ML20246A547
| ML20246A547 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/31/1988 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20246A529 | List: |
| References | |
| NUDOCS 8905080277 | |
| Download: ML20246A547 (162) | |
Text
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COMPANY PLANT V0GTLE UXIT 1
AXXUAL REPORT PART 2 l
DOCKET NUMBER 5000424 LICENSE NUMBER NPF-68
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I PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 1988' ANNUAL REPORT PART 2 TABLE OF CONTENTS I.
INTRODUCTION II. DESIGN CHANGES, PROCEDURAL CHANGES, AND TESTS OR EXPERIMENTS 0 PLANT DESIGN CHANGES 0 TESTS OR EXPERIMENTS III. EMERGENCY CORE COOLING SYSTEMS OUTAGE DATA REPORT IV. ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT V.
ANNUAL ENVIRONMENTAL OPERATING REPORT
I PLANT V0GTLE UN1T 1 1988 ANNUAL REPORT - PART 2 i
INTRODUC(ION Plant Vogtle Unit 1 is powered by a pressured water reactor rated at 3411 megawatts thermal.
It is located on the Savannah River in Burke County Georgia, at a site 34 miles southeast of Augusta.
An operating 3
l license was initially received on January 16, 1987 and Commercial Operation started on May 31, 1987.
The unit is currently operating in its second fuel cycle.
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l II 1988 ANNUAL REPORT - PART 2 10CFR50-50(b) REPORT i
1 PLANT DESIGN CHANGES 2
- a
l II 1988 ANNUAL REPORT - PART 2 10 CFR50.59(b) REPORT 86-V1 E0013 Proteus computer signal cable replace existing IV.X/IXC cables with card-edge to card-edge cables supplied by Westinghouse.
1.
Change is for cable replacement only.
System operation is unchanged.
2.
Replacement of signal cables minimizes possibility of malfunction.
3.
System reliability will be improved.
Non IE cable replacement only; no impact on safety.
87-VCE0043 Add new model number for 125V DC undervoltage Relay to existing drawing.
No physical change required. Drawing change only. New model number is purchased to use as replacement for old model.
1.
This change is only a drawing change which allows the use of new model relays whenever there is a need. The new relays are physically and functionally identical and will not increase the probability of an accident as described in FSAR.
2.
The new relay is used only as an alarm relay which is physically and functionally identical to the old relay.
The replacement will not create or increase the probability of an accident.
3.
Since the new relays are physically and functionally the same, the modification does not decrease the Safety Margin of Tech. Spec. 3.8.2.1, 3.8.2.2, 3.8.3.1, and 3.8.3.2 or other Tech. Spec. Sections.
87-V1E0050 This design change clariffes the replacement of the electromechanical timers "0DT" and " TOR" in the BTRS chillers with solid state timers.
1.
The changir.g of timers to solid state poses no change to the probability or consequences of any FSAR Chapter 15 accident analysis. The design change should increase the reliability of the BTRS chillers.
2.
This change is to the BTRS chillers which are not assumed to function during accident analysis performed in FSAR Chapter 15.
This change does not create the possibility for any accident or component malfunction not presently analyzed in the FSAR.
3.
The BTRS chillers are non safety related and are not discussed in the Technical Specifications and as such 3
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1I 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT have no margin of safety bases as defined by the Technical Specifications 3/4.4 or 3/4.7.-
87-V1E0070 This change provides a controlled exhaust air path from the ARB so that any airborne contaminants are pulled into the Auxiliary Building Continuous Exhaust Units.
1.
The ARB and the exhaust units are not safety related and are not included in the FSAR Section 15 accident analyses, so this change does not increase the probability or consequences of any analyzed malfunction.
2.
This change affects non-safety related equipment only end does not create the possibility of an accident described in the FSAR based on review of Sections 9.4, 11.4, and 14.
3.
This change does not decrease the safety margin defined in the Tech. Spec. (ref. Section 3.11.2.4), but instead the Tech. Spec. requirements with
-aids in fulfilling (even though the ARB itself is not regard to the ARB specifically referred to).
87-VIE 0072 The purpose of this DCP is to increase setpoint on nitrogen supply valve IPCV-7709 from 35 psig to 85 psig to prevent settling and clogging in the resin transfer piping an steam generator blowdown spent resin storage tank.
In addition this DCP changes setpoint on 1-PSV-7734 from 150 to 220 psig and design pressure for Resin Sluice pump from 150 to 220 psig.
1.
These changes have no effect on the equipment or comp:,nents assumed to function in the accident analysis of FSAR Section 15.
2.
An increase in pressure setpoints on valve IPCV-7709 and relief valve 1PSV-7734 is the only physical change involved since all piping and components are designed to accommodate the new pressure and system operation is not otherwise affected.
No new possibilities of accident or malfunction are created.
3.
These changes (increase setpoint for IPCV-7709 and PSV-7734) do not change the bases as defined in Section 3.4.11.1 of the Technical Specifications.
87-V1E0073 Remove the existing Waste Evaporator concentrates pump i
from the skid and replace with a larger more reliable i
pump.
Relocate Waste Evaporator distilled pump concentrates pump discharge gages. Add isolation and calibration taps to the Waste Evaporator level sensing 4
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l II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT l
line. Add a check valve in the Waste Evaporator recycle
.line. Move Waste Evaporator eductor upstream of feed preheater.
Add a level transmitter, level indicator, and a
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pressure gauge to the Waste Evaporator vent condenser.
Add
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a PH monitor in the sampling line and provide a remote e
readout for the monitor at the Waste Evaporator Control Panel. Add an interlock between concentrates discharge valve and boric acid discharge valve.
Provide an interlock on the Waste Evaporator concentrates pump'to prevent i
cavi tation.
1.
There is no change to the probability of occurrence or l
l malfunction consequences assumed in FSAR chapter 15, section 9.5, appendix 9 or 98.
2.
This change does not create a scenario which is not bounded by FSAR chapter 15, section 9.5 or appendix 9A or 9B.
l 3.
There are no bases for the Waste Evaporator discussed in the Technical Specifications.
This included review of Tech.
Specs. 3/4.7, 3/4.11, and 3/4.12.
87-V1E0076 Replace existirg 0-540 gpm scale on FI-7286 'brbine Plant i
Cooling Water to Steam Generator Blowdown TrLii Heat i
Exchanger) with a 0-750 gpm scale to show adequate cooling water flow rate without damage to the indicator.
1.
Providing proper flow indicator (F1-7286) scale 0-750 gpm on Turbine Plant Cooling Water (TPCW) to S.G.B. Trim Heat Exchanger does not change to FSAR Section 9.2.11 or 10.4.8.
2.
Scale change from (0-540 gpm to 0-750 gpm) to 62J device on non safety related system has no impact on FSAR Chapter 15 accident analysis.
3.
Scale change (from 0-540 gpm to 0-750 gpm) to 62J device, instrument and TPCW system is not in the Technical Specifications.
87-V1 E0107 This DCP pertains to the Control Building HVAC for the ESF switchgear.
The access door to the fan wheel section of 1 -1532-A7-001/-002 is stiffened via external angle iron addition. Also, the door latches are changed on all access doors for both AHUs.
l 1.
This DCP does not alter the existing design bases or increase the probability of equipment malfunction based on a review of Section 9.4.5, especially 9. 4. 5.1.1.1.
There is no effect on chapter 15 accident analysis.
2.
This DCP does not create the possibility of an accident 5
L II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT l
not described in FSAR Section 9.4.5 especially Section 9.4.5.4.1.
This DCP does not affect the integrity of the fan fan housing or casing.-
3.
This DCP will enhance the existing safety margin for the GK-02 system by upgrading the original access door hardware / stiffness design to ensure proper door / gasket seal exists.
87-V1E0145 Add Automated Access Control Terminals (ACAT) to l
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Rev 1 Control Building door 501 to facilitate roof top patrols.
1.
The probability of an accident is not increased by the addition of the ACAT's to Door 501.
2.
This change does not create the possibility of any malfunction not described in FSAR sections 15 and 6.2.
3.
Based on a review of Tech Spec sections 3/4.3 and 3/4.7 j
this change does not decrease the margin of safety.
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87-VIE 0150 Replace the existing Recycle Evaporator vent condenser vent checkvalve with one which has a lower differential pressure requirement. Also reroute the piping from the condenser to the Waste Gas system to remove water traps.
1.
The piping reroute and relocation of check valve will not affect the normal operation of the Boron Recycle or Waste Gas Systems as discussed in FSAR sections 9.3.4.2 and 11.3.2.3.
2.
This change does not increase the probability of occurrence or consequences of accidents analyzed in FSAR chapter 15. There is no affect on the FHA of the FSAR section 9.5, appendix 9A or 98.
3.
There is no bases for the Boron Recycle system discussed in the Technical Specifications. This is based'on review of Tech. Spec. 3/4.1 basis.
87-V1E0156 The ERF Computer CPU will interrogate and synchronize the sequence of events recorder on a routine basis. An l
error message will be generated if the SOE fails to l
respond properly to interrogation.
1.
The ERF Computer System is not assumed to function in any of the accident analyses in section 15.
2.
The ERF Computer System is only used for monitoring and does not control any plant equipment and as such, will not cause an accident or equipment / component l
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1988 ANNUAL REPORT - PART 2 1
10CFR50.59(b) REPORT i
malfunction.
3.
There are no Tech. Spec bases for the ERF Computer System, i
87-VlE0157 AMSAC cabinet is installed in the Control Room. AMSAC provides a method diverse and independent from the reactor protection system (RPS) to trip the turbine and initiate auxiliary feedwater flow in the event of anticipated transient without scram (ATWS) results in the loss of secondary heat sink.
1.
This change has no impact on the probability of occurrence or consequences of the malfunction of any equipment or component assumed to function to mitigate any postulated FSAR accidents.
This included review of FMEAs and associated FSAR sections 7 2, 7.3, 7.5, 10.4.9 & 15.
A credible fault occurring in the non-safety related AMSAC will not propagate through and degrade the RTS and/or ESFAS.
2.
This change does not create the possibility of any accident or equipment / component malfunction not described and j'
analyzed in the FSAR.
This included review of chapters 7 &
15.
1 3.
There is no change to the margin of safety defined by the Technical Specifications.
This included review of the basis for Tech. Spec. 3/4.3 & 3/4.7.6.
87-V1E0175 For each of the Diesel Generator Building girder cranes, i
change out the existing trolley motor with a new motor with integral brake.
No wiring changes are necessary.
1.
The design change does not impact the ability of Diesel Generator to perform its safety function.
There is no effect on any analysis or FSAR sections 9.1 or 15.
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2.
No physical changes other than a slight trolley motor configuration change are involved.
3.
The Diesel Generator Building girder cranes are not discussed in the bases for the Tech. Specs.
This included review of sections 3/4.8 & 3/4.7.
87V1 #0182 Route new 6" vent from Crud Tank to Waste Hold-Up Tank.
Route 2" line from 6" vent to Aux Bldg exhaust.
1.
This modification does not affect the probability or i
consequences of any malfunction of equipment assumed to I
function in FSAR chapter 15 analysis nor in FSAR sections 11.2 & 11.4.
The change is consistent with table 3.2.3-1 7
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT I
sht 18 criteria.
2.
Review of FSAR sections 11.2, 11.4, & 15 indicate that this modification affects no accidents or equipment nor changes any possibilities of such accidents or malfunctions, q
3.
This modification does not create the possibility j
of an accident since bases for Tech. Specs 3/4.11 &
3/4.12 have no applicable margin of safety affected by this design change.
87-VIE 0184 Separate existing ATSI (Advance Turbine Supervisory Instrumentation) Common Control Room Annunciator into three different annunciators.
- 1) Main Turbine Alarms 2)
Feedpump Turbine Alarms and 3) ATSI computer alarms.
This modification will allow for a more effective operator annunciator response.
j 1.
Modification will not increase the probability of an accident as described in Chapter 15 of FSAR. Equipment l
is non-safety related and does not affect any safety related equipment or system.
2.
Modification does not create the possibility of an accident other than evaluated in Chapter 15 of FSAR since equipment and system have no affect on safety related systems.
3.
Modification does not decrease safety margin. Margin of safety described in the bases of Tech Specs are not affected by this change.
87-V1E0187 Modify Registers for Auxiliary Building Air Balance 1
1.
This change replaces four ceiling diffusers with supply i
registers to provide adjustability for air balancing.
The ductwork affected is not safety related and the change has no effect on the accident analyses of FSAR Section 15.
2.
This change is on a non-safety related system with no potential to create a possible accident not included in the FSAR Section 15 analyses.
l 3.
This change has no effect on the safety margin defined by the Tech Spec bases in Sections 2,3 or 4.
87-V1E0191 Replace the pressure differential switch for Main Turbine tube Oil Reservoir Vapor Extractor Failure.
The General Electric recommended pressure differential switch is a Dietz ultra low differential air pressure switch.
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l 11 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 1.
Providing proper annunciation of the Main Turbine Vapor Extractor Failure has no effect on equipment used in FSAR Accident Analysis (FSAR Section 15).
2.
By providing proper annunciation of Main Turbine Vapor Extractor Failure, the probability of a failure, accidents, or malfunction not described in the FSAR is not affected.
J 3.
This modification does not decrease safety margins of the system. The basis of the system is not described in the Technical Specifications.
87-VIE 0195 The change was to correct wiring in the QPCP 7300 process cabinet for the Main Feedwater Pipe / Nozzle Differential Temperature annunciation and iMication and the Main Feedwater Pipe Temperature indication to allow the loop to function properly.
1.
The change corrects a wiring configuration to allow for proper operation of installed instrumentation.
The modification has no effect on equipment used in the FSAR
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Accident Analysis (Chapter 15) l 2.
By providing proper annunciation and indication of steam generator feedwater inlet temperature (pipe) and feedwater pipe / nozzle differential temperature, the probability of an accident or malfunction not described in FSAR Chapter 15 is not affected.
3.
This change does not decrease the safety margin as described in the bases for Technical Specification. The system / components are not addressed in VEGP Technical Specifications.
87-V1E0204 This change adds 16 new tubing supports and modifies 30 existing tubing supports to eliminate excessive vibration of Electrohydraulic Control (EHC) tubing around stop/ control valves and EHC pump.
1.
Adding new tubing supports and modifying existing tubing on EHC system does not increase probability of accident or change FSAR Chapter 15.
2.
By adding new tubing supports and modifying existing tubing no new postulated accident is created as a result of this change. This considers FSAR section 10.2.2 and Chapter 15, 3.
The margin of safety described in Technical Specihcation bases 3/4.7 is not affected by this change.
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1988 ANNUAL REPORT - PART 2 l
10CFR50.59(b) REPORT 87-VIE 0213 Provide opening in the Feed Pump Turbine Speed Control Cabinet to reduce occurrence of problems attributed to heat build-up.
1.
Increased ventilation of the SGFP Turb: a Speed Control cabinet has no effect on equipment used in FSAR Accident Analysis.
2.
By providing adequate ventilation to SGFP Speed Control
)
Cabinet, the probability of a failure, accidents or 1
malfunction not described in FSAR is not affected.
t 3.
This modification does not decrease safety margins.
87-VCE0220 The design change provides installation details for instrument tubing and mounting details for the installation of flow switch AFS-21036A.
1.
The design change provides installation and mounting details.
It does not increase the probability of occurrence of consequences of an accident as described in FSAR Sections 9.4 or 15.0.
2.
The design change adds a project class 62J instrument and its associated 424 tubing to the non-safety related TSC HVAC system. This design change will not create the possibility of an accident or equipment (component malfunction not described and analyzed in FSAR Section 9.4 or 15.0).
3.
There is no change in the basis of Technical Specifications 3/4.7.6 or 3/4.7.7. The design change does not decrease the margin of safety.
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87-VCE0221 Relocate filters A-1531-F7-001, 002, 003, 004, 005 & 006 from just inside the outside air inlet louver to just i
inside the OSA isolation dampers ATV-123168, 12316C, l
12316D, 12314B, 12314C, and 123140.
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1.
This design change does not affect any safety related or safe shutdown components nor does it affect any accident analysis described in Chapter. 15 of the FSAR.
2.
This DCP does not affect any components which are assumed to function during a design bases accident.
3.
his DCP does not affect any system described in the lechnical Specification and therefore does not decrease the margin of safety.
87-VCE0223 This DCP replaced the original spring isolators under 10 i
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT Control Room return fans, A-1531-B7-009 and l
A-1531-87-010, with a more rigid tube steel assembly.
1.
This DCP does not increase the probability of an accident described in the FSAR since the components involved are non-essential and not required for safe shutdown.
2.
This DCP does not create the possibility of an accident or malfunction not described in the FSAR since it involves subassemblies of non-essential equipment.
3.
This DCP does not decrease the margin of safety of the Tech. Spec. because the norma-1 CR HVAC system is not described in the Tech Spec.
87-VCE0230 This design change is to correct the wiring of the common BTRS chiller control circuit. The correction will provide indication at both the Unit 1 and Unit 2 MCB handswitches as to which unit handswitch has started the chiller.
1.
The probability of occurrence or consequences of an accident described in Chapter 15 of the FSAR is not increased by this design change. This design change improves the reliability of the non-Q BTRS common chiller.
2.
The common BTRS chiller is not described as functioning during any accident analyzed in Chapter 15 of the FSAR.
The design change does not increase the probability or consequences of the malfunction of the chiller but improves the reliability without changing the system operability as described in FSAR Section 9.3.4.
3.
The common BTRS chiller in non safety related and is not discussed in Technical Specifications. The change improves system reliability therefore the change does not decrease the margin of safety defined by the bases for the Technical Specification. This includes a review of Tech Spec 3/4.4 and 3/4.7.
87-V1E0240 Replace flow orifices to NSCW cross-tie line for compatibility with existing instrumentation.
1.
Modification to orifice plate docs not change or affect any component assumed to functior, for postulated accidents.
This included review"of FMEA Table 9.2.1-2 and chapter 15.
2.
Changing out the orifice plate will allow the flow switch to be set to required setpoint.
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II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT does not contribute to the possibility of equipment malfunction. The FMEA contained in FSAR Table 9.2.1-2 is not affected.
3.
It does not impact the margin of safety. The margin of safety described in the basis of Tech. Spec 3/4.7.4 is not affected by this change.
87-V1E0242 The purpose of this DCP is to change the overpressure interlock setpoint from 377 psig to 354 psig. This change would preclude challenges, due to instrument loop inaccuracies, to the RHR system relief valve because of the open permissive setpoint of 354 psig.-
1.
The overpressure open permissi s is not part of the RHR ECCS function. Therefore the propc ed change does not increase the probability or consequences of the malfunction of any equipment or compnnent assumed to function in accidents analyzed in the FSAR section 5.4.7.
2.
Proposed setpoint changes the value in section 5.4.7 such that the new setpoint will not create the possibility of an accident or equipment / component malfunction not described and analyzed in the FSAR.
3.
Proposed setpoint change given in FSAR section 5.4.7.1 and Technical Specification section 4.5.2.d.l.a will change the RHR suction pressure open permissive stepping from 377 psig to 354 psig. This change in setpoint does not change the reactor coolant system bases given in section 3/4.5 or decrease the margin of safety.
87-VlE0258 Add a counter balance weight on the Unit 1 hoist system of the Fuel Handling Machine to allow all 4 wheels of the hoist assembly to ride on the monorail.
1.
The change does not increase the probability or consequences of an accident descr1 bed in the FSAR.
The change does not affect the operation of the machine in any way. For this reason, there is no affect on the accident analysis delineated in section 15.7.4 - Fuel Handling Accident.
2.
The change does not create the possibility of an accident other than that previously evaluated. The change, which adds a counter weight to one of the hoists does not affect the operation of the hoist, nor does it create a new accident condition other than those outlined in FSAR section 15.7.4.
3.
The change does not reduce the margin of safety. The addition of a small amount of weight does r:ot reduce the 12
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1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT i
k margin of safety delineated in FSAR section 15.7.4 or i
discussed in the bases for section 2.0 and 3/4.9.6 and 3/4.9.7 of the Tech Specs.
87-VIE 0262 Add an additional containment narrow-range pressure transmitter and indication on HVAC control panel in the Main Control Room.
j 1.
The new instrument loop is not safety related and does not have any impact on the probability or consequences i
of an accident described in sections 15, 6.2.1.5.2 and Table 6.2.1-1.
j 2.
Device power is from non class 1E power supply, supports 1
are seismic category 1 and there is no process interface. Therefore, this change does not create the possibility of an accident not analyzed in the FSAR.
i 3.
This loop has no impact on safety and therefore does not impact the margin of safety of the Tech Spec Bases.
87-V1E0270 This design change involves four air operated valves for the Steam Generator Blowdown Spent Pesin Tank. These valves are used in the process of disposing of the resin from the tank and are normally controlled by handswitches. A three-way manual valve has been added in the air lines to each of the four valves to allow operation of the valve directly at the valve.
1.
System is non-safety related and no credit is taken for the system mitigating the affects of any postulated chapter 15 accident.
Based on review of FSAR sections 10.4, 11.4, and 11.5 and Chapter 15, this change has no affect on any component assumed to function in accidents.
2.
Revision to the valve control for the SGBD resin tank has no affect and creates no new accident not previously analyzed in Chapter 15 of the FSAR.
3.
This portion of the Steam Generator Blowdown system is non-safety related and is not addressed in the Tech.
Specs. Review of the basis for Tech. Spec. 3/4.7 shows that this change does not decrease the margin of safety.
87-V1E0271 Change the setpoint for the TPCW pump mini flow valves to eliminate pump vibration and pressure related noise.
1.
The proposed setpoint change (from 115 psig to 90 psig) on 1-PC-17208 & 1-PC-17224 for Turbine Plant Cooling Water (TPCW) pump mini flow valves should eliminate pump 13 i
11 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 4
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vibration and pressure related noise as experienced i
during startup. The change does not increase i
probability of accident described in FSAR section 15.0.
2.
The proposed set point change (from 115 to 90 psig) on j
TPCW mini flow valve is not discussed in FSAR section l
9.2.11 " Turbine Plant Cooling Water System".
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3.
The setpoint change TPCW mini flow valve is not discussed in the Technical Specification. The new l
setpoint will not create the possibility of an accident I
or decrease of the margin of safety.
j 87-VIE 0274 Nove the security card readers inside their lock doors I
Rev 1 to improve access and reduce nuisance door alarms.
1.
The probability of an accident is not increased by the j
relocation of these ACAT's. The integrity of the j
airlocks is maintained, and the personnel using the air j
locks must pause to use the ACAT, thus insuring the door i
is closed behind them, closing the air lock.
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2.
This change does not create the possibility of any malfunction not described in FSAR sections 15 and 6.2.
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i 3.
Based on a review of Tech. Spec sections 3/4.3 and 3/4.7 this change does not decrease the margin of safety.
1 87-V1E0277 This design change.will add a series resistor and
]
capacitor network to be installed across specific I
terminal blocks within the solid state protection system (SSPS) output cabinets, and the auxiliary relay panels. This network will be electrically paralleled with Potter-Brumfield MDR relay contacts which are within these panels. The addition of the network is to I
increase the current interrupting capability of the normally closed Potter-Brumfield MDR relay contacts.
1.
This modification improves the operation of the relay contacts which initiate the closure of the sample isolation valves.
It does not directly affect accidents described in FSAR Section 15, which concern coolant inventories or isolation. Therefore this change does not promote the malfunction of equipment assumed to operate in accidents or increase the probability of occurrence of an accident. This included review of FSAR sections 6.2 and 15.
2.
This design change improves the capabilities of the actuation relays of the sample isolation control circuitry to a level consistent with the original 1
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II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT i
design intent and specifications. The related control circuitry for these valves is designed in a fail-safe configuration and therefore this modification does not increase the probability of an accident or equipment malfunction. (Ref: FSAR Table 6.2.4-1) 3.
The Tech Spec does not define a margin of safety which is directly concerned with the control l
circuitry for the sample isolation valves.
This change f
does not adversely affect the ESFAS and associated systems nor does it decrease any margins of safety which are defined in the Tech Spec. This included review of the bases for Tech Specs 3/4.3 and 3/4.6.
87-V1E0278 This design change involves several modifications to the Steam Jet Air Ejector Radiation Monitoring skid.
These modifications include replacing the existing particulate filter holder with a SAIC filter holder with swagelok fittings and flex-line to reduce maintenance time, added a water source to the existing loop seal to maintain proper water level, added loop seal drains at i
piping low points to rid system of condensate formation as the discharge steam is cooled and compressed from the skid to the SJAE vent pipe, added flow totalizer for accurate radioactivity release assessment, modified the l
piping between the skid cooler and gas detector, replaced existing head trace with 215'F rated heat trace for the ',let piping to prevent collection of water in the part aulate filter holder and prevent particulate plateout in the sample inlet piping, added 120 F rated heat trace to midstream piping from the cooler outlet including the gas detector to maintain the gaseous state of the air and prevent condensation in the gas detector during the winter months.
1.
This change does not increase the probability of occurrence or consequences of an accident described in FSAR Section 15.0.
This change does not affect the ability of the equipment to indicate a postulated Steam Generator tube rupture in accordance with FSAR Section 15.6.3.
2.
This change does not affect the performance of any equipment assumed to function in the FSAR accident in the FSAR accident analysis. This included review of the FSAR chapters 11.0 and 15.0.
There is no impact on the monitor's ability of responding to a postulated Steam Generator tube rupture described in FSAR section 15.6.3.
3.
Based on review of Bases 3/4.3.3.10 " Radioactive Gaseous l
Effluent Monitoring Instrumentation" and 3/4.11.2 l
" Gaseous Effluents".
This change does not affect the 1
l 15 1
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1 II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT margin of safety. This modification will allow the equipment to function as designed.
87-V1E0279 Delete " Turbine Trip" input to steam line drain logic, allowing drain valve to function on dripleg level only.
)
1 1.
Modification will not increase the probabil'ity of an accicent as described in FSAR Section 15. Accident
)
analysis includes discussion of effects of turbine trip J
and effects of main steam piping rupture. The operation 1
of the main steam drain pot valves is not addressed in i
Section 15. Orain pot valves are not safety-related or required to function during an accident.
2.
