W3P87-0595, Rept of Facility Changes,Tests & Experiments for 1986 Per 10CFR50.59
| ML20205R952 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1986 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3P87-0595, W3P87-595, NUDOCS 8704060490 | |
| Download: ML20205R952 (60) | |
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J Louisiana Power and Light Company Waterford 3 SES Docket No. 50-382, License No. NPF-38 REPORT OF FACILITY CilANGES, TESTS AND EXPERIMENTS FOR 1986 PER 10CFR50.59 0704060490 061231 PDR ADOCK 05000302 R
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Waterford 3 SES 10CFR50.59 ANNUAL REPORT FOR 1986 TABLE OF CONTENTS i
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FACILITY CHANGES l
A.
Station Modifications (SMPs)
Report No.
Title 1.
SMP-107 Supplemental Fuel Pool Heat Exchanger l
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SMP-216 Safe Shutdown Analysis / Appendix R 3.
SMP-217 Paging System Flashing Beacon Lights and Speakers 4.
SMP-250 New Flush Water Supply for Radiation Monitor RT-627 5.
SMP-254 Addition of Condensate Polisher to Condensate System 6.
SMP-257 Radioactive Liquid Waste Storage Capacity Addition 7.
SMP-337 Drawing Corrections - Area Radiation Monitars 8.
SMP-338 Deaeration of Secondary Makeup Water 9.
SMP-471 RAB Normal Supply Fan Condensate Drain 10.
SMP-506 Reduce Contamination of Primary Sample Panel (PSL) 11.
SMP-540 Gland Steam Condenser Exhaust Drain 12.
SMP-584 Decontamination Room Liner 13.
SMP-701 Turbine Lube Oil Purifier 14.
SMP-740 Steam Traps on Emergency Feedvater Pump Turbine (EFWPT) Supply Lines 15.
SMP-748 Feedwater Heater Drain Valve 16.
SMP-774 Post Accident Sampling System Mass Flow Control Bypass Valve 17.
SMP-798 Portable Demineralizer Resin Transfer Line to Radwaste Solidification Building t
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SMP-889 Blowdown Demineralizer Slufce Connection l
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i Louiciens Pow 2r end Light Compzny Wetsrford 3 SES 10CFR50.59 ANNUAL REPORT FOR 1986 Table of Contents Continued A.
Station Modifications (SMPs)
Report No.
Title 19.
SMP-933 Vent Gas Collection Header Plumbing Vent 20.
SMP-942 Drawing Change for G-173 21.
SMP-970 Short Term Modification of Drains in Fuel Handling Building 22.
SMP-987 Reactor Trip / Loss of Load 23.
SMP-1015 Removal of Air From Condenser Outlet Waterboxes 24.
SMP-1029 Containment Sump Level Indication and Alarm 25.
SMP-1047 Spent Resin Transfer System Dewatering Mode 26.
SMP-1084 Condenser Sampling Pump Replacement and Installation 27.
SMP-1087 Replace Various Tank Level Indicators and Switches 28.
SMP-1139 Removal of Construction Phase Valve 29.
SHP-1185 Gland Seal and Vacuum Pump Exhaust Header Drain 30.
SMP-1197 High Pressure Safety Injection Pump A/B Alarm Logie Change 31.
SMP-1206 Incorporate DCN into G-167 Drawing 32.
SMP-1207 Post-Accident Sampling System (PASS) Drawing Updates
- 33. SMP-1223 Air Ejector Pumps Flow Measurement Air Dryers i
34.
SMP-1271 Emergency Diesel Generator Annunciator Modification 35.
SMP-1318 Post-Accident Sampling System (PASS) Drawing Update I
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i Louisienz Powsr and Light Comprny Waterford 3 SES 10CFR50.59 ANNUAL REPORT FOR 1986 Table of Contents Continued A.
Station Modifications (SMPs)
Report No.
Title 36.
SMP-1331 Letdown Heat Exchanger Outlet Pressure Alarms 37.
SMP-1334 Piping Modification to Feed Pump Lube Oil Transfer Pump 38.
SMP-1355 Circulating Water Sample System Downstream of Liquid Waste / Boron Management System 4
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SMP-1487 Control Room Ammonia and Chlorine Detectors 40.
SMP-1594 Sulfuric Acid Isolation Valve 41.
SMP-1605 No. 1 High Pressure Heaters Vent and Drain Valve Replacement 42.
SMP-1652 Instrument Air Valving and Piping 41 B.
Procedure Changes 43.
IIP-001-235 Calculation and Adjustment of Radiation Monitoring Setpoints 44.
OP-02-010 Reactor Auxiliary Building HVAC and Containment Purge System 45.
OP-10-002 Refueling 46.
