ML20214G280

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Annual Operating Rept of Dresden Nuclear Power Station for 1986
ML20214G280
Person / Time
Site: Dresden  
Issue date: 12/31/1986
From: Eenigenburg E
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
87-106, NUDOCS 8705260485
Download: ML20214G280 (27)


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ANNUAL OPERATING REPORT OF

. DRESDEN NUCLEAR POWER STATION, COMMONWEALTH EDISON COMPANY FOR 1986 UNIT NO.

DOCKET NO.

LICENSE NO.

1 050-010 DPR-2 2

050-237 DPR-19 3

050- 249 DPR-25 l'

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8705260485 861231

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-I TABLE OF CONTENTS Page Section 1: Dresden Unit 1 PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY-RELATED MAINTENANCE

- Amendments to Facility License or Technical

'l Specifications

- Other Changes, Tests and Experiments 2

~ Section 2: 'Dresden Unit 2

- PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY-RELATED MAINTENANCE

- Amendment-to' Facility License or Technical 3

Specifications

- Other Changes, Tests _and Experiments-

-- 4 Section 2/3: Shared Dresden Units 2 and 3

- Other Changes, Tests and Experiments 8

Section 3: Dresden Unit 3

-- PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY-RELATED MAINTENANCE

- Amendments to Facility License or Technical

~ 11 Specifications

- Other Changes, Tests and Experiments 14'

- GLOSSARY 22

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-l AMENDMENTS TO FACILITY LICENSE DPR-2 (UNIT 1) OR ASSOCIATED TECHNICAL SPECIFICATIONS

'No amendments issued in 1986.

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T UNIT l'

.OTHER CHANGES, TESTS AND EXPERIMENTS MODIFICATION M12-1-76-12 Provide bettercradwaste facilities for Unit 1.

The change involved. constructing a new building over.the-Unit 1 rad-waste storage vaults, installing resin and sludge sump pumps, also decanting' pump and' associated piping.

Installing level instrumentation on the storage' tanks, and installing a HVAC system in the'new building.

The safety evaluation concluded that the margin of safety is not reduced.

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-1l AMENDMENTS TO FACILITY LICENSE

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'DPR-19 (UNIT 2) OR ASSOCIATED

. TECHNICAL SPECIFICATIONS d

- AMENDMENT #92'-

On April 28,~1986, the Nuclear Regulat'ory Commission' issued Amendment #92

'to the Dresden Facility License No. DPR-19. 'The following is a resume'.of.

theichanges in the license'for incorporation of the Amendment:

Amendment #92 provided, as :specified in Technical-Specification 3.9.B.2, that the 2/3 diesel ~ generator will be allowed a one-time-only-outage extension' of seven. (7) days along with the normal seven (7) day outage

-time.

This fourteen'(14) day.. outage is necessary-to complete-10CFR 50, s

-Appendix R modifications to the 2/3 diesel generator during the spring-of-1986.-

AMENDMENT #93 the Nuclear Regulat'ry Commission issued' Amendment #93

'On August 13,.1986, o

to the Dresden Facility. License No. DPR-19.;.The following is a resume' of the changes ~in-the license for in' corporation'of the Amendment:

LAmendment #93 provides, as specifie'd in-. Tables 3.2.5, 4.2.3,'and 4.~8.1, surveillance, calibration,. operating limits and reporting requirements of the MVRS' Process Exhaust Samplers and the MVRS HVAC Exhaust Samplers.

'for iodine and particulate gaseous effluents.

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, 1 UNIT 2 Other Changes, Tests and Experiments MODIFICATION M12-2-80-49 Replace Unit 2 Furnace Sensitized Safe-Ends with Stainless Steel Safe-Ends.

The change involved replacing certain specified furnace sensitized safe-ends which are less susceptible to intergranular stress corrosion crack-ing. The safe-ends replaced are four (4) 2-inch instrument nozzles, the-2-inch SBLC nozzle, the 4-inch top head vent and two (2) 6-inch top head instrument nozzles. Other safe-ends were supposed to be replaced, but the outdated paperwork is no longer usable by present day procedures.

This modification is terminated and considered complete by the Station.

The work completed is accepted and the subject modification,is removed from the active list.

The safety evaluation concluded that the new safe-ends meet the original design bases, and the margin of safety is unchanged.

MODIFICATION M12-2-81-11 Modify the CRD SDV Piping to Meet the NRC's SER Dated 12/1/80 and INP0's SOER 80-6 Dated 12/19/80.

The changes involved replacing the existing instrument volume with two new instrument volumes, re-routing the SDV vent line piping, adding new drain lines en the instrument volumes, adding redundant water level instrumentation on the instrument volumes, double isolation valves on all vent and drain lines and seismic hanger supports on all new and existing safety related SDV piping.

