W3P86-0047, Annual Rept of Facility Changes,Tests & Experiments for 1985 Per 10CFR50.59

Annual Rept of Facility Changes,Tests & Experiments for 1985 Per 10CFR50.59

ML20155A907
Person / Time
Site:	Waterford
Issue date:	12/31/1985
From:	Cook K LOUISIANA POWER & LIGHT CO.
To:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
W3P86-0047, W3P86-47, NUDOCS 8604100119
Download: ML20155A907 (60)

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b-Louisiana Power and Light Company Waterford 3 SES Docket No. 50-382, License No. NPF-38 REPORT OF FACILITY CHANGES, TESTS AND EXPERIMENTS FOR 1985 PER 10CFR50.59 8604100119 851231 PDR ADOCK 05000382 R PDR l.

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g-o Louicitna Pow 2r & Light Comp:ny Waterford 3 SES 10CFR50.59 ANNUAL REPORT FOR 1985 TABLE OF CONTENTS I. FACILITY CHANCES A. Station Modifications (SMPs)

Report No. Title

1. SMP-0004 Addition of Shunts to Battery Disconnect Switches 3A-DC-S and 3B-DC-S

2. SMP-0025 Transfer of Loads to PDP3014AB

3. SMP-0035 Replace Bypass Transformers for Elgar Inverters

4. SMP-0090 Tie-In for Condensate Polisher

5. SMP-0094 Pressurizer Heater Time Delay Energization

6. SMP-0122 Boron Management System Discharge Cross Tie

7. SMP-0127 Piping Connections for New b:xiliary Feedwater Pump

8. SMP-0128 Station Air and Instrument Air Load / Unload Pressure Switches

9. SMP-0167 Safety Injection Flow Diagram. Corrections

10. SMP-0176 Decontamination Room and Hot Machine Shop Drain Piping Vent

11. SMP-0192 Resolution of Appendix R Deviations

12. SMP-0210 Demineralized Water Lines

13. SMP-0211 Revise!.Line and Valve List for Correct Design / Hydrostatic Pressure for Line 3FW2-42 A/B

14. SMP-0213 Condensate Pump Seal Piping

15. SMP-0220 Turbine Lube 011 Fystem

16. SMP-0244 Reactor Trip on Turbine Trip

17. SMP-0266 Blowdown Heat Exchanger Tubeside Relief Valves

18. SMP-0326 Computer Power Supply Battery

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i Louisiann Powar & Light CompIny 0- -Watsrford 3 SES 10CFR50.59 ANNUAL REPORT FOR 1985 Table of Contents Continued A. Station Modifications (SMPs)

Report No. Title

19. SMP-0354 Additional Cooler Capacity and Dissolved Oxygen Analyzer

20. SMP-0366 Condensate System Flow Diagram

21. SMP-0371 Update Dwg. C-162 Sh. 3 per PAS As-built Condition

22. SMP-0417 Reactor Auxiliary Building Operator Enclosure

23. SMP-0485 Additional Telephone in CAS

24. SMP-0514 Health Physics Control Point Office Modification

25. SMP-0531 Steam Binding of EFW Pumps (IEN 84-06)

26. SMP-0597 Addition of CPU-4 To Plant Monitoring Computer

27. SMP-0630 Plant Protection System Setpoint/ Plant Monitoring Computer Interface

28. SMP-0685 Seismic Rack for Scaffold Storage inside Reactor Containment Building

29. SMP-0730 Relief Valve to Replace Rupture-Disc.

30. SMP-0747 Fuel Handling Building HVAC Flappers

31. SMP-0760 Reactor-Coolant Pump Seal Water Circuit Modification

32. SMP-0765 Abandon Smoke Detector 31-1

33. SMP-0784 New Main Access Point to the Plant Site

34. SMP-0810 Power Service and HVAC Duct.in -4 elevation HP' Area

35. SMP-0867 Condensate Recirculation Lines 6CD6 -113 and 114 Add Orifices

36. SMP-0875 Oil Drain to Waste Drain !!odification

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' Wsttrford 3 SES 10CFR50.59 ANNUAL REPORT FOR 1985 Table of Contents Continued A. Station Modifications (SMPs)

Report No. Title

37. SMP-0891 Change Drawing for VCT Sample Point G-9

38. SMP-0896 CCW Surge Tank Vent Isolation

39. SMP-0934 CVC-103 Replacement

40. SMP-0964 Reconnection of Safety MOV Hester Circuit with Double Isolation Device in Containment

41. SMP-0974 Installation of Dual Tower Hydrogen Gas Dryer

42. SMP-1013 Emergency Diesel Generator "A" Starting Air Compressor Feeder Circuit Downgrade

43. SMP-1028 Circulating Water Pumps Bearing-Whter Supply Line Updates

44. SMP-1060 Diesel Generators (A&B) As-Built Conditions

45. SMP-1123 Polisher Building Sump Return to Backwash

46. SMP-1160 Gland Seal Steam Leak Off Line B. Procedure Changes

47. OP-901-056 Isolation Panel Fire

48. HP-1-235 Calculation and Adjustment of Radiation Monitoring Setpoints C. Special Evaluations

49. Manual Actuation of Reactor Power Cutback System II. TEST CHANGES

50. Biological Shield Effectiveness Survey, SIT-TP-715

51. Incore Detector Signal Verification, SIT-TP-735 52 Startup Integrated Test, SIT-TP-743

53. Initial Test Program Changes (FSAR Chapter 14) f l -111-l

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6 Waterford 3 SES 1985 Report of Facility Changes, Tests and Experiments

SUMMARY

This report provides the Waterford 3 Facility Changes and Tests made pursuant to 10CFR50.59(a)(1). The report covers the period from December 18, 1984 (issuance of low power operating license N?F-26) through December 31, 1985.

