RBG-26-521, Annual Operating Rept for 860301-870301
| ML20237K679 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/01/1987 |
| From: | Booker J GULF STATES UTILITIES CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RBG-26-521, NUDOCS 8709040475 | |
| Download: ML20237K679 (24) | |
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SECTION A - PLANT MODIFICATIONS This section contains brief descriptions and safety evaluation summaries for plant modifications completed between the period of March 1, 1986 and March 1, 1987 or otherwise included in the August, 1987 Updated Safety Analysis Report, pursuant to the requirements of 10CFR50.59. The Temporary Alteration Program described in Gulf States Utilities Company's (GSU) 198510CFR50.59 report has been terminated. Alterations have been removed or replaced with permanent modifications.
Modification /FSAR Section: MR 85-0137 / Figure 9.3-6a,g Figure 10.3-Ic Figure 10.4-7k
Title:
Drain Line Addition Description and Basis For Change: Added drain lines to each turbine stop valve, combined intermediate valve stem leak-off connection and routed drain lines to drain system which goes to Rad Waste. Addition of drains to catch basins are part of the General Electric turbine system design which was inadvertently omitted from the original design. The drains will prevent the accumulation of condensation and/or stem leakage in each basin.
Summary or Safety Evaluation: The addition of the drain lines is in accordance with the original design specification of the system. The addition of the equipment does not reduce the safety function capability of the system. This is a non safety related quality class II system.
No margin of safety, as defined in the bases for the Technical Specifications, is affected. Therefore it was determined that this modification did not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR 85-0143 / Table 6.2-46
Title:
Replace Annulus Pressure Gauge Description and Basis For Change: Technical Specification 4.6.5.1 requires a surveillance of the annulus region gauge pressure at least once per 24 hr. The previous device was determined not to have sufficient accuracy to monitor for the Technical Specification value.
The new installed instrument changes the instrument span and range as well as the recorder scale located in the main control room.
Summary of Safety Evaluation: The subject instrument loop provides no automatic functions. The loop is utilized for indication only. There exists several independent channels of Regulatory Guide 1.97, Rev. 3 instrumentation to ensure proper operator actions. The revis.fon to the loop allows for monitoring of the annulus region pressure in accordance Page A-1 8709040475 DR G70228 ADOCK 05000450 PDR
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, . i with Technical Specified requirements, thereby ensuring that the margin of safety is maintained. No new accidents or malfunctions can . result from this change. The design basis is not changed. Therefore this modification was determined to not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR 85-0179/ Figure 9.3-4a
Title:
Reactor Sample System Instrumentation Description and Basis For Change: A flow meter was added to the reactor sample system sink to provide additional monitoring capability.
Summary of Safety Evaluation: The change provides additional monitoring capability to the operator at the reactor sample sink. The additional equipment does not reduce the safety function or capability of the system.
Modification /FSAR Section: MR 85-0213 / Figure 9.2-7a Titlet Replace Auxiliary Boiler Sample Cooler with Larger Size Description and Basis For Change: The auxiliary boiler sample cooler was replaced with a larger sample cooler. Additionally the Turbine Plant Component Cooling Water (TPCCW) flow was increased through the sample cooler. The auxiliary boiler sampling line samples were flashing to steam, creating unstable boiler controls due to turbulence at the pH, conductivi v and dissolved solid probes. This condition created a safety hatard to personnel taking grab samples. The existing sample cooler and TPCCW flow were not large enough to maintain the sampling instruments' environmental temperature requirements.
Summary of Safety Evaluation: By increasing the size of the auxiliary boiler sample cooler and increasing the TPCCW flow, the sample temperature is reduced to within limits of the instrument sencors, thereby reducing the probability of occurrence, of auxiliary boiler malfunction. The sample from the boiler enables the auxiliary boiler to better operate in the automatic mode, thereby reducing the human element of manual control that could contribute to equipment malfunction. No margin of safety is reduced as e result of this change. Therefore, it was determined that no Unreviewed Safety Question exists as a result of this modification.
Modification /FSAR Section: MR 85-0291 / Figure 9.4-5
Title:
Diesel Generator Room Exhaust Fans Description and Basis For Change: Adjusted blades on diesel generator room exhaust fans to reduce air flow through fans to 100,000 cfo, each.
This modification was required to reduce the fan motor power for the Page A-2 4
purpose of load reduction on the emergency diesel generators. The flow through the fans was previously identified in the Safety Analysis Report as 134,650 cfm.
Summary of Safety Evaluation: The modification does not increase the probability of an accident or malfunction to the emergency diesel generators as the reduced fan capacity adequately provides cooling for the Diesel Generator Room and meets environmental room temperature requirements as provided in the Safety Analysis Report. By adjusting the fan blades, no new accident or malfunction is created. No margin of safety as defined in the Technical Specification basis is reduced.
Therefore it has been determined that no Unreviewed Safety Question exists as a result of this modification.
Modification /FSAR-Section: MR 85-0305 / Sections 6.4.2.2 and 9.4.1.2.1
Title:
Control Room HVAC Modification Description and Basis For Change: A recirculation path for the Main Control Room HVAC System air flow was established in order to reduce the amount of outside air being added to the system. The total air flow being filtered through the Control Room is still maintained at 4000 cfm.
The amount or outside air added to the system is reduced because the air leakage from the Control Room is less than originally predicted.
Positive pressure is still maintained.