The safety evaluation concluded that the margin of safety is increased.

MODIFICATION M12-2-81-12 Install New 125 Volt DC Switchgear for Fire Protection Separation of the Division I and Division II Distribution Buses.

The change involved separation of the two 125 volt DC Division buses by physically re-arranging the two divisions and electrically separating the two divisions by separate disconnect switches.

The safety evaluation concluded that the margin of safety has been improved.

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MODIFICATION M12-2-83-16 Replace the Existing MSL Radiation Monitors With Modern and Technically Superior Monitors The existing MSL radiation monitors RM2-1734-A,-B,-C and -D vere replaced by modern, technically superior (state-of-the-art) monitors. These com-patible units are being used since spare parts for the old style monitors are non-existent.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2-83-25 Install Reactor Pressure Indicator Gauges on Instrument Racks 2202-7 and 2202-8.

The change involved the addition of the Rx pressure indicators on the 517'6" elevation of the reactor building, independent of the Rx pressure indicators on 546'6" elevation racks 2202-5 and 2202-6, to provide redundancy in the unlikely event that both the control room and local i

Rx pressure indicators become inaccessible. The modification complies with 10CFR 50, Appendix R requirements.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2-83-38 Replace HPCI Pressure Indicators and Pressure Switches per I.E. Bulletin 79-01B.

The change involved replacing the existing DPIS 2-2352 and DPIS 2-2353 pressure indicators and the PS-2-2389-A,-B,-C,-D pressure switches with environmentally qualified instrumentation per I.E. Bulletin 79-01B. The new replacements are analog transmitter-trip Rosemount, Inc. instruments and hardware, and was installed as seismic Category I instrumentation.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2-83-40 Replace Reactor Water Level Instruments, LPCI Pressure Instruments and SBGT Instruments per I.E. Bulletin 79-01B.

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The change involved replacing existing reactor water level switches l

2-263-57A.-57B,-58A and -58B reactor water level transmitters 2-263-73A,

-73B, SBGT flow transmitter 2/3-7541-45A,-45B, LPCI DPIS 2-1501-55A.-55B, LPCI pressure transmitters DPS 2-1543-A,-B with environmentally qualified l

instrumentation per I.E. Bulletin 79-01B. The existing racks were modi-fled to accept the new analog transmitter-trip Rosemount, Inc. instrumen-l tation and associated hardware, all of which was installed as seismic Category I equipment.

The safety evaluation concluded that the margin of safety is not reduced.

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1 MODIFICATION M12-2-84-14 Install Flow Reversing Valves, Pressure Gauge and Flanges on the CCSW Vault Coolers to Allow End Tank Removal The change involved the addition by cutting and welding of flow reversal valves, flanges and pressure gauges on CCSW pump coolers 2-5700,-30B,-30D to allow end tank removal. The coolers are now easier to flush clean with

.the flow reversing capability and the local pressure gauge allows operat-ing to monitor the coolers.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2-84-16 Install Position Switches on Air-Operated Sample Line 2-0233 Valves 2-220-44 and -45.

The change involved installing two position switches that are environ-mentally qualified per I.E. Bulletin 79-01B on the 2-220-44 and the 2-220-45 sample line 2-0233 valves. The position switches and associated indicating lights will be mounted in the control room for better operating practices.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2-84-17 Install an Environmentally Qualified and Redundant Leak Detection System in the RWCU Room.

The change involved the installation of two (2) trains of five (5) RTD's, each of which input into a control room alarm and temperature switch.

Each train is electrically fed from a different source. This was ac-complished per I.E. Bulletin 79-01B criteria because of a possible upgrade of this system in the future.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2-84-38 Install Seismic Restraints on Reactor Building Instrument Racks per I.E.

Bulletin 79-01B.

The change involved the addition of bracing on instrument racks 2202-5,

-6,-7,-8,-19A,-19B and -28 by welding and anchor bolting. This was accomplished to ensure the racks are environmentally qualified per I.E.

Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2-84-40 Install a Baffle Between the D2 Diesel Generator Engine Crankcase Detec-tor and the Engine Accessory Gear Train Housing I

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  • 1 The change involved the addition of the baffle plate to alleviate any possible false crankcase pressure alarms during acceleration from zero to full speed following a cold start demand.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2-84-46 Install New Hydrogen Addition Control' Panel in Control Room The change involved relocating existing instrumentation into the new control room panel, add additional signals into the plant process computer and provide in-line calibration capability for the Orbisphere

  1. 2913 dissolved oxygen monitors.

The safety evalua, tion concluded that the margin of safety is not reduced.