Modification does not increase the possibility of an accident other than evaluated in Chapter 15 of FSAR since drain valves are not safety related or required to prevent the malfunction of any component assumed to function in an accident.
4 3.
Modification does not decrease safety margin. The margin j
of safety described in the bases of Tech Specs is not affected by this change since Technical Specification
]
Section b3/4.7.1 does not address drain pot valve in the discussion of the turbine cycle margin of safety.
87-V1E0283 Modify existing hangers associated with Heater Drain and Auxiliary Steam piping to eliminate excessive vibrations that were discovered during Thermal Growth Inspection.
1.
The modification to existing hangers that are located in Turbine Building has no change to FSAR Section 3.6, 3.9, 5.4.9 and 10.3.
2.
The modification to existing hangers that are located in Turbine Building does not affect the probability of any accident described in FSAR Chapter 15 or Section 3.6.
3.
The modification to existing hangers that are located in Turbine Building has no effect on margin of safety described in Technical Specification Bases 3/4.7.
87-V1E0288 The globe valves in the (H2) Aux gas system are changed to diaphragm valves due to leakage in the packing of the globe valve.
1.
The design change replaced existing globe valves with L
diaphragm valves to reduce H2 leakage.
The change does i
not alter system operation and does not increase the
]
1 16
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT probability of occurrence or consequences of an accident as described in FSAR Chapter 15.
2.
The design change is a direct replacement of system valves with a different type of valves.
No other components are affected. The change does not create the possibility of an accident or malfunction not previously described in FSAR Chapter 15.
3.
The change' does not affect any equipment addressed in the VEGP Technical Specifications. Therefore, there is no effect on the margin of safety as described by the Tech Spec basis.
87-V1E0291 Add tie-ins to existing hot water line, and route hot water to both decontamination showers in room R-110 of the Control Building.
1.
The probability or consequence of malfunction of any equipment is not changed as a result of this modification.
This system is not assumed to function in accidents analyzed in the FSAR. Reference FSAR sections 9.2.4.1.1 and chapter ?.5.
2.
This modification does not create the possibility of any accident or malfunction that is not described and analyzed in the FSAR. The plant is designed so that no plant equipment relies upon the potable w&ter system to perform its safety function. This is based on review of FSAR sections 9.2.5 and 15.
3.
There is no decrease in the margin of safety defined by the. Tech. Specs. as a result of this modification. There is no safety design basis for this system.
(FSAR 9.2.4.1.1)
This is based on review of the bases for Tech. Spec. 3/4.0.
87-VIE 0292 Provide a grounding strap from the pre-amp holding screw to the check source actuator assembly holding screw to provide a ground path for induced noise interference on liquid detector tubes.
1.
The grounding wire only provides a path for excessive signal noise to be eliminated and does not increase the probability of occurrence of the accidents described in Section 15 or the FSAR.
2.
The grounding wire provides a path for draining excessive signal noise and does not create a malfunction of these monitors.
These monitors are not safety-related and will not create the possibility of an accident not analyzed in the FSAR sections 11.5 and 15.0.
17
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1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 3.
This change has no impact on the margin of safety as defined by the Tech. Spec. bases for section 3/4.11 and 3/4.3.
87-V1E0299 Revise the setpoints of PDIS 140 and PDIS 141 (seal injection filter Delta P alarm) to annunciate high Delta P on the Seal Injection Filter.
l 1.
This change does not increase the probability of an accident because these instruments are used only to determine when to backflush the Seal Injection Filters.
2.
No new accidents are created by this change.
This change only accounts for the additional delta-P caused by the filters' inlet and outlet valves.
3.
There are no Technical Specification bases associated with the backflushable filter system.
87-VCE0302 Add a resistor to the Meteorology Tower Shelter temperature alarm to eliminate nuisance alarms in the Control Room from this device.
1.
This change does not increase the probability of an accident because the Met Tower Shelter Temperature is used to remotely monitor the Met Tower for HVAC failure or fire which would damage meteorological instrumentation.
2.
No new accidents are created by this change. This change only prevents spurious alarms.
3.
There are no Technical Specification bases associated with this alarm.
87-Y1E0309 Change rotor 4 on operator of Auxiliary Feedwater Valve HV-5106 from 2 in line and 2 opposing contacts to 3 in line and 1 opposing contact.
This configuration will allow the position indication to be set at a point more indicative of the actual valve position.
1.
There is no change to the probability of occurrence or malfunction consequences assumed in section 15.2, 9.5, appendix 9A, or appendix 9B.
1 2.
This change does not create a scenario which is not bounded by section 15.2, 9.5, appendix 9A or appendix 98.
l 3.
The margin of safety discussed in section 3/4.7.1.2 is not affected by this change.
87-V1E0311 Install the ZSC stem mounted limit switches and 18
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II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT f
associated cables for main FW isolation bypass valves.
This modification provides an electrical " seal-in" circuit for manual valve opening operation.
1.
The change increases the reliability of the original l
l design circuit operation which does not increase the probability of any accidents described in the FSAR section 15.0.
2.
The change increases the reliability of the original design circuit operation and does not affect the original system operation. Therefore, the change does not l
create the possibility of an accident or equipment malfunction not described and analyzed in the FSAR.
3.
The change increases the reliability of the original design circuit and does not affect the original system operation requirements. Therefore, the change does not decrease the safety margin as discussed in section 3/4.7.1.2 of Tech. Spec.
87-VCE0315 Modify the supply register inside the TSC Battery Room to increase air movement at the higher elevations of the room.
1.
This change reduces the possibility of H2 pocketing-in the Non-1E TSC Battery Room. This does not increase the probability of occurrence or consequences of an accident described in the FSAR.
2.
This change is to a Non-Safety ductwork and will not affect the performance of the HVAC system. The change does not affect any equipment / component malfunction not described and analyzed in the FSAR.
3.
The design change does not decrease the margin of safety defined by the bases of the Technical Specifications in FSAR Section 3/4.7.6.
87-V1E0316 Delete from the service air compressors, noise shielding cabinet walls, roof, support members, and entire vent fan assembly to improve air compressor cooling, system operation, and maintenance awareness of compressor status.
1.
The removal of the noise shielding cabinet and vent enhances system operation.
This change does not increase the probability of occurrence or consequences of an accident described in FSAR Chapter 15.
2.
The removal of equipment by this design change does not increase the probability of occurrence or consequences 19
l-II I
1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 1
l-of a malfunctin of any equipment or component assumed to function in accidents analyzed in FSAR Chapter 15. The change does not introduce any new malfunction or accident not previously idantified in FSAR Chapter 15.
3.
The compressed air system is not discussed in Section 2.0 or 3/4.7 of the Technical Specification; therefore there is no decrease in any safety margin as defined in the basis of VEGP Tech Specs.
87-VIE 0320 A stop check valve was added on the backflushing nitrogen header on each of the seal injection backflushable filters. The purpose of this modification is to prevent any leakage from a seal injection filter from damaging the nitrogen header whici, is rated for a much lower pressure than seal injection.
1.
This change does not increase the probability of an accident because the backflush nitrogen header is not associated with an accident nor is it used to mitigate the consequences of any accident.
2.
No new accidents are created by this change.
Failure of these valves will not create the possibility of an accident.
3.
There are no Technical Specification bases associated with the backflushable filters or the backflushing nitrogen line.
87-V1E0322 A drain line was added from the crud tank pump suction to a floor drain hub. The floor drain is routed to the waste hold-up tank. The purpose of this modification is to provide the crud tank with a manual drain path to the liquid radwaste system.
1.
This change does not increase the probability of an 3
accident because the crud tank and pump are not I
associated with any accident nor are they used to mitigate the consequences of any accident.
2.
No new accidents are created by this change.
3.
There are no Technical Specification bases associated with the crud tank or its pumps.
87-VIE 0323 Turbine trip signal input to stop valve before seat drain valves is rewired to allow valves initially to open upon turbine trip and then return to handswitch control independent of turbine status. Design change is implemented by adding a time delay energize relay to defeat the turbine trip signal after valves are fully l
20
II i
1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT i
i open.
1.
FSAR Section 15 accident analysis includes discussion of effects of turbine trip and effects of main steai J
piping rupture. The operation of the before seat drain valves is not addressed in section 15. Drain valves are not safety related nor required to function during an accident.
2.
Drain valves are not safety related nor required to prevent the malfunction of any other component assumed to function in an accident. This included review of FSAR chapter 15, 3.
Technical Specification section B3/4.7.1 does not address stop valve before seat drain valves in the discussion of the turbine cycle margin of safety.
There is no change in any Tech. Spec. margin of safety.
87-V1E0325 The cooling water to the reciprocating compressors is to be re, outed to flow in parallel to the cylinders and intercoolers. As a result of re-routing to parallel flow, total flow increases from 36 to 60 gpm.
1.
The change implemented by this des;gn change provided for increased cooling capacity for the air compressors for more reliable operation. The compressors operate as before and therefore the probability of occurrence or consequences of an accident described in FSAR Chapter 15 is not increased.
2.
The compressed air system operates as per its original design intent. The change does not increase the probability of occurrence or consequences of a malfunction or accident described in FSAR Chapter 15 or does it introduce any new malfunction or accident not previously identified in FSAR Chapter 15.
3.
The compressed air system is not discussed in Section 2.0 or 3/4.7 of the Technical Specification; therefore there is no decrease in any safety margin as defined in the basis of Tech Specs.
87-V1N0342 Add a check valve in the pneumatic line near diesel generator day tank fuel oil level indicator.
1.
The proposed change does not increase the probability of occurrence or consequences of an accident described in FSAR sections 9.5.4 and 15.0.
]
2.
The check valves 1-2403-X4-419 and 1-2403-X4-420 are J
non-safety related valves serving a non-safety related 21 l
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b)F'EPORT function in project class 424 pneumatic tubing. This change will not create the possibility of an accident or equipment / component malfunction not described and analyzed in the FSAR sections 15.0 and 9.5.4.
3.
The proposed change does not decrease the margin of safety defined by the bases of the Technical Specification 3/4.8.1.
87-VIN 0343 Add flow element, associated tubing and valves, and flow indicator in the Boric Acid Transfer Pump Discharge Line to the Boric Acid Tank.
1.
The new flow instrument is to facilitate inservice testing and does not impact the probability or severity of accidents described in 9.3.4 and section 15.
2.
Accidents not previously analyzed are unaffected by additional instrumentation for testing purposes. A review of this change indicates no impact on equipment or components.
3.
The proposed change does not affect the margin of safety as defined by the bases of Tech Specs 3/4.1.2.5 and 3/4.1.2.6 or impact surveillance requirements and thercSy impact the margin of safety.
87-VIE 0359 Modify cowling on north and south sides of generator to allow cooler air to flow into exciter cubicle air ve,it, and to allow easy access to flux probe test flange.
1.
Changes to the generator lagging will not increase the probability-of occurrence or consequences of an accident.
This included review of chapter 15 - Accident Analysis.
2.
Changes to the generator / turbine lagging do not create the possibility of an accident or equipment / component malfunction not described and analyzed in the FSAR. This included review of FSAR chapter 15.
)
3.
The turbine / generator 1r]ging is not discussed in the Tech. Spec. This included review of Tech. Spec. 3/4.8.
87-V1N0369 Replace the mechanical vacuum pump vacuum switches IPS-4175 and IPS-4178.
Revise setpoint to 25" HG vacuum to start the vacuum pump and adjust the adjustable deadband to stop the vacuum pump at 25.7" HG vacuum to accommodate turbine requirements.
1.
Per FSAR section 10.4.2 the main condenser evacuation syste.m serves no safety function and has no safety design bases.
Therefore, the proposed change does not 22
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) rep 0RT-l increase the probability of occurrence or consequence of an accident described in the FSAR. This includes a review of chapter 15.
2.
Repiccing the wide deadband vacuum switch with a narrow deadband vacuum switch will minimize the possibility of mechanical vacuum pump failure due to excessive run time.
There is no possibility of a new component malfunction not considered already in FSAR sections 10.4 or 15.
3.
No impact on section B 3/4.7.1 or any other Tech. Spec.
margin of safety.
87-V1E0395 Add an alarm to door B06 at the Containment Escape Hatch to properly control access to the hatch.
1.
The probability of an accident is not increased by the addition of alarm capability to the door to the hatch cubicle. The operation of the the door is not affected.
2.
This change does not create the possibility of any malfunction not described in FSAR sections 15 and 6.2.
3.
Based on a review of Tech. Spec. sections 3/4.3 and 3/4.7 this change does not decrease the margin of safety.
87-VIN 0417-These DCP's reduce the number of snubbers in the Main 87-VIN 0423 Steam and Nitrogen Gas systems. The design change is limited to modifications of pipe supports only and does not change the pipe routing, equipment, or components.
Piping system reanalysis with the intent to optimize the design and reduce the quantity of snubbers, has resulted in the elimination of snubbers from these systems while maintaining stresses within code parameters.
1.
This change does not affect system function or operation
)
and therefore does not affect the accident analysis probability or consequences of a Main Steam or Nitrogen Gas system accident as described in sections 9 and 15 of the FSAR.
2.
This change does not affect any system, equipment or component's function or operation and based on a review of sections 15.1 and 15.2 would not create the possibility of an accident or equipment / component malfunction in the Main Steam system not previously described and analyzed in the FSAR. The Nitrogen Gas system performs no safety related function.
3.
This change does not affect the Main Steam System / Equipment function or operation and therefore does not affect the safety margin defined by Tech. Spec 23 1
H 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 3/4.7. The Nitrogen Gas system is not addressed by Tech. Specs. There is no change in the bases of Tech Spec 3/4.8. The list of individual snubbers referenced in the bases of the Tech. Spec. 3/4.7.8 will change, but the margin of safety is unaffected.
87-VIN 0424 -
These DCP's reduce the number of snubbers in the 87-VIN 0425 Containment Spray system. The design change is limited to modifications of pipe supports only and does not change the pipe routing, equipment or components.
Piping system reanalysis, with the intent to optimize the design and reduce the quantity of snubbers,-has resulted in the elimination of snubbers from this system while maintaining stresses within Code parameters.
1.
This change does not affect system function or operation and therefore does not affect the accident analysis, probability or consequences of an accident described in Section 15.1.5 and 15.6.5 of the FSAR.
2.
This change does not affect any system, equipment or component's function or operation and based on a review of section 6.2.2.2 and 15.6.5 would not create the possibility of an accident or equipment / component malfunction in the Containment Spray system not previously described and analyzed in the FSAR.
3.
This change does not affect the Containment Spray system / equipment function or operation and therefore does not affect the safety margin defined by Tech Spec 3/4.6.2. There is no change in the bases of Tech. Spec 3/4.7.8. The list of individual snubbers referenced in the bases of the Tech Spec 3/4.7.8 will change, but the margin of safety is unaffected.
87-VIN 0426 These DCP's reduce the number of snubbers in the 87-V1N0427 Auxiliary Feedwater System. The design change is 87-V1N0429 limited to modifications of pipe supports only and does not change the pipe routing, equipment or components.
Piping system reanlysis, with the intent to optimize design and reduce the quantity of snubbers, has resulted in the elimination of snubbers from this system while maintaining stresses within Code parameters.
1.
This change does not affect system function or operation and therefore does not affect the accident analysis, probability or consequences of an accident described in i
section 15.1 and 15.2 of the FSAR.
2.
This change does not affect any system, equipment or components function or operation and based on a review of sections 15.1 and 15.2 would not create the 24 I
l 11 1988 ANNUAL REPORT - PART 2 10CFR50059(b) REPORT possibility of an accident or equipment / component malfunction in the Aux Feedwater system not previously described and analyzed in the FSAR.
?
This change does not affect the Aux. Feedwater system / equipment function or operation and therefore does not affect the safety margin defined by Tech Spec 3/4.7.1.2.
There is no change in the bases of Tech Spec, 3/4.7.8. The list of individual snubbers referenced in the bases of the Tech Spec 3/4.7.8 will change, but the margin of safety in unaffected.
87-VIN 0434 Provide permanent plant pressure gauges on CCW pumo suction. ESF chilled water pumps suction, charging pumps suction, NSCW Xfer pump discharge, RHR pump suction and discharge to aid ASME Section XI pump testing per Tech Spec Section 4.0.5.
1.
The proposed change is to comply with FSAR section S.6 (in service test program). Addition / Replacement of these pressure gauges has no affect on system performance or post accident requirements. Thi:,
includes a review of FMCA's and FSAR section 6.3, 9.2, 9.3 and 15.
2.
Instrument reading complying with article IWP-4000 of Section XI of ASME code per FSAR section 6.6 will provide better accuracy for inservice testing. These pressure gauges have no affect on accident possibilities. They provide enhanced indication only.
3.
The margin of safety is not decreased.
This change simply provides indication to meet requirements for in service testing and has no impact on the margin of safety as defined by the basis of Tech. Specs.
87-VIN 0443 Replace the Centronics 704 printers with TI-820 printers.
Replace the dataproducts 2230 lineprinter with a Centronics series "E" lineprinter.
1.
The probability of an accident is not increased by upgrading the printers for the Plant Computer.
2.
A printer failure will not affect the operability of the Plant Computer. Therefore this DCP will not create any new accident or component malfunction possibilities, refer to FSAR Section 15.0.
3.
The DCP does not affect the operability of the computer and thus does not decrease the margin of safety.
87-VIN 0447 Delete Main Turbine Trip on high exhaust hood 1
25
XI 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT i
temperature and low stator cooling water pressure, and convert the low Stator Cooling inlet flow turbine trip to a two-out-of-three logic.
1.
This DCP will not increase the probability or consequences of accidents described in the FSAR sections 15.2 and 3.5.
2.
This DCP does not create any new accident or equipment / component malfunction possibilities, FSAR review covered sections 3.5.1.3, 10.2 and 15.
3.
This DCP does not affect T/S margin of safety, specifically those described in sections 3/4.3.4 and 3/4.7.1.
87-V1N0463 Integration of the Unit 2 security cameras into the Unit I camera system.
1.
The probability of an accident is not increased by the integration of the Unit 2 Cameras into the Unit 1 Camera system. No change was made to the Unit 1 permanent camera system.
2.
This change does not create the possibility of any malfunction not described in FSAR sections 15 and 6.2.
3.
Based on a review of Tech Spec. sections 3/4.3 and 3/4.7 this change does not decrease the margin of safety.
87-V1N0470 A resistor-capacitor and diode network to MSIV logic.
This will increase the current interrupting capability of the Potter-Brumfield relays which are used in this circuit.
1.
Probability of an accident occurring is not increased.
Modification will reduce the chances of an inadvertent MSIV closure due to relay failure. Accident analysis in FSAR addresses the inadvertent closure of MSIVs.
2.
There is no possibility of an accident not evaluated in Chapter 15 of the FSAP. since the only affect is inadvertent closure of MSIV's which has already been evaluated.
]
i l
3.
Modification does not affect the bases of any Tech Spec.
other than as already noted.
)
87-V1N0472 Stake condenser tubes in the Main Condensers to help i
support the titanium tubes from vibration fatigue due to
{
high steam velocities.
26 1
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 1.
Staking the Main Condenser tubes will not increase the probability of occurrence or conseocences of an accident. This includes a review of FSAR Chapter 10.4 and 15.
2.
Adding stakes to reduce vibration fatigue of the Main Condenser tubes will not increase the probability of occurrence or consequences of an accident not described in the FSAR. The Main Condenser is not required for safe shutdown.
3.
No impact on Tech. Spec. 3/4.7 or any other Tech. Spec.
margin of safety since Condenser does not affect safe shutdown.
88-V1N0001 Provide a lead shim for the detector printed board assembly to reduce beta activity at the GM tube while the source is retracted for main steam line rad-monitors.
1.
The lead shield is used only to attenuate the radiation field existing at the detector tube; it has no impact on the electrical / functional design of the affected PERMS channels.
Consequently, the instrument channels possess functional equivalence relative to the original design.
2.
Futhermore, the only design feature potentially impacted
'1 by the addition of the lead shield will be the seismic qualification of the detector printed circuit board assembly. This additional weight has a negligible impact on the structural integrity and dynamic response of the PC board. Consequently, the seismic qualification is not adversely impacted by addition of the lead shield.
3.
Since neither the functional design, nor the qualification of the PERMS System are adversely impacted as a result of this modification, the modification does j
not pose a safety concern.
88-VIN 0004 Modify the statistical test limit table used by the and present algorithm to correct the excessive false alarm 88-VIN 0005 rate and to increase the statistical confidence level to 95% for rad monitors.
1.
There is no change to the consequences or probability of any accident described in the FSAR.
No credit is taken for these monitors in the accident analysis of chapter 15 including 15.7.
2.
This change does not affect the performance of the Radiation Monitors and does not create the possibility j
27
Il 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT of any malfunction / accident not already described and analyzed in the FSAR Chapter 15.
3.
There is no change to the margin of safety defined by the basis of the Tech. Specs. This included review of Tech. Specs. 3/4.3.2, 3/4.3.3 and 3/4.11.
88-V1N0006 Upgrade the control program for the micro-processor based SIGMA Refueling Machine to correct a positioning problem for the bridge and trolley and to incorporate the LOCUS instantaneous load limiting features.
1.
The change doe's not increase the probability or consequences of an accident described in the FSAR.
PROM replacement does not affect the accident analysis in a way to increase the probability of occurrence or consequences of an accident described in FSAR Sections 15.4.7 and 15.7.4.
The design change can, however, reduce the possibility of a misplaced fuel assembly as described in FSAR section 15.4.7.
2.
The change does not increase the possibility of an accident other than that previously evaluated. The changes to the program that controls the machine reduce the probability of damaging fuel or misplacement of a fuel assembly. As no other changes were made, no additional accidents were created.
3.
The change does not reduce the margin of safety. The control program modification does not affect the margin of safety involved in FSAR sections 15.4.7 and 15.7.4 or Tech Spec bases section 3/4.9.6.
88-V1N0007 Modify spent fuel rack BPRA inserts which were originally purchased for non-poison 13" center-to-center racks, to fit new high density 10.6" center-to-center racks.
1.
This modification will not increase the probability of an accident since there is no effect on the criticality results.
The criticality analysis of the spent fuel racks does not include any reactivity benefits from the insertion of BPRA's.
2.
Storage of the BPRA inserts with BPRA assemblies is not as limiting as the storage of standard fuel assemblies.
Thus, the thermal-hydraulic and seismic / structural analysis of the racks is not affected and the modification does not decrease the margin of safety.
3.
The modification does not create the possibility of an accident since the mechanical design characteristics of the modified rack inserts is actually better than the 28
i l'
ZI l
1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT original. This is due to the fact that the insert will be supported over a shorter span than on the original l
rack.
It increases the load carrying capacity of the insert.
88-V1N0009 Provide storage locations for the RCCA Change Tool and the Thimble Plug Change Tool. Provide an alternate storage location for the Spent Fuel Handling Tool.
1.
The change does not increase the probability or consequences of an accident described in the FSAR.
The accident postulated in FSAR section 9.1.4 paragraph G is not affected by the addition of handling tool support brackets to the spent fuel pool. The FSAR Chapter 15 safety analysis is not impacted, including chapter 15.7.4 - Fuel Handling Accident.
2.
The change does not create the possibility of an accident other than that previously evaluated. The accident analysis, as delineated in FSAR section 15.7.4, involved the drop of a fuel assembly on top of the fuel racks with the result bein, image to both the dropped assembly and one in the rack Since only the tooling is at risk of falling and the weight is much less than a fuel assembly, the accident evaluation envelopes this minor damage resulting from a support failure.
3.
The change does not reduce the margin of safety. The tool supports are installed to the same standards as the other supports in the spent fuel pit. The margin of safety for a fuel handling accident referenced in FSAR paragraph 15.7.4 is not reduced. The bases for the Tech. Specs, do not reference tool storage or case.
88-VIN 0014 Provide design for installation of cable tie down bars for cable support in Class 1E vertical trays.
1.
There is no change to the probability or consequence of l
any accident described in Chapter 15 of FSAR. The use of cable tie down bar will insure the electrical cable and associated termination are not subjected to excessive movement or stress during a seismic event.
Therefore proposed design effectively reduces the probability of consequence from an accident.
2.
There is no decrease in safety from this modification since the change ensures cables and associated terminations remain intact and prevent possible I
malfunction of equipment or component assumed to function during a seismic event.
29 1
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT l
l 3.
The is no new unanalyzed condition since the design l
eliminates tiie possibility of equipment malfunction by restraining cables during a seismic event.
1 88-V1N0017 RHR valves 8716A and 8716B are modified by adding a small j
vent hole to the RHR pump disk side of both gate i
valves. This will allow liquid to flow from the bonnet
)
cavity.
The modification will prevent entrapment of high pressure liquid in the bonnet that has prevented the valve from opening.
1.
There is no change to the probability of occurrence or consequences of any accident postulated in the FSAR.
This included review of FSAR FMEA's in Tables 5.4.7-4 and 6.3.2-5 as well as Chapter 15.
2.
No new component malfunctions are created by this modification. Addition of the vent hole makes the valve unidirectional in sealing against high pressure since the drilled side of the disc is towards the RHR pump.
The addition of this hole and unidirectional sealing does not invalidate the existing FMEA's (Tables 5.4.7-4 and 6.3.2-5) since the worst component malfunction, valve failure open or closed, is already considered.
3.
There is no change to the Tech. Spec. margin of safety.
This included review of the bases of Tech. Specs.
3/4.4.1, 3/4.4.6, 3/4.5 and 3/4.9.
88-VIN 0018 In order to avoid leak chases located on the floor of of the spent fuel pool, relocate the south spent fuel rack by increasing the spacing between the north and south racks to seven inches.
1.
The change does not increase the probability or consequences of an accident described in the FSAR. The accidents postulated in FSAR sections 9.1.2.2. paragraph G are not affected by the relocation of the spent fura rack.
There are no changes or affect on the accidens analysis of chapter 15, including section 15.7.4 - Fuel Handling Accident.
2.
The change does not create the possibility of an accident other than that previously evalua+ed.
Since no spent fuel was stored prior to the movement of the rack, the relocation of the rack (which increases the gap between the racks by three (3) inches) did not create the possibility of any new accident.
In addition, the new location of the rack does not create the possibility of an unevaluated accident, since this gap has no effect on fuel handling.
30 I
t
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 3.