Summary of Safety Evaluation: The control room is still maintained at positive pressure and the filtration flow rate is kept at 4000 cpm. The outside makeup air is reduced because the air leakage is less than-that originally calculated. The addition of the recirculation flow path does not create any different types of accidents or malfunctions.. The room pressurization is still maintained. Therefore, this modification was determined to not involve an Unreviewed Safety Question Modification / FSAR Section: MR 85-0312 / Figure 9.3-9
Title:
Standby Liquid Control System (SLCS) Drain Line .
1 Description and Basis For Change: Added a manual valve to the Standby l Liquid Control drain line to allow control of the drain flow going into l shipping drums. The SLC drain line provides a drain path for water used i during system testing. The addition of a manual valve on the drain line allows flow to be controlled during testing to prevent overflow of the shipping drums. I l
Summary of Safety Evaluation: The addition of the drain valve does not .
change the principle of operation or design of the SLC drain line. The )
line is normally capped closed and is used during surveillance testing l only. This modiffection does not effect the safety related function, increase the possibility of an accident or decrease the' margin of safety Page A-3 )
of the syttem. Therefore it was determined that this modification does not involve an Unreviewed Safety Question.
Modification / FSAR Section: MR 95-0430 / Figure 9.4-7a
Title:
Elevators Machine Room Ventilation Description and Basis For Change: Removed screen and transfer grille from elevator machine room ventilation opening to facilitate air balancing. The required flow path can be established without these devices. There is sufficient air flow into the elevator shaft to all'av the above devices to be deleted with little or no effect on air balance.
Summary of Safety Evaluation: The subject elevator, elevator equipment, and t rans fe r grills do not come into contact with or affect the operability of any safety related equipment. Sufficient air supply to subject mechanical equipment room has been verified. Outleakage down the elevator shaft ncgates the necessity for the transfer gril and screen. No new accidents or malfunction can result by making this change. The margin of safety as defined in the basis for the Technical Specifications is unchanged. Therefore, it was determined that this modification does not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR 85-0465 / Figure 10.4-3b
Title:
Circulating Water Blowdown Instrumentation Revisions Description and Basis For Change: The cooling tower Blowdown System was sized for two units but the final design is for one unit. The flow transmitters and sample system was revised to enable the equipment to funciton with the final design. The radiation detector purge line was modified to include a strainer to enhance the detector flushing source.
Summary of Safety Evaluation: The revisions do not affect any automatic or manual safety functions. The change to the flow indication and sample system are to account for the final design of River Bend. The change to the radiation detector flushing source is to insure the system is being properly purged.
Modification /FSAR Section: MR 85-0483 / Section 6.5.1.5
Title:
Differential Pressure Switches in SGTS Description and Basis For Change: Added an interlock to prevent operation of the SGTS heater units when the associated fan breaker is tripped. The diaphragm differential pressure switches, which are used to detect flow across the heater coils of the Standby Gas Treatment System, were set too low and were sensitive to small pressure changes.
This caused the heater to operate when it was not required to, and thus decreased the life of the heater.
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l Summary of Saf ety Evalt ation: This change ensures that the SGTS heater units will not inadvertently function upon failure or.misoperation of the flow switch. This tends to increase the reliability of the system by ensuring that the heaters do not age prematurely. The subject circuit revision does not affect the auto start function of the SGTS.
The modification has a negligible e f.fe c t on the probability of the heater starting by the addition of a series contact .from the breaker, when compared with all the possible failure mode contributing sequences.
The system meets the single failure criteria. Therefore, it was determined that this modification does not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR 85-0586 / Figure 10.4-Sa
Title:
Ultrasonic Resin Cleaner Modifications Description and Basis For Change: A set of resin samplers were installed in the condensate demineralized system to allow resin condition to be evaluated and to reduce radiation levels to the sampling i personnel.
Summary of Safety Eualuation: The samplers satisfy regulatory requirements and are in compliance with the Safety Analysis Report. The samplers were installed to facilitate accessibility and improve ALARA considerations.
Modification /FSAR Section: MR 85-0644/ Figure 11.2-If
Title:
Add Filter on LWS Backwash Tank Description and Basis For Change: Added filter to lower decant line on Liquid Waste Backwash Tank. The filter is used to prevent solids from being carried over to the floor drain tanks and subsequently into the filter / demineralized system. Solids in the filter / demineralized system could cause a malfunction.
, Summary of Safety Evaluation: This modification does not affect tank integrity nor does it affect any failure mechanisms of th- tank including the pressure boundary. The method of radwaste liquid or solids processing is not effected and this modification assures solid radwaste is not transferred to the floor drains.
Modification /FSAR Gection: MR 85-0735/ Section 6.2.3, 6.5.1, 7.3.1 and 9.4.6
Title:
Revise SGTS Suction Path as Backup For Annulus Pressure Control System Page A-5
Description and Basis For Change: The Standby Cas Treatment System (SGTS) serves as a backup to the Annulus Pressure Control System (APCS) during normal operation. The modification enables the air from the shielded compartments of the auxiliary building to be automatically diverted through the SGTS filter train in addition to air from the Annulus upon loss of APCS or upon an engineered safety feature signal.
Summary of Safety Evaluation: The modification configures the plant in the same condition for all events. All safety related functions and oprentions of the systems are unchanged. The change to the Safety Analysis Report in for consistency of the described action.
Modification /FSAR Section: MR 85-0956 / Section 9A.2.1.2
Title:
Add Keylocked Control Switch For Lockout of the RHR Shutdown Cooling Suction Valve.
Description and Basis for change: Added additional keylocked control switch at the Remote Shutdown Panel (RSP) for lockout of the residual heat remova' hutdown cooling suction valve (F008). Installation of the new contro. switch eliminated the need to de-energize F008 whenever reactor pressure exceeds that of the RHR suction piping design pressure.