No experiments were conducted at Waterford 3 during the report period. None of the items in this report represents an unreviewed safety question or a change to the Technical Specifications.

The report identifies 49 Facility Changes (46 changes under the Station Modification program, two procedure changes and one special safety evaluation change to the FSAR), and 4 line item Test Changes which includes 8 specific changes to the Initial Test Program previously reported to NRC in fulfillnent of License NPF-38 Condition 2.C.10.

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I. FACILITY CHANGES A. Station Modifications (SMPs)

1. Station Modification, SMP-0004 SMP-0004, Addition of Shunts to Battery Disconnect Switches 3A-DC-S and 3B-DC-S Description of Change Installed new shunts in the 3A-DC-S and 3B-DC-S battery disconnect switches and connected them with the battery ammeters.

Reason for Change In order to provide proper ammeter indication, the original shunts had to be disconnected and new shunts added directly to the battery leads.

I Safety Evaluation The new shunts are being added to a Class 1E, seismic category I system. The shunts are seismically supported and their installation is verified to meet the requirements of

, IEEE-344. Addition of shunts to the battery disconnect switches does not affect any descriptions in the FSAR.

There is no increase in the possibility of an accident and no accident scenarios not previously considered have been created.

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2. Station Modification, SMP-0025 SMP-0025, Transfer of Loads to PDP3014AB Description of Change This modification provided for the redistribution of loads from Static Uninterruptible Power Supply 3AB to 3014AB.

Reason for Change To alleviate the problem of overloading on the 3AB inverter.

Safety Evaluation The reassignments of the loads from the panel are considered as non-safety. These changes do not increase the possibility of an accident or create any new accident scenarios not previously considered.

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3. Station Modification, SMP-0035 SMP-0035, Replace Bypass Transformers for Elgar Inverters, Description of Change This modification provided the engineer 4_ag information necessary to replace the bypass power supplies to class IE Static Uninterruptible Power Supplies (SUPS) 3A-S and 35-S.

Reason for Change The bypass transformers for Elgar SUPS did not provide voltage regulation or transient suppression within the specified limits.

Safety Evaluation The changes do not adversely affect operation of the equipment. There is no increase in the possibility or probability of an accident or malfunction.

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4. Station Modification, SMP-0090' SMP-0090, Tie-In for Condensate-Polisher Description of Change Provided design and' installation of piping for condensate polisher tie-in to condensate system.

Reason for Change The condensate polishers were added to the condensate system to provide a positive means of chemistry control.

IX Safety Evaluation The condensate polishers are non-safety. The addition of this system does not impact the safe operation or shutdown of the plant. This change does not increase the possibility or probability of any accident or malfunction previously evaluated.

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5. Station Modification, SMP-0094 -

l SMP-0094, Pressurizer Heater Time Delay Energization Description of Change

! This change provided the means for reclosing the station service transformers feeder breakers so that the proportional pressurizer heaters can be loaded onto the emergency bus during SIAS presence and offsite power available.

Reason for Change To permit the operator to remotely energize the pressurizer heater to

the emergency bus during an emergency.

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4 Safety Evaluation 4

f This change does not affect the isolation criteria as set forth in the

[ FSAR. This change does not increase the possibility or probability of l any accident or malfunction previously evaluated.

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i Station Modification, SMP-0122 i

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.SMP-0122, Boron Management System Discharge Cross Tie j Description of Change This modification provides the design engineering required to cross

tie the Waste Management System effluent discharge with the Boron i Management System discharge to the Circulating Water System.

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1 To provide tie-in connections to allow waste management system effluent to be discharged through the. boron management system i flowpath.

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i Safety Evaluation

. The system is classified as non-safety and non-seismic. The addition 2 of two flanged tie-in connections does not increase the possibility of j- an accident or create any new accident scenarios not previously j considered.

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o 7.- Station Modification, SMP-0127 SMP-0127, Piping Connections for New Auxiliary Feedwater Pump Description of Change This change provided the piping and electrical tie-in connections required to implement the new Auxiliary Feedwater System.

Reason for Change To make the Auxiliary Feedwater System functional, i

Safety Evaluation

The system is classified as non-safety and non-seismic. The addition j of the system tie-ins does not increase the possibility of an accident or create any accident scenarios not previously considered.

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8. Station Modification, SMP-0128 SMP-0128, Station Air and Instrument Air Load / Unload Pressure Switches d

Description of Change Replace load / unload pressure switches with switches having higher 4

setpoints.