MODIFICATION M12-2-85-2 Reinforce 250 Volt DC Battery Rack The change involved reinforcement of the 250 volt DC battery rack by the addition of 2k-inch angle iron and unistrut. This was accomplished because of seismic considerations per SEP commitment, Topic III-6.

The safety evaluation concluded that the battery availability is enhanced and therefore the margin of safety is increased.

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' UNIT'2/3

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'Other Changes, Tests and Experiments MODIFICATION M12-2/3-78-4

Modify the. Fire' Suppression and Detection Systems to Meet the New NRC'

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Requirements.

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'The change' involve'd upgrading'the existing' fire sprinklers and the addition of sprinkler systems to meet-the current NRC requirements and standards.'. This was" accomplished by cutting and welding per the: Auto-matic. Sprinkler Corporation and Station. procedures.

i The safety evaluation concluded that the upgraded fire protection system will; increase the margin of safety.

h MODIFICATION M12-2/3-82-12 6

Construct a Two Story Building for a New Shift Engineer's Office, Locker 1 Rooms and a Decontamination Facility and Whole Body Counter Area h

The change involved the addition of a two story building between the old administration-building and the Unit 1 south auxiliary bay.. The upper floor will be utilized for the Shift Engineer's office-and lower floor was to be-locker rooms, a decontamination area, and a'whole body counting area.. Subsequently the lower floor has become a Radiation Protection Department office and a decontamination area.

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The old Shift Engineer's office became a TMI addressed commitment to 2

become a redundant HVAC area for the control room.-

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2/3-82-21 Install Relays to Protect Diesel Generator During Surveillance Tests and 4

Provide Underfrequency Trip Bypass During Auto-Start Operation The change involved specific wiring changes and the addition of relays in the trip and alarm circuits of the diesel generator to provide protection I

during surveillance testing and during auto-start conditions.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2/3-83-11 Control, Isolate and Fire Protect the 2/3 Diesel Generator Auxiliaries The change involved the addition of a transfer switch, an isolation switch and replacement of the cables that feed the 2/3 diesel generator vent fan and the 2/3 diesel generator oil transfer pump. The new switches and the' replaced cables that have a one-hour fire rating are the result of 5

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the Safe Shutdowns Analysis in accordance with 10CFR 50, Appendix R criteria.

'The safety evaluation concluded that the margin of safety is not reduced and the 2/3 diesel generator's availability is increased.

MODIFICATION M12-2/3-83-14 Modify the 2/3 Diesel Generator Logic to Allow Operation Whenever There is a Fire in the Five Major Areas of the Plant The change included the addition of a 4KV bus and switchgear and modifi-cation of the 2/3 diesel generator logic circuit. This was accomplished to allow manual simultaneous closure to buses 23-1 and 33-1 and provide isolation of power and control feeds for the 2/3 diesel generator and

'its auxiliaries per 10CFR 50, Appendix R requirements.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2/3-83-29 Install Shield Doors on Standby Gas Treatment System Control Panels

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The change involved the installation of shield doors on the SBGT control panels to isolate the cabinets from the harsh environment caused by the filters on the trains.

The safety evaluation concluded that the margin of safety is increased because the shield doors aid in proper equipment operation.

MODIFICATION M12-2/3-84-11 Replace the Crankshaft Vibration Damper and Modify the Lubricating 011 Filter Valve and the Stainer Housing Valve on the 2/3 Diesel Generator The change involved replacement of the viscous crankshaft vibration damper with a gear type crankshaft damper. The old style damper is no longer manufactured, and the new style does not require any maintenance, other than normal inspections. The modified valves will provide better seals with positive spring loading of the machined surfaces, which retain more oil in the valve housings after engine shutdown.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-2/3-84-18 Install a Baffle Between the 2/3 Diesel Generator Engine Crankcase Detector and the Engine Accessory Gear Train Housing The change involved the addition of the baffle plate to alleviate any possible false crankcase pressure alarms during acceleration from zero to full speed following a cold start demand.

The safety evaluation concluded that the margin of safety is not reduced.

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'd' MODIFICATION M12-2/3-84 '

-Install Isolation. Valves,' Fuel Lines, and the Crankcase Drain Lines of' the Security, Diesel The. change' included'the installation of isolation valves on the primary and secondary fuel lines of the Security diesel,'and an isolation valve-on-the crankcase oil drain line. 'Also, bleed valves were-installed on the primary'and secondary fuel filter housing.7 These. valves:were installed.to provide better availability.of the Security diesel =in.the-

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unlikely event of'a loss of allfelectrical power.to the gatehouse.

-c The' safety evaluation concluded that the' margin of safety-is not reduced.