The valve position indication is still maintained in the main control room.
Summary of Safety Evaluation: This modification did not change the original RHR System design intent and only provided an alternative means to assure subject valve is located out (blocked) when required. This change is considered an enhancement with no adverse safety or operations impact. No margin of safety was reduced as a result of this change.
Therefore, it was determined that this modification did not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR 85-0980 / Figure 9.3-4a, Figure 9.3-7h
Title:
Add Equipment Drain Line to Reactor Water Cleanup System (RWCU)
Description and Basis For Change: Added a drain line in the RWCU System for the drip pan under panel G33-2020, which is used to sample reactor water at various locations and terminate the piping in the raised rim equipment drain hubs. The drip pan serves to collect leakage in the panel. The original desi.gn inadvertently omitted the drainage piping from the drip pan to an equipment drain hub. This modification was made ;
in order to maintain consistency with design basis. l I
Summary of Safety Evaluation: The addition cf the drain line does not '
affect operation of reliability of the panel. The change is consistent with the design basis. There are no new possibilities for accidents or malfunctions as a result of the drain line. The added line only allows drainage of the drip pan. No margin of safety, as defined in the bases Page A-6
l for the Technical Specifications is reduced. Therefore it was determined that this modification does not involve an Unreviewed Safety Question.
l Modification /FSAR Section: MR 85-1079 / Figure 9.3-lb, 9.3-Ic
Title:
Add Air Filters For Containment and Drywell Airlocks Description and Basis For Change: Added air filters to instrument air lines that serve containment and drywell airlocks. These changes were recommended by the vendor to improve system reliability. They will prevent debris from entering the air locks.
Summary of Safety Evaluation: The addition of air filters does not compromise the safety related function of the airlocks. A loss of air supply (e.g. , clogged' air filters) is considered in the design basis for airlocks. The change improves operability and reliability of airlocks by preventing contaminants from entering the airlocks. In addition, the airlocks contain the necessary hardware to assure adequate air supply for up to 30 days after isolation from the air source. There is no reduction in the margin of safety for any equipment as a result of this change. Therefore, it was determined that an Unreviewed Safety Question did not exist as a result of this modification.
Modification /FSAR Section: MR 85-1140 / Fig. 6.2-73b
Title:
Add Heat Trace For Drywell Radiation lionitor.
Description and Basis For Change: Added heat tracing to sample tubing of the drywell atmospheric radiation monitor. The heat tracing is needed to prevent moisture from accumulating in the return sample line and draining back to the monitor. The modification is needed for reliable operation of the subject safety-related radiation monitor.
Summary of Safety Evaluation: The failure mode of this monitor to inadvertently alarm or to fail to alarm is unaffected by this change.
The reliability of the radiation monitor is improved as a result of preventing moisture from accumulating in the return sample line. The manufacturer's temperature limits on the detector will not be exceeded and the detectors ability to perform its function as required by Technical Specification 3.4.3.1 will be unaffected. Therefore, it was determined that no Unreviewed Safety Question exists as a result of this modification.
Modification /FSAR Section: MR 85-1460 / Figure 11.2-Ic, Figure 11.2-1k
Title:
Remove Restricting Orifice Page A-7
Description and Basis For Change:
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Removed restricting orifices in liquid radwaste fi1ter backwash pumps. The restricting orifices were removed to reduce the probability of cavitation of the backwash pumps and to help fluidize the filter media during the backwash agitation cycle. Prior to removal of the orifices, the filters would not backwash.
Summary of Safety Evaluation: The modification decreases the probability of pump cavitation during operation. The system operability is enhanced and no new possibilities for an accident or malfunction are created. This change does not affect any margin of safety for any technical specification basis, including radioactive effluents. The change allows for the operation of backwashing the filters, which improves system operation. Therefore, it was determined that no Unreviewed Safety Question exists as a result of this modification.
fs di stion/FSAR Section: MR 86-0203 / Figure 6.7-1B T1 a: Leakage Control System Description and Basis For Change: The change simplifies the compressor inlet vlave to normally open dcring systems stnedby and shutdown conditions by removing unnecessary controls. This change places the system in its safety mode.
Summary of Safety Evaluation: The system configuration is in the design (safety) condition. Since the operation and function of the system us discussed in the Safety Analysis Report is unchanged, no unreviewed safety question exists as a result of this change.
Modification /PSAR Section: MR 86-0223/ Fig. 9.3-6
Title:
Drain Line Deletion Description and Basis For Change: Deleted the ISO-Phase Bus Duct Cooler drain line. Water in the Coil Housing would be caused from tube leaks, not condensation. Tube leaks are very rare in these units. Therefore, the drain line is not necessary.
Summary of Safety Evaluation: In the event that a tube leak occurs, the internal level alarms will be activated. At that time any of the seven drain plugs can be removed for drainage and repairs. Therefore, the function of t'.is non-safety-related equipment will not be affected.
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Modification /FSAR Section: MR 86-0227 / Figure 10.4-7h i
Title:
Relocate Level Switch Variable Leg l l
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Description and Basis For Change: Relocated variable legs of 1HDL-LS8A and B from the bottom of the 5th pt. heaters to the 16-inch drain line out of the heaters. The change will lessen the chance of feedwater transients caused by spurious feedwater heater string isolations.
l l Summary of Safety Evaluation: Accidents and malfunctions eminating from feedwater heater isolations as described in the safety analysis report, are not effected by the change. The drainage will eliminate spurious isolations while still providing turbine protection. No margin of i safety, as defined in the bases for the Technical Specification, is reduced. Therefore, it- was determined that no Unreviewed Safety Question exists as a result of this modification.
l Modification /FSAR Section: MR 86-0374/ Figure 9.4-4c l
Title:
Add Duct Pieces to Unit Cooler Supply Air Header Description and Basis for Change: Added two duct pieces to supply air header from unit cooler 1 HUT-UC20. The west side of the main turbine did not receive any air circulation from the unit cooler. The modification will allow the unit cooler to supply air circulation to the west side of the main turbine.