Reason for Change.

i To maintain N accumulator manifold pressure at or above 92 psig 2

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Safety Evaluation These pressure switches are non-safety. No new accidents or malfunctions are created with the change and no previously evaluated malfunction is increased.

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9. Station Modification, SMP-0167 .

SMP-0167, Safety Injection Flow Diagram Corrections Description of Change Safety Injection System flow diagram, LOU 1564-C-167 sheet 1, has minor discrepancies between the flow diagram and the field. One discrepancy ,

is a typographical error and the other is a valve in differer.t location. ,

Reason for Change To change plant drawinEs to reflect as-built conditions. l

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Safety Evaluation  ;

! The correction of the flow diagram does not effect the probabilities

! or consequences of an accident or equipment malfunction.

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10. Station Modification, SMP-0176 SMP-0176, Decontamination Room and llot Machine Shop Drain Piping Vent Description of Change This modification is to complete the tie-in within the pipe chase for the vent-line from decontamination room and hot machine shop drain piping to the vent gas collection header.

Reason for Change To permit discharge to the vent gas collection header from the Decontamination Room and the Hot Machine Shop.

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4 Safety Evaluation The system is classified as non-safety, non-seismic. The completion of the tie-in between the 2" vent line and vent gas collection header within the pipe chase does not increase the possibility of an accident or create any new accident scenarios not previously considered.

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11. Station Modification, SMP-0192 1 SMP-0192, Resolution of Appendix R Deviations

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I Description of Change  !

i i This modification added emergency 8-hour battery packs, documented  !

i as-built condition.of existing conduits, rerouted certain essential cables, and provided fire-wrap for containment cable tray.

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Reason for Change' t

To revise plant drawings to reflect as-built conditions and to provide  ;

for miscellaneous cable wrapping and additional emergency lighting. j i

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Safety Evaluation l The changes made by this modification do not adversely affect plant  ;

operation or equipment. There-is no increase in the possibility or j probability of an accident or malfunction previously~ evaluated.

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12. Station Modification, SMP-0210 2

SMP-0210, Demineralized Water Lines i-i Description of Change Change flow diagram for several demineralized water lines to reflect  !

as-built configuration of the demineralized water system. i i

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Reason for Change >

l This modification is to correct a flow diagram to show the as-built j configuration of several demineralized water lines.

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Safety Evaluation The Demineralized Water System serves no safety' function and is not ,

j required to achieve safe shutdown or mitigate the consequences of an j accident. This change does not increase the'possbility or probability i of any accident or malfunction previously evaluated.

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13. Station Modification, SMP-0211  ;

1 SMP-0211, Revise Line and Valve List for Correct Design / Hydrostatic 4

i 1 Pressure for Line 3FW2-42 A/B.

Description of Change .

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Updating of line and valve list. ,

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l Reason for Change i

The Balance of Plant Line List and Valve List was updated to indicate .

7 correct design and hydrotest pressure-for a feedwater line and valve.

A flow diagram was revised to reflect the actual physical sequence of ,

connections for another feedwater line.

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3 Safety Evaluation i

This modification does not change the function of the equipment. The

probabilities or consequences of an accident or equipment malfunctJon

are not effected.

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o 14 Station Modification, SMP-0213 SMP-0213, Condensate Pump Seal Piping Description of_ Change This modification changed the flow diagram to reficet the actual segurace of the condensate pump seal water linc.9 from the supply header..

t Reanen for Change [

To change plant drawings to reflect as-built conditions, t

i Safety Evaluttion  !

The Condensate System is non-safety related; and non-scismic. This chango does not increase the possibility oc probability of accidents i previously evaluated, '

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{ 15. Station 2difieAtion, S!!P-0220 1

SMP-0220, 'Jutbine Lube 011Jptem i i i

t c ' Description of Change h Update flow diagran to indicate the correct line siras and to indicato

' r.on-yendor furnished lines on tha oil vapor extractor drain, t

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I To add line numbers and valve nutabers to the line if st and the flew 4

diagram. ,

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! Safety Evaluation i s  !

The 011 Vapor Extractor Drain Iines are classified as non-safety, non- I

seismic and do not perform any safety-related function. This change-l does not increase the possibility or probability of any accident or equipment malfunction previously evaluated.  ;

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16. : Station Modification, SMP-0244-SMP-0244, Reactor Trip on Turbine Trip 4

e Description of Change. '

t This modification previded the means to trip the reactor on turbine trip signal when tbc R.eactor Power Cutback System is inoperabic.

i Reason for Change I

i To provide the backup protection afforded by the non-safety reactor

, trip on turbine trip.

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Safety Evaluation This modification and test are supplemental and are provided as a l backup to the Reactor Power Cutback System. The system is designed.to ,

, reduce reactor power prior to safety oystems being activated. This '

i change does not increase the possibility or probability of any j accident or malfunction previously evaluated.

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17. Station Modification. SMP-0266 SMP-0266, Blowdown Heat Exchanger Tubeside Relief Valves Description of Change to revise Flow Diagram to show the existing relief valves on the Circulating Water side of the Blowdown Heat Exchanger.