MODIFICATION M12-2/3-84-81

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Install Curbs by.the Entrances to the Unit 2 and Unit-3 HPCI Pump Rooms The' change involved the-installation of concrete curbing near and in front of the entrances to the D2 and D3 HPCI rooms. This was accomplished

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to provide protection against-fire. hazards by preventing flammable liquids from. flowing into or out of the HPCI rooms.

-The safety evaluation ~ concluded that the. margin of safety is not reduced.

MODIFICATION M12-2/3-85-35 Install aLPressure Gauge on'the Suction Side of the 2/3 Diesel Generator Cooling Water Pump

'The change-involved'the' installation of:a pressure gauge and isolation valves on the' suction side of the 2/3 diesel generator cooling water

. pump. This was accomplished-by cutting and welding of a 1/2-inch tap to' the existing 8-inch suction line to facilitate IST monitoring capa-bilities.

The safety evaluation concluded that-the margin of safety is not reduced.

AMENDMENTS TO FACILITY LICENSE DPR-25 (UNIT 3) OR ASSOCIATED TECHNICAL SPECIFICATIONS AMENDMENT #86 On May - 27, 1986, the Nuclear Regulatory Commission issued Amendment #86 to the Dresden Facility License DPR-25.

The.following is a resume' of the changes in the license for incorporation of the amendment.

Amendment #86 provides specification, surveillance, calibration and reporting requirements to detect failure of the isolation condenser supply and return lines and actuate isolation. The sensors on the supply and return sides of the isolation condenser are arranged such that any one (1) of the four (4) sensors (two on the supply and two on the return) can cause isolation of the lines. To meet the single failure criteria, all four (4) sensors and associated instrumentation are required to be operable when fuel is in the reactor.

AMENDMENT #87 On July 24, 1986, the Nuclear Regulatory Commission issued Amendment #87 to the Dresden Facility License DPR-25.

The following is a resume' of the changes in the license for incorporation of the Amendment:

The License and Technical Specification changes support D3C10 operation with a mixed core of GE P8x8R, Exxon 8x8 and Exxon 9x9 fuel assemblies, Single Loop Operation (SLO), an expanded power / flow map, and revised Exxon methodology. The following sections outline the major areas revised in DPR-25:

A.

License Changes The requirements for SLO were removed from Facility Operating License No. DPR-25 (Section 3.L) and placed within various sections throughout the Technical Specifications.

B.

Technical Specification Changes MCPR 1.

The MCPR Safety Limit in Section 1.lA has been changed to 1.05 for all fuel types.

2.

The MCPR Operating Limit in Section 3.5.K has been changed to 1.33 for 8x8 fuel and 1.39 for 9x9 fuel.

In addition, the 10%

scram insertion time limit has been increased to 2.73 seconds and if exceeded, the MCPR Operating Limits shall be increased by the amount equal to 0.143t-0.39 for all fuel types (t is the average 90% scram insertion time).

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3.

New reduced flow MCPR Operating Limit Curves (Figure 3.5-2) for both 8x8 and 9x9 fuel have been incorporated in Section 3.5.K.

4.

The SLO MCPR Safety Limit and Operating Limit requirements have been incorporated in Sections.1.1.A and 3.5.K respectively.

MAPLHGR 1.

Several MAPLHGR Curves (Figure 3.5-1) for GE fuel types have been deleted from Section 3.5.I.

In addition, a curve for Exxon 9x9 fuel has been added to Figure 3.5-1.

2.

The SLO MAPLHGR penalty has been incorporated into Section 3.5.I which requires the MAPLHGR values to be reduced by a multiplica-tive factor of 0.70.

LHGR The local LHGR limits for Exxon fuel have been incorporated into Section.3.5.J (as a function of exposure). The GE LHGR limit is also included on the same figure (3.5-1A).

-Expanded Power / Flow Map The power / flow map (Figure 2.1-3) has been revised to include the expanded operating region along the APRM Rod Block Line which is supported by Exxon's Extended Load Line Limit Analysis (ELLLA).

Limiting Safety System Setting For SLO,- APRM Flux Scram Trip Setting in run mode and APRM Rod Block Setting have been incorporated into Sections 2.1.A.1 and 2.1.B, respectively.

In addition, Table 3.2.3 has been revised to reflect the SLO altered APRM upscale (flow biased) rod block equation and SLO altered Rod Block Monitor upscale (flow biased) equation.

Jet Pumps and Recirculation Pumps 1.

Section 3.6.G.3 has been split into two sections (3.6.G.3 and i

3.6.G.4).

The new 3.6.G.3 section requires that the indicated

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core flow be conservatively adjusted for SLO.