Summary of Safety Evaluation: The ductwork is not connected to any safety related components nor does the subject unit cooler perform a function necessary for the safe shutdown of River Bend. The air supply is still maintained within originally ventilated area. Ductwork from the subject unit cooler is not considered in the basis for any technical specification. Therefore, it was' determined that this modification does not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR86-0454 / 10.4.7.5.1 and Fig. 10.4-36
Title:
Feedwater System Instrumentation Description and Basis For Change: 'The modification adds a time delay to the feedwater pump low oil pressure trip to allow the backup oil pump to l start. The change is to reduce major feedwater transients and reactor i scrams.
l Summary of Safety Evaluation [
The feedwater system is not required for )
the safe shutdown of the plant. This change will allow continued j i operation of the feedwater system in the event of momentary low oil l pressure thereby maintaining system operation and function described by j the Safety Analysis Report and reducing unnecessary reactor trips, i
I Modification /FSAR Section: MR 86-0530 / Section 9.5.5.2 l Page A-9 l
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Title:
Revision to the Diesel Jacket-;later Cooling System Corrosion Inhibitor Description and Basis For Change: The Chemistry Department reported difficulty keeping the pH within the vendor's recommended range of 8.25 to 9.75 in. the diesel jacket water coolant. An engineering investigation revealed that one of the constituents of Malco 1355 was sodium nitrite. Per the vendor's documentation it is stated that the use of nitrites may adversely affect the fatigue life of the major cast parts such as cylinder heads. This information prompted a search for a suitable rust inhibitor which did not contain nitrites. Based upon an engin2ering evaluation of rust inhibitors, Calgon-LCS40, a molybdate inhibitor, was the most logical choice for the following reasons:
(1) It is not a toxic like' chromate (2) It is a metal salt like chromate, a good inhibitor and has good heat transfer characteristics (3) It does not have any nitroger which might affect the fatigue life I
of the cylinder heads.
(4) The pH range of the molybdate is 8.5 which falls within the vendor's specified range of 8.25-9.i5 l
(5) Disposal cost is eliminated since the . molybdate water mixture can be emptied to floor drains (6) Numerous utilities are using molydates inhibitors Summary of Safety Evaluation: The replacement of Nalco 1355 corrosion inhibitor with Calgon-LCS40 will increase the reliability of the diesel generator and does not cause major cast parts to become brittle or break. .Also, the molybdate-base inhibitor has no characteristics which would cause either direct or indirect environmental or disposal problems. 1 Modification /FSAR Section: MR 86-0588 / Sections 9.5.9.2, 9.5.9.2, Table 9.5-5 1
Title:
Nitrogen Bottles Stored Inside of Containment Description and Basis For Change: Three nitrogen bottles are now permanently stored inside of containment. The nitrogen bottles are used to recharge the Control Rod Drive (CRD) accumulators. Prior to this modification, the nitrogen bottles were stored outside containment and l had to be carried insidefto recharge the accumulators.
l Summary of Safety Evaluation: In accordance with performed !
calculations, the tanks are restrained such that during all plant !
conditions they cannot become missiles and damage any safety related equipment. The tanks are supplied with an integral safety relief valve in order to limit their internal pressure. In a fire environment, the cylinders are equipped with a s fety relief. Therefore, it has been determined that no Unreviewed Safety Question exists as a result of this modification.
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Modification /FSAR Section: MR 86-0672 / Figure 10.4-7a
Title:
Install Restricting Orifices Description and Basis For Change: Installed restricting orifices downstream of the feedwater pump minimum flow recirculation valves.
This modification was required to prevent cavitation damage to the downstream piping from the valve.
Summary of Safety Evaluation: This modification has no impact on the operability of the valve or feedpump recirculation system. The effects of the orifices on the system operability were analyzed and it was concluded not to effect system operability. The system operating lower limit recirculation flow rate is not impacted. No margin of safety, as defined in the bases for the Technical Specifications, is reduced.
Therefore it was determined that this modification does not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR86-0767/ Figure 4.6-5 a, b, c, and d
Title:
Control Rod Drive Hydraulic System Document Revision Description and Basis For Change: Editorial revisions were made to equipment data and mark numbers and continuation notation to reflect the final configuration. The changes to relief valve setpoint and the removal of the maintenance pump shutoff on high discharge pressure are to show the as-built design.
Summary of Safety Evaluation: Editorial revisions -to show equipment data, mark numbers and continuation notation will not affect the function or operation of the system. The revision to the safety valve setpoint will continue to support the function of the valve and the new setpoint is below the associated system design pressure. Therefore, the operability and function of the system is unchanged. The removal of the maintenance pump shutoff on high discharge pressure will not affect system operation or function. Since the operation and function of the system is unchanged and no new modes of operation have been introduced, the system, as revised, continues to support the safety analysis.
Modification /FSAR Section: MR86-0824/ Figure 9.4-3 a and b
Title:
Radwaste Building HVAC Document Revisions Description and Basia For Change: Editorial revisions were made to equipment mark numbers and drawing continuation notntion to reflect final design; also normal system flow data was included for information.
