ML20008E129
| ML20008E129 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/20/1980 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20008E128 | List: |
| References | |
| NUDOCS 8010240240 | |
| Download: ML20008E129 (12) | |
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REPORTABLE PILGRIM NUCLEAR POWER STATION MODIFICATIONS IMPLIMENTED BETWEEN The following are modifications to the Pilgrim Nuclear Power Station Unit #1 as described in the Safety Analysis Report which were implemented between July 1,1979 and July 1,1980, under the authorization of 10 CFR 50.59 (a).
In the safety evaluations provided prior to the modifications, a statement to the effect that a modification does not involve an unreviewed safety question indicates that the modification was reviewed and it was determined that:
1.
The modification would not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safo#,y previously evaluated in the safety analysis report; 2.
The modification would not create a possibility for an accident or mal-function of a different type than any evaluated previously in the safety analysis ~ report; and 3.
The modification would not reduce the margin of safety as defined in the be~is for any Technical Specification.
4.
The modification does not involve an unreviewed safety question as defined in 10 CFR 50.59 (a) or a change in Technical Specifications.
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PDCR 77-47-Feedwater Check Valve Disk Modifications (M208-58 A&B)
This change provides soft seating on the feedwater check valves to allow a low pressure back up to the hardsurface, metal to metal seals intended for high pressure sealing.
Ref.;
FSAR Table Sr.ct. 5.2.3.5.1 This change does nJt involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 76-89-D.C. Motor Concrol Centers This change involved changing relays and the logic on selected Motor Control Centers to provide a higher voltage rating and to alann an under voltage condition.
Ref.;
FSAR Section 8.6.3 Figures 8.0-9 and 8.0-10 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 77-78-Relief and Safety Valve Open/Close Detection This change provides a means of determing the opening and closing of the automatic depressurization valves.
Ref.;
FSAR 7.4.3.3, 4.4.5 This enange does not involve an unreviewed safety question as de cribed in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 78-27A-Installation Of Telemetering Equipment This change provided a means of telemetering the Megavars data from Pilgrim I to REMVEC at Westboro, MA.
Ref.; FSAR Section 8.2.2.5 This change does not involve an unreviewed safety question as described in 10 CFR 50.52 (a) or a change in Technical Specifications.
PDCR 79-06-Flow Element in A0G System This change substitutes the existing element with a fluidic element.
This new device is unaffected by the variable humidity present at this point in the system.
Ref.;
FSAR Amendment 31 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (.a) or a change in Technical Spee fications.
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PDCR 79-11-Process Radiation Monitors This change replaced the existing gamma detectors in the main stack and reactor build.g vent process radiation monitors with beta detectors, in conjunction with electronic scaler / timers to provide greater _ assurance the des'ign bases are met.
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Ref.;
FSAR Sections 7.12.3 1&2 and 7.12.5 1&2 This change does'not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-13-Modify Seismic Supports This change is in response to I.E.Bulletin 79-02.
Ref.; FSAR Section 2.5.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-14-Reactor Feedwater Pump Circuitry Modification This change is in response to an NRC letter concerning excess core flooding after scram. The change modified the trip circuitry to provide an automatic reactor feedwater pump trip after reactor water level reaches sixty inches above instrument zero.
Ref.; FSAR Sections 14.5.4.3, 14.5.4.2.1 and 14.5.4.4 This change does not involve en unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Techniccl Specifications.
PDCR 79-15-New Motor Operators This change involves the installation of new motor operators on MOV 1301-17 and MOV 2301-5 valves.
Ref.; FSAR Amendment 34 This change does not involve an unreviewed safety question a",
described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-16-Atlas-Copco Air Compressor This change replaces.a failed Air Compressor K-109 with one identical to K-110.
Ref.;
FSAR Section 10.11.3.2 and Fig. 10.11.-1 l
This change does not involve an unreviewed safeti question as l
described in 10 CFR 50.59 (a) or a change in Technical Specifications.
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PDCR 79-17-Valve Type Change in Augmented Off Gas System A need for better flow control in the cooling water system to the A0G condenser necessitated the substitution of a trunnion type valve for the piston actuated gate valve (A09230).
Ref.; Amendment 31 FSAR This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-18-Under Voltage Trip On Auxiliary Breaker This change utilizes existing space contacts of seismically qualified under voltage auxiliary relays for bus A5 and A6 to trip the unit auxiliary breakers 152-505 and 152-605.
Ref.; FSAR Figure 8.0.1 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-20-Screenwash Sluiceway Relocation This change relocated the screenwash sluiceway to return impinged marine organisms to ambient temperature waters.
Ref.;
FSAR Section 11.6.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-22-Reactor Vessel Drain Valve This change replaced a leaking valve with one of improved design Ref.;
F3R Figure 4.3.2 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-25-ATWS-RPT This. change implements General Electric Company's anticipated transient without Scram-Recirculation Pump Trip System (and Alternate Rod Insertion)
This responds to the Safety Evaluation (Dated August 25,1971) Section 6.2 done by the Division of Reactor Licensing U.S. A.E.C.
