ML20217C170

Supplement to Annual Rept for LaSalle County Station, for Period of Jan-Dec 1997

ML20217C170
Person / Time
Site:	LaSalle
Issue date:	12/31/1997
From:	Dacimo F COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9804230233
Download: ML20217C170 (11)

Text

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• ** l.a%alle ( ernorating Stath in 2 Nil Nortli 21st Ro.nl starsrilles.11613 a I 9 5' l'riMis. W W ni April 17,1998 1 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

)

Subject:

Supplement to Annual Report for LaSalle County Station LaSalle County Station, Units 1 and 2 4 Facility Operating License NPF-11 and NPF-18 l

NRC Docket Nos. 50-373 and 50-374 )

Reference:

Annual Report for LaSalle County Station LaSalle County Station, Units 1 and 2 Facility Operating License NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Enclosed is the supplemental report of 10 CFR 50.59 safety evaluations for LaSalle County Station for the period of January,1997, through December,1997.

The evaluations concluded that there were no unreviewed safety questions associated with the activities.

If there are any questions or comments conceming this letter, please refer them to Harry Pontious, Regulatory Assurance Manager, at (815) 357-6761, extension 2383.

Res etfully, l

Fred Dacimo l Site Vice President .

LaSalle County Station -vVU U I l \\

Enclosure ,[

cc: A. B. Beach, NRC Region til Administrator M. P. Huber, NRC Senior Resident inspector - LaSalle D. M. Skay, Project Manager - NRR - LaSalle F. Niziolek, Office of Nuclear Facility Safety - IDNS 9804230233 971231 3 DR ADOCK 0500

.. 1997 Supplemental 10CFR50.59 Safety Evaluation Summaries Design Change Package (DCP) 9700284 for the HIGH PRESSURE CORE SPRAY (HPCS)

DIESEL GENERATOR ENGINE HEAT EXCHANGER The 1B Diesel Generator Heat Exchanger,1E22-S001, contains spacer bars, similar to tie bars on modern heat exchangers. There are four of these spacer bars, evenly spaced around the heat exchanger. One spacer bar is directly in the flow stream as cooling water enters the heat exchanger. During a physicalinspection, this bar was found to be shorter than the other spacer bars, apparently to prevent the bar from vibrating in the flow stream and causing damage to the heat exchanger tubes. The design change approved having a shorter spacer bar in the location directly in the system flow path.

TEMPORARY ALTERATION (TALT) 1-0104-97, TEMPORARY POWER TO MCCs 1328-1 AND 132Y-2 A temporary power feed was installed from MCC 132Y-2/D4 to 15 KVA,480-120/208 VAC ,

distribution transformer at MCC 1328-1/E5 to provide temporary power for 15 KVA, 480-120/208 VAC distribution transformer at MCC 1328-1/E5 during Bus 152 outage. This distribution transformer provides power to the Reactor Manual Control System (RMCS).

TALT-1-0106-97, TEMPORARY POWER TO MCCs 2328-2 AND 132B-2 A temporary power feed was installed from MCC 2328-2/D2 to 15 KVA,480/120 VAC l distribution transformer at MCC 132B-2/F4 to provide temporary power for 15 KVA, i 480/120 VAC distribution transformer at MCC 1328-2/F4 during Bus 152 outage. This i distribution transformer provides power to the Reactor Manual Control System (RMCS). j DESIGN CHANGE PACKAGE 970398, ECCS EQUIPMENT AREA COOLING SYSTEM LOCAL PANEL AS-BUILT EVALUATION The DCR was issued to document the as-built mounting of ECCS Equipment Area Cooling

System Local Panels 1/2PL32J,33J,34J, and 35J. The mounting has been shown to be i acceptable and met all code /UFSAR allowables (reference S&L Caluclation L-001074,

) Revision 0). There are no functional or system changes per this DCR.