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Reason for Change To revise plant drawings to reflect as-built conditions.

l Safety Evaluation This modification was a paper change only to show vendor supplied reifef valves which are classified non-safety, non-seismic, and does not affect previously performed accident analyses.

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18. Station Modification, SNP-0326 i

SMP-0326, Computer Power Supply Battery Description of Change Replace all Computer SUPS Battery Cells with upgraded cells, i

i Reason for Change l

The computer SUPS l, battery bank had 20 permanently damaged cells and the remaining 160 cells were warped.

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i Safety Evaluation ,

The battery bank is a non-1E system and.is not needed to assure safe-shutdown of the plant. Also, the'new batteries will provide for more computer time without loss of power than the old battery system. This change does not increase the possibility or probability of any accident or malfunction previously evaluated.

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l 19. Station Modification, SNP-0354 SNP-0354, Additional Cooler Capacity and Dissolved Oxygen Analyzer i

i Description of Change This modification is for the addition of a.second sample cooler to be

cooled by component cooling water and a new dissolved oxygen analyzer.

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i. Reason for Change l

l- To provide the capability to sample and analyze in the three-hour time.

j limit which is in accordance with NUREG-0737, i

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j Safety Evaluation 1-l The Post Accident Sampling System (PASS) uis classified as non-safety and non-seismic. However, a portion of the component cooling watere piping servicing the additional sample cooler is safety Class 3 and Seismic Category I.

! The addition of the miscellaneous system tie-in connections and the replacement of the dissolved oxygen analyzer do not-increase the possibility of an accident or create any new accident scenarios not previously considered.

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20. Station Modification, SMP-0366 SMP-0366, Condensate System Flow Diagram Description of Change This modification provided for updating condensate system flow diagrams.

! Reason for Change To reflect an actual line location and corrected drawing reference coordinates.

4 Safety Evaluation This portion of the condensate system is designated non-safety, non-seismic and is not required to mitigate the consequences of an

accident. This change does not increase the possibility or probability of any accident or malfunction previously evaluated.

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21. Station Modification, SMP-0371 SMP-0371, Update Dwg. C-162 Sh. 3 per PAS As-Built Condition

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Description of Change 1-This modification provided for updating the post accident sampling system flow diagram.

l Reason for Change i

Drawing G-162, Sh. 3, is updated to reflect the as-built condition.

4 Safety Evaluation This change does not increase the possibility, probability, or consequences of any accident previously evaluated in the FSAR.

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22. Station Modification, SMP-0417 SMP-0417, Reactor Auxiliary Building Operator Enclosure Description of Change An 11 ft. by 6 ft. enclosure was installed on the -4 foot elevation for auxiliary operator use.

Reason for Change To provide break and eating area in the immediate area of the RCA access point.

Ssfety Evaluation This modification has no impact on any systems required for safe shutdown of the plant, nor does it have any impact on accidents previously evaluated in the FSAR.

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23. Station Modification, SMP-0485 SMP-0485, Additional Telephone in CAS Description of Change 4 An additional telephone was installed in the Central Alarm Station room for onsite use only.

4 Reason for Change The existing telephone in the CAS did not provide sufficient telephone communication capability for emergencies.

Safety Evaluation The modification is in the non-safety related, non-seismic Communications System. The Communications System is not required for safe shutdown of the plant and the modification has no impact on accidents previously evaluated in the FSAR.

24. Station Modification, SMP-0514 SMP-0514, Health Physics Control Point Office Modification Description of Change j Modify HP control point office by adding two doors, a sliding window and a service counter.

Reason for Change To improve flow of traffic into the Radiation Controlled Area (RCA).

l Safety Evaluation i The system is classified as non-safety and non-seismic. The addition of two doors and one window does not increase the possibility of an accident or create a new accident scenario not previously considered.

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25. Station Modification, SMP-0531 SMP-0531, Steam Binding of EFW Pumps (IEN 84-06)

Description of Change Install local temperature indicators on discharge side of EFW pumps.

The instrumentation will provide indication if the line heats up and there is a possibility for steam forming in the line.

Reason for Change ,

To implement recommendations resulting from corrective actions required to resolve IEN 84-06.

Safety Evaluation The changes provided with this modification will not adversely affect operation of the EFW piping system. The purpose of the changes is to further reduce the possibility of an accident or malfunction.

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26. Station Modification, SMP-0597 SMP-0597, Addition of CPU-4 To Plant Monitoring Computer Description of Change Addition of a fourth CPU System.to the cxisting three CPUs of the Plant Monitoring Coriputer.

l Reason for Change The original system did not allow for performance of all functions in real time under full loading conditions.

I Safety Evaluation Installation of the fourth CPU system will not. affect plant operation due to the dual complex - redundant Host Computer System. This change will not increase the possibility or probability of any accident or malfunction previously evaluated.

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27. Station Modification, SMP-0630 SMP-0630, Plant Protection System Setpoint/ Plant Mo,nitoring Computer Interface Description of Change This modification removed the Plant Protection System setpoint/ Plant Monitoring Computer cables.