The change does not reduce the margin of safety. The movement of the south rack and its increased gap have no effect on the margin of safety for a fuel handling accident delineated in FSAR Chapter 15.7.4.
Section 3/4.9 of the tech specs (concerning refueling related items) and all other sections including the bases do not address fuel rack location or spacing.
88-VCE0021 This change provides the design for those portions of the bullet resistant Control Room partition which will remain in place permanently.
1.
The proposed addition of the architectural finish materials to the Control Room partition will not have any impact on the probability or consequences'of an accident described in FSAR Chapter 6 or Chapter 15.
2.
The proposed addition of architectural finish materials to the Control Room partition does not create the possibility of an accident or equipment / component I
malfunction not described in FSAR Chapter 6 or 15.
3.
The proposed change does not affect the margin of safety defined in the Technical Specifications. This included a review of the bases of Technical Specifications 3/4.4, 3/4.7, and 3/4.11.
88-V1N0022 Vent path was provided for upper bearing oil level sight glass on condensate pump motors in order to provide accurate lube oil level indication.
1.
Accurate lube oil indication on condensate pump motor upper bearing has no effect on equipment used in FSAR AccidentAnalysis(FSARSection15).
2.
By providing accurate lube oil indication on condensate pump motor upper bearing, the probability of a failure, accidents, or malfunctions not described in the FSAR is not affected.
3.
This modification does not decrease safety margins of the system.
The basis of ac system is not described in the Technical Specifications.
88-VCN0024 Add a turnbuckle on the tension idler arm on the door operator for the auxiliary building crane bay missile door.
1.
The change does not increase the probability or consequences of an accident described in the FSAR.
Addition of the turnbuckle increases the reliability of 31
I1 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT door operation.
It does not affect the function of the door to prevent damage from tornado generated missiles (reference FSAR paragraph 3.5.1.4).
2.
The change does not create the possibility of an accident other than that previously evaluated. The addition of the turnbuckle has no effect on the function of the door. The addition of the turnbuckle, does not create any condition which may lead to an accident of any type.
3.
The change does not reduce the margin of safety. The addition of the turnbuckle increases operational reliability only. The door has no operating safety requirement and is not referenced in the Tech Specs or their bases.
88-V1N0030 The purpose of this DCP is to replace the existing cooling tower nozzle extensior, with a new design nozzle extension to improve performance of cooling tower.
Reasearch-Cottrell designed and remanufactured the nozzle extension with increased thickness and composition.
1.
This modification will not effect the design operation of circulating water system. The circulating water cooling tower is not availabie when determining and evaluating the limiting cases described in FSAR Chapter 15.
2.
This change does not create the possibility of an accident or equipment / component malfunction not described in the FSAR Chapter 15.
1 3.
This modification has no effect on margin of safety based on review of FSAR Chapter 15. There are no technical specification requirements for the circulating water cooling tower.
88-VCN0031 This change provided the capability to block both trains of the Fuel Handling Building isolation originating from the low - differential pressure (FHB to Atmospheric) sensors. The change was necessary to allow for opening of the railroad corridor door or other situations when 1
the negative boundary is breached and to allow shifting j
from Post-Accident operation back to Normal HVAC.
1.
The design change did not increase the probability of occurance of an accident since it did not affect any equipment directly associated with fuel handling. The analyzed consequences of an accident are not affected because no credit was taken for the operation of this 32
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT system in the accident analysis.
However, the " defense in depth" is maintained because the systems high radiation auto start and manual start signals remain unaltered.
2.
The change does not create the possibility of an accident or equipment malfunction not described and analyzed in FSAR, as noted above the radiation circuitry will start the post-accident on unacceptable levels of radiation in the Fuel Area.
The use of the dual train block is administratively controlled by Operations such that the low pressure actuation is operable during times when a Fuel Handling Accident could occur.
3.
The margin of safety defined in Technical Specifications is not reduced as discussed above.
No credit is taken for FHB emergency ventilation in offsite dose calculations, but the " defense in depth" is maintained by the radiation actuation circuitry and administrative controls on the use of the pressure channels block switch.
88-VIN 0034 Move level instrumentation for feedwater heaters 6A &
6B to platform area. Seal weld all connections to prevent steam leaks.
1.
Modification will not increase the probability of an accident as described in Chapter 15 of FSAR since equipment is non safety related.
2.
Modification does not increase the possibility of an accident other than evaluated in Chapter 15 of FSAR since equipment does not affect any other safety related systems.
3.
Modification does not decrease safety margin. Margin of safety described in the bases of Tech Specs is not affected by this change.
88-V1N0036 Replace existing range module card of Rod Insertion Limit Recorder 1-ZR-412 to: 1) Allow control bank D indication to operate in a negative region without recorder malfunction 2) Allow proper annunciation with low power conditions.
This change also replaces indicator scale and paper to give negative region indication.
1.
This change does not affect the probability of occurrence of any accident described in FSAR Section 4 and 15. This recorder is informational and not utilized l
for safe shutdown.
The change does not affect the l
operation and actually enhances the usability of ZR412.
I i
l 1
33 I
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II-1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 2.
Modification to this recorder does not create the possibility of any malfunction not already analyzed, Review of FSAR sections 4 and 15 and this recorder change, which is an enhancement, support this.
3.
Tech Spec. do not address this equipment including a review of 3.1.3.6, 3.1.3.3, 3.1.3.2, and 3.1.3.1 bases.
The margin of safety will not be reduced by increasing the voltage the recorder is capable of accepting.
88-V1N0037 This provides re-configuration of sensing lines for 1-LT-461, 462, 1PT457, and 458 to allow enhanced condensate pot refill of the reference leg during power operations and seal-welding all threaded connections on the sensing lines.
1.
There is no impact on accident analysis in FSAR sections 7.3.1 and 15. The ability of these transmitters to respond is enhanced and their intended purpose is unchanged. Therefore accident probability is not increased by this change.
I 2.
The modifications are evaluated for equipment qualification. New piping and tubing meet all original requirements of section 5.2.3.
System performance remains unaltered and will still perform its intended purpose. This change does not create a possibility of an accident' or equipment malfunction not described in the FSAR.
3.
Transmitter accuracy and performance as well as installation integrity remain intact.
This fact and a review of Tech. Spec. Bases 3/4.3, 3/4.4 and 3/4.9 yield that there is no reduction in safety margin due to this modification.
I 88-V1N0041 Valve TV-386 is used for Temperature Control in the BTRS. The present control loop produces reverse action.
Valve should be direct acting in order to provide increasing chill water flow on an increasing process temperature. Valve TV-386 will operate correctly during boron storage operation.
1.
Design change does not increase probability of an accident described in FSAR Section 15.4.6.1, 15.4.6.2, and 15.5.2.
Control loop for valve TV-386 is not safety related and is not required for the safe shutdown of the plant.
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2.
Design change does not create possibility of an accident i
or component malfunction.
Control loop for valve TV-386 l
is project class 61J non safety related and is isolated 34 l
TI 1988 ANNUAL REPORT - PART 2 10CFR50.59.(b) REPORT from any protection loops. Valve TV-386 is not required for the safe shutdown of the plant.
3.
The bases in Section 3/4.1.1 boration control ar d 3/4.1.2 boration systems describe margin of safety for the boration systems. BTRS temperature valve TV-386 is not addressed in these sections.
88-VCN0043 Removal of the Turbine Building Interim barrier fence to facilitate the extraction of the Unit 1 generator rotor.
1.
The probability of an accident is not increased by the-romoval of this fence since security properly compensated for the lack of a PA/VA fence.
2.
This change does not create the possibility of any malfunction not described in FSAR sections 15 and 6.2.
3.
Based on a review of Tech. Spec sections 3/4.3 and 3/4.7 this change does not decrease the margin of safety.
88-V1N0044 Add PABX telephones, page/ party handset stations, (5) flashing red lights, with the speakers in the valve areas of the control and auxiliary buildings.
1.
By providing a visual alarm in conjunction with the siren tone generator, this will increase the probability that plant personnel will be made aware of an emergency which should help decrease personnel accidents.
Therefore, this change does not increase the probability of occurrence or consequence of an accident described in Section 15 of the FSAR.
2.
This change involves no safety related equipment and is designed to interface with the existing tone generator and page units. Therefore, no accidents or equipment / component malfunction will result from this design that is not described in the FSAR.
3.
Adding phones and visual alarms to the North and South valve rooms does not affect the margin of safety defined by Section 83/4.9.5. This section addresses having proper communication during refueling.
88-V1N0045 Replace and relocate the stator cooling water temperature controller 1-TIC-6800.
1.
Per FSAR Section 10.2.12, the Turbine Generator serves no safety function and has no safety design basis.
Therefore, the DCP does not increase the probability of 35
t
.ig 1988 ANNUAL REPORT - PART 2
_10CFR50.59(b) REPORT occurrence or consequences of an accident described in l
the FSAR. This includes a review of Chapter 15.
2.
Relocating temperature controller, 1-TIC-6800, will minimize the possibility of instrument failure due to excessive vibration. There is no new component malfunction created that has not already been examined 1
in FSAR Chapter 15.
3.
Replacing and relocating 1-TIC-6800 has no impact on Tech. Spec. margin of safety. Tech. Spec. section 3/4.7.1 was reviewed.
88-VCN0048 Modify annunciation from demineralized plant to Main Control Room to provide improved clarity. Demin. Plant Trouble alarm was replaced by Demin. Storage Tank Hi/Lo Level and Demin. Header lo Pressure alarms.
1.
There is no change to the probability of occurrence or-consequences of any accident described in the FSAR.
This conclusion is based on review of Section 15 and 9.2.3.
2.
This change does not create the possibility of any accident or malfunction not already described in the FSAR. This is based on review of FSAR chapter 15 and 9.2.3.
This change will not affect local panel
{
annunciation and is consistent with the human factors j
considerations of Chapter 15.
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3.
There is no change to the margin of safety as defined in the bases of Tech Spec section 3/4.7.
88-VIN 0049 Add travel limit slots for thermostatically controlled valve to reduce the maximum flow to 786 GPM through Jacket Water Heat Exchanger of Emergency Diesel Generators. The Heat Exchanger was derated by vendor after conducting test in the factory.
1.
The proposed change will limit the flow through Heat Exchanger from 1600 gpm to 786 gpm. The Field Test proved 786 gpm flow is more than adequate to support cooling requirements of the Diesel Generator, which will continue to perform its function during an accident condition.
This change is within the boundary accident analysis in Chapter 15 of FSAR.
2.
Since the Diesel Generator function will not be affected by this change, no new possibilities or unanalyzed scenarios are created based on review of FSAR Sections i
9.5.5, 8.3 and 15.
Based on above, this change will not
)
36
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT create the possibilities of.an accident or equipment malfunction not described in FSAR.
3.
This change will not reduce or compromise the performance or function of the Diesel Generator or Diesel Generator operating parameters margin of safety as defined in basis of Tech. Spec. 3.7.4 or 3.4.8.
88-V1N0053 Replace globe valves 1-1206-V4-006, 1-1206-U4-007, and 1-1204-U4-151 with gate valves and plug valve respectively. The objective is to increase containment spray mini flow return line to RWST flow with higher valve flow coefficient values.
1.
This change replaces qualified globe valves with qualified gate and plug valves. System operability is not adversly affected and there is not an increase in accident probability or severity as a result of this substitution. Review included sections 6.2.2.2 and 15.
2.
There is not a change to an active component and thus no change to FMCA Table 6.2.2-5.
These valves still remain locked closed.
Therefore this change does not create the possibility of an accident or equipment / component malfunction.
3.
This change does not decrease the margin of safety defined by the bases of the Technical Specifications in sections 3/4.6.2 & 3, 3/4.5.2 & 3, or 3/4.9.8.
88 V1N0054-This Design change involves the modification of the 88 VIN 0055 In-Vent Radiation Monitors GM Tube mounting assemblies.
T" 9M Tube of each monitor is easily damaged when se, 'ed into the tube base socket and into the mounting mm at the top of the assembly. This change
.shes replacing the existing mounting grommet with a neoprene grommet and metal clamp to prevent damage to the GM Tube and facilitate installation.
1.
This change is a system improvement and does not increase the probability of occurrence or consequences of an accident described in the FSAR section 15.0.
2.
This change does not create the possibility of an accident or equipment / component malfunction not described and analyzed in the FSAR Sections 6.4, 9.4, and 15.0.
This change does not adversely affect seismic or environmental qualification requirements.
3.
This change does not affect the margin of safety defined by Tech. spec. Bases 3/4.3.2, 3/4.3.3, 3/4.7.6, 3/4.9.12, and 3/4.11.2/
37
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1988 ANNUAL REPORT - PART 2 10CFR50c59(b) REPORT l
1 88-VCN0062 Modify demineralized plant acid and caustic injection piping to provide adequate NPSH for pumps.
1.
This change involves the water treatment building which does not increase the probability of occurrence or consequences of an accident described in the FSAR, Chapter 15. System has no safety design basis per FSAR J
section 9.2.3.1.1.
2.
This change does not increase the probability of any accident. No new possibilities or unanalysed scenarios are created. This is based on review of FSAR sections 9.2.3 and 15.9.
3.
This change does not decrease the margin of safety as defined in the bases of Tech Specs 3/4.7 and 3/4.11.
88-VIN 0064 This Design Change involves replacing the existing Turbine Flowmeter and Flow Transmitter for the Waste Liquid Effluent Radiation Monitor (1RE-0018) due to repeated failures. The original flowmeter had a range of 2.5 - 250 gpm and the replacement has a range of 0-225 gpm. The range change is due to the discontinuation of manufacturing of the original model flowmeter and transmitter.
1.
There is no change to the probability or consequences of any accident described in FSAR Sections 11.0 and 15.0.
Replacing the existing flowmeter with another model of
.slightly different range does not affect the liquid waste processing system or associated radiation monitor.
2.
This change does not affect the performance of any equipment assumed to function in the FSAR accident analysis. This included review of FSAR Chapters 11.0 i
and 15.0.
This change does not alter equipment operation or design intent.
j 1
3.
There is no change in the margin of safety as defined by the bases of Tech. Specs. 3/4.3, 3.3.3.9, and 3/4.11.1 88-V1N0077 Modify the statistical test limit table used by the present algorithm and _the default parameter high and low alarm setpoint.
The present radiation monitors' logic exhibits a large number of false high alarms and system actuations.
It has been determined that the cause of l
these spurious alarms was due to the following items:
(1) DPM counting function software and (2) High and low alarm default parameter.
)
1.
There is no change to the consequences or probability l
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I1 1988 ANNUAL REPORT - PART 2 I
10CFR50.59(b) REPORT l
1 of any accident described in the FSAR. The i
modifications performed to these monitors do not affect i
their ability to respond to radiation in accordance with the accident analysis of FSAR Chapters 6 and 15. There I
is no change to the response times provided in FSAR
{
Chapter 16.
l 2.
This change does not create the possibility of any accident or component malfunction not presently analyzed in the FSAR. This included a review of FSAR sections 6, 9, 11, and 15.
l 3.
There is no change to the margin of safety defined by the basis of the Technical Specifications. This included review of Tech. Epecs. 3/4.3 and 3/4.11. There is no change in the response times provided in FSAR Chapter 16.
t 88-VIN 0078 Replace existing magnetic-only circuit breakers in MCC cubicles to 15 amp thermal-magnetic circuit breakers to provide redundant thermal protection for the associated penetration conductors.
1.
The proposed change does not increase the probability of occurrence or consequences of an accident described in the FSAR Section 15. This change provides greater protection for penetration conductors than previous type breakers.
2.
The proposed change does not create the possibility of an accident or equipment / component malfunction not described and analyzed in the FSAR Section 15. There is no change to the overcurrent protection devices listed in FSAR Table 16.3-5.
3.
There is no change to the margin of safety as defined in the bases of Technical Specifications. This included review of the basis of Tech. Spec. 3/4.8.4.
88-V1E0081 This design change stiffens duct and installs access doors in the area of 2RE-12116 and 2RE-12117, Control Room Intake radiation monitors. There are no changes to the detector sensitivity, system tolerances, or system actuation times.
1.
There is no change to any probability of occurrence or consequences of any Chapter 15 accident. The design change stiffens the duct and should improve rad monitor performance.
Adding access doors will make maintenance easier.
2.
This change does not create the possibility of any 39 l
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i II 1988 ANNUAL REPORT - PART 2 i l
10CFR50.59(b) REPORT accident or component malfunction not presently analyzed in the FSAR. There are no changes to the radiation monitor only to the HVAC ductwork. This included a review of Chapters 6, 7, 9, and 15.
3.
There is no change to the margin of safety defined by the bases of the Technical Specifications. This included review of the bases of Terh. Specs. 3/4.3.2, 3/4.3.3, 3/4.7.6 and 3/4.11.2.
88-V1N0083 This design change provides details of modifications to the Unit 1 Upper Cable Spreading Room Area (Control Building Level, 2 Rooms R-225 & R-226) floor penetration seals to provide water tight / leak proof seals. These modified seals should ensure that no water leaks from the upper cable spreading room area into the Unit 1 l
control room located below. These modified seals will meet all hazards, security and fire protection design criteria.
The seals requiring modification are i
generally located in blockouts with electrical cables.
This DCP also provides details of seals at bases of electrical cabinets and at joints between cabinets to prevent water leakage through these joints.
1.
These pen seal modifications will not increase the probability of occurrence of consequences of an accident as described in FSAR Section 15. (Accident Analysis) and Section 6 (Engineered Safety Features). All materials meet fire protection requirements.
2.
These pen seal modifications will not create the possibility for any accident or equipment malfunction not previously described and analyzed in the FSAR. The material being added does not adversely affect fire protection, or Control Room HVAC requirements of FSAR Sections 6 and 9.
3.
These pen seal modifications meet the margin of safety defined by the bases for the technical specifications.
This included a review of the bases of Tech. Spec.
3/4.7.6.
88-V1N0089 Approve use of Conax connectors for incore thermocouple connection between the thermocouple and extension cabling.
Present connectors are LEMO B connectors.
l 1.
The modifications to these thermocouple do not affect their ability to respond to temperature in accordance with accident analysis of FSAR Chapter 6 and 15.
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Il 1988 ANNUAL REPORT - PsRT 2 10CFR50.59(b) REPORT l
2.
This change does not create the possibility of any accident or component malfunction not presently analyzed in the FSAR. This included a review of FSAR Sections 4,7, and 15.
For replacement of like parts the calculated inaccuracy would t1 the same.
For either replacement with LEMO B or Conax, assumed total channel inaccuracy of E0P setpoints remains valid.
3.
Margin of safety remains unchanged as defined by the basis of Technical Specifications. This includes review of sections 3.3.3.5, 3.3.3.6, and 3.3.3.2.
88-V1N0091 Modify the motor stands on Reactor Coolant Pumps to store the articulated arms in place during pump operation.
1.
There is no change to the probability of occurrence or consequences of any accident described in the FSAR.
This included a review of Chapter 15 (accident analysis).
2.
No new component / equipment malfunctions are created by this design change.
This included a review of FSAR Chapter 15 (Accident Analysis). There is no change to the pump seismic or structural analysi.;.
3.
There are no changes to the Technical Specifications margin of safety. This included a review of the bases of Tech. Specs. 3/4.4.1 and 3/4.4.6.
88-VCN0092 Install video isolation transformers in the input to the SAS console from the field cameras to clean up the video from the perimeter assessment system.
1.
The probability of an accident is not increased by the addition of these transformers. The addition allows better perimeter assessment of alarms at night.
2.
This change does not create the possibility of any malfunction not described in FSAR sections 15 and 6.2.
3.
Based on a review of Tech. Spec. sections 3/4.3 and 3/4.7 this change does not decrease the margin of safety.
88-VIN 0093 Physical changes to the plant include the addition of 14 strap-on RTDs installed on unisolable piping.
This design change will provide the temperature monitoring instrumentation and data acquisition system that is required for compliance with the NRC Bulletin No. 88-08.
1.
The change does not increase the probability of occurrence or consequences of an accident as described in FSAR sections 3, 5.1, 6.3 and 15.0.
The 41
II
L 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT proposed change will add a non-safety related non-1E temperature monitoring and data acquisition system as recommended by Westinghouse.
2.
The recommended hardware mounted on the pipe will not affect the system design structural analysis due to the additional weight on the pipe. The temperature
,,N, acquisition system being added provides data for engineering analysis. The system does not perform any control or operation function, therefore the proposed change will not create the possibility of an accident or equipment / component malfunction not described and analyzed in FSAR Sections 3, 5.1, 6.3 and 15.0.
3.
The proposed change provides a non-safety related non-1E temperature monitoring and data acquisition system as recommended by Westinghouse. The proposed change will not impact the operation of any safety related system, therefore, no decrease in the margin of safety as defined by Technical Specifications bases 3/4.5.2 and 3/4.5.3.
88-V1N0094 This design change allows the use of Barksdale pressure switches in lieu of Whitman General pressure switches on the Main Steam Isolation Valves. The Barksdale switches were part of the original MSIV qualification program and are included in the EQDP.
1.
Since the switch is qualified by the actuator vendor for its intended purpose and in its proposed configuration, there is no impact on the probability of occurence or consequences of an FSAR accident, including review of Chapter 15.
2.
Since the switch was qualified by the vendor for its specific application, there is no new possibility for an accident or equipment / component malfunction.
3.
There is no decrease in the margin of safety defined by the bases of Tech. Specs.
l 1
88-VIN 0098 Add two surge suppressors in series with rod control j
powersupply)120VACinput(oneeachinMainandAux.
Power Supply to prevent voltage spikes due to lightning strike.
)
1.
The change does not increase the probability of occurance or consequences of an accident described in the FSAR Section 15.
The rod control power supplies are l
not Class 1E or safe shutdown equipment. This is due to i
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__ _ _ _ _ ___._ _ __J
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT the gravity failsafe design of the controlled drive mechanism.
2.
The change does not create the possibility of an accident or equipment component malfunction not described in FSAR Sections 15 and 8.3.
3.
There is no change to the margin of safety as defined in i
the bases of Tech. Specs. This is based on review of Tech. Spec. 3/4.8.
88-VCE0100 This change involves the removal and modification of I
the temporary interim barriers located in the Control, Auxiliary, and Fuel Handling Buildings. These barriers are being modified to allow access between the two units after Unit 2 lockdown.
In addition, the temporary 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire boundary between the units will be derated with the associated fire dampers and penetration seals.
1.
This change does not affect the probability or consequences of any accident described in the FSAR.
This is based on a review of FSAR sections:
3.4 - Flood Design 3.6 - Protection Against Dynamic Effects Associated With The Postulated Rupture of Piping 9A - Fire Hazards Analysis i
2.
This design change does not create the possibility of any component malfunction not already analyzed in the FSAR. This is based en review of FSAR Sections 3.4, 3.6 and 9A.
3.
There is no decrease to the margin of safety as defined in bases of Technical Specifications 3/4.3 and 3/4.7.
88-VCN0101 This change revised the setpoint of the low differential pressure actuation switches (APDSL-12567, APDSL-12568) for the Fuel Handling Building isolation. This change was required to eliminate spurious actuations of Fuel Handling Emergency Systems caused by Normal Plant operational opening of doors into negative pressure
- boundary, 1.
There is no change to the probability of occurrence or consequences of any accident described in FSAR. The setpoint still maintains the FHB slightly negative as required. The FSAR takes no credit for the Fuel Handling Emergency HVAC in the accident analysis.
2.
This change does not create the possibility of an accident or equipment malfunction not described in FSAR 43
1 II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT since no credit was taken for the operation of this system in the accident analysis. Equipment will continue to function as originally intended.
3.
The margin of safety defined in Technical Specifications is not required. The " defense in depth" concept is maintained since these changes will not effect the FHB Post Accident System because the High Radiation Auto Start is unaffected and Fuel Handling Building will still be assured to remain slightly negative as required.
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88-V1N0103 Six Containment Isolation Valcor valves (1HY-12977, 1HV-12978,;.HV-2793A, 1HV-2793B, 1HV-8211 and 1HV-8212) are re-installed in the reverse flow direction (rotating the valves 180 degrees) which will significantly reduce high leakage rates.
1.
This design change will not increase the probability i
of occurrerce or consequences of an accident described in FSAR Section 15.
2.
This change does not create the possibility of any malfunction not already described and analyzed in FSAR Section 15 and 6.2.
3.
Based on review of Bases of Tech. Spec. 3/4.6.1 this change does not affect the margin of safety.
88-VIN 0105 Change the sixteen (16) bolts on the pressurizer manway cover to a stud / nut configuration. This change is implemented in accordance with Westinghouse FCN's.
1.
Due to the similarity of the bolts and the studs and nuts there will be no change to the probability of occurrence or consequences of any accident described in the FSAR. This included a review of FSAR Chapter 15 (AccidentAnalyses).
2.
No new component / equipment malfunctions are created by this design change.
This included a review of FSAR Chapter 15 (Accident Analyses).
3.
There are no changes to the Technical Specification's margin of safety.
This included a review of the bases of Tech. Specs. 3/4.3 and 3/4.4.
88-V1N0107 Rework MSR high level drain lines in condenser to prevent damage to 1A Feedwater Heater lagging.
Rework Heater Drain Tank high level dump line in condenser to repair damage with higher strength material.
44
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 1.
The condenser is not included in FSAR accident analysis and therefore would not increase probability of accident.
2.
By rework of the drain lines in the condenser, the
)
probability of a failure, accident or malfunction described in the FSAR is not affected.
3.
This modification does not decrease safety margins of the system. The basis of the system is not described in the FSAR.
88-V1N0108 This desisI change eliminates the potential for undesired ESF chiller trips when the chillers are, running concurrent with a SI signal and allows for a process control trip during sequencing. This change removes the sequence block from the demand interlock circuit and the compressor trip circuit.
j i
1.
There is no change to the probability or consequences of
)
any accident described in FSAR. This is based on no change to the diesel load sequencing and shedding described in FSAR 8.3 and 15 as well as no change to the emergency chiller /HVAC described in FSAR Sectio..s 6.4, 9.2, 9.4 and 15.0.
2.
This design change does not create the possibility of an accident or equipment malfunction not already described in the FSAR. This is based on FMEA's in FSAR Sections 8.3.1 and 9.2.9 as well as review of Sections 6.4, 7.3, 8.3, 9.2, 9.4 and 15.
