ML20206D811

Annual Rept of Mods for 1986

ML20206D811
Person / Time
Site:	Oyster Creek
Issue date:	10/30/1988
From:	Wilson R GENERAL PUBLIC UTILITIES CORP.
To:	Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8811170286
Download: ML20206D811 (14)

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GPU Nuclear Corporst:o.a One Upper Pond Road

• - . N Ig Pars pra9y, New Jersey 07o54 201 316 7000 TELEX 136-482 Writer's D rect Dal Number; October 30. 1937 Mr. William T. Russell, Administrator Region !

U.S. Nuclear Regulatory Comission 631 Park Avenue King cf Prussia, PA 19406

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 10CFR50.59(b) Reporting Requirements Pursuant to the provisions of 10CFR50.59(b), enclosed is a brief description of changes made to the Oyster Creek Nuclear Generating Station as authorized under 10CFR50.59(a)(2) for the calender year 1986.

In each case, the corresponding safety evaluation concluded that there was no unreviewed safety question involved.

Should you have any questions concerning this submittal, please contact Mr.

Joseph Kowalski, Oyster Creek Licensing Manager at (609)971 A643.

Very truly yours, L'. &

R. F. W 1 son mer Director Technical Functions RFW:KB : dad (0346A)

At t achment s cc: Mr. Alexander W. Dromt'ick, Project Manager U.S. Nuclear Regulatory Commission Division of Reactor Projects I/l!

7920 Norfolk Avenue. Phillips Bldg.

Bethesda, MD 20014 Mail stop No. 316 NRC Resident Inspector Oyster Creek Nuclear Generating Station /,

Forked River, NJ 08731 //,'

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10 CFR 50.59 ANNUAL REPORT OF MODIFICAT 0NS - 1986 ,

1 B/A No. 328197 - Modification of Fire Detection Above Control Room Celling Existing fire detection system ceiling Zone D for the general Control Room area was modified to relocate six existing tonization type fire detectors for that zone and add one new detector to provide required fire protection coverage for the cable trays located in the hung ceiling space. As a result of this modification, all detectors previously I utilized for general coverage of the Control Room area were relocated for

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the concrete slab ceiling above the existing egg-crate hung ceiling.

This modification does not affect plant safety and does not constitute an i unresolved safety question, as defined in 10 CFR 50.59.

1 t B/A No. 402032 - RPS MG Sets 1 1 and 1 2 Six G.E. electrical protection assemblies were installed in the RPS Power  !

Supply. Two EPA's each are installed in series between RPS MG sets and !

the transfer panels and auxiliary power source and the transfer panels,  !

The modification provides redundant Class IE protection to the RPS power  !

supplies. The assemblics will monitor overvoltage, undervoltage, ano (

underfrequency conditions to the RPS power supplies, j I

The modification provides an assurance that the RPS power supplies will [

not be degraded in qua? tty during a seismic event, and the plant will j scram under the abnormal pc rer supply condit tons. [

The codification does not affect plant safety and does not constitute an i unreviewe6 safety question, as defined in 10 CFR 50.59. l l

J/A No. 402034 - 125V DC Systen Upgrade Phase !!!

l One set of four special brackets and uounting hardware were added on the  ;

! interior of the 125Y DC Distribution Panel "F' to enable the panel to be ,

seismically qualified to IEEE 344-1975.

i i This modification does not af fect plant safety and does not constitute an l unrevloed safety question as defined in 10 CFR 50.59.

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i l l 8/A No. 402136 -RPS/ECCS/ ESP Instrumentation _ Upgrade. Phase ! i

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Various instruments in the Reactor Protection System, Core Spr6y System,  !

Isolation Condenser System, Primary Containment Pressure Monitoring  !

Devices, and the Control Rod Drive system were upgraded. These upgrades ,

were performed to satisfy certain requirements of the following as  ;

appitcable: l NRC Generic Letter 84-?3 NRC Regulatory Guide 1.97 NRC IE Bulletin 79-27  !

NRC NUREG 0737 l Operational concerns (Drif t) of SOR 1RC switches  !