Reason for Change To relieve concerns that Plant Monitoring Computer Multiplexer site component failures would effect Plant Protection System input signals.

4 Safety Evaluation Deletion of the setpoint computer points does not increase the possibility or probability of any accident or malfunction previously evaluated.

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28. Statien Modification, SMP-0685 SMP-0685, Seismic Rack for Scaffold Storage inside Reactor Containment Building Description of Change This nodification covered design and installation of a seismically qualified storage rack to hold scaffolding that has been painted and designated for use in the reactor containment building (RCB).

Reason for Change To provide adequate storage for scaffolding in RCB thereby eliminating need to remove all scaffolding after each work effort in containment.

Safety Evaluation The system is classified as non-safety and saismically designed to withstand safe shutdown earthquake. The addition of the storage rack does not increase the possibility of an accident or create any new accident scenario not previously considered. The hydrogen generation due to galvanized clamps has been studied and it was concluded that the small amount of galvanized coating on these clamps is not considered detrimental with regard to the quantity of hydrogen gas produced during a LOCA. No aluminum material has been added.

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29. Station Modification, SMP-0730 SMP-0730, Relief Valve to Replace Rupture Disc.

Description of Change This station modification changed the Condensate Hotwell dump lines 6CD6-55 and 6CD6-252 by adding a multiple stage orifice plate sized to reduce system pressure from Condensate Pump discharge pressure to 50psig at a flow rate of approximately 1400gpm. This change also added a relief valve to replace the existing rupture disc.

Reason for Change This change replaced restriction orifice 6CD-K162 with a multiple stage orifice designed to eliminate cavitation which causes vibration and erosion.

Safety Evaluation The modifications are in the non-safety related Condensate System.,

located in the Turbine Building and the yard south of the Turbine Building. The Condensate System is not required for safe shutdown of the plant and the modifications have no impact on accidents previot ily evaluated in the FSAR. The portions of the system affected by this SMP are only used during start-up as the system water chemistry is being adjusted and their failure in that mode would not have any adverse radiological consequences. The existing rupture disc was replaced with a relief valve with a setpoint of 100psig. This replacement does not introduce any new flow paths which have not been analyzed before.

30, Station Modification, SMP-0747 SMP-0747, Fuel Handling Building HVAC Flappers i

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Description of Change Addition of restictions at core holes on the -35 elevation of the Fuel Handling Building.

1 Reason for Change To provide a positive means for maintaining a negative pressure-in the Fuel Handling Building.

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Safety Evaluation The walls where flappers are to be installed are seismic Category I.

This modification does not increase the probability of any previously evaluated accident and equipment malfunction, and it does not create the possibility of any new accident or equipment malfunction. The j margin of safety defined in any technical specification is not reduced.

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31. Station Modification, SMP-0760 SMP-0760, Reactor Coolant Pump Seal Water Circuit Modification Description of Change Revise seal cooler isolation valve circuitry to allow reopening the valves from the control room.

Control circuit was revised to have the seal cooler isolation valves controlled by t:ie temperature. If these isolation valves close by the temperature signal, operator can override the temperature signal and reopen the valves by a control switch being added on RTG Board CP-2 i Panel.

These valves will open for a preset time and after the lapse of this time, if the high temperature still exists, the valves will reclose.

Otherwise they stay open.

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To change seal cooler isolation valve actuation from pressure initiation to temperature initiation. Also, the operator can remotely reopen the valves.

Safety Evaluation The Component Cooling Water (CCW) to the RCP seal water is a non-essential, seismically qualified system. This change will not increase the possibility or probability of any accident or malfunction previously evaluated.

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32. Station Modification, SMP-0765 SMP-0765, Abandon Smoke Detector 31-1 Description of Change Delete one smoke detector from Fire Zone RAB 31 in the Reactor Auxiliary Building.

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Reason for Change j The detector was located in a pipe chase that was inaccessible during plant operations, i

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Safety Evaluation The changes will not adversely affect operation of plant. Based on the Fire Hazard Analysis, the creation of the new Fire Zone 23A will not have an adverse impact. An exemption request to delete the specific detector was filed with NRC via letter W3P85-0560, dated March 1, 1985.

33. Station Modification, SMP-0784 SMP-0784, New Main Access Point ~to the Plant Site Description of Change Reduce plant access to a single point for controlling personnel and traffic.

! Reason for Change To reduce the number of entrances to the Owner Controlled Area (OCA) to one.

t Safety Evaluation This change will not increase either t.e probability or the possibility of any accidents previously evaluated. The change will restrict access to the OCA which now includes all parking lots. The complete control of parking lots was not previously possible.

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34. Station Modification, SMP-0810 SMP-0810, Power Service and HVAC Duct in -4 elevation HP Area Description of Change Provide for the installation of a ventilation duct and electrical power for the Perkin-Elmer 5000 AA Unit.

Reason for Change The previous equipment was not capable of reaching the level of sensitivity required for iron, copper and sodium in the plant feedwater.