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. l 1997 Supplemental 10CFR50,59 Safety Evaluation Summaries REVISIONS TO LASALLE GENERAL ABNORMAL (LGA) PROCEDURES The Unit 1 and 2 procedures listed below were revised to be to be consistent with Revision 4 of the BWROG Emergency Procedure Guidelines (EPGs), NEDO-31331, March 1987:

LGA-01 Revision 15. RPV Control Level Control Leg I LGA-03 Revision 18. Primary Coniainment Control Hydrogen Control Leg Pressure Control Leg Pool Level Control Leg Pool Temperature Control Leg l LGA-05 Revision 11. RPV Floodina ATWS Condition Leg I

DCR 970399, VENTILATION CHARCOAL ADSORBERIFILTER UNIT DRAWING AS-BUILT EVALUATION A note was added to vendor drawings, which reads as: " Deluge valve piping header and fire protection sparger piping to be ASTM A-312 or A-376 (ASME SA-312 or SA-376) Type 304L Schedule 10S Stainless Steel with butt weld connections, or per PDT 141." This note allows like-for-like replacement of damaged portions of the deluge valve piping header and fire protection sparger piping as needed.

DIVISION 1 CORE STANDBY COOLING SYSTEMS (CSCS) WINDOW WORK This evaluation addressed plant equipment configuration in support of draining the piping and control of CSCS systems work during the outage window, which included the replacement of small sections of piping while the piping was drained.

TALTs 1-0103-97 AND 2-0037-97, TRAIN A & B AUXILIARY ELECTRIC EQUIPMENT ROOM (AEER) HEATING VENTILATION AND AIR CONDITIONING (HVAC) TEMPORARY COOLING Four 15-Ton Packaged Air Conditioning Units with water-cooled condensers were temporarily installed to provide cooling for the Unit 1 & 2 AEERs while the VE system was shutdown for repairs. The temporary cooling is necessary to maintain the AEER temperatures within the d

design limits when both trains of VE System are shutdown. Shutdown of both trains VE is necessary to facilitate the repair and inspection of the common ducts components.

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1997 Supplemental 10CFR50.59 Safety Evaluation Summaries DESIGN ISSUES ASSOCIATED WITH THE REPLACEMENT OF ECCS PUMPS SUCTION STRAINERS (DCPs 9700290,97002300,9700301,9700303, AND 9700304)

The suppression pool suction strainers for the ECCS (RHR, LPCS, HPCS System) Pumps were upgraded. The previous stainless steel wire wrapped strainers were replaced with stainless steel stacked disk, perforated plate strainers, increasing the surface area of the strainer by a factor of approximately 6. The diameter of the HPCS Pump Seal Flush Piping Drain Orifice was enlarged to a size greater than the new suction strainer hole size (3/32" diameter). j l

TEMPORARY ALTERATION TALT 1-0164-97 TO VE AND VC FANS TO PREVENT AUTO START ,

1 The control circuitry for Control Room HVAC Supply Fan OVC01CA, Control Room HVAC l Emergency Make-up Fan OVCO3CA, and Auxiliary Electric Equipment Room Supply Fan l OVE01CA were temporarily changed to prevent auto loading to buses fed from 142Y following a loss of off site power. The change is to prevent the VC and VE fans from starting l automatically upon restoration of power following a loss of off-site power and will require a  !

manual reset signal from the individual fan circuits. This temporary alteration allows return to service of the ventilation equipment without affecting the operability of the 1 A Diesel Generator.

PROCEDURE LLP-97-036 REVISION 0, CROSS CONNECTING UNIT 1 AND UNIT 2 REACTOR BUILDING CLOSED COOLING WATER (RBCCW)

The procedure aligns the RBCCW in such a manner as to cool the Unit 1 heat loads using the Unit 2 RBCCW heat exchanprs. Heated RBCCW flows into a common header at the inlet of the Unit 1 RBCCW Heat Ex.: hangers. The common heat exchanger crosstie valves are both open such that the heated RBCCW flows to the inlet header to the Unit 2 RBCCW heat exchangers. The crosstir, suction valves 1(2)WR043C to the common RBCCW pump OWRO1P is/are opened, providing suction to the common pump or to the Unit 1 pumps. A Unit 1 or common pump is run to supply the unit 1 heat loads. After the heat loads, the RBCCW retums to the <:ommon header at the inlet of the unit 1 RBCCW heat exchangers.

l DIVISION 2 CSCS SYSTEM WINDOW WORK (TEMPORARY ALTERATIONS 1-0122 97 and

! 2-0030 97) l l The Division 2 Core Standby Cooling System (CSCS) return pipe to the CSCS pond (ultimate l heat sink) was drained to support maintenance. The piping inside the reactor building was drained by installing temporary pumps drawing from the division 2 CSCS piping, to pump either outside the reactor building or into the Unit 2 Division 3 CSCS piping. The Division 2 CSCS retum pipe inside the CSCS outfall structure at the CSCS pond was dammed and/or plugged.