3.
TM s change does not affect the margin of safety as defined in the bases of Technical Specifications 3/4.3.2, 3/4.7.11, and 3/4.8 since the ESF chillers are still sequenced if not running and since, if the chillers are running concurrent with a SI signal, they are not shutdown.
j 88-V1N0109 This change removes the high radiation alarm interlock with the bypass and block relays for Radiation Monitor Channel 1RE25658.
This change will enable the DPM to be placed in the " Bypass" mode and block all Containment Ventilation Isolation signals when high alarms are initiated during testing.
This change will also allow a CVI signal to be initiated if a high alarm is generated while the DPM is in the " Remote" Mode.
1.
This design change will not increase the consequences or probability of any accident described in the FSAR Sections 6,0, 7.0, 15.0, and 9.0. This change does not alter the design intent of the monitor or its operation.
45 l
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1I 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 2.
This change does not increase the consequences or probability of any accident or component malfunction-which is not presently analyzed in the FSAR chapters 6.0, 7.0, 9.0, and 15.0.
This change provides proper operation of the monitor and has no affect on its ability or associated monitor ability to respond to radiation.
3.
There is no change to the margin of safety defined by the bases of the Tech. Specs. 3/4.3 and 3/4.11.
MIN 0R DEPARTURES FROM l'". SIGN (MDD's) i 88-VCM001 Revise oxygen analyzer micro-fuel cells from B2-X model to B2PM50 cells.
Revise resistance valves for oxygen analyzer to meet requirements of new fuel cells.
1.
There is no change to the probability of occurrence or consequences of any accident postulated in any chapter 15 accident.
2.
No new component malfunctions are created by this change nor is there a possibility of an accident not previously l
evaluated in the FSAR Section 11.3 and Section 15.
3.
There is no change to the Tech Spec margin of safety.
This is based on Review of the follow Pp: Section 3.3.3.10, 3/4.3.3, 3/4.11.2, 3.11.25, and Tables 3.3-10 and 4.3-6.
88-V1M002 Install an insulated coupling between the Main Gear Shaft and the splined coupling in the Turbine front standard.
This modification will electrically isolate the Auxiliary Rotor from the main rotor.
1.
Modification will not increase the probability of an accident described in Chapter 15 of FSAR since Turbine is not safety related.
2.
Modification does not increase the possibility of an accident other than evaluated in Chapter 15 of the FSAR since Turbine does not affect other safety related systems.
3.
Modification does not decrease safety margin. Turbine System is not included in basis for Technical Specification.
88-V1M003 Remove Health Physics terminals from the Security Computer to fully separate Health Physics functions from Security functions.
46 L_________________
Il 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 1.
The removal of these terminals removes H.P. access to the security system. The removal further reduces the possibility of system problems due to H.P.. functions.
Therefore the probability of an accident is decreased.
2.
The removal of these terminals decreases the probability of an equipment malfunction since they will no longer be tied into the security system.
3.
The removal of these terminals does not decrease the margin of safety as defined in Technical Specifications sections 3/4.3, and 3/4.7 because the equipment will not interface with the security system any longer.
88-V1M004 On'the Main Turbine upgrade the 10 existing vibration printed circuit cards. Revised card has a built-in filtering circuit which prevents a Turbine trip on a spurious vibration signal.
1.
Modification will not increase the probability of an accident as described in Chapter 15 of FSAR since Main Turbine is non safety related.
2.
Modification does not increase the possibility of an accident other than evaluated in Chapter 15 of FSAR since equipment does not affect any other safety related systems.
3.
Modification does not decrease safety margin since Turbine System is not included in bases for Technical Specification.
88-V1M005 Modification of Turbine Impulse Pressure Indicators to read in "% Power" in lieu of Pressure, also IPI-505 and IPI-506 scale change.
1.
Modification will not increase the probability of an accident as described in Chapter 15 of FSAR since PI's are not safety related.
l 2.
Modification does not increase the possibility of an l
accident other than evaluated in Chapter 15 of FSAR since PI's do not affect other safety related equipment.
l 3.
Modification does not decrease safety margin since Turbine System is not included in bases for Technical Specification.
88-V1M006 Install new orifice to bring flow through the various heat exchangers in the Boron Recycle Evaporator within allowable flow limits.
47
_j
XI 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 1.
FSAR Sections 9.2.8 (ACCW) and 9.3.2.2 (Boron Recycle Evaporator were reviewed. The proposed change still satisfies all the requirements as described in these sections of the FSAR. The proposed change does not involve a change in the facility as described in the FSAR, therefore there is no increase in probability of an accident.
2.
FSAR Sections 9.2.8 (ACCW) and 9.3.2.2 (Boron Recycle Evaporator were reviewed. The proposed change still satisfies all the requirements as described in these sections of the FSAR. The proposed change does not involve a change in the facility as described in the FSAR, therefore there is no decrease in safety margin.
3.
The only requirement for ACCW is Technical Specification 3/4.7.12 which requires isolation capability for the RCP Thermal Barrier. The proposed change does not impact this isolation function. Therefore, the proposed change does not make a change to Technical Specifications and does not create an unanalysed condition.
88-V1M007 On Drawing AX1008A06-2 make the 1 1/2" metal siding on the Auxiliary building at MSIV's optional. Show 6 wedge anchors 3/4" as permanent. These anchors are on Level 1 Containment west of the hoistway.
1.
These changes cannot increase the probability of an accident because the metal siding was only an architectural feature.
It provided no structural or security function. When siding is removed the MSIV valve room will ye increased natural draft and maintain a lower temperature.
2.
This change cannot create the possibility of an accident other than previously evaluated. These changes do not affect the hazards analysis in the FSAR.
In the event of a main steam line break the siding is expected to blow off the side of the Aux. Bldg.
Its removal prevents the siding from failing during this type of accident.
3.
These changes will have no effect on the margin of safety.
These items have no Tech. Spec. requirements.
88-V1M009 For piping outside containment allow the use of Nukon Pads or fiberglass with aluminum jacket.
1.
These changes do not increase the probability of an accident.
The insulttion change provides equivalent insulation of the piping.
The fiberglass with aluminum 48 I
--_____--___-_______Q
II 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT jacket is ciualified for use in all areas outside containment.
The fiberglass with aluminum jacket type of insulation outside containment will not affect the l
containment post-LOCA environment. This material will have no detrimental effect on the environmental conditions where used.
2.
This change cannot create the possibility of an accident other than previously evaluated.
The change allows materials equally qualified to be used outside containment.
3.
These changes will have no effect on the margin of safety. The insulation change was equal in quality outside containment. The insulation will have no effect on the Tech. Spec.
88-V1M010 The physical change to plant equipment consists of reducing the RCP under-frequency relay operating time from 24 cycles to 15 cycles. The 15 cycles time delay includes three consecutive bad cycles.
1.
Changing the under-frequency delay from 24 cycles to 15 cycles is consistant with the value in FSAR Table 16.3-1 and is within the bounds of safety analysis.
2.
The setpoint change will not increase the probability of malfunction of underfrequency relay or the system function. The relay setpoint is described in FSAR Sect.
15.3.2.1.
3.
The proposed change has a margin of safety consistant with Tech. Spec. bases as stated in Bases 2.2.1 Rx Trip l
System instrumentation setpoints.
88-V1M012 Upgrade the existing ATSI Printer with newer model.
1.
Modification will not increase the probability of an accident as described in Chapter 15 of FSAR since ATSI is not safety related equipment.
2.
Modification does not increase the possibility of an accident other than evaluated in Chapter 15 of FSAR since ATSI does not affect other safety related systems.
3.
Modification does not decrease safety margin since the Turbine System is not included in bases for Technical Specification.
88-V1M014 Security Bars were installed on the HVAC Intake at ESL 12679 by TMR 1-87-473.
Process this MDD to allow the Temp Mod to be upgraded to a permanent design status.
49
Il 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT 1.
The addition of rebar to HVAC intake dampers 1-1551-W7-300,301 does not interfere with the operation of the dampers, the probability or consequences of an accident are not increased.
2.
The change does not create the possibility for an accident or component malfunction of a different type not previously evaluated in the FSAR because the bars do not interface with the operation of the dampers.
3.
The addition of the bars does not decrease the margin of safety as defined by Technical Specifications 3/4.7.
The dampers are not affected by the bars.
88-VCM019 Hydrogen Recombiner oxygen analyzer circuit revision for oxygen analyzer resistance values to meet requirements of new fuel cells.
1.
There is no change to the probability ouccurrence or consequences of any accident postulated in any chapter 15 accident.
2.
No new component malfunctions are created by this change nor is there a possibility of an accident not previously evaluated in the FSAR section 11.3 and section 15.
l 3.
There is no change to the Tech Spec margin of safety.
This is based on review of the following:
Section 3.3.3.10, 3/4.3.3, 3/4.11.2, 3.11.25, and Tables 3.3-10 and 4.3-6.
50 u
f XI 1988 ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT TESTS OR EXPERIMENTS l
51
II 1988 ANNUAL' REPORT - PART 2 10CFR50.59(b) REPORT 4
T-ENG-88-6
'The purpose of test was to verify proper operation of PORV-0456A circuitry, pressurizer heaters and spray valves also pressurizer level control circuitry, due to penetration seal leakage into control panels.
1.
The proposed test does not increase the probability of' occurrence or consequences of an accident described'.in the FSAR, since this test only: demonstrates' proper operation of the pressurizer backup heaters, spray valves, PORV-456A, and level deviation annunciation by using approved site procedures.
2.
The proposed test does not create the possibility for 4n-accident or equipment / component malfunction of a different type other than any evalusted previously in the FSAR since this test only demonstrates proper operation of pressurizer pressure and level. design features using standard operating and calibration procedures.
i 1
52
II 1988~ ANNUAL REPORT - PART 2 10CFR50.59(b) REPORT l
3.
This test does not decrease the margin of safety defined by the bases for the Technical Specification since the test only demonstrates proper operation of certain pressure and cover control features using standard procedures. Tech Spec requirements were maintained during this test.
T-ENG-88-09 The purpose of this test was to collect data to be used to establish a quantitative basis for possible design changes and administrative controls, as required to prevent excessive vibration in the PD pump suction / discharge piping over the entire range of VCT pressures.
1.
This does not increase the probability of occurrence of an accident described in FSAR since the PD pump is non safety related and the safety related CCP's remained operable.
2.
The PDP will be operated in accordance with existing operating procedures as discussed in FSAR section 9.3.4
" Chemical and Volume Control System." The PDP was included in the original plant design accident analysis and therefore no accident or equipment /coniponent malfunction of a different type will be created as a result of this test.
3.
PD pump is non safety related and is not addressed in the plant Tech Spec.
Data collected per this procedure will provide guidelines for routine use of the PD pump.
This will in effect increase the margin of safety for Tech. Specs, on the CCP's by decreasing their operating run time.
T-ENG-87-16 Obtain Fuel Handling Building negative pressure boundary data when boundary doors are opened and closed.
1.
The probability of an analyzed accident increasing is not caused by this test since no permanent modifications are made, and Tech Spec requirements are met.
2.
This test does not increase the probability of an unanalyzed accident since no permanent modifications are made and Tech Spec requirements are maintained.
3.
Margin of safety is not reduced since irradiated fuel Tech Spec requirements are met.
T-ENG-87-5 Run Fuel Handling Building HVAC fan for vibration and motor data to aid in the disposition of an identified potential deficiency.
53
1988 ANNUAL REPORT - PART 2 10CFR50e59(b) REPORT 1.
No permanent modifications are performed by this test.
This test does not increase the probability of an analyzed accident.
2.
No permanent modifications are performed by this test.
l This test does not increase the probability of an unanalyzed accident.
3.
The margin of safety is not reduced since Tech Spec
)
requirements are maintained.
4 T-ENG-88-1 Obtain data on possible viaration of PERMS detectors while in service.
1.
This test does not increase the probability of an analyzed accident since Tech. Spec. requirements are met when monitors are taken out of service.
2.
This test does not increase the probability of an unanalyzed accident since Tech Spec requirements are maintained.
3.
Margin of safety is not reduced since Tech. Spec.
requirements for monitors are maintained.
T-ENG-88-14 Verify proper operation of Proteus graphics display program OS02.
1 This test does not increase the probability of an analyzed accident since computer operation does not impact Tech. Specs.
2.
This test does not increase the probability of an unanalyzed accident since computer operation does not impact Tech. Specs.
e 3.
Margin of safety is not increased since Tech. Spec.
requirements are maintained.
1 T-ENG-88-20 Obtain piping vibrction data on RHR system piping.
1.
This test will not increase the probability of an analyzed accident since plant components are operated within Tech Spec requirements.
2.
This test will not increase the probability of an u'1 analyzed accident since no system modification other than lanyard placement is used and system is operated within Tech Spec requirements.
3.
Margin of safety is not reduced since Tech Spec requirements are maintained.
54
II 1
1988 ANNUAL _ REPORT --PART 2
{
-10CFR50;59(b) REPORT i
T-ENG-88-22
' Provide procedural. instructions for setup and performance.
of Ma1n' Generator Rotor-Magnetic Field Flux Probe Test.
1.
This test will not increase the probability of an
-analy:'d accident since generator systems involved are not adikassed by Tech Specs.
2.
This test will not increase the probability of an unanalyzed accident since equipment involved does not affect Tech Spec-basis.
3.
Margin of safety is not reduced since Tech Spec requirements are maintained.
TER 88-01 Determine the actual' heat load in the Unit 1 Control Room 1.
This test will not increase the probability of a described accident since all systems will be operated within Tech Spec limits.
2.
This test will not increase the probability of occurrence of an unanalyzed accident since all equipment will be operated within Tech Spec limits. The Control Room environment as required by Tech Specs will be maintained.
3.
Margin of' safety will not be reduced since Tech Spec requirements will be met during equipment operation.
I f
ss
r III PLANT V0GTLE UNIT 1 ANNUAL REPORT PART 2 EMERGENCY CORE COOLING SYSTEM OUTAGE DATA REPORT Emergency Core' Cooling System components were out of' service a total of 280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br /> and 31 minutes in 1988.
This report contains:
a) outage dates and duration of outages b) ECCS systems or components involved in the outage c) cause of the outage, and d). corrective actions taken 1.
a) 1-6-88 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> & 30 minutes b & c) Accumulator #2 vent valve "A" position indicator failed surveillance testing.
d)
Indicator repaired per work order and returned to service 2.
a) 1-11-88 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> & 47 minutes b & c) Centrifugal Charging Pump "B" tagged out for deflector shield work, d)
Deflector shield secured, CCP returned to service 3.
a) 2-8-88 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> & 19 minutes b & c) Safety Injection Syrtem realigned for accumulator fill.
d)
Normal alignment restored (See LER 50-425/1989-011 for details of this event).
4.
a) 2-24-88 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> & 37 minutes b & c) Accumulator tank #3 taken out of service to change baron concentration d)
Boron concentration changed, level and pressure adjust'ed, accumulator returned to service.
5.
a) 3-4-88 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> & 45 minutes b & c) Residual Heat Removal Train "B" removed from service to perform preventive maintenance on discharge valve 1HV-0607 d)
Maintenance performed per procedure. Valve verified operable and Train "B" restored to service 6.
a) 3-23-88 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 24 minutes b & c) Centrifugal Charging Pump "A" tagged out for equipment qualification inspection d)
Inspection completed and pump returned to service 7.
a) 3-24-88 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 16 minutes b & c) Safety Injection Pump "A" miniflow valve taken out of service when motor lead insulation damage found.
d)
Damaged insulation repaired and valve restored to service.
8.
a) 6-10-88 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> & 20 minutes b & c) Safety Injection pump "A removed from service for preventive maintenance d)
Maintenance completed.
Pump t w ed and returned to service.
56
III PLANT V0GTLE UNIT 1 ANNUAL REPORT PART 2 EMERGENCY CORE COOLING SYSTEM OUTAGE DATA REPORT l
9.
a) 7-28-88 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> & 59 minutes i
b & c) Resideal Heat Removal Train "B" removed from service to perform preventive service on discharge valve 1HV-0607 d)
Maintenance perfonned per procedure.
Valve verified operable and Train "B" restored to service
- 11. a) 9-6-88 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> & 47 minutes b & c) Safety Injection pump "A" tagged out for preventive maint( *ance and inservice testing.
d)
Main dnance and testing completed and pump returned to service.
- 12. a) 9-9-88 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br /> & 18 minutes b & c) Centrifugal Charging Pump "A" removed from service for preventive maintenance.
d)
Maintenance perfonned per procedure and pump returned to service.
13.
a) 9-12-88 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> & 22 minutes b & c) Safety Injection pump "B" removed from service for preventive maintenance.
d)
Maintenance perfonned per procedure.
Pump tested and returned to service.
- 14. a) 9-16-88 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> and 20 minutes b & c) Residual Heat Removal Train "B" removed from service to perform calibration of discharge valve 1HV-0607.
d)
Valve calibrated per procedure, tested, and Train "B" returned to service.
- 15. a) 11-23-88 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> & 25 minutes b & c) Safety injection system realigned for accumulator fill.
{
d)
Nonnal alignment restored (See LER 50-425/1989-011 for i'
details of this event).
16.
a) 12-21-88 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> & 28 minutes b & c) Residual Heat Removal Train "B" removed from serivce I
to install pipe support.
d)
Pipe support' installed, tested, and Train "B" returned
]
to service, j
57 i
b
I' IV GEORGIA POWER COMPANY V0GTLE ELECTRIC GENERATING PLANT.
ANNUAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT-CALENDAR. YEAR 1988 NRC DOCKET NO. 50-424 NRC OPERATING LICENSE NO. NPF-68 i
l l
V0GTLE ELECTRIC GENERATING PLANT RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT r
TABLE OF CONTENTS SECTION TITLE PAGE j
1.0 INTRODUCTION
1-1 2.0
SUMMARY
DESCRIPTION 2-1 3.0 RESULTS
SUMMARY
3-1 4.0 DISCUSSION OF RESULTS.................
4-1 4.1 Airborne 4-3 4.2 Direct Radiation 4-5 4.3 Milk........................
4-7 4.4 Vegetation.....................
4-8 4.5 River Water......................
4-9 4.6 Drinking Water,...................
4-10 4.7 Fish........................
4-11 4.8 Sediment 4-12 5.0 INTERLABORATORY COMPARIS0N PROGRAM...........
s-1
6.0 CONCLUSION
S 6-1 l
1 1
l
TABLE-0F CONTENTS (Continued)
LIST OF TABLES
.TARLE IIILE PEE 2-1 SUMMARV' DESCRIPTION OF RADIOLOGICAL ENVIRONMENTAL. MONITORING PROGRAM 2-2 2-2 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 2-7 3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
3-2 4-1 LAND USE CENSUS RESULTS 4-2 5-1 CROSSCHECK PROGRAM RESULTS FOR AIR FILTERS 5-2 5-2 CROSSCHECK PROGRAM RESULTS FOR MILK SAMPLES 5-3 5-3 CROSSCHECK PROGRAM RESULTS FOR WATER SAMPLES 5-4 ii
TABLE OF CONTENTS (Continued)
LIST OF FIGURES FIGURE lilLE PAGE 2-1 TERRESTRIAL STATIONS NEAR SITE B0UNDARY 2-10 2-2 TERRESTRIAL STATIONS BEYOND SITE B0UNDARY OUT TO APPR0XIMATELY FIVE MILES AND AQUATIC STATIONS 2-11 l
2-3 TERRESTRIAL STATIONS BEYOND FIVE MILES 2-12 2-4 DRINKING WATER STATIONS 2-13 I
iii
ACRONYMS CL Central Laboratory CSRA Central Savannah River Area CY Calendar Year EPA Environmental Prot ection Agency GE Greater Than or Equal to GPC Georgia Power Company LLD Lower Limit of Detection LT Less Than MDD Minimum Detectable Difference MDA Minimum Detectable Activity NA Not Applicable NDM No Detectable Measurement (s)
NRC Nuclear Regulatory Commission ODCM Offsite Dose Calculation Manual REMP Radiological Environmental Monitoring Program RL Reporting Level RM River Mile s
Standard Deviation SRP Savannah River Plant TLD Thermoluminescent Dosimeter TS Technical Specifications for Unit 1 VEGP Vogtle Electric Generating Plant iv
V0GTLE ELECTRIC GENERATING PLANT RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT
1.0 INTRODUCTION
This is the second annual Radiological Environmental Surveillance Report for the Alvin W. Vogtle Electric Generating Plant (VEGP).
It covers activities of the Radiological Environmental Monitoring Program (REMP) during calendar year (CY) 1988.
Hence all dates in this report are for the year 1988 unless otherwise indicated.
The specifications for the REMP are provided by Section 3/4.12 of the Technical Specifications for Unit 1 (TS).
The objectives of the REMP are to ascertain the levels of radiation and the concentrations of radioactivity in the environs of VEGP and to evaluate any radiological impact to the environment due to plant operations. A comparison between the results obtained during the preoperational and operational phases provides some basis for such an evaluation. A comparison between the results obtained at control stations (locations where radiological levels are not expected to be significantly affected by plant operations) and at indicator stations (locations where it is anticipated that radiological levels are more likely to be affected by plant operations) provides a further basis for the evaluation.
A summary description of the REMP is provided in Section 2.
This includes maps showing the sampling locations; the maps are keyed to a table indicating the distance and direction of each sampling location from a point midway between the two reactors.
An annual summary of the main laboratory analysis results obtained from the samples utilized for environmental monitoring is presented in Section 3.
A discussion of the results including assessments of any radiological impacts upon the environment is provided in Section 4.
s The results of the Interlaboratory Comparison Program are presented in Section 5.
The chief conclusions are stated in Section 6.
1-1 l
2.0
SUMMARY
DESCRIPTION A summary description of the REMP is provided in Table 2-1.
This table portrays the ' program in the manner by which it is being regularly i
carried out; it is essentially a copy of Table 3.12.1-1 of the TS which j
delineates the-program's requirements.
Sampling locations specified by j
Table 2-1 are described in Table 2-2 and are shown on maps in Figures j
2-1 through 2-4.
This description of the sample locations closely follows that found in the table and figures of Section 3.0 of the Offsite Dose Calculation Manual (0DCM).
I It is stated in Footnote (1) of Table 3.12-1 of the TS that deviations are permitted from the required sampling schedule which is delineated in Table 2-1 herein, if specimens are unobtainable due to circumstances, such as, hazardous conditions, seasonal unavailability, and malfunction of sampling equipment. Any devictions are accounted for in the discussions for each particular sample type in Section 4.
During 1988, all the laboratory analyses except for the reading of the thermoluminescent dosimeters (TLDs) were performed by Georgia Power Company's (GPC's) Central Laboratory (CL) in Smyrna, Georgia. The reading of the TLDs was provided by Teledyne Isotopes Midwest Laboratory in Northbrook, Illinois.
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-l L
TABLE NOTATIONS (1)
One or more' instruments, such as'a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition-to, integrating dosimeters.
For the purposes of this table, a TLD is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film badges.shall-rnot be used as dosimeters for measuring direct radiation.
(2)
Airborne particulate sample filters shall be ' analyzed for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.
If gross beta activity in air particulate' samples is greater than 10 times the yearly mean of control samples, gamn'a isotopic analysis shall be performed on the individual samples.
(3)
- Gamma isotopic analysis means -the identification and quantification of gamma-emitting radionuclides that may be attributable to.the effluents from the f*c0 ity.
(4)
The upriver sample is taken at L distance beyond significant influence.
of the discharge. The downrivec samples are be taken in areas beyond and near the mixing zone.
(5)
Composite sample aliquots shall be collected at time intervals that are very short-(e.g., hourly) relutive to the compositing period (e.g.,
monthly) in order.to assure obtaining a representative sample.
(6)
The dose shall be calculated for the maximum organ and age group, using the methodology and-parameters in the ODCM.
(7)
A milking animal is a cow or goat producing milk for human consumption.
(8)
If gamma isotopic analysis is not sensitive enough to meet the Lower.
Limit of Detection (LLD) for I-131, a separate analysis for I-131 will be performed.
I 2-6 I-E__________
TABLE 2-2' (SHEET 1 0F 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station.
Descriptive Direction (2) Distance (2)
Sample i
Number Tvoe (1) location (miles)
Tvoe(3) 1 I
Hancock Landing Road N
1.1
_D l
2-I-
River Bank NNE 0.8 D
3 I
Discharge Area NE 0.6 A
3.
.I River Bank NE 0.7 D
4.
I River Bant ENE 0.8 D
5 I
. River Bank E
1.0 0
6 I
Plant Wiison ESE 1.1 D
7 I
Simulator Building SE 1.7 0,V,A 8
I River Road SSE 1.1 D
9 I
. River Road S
1.1 0
10 I
10 I
River Road SSW 1.1 D
11 I
River Road SW l.2 D'
12-I-
River Road WSW l.1 D,A 13:
I:
River Road W
l.3 0
14 I
River Road WNW 1.8 D
15 I
Hancock Landing Road NW 1.5 D,V
- 16 I
Hancock Landing Road NNW 1.4 D,A 17 0
Savannah River Plant River Road N
5.4 D
18 0
Savannah River Plant D Area NNE 5.0 D
19 0
Savannah River Plant Road A.13 NE 4.6 D
20 0
Savannah River Plant Road A.13.1 ENE 4.8 D
21 0
Savannah River Plant Road A.17 E
5.3 D
22 0
River Bank Downstream of Buxton Landing-ESE 5.2 0
23 0
River Road SE 4.7 D
24 0
Chance Road SSE 4.9 D
25 0
Chance Road and Highway 23 S 5.2 D
26 0
Highway 23, Mile 15.5 SSW 4.6 0
27 0
Highway 23, Mile 17 SW 4.8 D
28 0
Claybon Road WSW 5.0 D
29 0
Claxton-Lively Road W
5.0 0
30 0
Nathaniel Howard Road WNW 5.0 0
31 0
River Road at Allen's 4
Church Fork NW 5.0 D
32 0
River Bank NNW 4.8 0
33 0
Nearby Permanent Residence SE 3.3 D
f 34 0
Girard Elementary School SSE 6.3 D
2-7
TABLE 2-2 (SHEET 2 0F 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Station Station Descriptive Direction (2) Distance (2)
Sample Number Tvoe (1)
Location (mi l e tl___
Iype(3) 35 0
Girard SSE 6.6 D,A 36 C
Waynesboro WSW 14.9 D,A 37 C
Substation (Waynesboro)
WSW 17.5 D,V 43 0
Employees Recreation Area SW 2.2 0
80 C
Augusta Water Treatment Plant NNW 24.5 W(4) 81 C
Savannah River N
2.2 F(5),S(6) 82 C
Savannah River (RM 151.2)
NNE 0.8 R
83 I
Savannah River (RM 150.6)
ENE 0.8 R,S(6) 84 0
Savannah River (RM 149.5)
ESE 1.6 R
85 I
Savannah River ESE 5.0 F(5) 87 I
Beaufort-Jasper County Water Treatment Plant; Beaufort, SC SE 76 W(7) 88 I
Cherokee Hill Water Treatment Plant; Port Wentworth GA SSE 72 W(8) 98 C
W. C. Dixon Dairy SE 9.8 M
99 C
Boyceland Dairy W
24.5 M
TABLE NOTATION:
(1)
Station Types C - Control I - Indicator 0 - Other (2)
Direction and distance are reckoned from a point midway between the two reactors (3)
Sample Types A - Airborne Radioactivity D - Direct Radiation F - Fish M - Milk R - River Water S - River Shoreline Sediment W - Drinking Water (at water treatment plant)
V - Vegetation 1
2-8 1
I
TABLE 2-2 (SHEET 3 0F 3)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS TABLE NOTATIONS (Continued)
(4)
'The intake for the Augusta Water Treatment F b,c is located on the Augusta Canal. The entrance to this canal is at River Mile (RM) 207 on the Savannah River. The canal effectively parallels the river.