OP-903-013 Surveillance Procedure - Monthly Channel Checks J
47.
OP-903-072 Surveillance Procedure - Refueling Containment Building Penetration Check 1
C.
Special Evaluations 48.
Missing Steam Generator Tube Plugs 49.
Pressurizer Safety Valve Leakage 50.
Verify acceptability of changing a footnote in FSAR Table 3.2-1 (PER-40111)
St. Changes to FSAR Table 17.2-1 and Section 3.8.3.6.1.3.
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Louisiens Powar and Light Comprny Waterford 3 SES 10CFR50.59 ANNUAL REPORT FOR 1986 Table of Contents Continued II.
TESTS 52.
Fuel Pool Cooling Pump Flow Performance (SMP-947) 53.
Reactor Power Cutback System Operational Verification (STP-028182-A) i l
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i Waterford 3 SES 1986 Report of Facility Changes, Tests and Experiments 1
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SUMMARY
t This report provides the Waterford 3 Facility Changes and Tests made pursuant to 10CFR50.59(a)(1). The report I
covers the period from January 1, 1986 through December j
31, 1986.
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No experiments were conducted at Waterford 3 during the i
report period. None of the items in this report represents l
an unreviewed safety question or a change to the Technical l
Specifications.
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i The report identifies 51 Facility Changes (42 changes under the l
Station Modification program, five procedure changes and four special safety evaluation changes to the FSAR), and two Tests.
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FACILITY CHANCES A.
Station Modifications (SMPs) 1.
Station Modification, SMP-107 SMP-107, Supplemental Fuel Pool ifeat Exchanger Description of Change Install supplemental fuel pool heat exchanger and accessories in response to NRC Question No. 010.40 Rennon for Change To alleviate unacceptable level of radioactivity being releaned from the spent fuel pool while the existing heat exchanger in out of nervice.
Safety Evaluation This modification will not have any impact on accidents or malfunctions previounty evaluated and does not represent an unreviewed safety question.
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Station Modification, SMP-216 SMP-216, Safe Shutdown Analysin/ Appendix R I
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Description of Change This change providen information necessary to reflect as-built conditions of safe shutdown cables / raceways.
Rennon for Change l
l This information was not previously shown on design documents.
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i Safety Evnluation l
This change does not include any physieni changes to the plant. This t
change provides updated drawings to reflect plant as-butit conditions
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and as nuch does not change any analyses or evaluations previously considered. This change does not create an unreviewed safety question.
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Station Modification, SMP-217 SMP-217, Paging System Flanhing Rencon f.ights and Spenkers Description of Change Install Finshing Beacon lights in plant areas with high operating noise levels.
Reason for Change To fulfill commitment made in the LP&T, review of the NRC Inspection and Enforcement Bulletin, IER 79-18, entitled, " Audibility Problems Encountered on Evacuation of Personnel from liigh-Noise Arens".
Safety Evaluation This change does not impact the safety of the plant and was done to annure that personnel could be made aware of plant conditions when working in high noise areas of the plant.
The changes will not adversely affect operation of the plant. There in no increase in the ponnibility of an accident or malfunction of a different type than any previously evaluated. This change does not create an unreviewed safety question..
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Station Modification, SMP-250 l
SMP-250, New Flush Water Supply for Radiation Monitor RT-627 i
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Description of Change 1
Change the source of flush water for Radiation Monitor RT-627 from i
Primary Makeup Water to Condensate Demineralized Water.
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Reason for Change
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i The primary makeup water currently used may have higher background activity then the alert alarm setpoint for the monitor.
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j Safety Evaluation This change affects a non-safety /QA required system. The change does l
not alter any previous accident or equipment malfunction analyses.
This change does not create an unreviewed safety question.
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Station Modification, SMP-254 l
SMP-254, Addition of Condensate Polisher to Condensate System i
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Description of Change Addition of Condensate Polisher System to the Condensate System.
Reason for Change The existing condensate system chemistry was continually out of specification during startup and it was determined that full flow polisher system would be needed to assure the plant had an adequate water purity for feedwater.
Safety Evaluation This is a non-safety system and is not required to shutdown the plant or maintain the plant in a safe shutdown condition. The use of the system was not considered for mitigation of previously evaluated accidents or equipment malfunctions.
The addition of this system does not create an unreviewed safety question. l I
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Station Modification, SMP-257 SMP-257, Radioactive Liquid Waste Storage Capacity Addition i
Description of Change Installation of 40,000 gallon Radwaste Storage Tank and Related Components.
Reason for Change To provide additional radwaste storage capacity as an extension of existing storage facilities.
Safety Evaluation The addition of the radwaste storage tank and its components will not create any new accident scenarios and will not increase the consequences of any accident previously evaluated. This change does not create an unreviewed safety question.