Maintenance activities and design changes are being made to the division 2 CSCS system.

1997 Supplemental 10CFR50.59 Safety Evaluation Summaries RENSION TO ELECTRICAL INSTALLATION WORK SPECIFICATION T-3765 FOR MAINTENANCE / MODIFICATION WORK The Electrical Installation work Specification for Maintenance / Modification Work, LaSalle County Station Units 1 and 2 (T-3765) was revised to include guidelines for repairing damaged cable without prior Engineering approval. Engineering guidance was incorporated into Specification T-3765 to allow Maintenance the flexibility to perform a limited scope of non-safety and safety related cable repairs under the Specification without prior Ertgincedng approval. The revision to Specification Ts-3765 also allows Maintenance to perform minor racewaf changes to accommodate repairs to non-safety related cables in non-seismic areas '

under Specification T-3765 without prior Engineering approval.

RHR HEAT EXCHANGER TUBE PLUGGING Eddy Current testing determined that two of the 1 A RHR heat exchanger "U" tubes have ,

indications such that plugging is required. The two tubes were plugged with welded type plugs using a procedure provided by the heat exchanger original equipment manufacturer.

RCIC SYSTEM PANEL DRAWING AS-BUILT EVALUATION Drawing changes were initiated to document changes to reflect the as-built configuration of Unit 1 and 2 Reactor Core Isolation Cooling (RCIC) System Panels 1(2)H22-P017.

I PROCEDURE LLP-97-024 REVISION 2 Added a step to change out spool piece on the suction side of 1/2WF01P for using vendor sample pump skid to take suction from 1/2WF01P, and added a step to retum the spool piece to normal. Changed vendor procedure to show current configuration of skid, deleted valve V-19 from drawing and from procedure steps. Added a section to operate the filter in bypass to allow setting up flows before placing the filter in operation.

PROCEDURE LOP-WF-06 REVISION 9 Added a new subsection which requires jumpers to be temporarily installed to defeat the pump low level trip to drain the Floor Drain Concentrator Feed Tank below the low level trip to allow complete draining of the high TOC, conductivity, and sludge concentrated water to the Waste i Studge Tank, and to allow the tank to be filled with water that can be processed using the vendor filter skid system. Added a new subsection which requires jumpers to be temporarily installed to defeat the pump interlock with the discharge valve to flush suction and discharge piping by using flushing hoses to cross-connect main condensate and radwaste sludge subsystem piping if bottom blow performed without tank being recirculated to ensure that any sludge left in the piping is flushed out to prevent piping from plugging.

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1997 Supplemental 10CFR50.59 Saf'ety Evaluation Summaries FIRE PROTECTION PIPING DRAWING AS-BUILT EVALUATION Drawings M-71 Sheet 1 Revision AM,. M-783 Revision L, and M-787 Revision S were revised to reflect the as-built configuration of the discharge piping for Fire Pump 0FP01PA.

CORRECT UFSAR DIESEL GENERATOR DAY TANK LEVEL ALARM SETPOINT UFSAR Subsdection 9.5.4.3 is revised to read: "To ensure a reliable fast start, the diesel generator day tank standby level is maintained at an elevation to assure slight positive pressure at the engine pumps. the fuel transfer pump start setpoint and low-level alarm setpoints are established to assure an adequate net positive suction head at the engine fuel pumps and to ensure that the fuel transfer pump will start and deliver the required fuel oil before the low level alarm actuates."