The intake to the pumping station is 3.6 miles down the canal and only a
. tenth of-a mile across a narrow neck of land to the river.
(5)
About a five mile stretch of the river is generally needed to obtain adequate fish samples.
Samples are normally gathered between RM 153 and 158 for upriver collections and between RM 144 and 149.4 for downriver collections.
(6)
Sediment is collected at locations with existing or potential recreational value.
Because high water shifting of the river bottom or other reasons could cause a suitable location for sediment collection to become unavailable or unsuitable, a stretch of the river between RM 149.7 and 150.7 is designated for downriver collections while a stretch between RM 153 and 154 is designated for upriver collections.
In practice, collections are normally made at RM 150.2 for downriver collections and at RM 153.2 for upriver collections.
(7)
The intake for the Beaufort-Jasper County Water Treatment Plant is located at the end of a canal which begins at RM 39.2 on the Savannah River. This intake is about 16 miles by line of sight down the canal from its beginning on the Savannah River.
4 (8)
The intake for the Cherokee Hill Water Treatment Plant is located on Abercorn Creek which is about one and a quarter creek miles from its mouth on the Savannah River at RM 29.
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UNIT 1 AND UNIT 2 FIGURE 2-3 433 9 2-12
l 1
i h AUGUSTA WATER TREATMENT PLANT so SAVANNAH j
nevEn PLANT j
VEGP W N
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D Sav4NNA Y
O vooTLE DRINKING WATER STATIONS ELECTRIC OENERATING PLANT GeorgiaPower unit i ANo unit :
FIGURE 2-4 C33-9 2-13
)
f 3.0 RESULTS
SUMMARY
In accordance with Section 6.8.1.3 of the TS, summarized and' tabulated results of all of the regular radiological environmental samples and radiation measurements taken during the year at the designated indicator and control stations are presented in Table 3-1 in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November, 1979. Naturally occurring radionuclides which are not-included in the plant's effluents are not required to be reported.
Results for samples collected at locations other than indicator or control stations or in addition to those stipulated by Table 2-1 are included in Section 4, the discussion of results section, for the type sample.
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(
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ud' i
l i :
l'
TABLE 3-1 (SHEET 10 0F.10)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
Vogtle Electric Generating Plant, Docket No. 50-424 Burke County, Georgia, Report Period 1988 TABLE NOTATIONS a.
The LLD is defined in table notation 3 of Table 4.12-1 of the TS.
Except as noted otherwise, the values listed in the column are those found in that table.
b.
Mean and range are based upon detectable measurements only.
Fraction of detectable measurements at specified locations is indicated in parenthesis.
c.
No Detectable Measuronent(s).
d.
Not Applicable, e.
The CL has determined that this value may be routinely attained. No value was provided in Table 4.12-1 of the TS.
f.
In accordance with Item 3b of Table 3.12-1 of the TS, an I-131 analysis is not required to be performed on these samples when the dose calculated from 'the consumption of water is less than 1 mrem per year, g.
The mean for the control station was the same as that for the indicator station.
3-11
+
l 4.0 DISCUSSION OF RESULTS An interpretation and evaluation, as appropriate, and an analysis of the laboratory results for each type sample are included in this section.
Relevant comparisons were made between the difference in average values for indicator and control stations and the calculated Minimum Detectable Difference (MDD) between these two groups at the 99-percent confidence level.
The MDD was determined using the standard Student's t-test. A difference in the average values which is less than the MDD is considered to be statistically indi-scernible.
Pertinent results were also compared with past results including preoperations. The results were examined to perceive any trends. To provide perspective, a result might also be compared with its LLD or Reporting Level (RL). Attempts were made to explain any RLs or other high radiological levels found in the samples.
There were no failures in the laboratory analyses of each of the samples in attaining the LLDs required by Table 4.12-1 of the TS for this report period. Any deviations from the sampling scheduled are documented by sample type in this section.
Unless otherwise indicated, any references made in this section to the results of a previous period will be results which have been purged of any obvious extraneous short term impacts.
During preoperations these included nuclear weapons tests, abnormal releases from the Savannah River Plant (SRP) and the Chernobyl incident.
During the operations part of 1987, these included abnormal releases from SRP.
There were no obvious extraneous short term impacts during CY 1988.
Also unless otherwise indicated, any references to CY 1987 will be to the operations part of 1987.
The annual land use census was conducted on April 25; follow-ups to the census were conducted on June 22 and July 8 to obtain confirmatory and additional information. The locations of the nearest milk animal, residence and garden of greater than 500 square feet producing broad leaf vs.getation in each of the 16 meteorological sectors within a distance of 5 miles are tabulated in Table 4-1.
Land within SRP was excluded from the census.
Any consequences of the results of the land use census upon sample collections are discussed in bections 4.3 and 4.4.
The results of the annual survey conducted downstream of the plant to determine whether water from the Savannah River is being used for drinking or irrigation purposes are presented in Section 4.5.
1 1
4-1
TABLE 4-1~
LAND USE CENSUS RESULTS Distance in Miles to Nearest Locations-in Each Sector SECTOR
-MILK RESIDENCE LEAFY ANIMAL GARDEN N
NNE NE' ENE E
4.4' I
SSW 4.6 i
1 1
SW-3.0
.WSW 1.2 3.1 W-1.8 WNW 1.7 3.5 NW 2.1 NNW
- None within 5 miles and outside of SRP.
i l
l 4-2 l
4.1 Airborne As indicated by Tables 2-1 and 2-2, airborne particulate and airborne radioiodine are collected at 5 indicator stations (Nos. 3, 7, 10, 12, and 16) which encircle the site boundary, at a nearby community (No. 35) j and at a control station (No. 36). At these locations, air is continuously drawn through a particulate filter and a charcoal canister in sequence to retain airborne particulate and to adsorb airborne radioiodine, respectively. The filters and canisters are collected weekly.
Each of the air particulate filters is counted for gross beta activity. A gamma isotopic analysis is performed quarterly on a composite of the air particulate filters for each station.
Each
]
charcoal canister is analyzed for I-131 by gamma spectroscopy.
As seen in Table 3-1, the averaae weekly gross beta activity during the i
year for the indicator statior.' was 1.0 fCi/m3 greater than that for the l
control station.
However, this difference is not discernable since it is less than the MUD which was calculated as 2.0 fCi/m3, The average gross beta activity in units of fCi/m3 for the indicator, community and control stations during CY 1988 are compared below with those attained during CY 1987, the entire preoperational period (which began in September 1981 for the air monitoring stations) and with the range of annual averages during the calendar years of preoperations.
Preop b eop Group CY '88 CY '87 Overall Ranaes Indicator 24.7 23.0 22.9 18.1-28.1 Community 22.8 22.3 21.9 19.3-25.5 Control 23.7 23.5 22.1 18.3-26.5 Each of the period averages fall well within the ranges of the annual average values for the years of preoperations.
No positive results for manmade radionuclides were found during the year from the gamma isotopic analyses of the quarterly composites of the air particulate filters. During CY 1987, Cs-137 was found in 40% of the indicator composites and none of the control composites; the average level was 8 fCi/m3 During preoperations Cs-137 was found in an eight of the indicator composites and a seventh of the control composites with average levels of 1.7 and 1.0 fCi/m3, respectively.
The required LLD is 60 fCi/m3 Also, during reoperation Cs-134 was found in about 8% of the indicator composites; the average level was 1.2 fCi/m3, I-131 was not detected in any of the charcoal canisters during the year.
There were no positive results during 1987.
During preoperations, positive results were obtained only during the aftermath of the i
l 4-3 4
Chernobyl incident when levels as high as 182 fCi/m3 were obtained. The maximum allowed LLD is 70 fCi/m3; however, the LLD usually attained was about 30% of this value. The RL is 900 fCi/m3, There was a failure.in obtaining a charcoal sample at Station 7 for the collection on March 1, as the canister had not been installed. To
-prevent a recurrence, those collecting the samples were carefully instructed in the steps to be followed in the installation process.
I 4-4
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4.2 Direct Radiation Direct (external) radiation is measured by TLDs. A TLD badge is placed I
at each station; each badge contains 4 calcium sulfate cards. Hence, each of the TLD badges consists of 4 dosimeters.
Two TLD stations are established in each of the 16 meteorological sectors about the plant. The inner ring of stations (Nos. I through 16) l is located near the site boundary, ahile the outer ring (Nos.17 throu.;h
)
I
- 32) is located at a distance of about 5 miles. The 16 stations forming the inner ring are designated as the indicator stations.
The 2 control stations (Nos. 36 and 37) are well over 10 miles from the plant.
Special interest areas consist of a nearby permanent residence (No. 33),
the Girard Elementary School (No. 34), the Town of Girard (No. 35), and l
the GPC employees' recreational area (No. 43).
l Frequently, TLDs are lost due to theft and damaged due to vandalism.
A l
total of 3 badges from 3 different stations was found to be missing during the year.
As may be seen from Table 3-1, the average quarterly dose acquired at the indicator stations over the year was 0.7 mR more than that acquired at the control stations; this difference was not discernable, however, since it was less than the MDD of 2.1 mR.
The quarterly doses acquired at the outer ring stations ranged from 12.4 to 26.7 mR with an average of 16.0 mR for the year which is 0.8 mR less than that found for the inner ring. There was no discernable difference l
between the averages of the inner and outer rings since this difference was less than the MDD of 1.1 mR.
The quarterly doses in units of mR acquired at the special interest areas were as follows.
Station No.
Averaae Minimum Maximum l
33 19.7 18.4 22.3 34 18.4 17.1 21.2 35 18.1 16.3 21.2 43 14.8 13.9 15.6 The doses acquired at the special interest stations are seen to be somewhat typical and within the range of those acquired at the other stations.
4-5
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Listed below for the indicator, control and outer ring stations, as well as for the special interest areas, are the average levels in units of mR/91 days obtained during the CY 1988, CY 1987 and the entire period of preoperations along with the ranges of annual averages obtained during the calendar years of preoperations.
Preop Preop Group CY '88 CY '87 Overall Ranoes Indicator 16.8 17.6 15.3 15.1 - 16.9 Control 16.1 17.9 16.5 14.1 - 18.2 Outer Ring 16.0 16.7 14.7 12.5 - 16.2 l
No. 33 19.1 21.3 16.6 13.6 - 19.9 l
No. 34 18.4 20.1 15.1 12.5 - 18.1 No. 35 18.1 18.5 15.1 12.6 - 17.6 i
No. 43 14.8 15.2 15.3 13.9 - 25.0 Overall, the doses for CY 1988 were about 5% lower than those for CY 1987.
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I 4.3 Milk As indicated by Tables 2-1 and 2-2, milk is collected biweekly from two a
control locations, Dixon Dairy (No. 98) and the Boyceland Dairy (No.
99).
Gamma isotopic and I-131 analyses are performed on each sample.
Milk has not been available from an indicator station (a location within 5 miles of the plant) since April 1986 when the cow from which milk was being obtained went dry and was subsequently removed from the area. As indicated by Table 4-1, no milk animals were found in the land use census.
The availability of milk within 5 miles of the plant was meager throughout preoperations. Dixon Dairy is believed to be the closest location of milk animals to the plant.
As may be seen in Table 3-1, Cs-137 was found in three samples from Dixon Diary; the average level, was 6.9 pCi/1.
During CY 1987, positive results were found in two samples; the average level was about 50%
greater than that for CY 1988.' During reoperation when positive results were found in 3.6% of the samples, the average level was about 150% more'than that for CY 1988.
The LLD and RL.as required by the TS are 18 and 70 pCi/1, respectively.
During CY 1988, I-131 was not detected in any of the milk samples. The same was true for 1987. During preoperations, I-131 was detected only during the Chernobyl incident; the positive results ranged from 0.53 to 2.22 fCi/1.
The LLD and RL required by the TS are 1 and 3 pCi/1, respectively.
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4.4 Vegetation l
The TS call for the gamma isotopic analysis of grass or leafy vegetation collected monthly from two onsite locations near the site boundary (Stations 7 and 15) and one control location at about 15 or more miles from the plant (Station 37).
Grass is collected at each of these locations.
In January, leafy vegetation was also collected from a garden in a trailer park at 1.3 miles in the WSW Sector. Afterwards, samples became unavailable, as the garden's yield became scant.
Several samples had been collected at this location in CY 1987.
No gardens were found in the land use census where the calculated dose commitment would be 20%
greater than that of any of the other locations at which vegetation is being sampled.
As indicated in Table 3-1, Cs-137 was the only manmade radionuclides detected; it was detected only at the indicator stations. A comparison of the results for CY 1988 with those from CY 1987 and preoperations is l
as follows.
Indicator Stations Control Station 1
CY 1988 CY 1987 Preco.
CY 1988 CY 1987 Preco.
Average Level 38.7 24.4 54.6 0.0 61.5 43.7 (pCi/kg wet)
Fraction 0.280 0.318 0.573 0.000 0.250 0.193 The levels found at the indicator stations continue to be lower than those found during preoperations.
The LLD and RL are respectively 60 and 2000 pCi/kg wet.
J 4-8
1 4.5 River Water i
Surface water is composited from the Savannah River at three locations J
using ISCO autcmatic samplers.
Small quantities of river water are collected at intervals not exceeding a few hours.
River water collected by these machines is picked up monthly; quarterly composites are composed of the monthly collections.
The collection points consist of a q
control station (No. 82) which is located about 0.3 miles upriver of the plant intake structure, an indicator station (No. 83) which is located about 0.3 miles downriver of the plant discharge structure and a special station (No. 84) which is located about 1.4 miles downriver.
A gamma isotopic analysis was made on each monthly collection.
Like CY 1987, no manmade radionuclides were detected in CY 1988; this includes Be-7.
A tritium analysis was performed on each quarterly composite. A positive result was obtained from each analysis. As indicated in Table 3-1, the average level at the indicator station is 416 pCi/1 greater than that at the control station; this difference is discernable because it is greater than the MDD of 271 pCi/1. At Station 84, the results ranged from 900 to 2320 pCi/l with an average of 1430 pCi/1.
While the average level at the control location (Station 82) for the year was about 20% lower than that for CY 1987 and the average level at the indicator location (Station 83) was about 25% higher than that for CY 1987, the average level at Station 84 increased by only 1%. The average tritium levels obtained during the year at Stations 82, 83 and 84 were respectively 427, 843 and 1430 pCi/1.
The profile of increasing tritium level with downriver location is similar to that found during CY I
1987 and preoperations.
The LLD is 3000 pC1/1 an the RL is 10 times greater.
l On September 27 the annual survey of the Savannah River was conducted downriver of the plant for approximately 130 river miles to identify any parties who may use river water for purposes of drinking or irrigation.
The only parties found to be withdrawing river water for drinking purposes were the two downriver water treatment plants (Stations 87 and
- 88) from which samples are collected monthly. As in all previous surveys, no intakes for irrigation use were observed. On September 29, the survey results were corroborated by contacting the Georgia l
l Environmental Protection Division and the South Carolina Department of Health and Environmental Control; it was found that no new surface or drinking water withdrawal permits had been issued for the Savannah River during the previous 12 months.
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4.6 Drinking Water Samples were collected at a control station (No. 80), the Augusta Water Treatment Plant in Augusta, Georgia, which is located about 56 miles upriver and at two indicator stations (Nos. 87 and 88), the Beaufort-Jasper County Water Treatment Plant near Beaufort, South Carolina and the Cherokee Hill Water Treatment Plant near Port Wentworth, Georgia, which are respectively located about 112 and 122 miles downriver.
These upriver and downriver distances in river miles are the distances from VEGP to the point in the river where water is diverted to the intake for each of these water treatment plants.
At each of the water treatment plants, monthly collections were made of riverwater which was composited near the plant's intake (raw drinking water) and of grab samples of finished drinking water. Gross beta and gamma isotopic analyses were performed on each of the samples collected monthly. Tritium analyses were performed on the quarterly composites.
As indicated by Table 3-1, the average gross beta activity for raw drinking water was 0.3 pCi/1 greater for the control station than for the indicator si ations.
However, this difference was not discernable because it was less than the MDD of 1.4 pCi/1.
For finished drinking water, the average gross beta activity was 0.1 pCi/l greater for the control stations than for the indicator station.
This difference was not discernable because it was less than the MDD of 0.9 pCi/1.
Although no positive results were obtained from the gamma isotopic analyses of any of the monthly collections, positive results were obtained from the tritium analysis of each of the quarterly composites.
Furthermore, there was a discernable difference between the average tritium values for the two type stations for both the raw and finished l
drinking water since these differences were each greater than their l
MDDs.
As indicated by Table 3-1, the average values of the tritium levels for the indicator stations were 2390 and 2630 pCi/l greater than those for the control station for raw and finished drinking water respectively while the MDDs were correspondingly 580 and 830 pCi/1.
Similar results were obtained during both CY 1987 and preoperations.
Starting in June, I-131 analyses were also performed on the monthly samples of finished drinking water in addition to those specified in Table 2-1.
All results were below the minimum detectable activity (MDA) which ranged from 0.21 to 0.49 pCi/1.
4-10
i 4.7 Fish d
The TS call for the collection of at least one sample of any anadromous species of fish in the vicinity of the plant discharge during the spring spawning season.
The TS also call for semiannual collection! of any commercially r "reationally important species in the vicinity of the plant discharge.irea and in areas not influenced by plant discharge.
i Furthermore, the TS call for a gamma isotopic analysis on the edible i
portions of each sample collected.
About a five mile stretch of the eiver is generally needed to obtain adequate fish samples.
For the semiannual collections, the control station (No. 81) extends from approximately 2 to 7 miles upriver of the plant intake structure and the indicator station (No. 85) extends from about 1.5 to 7 miles downriver of the plant discharge structure.
For the anadromous species all collection points can be considered as j
indicator stations.
l On Marcn 1, American shad, an anadromous species, was collected at Station 86 but no positive results were obtained from the gamma isotopic analysis. A white bass (an extra sample), which is not an anadromous species but is recreationally important, was also collected at Station i
81 on this date; Cs-137 was found at a level of 54 pCi/kg wet. This value is below levels identified in control and indicator samples discussed below.
The result of this extra sample is not included in the summary listed in Table 3-1.
i On April 18 and October 24, the regular collection dates for the commercially or recreationally important species, the composition of the catches were as follows:
Ra_t_q Station 82 Station 85 April 18 Channel Catfish Red Breast Su Jish Largemouth Bass Redear Sunfish Redear Sunfish October 24 Chain Pickerel Largemouth Bass Channel Catfish Redear Sunfish Redear Sunfish L
As indicated in Table 3-1 Cs-137 was the only manmade radionuclida 3
(including Be-7) found in the commercially or recreationally impurtant species and it was found in each of the samples.
The average level for the indicator station, 65.8 pCi/kg wet is seen to be 49.9 pC1/kg wet 4
less than that for the control station but this difference is not discernable since the MDD is 137 pCi/kg wet. The fish caught at the
)
indicator station during CY 1987 had Cs-137 levels more than five times 1
those for CY 1988, while the levels for the control station were less than 3% greater. The LLD and RL as specified by the TS are 150 and 2000 J
pCi/kg wet, respectively.
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4.8 Sediment Sediment was collected along the shoreline of the Savannah River on April.18 and October 10 at Stations 81 and 83.
Station 81 is a' control station located about 2.3 miles upriver of the plant intake structure at RM 153.2 while Station 83 is an indicator station located about 0.7 miles downriver of the plant discharge structure at RM 150.2. A gamma l
isotopic analysis was performed on each sample.
Positive readings for Be-7 and Cs-137 were found in each sample as occurred in CY 1987 and the readings were en the same order as found in CY 1987. As may be noted in Table 3-1, there is a wide spread between the two readings for Be-7 at each station; the higher reading at each station was found with the October collections; the same phenomenon, albeit less pronounced, occurred CY 1987.
For Be-7, the average reading for the collections from the indicator station, 970 pCi/kg dry, is 160 pCi/kg dry greater than that for the control station; there is no discernable difference, however, since this difference is less than the MDD of 6534 pCi/kg dry.
For Cs-137 the average reading of 175 pCi/kg dry was the same for the collections from each station; the higher readings also were found in the October collections.
Also indicated in Table 3-1 is the presence of the activation products, Mn-54,Co-58 and Co-60 at the downriver station.
Positive results for Co-58 were found in both the April and October collections - the higher reading was for the October collection.
Positive levels for Mn-54 and Co-60 were found in the October collection only.
Each of these radionuclides are among the plant's liquid effluents.
During preoperations, positive levels of Mn-54 were found in sediment samples, both upstream and downstream.
Generally, these levels were slightly higher.than that listed in Table 3-1.
The levels in pCi/kg dry were as follows.
03/31/86 RM 150.2 37.3 10/13/86 RM 151.2 18.0 10/13/86 RM 153.2 25.0 Although Co-60 has not been found in sediment samples previously, by GPC, others have.
It is reported in Table 7-5 of the SRP Environmental Report for 1937 (DPSPU-88-30-1, Volume II, page 387) that the mean Co-60 level in sediment at RM 150.2 was 180 pCi/kg dry for 1977-1984.
Co-58 has not been found previously.
It is not known to have been found previously by others conducting a REMP in the Central Savannah River Area (C.SRA).
The presence of Co-58 in the sediment is likely due to liquid releases from the plants.
it is plausible that the presence of Mn-54 and Co-60 is also due to plant releases at least partielly so.
4-12
The radiological impact due'to readings of Mn-54, Co-58 and Co-60 in the shoreline sediment was assessed by calculating the whole body dose by direct radiation (from the sediment) to an individual using the methodology and parameters of Regulatory Guide 1.109, Revision 1,
)
October 1977 and comparing this dose with that permitted by.Section 3.11.1.2.b of the TS (3 mrem per' year). The theoretical dose was determined to be 0.0036 mrem per year or 0.12% of the TS limit. This J
extremely low dose, although calculable, poses no measurable negative
[
environmental or public health impact.
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5.0-INTERLABORATORY COMPARISON PROGRAM lL l
Section 3.12.3 cf the TS requires that analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Nuclear Regulatory Commission j
(NRC).
The Environmental Protection Agency's (EPA's) Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program conductsu by the Environmental Monitoring and Support Laboratory in Las j
Vegas, bevada provides such a program and the CL participates in the l
program. Analyses are performed only where the type analysis and sample 1
in the EPA Crosscheck Program are the same as that delineated in Table 2-1.
Reported herein, as required by Section 4.12.3 of the TS are the results of participation in the EPA Crosscheck Program by the CL.
Any results for which disagreement is established using the NRC's
" Criteria for Comparing Analytical Measurements", as described in to this section, requires an investigation to determine the cause of the disagreement and corrective actions as warranted to prevent a recurrence. The results of any such investigations and corrective i
actions would be reported in this section.
None of the comparisons
'i showed a disagreement.
The results of the gross beta and Cs-137 analyses of air filters are given in Table 5-1.
Listed in Table 5-2 are the results of the I-131 and gamma analyses of milk samples. Table 5-3 presents the results of the gross beta, gamma and tritium analyses of water.
Since all of the results reported herein are presented in the same tabular format, an explanation of the column headings is provided.
"Date" means the collection date given by the EPA. "Known" refers to the EPA known value one standard deviation, s.
" Result" is the average value measured by the laboratory experimental s.
" Resolution" is determined by dividing the known value by its s value.
" Ratio" equals the ".esult" (value determined by the laboratory) divided by the "known" (value determined by EPA). An explanation would have been provided if
~
any of the comparisons had shown " Disagreement."
It should be noted that whenever the EPA known value is zero or the laboratory-determined result is a less than (LT) value, or the calculated resolution value is less than 3, a comparison l,y the NRC criteria cannot be made.