Changes to instrumentation and ductwork configuration to show as-built design and routing information.
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Summary of Safety Evaluation: Editorin) revisions to show equipment mark numbers, continuation and flow data will not affect the function or operation of the system as required to support the safety analysis. The revisions to the instrumentation to show the as-built design will not change the system discussion contained in the safety analysis report or result in new modes of operation. The changes to ductwork configuration is to show the as-beilt design which will support the discussion contained in the Safety Analysis Report. This change will not produce new modes of operation from those previously evaluated.
Modification /FSAR Section: MR 86-0893 / Figure 9.2-24b
Title:
Modification to Makeup Water System Description and Basis of Change: Added flanged correction and gate valve to makeup water system. The connection is for a blowdown cooling system in the event the Circulating Water System flume blowdown line to the Mississippi River approaches NPDES permit temperature limits. The gate valve is to isolate the connection.
Summary of Safety Evaluation: The correction is to a non-nuclear safety system. The flanged correction is isolated by a gate valve. Its failure has no effect on the operation of equipment important to safety.
This system is not addressed in the technical specification bases.
Therefore, it was concluded that this inodification does not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR 86-0894/ Fig. 9.2-21b
Title:
Replaced Valve With a Tee in the Condensate Line Description and Basis For Change: A lock-closed valve (V490) was replaced with a flange tee to supply condensate water during radwaste start-up and test activities. The tee is part of the condensate make-up system located in the Radwaste Building (Cat II) and is a non-safety related portion of the system. This tee may be needed in the future and will remain installed.
Summary of Safety Evaluation: A tee in the condensate line in the Radwaste Building will not affect the condensate system due to the small Ifne size (2 inches diameter) and will not create an event different than the previous design. System operation and safety related equipment is unchanged.
I Modification /FSAR Section: MR 86-1000/ Fig. 9.4-2a
Title:
Capping of One Line on the Fuel Building Pressure Monitoring System.
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Description and Basis For Change: The Fuel Building Pressure Monitoring System has 3 (3/4") small bore lines sensor located outside the building at approximately 160' Elev. on the West, North and East sides of the buildings. These lines monitor the Fuel Building pressure with respect to atmospheric pressure. The west side of the Fuel Building is surrounded by the Radwaste Building, ' Standby Service Water Cooling Tower 6nd other Plant Buildings forming a configuration which in turn develops a unique wind pattern in the vicinity which cause spurious alarms.
Summary of Safety Evaluation: This part of the system is Q-Class 2. It is isolated from all Q-Class I systems and equipment. The building pressure still can be monitored by the remaining two redundant taps.
Therefore, the west side tap was capped to prevent spurious alarms. The l subject change does not create any malfunction to any other safety-related equipment / systems or create any kind of accident.
Modification /FSAR Section: MR 86-1038 / Figure 9.2-21a
Title:
Add Drain Line From Condensate Transfer Pumps Description and Basis For Change: Add drain line from drip pans of condensate transfer pumps to the condensate storage tank sump. The drip pans previously drained into buckets beside the pumps. This is contaminated water and there is a possibility of spilling the buckets and contaminating the surrounding area. This is a solution to a ALARA concern.
Summary of Safety Evaluation: The added drain line configuration is less susceptible to accidents or spills than the buckets. A different type of accident or malfunction is not created by routing a drain line from the pumps to the storage tank sumps. The margin of safety will be increased by this modification. Therefore, it has been determined that no Unreviewed Safety Question exists as a result of this modification Modification /FSAR Section: MR86-1120/ Figure 10.4-4
Title:
Chemical Feed System Description and Basis For Change: Changed the normal position of two valves to closed with logic to open when the respective pump starts.
Added and relocated drain valves and piping for system maintenance purposes and added a hypochlorite injection system in response to I6E Bulletin 81-03.
Summary of Safety Evaluation: This system is not safety related and will continue to function as discussed in the Safety Analysis Report.
The changes to valve position has been determined not to affect the operation or function. The revisions to system drain valves and piping will not affect system function because the drain valves are closed during normal operation. The addition of the injection system is to Page A-13 i
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l enhance the reliability of plant heat exchangers, thereby assuring l operation as required.
Modification /FSAR Section: MR 86-1134 / Section 11.4.2.3.3
Title:
Install Dry Activated Waste (DAW) Compactor.
Description and Basis of Change: The Dry Activated Waste Compactor was '
installed in the Radwaste Building at elevation 106 and was added to the l applicable FSAR Figures. The compactor was installed as previously described in FSAR Section 11.4.2. The compactor utilizes 52 gallon drums for compaction of dry activated compressible waste. When filled, these drums are packaged in DOT approved 55 gallon drums for shipment.
Summary of Safety Evaluation: The dry activated waste compactor is currently described in the FSAR. Its installation and use is as described and thus has been previously evaluated. The change in drum size will allow for compaction and will not effect any safety evaluations in the FSAR. DAW will still be shipped in DOT approved-containers. Therefore, this modification was determined to not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR 86-1294/ Fig. 9A.2-1
Title:
Revise Fire Wall Rating Description and Basis for Change: Fire areas (C-10A and C-12) in the Control Building were originally determined on the basis of the fire hazards analysis but prior to development of the safe shutdown specification 240.201. A detailed evaluation indicates that these two fire areas can be combined into one fire area without compromising the safe shutdown of the plant. Both areas contain only Division I cables and an alternate method can be utilized to ensure safe shutdown of the plant in case of fire in either fire area C-10A or C-12. I Summary of Safety Evaluation: Fire areas C-10A and C-12 contain Division I cables only. No other safety related equipment is involved.
