ML20149G876

Forwards Status of Previously Described Q1R13 Matl Condition Improvement Actions (Mcia),Addl Matl Condition Improvements & Emergent Work Activities Implemented During Q1R13 & Status of Previously Described non-outage Mcias

ML20149G876
Person / Time
Site:	Quad Cities
Issue date:	11/03/1994
From:	Kraft E COMMONWEALTH EDISON CO.
To:	Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
ESK-94-073, ESK-94-73, NUDOCS 9411080146
Download: ML20149G876 (12)

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• Commonwoalth Edison Quad cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 November 3,1994 ESK-94-073 Mr. William T. Russell, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comrnission Washington D.C. 20555 Attn.: Document Control Desk

Subject:

Quad Cities Station Unit 1 Status of Outage-Related Material Condition initiatives, Activities, and Commitments NRC Docket Nos. 50-254 and 50-265

References:

As listed in Attachment A Mr. Russell, Commonwealth Edison (Comed) has, in various letters, including the response to the Diagnostic Evaluation performed at the site in the Fall of 1993 (Reference 2), described actions which would be taken at Quad Cities Station to improve material condition. This letter describes:

- The status of each material condition improvement action which was originally described in References (1) through (3). This includes both outage (Q1R13) and non-outage improvement actions;

- A description of additional material condition improvement efforts and emergent work activities which were implemented during Q1R13; and,

- The status of other outage-related NRC commitments for Quad Cities Station Unit 1.

The following attachments provide this information:

Attachment B to this letter provides the status of the Q1R13 material condition improvement actions which were originally described in References (1) through (3).

This includes the schedule for completion of material condition improvement actions which were not completed during Q1R13.

l 9411080146 941103 O PDR ADOCK 05000254 i P PDR g

Mr. William T. Russell Page 2 November 3,1994 Attachment C is a description of additional material condition improvement efforts and emergent work activities which were implemented during Q1R13.

Attachment D provides the status of non-outage material condition improvement actions originally described in References (1) through (3), which are scheduled for completion in 1994 (non-outage related work).

Attachment E describes the status of other outage-related NRC commitments for Quad Cities Station Unit 1.

Certain material condition improvement actions were deferred from Q1R13. The decisions to defer work were made based on prioritization of ongoing, scheduled, and emergent work. These prioritizations required Comed to reschedule planned work during Q1R13 in order to redirect efforts and resources from previously described improvement actions to other, more safety significant actions. The emergent work, which necessitated the reprioritization of previously described improvement actions is described in Attachment C to this letter.

Comed has evaluated all work which was originally scheduled, as well as the status of all Unit 1 safety systems. Based upon this evaluation, Comed has concluded that all Unit 1 safety systems and components have been fully tested, and will perform the required design functions.

If there are any further questions, please contact Nick Chrissotimos at (308)-654-2241, ext. 3100.

Very truly yours, (d[S. Krafr. 4,

) (d .

Site Vice resident Quad Cities Station Attachments:

A: References B: Status of Previously Described Q1R13 Material Condition improvement Actions C: Additional Material Condition improvement Efforts and Emergent Work Activities which were implemented during Q1R13.

D: Status of Previously Described Non-outage Material Condition improvement Actions.

E: Status of other Outage-Related NRC Commitments for Quad Cities Station Unit 1 cc: J. Martin, Regional Administrator - Region Ill C. Miller, Senior Resident inspector - Quad Cities Station R. Pulsifer, Project Manager- NRR Office of Nuclear Facility Safety - IDNS 1

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1 Attachment A References (1) R. Pleniewicz to J. B. Martin letter dated November 12,1993.

(2) J. J. O' Connor to J. M. Taylor letter dated December 30,1993.

(3) L. O. DelGeorge to T. E. Murley letter dated November 1,1993.

(4) R. Pleniewicz to J. M. Taylor letter dated February 22,1994.

(5) J. L. Schrage to T. E. Murley letter dated January 11,1994.

(6) J. L. Schrage to W. T Russell letter dated May 23,1994.

(7) J. L. Schrage to T. E. Murley letter dated November 13,1992.

(8) J. F. Stang to D. L. Farrar dated July 6,1994.

(9) D. Chrzanowski to T. E. Murley letter dated March 5,1993.

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ATTACHMENT B Status of Previously Described Q1R13 Material Condition improvement Actions i

Unit 1 Emergency Diesel Generator (EDG)

Replace the lube oil cooler - Complete  !