Safety Evaluation This is a non-safety related modification. A failure of the unit in no way prevents the reactor from shutting down nor can it impact the ability to maintain the plant in a safe shutdown condition. -This change does not increase the possibility or probability of any accident or malfunction previously evaluated.

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35. Station Modification, SMP-0867 SMP-0867, Condensate Recirculation Lines 6CD6 -113 and 114 Add Orifices Description of Change Orifices were added downstream of valves CD137B and CD137C.

Reason for Change The valves were of the wrong design to effect the necessary pressure drop to achieve design flow of 2800gpm through lines 6CD6 -113 and

, 114.

4 Safety Evaluation The modification is in the non-safety related Condensate System. The Condensate System is not required for safe shutdown of the plant.

This change does not inccease the possibility or probability of any

, accident or malfunction previously evaluated.

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36. Station Modification, SMP-0875 SMP-0875, 011 Drain to Waste Drain Modification Description of Change To provide design and construction information for rerouting of the Charging Pumps and Oil Separator Drains from the Oil Sump of the Liquid Radwaste System.

Reason for Change The purpose of the modification was to eliminate the possibility of releasing contaminated oil to an unrestricted area.

Safety Evaluation The changes will not adversely affect operation of the subject piping system. There is no increase in the possibility or probability of an accident or malfunction that was previously evaluated.

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37. Station Modification, SMP-0891 EMP-0891, Change Drawing for VCT Sample Point G-9 Description of Change Change drawing to reflect as-built conditions.

i Reason for Change VCT sample point mislabled as P-9 and needed to be changed to G-9.

Safety Evaluation This change does not reflect an actual change to the plant and does not reflect a difference from conditions previously evaluated. This change does not increase the possibility or probability or any

-accident or malfunction previously evaluated.

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38. Station Modification, SMP-0896 SMP-0896, CCW Surge Tank Vent Isolation Description of Change A one inch check valve, designed for gas service, was installed in the Component Cooling Water Surge Tank Vent line (7CCl-262).

Reason for Change To prevent activity from the Vent Gas Collection Header from entering the surge tank.

Safety Evaluation The change involves non-safety equipment and is not required for safe shutdown of the plant. This change does not increase the possibility or probability of any accidents or malfunction peeviously evaluated.

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j- 39. Station Modification, SMP-0934 s SMP-0934, CVC-103 Replacement

,i Description of Change

, This modification provided replacement of the WKM supplied CVCS letdown containment isolation valve with a-Masoneilan globe valve._ It  ;

also provided clearance for the operator of the replacement valve by ,

reorienting the hydrotest connection furnished and the replacement valve operator with the necessary tie-ins from electrical and

, instrument air supplies.

I Reason for Change The original valve consistently stuck in the open position during and i after the process of plant cooldown.

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4 Safety Evaluation The modified portion of the system (with the exception of the leakoff I i

piping and the instrument air supply to the operator) is classified as

, seismic Category I and safety related. None of the modifications increase the possibility of an accident nor create any new accident

scenarios not previously considered.

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40. Station Modification, SMP-0964 SMP-0964, Reconnection of Safety MOV Heater Circuit with Double Isolation Devico in Containment Description of Change This modification provides double circuit protection to meet isolation requirements for IE and non-lE circuits.

Reason for Change To assure the non-safety heaters in containment will not affect the IE power circuits.

Safety Evaluation The changes will not adversely affect operation of.the subject equipment and satisfies the isolation criteria for feeding non-safety systems from lE power circuits. The change will not increase the probability or possibility of any accident or malfunction previously evaluated.

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41. Station Modification, SMP-0974 SMP-0974. Installation of Dual Tower Hydronen Cas Dryer 4

~ Description of Change Replaced the single tower hydrogen gas dryer with a dual tower unit.

y Reason for Change The performance of the original single tower hydrogen gas dryer was unacceptable.

• The replacement of the e1.iating generator hydrogen gas dryer improves

generator protection against maisture and reduces future maintenance

costs.

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i Safety Evaluation, The hydrogen gas generator coolant system is non-safety related and -

non-seismic and is not required to shut down the turbine generator af ter a turbine trip. This change will not increase the possibility. ,

or probability of any accident or malfunction previously evaluated.

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42. Station Modification, SMP-1013 SMP-1013. Emergency Diesel Generator "A" Starting Air Oceprescot Feeder Circuit _ Downgrade Description of Change Add double protection devices in sonc 480V power circuits.

Reas_on for_Cha'nge To meet separation criteria for honesafetf systems that are fed from 1E power cfrsuits.

Safe'v_Evalua_tica e

Singte failur6 of a prbtective device vill not effect the load on the respective IE power circuit and will provide greater assurance that the separation criteria are being r.et. This change will not increase the possibility or probability 6f any accident or ma,1 function

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43. Station Mcdtf tcation. SMP-1028 SMP-1028, Circulating Water Pumps _ Bearing Water Supply Line Updates Description of Change _

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Treated Water System valves TW-2102, TW-2101 and temporary strainer '

7FP-S682 were not in the field but appeared on all plant drawings.