Another method can be used to safely shutdown the plant in case of fire in either fire area. Therefore, deleting fire ratings of the common walls between areas C-10A and C-12 and redesignating these areas as one fire area with tuo zones C-10A/Z-1 and C-10A/Z-2 does not affect safe operation or safe shutdown capabilities.
Modification /FSAR Section: MR 86-1304/ Fig. 10.4-3b
Title:
Flow Improvement to Circulating Water Blowdown Cooler Description and Basis for Change: In order to increase blowdown flow to j the circulating water blowdown system (CWS) heat exchangers, the lateral l Page A-14 l
line between valves ICWS-V61 and ICWS-V62 was replaced with a 45 elbow.
This modification, results in an improved flow path, reduced pressure drop and increased flow to the circulating water blowdown heat {
exchangers (ICWS-El and ICWS-E2).
Summary of Safety Evaluation: The improvement of flow to the non-safety related circulating water blowdown heat exchangers does not affect the safe operation and shutdown of the' plant since circulating water blowdown flow is not a parameter used in the safety analysis, j l
Modification /FSAR Section: MR 86-1309/ Fig. 7.3-12
Title:
Elimination of Spurious Alarm in Control Room Description and Basis For Change: The Control Room is maintained at a positive pressure relative to ambient differential pressure. An alarm alerts the operators when the pressure drops below a predefined value.
Modifications were made to the alarm circuit to eliminate spurious alarms. Indications of low differential pressure in the Control Room j and low pressure conditions exist whenever personnel enter the Control Room. A.. time delay has been added so that spurious alarms will be eliminated.
Summary of Safety Evaluation: The subject alarm is used to indicate the pressure differential so that appropriate actions can be taken.
However, these alarms are not used to initiate actions required by the Safety Analysis. There is no change to the function and therefore does not create or modify the probability of a accident or the consequences. '
l Modification /FSAR Section: MR 86-1496/ Fig. 5.4-8 Fig. 5.4-12a, b, e j j Fig. 6.3-1 1 Fig. 6.3-4 Fig. 6.7-lb MR 86-1568/ Fig. 4.6-Sa Fig. 5.4-12a, b & c Fig. 5.4-15a & b-Fig. 6.2-73c Fig. 9.2-la, b, c, d, e & f Fig. 9.2-2a & b Fig. 9.2-8a, d, f, g, h & j j Fig. 9.2-21a, b & c j Fig. 9.3-la, b & c
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Fig. 9.3-2c j Fig. 9.3-7b, f & n I i Fig. 9.4-la l Fig. 9.4-7a Fig. 9.5-2a j Page A-15 l l
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Fig. 10.3-lb Fig. 10.4-6a Fig. 10.4-7a & b MR 86-1636/ Fig. 11.2-la through f MR 86-1673/ Fig. 10.4-7a,'b, c, d, e, f, g, b & j Fig. 9.3-la, b,.c Fig. 10.4-4 Fig. 9.5-la Fig. 9.3-8a, b, c, d & e Fig. 11.4-1 Fig. 11.3-2c Fig. 9.3-6a, b & d
Title:
Delete or Add Locking Requirement to Valves Description and Basis For Change: The locking requirements for valves were revised such that only valves required to be locked by regulatory or design requirements are required to'be locked.
Summary of Safety Evaluation: Those valves required by . regulatory or design requirements shall be shown on P&ID's as locked either open or closed. The valves identified do not require manual operation for a j safe shutdown of the plant for design basis events. The locking of the j valves will not inhibit any motor operated valve from actuation. j Modification /FSAR Section: MR 86-1584/ Fig. 9A.2-3 Fig. 9A.2-5 Fig. 9A.2-6 l Fig. 9A. 2--9 )
Title:
Change Turbine Bearing Fire Protection Nozzles Description and Basis For Change: This MR changes turbine bearing fire I protection systems WS-3A, 3B, 3C & 3D from deluge to preaction systems (PS) by addition of a fusible link sprinkler head. By changing to the ,
PS, it will reduce the risk of inadvertent wetting of. turbine bearings !
which has previously caused a turbine trip and reactor scram. ,
Summary of Safety Evaluation: By changing nozzles, the water supply to j turbine bearing will be slightly increased. System operation by I manually tripping the deluge valve is unchanged. Fusible link heads I insure that a fire is present before water is discharged.
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. Modification /FSAR Section: MR 86-1626 / Section 11.4.2, 12.4.2 Table 12.4-2
Title:
Add Dry Active Waste Storage Facility Description and Bases For Change: Use existing warehouse for storage of Dry Active Waste (DAW) on a temporary (less than five. years) basis.
Additional etorage space is required due to the limited offsite burial allocation and the limited onsite storage space in the Radwaste Building. No liquid or gaseous. radioactive waste is stored in the new DAW storage facility. A limited amount of DAW storage space is currently available in the Radwaste Building and has been evaluated in the FSAR. The new facility adds additional storage space equivalent to approximately 1070 drums (55 gallon), or ten months storage of Dry Activated Waste.
Summary of Safety Evaluation: The offsite dose due to direct radiation from the DAW temporary storage facility is less than that stated in the Standard Review Plan, Section 11.4. Offsite dose calculations have been performed that show the dose to be less than 1 mrem at the nearest boundary. The minimum storage requirements, as detailed in the FSAR, are maintained. There will be no open processing of DAW, nor handling or storage of liquids in the building. Therefore, there is no possibility for liquid or gaseous releases in the building. The building protects the containers from weather (i.e., wind, rain) damage.