Section 3.6.G.4 requires immediate corrective action if flow indication failure occurs for two or more jet pumps.

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2.

Section 3.6.H.3 has been revised to allow SLO except with the l

Master Flow Control in Auto.

Section 3.6.H.4 and the SLO i

requirements from the license have also been included in Section j

3.6.2) that typically exhibits less margin to stability.

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Section 3.6.A.4 has been moved to Section 3.6.H.4 along with corrective action to restore operation within the prescribed thermal power limit during natural circulation.

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AMENDMENT #88 On August 13, 1986, the Nuclear Regulatory Commission issued Amendment #88 to the Dresden Facility License DPR-25.

The following is a resume' of the changes in the license for incorporation of the Amendment:

Amendment #88 provides, as specified in Tables 3.2.5, 4.2.3, and 4.8.1, surveillances, calibration, operating limits and reporting requirements of,the MVRS Process Exhaust Samplers and the MVRS HVAC Exhaust Samplers for iodine and particulate gaseous effluents.

AMENDMENT #89 On September 2, 1986, the Nuclear Regulatory Commission issued Amendment #89 to the Dresden Facility License DPR-25.

The following is a resume' of the changes in the license for incorporation of the Amendment:

Amendment #89 provides the surveillance, calibration and reporting requirements of the Analog Trip System (ATS) as specified and estab-lished by Licensing Topical Report NED0-21617-A (December, 1978), pertain-ing to reactor low water level instrumentation.

UNIT 3 Other Changes, Tests and Experiments MODIFICATION M12-3-81-12 Install New 125 Volt DC Switchgear for Fire Protection Separation of Division I and Division II Distribution Buses The change involved separation of the two (2) 125 volt DC Division buses by physically re-arranging the two divisions into separate cable trays and providing separate disconnect switches.

The safety evaluation concluded that the margin of safety has been improved.

MODIFICATION M12-3-81-44 Install Torus Attached Piping (TAP) and Associated Supports as Part of the Dresden 3 Mark I Containment Program The change involved the installation of TAP and supports to enable SRVD piping to withstand the Mark I hydrodynamic loading condition transmitted by the torus during a LOCA. This modification was accomplished by cutting, welding, and installation of new piping and supports per the D3 Mark I containment program.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-83-16 Replace the Existing MSL Radiation Monitors with Modern and Technically Superior Monitors The existing MSL radiation monitors RM3-1734-A,-B,-C and -D were replaced by modern, technically superior (state-of-the-art) monitors. These new, compatible units are being utilized because spare parts for the old style monitors is non-existent.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-83-23 Provide Alternate Source of Electrical Power to Isolation Condenser Valves M03-1301-1 and M03-1301-4 The change involved the addition of a source of electrical feed to the M03-1301-1 and -4 valves from Unit 2 MCC 28-1.

Transfer switches were installed in the TIP room and shutdown cooling pump room to provide throw-over capabilities per 10CFR 50, Appendix R fire protection requirements.

i The safety evaluation concluded that the margin of safety is improved.

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t MODIFICATION M12-3-83-24 Provide Cooling for CRD Pumps 3A and 3B from the Service Water System The change involved the installation of 1-inch piping from the service water system to provide alternate cooling of the CRD pumps in the event normal cooling is not available.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-83-37 Replace Core Spray Instruments with Environmentally Qualified Instruments The change involved the replacement of Core Spray flow instruments FS3-1464-A and -B with environmentally qualified instruments per I.E.

Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-83-38 Replace HPCI Instruments with Environmentally Qualified Instruments The change involved the replacement of pressure instruments DPIS 3-2352, DPIS 3-2353, PS3-2389-A -B,-C and -D with environmentally qualified instruments per I.E. Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-83-57 Install Shear Lugs on MSL for Snubber Pipe Clamps The change involved adding, by welding, shear lugs on vertical MSL snubber locations 41, 42 and 43 to prevent slippage of the pipe clamp.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-9 Modify the Closing Circuit for Core Spray Valves 3-1402-25A and 3-1402-25B The change involved rewiring the closing logic circuit of the 3-1402-25A and -25B CS valves so that the valves still have throttling capabilities, but once closed will not be " hammering" through the torque switch con-tacts.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-13 Replace the Acoustic Accelerometers on the Main Steam Safety and Relief Valves

The change involved replacing the existing acoustic monitoring system on the main steam line safety and relief valves with an environmentally qualified monitoring system per NUREG-0737 Item 11.D.3.

l The safety evaluation concluded that the margin of safety is not reduced because the new equipment provides the operator with more reliable infor-mation.