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This modification does not adversely affect plant safety and does not  !

constitute an unreviewed safety question as defined in 10 CFR 50.59. i L

B/A No. 402187 - Containment High Range Radiation Monitoring System ,

l Two High Range Radiatten Monitors have been installed in the drywell, l with readouts in the Control Room. These monitors will provide  !

information indicative of a breech in the fission product barrier, i.e.,  !

i the primary coolant pressure boundary and/or fuel cladding. The j modification is installed in response to NUREG 0737,Section II.F.1.3  ;

requirement 5. }

This modification does not affect plant safety and does not constitute an  !

unreviewed safety question, as defined in 10 CFR 50.59. 7 I

I B/A No. 402207 - Recirculation Valve Interlock Modification -

l To assure that an adequate flow path will entst fro:n the annular space (

between the pressure vessel wa.1 and the core shroud to the core region.  ;

a new alarm has been added in tn* Control Room which alerts the operator  !

when either the suction and/or tue associated discharge valve in more i than three (3) out of five (5) recirculation loops are not fully open. j An auxiliary relay which has been wired onto the control circuitry of the  :

recirculation pump suction and discharge valves in each loop has been I used to perform the necessary logi; for alarm actuation.

This modification does not affect ;:lant safety and does not constitute an [

ut. reviewed *sfety question, as defined in 10 CFR 50.59. [

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l 402248 - Contains.nt Vent and Purge Isolat_ ion on High Radiation Drywell high radiation signals are used to initiate the drywell ventilation isolation. Valve V-27-1, V-27-2, V-27-3, V-27-4, V-28-17 and V-28-18 will close on a drywell high radiation signal through two redundant high radiation laulation logic channels that will serve 6 a backup to the existing RPS isolation signals.

The modification is installed in response to the requirements'of, NUREG 0737, Item II E.4-2(7).

This xdli'ication does not affect plant safety and does net constitute an unreviewed sarety question, as defined in 10 CFR 50.59.

B/A No. 402382 - Reactor Head Vent Valve Modification This modification replaced the exitting manually operated reactor head vent globe valves V-25-21 and V-125-22 with solenoid-operated valves with retcote control, to alleviate per >conel safety and ALARA concerns.

This modification does not affect plant safety and does not constitute an "

unreviewed safety queetion, as defined in 10 CFR 50.59.

8/A No. 402415 - Torus Room Watertight Door Alarms The purpose of the Torus Room Door Alarm System is to provide information concerning the position of the torus Room doors. This modification provides a comon audible alsrm and individual open/ closed information for the Northeast and Joutheast Torus Room doors. A limit switch was installed for each door that indicates s*.stus of the respective door.

Indication lights for cach door are on Control Panel ER41 in the Reactor Building. A common alarm, derived from the two limit switches, is provided with the indicating lights in order to alert area personnel that a door has been left open.

This modification presents no detrimental effect on safety and does not pose an unreviewcd safety question per 10 CFR 50.59.

Y B/A No. 402523 - RBCCW System and Heat Exchanger Modification The systems affected by this modification are the Reactor Building Closed Cocling Water (RBCCW) and Service Water (SW) systems. The extent of the change to the RBCCW system by this modification is limited to the replacement of the RBCCW Heat Exchangers and their support pedestals, the replacement of temperature instruments TI-43 and TI-44, the replacement of pressure instruments PX-71 and PX-72, the addition of a manually operated flow control valve in the RBCCW return line from the drywell and the addition of a differential pressure gauge across the drywell RBCCL' supely 2nd return lines. ,

The extent of change to the SW system by this modification is limited to the addition of a flowrata measuring device upstream of the inlet to the RBCCW Heat Exchangers, the replacement of pressure instruments PI-3-385 and PI-3-386, and the addition of temperature instruments located in each RBCCW Heat Exchanger SW outlet neck.

The modifications do not affect plant safety and do not constitute an unraviewed safety question, as defined in 10 CFR 50.59.

b B/A No. 402546 - Alternate Coolir.g Water Supply to Augmented Spent Fuel Pool f Heat Exchanger Cooling water supply and return lines were added between RBCCW piping at ,

the augmented fuel pool heat exchanger and the Turbine Building Closed t Cooling Water System in the upper cable spreading room.

This modification provides an alternate cooling water supply to the augmented fuel pool heat exchanger NN-02C when the RBCCW is unavailable and when the plant is in-cold shutdown. The modification provides a heat .

removal path which has attributes that are equivalent to the existing heat removal path for spent fuel pool cooling.