There is no existing analysis in the FSAR which would preclude use of the existing building for storage of DAW. No new type of accident is peatulated as DAW storage.has been previously evaluated in the FSAR and the differences are not postulated to cause a different type of accident or malfunction. Based on design calculations, this change will not significantly effect total dose, as identified in Technical Specification 3/4.11.4. Therefore it has been concluded that this modification does not involve an Unreviewed Safety Question.
Modification /FSAR Section: MR 86-1647/ Fig. 7.3-14
Title:
Rewiring of HVK Pump Start Switch Description and Basis For Change: This modification revises the start circuit for chilled water pumps IHVK*PIC and 1HVK*PID (circuit 1HVKA04 and 1HVKB04, respectively). It allows these pumps to be started when no air flow exists across the respective air conditioning units or when either associated chiller is auto-tripped. This change does not bypass or modify any safety related functions.
Summary of Safety Evaluation: This modification- provides greater flexibility in the operation of the HVC/HVK systems. This change bypasses the " chiller auto-trip" and "Iow air flow at ACU" trips in the start circuit of the back-up pumps to allow the respective air conditioning unit to start thereby increasing the availability of the HVK/HVC systems. Since no safety related functions have been bypassed and the remaining system functions are as discussed in the FSAR.
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Modification /FSAR Section: MR 86-1652/ Fig. 9.3-le
Title:
Add Sprinkler Connection Description and Basis For Change: A sprinkler system was added to a new tool issue / storage facility on the west side of the Site Administration Building. This installation taps off the existing sprinkler system in the Site Administration to supply water to the new building. The new structure was placed between two existing temporary buildings and the southern most building (temporary) was already supplied from this tap to.
protect the Site Administration Building from exposure fires originating in the temporary structures on the west side.
Summary of Safety Evaluation: The fire systems involved are not in or adjacent to safety related areas. This modification has been evaluated and found to be within present system performance requirements.
Therefore, the change will not create an adverse effect on any equipment required for safe operation or safe shutdown of the plant.
Modification /FSAR Section: MR 86-1658/ Fig. 4.6-Sc i
Title:
Lock Valves in Neutral Position Description and Basis For Change: Valves IC11*A0VF180 and IC11*A0VF181 were locked in the neutral position. If handwheels are not in the neutral position upon receipt of an' auto-actuation,-a signal from the Control Room may result in damage to the valve.
Summary of Safety Evaluation: Locking of the valve handwheel in the i neutral position does not change the design, function or operation of the valves, this change will only prevent the handwheel from turning during motor operated actuation and ensure that there is no interference with the actuation of the valves.
Modification /FSAR Section: MR 86-1691/ Fig. 6.7-2 Fig. 9.3-6 Fig. 15.6-5
Title:
Revising Trip Set Points for Flow Indicator Switch (1E33*ESN608)
Description and Basis For Change: During testing of the Main Steam -
Positive Leakage. Control System (MS-PLCS), the steady state air flow i rate approached the trip setpoint of IE33*ESN608. This trip isolates ;
the air supply and isolates the system. Raising the setpoint from 12 scfm to 14 sefm will still maintain the original design basis of the ;
limiting maximum air flow which will not over-pressurize the containment i post-LOCA. This will allow functional testing of MS-PLCS Div. I without approaching the trip setpoint.
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- l. Summary of Safety Evaluation: Changes in the high air flow setpoint will not impact the safety-related functions of this system. The amount of air flow allowed prior to a trip will continue to support the design requirement and will not affect the operability of the system.
Modification /FSAR Section: MR 86-1789/ Fig. 9.4-6a
Title:
Revise dampers IHVY*DMP6A, 6B, 6C & 6D to Normally Open l
l Description and Basis For Change: Revised dampers IHVP*DMP6A, 6B, 6C &
6D to be normally open. .The original design of the dampers is to i
prevent backflow through the Standby Cooling Towers switch gear i ventilation fan.
1 Summary of Safety Evaluation: The final design of the cooling tower results in a free air path to the environment on both the fan inlet and exhaust; therefore, back draft protection is not required. The ventilation requirements for the room have been maintained.
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i SECTION B - PROCEDURE CHANGES During this time frame, various procedures were revised within the descriptions in the safety analysis report (FSAR) rursuant to 10 CFR 50.59. No procedure changes were performed that constituted unreviewed safety questions.
Special test procedures performed were also reviewed and no unreviewed safety questions were found. No special tests which were different than those described in the safety analysis report were identified.
Procedure /FSAR Section: ADM-0003 / Section 13.5.1
Title:
Development Control and Use of Procedures j Description and Basis for Change: The procedure was . revised to ;
incorporate minor administrative changes to clarify how procedures may be cancelled and to reflect recent engineering organization changes.
Summary of Safety Evaluation: This change was administrative in nature with minor procedural changes and reflecting organizational changes. 1 The organizational changes are covered in other FSAR changes. The changes present no impact on plant safety in that this procedure only describes administrative controls for developing and revising plant procedures.
Procedurt/FSAR Section: Temporary Change Notice 87-0016 to MLP-7509/
Section 9.1.4.3
Title:
Containment Shield Plug Movement in Mode 1 Description and Basis for Change: This change was recommended to allow the shield plugs to be installed while the unit was in Mode 1. Existing plant procedures did not allow this activity as did the FSAR. This restriction was based on a general interpretation of NUREG-0612 evaluation. A detailed definition was necessary to allow shield plug installation.