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Station Modifiention, SMP-337 SMP-337,' Drawing Corrections - Area Radiation Monitors l
Description of Change Correct errors on drawings.
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Reason for Change s
l To correct errors on drawings showing radiation monitors.
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a Safety Evaluation j
This change was to correct minor drawing errors and does not affect the safety of the plant. This change does not alter accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-338 SMP-338, Deaeration of Secondary Makeup Water Description of Change Addition of a secondary makeup water deaeration system.
Reason for Change To remove air entrapped in water used to fill condensate, demineralized and primary water storage tanks.
Safety Evaluation The secondary vacuum degasifier (SVD) system is non-safety /non-quality related. The design, operation or malfunction of the SVD will not affect, either directly or indirectly, any safety related structures, systems, or components.
The addition of the system does not create an unreviewed safety question.
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Station Modification, SMP-471 SMP-471, RAB Normal Supply Fan Condensate Drain Description of Change Reroute fan drains from Liquid Waste Management System to storm drains.
Reason for Change To eliminate the expensive processing cost of the condensate which was being routed to the Liquid Waste Management System.
Safety Evaluatioe RAB Normal Supply Unit (S-6) handles only outside air to supply various areas in the RAB which in turn is exhausted by the Filter Train System E-22 through the plant stack. The modification involves routing the drain from S-6 unit to the existing storm and non-radioactive drain line. The modification also adds six seismic supports to the new drain piping. This modification does not increase the possibility or probability of an accident or equipment malfunction previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-506 SMP-506, Reduce Contamination of Primary Sample Panel (PSL)
Description of Change Reduce contamination of PSL panel by seal welding threaded connectinns, provide flanges for removal of flow indicator, and add an exhaust duct to the panel piping area.
Reason for Change To reduce the overall possibility of contamination of the chemistry laboratory.
Safety Evaluation This change will not affect the operation of the equipment and was done to provide more protection for the technicians. This modification does not alter the evaluations previously conducted.
This change does not create an unreviewed safety question.
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Station Modification, SMP-540 SMP-540, Gland Steam Condenser Exhaust Drain Description of Change Install individual loop seal for each gland steam condenser (GSC) off the existing drain connection and pipe it to a local equipment drain adjacent to the GSC.
Reason for Change This change will eliminate (1) unsightly appearance of water running down the side of the GSC, (2) potential for uninformed personnel plugging drain, and (3) possibility of restricting the free flow of water from the housing.
Safety Evaluation This system is classified as non-safety /non-seismic.' This change does not alter the accident scenarios or equipment malfunctions previously evaluated.
This change does not create an unreviewed safety question.
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- 12. ' Station Modification, SMP-584 l'
SMP-584, Decontamination Room Liner i
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4 Description of Change Declassify decontamination room liner from seismic Category I to non-seismic.
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Reason for Change To document change of decontamination room that was evaluated per NCR-W3-1978. FSAR Table 3.2-1 was not revised to reflect the change.
i Safety Evaluation The decontamination room liner is non-safety.
Evaluation of the liner was not considered in any of the accident'or equipment malfunctions I
previously evaluated. This change does not' create an unreviewed safety question.
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l 13.' Station Modification, SMP-701 SMP-701 Turbine Lube Oil Purifier 4
e Description of Change Permanently install the turbine lube oil purifier.
l Reason for Change To provide more reliable operation of the purifier and to minimize oil leakage; the temporary purifier system was intalled permanently.
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This is a non-safety /non-seismic system. The function-or changes to this system will not impact the safety of the plant. The system was I
not involved in any accident scenarios or equipment malfunctions previously evaluated. This change does not create lua unreviewed j
safety question.
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Station Modification, SMP-740 SMP-740, Steam Traps on Emergency Feedwater Pump Turbine (EFWPT)
Supply Lines Description of Change Add steam traps and bypass test lines to EFWPT steam supply lines.
Reason for Change To provide a means to bleed off moisture condensing in the lines caused by steam leaking past isolation valves and condensation of steam following surveillances.
Safety Evaluation This change provides for corrective action on the major water problem in the EFWPT (water hammer) during startup. This change does not increase the probability or possibility of any accident scenarios or equipment malfunctions previously evaluated. This change does not create a different type of accident or equipment malfunction from those previously evaluated and does not create an unreviewed safety question.
15.
Station Modification, SMP-748 SMP-748, Feedwater Heater Drain Valve Description of Change Add 1" feedwater heater drain valve to drawings.
Reason for Change Correct drawing to reflect as-built conditions.
Safety Evaluation This is a non-safety /non-QA system. This change does not affect any of the previous accident or equipment malfunction scenarios evaluated.