The modification does not pose an unreviewed safety question as described in 10 CFR 50.59. I

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B/A 402547 - Drywell Equipment Drain Tank Modification Two existing solenoid operated globe valves were replaced with pneumatic

! operated plug valves. The piping was modified so that the normal flow from DEDT pumps will bypass the DEDT heat exchanger. The heat exchanger will only be utilized in the recirculation flow path when tank temperature is high.

This modification does not affect plant safety and does not create an unreviewed safety question as defined in 10CFR 50.59.

B/A No. 402576 - Turbine Building Sump 1-5 Radiation Monitor, A Liquid Radiation Monitoring System (LRMS) has been installed in the Turbine Building Sump 1-5 to protect against a possible uncontrolled release to the environment. The LRMS provides local indication, local alarm and a Control Room alarm under high radiation conditions. The LRMS is interlocked with the sump pumps 1-5A and 1-5B to terminate discharge in the event the sump becomes contaminated.

This modification does not affect plant safety and does not constitute an unreviewed safety question, as defined in 10 CFR 50.59.

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B/A No. 402613 - Feedwater Regulating Valve Hodification This modification replaces the existing trim of feedwater regulating valves ID11-A, -B and -C and 1012-A and -C. The present valve body and controller has not been modified by this change; however, for each of the l 1011 valves, a pneumatic function generator has been installed between its current-to-pneumatic (1/0) signal convertor and positioner.

This modification does not affect plant safety and does not constitute an unresolved safety issue as defined in 10 CFR 50.59.

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6-3 B/A No. 402625 - Radwaste Tank Vault Modifications This modification, which is based on Licensee Event Report.81-08 and IE Inspection Repurt No. 81-03, provides a positive means of alerting a New Radwaste (NRW) Building Control Room operator of the presence of water in any of the tank vaults. An NRW Building Control Room Annunciator System and a 120V AC power supply system to the light box has been installed in the NRW Building Control Room. The probe has been fixed to the concrete structure.

In addition, the interior surfaces of the New Radwaste Building Chem Waste Collector Tank Vaults have been coated, for the purpose of ensaring that radioactive water will not leak through the walls to the environment and to reduce significant decontamination demands following a tank overflow event.

The modifications do not affect plant safety and do not constitute unresolved safety issues, as defined in 10 CFR 50.59.

8/A No. 402635 - Appendix R Modifications to Electrical Systems A complete analysis of fire hazaids, based on Appendix R requirements, identified recommendations for electrical system aodifications, such as rerouting of existing circuits and the addition / relocation of circuit breakers and motor starters for selected equipment. The following plant systems are directly affected by these modifications:

Electrical Power System Isolation Condenser System Condensate Transfer System Ventilation Systems Control Rod Drive System Recirculation System Clean-Up System ADS /EMRV System Reactor Vessel Instrumentation The net effec't of these modifications has been a reduction in the adverse consequences of a fire relative to achieving and maintaining safe shutdown.

The modifications do not affect plant safety and do not constitute an unreviewed safety question, as defined in 10 CFR 50.59.

8/A No. 402683 - Upgrade of Plant Paging System The purpose of this modification is to correct deficiencies serious .

enough to warrant immediate attention per findings I / the Institute of Nuclear Power Operations (INPO) and the subsequent Oyster Creek plant engineering survey. The work consisted of installation of new speakers for nine (9) dead audio plant areas and the tie-in of the Site Emergency Building as part of the overall plant paging system.

This modification does not affect plant safety and does not constitute an unreviewed safety question as defined in 10CFR 50.59.

B/A No. 402685 - Seismic Upgrade of Spent Fuel Pool Cooling System (SFPCS)

The purpose of this modification is to upgrade the original SFPCS from its current non-seismic condition to a condition which will assure the pressure boundary remains intact and functional following a seismic event.

The modification consists of the following upgrades to the SFPCS in the Reactor Building:

1. Addition of eight (8) new pipe supports and nine (9) modified pipe supports.

2. Addition of a gate valve to the SFPCS for the purpose of bypassing the Radwaste Facility in the event of a seismic event. This is required in order to maintain system integrity in the event of a break in the filter / demineralization subsystem of the SFPCS.

3. Addition of seismic supports to the SFPCS heat exchangers.

4. Seismic qualification of eight (8) SFPCS valves to ensure structural integrity and operability following a seismic event.

This modification does not affect plant safety and does not constitute an unreviewed safety question as defined in 10 CFR 50.59.