Install and upgrade local indication - Rescheduled to a later non-outage System l Window I

- Upgrade air starting skid through the installation of a moisture separator and the replacement of the existing copper tubing with stainless steel - Rescheduled to Q1R14 Unit 1 High Pressure Coolant injection (HPCI)

- Install turbine exhaust line sparger modification - Complete Install cutwater modification on booster pump - Rescheduled to a later outage

- Install steam line drain modification - Complete

- Upgrade trim on MOV 2301-46 (cooling water pressure control valve) to alleviate cavitation induced vibration - Complete

- Overhaul emergency oil pump (balance pump impeller and motor rotor) - Complete Perform cold alignment check on turbine-pump - Rescheduled to Q1R14 Unit 1 Reactor Com isolation Cooling (RCIC)

Overhaul turbine - Rescheduled to Q1R14

- Upgrade turbine exhaust line rupture disc design - Complete i

Unit 1 Core Spray (CS)

- Overhaul 'A' Pump - Complete

- Refurbish motor for the 'A' Pump - Complete (motor replaced)

- Balance motor-pump coupling for 'A' Pump - Complete

- Upgrade trim on MOVs 1402-4A & -4B (torus test return) and removal of downstream restricting orifices in order to alleviate cavitation induced vibration - Complete

- Convert testable check valves 1402-9A & -98 to conventional swing check design in -

order to alleviate pneumatic actuator concems - Complete Unit 1 Residual Heat Removal (RHR) and RHR Service Water (RHRSW)

- Overhaul 'A' RHR Pump - Rescheduled to Q1R14 l

- Refurbish the 'C' and 'D' RHR Pumps motors *B' pump motor refurbished to alleviate vibration concems; 'C' and 'D' pump motors rescheduled to Q1R14

Attachment B

'. (cont.)

- Refurbish motor for the 'B' and 'C' RHRSW Pumps - Complete (support work also performed)

- Complete RHR heat exchanger maintenance activities - Complete ('1 A' Heat Exchanger)

- Upgrade trim on MOVs 1001-5A & -5B (heat exchanger service water outlet) and removal of downstream restricting orifices in order to alleviate cavitation induced vibration - Rescheduled to Q1R14 Upgrade the trim on MOVs 1001-36A & -368 (torus cooling) to alleviate cavitation induced vibration - Complete

- Replace the 1001-29B (LPCI injection) valve stem with a higher strength material -

Complete Other Q1R13 Activities

- Recoat the Torus - Complete

- Refurbish motor for the Reactor Recirculation Pumps - Rescheduled to later outages

- Motor refurbishment for the 'C' and 'D' Condensate / Condensate Booster Pumps -

Complete

- Overhaul 'D' Condensate / Condensate Booster Pump - Complete ('C' Condensate Booster pump also overhauled)

- Overhaul the Unit Aux Transformer (TR-11) - Complete (TR-11 replaced)

- Complete MOV dP testing - Complete (see Attachment D)

- Upgrade outboard MSIV air lines (stainless steel piping being installed)- Rescheduled to future refuel outage.

Rebuild / replace the discharge accumulator for each SBLC pump - Complete

- Install new/ revised MSL support arrangements (as required)- ERV replacement to be scheduled for Q1R14 - Complete (new hydraulic snubbers Installed)

- Stake main condenser tubes to alleviate vibration - One half completed; Remainder scheduled for Q1R14

- Overhaul low pressure turbine 'B' - Complete Replace main condenser section 'A' boot - Complete Replace 4kV Bus 14 breaker - Complete

- Install time delay relays in the MSL low pressure circuitry - to alleviate Group 1 isolation concems following scrams - Complete

- Replace the signal cables (triple shielded cables) and drive cables for the SRMs and IRMs - Complete

- Install varistors in 250 Vdc motors for selected HPCI, RCIC, and RHR valves -

Ongoing

- Install test laps for the RHR testable check valves 68A & 68B - performance of the pressure test on the check valves (68A&B) - Complete Main generator rotor overhaul - Complete B-2

Attachment B (cont.)

Modify RFP low suction trip logic to 'two-out-of-two' with time delay - Rescheduled to Q1R14

- Upgrade of 'A' and 'B' Feedwater Regulating Valves (FRVs) to new hydraulic actuator design (note 'A' FRV is being converted from an air actuator design)- Rescheduled to Q1R14

- Inspect the following room coolers: 'A' & 'B' Core Spray, 'A' & 'B' RHR, HPCI, and 'A'

& 'B' RHRSW Pumps - Complete (U1 EDGCWP Cubicle Room Cooler also inspected)

- Disassemble and repair the ' disk / pilot assembly' for the MSIVs (with the exception of the '1C' MSIV) - Complete (*1B' and '1D' also disassembled and repaired) .

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l ATTACHMENT C  :

• Additional Material Condition improvements and Emergent Work Activities ' )

Implemented during Q1R13 l Additional Material Condition improvements - Q1R13 Quad Cities Station implemented additional material condition improvements during Q1R13.