The specified setpoints are incorrect for the Division 3 diesel generator. The UFSAR revision will not only correct the error but specify only the required criteria and not the result of the

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calculations or instrument setpoints specifics. The change applies to all 5 emergency diesel generators since the criteria is common to all diesel generators fuel oil systems.

HPCS DIESEL GENERATOR CONDUlT INSTALLATION DRAWING AS-BUILT EVALUATION Conduit installation drawings were revised to reflect the as-built condition of the 1.25" C (1GK) conduit routing and to shaw an additional abandoned conduit.

REACTOR BUILDING CLOSED COOLING WATER (RBCCW) CHEMICAL FEED POT DRAIN VALVES DRAWING AS. BUILT EVALUATION Piping and Instrumentation Drawings (P&lDs) M-90 Sheet 1 and M-136 Sheet 1 were revised to reflect the as-built condition of the RBCCW Chemical Feed Pot Drain Lines and Valves.

TEMPORARY ALTERATION 1-038 97, TEMPORARY POWER CABLE ROUTED THROUGH REACTOR BUILDING INTEGRATED LEAKAGE RATE TEST (ILRT) SERVICE WATER PIPE SPOOL Unit 1 Reactor Building ILRT (service water) pipe spool 1RB-786 was used to route / Install temporary power from a 480V Disconnect Switch located near main transformer to a temporary power unit in the Unit #1 Reactor building. This supported Unit 1 suppression pool cleaning  ;

and inspection, in addition to other miscellaneous activities.

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1997 Supplemental 10CFR50.59 Safety Evaluation Summaries DRAWING CHANGE REQUEST (DCR) 970561, ADDITION OF PIPE SUPPORT DETAll TO FIRE PROTECTION DRAWINGS An attemate pipe support detail for fire protection piping was qualified. The alternate hanger l detail was required because the original drawings did not provide the required hanger  !

installation details. The new attemate support detailimproves the original design margin for the support details and improves the structural stability of the pipe supports.

UFSAR REVISION FOR REACTOR POWER FLOW MAP CHANGES UFSAR Appendix G Figure G.2.3-2 " Typical Reactor Power Flow Operating Map" was revised to be cons! stent with station procedures. Added details conceming the lines found on the power to flow map. Re-titled the power to flow maps for two pump (Figure G.2.5-1) and one pump (Figure G.2.5-2) operation to include the word " typical" in their descriptions, and to clarify that they are for reference only. Added that the Core Operating Limits Report (COLR) contains the information that defines the operational boundaries of the power to flow map of interest.

Stated which parts of G.2.3-2 are for reference only The source of information for the 20%

feedwater interlock in was added in Subsection G.2.3.2.6, and the reference for the 10.1 F interlock was added to Reference Section G.7.

I TEMPORARY ALTERATION 1-0006-97, UPSTREAM ISOLATION OF VC DUCTS FOR l DAMPER MAINTENANCE l l

This activity consisted of instaillNG temporary blank off plates upstream of isolation dampers OVC15YA & OVC15YB. During normal operation when train "A"is running damper OVC15YB is closed to isolate train "B", and when train "B" is running damper OVC15YA is closed to isolate train "A". this activity also included the insertion of a temporary duct section in the place of OVC15YB to maintain the structuralintegrity of the ductwork while maintenance was performed on the damper. This temporary modification was required to allow maintenance to be performed on isolation dampers OVC15YA and OVC15YB.

PROCEDURE LOP-WF-02 REVISION 8 Added a new step for flushing suction and discharge piping when required by using a flush

. hose to cross-connect main condensate and radwaste collector subsystem piping which cross connects a clean system to a contaminated system and temporarily alters the system. This new section connects a flush hose to the valve on the temporary spool piece that was evaluated and installed per LLP-97-024. Flushing of piping helps to keep lines from plugging, and aids in lowering the radiation dose in the piping area when required.

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1997 Supplemental 10CFR50.59 Safety Evaluation Summaries PROCEDURE LAP-100-56 REVISION O this procedure involved the storage of equipment / parts in Plant Areas containing safety-related equipment. This procedure applies to all modes of plant operation including cold shutdown and defueled conditions. All temporary storage requests not meeting the intent of this procedure are assessed by Engineering on a case-by-case basis.