B/A No. 402704 - Turbine Building Sump 1-5 Relining Turbine Building Sump 1-5 has been provided with a high density polyethylene (HDPE) liner as a replacement for the original carbon steel liner, in order to terminate future deterioration of the underlying sump concrete.

This modification does not affect plant safety and does not constitute an unreviewed safety question as defined in 10 CFR 50.59.

< B/A No. 402716 - Maintenance Platforms Drywell Elevation 51' This modification installed approximately 750 square feet of additional platforming at el. 46'-0" in the drywell to provide safe working areas during drywell maintenance activities. The platforming does not have any effect on plant systems or operation other than shortening outages by eliminating scaffolding.

The modification presents no detrimental effect on safety and does not pose an unreviewed safety question per 10 CFR 50.59.

8/A No. 402718 - New Radwaste Sparger Re)lacement in Chem. Waste / Floor Drain Collection Tanks WC-T-13/lc Plugged tank mixing spargers were replaced with the same to facilitate extended filter runs and economies in waste processing and disposal.

Existing waste piping we.s modified by adding cross connect piping to allow discharge of waste (from backwash / dewatering) to all chemical waste tanks.

Tha modification does not affect plant safety and does not constitute an unreviewed safety question, as defined in 10 CFR 50.59.

B/A No. 402719 - Modification to Hasonary Block Walls - Phase II In response to NRC Bulletin 80-11, which required assessment of the design adequacy of safety-related masonary walls, it was determined that certain walls required structural modification in order to withstand a seismic event. During Cycle llR outage the following walls were modified:

8, 17 (inside face) 18 (inside face), 19 43 and 53 This modification does not affect plant safety, and does not constitute an unresolved safety issue, as defined in 10 CFR 50.59.

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B/A No. 402728 - Alternate Shutdown Facility - 17pendix R Hodifications are installed to provide an Alternate Shutdown System for the control room, the'two cable spreading rooms and cable tunnels to comply with section III.G.3 of 10 CFR 50 Appendix R.

The plant electrical distribution system whicn directly provided power to equipment relied upon for safe shutdown during an tppendix R fire event is modified to assure proper coordination of the fault interrupting devices. The plant 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> emerger:y lighting system is also modified under the budget euthorization.

Modification made to the Emergency Lighting System includes the addition of twenty-one new emergency lighting units, nine remote-mounted halogen lamp fixtures and four additional lamps to existing unit to supplement the existing emergency lighting system.

The modifications do not affect plant safety and do not constitute an unresolved safety question, as defined in 10 CFR 50.59.

3/A No. 402729 - Appendix R Modifications to 480V Switchgear Ronm and A/B Battery Room Modifications made to the 480V Switchgear Room include:

1. Division of the existing switchgear room fire area into two independent fire zones in order to separate Division "A" and Division "B" switchgear to comply with Appendix R.

2. Independent ventilation systems for each of the two switchgear rooms.

Modifications made to the A/B Battery Room and MG Set Room Ventilation System involved changes to the system controls and instrumentation to enhance system redundancy and plant safety.

The modifications do not affect plant safety, and do not constitute un unreviewed safety question, as defined in 10 CFR 50.59.

B/A No. 402730 - Fire Protection Svid .o Appendix R Modifications Fire protection system related changes / modifications as described below were incorporated in order to comply with the Fire Hazard Analysis Report and Appendix R,Section III.G. Saf e Shutdown Evaluation Report:

1. Addition of penetration seals, including conduit sealing, and/or the addition of steel plate covers, for those fire zone boundary mechanical / electrical penetrations identified in the report. New penetrations through fire rated partitions were sealed to retain the existing fire rating of the partition.

2. Addition of Fire Detection Systems in the Monitor and Control Area and in other areas mentioned in the report to provide fire detection where electrical circuits of safe shutdown trains are located.

3. Modification to the existing 480V switchgear room halon fire protection system, in order to provide separate halon fi e suppression for each of the two independent switchgear rooms.

4. Modification to the existing diesel fuel supply system to provide an alternate source of diesel oil to the Emergency Diesel Generators.

5. Installation of water curtains at the Reactor Building equipment hatch and west corner stairwell.

6. Installation of fire dampers in the HVAC system throughout the Reactor Building.

7. Installation of an enclosure at the northeast corner of Reactor Building elevation 23'-6".

The modifications do not affect plant safety and do not constitute an unresolved safety issue as defined in 10 CFR 50.59.