Significant material condition improvements (modifications and completed work requests) are listed below:

- Motor Operated Valve Enhancements 1001-7D, RHR Torus Suction Valve: Installation of new valve 1001-19B, RHR Loop Crosstie Valve: Installation of new gearing and valve stem 1001-34A and -348, RHR Torus Test / Spray Valves: Installation of new trim, actuator, motor, yoke, disc, stem and cable 1001-36A & -368, RHR Torus Cooling Valves: Installation of new yoke, gearing and spring '

pack 1301-16, Inboard RCIC Steam Supply isolation Valve: Installation of new actuator, motor, gearing, yoke, and spring pack 1301-17, Outboard RCIC Steam Supply isolation Valve: Installation of new motor and yoke 1402-4A and -48, Core Spray Test Line Valves: Installation of valve trim, motor, gearing, '

cab:e, and yoke 2301-4 & -5, HPCI Steam Supply isolation Valves: Installation of new actuator, motor, gearing, cable, and yoke

+ Feedwater System Overhaul of 'B' Reactor Feed Pump installation of 'B' Reactor Feed Pump Seal Cooling Vent line Implementation of Feedwater heater shell and nozzle repairs Replacement of all Feedwater Heater level controllers Repair of body / bonnet leaks on Feedwater Reg Valves Repair of Feedwater injection check valve Repair of 4 Feedwater extraction check valves Repair / Replacement of 7 extraction steam valves Repair of 11 level control valves ,

l Attachment C (cont.)

. RHR and RHRSW Systems Replacement of RHRSW vault sump pump check valve ,

Modification of RHRSW pump piping support (to improve alignment and reduce l vibration and seal wear)

Installation of RHRSW flow indication (square rooter for linear indication)

Dilute Chemical Decontamination of RHR System  :

Replacement of RHR valves 1001-201 A and -201B, manual maintenance isolation (butterfly) valves for the RHRSW heat exchanger outlet inspection and repair of the RHR heat exchanger flow reversing valves <

- Condenser and Condensate System Installation of Condensate Pump piping supports Installation of upgraded bearings in 'C' and 'D' Condensate pumps Replacement of Condensate Demin flow control valves Replacement of all 8 Main Condenser Flow Reversing valves and thermal operators; Upgrade of valve operators Alignment of Condensate pumps ,

inspection of 8 Condensate check valves l l

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• Reactor Recirculation System I Dilute Chemical Decontamination of Reactor Recirculation System inspection and rebuild of 'B' Reactor Recirculation MG set Replacement of seals in both Reactor Recirculation pumps

+ HPCI and RCIC Systems j Replacement of RCIC drain lines with stainless steel (see Attachment B for similar HPCI work)

Inspection and upgrade of RCIC Steam Supply valves inspection of 4 RCIC check valves and manual valves Inspection of the RCIC Trip Throttle valve Rebuild of RCIC Steam Trap Inspection of 14 HPCI check valves Replacement of HPCI and RCIC 250 VDC Breakers Inspection of HPCI Stop Valve and 9 HPCI check valves

- Standby Liquid Control (SBLC) System l Replacement of SBLC accumulators and pump packing  !

Repair of valve seats in SBLC valves 1101-15 and -16, inboard and outboard I isolation check valves C-2 l

. Attachment C I

'. (cont.)

• Main Turbine and EHC System Drain and clean main turbine oil tank and EHC tank Overhaul of both EHC pumps Replacement of 3 bypass valves,2 control valves, and 2 stop valves _ >

I a- Auxiliary Electric System Completion of Station Blackout tie-in to Buses 13-1 and 14-1 (including cubicle t installation)

Installation of Bus 18 undervoltage relay

• Standby Gas Treatment System (SBGTS)

Installation of SBGTS heater failure circuit and SBGTS flow instrumentation a Reactor Water Cleanup System Dilute Chemical Decontamination of RWCU system Replacement of unwired motor operators with beveled gear manual operators on .

RWCU valves 1299-9 through -14, hot suction to cold suction transfer' valves  !

Overhaul of RWCU Reject Flow Control Valve

. Other Material Condition Enhancements Replacement of X-23 containment penetration bellows assembly l Installation of RVLIS Backfill system (NRC Bulletin 93-03)

Replacement of the Target Rock safety / relief valve and four safety valves Major Emergent Work - Q1R13 ,

- Replacement of two SRM/lRM Dry Tubes

- Fabrication and installation of Jet Pump Riser Brace

- Replacement of '1 A' Core Spray motor

- Redesign and installation of trim on 1001-36A & -368 RHR Valves

. Expanded check valve inspection

. Expanded snubber inspections

. Expanded relief valve testing

• Redesign and repair of refuel bridge ,

- Expanded MOV testing l

. Overhaul of '1C' RHR pump I I

- Overhaul of '18' RHR pump

- Core Shroud inspection C-3 l

.- ATTACHMENT D Status of Previously Described Non-Outage Material Condition improvement 1 Actions Unit 1/2 (Swing) Emergency Diesel Generator (during '94) ,