Ref.; FSAR Section 4.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
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PDCR 79-26-Replacement of RFP Minimum Recirculation Valves This change replaced the three reactor feed pump minimum recirculation valves; FV-3435, 3436 and 3437 of the double-seated globe type with four stage turbo cascade valves.
Ref.;
FSAR Section Figure 11.8-2 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-27-A0G System Improvements This change involved new angle type steam valves, new temperature sensors and continuous drainers for the condensers.
Ref.; Amendment 31 FSAR This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) cc a cnange in Technical Specifications.
PDCR 79-28 A.1 & A.2-Reactor Shutdown Due To Loss Of the Cable Spreading Room This change added instruments and controls and modified existing equipment such that the reactor can be safely shutdown assum.ng the loss of the cable spreading room.
Ref.;
FSAR and Sections 8.4, 8.6, 8.8 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-29-Containment Atmospheric Control Monitor This change provided various tie-in connections to facilitate future installation of post-LOCA recombiners and appropriate containment atmospheric monitoring instruments.
Ref.;
FSAR Section 5.2.3.8 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-39-Torus Drainline Valve Installation This change adds valves and associated hardware to the torus to facilitate draining of the torus during refuel outages.
Ref.; FSAR Section 5.2.3.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Techni al Specifications.
PDCR 79-34-Torus Modification This change provides for new components or removal or strengthening of existing parts of the torus and support structure to return safety margins to original values and comply with 10 CFR 50.55A.
Ref.;
FSAR Section 5.2.3.3 This change does not involve an unreviewed safety question as des:ribed in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-36-Eposy Coating Of Condenser Water Boxes This change provides epoxy coatings to the tube sheets in the main condensers to prevent galvanic attack of the tube sheet material.
Ref.;
FSAR Section 11.3.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-38-Met. Panel Cable and Antenna This change connected an antenna and its cable to the control rcom Meterological panel.
Ref.;
FSAR Amendment 2.3.2 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-40-Removal of Neutron Source Holders During the 1980 refuel outage, the five (5) neutron source holders were removed from the reactor vessel.
Ref.; FSAR Section 3.3.4.11 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-41-Feedwater Sparger Replacement and Nozzle Clad Removal This change replaced t.9 original liners with liners having an integral seal to prevent leakage between liner and nozzle wall.
The stainless clad material on the nozzle interior was also removed.
Ref.; FSAR 3.3.4.6 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
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PDCR 79-42-Installation of NA-200 LPRMs
' This change replaced existing Type NA-100 LPRMs with Type NA-200 LPMRs.
Ref.; FSAR Section 7.5.6.2 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-45-Scram Discharge Header Modification This change modified the scram discharge header piping to allow improved cleaning by hydrolazing.
Ref.; FSAR Figure 3.4-8 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-46-Feedwater Heater 103A Replacement This change involved the replacement of the original feedwater heater (103A) with one of improved design.
Ref.; FSAR Section 11.8.3.2 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-47-Startup Transformer Fast Transfer Logic Change This change added time delay and latching relays to the spring changing circuitry of startup transformer 4.16 KV breakers A104. A204, A304, and A404.
This provides. automatic recharging of the breakers 20 secords after the total loss of all 345 KV off site power.
Ref.;
FSAR Section 8.4.5.1 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-49-Reactor Water Sample Valve Replacement This change removed a 900 PSI bolted and gasketed bonnet valve and replaced it with a lighter weight 1500 PSI threaded, clamp locked and seal welded valve. The valve numbers are A0220-44 and A0220-45.
Ref.;
FSAR~Section Table 7.3.1 This chance does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-52-Refuel #4 and Operation In Cycle #5 This change consists of refueling the core and operation in Cycle #5 with 184 new 8x8 fuel bundles.
Ref.;
FSAR 3.2.5 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) ar a change in Technical Specifications.
PDCR 79-54-Replacement of 125 and 250V Safety Batteries This change replaced existing 125V and 250V battery cells with identical size ard amphere hour capacity cells.
Ref.; FSAR 8.6.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-60-Containment Pressure Monitoring This change added two channels of redundant pressure instrumentation for the extended ranges of drywell pressure monitoring required by NUREG-0578.
Ref.; FSAR Figure 7.4-6 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-62-Noble Gas Effluent Monitors This change consists of three (3) field mounted detectors capable of monitoring extended ranges of noble gases with indication and recording in the central room.
Ref.; FSAR Section 7.12 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-63-Secondary Penetrations For Torus Modification Work This change provides pennanent secondary containment penetrations to facilitate routing of services (water, air and electricity) to the torus area.
Ref.; Section 5.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-64-Fast Acting Under Voltage Relays For 4160 V Emergency Bus This change provided 4 undervoltage relays, 4 time delay pick-up auxiliary relays and test switches to the 4160 V source side of A504 and A604 startup transformer breakers.