ECCS AND RCIC SUCTION STRAINER INSTALLATION SEQUENCE PER LLP 97-041 Special procedure LLP-97-041 was written as a control and coordination procedure to govem critical evolutions in support of the Unit 1 ECCS and RCIC suction strainer replacement while in Operating Mode 4 with fuel in the vessel.

TEMPORARY ALTERATION 1-0235-97 GAG OPEN RHR VALVE TO RESTORE OPERABILITY The manual operator of residual heat removal (RHR) valve 1E12-F090B was gagged to hold the valve open. This was done to prevent the valve form closing, even in the event of an earthquake. The specific design was originally developed for 1E12-F090A. There are no substantial differences between the locations of the valves, and the valves are identical in form, fit, and function. The valve limit switches are functionally defeated with the operator is removed. The manual operator has degraded, disassembled, and no longer functional.

TEMPORARY ALTERATION 1-0208-97 DRYWELL VENTILATION SYSTEM TEMPORARY CHANGES TO SUPPORT SRV MAINTENANCE The drywell coolers were secured during the installation and removal of those portions of this TALT that affect ventilation system operation. Two horse-shoe shaped sections of ductwork at Unit 1 elevation 794' and approximate 90 and 270 degrees azimuth were removed. Four sections of flexible ductwork, associated supports, and dampers will be removed to eliminate interference for maintenance activities. The horse-shoe shaped ducts were blanked off. The activity removed interferences for drywell maintenance activities including removal for testing of main steam safety relief valves.

PROCEDURE LOP-RH-07 REVISION 40 Added guidance in the procedure to allow an inoperable Shutdown Cooling Loop to be considered a Technical Specification attemate decay heat removal method provided the system can be operated per LOP-RH-07, and the Shutdown Cooling loop is made inoperable solely due to the loss of the emergency power source.

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l 1997 Supplemental 10CFR50.59 Safety Evaluation Summaries l PROCEDURES LLP-07-044 REVISION 0, REMOVAL AND INSTALLATION OF UNIT 1 SRVS i WITH RPV HEAD INSTALLED, AND LLP-97-047 REVISION 0, REMOVAL / INSTALLATION l OF UNIT 1 MAIN STEAM SAFETY REllEF VALVES UNDER LLP-97-044 These procedures were written to support the removal and installation of Unit 1 safety relief valves (SRVs). Removed SRVs are transported from their installed location on the main steam l lines, around the RPV on both the path defined by engineering for temporary trapezing and the path defined by the permanently installed trolley beam. The rigging scheme provides two acceptable methods of rigging to maintain compliance with NUREG 0612, Control of Heavy

Loads at Nuclear power Plants. Temporary blind flanges will be installed whence the SRVs were removed. These are designed based on the shutoff head of LPCS. SRVs are replaced either with spare SRVs or tested SRVs.

CSCS COOLING POND SHAD NET AS-BUILT UFSAR UPDATE i

This evaluation was intended to formalize the Design Basis for the Shad net installed by LaSalle Station in 1982 as a non-safety related component. The Shad net provides no safety

, function and is introduced only to aid in the maintenance of existing plant systems strainers l and screens by preventing fish from entering plant components. The net is maintained in i place by a 1" top steel cable and bottom weights and is reinforced by 24" steel double floats l (pontoons) spaced 20 feet apart. The middle section of the net is polyester while the two l sections closer to the anchor bulk heads are stainless steel. The mesh size is selected not to entrap or capture the fish. ,

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TEMPORARY ALTERATION 1-0246-97, TEMPORARY REACTOR BUILDING VENTILATION SYSTEM CONFIGURATION DURING RWCU SYSTEM MODIFICATION INSTALLATION

! The TALT configured the VR System Duct Work in the Reactor Water Clean Up (RWCU) l pump rooms during modification installation. It was necessary to remove some duct work to complete required concrete cuts to support blowout panel changes per DCP 9700208. The Unit 1 VR System was shutdown and a means of maintaining the reactor building negative differential pressure was established in accordance with operating procedures.

