flow rate sufficient to support fullload operation.
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Bervir Vall:;y Pow r St: tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 25 of 27 CHANGE TITLE UFSAR Revision, Testing of the Power Range Channels i
CHANGE DESCRIPTION This change revised the UFSAR to reflect the methodology used for testing the nuclear instrumentation system power range channels. The UFSAR stated that the channels were tested by superimposing a test signal on the actual detector signal and that the output of the bistable was not placed in a tripped condition prior to testing. This description accurately described the operating surveillance testing methodology.
However, the methodology of the maintenance surveillance procedures (MSPs) disconnects the channel detectors and places the bistable outputs in a tripped condition prior to testing. This change updated the UFSAR to reflect the more comprehensive test methodology used by the MSPs.
The MSP methodology is a more accurate method of calibration. Disconnection of the detector cable removes circuit noise and the detector signal allowing a calibration over the entire range of the detector. This testing methodology change did not impact design basis accidents, nor create a new type of accident or new failure mode. Since the MSP would place the channel under test in a tripped condition, no design basis accidents were affected by this change. This change did not represent an unreviewed safety question.
CHANGE TITLE UFSAR Revision, Electronic Supervision of Diesel Generator Room Doors CHANGE DESCRIPTION This change revised the UFSAR to reflect the actual plant configuration for electronically supervised doors for areas that were protected by carbon dioxide fire suppression. The UFSAR had a statement that areas protected by carbon dioxide fire suppression systems are equipped with electrically supervised doors. The current plant configuration did not provide electrical supervision for a redundant pair of doors connecting the emergency diesel generator rooms.
The change updates the UFSAR to accurately reflect the original design. The change did not affect the performance of the carbon dioxide suppression system nor the associated fire doors The change did not degrade the reliability of any structures, systems, or components because the integrity of the subject fire areas was not affected. No design basis accidents were affected by this change, no new failure modes were introduced, nor did it create a new type of accident. This change did not represent an unreviewed safety question.
B2 vgr Vcil2y Power St: tion Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 26 of 27
_ HANGE TITLE C
UFSAR Revision, Check of Logic Matrices / Testing of Reactor Trip Breakers CHANGE DESCRIPTION This change updated the UFSAR to reflect the actual test methodology used to test the solid state protection system. The UFSAR stated that the logic testing employed pulse techniques which avoid tripping the reactor trip breakers, thereby eliminating the need to bypass the trip breaker. However, during the performance of the maintenance surveillance procedures (MSPs), the bypass breaker is closed because reactor trip breaker testing is conducted by the MSP along with the logic testing. The UFSAR also stated that one bistable from each channel is tripped at the completion of logic testing to check closure of the input error inhibit switch. The MSPs use channel inputs that are already tripped, if available, or a continuity check to verify contact closure.
The MSPs employ an equivalent, less plant-challenging and more conservative technique than that described in the UFSAR. Since the method of testing the input error inhibit switch restoration used in the MSPs is equivalent to that described in the UFSAR, no design basis accidents were affected by this change. Closing the bypass breakers during logic testing is less challenging to the plant and creates an additional margin of safety. This testing methodology change did not impact design basis accidents, nor create a new type of accident or new failure mode. This change did not constitute an unreviewed safety question.
CHANGE TITLE Licensing Requirements Manual Revision, Addition of MeteorologicalInstrumentation Technical Specifications CHANGE DESCRIPTION License Amendment No. 220 permitted meteorological instrumentation technical specifications to be removed from the license and placed in the Licensing Requirements Manual. As part of the relocation i
various changes were mcde to the relocated material. These included (1) addition of " rules of usage" similar to those found in the Technical Specifications 3.0/4.0, (2) changing an action statement to require reporting to the BVPS Nuclear Safety Review Board (rather than to the NRC), and (3) revising the BVPS-1 meteorologicalinstrumentation table to be consistent with the more conservative BVPS-2 table regarding equipment availability requirements.
The probability and consequences of analyzed -accidents were not affected by changes to the administrative controls associated with this change. No unreviewed safety question was invo,'ved.
Berv:r Vcilly Power Station Unit 1 Facility Changes, Tests, and Experiments January 23,1998 - January 22,1999 Page 27 of 27 QHANGE TITLE Licensing Requirements Manual Revision, intermittent Manipulation of Locked or Sealed j
Containment isolation Valves (CIVs)
CHANGE DESCRIPTION The Licensing Requirements Manual (LRM) contains a table of CIVs associated with containment penetrations relocated from the technical specifications as the result of a license amendment. The table identified some (but not all) locked or sealed closed CIVs by a footnote indicating that the valves
- could be opened on an intermittent basis under administrative control.
However, Technical Specification 3/4.6.3 permits locked or sealed closed isolation valve to be opened ir:termittently under administrative control. This caused confusion regarding application of administrative controls when opening CIVs because the footnote had not been applied in the table consistently to all locked or
. sealed closed CIVs.
This LRM revision removed the confusing footnote from all locked or sealed closed CIVs so that the LRM no longer overlaps Technical Specification 3/4.6.3 requirements. Other clarifications were made to help separate LRM requirements for CIVs that are not locked or sealed closed from CIVs subject to the technical specification. The UFSAR was also revised to identify two CIVs associated with the pressurizer dead weight calibrator as sealed closed instead of locked closed.
The LRM changes were clarifications intended to eliminate confusion regarding correct application of requirements. Therefore, they had no adverse impact on the safety performance of affected systems.
Sealing dead weight calibrator CIVs rather than locking them was considered equivalent because of Standard Review Plan guidance. It was determined that these changes did not involve an unreviewed safety question.
CHANGE TITLE UFSAR Description Changes pertaining to Reactor Coolant Hydrogen Content CHANGE DESCRIPTION The UFSAR stated that hydrogen overpressure in the volume control tank controls reactor coolant hydrogen concentration at 25 to 35 cc/kg. This change replacad the hydrogen concentration by a reference to the BVPS Chemistry Manual and increased the maximum concentration to 50 cc/kg.
This change did not affect potential failure modes of the involved systems and no changes were made that would affect radiological consequences of a postulated accident. It was determined that no unreviewed safety question was involved.
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