The change does not introduce any new conditions that would require an evaluation. This change does not create an unreviewed safety question.
16.
Station Modification, SMP-774 SMP-774, Post Accident Sampling System Mass Flow Control Bypass Valve Description of Change A bypass line and valve were installed around the mass flow control valve in the Post Accident Sampling System.
Reason for Change The maas flow control valve limits the flow of nitrogen used for the initial pressurization of the liquid gas separator.
This flow limit is necessary during the sampling procedure but the original design t
required 40 minutes to pressurize the separator in preparation for the sampling. The bypass line will speed up the initial pressurization.
The flow diagram must be revised to reflect the actual configuration.
Safety Evaluation This change does not alter any of the accident scenarios or equipment malfunctions previously evaluated. The change does not create the possibility of a different type of accident from those previously evaluated.
The change does not create an unreviewed safety question.
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Station Modification, SMP-798 SMP-798, Portable Demineralizer Resin Transfer Line to Radwaste Solidification Building Description of Change Install a 2" SS pipe in an unused 4" penetration between the RAB and the Radwaste Solidification Building.
Reason for Change Prior to this change, there were no provisions to transfer spent resin from the portable demineralizer unit to the radwaste solidification area.
Safety Evaluation This system does not interact with any safety related systems or components.
This change does not increase the probability or possibility of any accidents or equipment malfunctions previously evaluated.
The change does not create the possibility of an accident different from those previously evaluated and does not create an unreviewed safety question. __
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Station Modification, SMP-889 SMP-889, Blowdown Demineralizer Sluice Connection Description of Change Add a valve to the Blowdown Demineralizer.
Reason for Change To allow sluicing of resin to an alternate location rather than be i
restricted to the spent resin tank.
1 Safety Evaluation The modification does not impact any system required for safe shutdown of the plant.
This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question. _
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Station Modification, SMP-933 SMP-933, Vent Gas Collection Header Plumbing Vent Description of Change The plumbing vent line which was disconnected from the Vent Gas Collection Header was rerouted to an HVAC duct.
Reason for Change To eliminate the flow of gases back through the plumbing vent lines which subsequently wound up in floor and equipment drains.
This caused airborne contamination in the RAB.
Safety Evaluation This system is non-safety /non-quality related. There is no impact on equipment required for safe shutdown of the plant. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-942 SMP-942, Drawing Change for G-173 Description of Change Add clarification of sump drain lines to indicate source of flow.
Reason for Change To provide operations with a means to specifically identify source of flows to the leak detector and the contairment sump.
Safety Evaluation This is a paper change only. No physical change to the plant occurred, therefore, there was no change to the evaluations conducted previously. -__
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Station Modification, SMP 970 t
i SMP-970,.Short Term Modification of' Drains in Fuel Handling Building i
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Description of Change 1
Remove valve FS-203 in the Fuel Handling Building; install a blank j.
flange and provide a spool piece for future reconnection if required.
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Reason for Change To eliminate the potential of draining highly radioactive water from j
areas within the Fuel Handling Building to -35' FHB sump or the -35' l
wing area.
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i Safety Evaluation This change provides additional assurance that highly radioactive i
water will not be inadvertently drained to' the FHB sump or -35' wing area. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-987 SMP-987, Reactor Trip / Loss of Load i
Description of Change Provide an alternate means of reactor trip in the case of large load rejection ( > 70% power).
Reason for Change To provide Reactor Trip on loss of load which will assure that the main safety valves do not lift with a loss of load event.
Safety Evaluation This is a non-safety system. A failure of the circuitry will not prevent the plant from safely shutting down. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-1015 SMP-1015, Removal of Air From Condenser Outlet Waterboxes Description of Change Provide a means to periodically vent the air from the condenser outlet waterboxes.
t Reason for Change To assist plant operators in the periodic removal of air from the condenser waterboxes.
i Safety Evaluation This is a non-safety related system.
The failure of the equipment and piping does not introduce any new risks to safe operation and shutdown of the plant. This change does not alter any accident scenarios or equipment malfunctions previously evaluated.
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Station Modification, SMP-1029 SMP-1029, Containment Sump Level Indication and Alarm Description of Change Shift the range of containment sump level downward and revise the alarm setpoint to a level just below the bottom of the HVAC access door.
Reason for Change To make the operator aware of the water level being at the bottom of the access door.
Safety Evaluation This system is only for monitoring purposes and it does not initiate any safety related actions. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-1047 i
SMP-1047, Spent Resin Transfer System Dewatering Mode i
Description of Change Added dewatering pump and segregated dewatering mode piping from spent resin recirculation / discharge loop.
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Reason for Change I
i To eliminate the accumulation of resin in the " dead leg" which will reduce clogging of the strainer in the dewatering mode of operation.