Ref.; FSAR Figure 8.0-4 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications, PDCR 80-2-CRD Platform Extensions This change provides additional working surface beneath the RPV to facilitate maintenance functions.
Ref.;
FSAR Figure 12.1-15 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specificiations.
PDCR 80-3-Primary Containment Isolation Valve Mo dification This change involves the addition of solenoid valves to provide redundant paths to and from the drywell and torus for remote venting and Nitrogen make up.
In addition, various logic changes to the existing valve control circuitry have been incorporated to meet the requirements of 10 CFR 50.44.
Ref.; FSAR Sections 5.2.3.8 and 7.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 80-4-Safety and Relief Valve Modifications This change replaced the 3 stage top works with 2 stage top works as described in G.E. FD1-172 and Target Rock report #2119 Rev.12.11.79.
Ref.;
FSAR Sections 4.4.5, Digs. 4.4-1 and 4.4 7.4.3.3.2 and 7.4.3.3.4 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 80-6-Drywell Penetrations For Containment High Radiation Monitors This change reworked spare penetrations X-101D and X-105C to accommodate G.E. high range radiation detectors (not yet installed)
Ref.;
FSAR Tables 5.2.3 and 7.3.1 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
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PDCR 80-7-Data Link For Technical Support Center This change installed a closed-circuit television camera, along with computer data links, for display of control room instrumentation in the Technical Support Center as required by NUREG 0578.
Ref.; FSAR Figure 12.3.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 80-9-Installation of Post Accident Monitoring Panels This change provides two (2) safety related control panels containing the major part of the remote display and selective control of isolation valves as required by NUREG-0578.
Ref.; FSAR Figure 12.3.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 80-10-Flanges on Start-up Air Piping on Emergency Diesel Generators This change provided flanges on the start-up put piping on the Emergency Diesel Generators to facilitate maintenance work on af ter coolers.
Ref.; FSAR Section 8.5 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 80-14-Structural Modifications To The Intake Building This change added bracing to the circulation water bays of the intake building to' strengthen t:1e walls to withstand the pressure resulting from dewatering.
Ref.; FSAR Figure 12.1-19 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 80-26-Modifications to Existing Supports on Category I Piping Systems This change added snubber lugs to the supports at 8 locations, to comply with I.E.Bulletin 79-14 or Ref.;
FSAR Section 2.5.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
t-Test - Reference Column Temperature Monitoring This test involved direct temperature monitoring of the Reactor water level reference columns ins'ide the primary containment.
This was necessary to allow accurate evaluation and calibration adjustments to be determined in response to G.E. SIL #299.
This test does not involve an unreviewed safety question as described in 10 CFR 50.59 (e) or a change in Technical Specifications.
The following changes were implemented in response to the Safety Evaluation Report issued to PNPS as Amendment 35 to the station Technical Specifications.
The report summary for each change will reference the appropriate section or figure of the FSAR.
PDCR 79-03A-1-Fire Docr Installations This change upgraded appropriate fire doors to a Class "A" rating in response to qucstion #5 of the NRC Fire Hazards Analysis evaluation.
Ref.; FSAR Section 12.2 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-03A.3-Smoke Barrier Installation This change installed 2 smoke partitions in the Turbine Building to minimize the smoke infiltration to the access control stariways during a fire.
Ref.;
FSAR Figure 12.1-2 and 12.1-4 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-03A.5-Folding Fire Door Installation This change provides a' Class "A" 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated fire door in the doorway between the A and B RBCCW pump rooms. This door is of a folding design to permit the use of the existing flood control door.
Ref.;
FSAR Figure 12.1-5 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-03B.2-Fire Damper Installation This change replaced the 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> fire rated dampers with 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated dampers in the heating and ventilating air ducts.
Ref.; FSAR Section 12.2 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
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PDCR 79-03D.1-Emergency Lighting Units This change provides emergency battery operated lighting units in selected zones having the potential of losing both normal and emergency lighting due to a fire.
Ref.; -FSAR Section 10.16.3 This change.does not involve an unreviewed safety question as described in 10 CFR 50.59.(a) or a change in Technical 5, rifications.
PDCR 79-03D.3-Flow Switches for Battery: Rooms Vent This change provided for flow switches in the ducting of the battery rooms to detect a failure of the exhaust system.
Ref.;
FSAR Section 10.9.3.4.7 This change does not involve' an unreviewed safety _ question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
i PDCR 79-08A.1-Halon Fire Suppression System i
This change provides the Computer Room with an automatic Halon 1301 gaseous fire suppression system.
Ref.;
FSAR Section 10.8.3.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change in Technical Specifications.
PDCR 79-088.4-Seismic Supports.for Fire Protection Pipeline i
This change provided 2 additional pipe supports to sustain earthquake loadings, for a fire protection line (8"-KB33) routed over MCC B-18.
Ref. ;- FSAR Section 2.5.3 This change does not involve an unreviewed safety question as described in 10 CFR 50.59 (a) or a change.in Technical Specifications.
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