! REACTOR RECIRCULATION PUMP EOC TRIP TIMES UFSAR CHANGE This UFSAR change corrects the discrepancies in the End of Cycle - Recirculating Pump trip l (EOC - RPT) times as shown in UFSAR Subsections G.3.2.2.2.d.1 and G.5.1.3.1 in l comparison with the values shown in other Sections of the UFSAR, Technical Specifications, and Transient Analyses Reports submitted by General Electric (GE) and Siemens.

TEMPORARY ALTERATION 1-0236-97, VESSEL LEVEL CONTROL WITH MAIN CONDENSER UNAVAILABLE, AND SPECIAL PROCEDURE LLP-97-055 This TALT installed a blank flange in the residual heat removal (RH) and reactor water cleanup (RT) reject line to the main condenser. LLP-97-055 was written to be used to control Reactor 8

c 1997 Supplemental 10CFR50.59 Safety Evaluation Summaries Vessel level with the Main Condenser unavailable to receive water. A 3/4-inch drain line and valve was installed as close as possible to the flange. This TALT establishes a flowpath from the Reactor Vessel RH return lines to the Waste collector Surge Tank. This flowpath supports the operation of the Control Rod Drive system. Operation of the Control Rod Drive system will add water to the Reactor Vessel which will cause Reactor Vessel level to increase. The new >

flowpath to the Waste Collector Surge Tank is required since the main Condenser is I

unavailable during the CD-10 window.

PROCEDURE LLP-97-045 REVISION 0, AUXILIARY ELECTRIC EQUIPMENT ROOM (AEER)

PRESSURIZATION While the VE system was shutdown, and temporary cooling provided TALT 1-0103-97 and 2-0037-97, controlled by LLP-96-118, LLP-97-045 was used to control the temporary pressurization of the AEER to check for leakage. Repair of the AEER leakage is required to ensure UFSAR positive pressure requirements can be established using the VE train and EMU.

TEMPOARY ALTERATION TALT 1-0242-97, TEMPORARY REMOVAL OF FIRE HYDRANT, REPLACED BY BLANK FLANGE l

The TALT was installed to support a maintenance activity that required removal of Yard Fire Hydrant 508 and its associated isolation valve,0FP023. A blank was installed in place of valve 0FP023 for the period of time necessary to replace / restore the system to service to service during the inclement winter months.

PROCEDURE LST-97-989 REVISION 0, VC SYSTM AIR LEAKAGE MEASUREMENT Thge procedure was used to quantify the amount of leakage within a boundary of the Main Control Room, supply and exhaust isolation dampers, and associated ducts.

l REVISION TO LTS-100-33, DRYWELL PNEUMATIC DRYER PURGE VALVES LOCAL LEAKAGE RATE TEST The procedure was revised to make local leakage rate testing (LLRT) of containment isolation valves 1(2)lN074 consistent with ANSI /ANS 56.8 standards. This change also allows for 1(2)lN074 to be tested in the normal direction, from inside the Primary Containment.

1 NEW PROCEDURE LST-97-993 FOR SIMULATED OUTSIDE ARE MAKUP FLOW TO AEER HVAC SYSTEM The procedure was written to determine VC system performance under the following conditions: Outside makeup air flow rates of ~1500 CFM to the VC system and ~2500 CFM to the VE system; and, Simulation of DCP 9700604 drawing outside makeup air to the suction of VC return fan OVCO2CA.

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1997 Supplemental 10CFR50.59 Safety Evaluation Summaries Special Procedure LLP-97-031 utilizes previously approved LOP-CD-10,"Use of Main Condense'r As An Alternate Decay Heat Removal Method in Cold Shutdown" methodology for decay heat removal for shutdown risk purposes only. This procedure provides a flow path from  ;

the main condenser to the reactor and returns water to the main condenser via the steam line drains.

ISOLATE AIR SIGNAL FROM RADWASTE BUILDING EXHAUST DAMPERS (TALT 1-0167-97)

The temporary alteration disconnected the air signal from the pneumatic controllers to dampers OVWO4YA/B and OVW28Y to allow calibration of the control loops with the ventilation system in I service. Negative pressure was maintained in the Radwaste Building.

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