• These items were not required as other upstream block valves can be used in lieu.of TW-2102. The temporary strainer was not necessary as there are individual strainers going to all hearings. All affected drawings and valve lists will be modified, Reason for Change To remove two valves and a temporary strainer from plant drawings to reficet as-built conditions.

Safety Evaluation The modification is in the non-safety related Treated Water System.

The Treated Water System is not required for safe shutdown of the ,

plant. This change does not increase the possibility or probability of any accident or malfunction previously evaluated.

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44. Station Modification. SMP-1060 SMP-1060, Diesel Generators (AIB) As-Euilt Conditions r

Description of Change Provides an update on Diesel Generator paperwork to reflect as-built conditions.

i Reason for Change ,

To reflect as-built conditions. '

i Safety Evaluation The changes incurred do not affect the operation of the equipment or the safety of the plant. There is no increase in the possibility or i the probability of any accidents previously evaluated. ,

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45. Scation Modification,.sMP-1123 i SMP-1123, Polisher Building Sump Return to Backwash 4

i Description of Change 4

Change valve lineup so that polisher building eump is discharged to backwash tank instead of going to yard oil separator.

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Reason for Change

To eliminate discharge of resinous waste to yard oil aeparator.

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Safety Evaluation i

This is a non-safety, non-quality system. This change does not-increase the pocaibility or probability of any accidents or i.

malfunction previously evaluated.

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46. Station Modification, SMP-1160 SMP-1160, Gland Seal Steam Leak Off Line Description of Change Provide additional pressure taps in gland seal steem leakoff lines.

4 Reason for Change To eliminate drainage problems caused by slope problems in the lines.

The modification enhances operation.

i Safety Evaluation This is a non-safety related system. This change will not increase either the possibility or the probability of any accident previously evaluated.

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- l B. Procedure Changes

47. Procedure, OP-901-056 OP-901-056, Isolation Panel Fire i

Description of Change This was a new procedure to describe the specific actions to be taken in the event of a fire in the +35 elevation RAB Isolation Panel.

Reason for Change To satisfy 10CFR50, Appendix R commitments to resolve fire-watch requirements.

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Safety Evaluation

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Use of this procedure will not increase the probability or possibility of any accident or malfunction previously evaluated. The bases for this evaluation is documented in the Associated Circuits Analysis - Engineering Report, that was transmitted to the NRC per letter LW3-024-85 dated January 15, 1985.

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48. Procedure, HP-1-235, Rev. 3 HP-1-235, Rev. 3, Calculation and Adjustment of Radiation Monitoring Setpoints Description of Change This chagge increased the iodine channel setpoints from 1x10' uCi/ml to 1x10 uCi/ml.

Reason for Change The origninal setpoint was near the extrame limit of the monitors' sensitivity and would have resulted in frequent nusiance alarms.

Safety Evaluation The monitors are classified as non-safety and non-seismic. The monitors are not utilized in the accident analysis nor do they have an impact on the accident analysis. This change will not increase the possibility or probability of any accident or malfunction previously evaluated.

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C.- Special Evaluations

49. Manual Actuation of Reactor Power Cutback System i

Description of Change Activate the Reactor Power Cutback System (RPCS) using the manual rod group select mode.

Reason for Change i The change was needed to allow the operators to preselect rod groups to be inserted in the event of a feedwater pump trip. With the change in effect, the RPCS may be able to reduce power quickly enough to eliminate a reactor trip on-low steam generator level.

Safety Evaluation Based on the fact that the impact of the Reactor Power l Cutback System's operation on safety has been previously analyzed, the 10CFR50.59 evaluation revealed no unreviewed

safety question. CE report CEN-200 provides the safety analysis to address the implications of the RPCS on reactor safety and found that the plant is protected against single failuren of the RPCS. This report was reviewed and found acceptable by the staff in SER Supplement No. 5 (paragraph 4.4.2.2). No scenario of RPCS operation or misoperation can be postulated which would reduce reactor safety or hinder safe shutdown.

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II. TEST CHANGES

50. Biological' Shield Ef fectiveness Survey, SIT-TP-715 Description of Change Change the FSAR to reflect as-found radiation levels in containment and RCA during power ascension testing.

l l Reason for Change During the conduct of SIT-TP-715, three areas were found to have

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radiation levels higher than predicted. None of the radiation levels warranted design changes, therefore the changes will be made to the FSAR, A q

Safety Evaluation None of the higher radiation levels represent.an unreviewed safety question and do not affect any technical specification safety margin. Operation of the plant with slightly higher than anticipated radiation levels will not have any impact on_ FSAR l accident analysis or other' accident possibilities.

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51. Startup Test, SIT-TP-735 SIT-TP-735, Incore Dectector Signal Verification

Description of Change

Acepetance of test deficiency for SIT-TP-735.

Reason for Change

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Six incore detectors did not meet acceptance criteria as set forth in the procedure.

F l Safety Evaluation

This deviation does not increase the possibility or probability of any j accidents or malfunction previously evaluated. The incore detectors are not required for plant safety since they do not initiate any direct safety-related functions.