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Safety Evaluation The spent resin transfer system is not required for-safe shutdown of j
the plant. This change does not alter the accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-1084-SMP-1084, Condenser Sampling Pump Replacement and Installation j
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4 Description of Change Add new sampling pumps and throttling valves to condenser hotwell sample pumps.
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I Reason for Change The addition of throttling valves in the recirculation line to the condenser in series with existing isolation valves provides for proportioning flow between sample panel and recirculation.
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Safety Evaluation l-This change does not impact the safety of the plant. This change does not impact any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-1087 SMP-1087, Replace Various Tank level Indicators and Switches Description of Change Replace various tank level indicators / switches for Condensate Storage Tank, Lube Oil Batch Tanks A&B, Primary Water Storage Tank, Fire Water Storage Tank, Auxiliary Boiler Fuel Oil Tank and the EDG Diesel Oil Storage Tank.
Reason for Change To increase the reliability of level indication and to reduce maintenance.
Safety Evaluation The new level instrumentation is better than or equal to the old equipment.
This change will not alter any accident scenarios or equipment malfunctions previously evaluated. This change will not create an unreviewed safety question.
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Station Modification, SMP-1139 SMP-1139, Removal of Construction Phase Valve Description of Change This change removes a construction phase valve used to supply fire protection water from the turbine building.
Reason for Change The valve is no longer needed and it was starting to leak.
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Safety Evaluation
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This change does not impact any safety related systems. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. The change does not create an unreviewed safety 1
question.
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Station Modification, SMP-ll85 SMP-1185, Gland Seal and Vacuum Pump Exhaust Header Drain Description of Change Change exhaust header drain valve from " globe" type to " gate" type.
Reason for Change Globe valve had a tendency to clog with rust and debris.
Safety Evaluation This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed cafety question.
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Station Modification. SMP-1197 SMP-1197, High Pressure Safety Injection Pump A/B Alarm Logic Change Description of Change Provide wiring changes to block alarms for any HPSI pumps that are not selected for emergency operation.
Reason for Change To eliminate alarms for HPSI pumps that are bypassed or inoperable and are not on emergency operation lineup.
Safety Evaluation Annunciator circuits are non-safety related. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-1206 SMP-1206, Incorporate DCN into G-167 Drawing Description of Change Flow diagram G-167, Sheet 1, Rev. 23 to be changed to reflect DCN-IC-1448.
i Reason for Change Flow diagram did not reflect correct operation sequence of HPSI pump mini-recirculation isolation valves.
Safety Evaluation l
This modification did not require an actual change to the plant. The l
drawing was changed to reflect the FSAR text. This change does not alter any accident scenarios or equipment malfunctions previously 4
evaluated. This changes does not create an unreviewed safety I
question.
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Station Modification, SMP-1207 SMP-1207, Post-Accident Sampling System (PASS) Drawing Updates Description of Change This change is to update PASS drawings to reflect as-built conditions.
Reason for Change To reflect as-built conditions.
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Safety Evaluation This is a non-safety system. The change does not increase the possibility or probability of any accidents or malfunction previously evaluated.
This change does not create an unreviewed safety question.
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Station Modification, SMP-1223 SMP-1223, Air Ejector Pumps Flow Measurement Air Dryers Description of Change Add heat exchanger and moisture separator to the rotometer air lines on each condenser vacuum pump.
Reason for Change To eliminate moisture from the system thereby providing more accurate rotometer readings.
l Safety Evaluation This is a non-safety related system. This change does not alter any accident scenarios or equipment malfunctions previously evaluated.
This change does not create an unreviewed safety question.
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Station Modification, SMP-1271 SMP-1271, Emergency Diesel Generator Annunciator Modification Description of Change Rewiring of EDG " Diesel Generator Unavailable" and " Diesel Generator Trouble" annuciators.
Reason for Change To eliminate the " Diesel Generator Unavailable" annunciator when only one of the two redundtnt starting air receivers has low pressure signal.
I Safety Evaluation Annunciator circuits are non-safety related. Modification of the annunciator will not compromise the ability to safely shut the plant down. This change does not alter any of the accident scenarios or equipment malfunctions previously evaluated.
This change does not create an unreviewed safety question. -
35.. Station Modification, SMP-1318 SMP-1318, Post-Accident Sampling System (PASS) Drawing Update Description of Change Change the location of valve PAS-410.
Reason for Change To correct the location of valve PAS-410 on Drawing G-162, Sheet 3 to reflect as-built condition-and be in agreement with EMDRAC-5817-5945..
Safety Evaluation This is a design document correction only.
This. change does not alter
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any accident scenarios or equipment malfunction previously evaluated.