Replace all 20 EDG engine power packs - Complete

- Install field ground indication modification (installation of time delay) - Complete . >

+ Install modification on EDG fuel oil system to a!!ow for flexible hose installation - '

Complete _

Install upgrade of local indication - Scheduled for later non-outage system window

- Install new digital tachometer - System window scheduled for 1994

+ Inspect current transformers in local diesel generator panels - Complete (transformers were replaced)

+ Upgrade air starting skid through the installation of a moisture separator and .;

the replacement of the existing copper tubing with stainless steel- Scheduled  !

for later system window ImpellerfCutwater Modification on the RHRSW Pumps

- Modifications completed on '1 A', '1D', and '2C' pumps - Complete -

Complete modifications on '1B', '1C', 2A', '2B' and '2D' pumps during '94 '2A' and '2B' pumps completed; '2D', '1B' and '1C' will be completed.at a later time O perator Work-Arounds/Concems

. 48 issues identified by operators 4

- 21 issues resolved (e.g., Service Water Radiation Monitors) by the completion of 02M11 - Compbkd dudng Q2M11 .

- Resolve an additional 26 issues by the end of '94 - Of the original 48 issues,9 remain. 3 of these will be resolved during 1994. The Operator Work-Around program is an ongoing process. Cunently,11 issues are being tracked in this l program.

. Resolve remaining issue during '95 - There are cunently 6 issues tracked which will be resolved in '95 or '96. 4 of these are from the original 48.

Vulnerability Assessment issues i i

- Resolve approximately 80% (total) of the VAT issues by the end of '94 - .l

Approximately 50% complete at the end of Q1R13 1

.- Attachment D (cont.)

Motor Operated Valve (MOV) Differential Pressure Testing

- Complete MOV dP testing by the end of '94 - 31 OF 33 Complete (all high and ,

medium priority valves completed); Remaining two valves (Core Spray ,

Outboard injection Valves) are low priority valves. 1 t

Material Condition

- Upgrade Unit 1 RHRSW Vaults by the end of the first quarter of '94 - Complete

. Upgrade Unit 2 RHRSW Vaults by the end of the second quarter of '94 -

Complete

- Complete Area reclamation initiative - schedule established and initiative is being implemented - in progress.

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. .c ATTACHMENT E Status of Other Outage-Related NRC Commitments j Quad Cities Station Unit 1 In References (5) and (6), Comed requested relief from the Section XI of the ASME Code for three instances of localized wall loss (pitting) on the Quad Cities Station Uni ~ 1  :

Residual Heat Removal Service Water (RHRSW) piping. Reference (5) also provided Comed's evaluation of the localized RHRSW piping wall loss in accordance with Generic

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Letter (GL) 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping, and a commitment to replace the affected Quad Cities Unit 1 RHRSW piping during the next Unit i refuel outage. In Reference (6), Comed stated that a code replacement of the affected RHRSW piping was implemented during Q1R13. ,

i in Reference (7), Comed provided a schedule for replacement of Rosemount trip units at Quad Cities Station in order to reach conformity with the NRC Staff's position with respect to Alternate Rod Insertion System diversity requirements (10 CFR 50.62). Comed replaced these trip units at Quad Cities Station Unit 1 in November 1993 (during the planned Q1M09 maintenance outage).  ;

in Reference (8), the NRC issued a Safety Evaluation and Technical Specification  ;

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Amendment associated with the installation of equipment necessary to meet the requirements of NRC Bulletin 93-03, Resolution of Issues Related to Reactor Vessel Water Level. Comed ,

installed this equipment on Quad Cities Station Unit 1 during Q1R13. Therefore, all actions necessary to meet the requirements of NRC Bulletin 93-03 have been met for Quad Cities Station Unit 1.

In Reference (9), Comed provided a response to NRC Bulletin 90-01 Supplement 1, Loss of Fi/I Oilin Rosemount Transmitters. Comed indicated that 18 Rosemount Transmitters at Quad Cities Station were within the scope of Bulletin 90-01 Supplement 1. As of November 19,1993, Comed had replaced all of these transmitters. t in Reference (3), Comed provided a status update for Generic Letter 89-10 activities at all Commonwealth Edison Stations. In that update, Comed committed to performing a

" deterministic /PRA" reprioritization ranking and a margin review for all GL 89-10 MOVs. In addition, Comed indicated that corrective actions associated with the margin reviews would be initiated. The deterministic /PRA reprioritization ranking and margin review for all GL 89-10 MOVs has been completed at Quad Cities Station. Comed has also initiated corrective actions at Quad Cities Station resulting from the margin reviews.

Also as part of Reference (3), Comed committed to submitting a GL 89-10 closure plan for the butterfly valve population. This commitment is not applicable to Quad Cities Station. There are no butterfly valves in the GL 89-10 program at Quad Cities Station.

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