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5-1
TABLE 5-1 CROSSCHECK PROGRAM RESULTS FOR AIR FILTERS (pCi/ filter)
Date Known Result Resolution Ratio Gross Bet _a 3/25/88 50' 5
47.0 0.0 10.0 0.94
'8/26/88 29 5
26.3 1.2 5.8 0.91 Cs-137 3/25/88 16 5
20.3 2.5 3.2 1.27
'8/26/88 12 5
13.0 1.0 2.4 1.08 I
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TABLE 5-2 CROSSCHECK PROGRAM RESULTS FOR MILK SAMPLES (pCi/1)
Date Known Result Resolution Ratio I-131 2/26/88 4.0 i 0.4 4.0 1.0 10.0 1.00 6/24/88 94.0 9.0 96.7 7.4 10.4 1.03 i
10/28/88 91.0 9.0 85.3 4.0 10.1 0.94 Cs-13Z 6/24/88 51.0 5.0 50.0 5.3 10.2 0.98 10/28/88 50.0 5.0 48.0 5.0 10.0 0.96 1
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TABLE 5-3 CROSSCHECK PROGRAM RESULTS FOR WATER SAMPLES l
(pCi/1)
Date Known Result Resolution Ratio l
l Gross Beta l
1/22/88 8.0 5.0 7.3 1.2 1.6 0.91 3/18/88 13.0 5.0 11.7 0.6 2.6 0.90 5/20/88 11.0 5.0 10.0 0.0 2.2 0.91 7/22/88 4.0 5.0 4.3 0.6 0.8 1.08 9/23/88 10.0 5.0 9.3 0.6 2.0 0.93 11/25/88 9.0 5.0 8.0 0.0 1.8 0.39 Cr-51 6/03/88 302.0 30.0 339.3 11.9 10.1 1.12 01/07/88 251.0 25.0 268.0 12.5 10.0 1.07 Co-60 2/05/88 69.0 5.0 66.0 2.0 13.8 0.96 6/03/88 15.0 5.0 15.3 1.5 3.0 1.02 10/07/88 25.0 5.0 23.7 2.5 5.0 0.95 Zn-65 2/05/88 94.0 9.4 86.7 4.0 10.0 0.92 6/03/88 101.0 10.0 106.0 9.9 10.1 1.05 10/07/88 151.0 15.0 140.7 5.8 10.1 0.93 Ru-106 2/05/88 105.0 10.5 109.0 13.5 10.0 1.04 6/03/88 195.0 20.0 214.0 20.8 9.8 1.10 10/07/88 152.0 15.0 135.7 19.9 10.1 0.89 Cs-134 2/05/88 04.0 2 5.0 H.0 1.7 12.8 0.84 6/03/38 20.0 5.0 20.0 5.3 4.0 1.10 10/07/68 25.0 5.0 25.7.4 1.2 5.0 1.03 Cs-137-2/03/88 94.0 1 5.0 90.0 6.6 18.8 0.96 6/03/85 25.0 5.0 22.0 5.0 5.0 0.88 10/07/88 15.0 5.0 13.7 3.5 3.0 0.91 5-4 a
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TABLE 5-3 (Continued)
CROSSCHECK PROGRAM RESULTS FOR WATER SAMPLES-(pCi/1)
Qa.t_q Known Result Resolution Ratio
-f H-3
-2/12/88 3327.0 i 362.0 3636.0 i 74.4 9.2 1.09 6/10/88 5565.0 557.0 5353.0 110.0 10.0 0.96 10/14/88 2316.0 350.0 2286.7
- 47.3 6.6 0.99 1
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__-__-_._____m____
.___.i___._m_._____________________.m._
ATTACHMENT 1 Criteria for Comoarina Analytical Measurements This attachment provides criteria for comparing results of capal,ility tests and verification. measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.
In these criteria, the judgment limits are variable in relation to the comparison of the Reference Laboratory's value to its associated one sigma uncertainty. As this comparison, referred to as " Resolution", increases, the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement should be considered acceptable as the resolution decreases.
The values in the ratio criteria may be rounded to fewer significant figures to maintain statistical consistency with the number af significant figures reported by the Reference Laboratory, unless such rounding will result in a narrowed category of acceptance.
The acceptance category I
reported will be the narrowest into which the ratio fits for the resolution being used.
RESOLUTION RATIO - LICENSEE VALUE/ REFERENCE VALUE Possible Possible Aareement Aareement "A" Aareement "B" LT 3 No Comparison No Comparison No Comparison GE* 3 and LT 4
0.4
- 2.5 0.3
- 3.0 No Comparison GE 4 and LT 8
0.5
- 2.0 0.4
- 2.5 0.3
- 3.0 GE 8 and LT 16 0.6
- 1.67 0.5
- 2.0 0.4
- 2.5 GE 16 and LT 51 0.75 - 1.33 0.6
- 1.67 0.5
- 2.0 GE 51 and LT 200 0.80 - 1.25 0.75
- 1.33 0.6
- 1.67 GE 200 0.85 - 1.18 0.80
- 1.25 0.75
- 1.33
- CE means greater than or equal to "A" criteria are applied to the following analyses:
Gamma spectroscopy where principal gamma energy l
used for identification is greater than 250 key.
Tritium analyses of liquid samples, i
"B" criteria are applied to the following analyses:
Gamma spectroscopy where principal gamma energy used for identification is less than 250 key.
Sr-89 r.nd Sr-90 determination.
Grnss beta where samples are counted on the same date using the same reference nuclide.
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6.0 CONCLUSION
S This rcport has shown the licensee's conformance with Section 3/4.12 of the TS dur ing the year.
It has shown that all data were carefully examined. A summary and a discussion of the results of the laboratory analyses for each type sample collected were presented.
i l
No measurable radiological impact upon the environment as a consequence of plant discharges to the atmosphere was established. Although low levels of Mn-54, C0-58 and Co-60 were identified in sediment samples collected downriver of the plant, and are assumed to be at least partially due to liquid effluents from the plant, evaluations show they pose no measurable negative impact upon the environment or public health.
The relevant comparisons of the analytical measurements made by the CL with those made by the EPA in the Crosscheck Program showed no disagreements.
6-1 I
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V V0GTLE ELECTRIC GENERATING PLANT - UNIT 1 NRC DOCKET NO. 50-424
(
FACILITY OPERATING LICENSE N0. NPF-68 ANNUAL ENVIRONMENTAL OPERATING REPORT FOR 1988 (NONRADI0 LOGICAL) 4 l
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O V0GTLE ELECTRIC GENERATING PLANT - UNIT 1 ANNUAL ENVIROP4 ENTAL OPERATING REPORT (N0NRADI0 LOGICAL)
SPECIFICATION In accordance with Section 5.4.1 of the Vogtle Electric Generating Plant Environmental Protection Plan (Nonradiological), Appendix B to Facility Operating License No. NPF-68, this report is submitted describing implementation of the Environmental Protection Plan for the calendar year 1988.
REPORTING REQUIREMENTS A.
Summaries and Analyses of the Results of the Environmental Monitoring Activities for the Report Period 1.
Aquatic Monitoring - Liquid effluent monitoring was performed in accordance with National Pollutant Discharge Elimination System (NPDES)
Permit No. GA0026786; there was no additional requirement for aquatic monitoring during 1988.
2.
Terrestrial Monitoring - Not required.
3.
Maintenance of Transmission Line Corridors a.
There was no herbicide use within the VEGP transmission line corridors during 1988.
b.
There was no clearing or maintenance activity within the Ebenezer Creel or Francis Plantation areas during 1988.
c.
Routine maintenance activities within the designated cultural properties along transmission line corridors were conducted in accordance with the Final Cultural Resource Management Plan.
4.
Noise Monitoring - There were no complaints received by Georgia Power Company during 1988 regarding noise along the VEGP-related high voltage transmission lines.
B.
Comparison of the 1988 Monitoring Activitics with Preoperational Studies, Operational Centrols, and Previous Mor,itoring Reports l
These comparisons were not required because no nonradiological monitoring l
pregrams were conducted during 1988.
C.
An Assessment of the Observed Imp nts of Plant Operation on the Environment l
l There was no signif'. cant adverse environm?ntal impact associated with plant operation during 1988.
l
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D.
Environmental Protection Plan (EPP) Noncompliance and Corrective Actions There were no EPP noncompliance during 1988.
E.
Changes in Station Design or Operation, Tests, and Experiments Made in Accordance with EPP Section 3.1 which Involved a Potentially Significant Unreviewed Environmental Question There were no changes in station design or operation, tests, or experiments during 1988 which involved a potentially significant unreviewed environmental question.
F.
Nonroutine Reports Submitted in Accordance with EPP Subsection 5.4.2 There were no nonroutine reports submitted during 1988.
1
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_ _ _ __ _ __ l l
. Alabama PowerCompany.
{
.3g
- 600 North 18th Strut i
Post Office Box 2641 i
Birmingham, Alabama 352910400 Telephone 205 250-1837 W. G. Hairston, lit Senior Vice President Nuclear Operations AlabamaPower the southern electrc systern March 29, 1989 10CFR50.59 i
Docket Nos. 50-348 l
U. S. Nuclear hegult'ory Commission ATTN:
Document Control Desk Vashington, D. C.
20555 Gentlemen:
Attached for your review is the annual report required by 10CFR50.59 for 1988. This report summarizes changes to the plant performed in accordance with the provisions of 10CFR50.59 for Joseph M. Farley Nuclear Plant Unit 1.
If you have any questions, please advise.
Respectfully submitted, h-W. G. Hairston, III VGH,III/JARidst-6.37 Attachment ec:
Mr. S. D. Ebneter Mr. E. A. Reeves Mr. G. F. Maxwell ud 0* $ 91?
1
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ALABAMA POWER COMPANY a
JOSEPH M. FARLEY NUCLEAR PLANT UNIT 1 - ANNUAL REPORT REQUIRED BY 10CFR50.59 Section 50.59 of Part 50, Licensing of Production and Utilization j
Facilities, of the regulations of the United St&tes Nuclear Regulatory i
Commission, states that the holder of a license authorizing operation of a production or utilization facility may (1) make changes in the facility as described in the safety analysis report, and (2) make changes in the procedures as described in the safety analysis report, and (3) conduct tests or experiments not described in the safety analysis report, without prior commission approval, unless the proposed change, test or experiment involves a change in the technical specifications incorporated in the j
license or an unreviewed safety question (as defined in 10CFR50.59).
The licensee is required to maintain records of such changes, tests or experiments, and those records are required to include written safety evaluations which provide the basis for the determination that the changes, tests or experiments do not involve any unreviewed safety questions.
Brief descriptions and a summary of the safety evaluations of the changes, tests or experiments as described above, for the Joseph M. Farley Nuclear Plant Unit 1 which were completed in 1988, are provided in the following.
Tech-Misc 3/4
Subject:
FNP-0-CCP-640, Revision 1
==
Description:==
Added the use of a windowed 2H internal proportional counter for radioactivity measurements at FNP.
Safety Evaluation:
The low background windowed 20 internal proportional counter is suitable for use in the same applications as the windowless 2H internal proportional counter currently being used. The windowed counter provides for improved accuracy, precision and sensitivity of gross activity measurements.
PORC Review:
PORC Meeting 1908, 8-4-88
Subject:
FNP-0-CCP-708, TCN 3F, TCN 4A
==
Description:==
TCNs 3F and 4A provided for the continuous chlorination of the service water systera using sodium hypochlorite to reduce the number of corbicula (clams) in the system. The addition of sodium hypochlorite will be limited to one unit at a time, while chlorine dioxide will be added to the opposite unit during the hypochlorination.
Safety Evaluation:
Sodium hypochlorite addition can be quickly terminated if deemed necessary.
Emergency actions and precautions already exist in this procedure. The use of both chlorine dioxide and sodium hypochlorite for prevention of fouling in the service water syste.m is already addressed in the FSAR.
PORC Review:
PORC Meeting 1799, 1/7/88 PORC Meeting 1864, 5/3/88
Subject:
FNP-1-ETP-3660, Revision 3
==
Description:==
Allowed the use of the ASEA Brown Boveri Failed Fuel Rod Detection System (FFRDS) to perform leak testing 4
of fuel assemblies.
Safety Evaluation:
The Brown Boveri FFRDS has been utilized by Westinghouse for fuel leak detection at various sites without detrimental effects to the fuel. The use of FFRDS has been determined to have no adverse impact on the safety of the plant.
PORC Review:
PORC Meeting 1842, 3/31/88 1
Tech Misc 3/2
,4
Subject:
FNP-1-M-046, Revision 1
==
Description:==
Revised valve closure times for certain containment isolation valves as stated in the FSAR so that they agree with the closure times stated in the Technical Specifications. Also, the valve closure times as stated in th? FSAR for certain steam generator blowdown isolation valves has been revised.
Safety Evaluation:
The revised closure times for the containment isolation valves do not violate accident analysis assumptions or Technical Specification requirements.
Also, the design organization has determined that the revised closure times are acceptable.
The revised closure times for the steam generator blowdown valves would result in a negligible change in the steam generator inventory during postulated accident conditions.
PORC Review:
PORC Meeting 1932, 10/11/88
Subject:
FNP-1-SOP-2.4, Revision 23
==
Description:==
Changed the normal position of the valves which route the equipment drain water and valve leakoff water to the recycle holdup tanks (RHT's).
Previously, the normal position of these valves (one f
valve per RHT) had been " locked open" for all three RHT's.
This sa.fety evaluation allowed the position of the valves for the off-scrvice RHT's to be changed to " locked closed".
Safety Evaluation:
This change prevents inadvertent water addition to the off-service RHT's.
Routing equipment drain and valve leakoff to one RHT instead of three has no operational consequences since normally this amount of water is insignificant when compared to the 28,000 gallca capacity of the RHT.
If the leakoff becomes abnormally high, routine operational monitoring would detect this inleakage prior to overfilling the tank.
PORC Review:
PORC Meeting 1874, 5/17/88 Tech Misc 3/2
Subject:
FNP-1-SOP-16.1, Revision 14
==
Description:==
Revised Appendix 1 to allow defeating the low service water dilution flow trip of 1-BD-RCV-023B during any mode of operation.
Safety Evaluation:
Service water dilution flow is continuously recorded in the main control room. When the trip is defeated, steam generator blowdown (SGBD) releases will be calculated and authorized on a batch release permit to ensure that the total dilution flow from both units is sufficient to prevent Technical Specification dose limits from being exceeded. SGBD 1
will be caution tagged to require that blowdown be secured if the minimum dilution of the release permit is not met. The total dilution flow will be logged every 15 minutes while the low flow trip is defeated.
Defeating the low service water flow trip does not affect the ability of RCV-023B to close on high SGBD activity.
PORC Review:
PORC Meeting 1939, 11/1/88
Subject:
FNP-1-SOP-23.0, TCN 18C
==
Description:==
Added an appendix to this procedure to provide guidance for performing a feed and bleed evolution on the component cooling water (CCW) system. This evolution will be performed by diverting approximately 20 gpm of CCW from the off-service CCW train through a portable demineralized package to the floor drain system.
Safety Evaluation:
This evolution will improve the chemical composition of the CCW system. CCW surge tank level indication will be monitored continuously using both trains of level indication.
Feed and bleed activities will be suspended if CCW surge tank level cannot be maintained within the desired range.
The normal off-service train CCW flow is approximately 3500 gpm. Thus, diverting approximately 20 gpm will not affect system flow significantly. During accident conditions the feed and bleed evolution will be terminated immediately.
Thus, CCW flow during a postulated accident will not be affected adversely.
j PORC Review:
PORC Meeting 1882, 6/6/88 i
)
3 i
Tech Misc 3/2 j
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P 4Subjsct:
FNP Emergrncy Plan, Rsvision 14, TCN 14B, cnd Revision 15
==
Description:==
Revision 14 to the Emergency Plan updated telephone directories, made title changes, and made other administrative changes. 'ICN 14B relocated an emergency cabinet in the control room. Revision 15 deleted the responsibilities of the Manager..- Nuclear Technical Support (MNTS) since.that position no longer exists. Further, changes were made to personnel designations for the Recovery Phase to use the available managers more efficiently.
Safety Evaluation:
The administrative changes of Revision 14 do not decrease the effectiveness of the emergency plan and the plan, as changed, will continue to meet the standards of 10CFR50.47(b) and 10CrR50 Appendix E.
With regard to TCN 14B, the contents and accessibility of the emergency cc
- 1. net will remain unchanged.
The responsibility formerly delegated to the MNTS was reassigned to the Manager - Nuclear Engineering and Licensing. All changes to position designations were reviewed to ensure that the qualifications necessary to hold the newly assigned positions are adequate.
PORC Review:
PORC Meeting 1795, 12/31/87 PORC Meeting 1945, 11/17/88 PORC Meeting 1953, 12/20/88 i
i 1
4
Subject:
MD 88-1812
==
Description:==
Changed the setpoints for the 1C diesel generator starting air pressure switches.
Safety Evaluation:
The revised setpoints give more air for starting the diesel generator as well as provide better indication of air pressure for the control room operator.
PORC Review:
PORC Meeting 1825, 3/4/88
Subject:
MD88-1838 1
==
Description:==
Authorized bypassing the auto shunt trip pushbutton on the "A" reactor trip breaker.
FSAR Section 7.2-30 will be updated to reflect this minor departure.
Safety Evaluation:
The auto shunt trip pushbutton is utilized only in testing of the reactor trip breaker.
By installing a jumper across the pushbutton, the jumper will provide the continuity normally provided by the pushbutton.
This minor departure changes the test features in that the test function is defeated. However, during normal operation, the tett feature is not necessary.
Procedural guidance ensures that the jumper is removed for testing the shunt trip feature.
PORC Review:
PORC Meeting 1819, 2/19/88
Subject:
MD G8-1841
==
Description:==
Authorized replacement of the Agastat relay with a new relay for 600 volt breaker EK02.
FSAR Figure 8.3-17 will be updated to reflect this replacement.
Safety Evaluation:
Replacement relays have a new part number. The replacement relay is similar to the device as required on the drawing and has nuclear grade documentation.
PORC Review:
PORC Meeting 1823, 3/2/88 l
i l
5 1
1
Subject:
==
Description:==
Authorized the installation of jumpers to allow the operation of the radwaste area exhaust fan with the supply fan out of service.
FSAR Section 9.4.3 will be updated to reflect this minor departure.
Safety Evaluation:
The purpose of the radioactive waste area ventilation system is to maintain temperature between 65'F and 110'F when outside air is between 20'F and 95'F.
While the supply fan is out of service the boric acid tank area temperature is to be monitored to ensure the temperature remains greater than 65' while the exhaust fan is being run. Also, the exhaust fans are required to be shut down when the outside air temperature is less than 20'F.
Appropriate doors between the radiation controlled area (RCA) and the outside air are opened to allow ventilation.
PORC Review:
PORC Meeting 1828, 3/9/88 PORC Meeting 1956, 12/29/88 i
Subject:
MD 88-1862
==
Description:==
Authorized the installation of a jumper to allow the operation of the containment purge exhaust fan with the containment purge supply fan out of service.
FSAR Section 6.2.3 will be updated to reflect this minor departure.
Safety Evaluation:
Operating the containment purge system without the supply fan in operation eliminates refiltering and heating of the air and requires an alternate air supply path. Neither the refiltering capability nor i
the heating function are safety concerns. Supply air i
to the containment is provided by maintaining tne equipment hatch, personnel access hatch, or other appropriate doors open.
PORC Review:
PORC Meeting 1840, 3/29/88 PORC Meeting 1842, 3/31/88 l
l l
6 Tech Misc 3/2 l
l 1
Subject:
MD 88-1869
==
Description:==
Authorized jumpering out high energy line break j
(HELB) contacts on the steam generator blowdown I
isolation valves to allow operation of the valves during modes 5 or 6.
FSAR Sections 3k.2.1, 3k.2.1.1 and 10.4.8 will be updated to reflect this minor departure.
Safety Evaluation:
Operation of these valves is needed to allow draining of the steam generators. The HELB sensors mitigate the consequences of a release of steam from the blowdown lines which contain high temperature, high pressure water during operating conditions.
In mode 5, the temperature of the reactor coolant system is required to be less than or equal to 200*F (lcss than or equal to 140"F for mode 6).
The steam generator secondary side is at atmospheric pressure during the draining process. Thus the high temperature, high pressure condition does not exist in modes 5 or 6.
PORC Review:
PORC Meeting 1850, 4/10/88
Subject:
MD 88-1915
==
Description:==
Replaced the carbon steel flanges in the component cooling water piping to the 1A, 1B, and 1C charging pumps' gear and bearing oil coolers with stainless steel flanges,. A small section of carbon steel piping was also replaced with stainless steel to facilitate this modification.
Safety Evaluation:
The stainless steel flanges and the small section of associated piping are made from steel of comparable tensile and yield strength with equal pressure and temperature ratings. The stainless steel flanges are geometrically identical to the carbon steel flanges so system flow characteristics will not be affected.
PORC Review:
PORC Meeting 1891, 6/24/88 s
i Tech Misc 3/2
4 0
Subject:
MD 88-1916
==
Description:==
Replaced the 75 foot sections of fire hose in fire hose cabinets D-108, D-122, and D-115 with 100 foot sections of fire hose.
Safety Evaluation:
The 100 foot length fire hoses in these cabinets is necessary to provide adequate fire fighting capability for these areas.
PORC Review:
PORC Meeting 1892, 6/28/88
Subject:
MD 88-1969
==
Description:==
Removed the internals from check valve Q1G22V009 to allow eductor flow from the recycle holdup tanks (RHT's).
Safety Evaluation:
The purpose of the check valve is to prevent suction pressure from passing to the discharge of the waste gas compressors when the system is shutdown. 'Ihe check valve is not necessary since the manual valve downstream of the check valve is normally closed except when educting RHT gas. Procedural guidance ensures the valve is closed upon completion of the eduction process.
PORC Review:
PORC Meeting 1942, 11/10/88 1
1 Tech Misc 3/2
Subject:
PCR/PCN 80-703 (B80-1-703)
==
Description:==
Replaced the volume control tank (VCT) purge flowmeter (FT-1094) and recycle holdup tank (RHT) eductor flowmeter (FT-252), which are both turbine type meters, with a variable area flowmeter (FT-1094) and a pressure transmitter (PT-252), respectively.
Safety Evaluation:
These changes will preide a more reliable indication of VCT purge flow and RHT eductor performance. This instrumentation does not have a safety function.
PORC Review:
PORC Meeting 1813, 2/9/88 PORC Meeting 1832, 3/18/88
Subject:
PCR/PCN 82-1236 (B82-0-1236)
==
Description:==
Replaced the control room air conditioning system fire dampers OsV49xV2782AC, AD, BC, and BD with Ruskin model FD-31 fire dampers. This change also removed the smoke release device (SRD) actuation circuits from the above referenced dampers and the control room pressurization system dampers OSV49xv2783A and B.
Also, the lower restraining flange for the FD-31 fire dampers was deleted.
Safety Evaluation:
The fire dampers were replaced because they would not l
close with normal air flow from the air conditioning unit. An engineering review performed by the design organization showed that the SRD circuit was not necessary.
PORC Review:
PORC Meeting 1728, 9/15/87 j
PORC Meeting 1805, 1/21/88
Subject:
PCN/PCN 83-1399 (B83-1-1399) l
==
Description:==
Replaced the existing battery pack type emergency lighting in containment with 30W incandescent lamp fixtures powered by two uninterruptible power supplies (UPS's) located outside of containment.
Safety Evaluation:
The previously existing lights, which were powered by battery packs, have experienced a short service life due to the high ambient temperature. The UPS's installed by this modification are outside containment where the temperature is lower. This change will upgrade emergency lighting in containment.
PORC Review:
PORC Meeting 1884, 6/9/88 l
9 Tech Misc 3/2
I
Subject:
PCR/PCN 83-1463 (B83-1-1463)
==
Description:==
Complete the installation of the Combustion Engineering inadequate core cooling monitoring system (ICCMS).
Installed by this design change are:
- Environmentally qualified connectors for the core exit thermocouple (CET's) at the reactor and mineral insulated transition cables to connect with existing cables.
- Train oriented CET displays on the main control board.
- Subcooling margin inputs to the ICCMS processor.
I i
- Train oriented subcooling margin displays on the j
main control board. The existing subcooling margin j
monitors are to be removed.
4 Safety Evaluation:
This upgrades the CET system to Regulatory Guide 1.97 Category 1 requirements. This new system will t
provide the operator with the required information to monitor core cooling.
Implementation of this design change will not adversely affect any other system.
The capability to monitor conditions in the reactor vessel will be enhanced.
PORC Review:
PORC Meeting 1760, 11/3/87
Subject:
PCR/PCN 84-2866 (B84-1-2866)
==
Description:==
Installed a new 3 inch gate valve (N1G21V915) between the containment sump pumps and containment isolation valve HV-3376 outside the bio-shield. Also, installed a new vent valve (N1G21V916) between N1G21V915 and HV-3376.
Safety Evaluation:
These changes result in reduced radiation exposure to plant personnel.
PORC Review:
PORC Meeting 1748, 10/15/87
Subject:
PCR/PCN 84-2914 (S84-1-2914)
==
Description:==
Replaced various portions of small (2 inch diameter and under) carbon steel service water pipe. The replacement piping is stainless steel. Also, valves l
and flanges were added ur replaced as required to l
enhance maintenance and cleaning of the service water piping.
l 4
10 Tech Misc 3/2
Safety Evaluation:
Replacing the carbon steel pipe with stainless steel pipe reduces corrosion'and provides for enhanced service water flow. Other changes to the service water system, such as adding flanged connections and adding or replacing valves will make the service water system more reliable and easier to maintain.
The added components are consistent with the design and safety requirements of the service water system.
PORC Review:
PORC Meeting 1563, 9/2/86 PORC Meeting 1568, 9/16/86 i
PORC Meeting 1690, 6/23/87 PORC Meeting 1728, 9/15/87 PORC Meeting 1810, 2/2/88 PORC Meeting 1904, 7/22/88
Subject:
PCR/PCN 84-2923 (S84-1-2923)
==
Description:==
Provided the design for the installation of a separate sensing line from each instrument air receiver to its compressor control station air pressure switch.
Safety Evaluation:
A separate sensing line will provide for the proper unloading and loading of the compressor in the receiver mode.
PORC Review:
PORC Meeting 1644, 3/3/87
Subject:
FCR/PCN 84-2989 (S84-1-2989)
==
Description:==
Assigned total plant numbering system (TPNS) numbers to the instrument air drain valves.
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1900, 7/12/88 i
Subject:
PCR/PCN 85-3117 (S85-1-3117)
==
Description:==
Raised the setpoint of the boric acid batching tank high temperature alarm from 100'F to 120'F. This will prevent erroneous alarms during the summer
{
months due to high ambient temperatures.
Safety Evaluation:
This alarm switch provides no control function and serves as an annunciator only. By raising the setpoint from 100'F to 120'F, the batching tank high temperature alarm can indicate potential problems to operating personnel.