This change does not create an unreviewed safety question.
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Station Modification, SMP-1331 SMP-1331,-Letdown Heat Exchanger Outlet Pressure' Alarms
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Description of Change Change "LO" pressure alarm setpoint from 420 psig to 350 psig-and "HI"'
pressure alarm'setpoint from 500 psig to 530 psig.
Reason for Change To eliminate the frequent-alarms caused by jerky control valve which causes the pressure oscillations.
Safety Evaluation Letdown flow control valves and backpressure valves do not perform a safety function. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-1334 SMP-1334, Piping Modification To Feed Pump Lube Oil Transfer Pump i
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Installation of valve and flanges in the discharge.of'the steam generator feed pump lube oil transfer pump.
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Reason for Change To facilitate cleaning lube oil, t
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Safety Evaluation
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The change to the turbine driven feed pump lube oil system'does not-degrade its integrity. This change.does not' alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety-question.
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Station Modification, SMP-1355 i
SMP-1355, Circulating Water Sample System Downstream of Liquid
. Waste / Boron Management System 4
Description of Change Added a sample connection, accumulator and three valves for circulating water sampling, i
Reason'for Change So that circulating water can be sampled prior to release to the environment.
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I Safety Evaluation Failure of this system would have no impact on the safety of the plant. This change does not alter any accident scenarios or equipment 1
malfunction previo'usly evaluated. This change does not create an unreviewed safety question.
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Station Modificati$n, SMP-1487 SMP-1487, Control Room Ammonia and Chlorine Detectors-i 1
' Description of Change i
3 This change covers replacement of the old chlorine detector with a new I
.make and removal ~of the old broad range toxic gas monitor.
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l The old' systems were continually out of service, i
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1 Safety Evaluation 1
The new instrumentation will perform.the same non-safety indication and safety control functions as the old equipment. This changes does
-not alter any accident scenarios or equipment malfunctions previously.
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evaluated. This change does not create an unreviewed safety. question.
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40.
Station Modification, SMP-1594 SMP-1594, Sulfuric Acid Isolation Valve Description of Change Add a 3/4" manually operated ball valve and spool piece.
Reason for Change Because of leakage from the sulfuric acid tank on the blowdown demineralizer system.
Safety Evaluation This modification does not affect the safety of the plant. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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41.
Station Modification, SMP-1605 SMP-1605, No. 1 High Pressure Heaters Vent and Drain Valve Replacement Description of Change Replace 3/4" valves with 1" valves and increase downstream nipples and caps to 1" material.
Reason for Change Needed to replace old valves because they were leaking. Since no 3/4" valves were in stock they were replaced with 1" valves.
1 Safety Evaluation This change does not affect the safety of the plant. This change does not alter any accident scenarios or equipment malfunctions previously evaluated. This change does not create an unreviewed safety question.
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Station Modification, SMP-1652 SMP-1652, Instrument Air Valving and Piping Description of Change Change the drawings for the instrument air headers to match the as-built condition.
Reason for Change Non-safety Instrument Air (IA) headers were inadvertently left on Blowdown drawings instead of on IA drawings.
Safety Evaluation This change does not affect the safety of the plant. This change does not alter any accident scenarios or equipment malfunctions previosly evaluated. This change does not create an unreviewed safety question.
B.
Procedure Changes 43.
Procedure, HP-001-235 HP-001-235, Calculation and Adjustment of Radiation Monitoring Setpoints Description of Change Clarified the procedure and include setpoint changes for Steam Generator Blowdown and Gaseous Waste Management System Monitors (GWMS). Recalculated plant stack setpoints to correspond to 1 gpm RCS leak rate. GWMS alert alarm was changed to high alarm value.
Reason for Change Station Modifications caused the iodine setpoints to change on the three portable PIG monitors. Plant stack flowrate changed from 92,190 to 83,000 cfm. Containment Atmosphere Monitor setpoint needed to be corrected to reflect an RCS containment leak rate of Igpm. Alert alarm is now of the 10CFR20 limits.
Safety Evaluation These monitors are not utilized in the accident analysis nor do they have any impact on the accident analysis. Their failure following a design basis accident will not have any adverse effect on safety related components or systems.
The containment atmosphere monitor is a class IE monitor required by Technical Specification, although the alarm setpoint is not designated in the Technical Specification.
It monitors the containment atmosphere and serves as an indicator of RCS leakage inside containment.
Operational experience and calculations have indicated that a setpoint of 2.7E-3 pCi/mi would correspond to an RCS containment leak rate of I gpm The FSAR currently 3
designates the setpoint as 10 pCi/ml and clarifies by stating that it is an approximate value (see page 12.3-28 of the FSAR).