B/A No. 402737 - Control Roor. Recorder Upgrade Of 14 recorders in che Control Room, one (LPRM trend) has been removed, one (RPST) has bsen replaced by two digital indicators and two selector switches, and ten ncye been replaced by new recorders. The replacements will correct variots humes engineering discrepanci(4 found during the Control Room review.

This modification does not affect plant safety and does not constitute an unreviewed safety question, as defined in 10 CFR 50.59.

B/A No. 402754 - Access to Old Radwaste Building Roof Pref abricated stairs have been secured to the outer south wall of the Old Radwaste Building to provide access to the building roof.

This modification does not affect plant safety and does not constitute an unreviewed safety question, as defined in 10 CFR 50.59.

B/A No. 402759 - Fuel Fool Heat Exchanger NN02A Replacement l

Replace the two existing original plant horizontal shell and tube fuel pool heat exchangers (NN02A and NN028) with two heat exchangers of identical design to enhance reliability of the fuel pool cooling system.

This modification does not affect plant safety and does not constitute an unresolved safety issue, as defined in 10 CFR 50.59.

B/A No. 402765 - Diesel Generator UF Trip and Protective Interlocks The purpose of this modification is to: (1) provide the necessary logic to trip the diesel generator under overloading conditions and (2) bypass the leading VAR and reverse power relays to meet the NRC criteria as applicable to SEP Topic VIII-2.

The modification bypasses leading VAR and reverse power relays during loss of offsite power and provides protection during test conditions and when the DG is connected in parallel with offsite power. The modification provides an underfrequency relay for tripping the DG breaker to protect the DB from one load. This modification also relocates the toggle switches for DG Fuel Oil Transfer Pumps and immersion Heaters from outside of the engine electrical cabinet to within the cabinet.

This modification does not affect plant safety and does not constitute an unresolved safety issue, as defined in 10 CFR 50.59.

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B/A No. 402775 - Diesel Generator Lube Oil System Modifications 1 An AC motor-driven pump (o.75 lip) and a DC back-up were added, as well as _i small piping and tubing changes. The modification will provide pressurized oil to the DG engine bearings at all times, even when the '

engine is not running. This modification was recommended by the DG unit supplier and decreased the possibility of DG and turbocharger bearing failure, i This modification does not affect plant safety and does not constitute an unresolved safety issue, as defined in 10 CFR 50.59.

B/A No. 402786 - 480V USS 1A2 and 182 Transformer Cooling Fans j Cooling fans actuated by thermal switches have been installed on transformers of USS lA2 and 182 which will increase the rating of each transformer from 2000 to 2300 kVA.

This modification does not affect plant safety and does not constitute an unreviewed safety cuestion, as defined in 10 CFR 50.59.

i-B/A No. 402787 - Chilled Water Drywell Cooling System I A new Drywell Chiller Water Cooling System has been provided to supply cooling water to the drywell coolers by bypassing the existing RBCCW -

system main feed lines to the units during outages. A piping loop is -

installed from within the drywell (RBCCW drywell coolers) to outside the l East Wall of the Reactor Building (chiller location)- This modification i improves working conditions inside the drywell during summer refueling  ;

i outages. [

This modification does not affect plant safet/ and does not constitute an i unreviewed safety ouestion, as defined in 10 CFR 50.59.

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l 8/A No. 402839 - Fire Damper Modifications IE Information Notice 83-69 initiated an evaluation of all duct penetrations through the fire barriers in all major plant areas. Based on the inspaction, nine (9) of the fire dampers were identifie1 as

- ncn-functional becaote of non-conformance to JL requirements and manufacturer's installation requi.ements. Correct ive action required modification to some ducts and replace:nent of the fire dampers. The nine (9) damper locations which were subject to these "nodifications are as follows:

1. Exhaust and supply the Electrical Tray Rnom

2. Exhaust and supply the "C" Vault in the 4160 Volt Switchgear

3. Exhaust and supply to the "D" Vault in the 4160 Volt Switchgear

4. One exhaust and two supply cpenings to the "C" Battery Reom in the 4160 Volt Switchgear area.

The modification does not affect plant safety and does not constitute an unresolved safety issue as defined in 10 CFR 50.59.

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