Summary of Safety Evaluation: The evaluation indicated that the I Technical Specification's safety margins were not reduced. The load lifting evaluation performed in accordance with NUREG-0612 which confirmed the lifting of the shield plugs and a postulated drop would be within the present design criteria for the structures involved and would not result -in damage to the RWCU System. Administrative Controls are estabidshed to ensure the shield plug movements would be limited to the areas evaluated and to limit the height of lifting to less than the postulated drop heights.
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Procedure /FSAR Section: Temporary Procedure 86-05/
Section 6.2.4.3.7.2 and Tbl. 6.2-52
Title:
Containment Purge Valve Tests Description and Basis for Change: Plugs were temporarily installed in the exhaust solenoids for the containment purge valves in an attempt to slow down the closing strokes of the valves. Data were taken with different combinations of exhaust solenoids plugged. MR 86-0228 was generated from the data collected by this procedure.
Summary of Safety Evaluation: This procedure was performed with the plant in cold shutdown. To ensure operability of the valves, the valves were returned to their normal configuration and stroke time tested per the applicable ASME Section XI ISI procedure after completion of the test.
b Procedure /FSAR Section: SOP-0006/ Temporary Procedure 86-21/
Section 13.5.1.2
Title:
Circulating Water, Cooling Tower Vacuum Priming and Blowdown Heat Exchangers Description and Basis for Change: This procedure revision provides instructions for the start-up, normal operations and shutdown of the Circulating Water Blowdown Heat Exchanger System.
Summary of Safety Evaluation: The systems involved are not required for the safe shutdown of the plant and will not affect the operation or function of the safe shutdown or other safety-related equipment. The operation or failure of the systems addressed will not affect the circulations or makeup water systems.
Procedure /FSAR Section: Temporary Procedure 86-26 / Section 10.2
Title:
Turbine Generator Torsional Natural Frequencies Test Description and Basis for Change: The procedure was for analysis purposes only. Torsion collars and probes were temporarily installed on the turbine generator bearings. The turbine generator rotor natural frequencies and damping, of sub and super synchronous modes, were measured from approximately 10 Hz to 135 Hz. Data was collected to determine if high order resonant torsional frequencies were present around 120 Hz which could create a reliability problem for the last ctage buckets on the turbine. The procedure was issued for one time use ,
i and was cancelled 90 days after issuance.
{
i Summary of Safety Evaluatiog: Calculations indicate that the responses to the procedure are within the design capabilities of the machine. The torque level applied during this test was significantly less than that Page B-2
3 m !
encountered during normal full load operation. With the completion of the procedure the generator was successfully returned to service and synchronized to the grid.
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'I Procedure /FSAR Section: SSP-1-001 (IPC-1-001-1-4) / Section 13.5.2.1 l
Title:
Preparation, Revision, and Control of Station Support Procedures Description and Basis for Change: Procedure change to the periodic review requirements for Station Support Procedures. Station Support Manual procedures are controlled by ANS-3.2, ANSI N18.7- 1976 Paragraph 5.2.15 which requires that plant procedures be reviewed no les than every two years to determine if changes are necessary or desirable.
Previously, all station support manual procedures were to be reviewed ,
once every year which in in excess of Regulatory requirements given in !
Regulatory Guide 1.33. The emergency implementing procedures (EIPs) require a periodic review once a year pursuant to Emergency Plan Section 13.3.7.2 and the plant security procedures (PSP) also require periodic review once a year pursuant to Technical Specification 6.5.2.3.
Summary of Safety Evaluation: This change remains in compliance to the l requirements of ANS-3.2, ANSI N18.7 1976 Paragraph 5.2.15 which requires ,
l at a minimum a two year periodic review be conducted on station support !
l manual procedures (except EIPs and PSPs). Since the change complies '{
with all regulatory requirements, will not revise the design or "
operation of the plant and any interim revision to the affected procedures as required by ANSI N18.7-1976. The changes does not l represent an increase in the probability of an event described in the )
Safety Analysis Report. I Procedure /FSAR Section: RBNP-042, Rev. 0 l FSAR, Chapter 17
Title:
River Bend Station ASME Section XI Program, Organization, and Responsibilities Description and Basis: A procedure change was initiated to reflect administrative changes / reorganization (i.e., Engineering reorganization).
Safety Evaluacion The reorganization results in a change of administrative reporting by the ASME XI program organization only. No revision to the responsibilities or function have been made. The ability and authority of the group to perform the specified duties is unchanged.
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GULF STATES UTILITIES COMPANY HIVER BIND ST Ah0h POST OFFICE HOX 220 ' ST FRANCISvlLLE LOulSIANA 7077E ARE A COD ( 504 635 00901 346 Ft651 August 28, 1987 RBG- 26,521 File Nos. C9.5, G9.25.1.5 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 I Enclosed is Gulf States Utilities' Annual Report . pursuant to 10CFR50.59(b) (2) . This report describes facility changes, procedure changes, tests and experiments from March 1, 1986 to March 1, 1987.
These changes are included in the August, 1987 Updated Safety Analysis Report which is up to date as of a maximum of 6 months prior to its submittal (i.e. , March 1, 1987) . As a result of preparing the subject-reports, additional " document change only" changes were identified. A supplemental report will be submitted on these additional changes for which 10CFR50.59 evaluations have been performed. If further information is required, please contact Mr. L.A. England at (409)839-3011.
Sincerely, J. E. Booker Manager-River Bend Oversight River Bend Nuclear Group JEB/ ERG / /ch cc: Mr. Robert D. Martin, Regional Administrator U.S. Nuclear Regulatory Commission l Region IV l 611 Ryan Plaza Drive, Suite 1000 l Arlington, TX 76011 NRC Resident Inspector Post Office Box 1051 St. Francisville, LA 70775 g., h
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