Changing the setpoint of this monitor does not affect the monitor's performance.
Based upon the above, an increase in the iodine channel setpoint for these monitors does not involve an unreviewed safety question.
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- 44. Plant Procedure, OP-02-010 i
OP-02-010, Reactor Auxiliary Building HVAC and' Containment-Purge System i
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Description of Change
. Add section to procedure to enhance containment pressure control using the containment. purge system.
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Reason for Change Clarify the use of the Containment Purge System.
i Safety Evaluation The purge valves are restricted mechanically to a position that will ensure closure on demand during an event. Radiation monitors provide override closure of these valves..These aspects will prevent unacceptable offsite dose rates in case of-failure.
No alterations to systems will be made. The possibilities or probabilities of' accidents.
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or malfuncticas previously evaluated will not be' increased. The-consequences or possibilities of equipment malfunction will not be increased from those previously-evaluated, i
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-45.
Plant Procedure, OP-10-002 OP-10-002, Refueling Description of Change Complete re-write to provide for. wet refueling and refueling machine preoperational testing.
l Reason for Change Procedure would have been inadequate for second cycle refueling.
Safety Evaluation This change was required to modify fuel handling differences between initial core load and 2nd cycle core loading.- The changes do not alter any accidents or equipment malfunctions from those previously evaluated. The change does not decrease'any margin of safety and does not create an unreviewed safety question.
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Plant Procedure, OP-903-013 OP-903-013, Surveillance Procedure - Monthly Channel Checks Description of Change Added QSPDS readings for accident monitoring to Attachment 10.3.
Reason for Change To update the procedure and allow for QSPDS readings to substitute for either Train "A" or "B" if they are inoperable. This will ensure compliance with minimum number of channels required.
Safety Evaluation This change does not alter the possibilities or probabilities of accidents or equipment malfunctions previously evaluated. This change does not introduce accident scenarios or equipment malfunctions different from those previously evaluated.
This change does not represent an unreviewed safety question. - -
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47.
Plant Procedure, OP-903-072 OP-903-072, Surveillance Procedure - Refueling Containment Building Penetration Check Description of Change Modify HVAC vacuum breaker penetration to accommodate a temporary seal plate with several small diameter pipe nozzles and threaded pipe caps.
Reason for Char:ge This change allowed for temporary electrical or test lines to be available in containment for use during refueling.
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i Safety Evaluation
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The vacuum breakers are not needed during the refueling outage. The pipe nozzles will be capped until they are needed. When the temporary lines are pulled, the pipe nozzles will be injected with Dow Corning 3-6548 silicone RTV to assure that a fire / air seal is maintained. The seal configuration is rated for a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire and a 6.0 psi pressure differential.
In the event of an accident, the fire / air seal would prevent the transfer of any air from the containment building into the annulus area. This temporary change does not increase the possibilities or probabilities of any accidents or equipment malfunctions previously evaluated. The change does not introduce any new accident or equipment malfunctions not previously evaluated.
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C.
Special Evaluations 48.
Missing Steam Generator Tube Plugs Description of Change Special Evaluation of missing Steam Generator tube plugs.
Reason for Evaluation In preparation for eddy current examination of steam generator tubes, it was discovered that in the outlet plenum of Steam Generator #1 that 5 plugs were missing.
Subsequently one of the tube plugs was found.
Safety Evaluation A review of the possible impact that might be caused by the four loose tubes plugs was conducted which resulted in an adequate assurance that the four missing tube plugs would not cause any significant problems even if they remain in the reactor vessel until the ten year inservice inspection.
The missing plugs are judged not to create the potential for a new accident scenario or to increase the probability of a previously evaluated accident.
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Pressurizer Safety Valve Leakage Description of Change l
Special evaluation to determine ability to maintain natural l
circulation in hot' standby after a loss of offsite power with 2.1 gpm l
pressurizer safety valve leakage.
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Reason for Evaluation The pressurizer safety valve leakage was approximately 2.1 gpm and the proportional heater controller is powered from a non-safety bus.
1 Safety Evaluation An Operational Heat Balance performed found that approximately 230 kw of the Pressurizer Backup heaters was necessary to maintain 2250 lb.
pressure in the RCS.
Backup heaters were utilized because there are 1200 kw of these heaters available powered from a safety bus (3A32 and 3B32) and can be loaded onto the diesels, on a loss of offsite power.
With existing estimated relief valve leakage to be not more than 2.1 i
gpm there exists substantial excess backup heater capacity to meet natural circulation requirenents and plant pressure control for i
maintaining a minimum of 50*F subcooled margin.
This evaluation concludes that this event is still within the design bases for the plant and does not involve an unreviewed safety question.
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50.