MODIFICATION M12-3-84-14 Install Flow Reversing Valves, Pressure Cauge and Flanges on the CCSW Vault Coolers to Allow End Tank Removal The change involved the addition, by cutting and welding, of flow reversal valves, flanges and pressure gauges of CCSW pump coolers 3-5700-30B and 3-5700-30D to allow end tank removal. The coolers are now easier to flush clean with the flow reversing capability and the local pressure gauge allows operating to monitor the coolers.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-15 Install Indicating Lights for Valve 3-1201-1A on Control Room Panel 903-3 The change involved the addition of position indicating lights on the control room panel 903-3 for RWCU isolation valve 3-1201-1A.

This was accomplished to provide valve position indication with other valve groups on the 903-3 panel..

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-16 Install Position Switches on Air-Operated Sample Line 3-0233 Valves 3-220-44 and -45 The change involved installing two (2) position switches per I.E. Bulletin 79-01B on the 3-220-44 and 3-220-45 sample line 3-0233 valves. The posi-tion switches and associated indicating lights are mounted in the control room for better operating practices.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-17 Install an Environmentally Qualified and Redundant Leak Detection System in the RWCU Room The change involved the installation of two (2) trains of five (5) RTD's each of which input into a control room alarm and temperature switch.

Each train is electrically fed from a different source. This was accomplished per I.E. Bulletin 79-01B criteria because of a possible up-grade of this system in the future, t

_17-I The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-28 Replace the Torus Pilot Versa Solenoid Valve S0-3-1601-50B The change involved replacing the existing solenoid valve So-3-1601-50B with an environmentally qualified solenoid valve per I.E. Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is not reduced because the replacement solenoid will perform its function throughout the specified design range.

MODIFICATION M12-3-84-38 Install Seismic Restraints on Reactor Building Instrument Racks per 1.E. Bulletin 79-OlB The change involved the addition of bracing on instrument racks 2203-5,

-6,-7,-8.-19A.-19B, and -28 by welding and anchor bolting.

This was accomplished to ensure the racks are environmentally qualified per I.E.

Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-40 Install a Baffle Between the D3 Diesel Generator Engine Crankcase Detector and the Engine Accessory Gear Train Housing The change involved the addition of the baffle plate to alleviate any possible false crankcase pressure alarms during acceleration from zero to full speed following a cold start demand.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-49 Replace Motor #3-57A6A on West LPCI Room Cooler The change involved replacing motor #3-57A6A on the west LPCI room cooler with an environmentally qualified motor per I.E. Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is not reduced because the motor is now qualified for normal and post-accident environ-mented conditions.

MODIFICATION M12-3-84-50 Replace Motor #3-57A6B on East LPCI Room Cooler The change involved replacing motor #3-357A6B on the east LPCI room cooler with an environmentally qualified motor per I.E. Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is not reduced because the motor is now qualified for normal and post-accident environ-mented conditions.

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MODIFICATION M12-3-84-84 Replace 3-Way control and Test Valve on Fire Alarm Sprinkler Valve 3-41198-500 The change involved replacing the 3-way control and test valve with two (2) ball valves and a tee.

This was accomplished because the old style valve is no longer available.

The' safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-91 Replace Microswitches and Install Quick Disconnects on the MSL Tunnel Temperature Switches The change involved replacing microswitch BZ-R184-P5 with an environ-mentally qualified microswitch and installing E.Q. quick disconnects on temperature switches TS 3-261-15 A thru D, TS 3-261-16 A thru D, TS 3-261-17 A thru D and TS 3-261-18 A thru D per I.E. Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is maintained.

MODIFICATION M12-3-84-103 Replace the Existing Recirculation Valve Motor on Valve 3-202-5B with an Environmentally Qualified Motor per I.E. Bulletin 79-01B The change involved replacing the existing motor with a "Limitorque" motor that is environmentally qualified and designed for greater relia-bility.

The safety evaluation concluded that the margin of safety is not reduced because the new motor will perform its function throughout the design range of the originally installed motor.

MODIFICATION M12-3-84-104 Replace the Existing Recirculation Valve Motor on Valve 3-202-5A with an Environmentally Qualified Motor per I.E. Bulletin 79-01B The change involved replacing the existing motor with a "Limitorque" motor that is environmentally qualified and designed ror greater relia-bility.

The safety evaluation concluded that the margin of safety is not reduced because the new motor will perform its function throughout the design range of the originally installed motor.

MODIFICATION M12-3-84-118 Modify Control Logic of the Drywell Coolers and RBCCW Operation The change involved wiring movements and re-connection of the drywell coolers and RBCCW control logic. This was accomplished to allow

s continuous operation of the system to reduce drywell pressure after a scram. The drywell coolers and-the RBCCW pumps will automatically trip only when there is a concurrent ECCS signal and a loss of normal control

v power.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-84-163 Remove Temporary Off-Gas Monitor and Sample Lines The change involved the removal of temporary off-gas monitor KR 85, its associated sample lines and capping the take-offs. This was accomplished because the temporary monitor has not been used for some time and is no longer required.