PORC Review:
PORC Meeting 1900, 7/12/88 j
11 Tech Misc 3/2 I
l 1
Subject:
PCR/PCN 85-3167, (B85-0-3167)
==
Description:==
Replaced the spent fuel cask crane's stainless steel, non-lubricated hoist rope with a lubricated, carbon steel main crane hoist rope.
Safety Evaluation:
The original purchase specification for the cask crane called for a stainless steel, non-lubricated hoist rope but the manufacturer was unable to supply this. Substitution of a lubricated, carbon steel rope was proposed by the manufacturer and approved by Alabama Power Company before delivery of the crane.
The verbage in the FSAR was updated to reflect this but a figure in the FSAR had not been updated.
PORC Review:
FORC Meeting 1908, 8/4/88
Subject:
PCR/PCN 85-3297 (S85-1-3297)
==
Description:==
Assigned TPNS numbers to the main condenser basket tip connections. These connections were installed to facilitate local readings of condenser vacuum for daily calorimetric and routine testing.
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1491, 2/20/86
Subject:
PCR/PCN 85-3351 (S85-1-3351)
==
Description:==
Replaced the existing digital electro-hydraulic (DEH) turbine control system with a state-of-the-art microprocessor based DEH III turbine control system.
Safety Evaluation:
The replacement DEH III system will provide for better control of the turbine, as well as improve plant availability, avoid maintenance downtime and provide operating flexibility. This will not adversely affect safe operation of the plant.
PORC Review:
PORC Meeting 1827, 3/8/88 12 Tech Misc 3/2
'Subjset:
PCR/PCN 85-3431 (B85-1-3431)
==
Description:==
Partial modification to the radiation access control area.
Safety Evaluation:
This modification allows for more effective use of the space and facilities available in the access control area.
It provides separate men's and women's hot showers and toilets, a janitor's closet, and a wonen's toilet outside the radiation controlled area.
PORC Review:
PORC Meeting 1535, 6/17/86 1
Subject:
PCR/PCN 85-3431 (S85-1-3431)
==
Description:==
Provide fire protection coverage (system 1A-52) to the newly modified radiation access control area.
Three sprinkler heads were installed and the suppression coverage for the disrobe area and Room 4
438 was removed.
Safety Evaluation:
These modifications do not degrade the capability of the fire protection system to perform its intended function of prctecting safety related or safe-shutdown related equipment during a fire.
Additionally, the failure of the non-seismic portions of system 1A-52 during a seismic event has been determined not to cause a failure of safety related cabling located above the fire protection piping or the seismically designed portions of system 1A-52.
The removal of suppression coverage from the disrobe area and Room 438 is acceptable because the remaining combustible loading is insignificant in quantity and no change to fire detection has been made by this modification. The modification of the sprinkler system will enhance sprinkler coverage of the women's toilet, the men's toilet, and the janitor's closet.
PORC Review:
PORC Meeting 1538, 6/27/86 l
I
)
13
l j
j l
Subject:
PCR/PCN 86-3542 (B86-1-3542)
==
Description:==
Installed a pressure switch to control the power to the carbon monoxide (CO) monitor for the breathing air system. This pressure switch will turn off the power to the monitor if the pressure in the sample line drops below 20 psig.
)
Safety Evaluation:
This change will extend the life of the CO monitor sensing heads. The CO monitor does not have any l
nuclear safety functions.
l FORC Review:
PORC Meeting 1790, 12/17/87
Subject:
PCR/PCN 86-3544 (B86-1-3544)
{
{
==
Description:==
Provided for automatic sequencing of swing battery charger 1C to the diesel generators for a loss of site power (LOSP).
Safety Evaluation:
This change will eliminate operator action required during the shutdown of the plant following a LO3P, should battery charger 1C be in operation. As such, the safe shutdown capability of the plant will be enhanced.
PORC Review:
PORC Meeting 1712, 8/7/87
Subject:
PCR/PCN 86-3545 (B86-1-3545)
==
Description:==
Replaced the existing 3/8 inch valves on the blowdown lines for steam generator blowdown transmitters FT1171, FTll72 and FT1173 with 1/2 inch gate valves.
Also, a new 3/8 inch instrument valve was installed in each line. These instrument valves will be open normally.
Safety Evaluation:
These changes will alleviate the problem with the isolation valves becoming plugged and inoperable.
1 Leaving the instrument valves open will prevent them from becoming clogged.
PORC Review:
PORC Meeting 1748, 10/15/87 l
1 l
1 14 j
Tech Misc 3/2 l
1
Subject:
PCR/PCN 86-3681 (B86-1-3681)
==
Description:==
Replaced cable and connectors associated with the control rod drive modules and the digital rod position indication system.
Safety Evaluation:
This change upgraded the previously existing cable and connectors with equipment that is less susceptible to wear and reduced the potential for loose connectors. Testing was performed to ensure that design requirements are satisfied.
POFC Review:
PORC Meeting 1837, 3/25/88 l
PORC Meeting 1848, 4/7/88 PORC Meeting 1866, 5/5/88 PORC Meeting 1874, 5/17/88
Subject:
PCR/PCN 86-3692 (B86-1-3692)
==
Description:==
Upgraded the existing capacity of the new fuel monorail hoist from 2000 pounds to 2500 pounds. This modification involved the installation of a new motor, load block, hoist cable, and capacity plates.
Safety Evaluation:
This upgrade is needed in order to utilize the new fuel monorail to lift the ceiling hatches which weigh about 2400 pounds each. A structural evaluation was performed to ensure that the increased lift capacity would not impart an unacceptable lifting load on the new fuel storage racks.
It has been concluded that the new fuel storage racks are capable of withstanding lifting loads in excess of the new hoist capacity of 2500 pounds without failure.
PORC Review:
PORC Meeting 1715, 8/13/87
Subject:
PCR/PCN 86-3727 (586-1-3727)
==
Description:==
Changed the reducer on the condenser tube plate seal water system from a welded type to a screw type and installed a union fitting upstream of the reducer.
Safety Evaluation:
The condenser seal water system has no safety function. The system is low temperature and low j
pressure so a leak or rupture would have a minimal effect on plant operation.
[
l PORC Review:
PORC Meeting 1902, 7/19/88
[
l i
l 15 l
Tech Misc 3/2 l
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_.___________-___.__m_
Subject:
PCR/PCN 86-3739 (S86-1-3739)
==
Description:==
Revised drawing D-170807 sheet 2 of the air start system for diesel generator 2C to show the as-built valve orientation.
Safety Evaluation:
Drawing change only. The as-built valve orientation is correct for proper system operation.
PORC Review:
PORC Mceting 1902, 7/19/88
Subject:
PCR/PCN 86-3779 (S86-1-3779)
==
Description:==
Revised drawing D-175042 sheet 6 to delete a redundant hydrogen supply line. This line was never installed in the plant and is not needed.
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1902, 7/19/88
Subject:
PCR/PCN 86-3802 (S86-1-3802)
==
Description:==
Changed two B-train service water pond temperature transmitters from "Q" (safety-related) to "N" (non-safety related). The existing transmitters were replaced with high quality non-safety related transmitters. Also, new TPNS numbers were provided for the thermowells and elements associated with these transmitters.
Safety Evaluation:
There are redundant temperature indicators on each train for both units. Therefore, there is sufficient redundancy to ensure that reliable service water pond temperature indication is available in the control room. These transmitters are not required for post-accident monitoring and are not required to function following a seismic event. The pressure retaining capability of the service water system will j
not be affected.
j PORC Review:
PORC Meeting 1818, 2/16/88 f
16 l
Tech Misc 3/2 l
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l
'Subjcct:
PCR/PCN 86-3826 (S86-1-3826) i.
==
Description:==
Revised drawing D-175033 sheet 1 to show the previously installed steam generator (S/G) level transmitters LT-473 (S/G 1A), LT-483 (S/G 1B) and LT-493 (S/G 1C).
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1902, 7/19/88 l
Subject:
PCR/PCN 86-3836 (B86-1-3836)
==
Description:==
Provided the design for the installation of the Westinghouse anticipated transient without scram mitigation system actuation circuitry (AMSAC) electronics cabinet and two output relay panels, the addition and installation of new pressure transmitters and their associated signal conditioning circuits, as well as the AMSAC interfaces with the existing plant equipment and new pressure transmitters.
Safety Evaluation:
AMSAC is a system which provides an alternate means for tripping the turbine and initiating auxiliary feedwater flow.
It is diverse and independent from the existing reactor protection system (RPS) and was developed in response to NRC requirements and 10CFR50.62. The addition of the AMSAC system enhances the safe shutdown capability of the plant.
PORC Review:
PORC Meeting 1712, 8/7/87 subject:
PCR/PCN 86-3896 (S86-1-3896)
==
Description:==
Revised drawings A-170255 sheet 9, B-170249 sheet 7 and D-170114 sheet 2 to reflect the replacement of a Leeds and Northrup model 1971 flow transmitter. The replacement of the transmitter had been accomplished by Minor Departure From Design 86-1610.
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1902, 7/19/88 17
~
Subj:ct:
PCR/PCN 66-3911 (B86-1-3911)
==
Description:==
Replaced the existing containment temperature monitor (TISH-3192) and containment temperature recorder (TR-3188) with a Honeywell digital recorder, q
Safety Evaluation:
The previous monitor was obsolete and replacement parts could not be purchased. The new Honeywell recorder will provide all the functions that the previous monitor and recorder provided. The new recorder will give the plant operator more versatility and convenience.
PORC Review:
PORC Meeting 1711, 8/4/87
Subject:
PCR/PCN 87-3962 (S87-1-3962)
==
Description:==
Revised drawings D-177025 and D-181747 to correct the TPNS number on breaker #5 and the loads on breakers 7, 13, 15 and 16,n 120V AC Distribution Panel 1K.
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1925, 9/22/88
Subject:
PCR/PCN 87-3975 (B87-1-3975)
==
Description:==
Added an indicator on the main contro) board to provide indication of total auxiliary feedwater flow.
Safety Evaluation:
This modification provided a reliable control room indication of total auxiliary feedwater flow on the main control board. This enables the plant operator to take action based on total auxiliary feedwater flow during emergency conditions as directed by Emergency Operating Procedures.
PORC Review:
PORC Meeting 1787, 12/10/87
Subject:
PCR/PCN 87-3977 (B87-1-3977)
==
Description:==
Revised Figure 9.5-6 of the FSAR to show the newly modified Gai-Tronics public address station at the main control board.
j t
Safety Evaluation:
This modification enhances the control room public address system.
PORC Review:
PORC Meeting 1818, 2/16/88 l
18
{
j
Subject:
PCR/PCN 87-4018 (S87-1-4018)
==
Description:==
Revised drawing D-170119 to show the installation of stainless steel piping between the service water.
I minimum flow bypass line 8-HBC-214 and valve Q1P16V639. The installation was performed by Minor Departure From Design 86-1541.
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1902, 7/19/88 l
Subject:
PCR/PCN 87-4052 (B87-1-4052) l
==
Description:==
Added header isolation valves to the 2.5, 3 and 4-inch service water branch lines to safety related coolers in the Auxiliary Building. This will l
facilitate the subsequent replacement of the carbon l
steel branch header piping with stainless steel ii P P ng.
Safety Evaluation:
The addition of the header isolation valves will facilitate individual cooler isolation without having l
the service water system out of service. The replacement of this piping will improve the performance of these coolers and the service water j
system. This modification has no impact on the safe shutdown capability of the plant.
PORC Review:
PORC Meeting 1823, 3/2/88
Subject:
PCR/PCN 87-4076 (B87-1-4076)
==
Description:==
Replaced the existing Type 4LCY-5 batteries with Type 4LCY-420 batteries for the turbine driven auxiliary feedwater pump (TDMWP) uninterruptible power supply (UPS).
-Safety Evaluation:
The replacement battery has at least the same capacity as the existing battery. Therefore, the operation of the TDAFWP UPS is not affected and the safe shutdown of the plant will not be adversely affected.
l PORC Review:
PORC Meeting 1858, 4/22/88 19 Tech Misc 3/2
Subject:
PCR/PCN 87-4084 (S87-0-4084)
==
Description:==
Revised drawing D-170084 (site plot plan) to remove reference to Units 3 and 4.
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1938, 8/4/88
Subject:
PCR/PCN 87-4093 (S87-1-4093)
==
Description:==
Revised drawings D-170117 and D-170149 to designate the drain lines on the suction of the condensate pumps as an alternate means to add boric acid and other chemicals to the steam generators.
Safety Evaluation:
Drawing change only.
PORC Review:
PORC Meeting 1902, 7/19/88
Subject:
PCR/PCN 87-4099 (B87-1-4099)
==
Description:==
Modified the internals lifting rig to improve the method of latching the rig to the internals. The modification includes the addition of a triangular work platform with handrails at the top of the rig.
This platform is used to support three remote operating tools for latching to the internals. Also included in the modifications are removal of the protective ring pick-up assemblies and modification of the torque tube assemblies and tool engagement indicators.
Safety Evaluation:
This modification did not affect the safe operation of the internals lifting rig. The modification improved the method of latching the lift rig to the reactor vessel internals.
PORC Review:
PORC Meeting 1800, 1/12/88 PORC Meeting 1834, 3/22/88 l
j 20 1
Tech Misc 3/2
'Subj ct:
PCR/PCN 87-4143 (S87-0-4143)
==
Description:==
Revised drawings D-170119 and D-200013 to show the correct safety class boundary and location. Line No.
30 HBC-208 was changed from non safety related to a safety class 2B and line No. 24 HBC-209 was changed from safety class 2B to a non safety related line.
Also, the safety class symbol for line No. 30 HBC-211 at valve OlP16v550 was rotated 180a.
Safety Evaluation:
Drawing change only PORC Review:
PORC Meeting 1902, 7/19/88
Subject:
PCR/PCN 87-4227 (B87-1-4227)
==
Description:==
Replaced the existing bolts on all three steam generator primary manway covers with a stud and nut arrangement.
Safety Evaluation:
The replacement studs and nuts are sized to require no modification of the covers, gaskets, or the threaded holes in the steam generator. The design, fabrication, materials, and inspection of the studs and nuts meet ASME Boiler and Pressure Vessel Code requirements as specified in the reference drawings.
The loads on the studs, nuts, washers, covers, gaskets, and the steam generator have been evaluated as acceptable. The stresses due to the preload on the studs and design loads of the steam generator are determined to be less than the allowable limits as specified in Section III of the ASME Code. Also, studs of a similar design have been assessed to have a fatigue life equal to or greater than the fatigue life of the original bolts.
PORC Review:
PORC Meeting 1790, 12/17/87 Sibject:
PCR/PCN 87-4229 (B87-1-4229)
==
Description:==
Installed an additional walkway and handrail on the drive motor side of the manipulator bridge crane to provide for safer access to the drive motor area.
21
Safety Evaluation:
This modification enhances the safety of personnel who need to access the manipulator crane drive line or operate the crane manually. A seismic evaluation of the crane with the added walkway was performed.
The evaluation concluded that safety related equipment will not be degraded as a result of seismically induced loads on the crane.
PORC Review:
PORC Meeting 1804, 1/19/88
Subject:
PCR/PCN 87-4255 (B87-1-4255)
==
Description:==
Installed a two-hour, 30 KVA uninterruptible power supply (UPS) for the new plant computer. This involved the modification of the ventilation system in rooms 463 and 464 due to the increased heat loads in the rooms. The modification in the ventilation system included the installation of a computer UPS supply fan, a computer UPS primary exhaust fan, and a computer UPS secondary exhaust fan.
Safety Evaluation:
The computer UPS configuration is non-safety related.
Rooms 463 and 464 located in the Auxiliary Building fall within the boundaries of the non-radwaste area ventilation system. This is not an engineered safeguard system and no credit is taken for its operation in analyzing the consequences of any accident. A fire analysis was performed and the results indicated that this modification will not decrease the effectiveness of the fire protection program.
PORC Review:
PORC Meeting 1805, 1/21/88 PORC Meeting 1837, 3/25/88
Subject:
PCR/PCN 87-4271 (B87-1-4271)
==
Description:==
Replaced the existing manipulator crane Dillon load control system with a computer controlled load control system. The'new system has data collection capabilities and improved control for reducing fuel assembly grid strap damage during fuel movement.
Safety Evaluation:
This system allows monitoring and controlling of actual loads, plus providing a historical record of the loading on fuel handled by the machine.
It automatically compensates for the constantly changing resistance to movement as the fuel assembly is raised or lowered, keeping the overload or underload trip limit on the fuel at a constant value.
PORC Review:
PORC Meeting 1827, 3/8/88 22 Tech Misc 3/2
Subject:
PCR/PCN 87-4353 (B87-1-4353)
==
Description:==
Removed two excess flow check valves Q1E21V398 A and B from the chemical and volume centrol system letdown line.
Safety Evaluation:
Other valves (HV-8175 A and B) are available to isolate the letdown line in case the line ruptures.
Analyses showed that removal of the excess flow check valves will not adversely impact any affected area of the plant.
PORC Review:
PORC Meeting 1830, 3/15/88
Subject:
PCR/PCN 87-4452 (B87-1-4452)
==
Description:==
Installed a flow interrupter downstream of fire damper 1-116-15. Also, a plexiglass viewing window was installed to allow the flow interrupter to be seen without opening the duct.
Safety Evaluation:
The flow interrupter enhances fire isolation capability by actuating in advance of the fire damper thus allowing the fire damper to close under no-flow conditions. The installation of the plexiglass viewing window increased the fire loading in the area but it is still under the limit for a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> fire severity rating.
PORC Review:
PORC Meeting 1818, 2/16/88 PORC Meeting 1823, 3/2/88
Subject:
PCR/PCN 87-4490 (B87-1-4490)
==
Description:==
Replaced the pipe spools on the service water piping to the containment air coolers with flexible hose assemblies to reduce the loads on the containment air cooler nozzles.
Safety Evaluation:
The use of flexible hose assemblies has been evaluated and it has been determined that all containment air cooler nozzle loads are within the maximum limits provided by the cooler manufacturer.
PORC Review:
PORC Meeting 1829, 3/11/88 3
i 23 Tech Misc 3/2
l l
- Subj;ct:
PCR/PCN 88-4763 (B88-1-4763) i
==
Description:==
Removed a section of the boron injection tank (BIT) bypass line and installed pipe caps on the line.
Also, the normal position of the BIT bypass valve was changed from " locked closed" to " closed".
Safety Evaluation:
With the elimination of the high concentration boric acid from the BIT, the BIT bypass line is no longer needed. This modification will eliminate the potential for leakage of normal charging past the BIT bypass valve into the reactor coolant system via the safety injection piping. The leakage could cause thermal cycling of the safety injection lines. Also, changing the designation of the BIT bypass valve from
" locked closed" to " closed" will not prevent it from maintaining the safety injection system pressure boundary.
PORC Review:
PORC Meeting 1823, 3/2/88 PORC Meeting 1851, 4/12/88
Subject:
PCR/PCN 88-4826 (B88-1-4826)
==
Description:==
Installed lockable wire mesh fences and barriers to prevent inadvertent and unauthorized entry into the spent fuel pool (SFP) demineralized room (Room 449) the SFP valve room (Room 450), and the SFP filter room, (Room 451). These rooms are classified as exclusion areas due to radiological conditions.
Also, lead blankets were placed between rooms 449 and 450 to prevent reaching 1 g/hr on the outside of the new exclusior. area barrier.
Safety Evaluation:
This modification allows for administrative control of these exclusion areas. Seismic considerations and the added fire loading as a result of this modification have been evaluated.
It is concluded that the installation of these barriers does not affect the safe shutdown of the plant.
PORC Review:
PORC Meeting 1916, 8/23/88 PORC Meeting 1936, 10/25/88 j
l 24 l
1 L
Subject:
PCR/PCN 88-4848 (B88-1-4848)
==
Description:==
Installed barriers to prevent inadvertent or unauthorized entry into the primary spent resin storage tank room.
Safety Evaluation:
This modification allows for administrative control of this area. The installation of these barriers does not affect the safe shutdown of the plant.
PORC Review:
PORC Meeting 1925, 9/22/88
Subject:
PCR/PCN 88-4858 (B88-1-4858)
==
Description:==
Installed barriers to prevent inadvertent or unauthorized entry into the secondary spent resin storage tank room.
l l
Safety Evaluation:
This modification allows for administrative control of this area. The installation of these barriers does not affect the safe shutdown of the plant.
PORC Review:
PORC Meeting 1925, 9/22/88
Subject:
PCR/PCN 88-4979 (B88-1-4979)
==
Description:==
Installed a water loop seal in the piping between the residual heat removal heat exchanger and the suction of the charging pumps. Also, two new vent valves were installed.
Safety Evaluation:
The purpose of these modifications is to mitigate the accumulation of gas at the suction of the charging pumps. The loop seal is intended to prevent the migration of gas to the charging pump suction. The vent valves allow venting of accumulated gas from the piping. There will be a negligible effect on the normal operation of the charging pumps. The modification complies with all applicable safety codes.
PORC Review:
PORC Meeting 1851, 4/12/88 25 Tech Misc 3/2
1 I
Subject:
PCR/PCN 88-4997 (S88-1~4997)
==
Description:==
Replaced i.he spargers on the steam generator feed pump recirculation lines. The supports for the spargers were also modified.
{
(
Safety Evaluation:
The previous spargers were found to be severely J
damaged. The revised design can better withstand the
{
effects of a pressure transient in the system.
1 PORC Review:
PORC Meeting 1852, 4/14/88
Subject:
PCR/PCN 88-5003 (B88-1-5003)
==
Description:==
Reduced the turbine driven auxiliary feedwater pump (TDAEWP) overspeed trip setpoint from 125% to 115% of rated speed.
Safety Evaluation:
The potential exists for overpressurizing portions of the TDAFWP discharge piping if the pump speed exceeds 115% of rated speed with the pump operating near minimum flow conditions. Tests were conducted to ensure that the reduction of the trip set point did not lea.d to spurious trips. Normal operating characteristics of the pump were not affected.
PORC Review:
PORC Meeting 1867, 5/6/88 26 Tech Misc 3/2
l.
- Subjset:
'FSAR Update, Ravision 6
==
Description:==
Annual updating of the FSAR as required by 10CFR50.71(e).
Safety Evaluation:
All changes have been reviewed to insure that they do not adversely affect the safe operation of FNP.
These changes were found not to involve any unreviewed safety questions.
PORC Review:
PORC Meeting 1896, 7/1/88
Subject:
FSAR PC 88-05
==
Description:==
Broaden the scope of existing health physics training as stated in section 12.2.5.2 of the FSAR.
Safety Evaluation:
To make the FSAR consistent with the requirements of 10CFR19.12. This modified training commitment does not involve an unreviewed safety question.
PORC Review:
PORC Meeting 1896, 7/1/88
Subject:
FSAR Section 17.2
==
Description:==
Added a footnote to FSAR Section 17.2 to note an exception that the independent review and audit group (the NORB) shall consist of at least four persons, vice the five required by ANSI N18.7-1972.
Safety Evaluation:
This FSAR change does not change the minimum number of NORB members as required by the FSAR or Technical Specifications, it only notes an exception taken to ANSI N18.7-1972.
PORC Review:
PORC Meeting 1911, 8/11/88
Subject:
FSAR Section 98.1
==
Description:==
Clarified the status of Appendix 9B of the FSAR. The existing Unit 1 and Unit 2 fire protection license conditions reference the Fire Protection Program Reevaluation (FPPR) as the licensing basis. However, since July 1987, Appendix 9B of the FSAR has been the current document describing the fire protection program.
27 I
__ _ _ a
Safety Evaluation:
This resolves any ambiguity by explicitly stating that Appendix 9B embodies the FPPR. Appendix 9B was created in response to the requirements of Generic Letter 86-10. This does not decrease the effectiveness of the FNP fire protection program.
PORC Review:
PORC Meeting 1915, 8/17/88
Subject:
Changes Made to the FPPR to Create Appendix 9B of the FSAR
==
Description:==
Documented the bases for several items in Appendix 9B of the FSAR. Prior to 1987, the FNP fire protection program had been documented in the Fire Protection Program Reevaluation (FPPR). This document has been incorporated into the FSAR (as Appendix 9B) in accordance with Generic letter 86-10. This safety evaluation documents the change made to each section of the FPPR prior to incorporation into the FSAR.
Safety Evaluation:
Information in the FPPR was changed to be in a format consistent with the FSAR. Bases for each change were stated. These changes do not decrease the effectiveness of the FNP fire protection program.
PORC Review:
PORC Meeting 1928, 9/17/88 The following five safety evaluations document other changes to the information in the FPPR.
Subject:
FSAR Section 9B, Attachment A
==
Description:==
A conservative method has been used to calculate the fire loading due to cable insulation. This method was documented in a safety eva.:uation which was approved by the PORC previous?y. However, the effects of the new methods up]n the Appendix R exemptions had not been evaluated. This safety evaluation considers the effects that an increase in fire severity would have on the fire protection program including the exemptions granted by the NRC.
Safety Evaluation:
Some rooms did not have an exemption. Also, some exemptions were not based on fire severity. The fire loading of many of these rooms is primarily uue to cable insulation which has a relatively slow rate of heat release. Typically, the rooms are provided with fire suppression systems which are designed for a high rate of heat release. Therefore, the fire suppression systems are adequate to protect the rooms.
28 Tec.h Misc 3/8
1 For other rooms, the actual fire severity is not greater than the fire severity stated in the exemption requests. Therefore, the present fire protection measures are adequate.
PORC Review:
PORC Meeting 1928, 9/27/88
\\
l
Subject:
FSAR Section 9B.4.1.6
==
Description:==
Compressible material (self expanding cork) is used I
to isolate the Auxiliary Building from the i
containment Building. The FPPR originally stated that the compressible material is covered with a half-hour rated fire blanket in areas where the compressible material forms a part of a fire r.ea boundary. This statement was deleted when the FPPR was incorporated into the FSAR because the statement is not accurate.
Safety Evaluation:
The statement was inadvertently incorporated into the FPPR. However, APCo has concluded and documented to the NRC that the absence of a half-hour rated fire barrier does not decrease the effectiveness of the fire protection program. Testing has indicated that the cork will act as an adequate fire barrier.