Verify acceptability of changing a footnote in FSAR Table 3.2-1 (PER-40111) l l
Description of Change j
Change the seismic requirements from " full 10CFR50, Appendix B QA Program" to " pertinent 10CFR50 Appendix B requirements".
Reason for Evaluation The reason for the change is to modify the FSAR requirement to reflect consistency with Regulatory Guide 1.29 Position 4.
(Sept. 1978, Rev.
3).
The revised note #13 to FSAR Table 3.2-1 allows for an appropriate graded application of 10CFR50, Appendix B to reflect requirements for Seismic Category I equipment.
Safety Evaluation The change makes LP&L guidelines for procuring Non-Safety Related/ Seismic Category I equipment in line with Regulatory Guide 1.29.
The technical and quality requirements of 10CFR50, Appendix B pertinent to activities affecting the safety related functions of the equipment will still be imposed. The change will not increase either the possibility or probability of accidents previously evaluated. The possibility of a malfunction of equipment different than any previously evaluated will not be created. The consequences of malfunction of equipment important to safety previously evaluated will not be increased. -
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C.
Special Evaluations 51.
Changes to FSAR Table 17.2-1 and Section 3.8.3.6.1.3 1
Description of Change Add Specification No. 100 to list of Purchase Specifications for concrete and revise requirements for periodic testing of concrete materials to match requirements of Specification 100 during operations phase.
Reason for Change To allow LP&L to mothball the onsite concrete batch plant.
Safety Evaluation Specification LOU 3988.400 has been prepared to accept off site ready mixed concrete for future retrofit modification.
This Specification deviates from some of the material and testing requirements which were appifcable during construction stage and are as described in FSAR Section i
3.8.3.6.1.
This change does not impact the safety of the plant. The changes does not alter any accident scenarios or equipment malfunctions previously evaluated.
This change does not create an unreviewed safety question.
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II.
TESTS 52.
Fuel Pool Cooling Pump Flow Performance (SMP-947) i Description of Change Special test conducted to verify pump flow was in compliance with licensing basis.
Reason for Change During startup testing, the pump flow curves did not match vendor curves. The special test was conducted to collect as-built data to determine that acceptable flow values were being achieved.
4 Safety Evaluation This test does not change the system, therefore, the previous evaluations are not affected.
The test did result in changing net positive suction head, but the flow values measured were still in excess of :he design basis flow rate.
This change does not alter any accident scenarios or equipment malfunctions previously evaluated r J does not create an unreviewed safety question. -..
e e's a 53.
Reactor Power Cutback System Operational Verification (STP-028182-A)
Description of Change Install a data acquisition system (DAS) to allow for collection of data during either an automatic or planned loss of load transient.
1 Reason for Change The reason for the change is to be able to verify operability of the RPCS after the plant is on line rather than intentionally tripping the generator as part of startup testing.
1 Safety Evaluation The impact of the RPCS operation on safety has been previously analyzed by CE and accepted by the NRC. Changing the test method to i
allow either an automatic or manually initiated transient doea not effect the previous safety analysis. This change does not increase the possibility or probability of any accidents previously analyzed nor does the change decrease the margin of safety.
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cr Rafart 10CFR50.59 q
LOUISI AN A / 317 BARONNESTREET P. O. BOX 60340 POWER & LIGHT NEW ORLEANS, LOUISIANA 70160 (504) 595-3100 N N IVs b March 31, 1987 W3P87-0595 A4.05 QA U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 1986 Report of Facility Changes, Tests and Experiments
Reference:
W3P86-2936, December 11, 1986, Final Safety Analysis Report Update.
Enclosed is the 1986 Report of Facility Changes, Tests and Experiments for Waterford 3 which is furnished pursuant 10CFR50.59 (a) (1). This annual report covers the period from January 1, 1986 through December 31, 1986.
This report does include the 10CFR50.59 changes for the period of January 1 through June 18, 1986 provided in the referenced FSAR update. As mentioned in the referenced letter, LP&L intends to submit future annual reports pursuant to 10CFR50.59 concurrent with the annual FSAR update required by 10CFR50.71(e). As such, the next and future 10CFR50.59 reports will use a cutoff date of June 18 consistent with FSAR updates.
If you have any questions regarding this report, please contact G.E. Wuller, Operational Licensing, at (504) 464-3499.
Ne'r[ ruly yours,
,/-
'/ & d A K.W.
ook Nucient Safety and Regulatory Affairs Manager KWC GEW:ssf Attachment cc R.D. Martin, NRC Region IV C.W. Knighton, NRC-NRR J.H. Wilson, NRC-NRR NRC Renident Inspectors Office E.L. Blake W.M. Stevenson h
/ 4 "AN EQUAL OPPORTUNITY EMPLOYER"