The safety-evaluation concluded that the margin of safety is not red"ced.

MODIFICATION M12-3-85-2 Reinforce 250 Volt DC Battery Rack The chan);e involved reinforcement of the 250 volt DC battery rack by the addition of 2k-inch angle iron and unistrut. This was accomplished k

because af seismic considerations.

SEP commitment, Topic III-6.

~

The saft.ty e' valuation concluded that the battery availability is enhanced and therefore the margin of safety is increased.

MODIFICATION M12-3-85-16 Replaced and modified the majority of Unit 3 piping susceptible to intergranular stress corrosion cracking with new material (316 NG) and improved welding techniques. Affected systems included Reactor Recircu-lation, Reactor Water Cleanup, Shutdown Cooling, Core Spray, Low Pressure Coolant Injection, Isolation Condenser, Jet Pump Instrument Safe-ends and the Control Rod Drive return line and safe-end. Modification included replacement of Isolation Condenser condensate elbow taps with an anubar and miscellaneous other small scale improvements on the affected sections of piping.

The safety evaluations completed for this modification concluded the margin of safety is maintained or improved by 212 facets of the project.

MODIFICATION M12-3-85-17 Removal and Re-installation of Mechanic..- In.. a trences Associated with the Unit 3 Recirculation Piping Replacement Modification (M12-3-85-16) y This modification provided the framework for controlling removal, i

re-installation and in some cases mod:.fications to mechanical components and structures tnat were interferences to the pipe replacement.

The safety evaluation concluded that the margin of safety was maintained for all interferences re-installed in a like-for-like configuration and wether maintained or improved for interferences which were modified.

s t

)

1

~~

4-N'

" MODIFICATION M12-3-85-25 Replace the-125 Volt DC Batteries and Battery Rack The change involved replacing the existing 125 volt DC plante batteries with lead calcium batteries and replacing the battery rack. The new batteries are. sized to provide sufficient power for the worst case acci-

-dent profile and the new rack is seismically qualified to support the-batteries.

The' safety evaluation concluded that the margin of safety is maintained.

MODIFICATION M12-3-85-26 Removal and Re-installation of Electrical Interferences Associated with the Unit 3 Recirculation Pipe Replacement Modification (M12-3-85-16)

This modification provided the framework for controlling _ removal, re-installation and in some cases modifications to the electrical compo-nents that were interferences to the pipe replacement. Most interferences were re-installed for like-for-like.

The safety evaluation concluded that the margin of safety was maintained for those re-installed like-for-like and either maintained or improved for those interferences modified.

MODIFICATION M12-3-85-28 Construct a Material Interlock to Facilitate the Passage of Material Into and Out of the Unit 3 Reactor Building to Support the Unit 3 Recircula-tion Pipe Replacement Modification (M12-3-85-16)

A new interlock was constructed against the south exterior wall of the Unit 3 reactor building at-the location of an existing steel door.

Utilization of the building and opening of the existing door are control-led through an Administrative procedure.

The safety evaluation concluded that the margin of safety is not reduced through the existence or usage of this interlock.

MODIFICATION M12-3-85-30 Install Push-to-Make Pushbutton Switch on SRM #22 The change involved the installation of the pushbutton switch, contacted between terminals #6 and #12 (operate mode) of SRM #22 to provide in-line calibration of the unit while in an operating condition.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-85-54 Seal the Solenoid Connecting Conduit of the Safety / Relief Valves The change involved the addition of "RayChem" sealant in the solenoid connecting conduits of the safety / relief valves. Also, the installation l

m-s t, ;;..

I I

of heat shrink tubing over the sealant..

l The safety evaluation concluded that.the margin of safety is not reduced.

- MODIFICATION M12-3-85 !'

Replace Limitorque Valve-Operator of M03-1501-3A

.The change involved replacing th'e existing Limitorque valve operator of LPCI valve M03-1501-3A with~a Limitorque valve operator per I.E. Bulletin 79-01B.

The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-85-59 Replace Limitorque Valve Operator of M03-1501-3B The change involved replacing the existing Limitorque valve operator of-LPCI valve M03-1501-3B with a Limitorque valve operator per I.E. Bulletin

.79-01B.

I The safety evaluation concluded that the margin of safety is not reduced.