PORC Review:
PORC Meeting 1928, 9/27/88
Subject:
FSAR Section 98.4.2.5
==
Description:==
The rPPR had stated that the Turbine Building is separated from the rest of the plant by a 3-hour rated fire wall and that tSe Turbine Building contains no equipment necessary for safe shutdown.
These statements were modified when the FPPR was incorporated into the FSAR since the statements are not totally correct.
Safety Evaluation:
Should a fire originate in the Turbine Building, safe shutdown can still be accomplished using safe shutdown equipment located in the Auxiliary Building.
The propagation of a fire from the Turbine Building to the Auxiliary Building is not considered credible.
PORC Review:
PORC Meeting 1928, 9/27/88 29 Tech Misc 3/8 i
4
Subject:
FSAR Section 9B.4.1.19
==
Description:==
The FPPR had stated that all areas of the plant requiring personnel occupancy to bring the plant to safe shutdown were provided with 8-hour i
battery-powered emergency lights or essential AC lighting. However, Appendix 9B of the FSAR states that all such areas are provided with 8-hour battery powered emergency lights. This safety evaluation clarifies that the control room is provided with lighting powered from the essential AC power system and DC lighting powered from the station batteries.
Safety Evaluation:
This revision is for clarification purposes. The AC lights are powered from MCC's IF and 1G.
In case of a loss of offsite power, these MCC's are powered by an emergency diesel generator. Emergency DC lighting for the control room is powered from the station batteries. The DC lights come on automatically upon loss of AC power.
PORC Review:
PORC Meeting 1928, 9/27/88
Subject:
FSAR Section 9B.4.1.26
==
Description:==
This safety evaluation provides justification for not having fire breaks in the South, West, and inside I
cable chases.
Safety Evaluation:
All these areas have detection and automatic fire suppression systems to limit the spread of fire.
Fire breaks in these areas are not required by the fire hazards analysis.
Further, combustible loads in these areas are due to cable insulation and all cables in these areas meet the requirements of IEEE 383, which requires that these cables do not propagate flane and are self-extinguishing when the ignition source is removed.
PORC Review:
PORC Meeting 1928, 9/27/88 30 Tech Misc 3/8
+
Subject:
FSAR Appendix 9B Changes
==
Description:==
Revised the FSAR to refer to the "Vice President -
Nuclear" instead of the " Senior Vice President".
Also, the resume of the " Engineer in Charge" was deleted from the FSAR and other editorial changes were made concerning titles for various positions.
Safety Evaluation:
The FSAR change to reference the Vice President - Nuclear rather than the Senior Vice President may be considered administrative since the NRC approved this change through issuance of Amendments 78 & 70 to the Unit 1 and Unit 2 Technical Specifications, respectively. The other editorial changes reflect the current APCo organization previously incorporated in other FSAR sections.
Deletion of the resume for the Engineer in Charge does not alter the requirements for the designated individual.
PORC Review:
PORC Meeting 1946, 11/22/88
Subject:
ADIF 87-05
==
Description:==
Clarified that the fuel transfer tube gate valve is not a containment isolation valve.
Safety Evaluation:
The fuel transfer tube is sealed with a blind flange during normal operating conditions. The flange has two seals around the periphery and the seals can be checked for leaks. This meets the applicable requirements and there is no need for the gate valve to be a containment isolation valve.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-11
==
Description:==
Revised FSAR section 6.4.1.1 to state that odorizers are not used for 00, hose reels.
Safety Evaluation:
Not using odorizers is acceptable since odorizers are necessary only when there is the potential for unintentionally introducing CO into occupied areas.
2 CO hose reels are not located in areas where leakage 2
of CO,ticular, the hose reels referred to in sectionfrom them could adv In par 6.4.1.1 are located outside of the control room in a corridor area such that leakage from them could not affect the control room atmosphere.
Therefore, odorizers are not needed.
PORC Review:
PORC Meeting 1893, 6/29/88 31 Tech Misc 3/8 9
Subject:
ADIF 87-30
==
Description:==
Revised the fire area hazards analysis to include the newly created fire area 1-508.
Safety Evaluation:
Fire area 1-S08 contains one safe shutdown cable.
Diverse means to accomplish the affected safe shutdown function are available and the boundary of the fire area has a sufficient fire rating. Hence, a fire internal or external to fire area 1-S08 will not result in the unacceptable loss of safe shutdown functions.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-37
==
Description:==
Deleted radiation monitors R-27A & B from Figure 12.1-2 in the FSAR. Also, Figure 12.1-2 was updated to show the differences between Unit 1 and Unit 2.
Safety Evaluation:
Radiation monitors R-27A & B are different from the other area monitors listed in section 12.1.4.2.
Because of this difference, their functional block diagram is different from Figure 12.1-2.
Therefore,
-27A & B are deleted from this figure.
The differences between Unit 1 and Unit 2 are already reflected in section 12.1.4.2.
The figure is being updated to be consistent.
PORC Review:
PORC Meeting.1893, 6/29/88
Subject:
ADIF 87-67
==
Description:==
Changed FSAR section 9.5.4.2 to correctly state the type of strainers installed in the discharge lines of the centrifugal pumps that transfer diesel fuel oil from the underground storage tanks to the day tanks.
The statement " Wye strainers fitted with 80 mesh screen" was changed to " Wye strainers fitted with type 316 stainless steel screen with 0.045 inch perforations".
32 Tech Misc 3/8
- Safety Evalu3 tion:
Th3 original specification for the strainers calls for 0.045 inch perforations. Also, each diesel generator has an additional filter downstream of these Wye strainers. An 80 mesh strainer would be unnecessarily restrictive for the first of two filters in series. This revision to the FSAR is considered a correction rather than a change in a specification for the strainer. This correction will have no affect on the safety or operation of the plant.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-92
==
Description:==
Described the anticipated transient without scram mitigation system actuation circuitry (AMSAC).
Safety Evaluation:
AMSAC has been designed to meet.and fulfill the applicable requirements. This system will provide a backup to the existing protection system to initiate auxiliary feedwater and a turbine trip in the event 1
that an anticipated transient results in the complete loss of main feedwater while the power level is above a specified value. AMSAC actuation will ensure that the reactor coolant system pressure will remain below the ASME Boiler and Pressure Vessel Code Level C service limit stress criteria of 3200 psig.
Moreover, this system will operate as intended and will~not negatively affect the safety of the plant.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-97
==
Description:==
Deleted the Regulatory Guide 1.21 exemption which states that the gross alpha analysis at FNP is performed to a minimum detectable activity of 1.0E-6 microcuries per milliliter rather than the Regulatory Guide 1.21 requirement of 1.0E-7.
Safety Evaluation:
Removing this exemption will require the gross alpha analysis to be done to a more conservative sensitivity (1.0E-7 versus 1.0E-6).
Also, this rakes the FSAR consistent with the Technical Specifications.
PORC Review:
PORC Meeting 1892, 6/28/88 l
33 t
j
4
Subject:
ADIF 87-109
==
Description:==
Corrected the values and sequences of events in the FSAR tables showing the results of the single reactor coolant pump locked rotor transient. These 4
corrections are due to the discovery that the tables inadvertently incorporated information from two different analysis: one originally performed assuming 15 x 15 fuel and the other performed essuming the 17 x 17 fuel used at FNP.
Safety Evaluation:
These corrections are typographical. The conclusions of the locked rotor analyses remain valid and no reduction of safety occurred.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-111
==
Description:==
Changed Table 3.2-1 of the FSAR to show the refueling water storage tank ( NST) as having tornado protection.
Safety Evaluation:
This change serves only to make the FSAR internally consistent in its description of the tornado resistance of the NST.
Section 3.3.2 " Tornado Loadings", states that all above-ground Category 1 structures are designed to withstand tornado loadings and tornado-generated missiles. Being a' Category 1 above-ground structure, the NST comes under this requirement. No safety issue is raised by this change.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-112
==
Description:==
Clarified which portions of the sample system shown in FSAR Figure 9.3-2 are safety related seismic category 1.
The boundaries are specified in Figure 9.3-2.
Safety Evaluation:
These changes were made to clarify the distinction in codes and standards applied to safety and non-safety related parts of the system. These changes are consistent with other design documents. These changes will not affect the safe shutdown of the plant.
PORC Review:
PORC Meeting 1893, 6/29/88 34 Tech Misc 3/8
Subject:
ADIF 87-114
==
Description:==
Corrected FSAR references to the boron injection tank I
(BIT) and associated systems. Deletion of the l
Technical Specification Limiting condition for Operation and surveillance requirements for the BIT and the BIT heat tracing system was approved in License Amendment No. 30 for ENP Unit 1 and No. 22 for FNP Unit 2.
FSAR section 6.3 was subsequent.y l-modified to reflect these license amendments. This l'
safety evaluation changes some items not previously identified.
Safety Evaluation:
The changes covered by this safety evaluation are consistent with the license amendments which were approved by the NRC.
PORC Review:
PORC Meeting 1896, 7/1/88
Subject:
ADIF 87-118
==
Description:==
Changed section 9.2 and Table 9.2-6 of the FSAR to state the correct coolant flow rate for the residual heat removal pump seals.
Safety Evaluation:
The new flow rate (5 gpm) is consistent with the requirements stated by the pump manufacturer. This change is not a safety issue since it meets the manufacturer's prescribed coolant flow rate.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-118A
==
Description:==
Changed section 9.2 Table 9.2-6 of the FSAR to state the correct. coolant flow rate for the charging pump seals.
Safety Evaluation:
The new coolant flow rate (5 gpm) has been approved by the pump manufacturer. Testing and operating experience has shown that the pump will operate satisfactorily with the flow rate.
PORC Review:
PORC Meeting 1893, 6/29/88 35 Tech Misc 3/8 l
______________._________J
0 0
Subject:
ADIF 87-146
==
Description:==
Modified section 3.9.4.1 of the FSAR to reflect that l
only valves that are so designated by the FNP l
Inservice Inspection (ISI) program undergo the
{
periodic inspection and operability testing specified in this section. Also, corrected typographical errors in Table 5.2-8.
I Safety Evaluation:
The ISI program was established following the guidance of Section XI of the ASME Code and has been accepted by the NRC as being adequate to insure the i
operability of ASME Code Class Valves. Therefore, it is acceptable to revise the FSAR to refer to this program to specify which valves must be periodically inspected or tested. The other changes corrected errors of a non-technical nature.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-148
==
Description:==
Corrected typographical errors made in the FSAR when Attachment B was added to Appendix 9B.
Safety Evaluation:
Editorial change only.
PORC Review:
FORC Meeting 1893, 6/29/88
Subject:
ADIF 87-160
==
Description:==
Revised the small break LOCA analysis results presented in the FSAR. The LOCA analysis assumes that all safety injection flow to a faulted cold leg spills and is lost. A review had determined that the FNP LOCA analysis assumed that the safety injection flow to the faulted loop spills to reactor coolant system backpressure for all break sizes. This is inconsistent with the current small break LOCA methodology which assumes that the safety injection flow to the faulted cold leg spills to containment backpressure for break sizes greater than the diameter of the safety injection line. Other minor corrections were made in the analyses.
36 Tech Misc 3/8
Safety Evaluation:
The small break LOCA analysis in the FSAR remains limiting for all small breaks except a break in the safety injection line equivalent to or larger than l-the double ended severance of that line. Revised calculations have determined that the changed backpressure would result in a small increase in the peak cladding temperature. The revised peak cladding temperature has a considerable margin to the 2200'F limit imposed by 10CFR50.46 and continues to be bounded by the large break LOCA results.
PORC Review:
PORC Meeting 1802, 1/14/88 PORC Meeting 1892, 6/28/88
Subject:
ADIF 87-161
==
Description:==
Changed sections 5.2 and 9.3 of the FSAR to correctly state the reactor coolant system (RCS) lithium range for 18-month fuel cycles. The lithium range of 0.7-2.2 ppm (Table 5.2-22), based on boron concentrations ranging from 0 to 1200 ppm was changed to 0.7-3.76 ppm, based on boron concentrations ranging from 0 to 2000 ppm.
Safety Evaluation:
The extension of the lithium range is required to maintain the desired RCS pH.
This change represents an adjustment to chemistry control to assure correct pH control.
Since the effect on fuel corrosion, RCS corrosion and primary stress corrosion cracking is i
negligible, the conclusions of the FSAR remain valid and no decrease in safety margin occurs.
In addition, no margin of safety as defined in the basis for any Technical Specificat. ion is affected.
PORC Review:
PORC Meeting 1896, 7/1/88 PORC Meeting 1921, 9/6/88
Subject:
ADIF 87-110
==
Description:==
Corrected typographical and editorial errors in FSAR Appendix 9B.
Safety Evaluation:
Editorial and typographical changes only.
PORC Review:
PORC Meeting 1893, 6/29/88
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37 i
Tech Misc 3/8 l
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Subject:
ADIF 87-171 Section 9B.3.M l.
==
Description:==
Changed the table on page 9B-45 of Appendix B of the l
FSAR to correctly identify the power level for the low power 600v cable trays.
l Safety Evaluation:
The FSAR revision serves only to clarify data.
PORC Review:
PORC Meeting 1893, 6/29/88 l
Subject:
ADIF 87-171 Section 98.4.1.16
==
Description:==
Corrected the FSAR statement concerning electrical supervision of the total flooding CO fire 2
suppression system in the cable spreading room..
Previous revisions of the FSAR had stated that the cable spreading room CO system had electrical 2
supervision of the heat detectors and associated circuitry.
Safety Evaluation:
The total flooding system in the cable spreading room is manually operated and does not have any heat detectors. Manually actuated systems do not require associated detectors or detection system electrical circuitry in order to function. This revision now reflects as-built and as-designed conditions. The revision will not decrease the effectiveness of the fire protection program.
PORC Review:
PORC Meeting 1895, 7/1/88
Subject:
ADIF 87-171 Section 9B.4.1.3.3
==
Description:==
Corrected the FSAR description of the insulating fluid utilized in all high-voltage, high-amperage transformers. The FSAR referred to the insulating fluid as a "high flash point fluid." The National Fire Protection Association now classifies the fluid as "less flammable."
Safety Evaluation:
This revision was an editorial change only. There were no changes to the plant as-built status or to combustible loadings.
PORC Review:
PORC Meeting 1893, 6/29/88 38 Tech Misc 3/8
-- - -_ _ _ ____ ___. _ _ _ - - _ _ = _ _ = _ _ _ _ _
4
Subject:
ADIF 87-171 Fire Area 1-20
==
Description:==
Delete the word " channel" in the safa shutdown train column for fire area 1-20, Room 210, in Appendix 9B of the FSAR.
Safety Evaluation:
This change corrects a typographical error. Room 210 contains no safe shutdown channels. This FSAR revision reflects as-built and as-designed conditions.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-177
==
Description:==
Changed FSAR section 9B.4.1.26 to exempt fire breaks for vertical cable runs in containment.
Safety Evaluation:
The fire hazai:ds analysis did not require fire breaks since containment has a low combustible loading. The probability of a fire of sufficient magnitude to damage redundant cables or components is unlikely and the incorporation of fire breaks would not enhance this position. Also, since the containment is a large open volume, fire breaks would not be effective. This absence of fire breaks will not affect the safe shutdown of the plant.
)
PORC Review:
PORC Meeting 1893, 6/29/88 I
Subject:
ADIF 87-180
==
Description:==
Changed section 6.2.3.5.1 of the FSAR to indicate that only Unit 2 has a spray additive tank empty alarm.
Safety Evaluation:
The change was made for clarification purposes only.
FSAR Figure 6.3-3 sheets 1 and 2 currently reflect this clarification. This change will not affect the safe shutdown of the plant.
PORC Review:
PORC Meer',g 1893, 6/29/88 39 Tech Misc 3/8
4
Subject:
ADIF 87-181
==
Description:==
Corrected paragraph 15.4.2.1.2.2 of the FSAR. This paragraph stated that, following a steam line rupture, safety injection would be initiated by high steam flow coincident with low steam line pressure or low Tavg. The correction states that, following a steam line rupture, safety injection will be initiated by low steam line pressure or low pressurizer pressure.
Safety Evaluation:
The paragraph was not consistent with FSAR Figures 7.2-7 and 7.2-8 and Technical Specification Table 3.3-3.
Since this change simply corrects the FSAR the change does not involve an unreviewed safety question.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-182
==
Description:==
Modified the FSAR statement that all fire protection water distribution and suppression systems meet seismic Category 1 requirements. Two Unit 1 wet pipe fire protection sprinkler systems (lA-21 and 1A-52) were determined to lack seismic Category 1 qualifications.
Safety Evaluation:
The analyses conducted on both sprinkler systems indicated that although they do not meet seismic Category 1 criteria, their failure during a seismic event would cause no damage to safe shutdown equipment or cabling. Their existence does not involve an unreviewed safety question nor does their lack of seismic Category 1 qualification decrease the effectiveness of the fire protection program.
PORC Review:
PORC Meeting 1896, 7/1/88 40 Tech Misc 3/8 i
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Subject:
ADIF 87-183
==
Description:==
Added additional exemptions to Regulatory Guide 1.21 on page 3A-1.21-1 of the FSAR.
Safety Evaluation:
The additional exemptions are minor in nature and do not reflect a safety hazard.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-184
==
Description:==
Changed item 22 on Table 6.2-31 of the FSAR from
" Containment Air Sample In" to "Containtnent Air Sample Out".
Also, item 23 was changed from
" Containment Air Sample Out" to " Containment Air Sample In".
Safety Evaluation:
The change was made to agree with the direction of the containment air sample flow as shown on Figures 6.2-91 and 6.2-124 of the FSAR.
PORC Review:
PORC 1893, 6/29/88
Subject:
ADIF 87-184A
==
Description:==
Revised the closure times for the following valves in 3
the FSAR to agree with the values listed in Technical Specifications: Q1P13V301, Q1P13v302, Q1P13V303, Q1P13V304, 01E14HV3657, 01G21HV3380, 01P14HV3611, 01P16V071, Q1P16V072, 01P16V081, 01P17HV3067, and 01P17HV3095.
Safety Evaluation:
This change involves increasing the FSAR specified closure time for the containment isolation valves listed above. The new closure time for each valve had been evaluated and it was determined that it will not increase dose levels outside the containment.
PORC Review:
PORC Meeting 1893, 6/29/88 41 Tech Misc 3/8
l
Subject:
ADIF 87-190 l
==
Description:==
Removed the Turbine Building fire detection and sprinkler systems from the operability requirements in Tables 9B.C-1 and 9B.C-2 (for Unit 1) and Tables 9B.C-5 and 98.C-6 (for Unit 2) of the FSAR (Attachment C to Appendix 9B).
Safety Evaluation:
The fire detection and suppression systems in the Turbine Building are not required to achieve safe shutdown of the plant. The detection and sprinkler systems in the Turbine Building do not meet the applicable criteria and therefore are not required to be included in the operability requirements of Attachment C to Appendix 9B.
This deletion does not decrease the effectiveness of the fire protection l
program.
PORC Review:
PORC Meeting 1895, 7/1/88
Subject:
ADIF 87-193
==
Description:==
Separated Unit 1 stairwell No. 8 from fire area 1-4 and designated it fire area 1-S08.
Safety Evaluation:
The designation of the stairwell as a separate fire area does not result in a modification to the plant's i
physical or functional features nor its fire protection program. This is an administrative change only.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
ADIF 87-195
==
Description:==
Revised an organization chart (Figure 13.1-1) shown in the FSAR. The position of Executive Vice I
President - Nuclear Operations was added and the title of Senior Vice President - Nuclear Generation was changed to Senior Vice President - Nuclear Operations.
Safety Evaluation:
These managenent changes provide more focused upper management attention to Nuclear Operations. This reflects the continuing APCo commitment to safe and reliable operation of FNP.
These organizational changes do not have an adverse affect on safety.
i PORC Review:
PORC Meeting 1893, 6/29/88 42 Tech Misc 3/8 4
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~.Subjset:
ADIF 87-196
==
Description:==
Deleted the Senior Vice President - Construction from Figure 17.2-1 of the FSAR.
Safety Evaluation:
The intent of Figure 17.2-1 is to reflect the APCo Nuclear Operations QA Organization. The Senior Vice President - Construction no longer reports to the Executive Vice President in charge of nuclear operations.
PORC Review:
PORC Meeting 1893, 6/29/88
Subject:
Cycle 9 Reload Safety Evaluation
==
Description:==
Provided the design for the Cycle 9 core which is based on a Cycle 8 end-of-life burnup within a range of,15,000 to-16,400 MND/HTU. A total of 28 Region-9, 61 Region-10, and 68 fresh Region-11 fuel assemblies are used in the design. A total of 704 fresh wet annular burnable absorbers (WABAs) are used in clusters of 4, 12, and 16. The Region-11 assemblies differ from the previous design in that they have standardized fuel pellets, reconstitutable top nozzles, a modified fuel rod end plug, and a modified top nozzle holddown spring and screw.
Safety Evaluation:
Based on the reload safety evaluation and the analyses performed by Westinghouse and Southern Company Services, Inc., this reload does not involve any unreviewed safety questions.
PORC Review:
PORC Meeting 1823, 3/2/88 PORC Meeting 1855, 4/19/88 43 l
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Subjtct:
GO-EIP-112, R vision 8
==
Description:==
Revision 8 to the procedure: updates telephone numbers, personnel titles, and names of people holding positions; and prompts Emergency Operations Center personnel to obtain the radio call numbers of the security vehicle from Security instead of relying on a listing of security vehicle call numbers.
Safety Evaluation:
This procedure revision will maintain the accuracy and efficiency of the procedure.
Subject:
GO-EIP-114, Revision 7
==
Description:==
Revision 7 to the procedure includes: a change to make it clearer that it is the Engineering and Licensing Support Director's responsibility to draft NETWORK informational releases; a change that gives the Engineering and Licensing Support Director guidance on what should be included in the NETWORK release; and a change that provides for only one notification of the Public Information Organization of an impending release instead of three.
Safety Evaluation:
This revision will make the procedure clearer and more efficient.
l
Subject:
GO-EIP-ll6, Revision 5
==
Description:==
Revision 5 to the procedure involves: changes to f
ensure all Emergency Operations Facility telephone operator positions are manned and that all plant telephone operators are provided with an updated Emergency Operations Facility phone number list; a change to ensure the Engineering and Licensing Support Director reviews the status of NETWORK news releases on turnover; a change to indicate the new telecopier number for the Dose Assessment Room; a change to more accurately reflect the present telecopier equipnent used in the Dose Assessnent Room; and changes to ensure the Dose Assessment Director obtains offsite agency status for the Recovery Manager.
Safety Evaluation:
This procedure revision will maintain the accuracy and thoroughness of the procedure.
44
)
, a.Subjrct:
GO-EIP-ll7, R3 vision 6
==
Description:==
Revision 6 to the procedure involves:
changes that clarify the Administrative Support Director's responsibility to coordinate the manning of the telephone operator's position in the Emergency Operations Facility; changes that will direct the Emergency Operations Facility telephone operator to screen only calls that ring directly to him; an addition to the procedure that assigns responsibility to the Administrative Support Director for the rerouting of the two dedicated state information lines to the Emergency Operations Facility once it has become fully operational; an update to the " Blanket Purchase Orders and Service
]
Contract" table; and a change that ensures all telephone console operators are provided a current telephone listing during an emergency.
Safety Evaluation:
This revision will serve to maintain the accuracy for the procedure and allow the most efficient method of communications coordination.
Subject:
GO-EIP-120, Revision 3
==
Description:==
Revision 3 to the procedure involves title changes and the incorporation of the Public Information Emergency Coordinator as one of the approval authorities.
Safety Evaluation:
This revision will maintain the accuracy of the procedure and allow the most efficient approval for news releases.
Subject:
GO-EIP-132, Revision 6
==
Description:==
Revision 6 to the procedure involves title changes and a change which will reference GO-EIP-102 for Corporate Communications Department responsibilities rather than having the responsibilities in EIP-132. Thus, changes can be made to EIP-132 without Corporate Communications Department approval for each revision.
Safety Evaluation:
This revision will maintain the accuracy of this procedure and streamline the revision process.
45
'Subj:ct:
GO-EIP-134, Revision 7
==
Description:==
Revision 7 to the procedure involves:
changes that take the Corporate Communications Department training requirements out of this procedure since they are already listed in GO-EIP-102; and changes that remove Corporate Communications Department responsibilities for the News Media Orientation Program from this procedure since they already exist in GO-EIP-102.
Safety Evaluation:
This revision will remove duplication of requirements that are listed in two procedures.
Subject:
GO-EIP-136, Revision 4
==
Description:==
Revision 4 to the procedure changes the name of the alert radio from NOAA Weather Radio to Alert Radio; and includes reference as to how the Corporate Communications Department will maintain records of tone alert radios.
Safety Evaluation:
This revision will maintain the accuracy of the procedure since the NOAA Weather Radio is no longer in use.
Subject:
GO-EIP-137, Revision 3
==
Description:==
Revision 3 to this procedure involves:
changes that reflect the Alert and notification System title description being changed from the " Prompt Notification System" to the " Alert and Notification System"; a change that takes the Corporate Communication Department's responsibility for lowering the siren activation testing signs out of the procedure since it has been incorporated in GO-EIP-102; a change to increase the full cycle activation testing frequency to semi-annual vice annual testing.
Safety Evaluation:
This revision will maintain the accuracy of the procedure and increase the reliability of the siren system with the increased testing frequency.
i 1
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Subjsct:
GO-NG-1, Revision 8A I
i
==
Description:==
Revision 8A acknowledges the creation of the position of Vice President-Nuclear.
l Safety Evaluation:
This revision enhances the efficiency and effectiveness of the support services provided to Farley Nuclear Plant.
l
Subject:
GO-NG-26, Revision 5
==
Description:==
Revision 5 to the procedure incorporates the requirements of 10CFR73.57 for access to Safeguards Information and makes minor corrections to titles and addresses.
Safety Evaluation:
This procedure revision addresses NRC requirements and establishes methods for access control to Safeguards Information.
Subject:
GO-NG-5, Revision 4 i
==
Description:==
Revision 4 to the procedure involves: a change which more accurately defines the actual
~
transmission of river flow data from Andrews Dam to Farley Nuclear Plant; and an editorial correction of the title of Senior Vice President to Vice President Nuclear.
Safety Evaluation:
The revision does not change, modify, nor create any additional requirements or responsibilities.
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