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52. Startup Integrated Test, SIT-TP-743 SIT-TP-743, Power Ascension Testing Ventilation Capability Description c f Change Containment ambient air and reactor cavity temperature acceptance criteria were changed to reflect as-found condition.

Reason-for Change During power ascencion testing (100% Power), the containment ambient air and reactor cavity temperature exceeded acceptance criteria by 2.8'F and 1.8'F respectively.

Safety Evaluation The two temperatures being above 120*F will not increase the probability of occurrence of any accident previously calculated nor will it create possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR. No Technical Specification limits will be exceeded as a result of this change.

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.53. Initial Test Program Changes (FSAR Chapter 14)

Safety evaluations pursuant to 10CFR50.59 were conducted for the test changes described below. These test changes were reported to the NRC in accordance with License NPF-38, Condition 2.C.10, and are included herewith for completeness of the report relative to 10CFR50.59(b).

None of the changes to the Initial Test Program required a change to the Technical Specifications or constituted an unreviewed safety question. The required FSAR changes are to be made in accordance with 10CFR50.71(a).

The Phase III - Initial Startup Testing changes included:

(1) FSAR Test 14.2.12.3.31, Control Systems Checkout Change: The Megawatt Demand Setter (MDS) was deleted as a test prerequisite because Waterford 3 does not have an MDS.

Boron concentration was deleted from accpetance criteria since it is maintained manually not by a control system.

Reference Document: Reported to NRC by LP&L letter W3P85-1263, dated 5/10/85.

(2) FSAR Test 14.2.12.3.31, Control Systems Checkout Change: The 20% reactor power level test was deleted from the test schedule.

Reference Document: Reported to NRC by LP&L letter W3P85-1290, dated 5/17/85.

(3) FSAR Test 14.2.12.3.38, Loss of Load Transients at 50, 80 and 100 Percent Power Change: Clarification was provided of when the" test was to be performed, i.e., loss of load transients will be performed only if the Reactor Power Cutback System is to be declared operational.

Reference Document: Reported to NRC by LP&L letter W3P85-1418, dated 7/8/85.

(4) FSAR Test 14.2.12.3.37, Turbine Trip Change: Clarification of when the - test was . , be performed, i.e., to allow the turbine trip test to be conducted at a lower power level.

Reference Document: Reported to NRC by LP&L letter W3P85-1431, dated 7/29/85.

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53. (Continued) - Initial Test Program Changes (FSAR Chapter 14)

(5) FSAR Test 14.2.12.3.17, Piping Thermal Crowth, Vibration, and Shock Change: A satisfactory evaluation of piping stresses in main steam piping after the revised test will be acceptable instead of an actual instrumented level 4 transient monitoring of the main steam system during turbine trip from 100% power.

Reference Document: Reported to NRC by LP&L letter W3P85-1441, dated 7/29/85.

(6) FSAR Test 14.2.12.3.31, Control Systems Checkout Change: Deletion of step and ramp unit load changes at 50%

power. The control systems described in the test are not safety related and no credit for their operation is taken in the Waterford 3 FSAR Chapter 15 accident analyses.

Reference Document: Reported to NRC by LP&L letter W3P85-1432, dated 7/29/85.

(7) FSAR Test 14.2.12.3.31, Control Systems Checkout Change: Deleted the Control Systems steady-state operation checkout at 100% power level.

Reference Document: Reported to NRC by LP&L letter W3P85-3209, dated 10/15/85.

(8) FSAR Test 14.2.12.2.58, Movable Incore Detector System Change: Deleted the Movable Incore Detector responsiveness testing from the power ascension test program. The system is not required to support any safety analyses.

Reference Document: Reported to NRC by LP&L letter W3P85-3209, dated 10/15/85.

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LOUISIANA 342 onAnoNoe Sincer POWER & L1GHT P. O. BOX 6008

• NEW ort.EANS. LOUISIANA 70174 * (504) 366-2345

$iuSi$ SYS April 1, 1986 W3P86-0047 A4.05 QA Mr. Robert D. Martin ] @ Q []\[ [@ p :;

Regional Administrator, Region IV U.S. Nuclear Regulatory Commission ' !!

611 Ryan Plaza Drive, Suite 1000  !

Afd - 31986 c h i

Arlington, TX 76011 j

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 1985 Report of Facility Changes, Tests and Experiments

Dear Mr. Martin:

Enclosed is the 1983 Report of Facility Changes, Tests and Experiments for Waterford 3 which is furnished pursuant to 10CFR50.59(a)(1). The antar.1 report covers the period from December 18, 1984 (issuance of low power operating license NPF-?6) through December 31, 1985. The original and 39 copies of the report are provided the accordance with 10CFR50.59(b). '

If you have any questions regsrding this report, please contact G.E. Wuller, Onsite Licensing, at (504) 464-3499.

Very uly yours, v \;L/) 4Jby\g K.W. Cook Nuclear Support & Licensing Manager KWC:GEW:ssf Attachment cc: NRC, Director, Office of I&E G.W. Knighton, NRC-NRR ,

J.H. Wilson, NRC-NRR l NRC Resident Inspectors Office ,

I B.W. Churchill W.M. Stevenson  !

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