MODIFICATION M12-3-85-70

~

Modify Closing Circuitry of Certain 4KV Bus Breakers The change involved removing the associated test switches.and lockout relay permissive contact on the 4KV feed breakers #3105, #3201', #3312 and

  1. 3401 closing circuitry. This change allows an automatic transfer of off-

-site power from transformer 32 to transformer 31, independent of the cause of power interruption to transformer 32.

The safety evaluation concluded that the margin of safety'is increased.

~,_

GLOSSARY The following is a list of abbreviations which may appear in this report:

ADS-

- Automatic Depressurization System AO

- Pneumatic Operated Valve (Air Operated)

APLHGR

- Average Planar Linear Heat Generation Rate APRM

- Average Power Range Monitor AR1

- Alternate Rod Injection ARMS

- Area Radiation Monitoring System ATS

- Analog Trip System ATWS

- Anticipated Transient Without Scram BKR

- Motor Control Center or Bus Breaker-CAD / CAM

- Continuous Air Dilution / Continuous Air Monitoring CCSW

- Containment Cooling Service Water Pump CS

- Core Spray CRD

- Control Rod Drive CTP

- Core Thermal Power CW

- Concentrated Waste D/G

- Diesel Generator DPIS

- Differential Pressure Indicating-Switch ECCS

- Emergency Core Cooling System EGC

- Economic Generation Control EHC

- Electro-Hydraulic Control Eg

- Environmentally Qualified ESS

- Essential Service System FIC

- Flow Indicating Controller FPC

- Fuel Pool Cooling FSAR

- Final Safety Analysis Report

FW

- Feedwater GSLO

- Gland Seal Leak Off 13}

- Hydraulic Operated Valve HPCI

- High Pressure Coolant Injection System HRSS

- High Radiation Sampling System HVAC

- Heating,. Ventilation, and Air Conditioning HVPS

- High Voltage Power Supply ILRT

- Integrated Leak Rate Test IRM

- Intermediate Range Monitor ISI

- In-Service Inspection LHGR

- Linear Heat Generation Rate ILRT

- Local Leak Rate Test LPCI

- Low Pressure Coolant Injection System LPRM

- Local Power Range Monitor LTPF

- Limiting Total Peak Factor MAPLHGR

- Maximum Average Planar Linear Heat Generation Rate MCPR

- Minimum Critical Power Ratio pi}

- Motor Generator j

MO or MOV - Electric Motor Operated Valve MSIV

- Main Steam Isolation Valve MSL

- Main Steam Line MSLHR

- Main Steam Line High Radiation MSV

- Main Stop Valve MVRS

- Mobile Voluma Reduction System OBE

- Operation Base Earthquake RBCCW

- Reactor Building Closed Cooling Water System RBM

- Rod Block Monitor RETS

- Radiological Effluent Technical Specifications

3 R_M

- Remotely Operated Manual Valve RPIS

- Control Rod Position Indication System RPS

- Reactor Protection System RWCU

- Reactor Water Cleanup RWM

- Rod Worth Minimizer SBLC

- Standby Liquid Control System SCRE

- Shift Control Room Engineer SDV

- Scram Discharge Volume SER

- Safety Evaluation Report SGTS

- Standby Gas Treatment System SJAE

- Steam Jet Air Ejector S0

- Solenoid Operated Valve SPING

- System Particulate Iodine and Noble Gas SRM

- Source Range Monitor SRDV

- Safety Relief Valve Discharge SSG

- Secondary Steam Generator TAP

- Torus Attached Piping TBCCW

- Turbine Building Closed Cooling Water System TIP

- Traversing In-Core Probe IPE

- Total Peaking Factor P

a

- Micro Micro Ammeter Nuclear Instrument

r Commonwealth Edison 6

Dresden Nuclear Power Station R.R. #1 Morris, !!Iinois 60450 Telephone 815/942-2920 May 13, 1987 EDE LTR:

87-106 Director, Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk

Dear Sir:

Enclosed, please find Dresden Station's operating data for the year 1986. This information is supplied to your office per the instruc-tions set forth in Regulatory Guide 1.16.

Sincerely, i

E. D. Eeni en urg Station Maha er Dresden Nuclear Power Station EDE:DCM:hjb Enclosure cc: Region III, Regulatory Operations, U.S. NRC Chief, Division Nuclear Safety, State of IL U.S. NRC, Document Management Branch Nuclear Licensing Administrator Nuclear Fuel Services Manager Nuc. Sta. Div. Vice Pres.

Manager, Tech. Nuc. Sta.

Tech. 5taff A.E.

(2)

On-Site NRC Inspector Sta. Nuc. Eng. Dept.

Ass't. Supv. Tech. Services Comptroller's Office Sta. Q.A. Dept.

PIP Coordinator INPO Records Center File /NRC Op. Data j

File / Numerical fj b

i