IR 05000352/1993025
| ML20059L723 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/08/1993 |
| From: | Anderson C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20059L718 | List: |
| References | |
| 50-352-93-25, 50-353-93-25, NUDOCS 9311170314 | |
| Download: ML20059L723 (58) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
z Report No Docket No License No NPF-39 NPF-85 Licensee: Philadelphia Electric Company Correspondence Ccatrol Desk P.O. Box 195 Wayne, Pa 19087-0195 Facility Name: Limerick Generating Station, Units 1 and 2 Inspection Period: September 26 - November 1,1993 Inspectors: N. S. Perry, Senior Resident Inspector T. A. Easlick, Resident Inspector R. R. Temps, Project Engineer I Approved by: // f Id Clifford'M And6rson, Chief Date Reactor Projects Section No. 2B '
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I EXECUTIVE SUMMARY i
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- Limerick Generating Station
- Report No. 93-25 & 93-25
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j Plant Operations !
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The Unit I high pressu.e coolant injection system was found to be properly aligned with no ! conditions that might degrade overall performance (Section 1.3). A detailed walkdown of i the Unit 2 spent fuel pool cooling and cleanup system showed that the system does not have the same potential problems as discussed in Information Notice 93-83 (Section 1.4). One I
- identified instance of an operator failing to log readings on the daily operations surveillance
log was left unresolved pending NRC review of the completed event investigation (50- l j 352/93-25-01) (Section 1.5).
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-Maintenance
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, 1 Observed maintenance activities were found correctly performed with good supervision and , coordination (Section 2.1). A D14 emergency diesel generator start failure event was left j , unresolved pending NRC review of the completed troubleshooting activities (50-352/93-25- ) 02) (Section 2.2). The first seven Shoreham fuel shipments were completed without incident ; l with good management oversight observed (Section 2.4). A comprehensive plant cleanup f was conducted with no impact on plant operations; good direction concerning management expectations was communicated to the workers (Section 2.4) ,
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Surveillance :
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Observed surveillances were properly conducted and supervised (Section 3.1). :
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t i ! Plant Suonort ! '. I 1 e . Radiological protection and security activities observed were found acceptable (Section l j and 4.2). l
Miscellaneous ! A Licensee Event Report concerning a missed firewatch inspection resulted in a non-cited , ] violation due to PECo's efforts in identifying the event and the comprehensive corrective ! i actions taken (Section 5.1). Commissioner de Planque toured the plant and met with plant management (Section 6.3).
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J EXECUTIVE SUMMARY ...................................... 11
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I i 1.0 PLANT OPERATIONS ................................... 1 i Operational Overview . ............................... I l j j j Event Report . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I j Engineered Safety Feature Walkdown - Unit 1 High Pressure Coolant ,
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Injection Sy stem . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 l
; System Walkdown - Unit 2 Fuel Pool Cooling and Cleanup System . . . . . 2 l Missed Operator Log Readings . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 ;
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2.0 MAINTENANCE ....................................... 4 l Maintenance Observations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 : i D14 Diesel Generator Failure to Start . . . . . . . . . . . . . . . . . . . . . . . 4 l . Shoreham Fuel Shipments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 : General Plant Cleanup ................................ 6
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< 3.0 SURVEILLANCE . . . . ............................. . . . . 6 !
' Surveillance Observations ............................ . 6 i
4.0 PLA NT S U PPO RT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 Radiological Protection . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 i
, S ecu ri ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 l
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i 5.0 REVIEW OF LICENSEE EVENT AND ROUTINE REPORTS . . . . . . . . . . . 7 a Licensee Event Reports . . . . . . . . . . . . . . . . . . . . . . ......... 7
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< , 6.0 M A NAG EM ENT M EETING S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 l Exit Intersiews . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 ! Additional NRC Inspection this Period ...................... 9 2 Commissioner Visit . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 . l l
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1, DETAILS j; PLANT OPERATIONS (71707)' The inspectors observed that plant equipment was operated and maintained safely and in conformance with license and regulatory requirements. Control room staffing met all
- requirements. Operators were found alert, attentive and responded properly to annunciators and plant conditions. Operators adhered to approved procedures and understood the reasons fo
- lighted annunciators. The inspectors reviewed control room log books for trends and activities, observed control room instrumentation for abnormalities, and verified compliance
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with technical specifications. Accessible areas of the plant were toured; plant conditions, activities in progress, and housekeeping conditions were observed. Additionally, selected < valves and breakers were verified to be aligned correctly. Deep backshift inspections were conducted on September 26,28, October 3,17 and 31,1993.
q Operational Overview Unit 1 operated at full power from the beginning of the inspection period until October 8, 1993, when the unit began a coast down due to fuel burn-up. At approximately 98% power, in mid-October, the number six feedwater heaters were removed from service, restoring Unit 1 power to 100 %. The unit remained at full power until the coast down resumed at the end 3 of the inspection period, reducing power to 98% of rate ,
- Unit 2 operated at full power throughout the inspection period, except for minor power reductions for surveillance testing and control rod pattern change i Event Report ,
- On October 29,1993, PECo made a Four-hour report to the NRC pursuant to 10 CFR 50.72. The report concerned the inadvertent initiation of isolation signals and ESF actuations during the performance of a surveillance test. The primary containment instrument gas,
! containment atmospheric sampling, and containment leakage detection systems received ' isolation signals. All isolations functioned as expected. The isolation signals were initiated j when an operator inadvertently grounded a jumper, during removal, while performing ST-6- i 051-201-1, RHR Ultimate Cooling Refuel Valve Test. Grounding the jumper caused panel 10-Y-102, circuit 02 to trip, resulting in the isolation signals. Approximately 15 minutes , after the isolations,10-Y-102, circuit 02 was reset and all valves that isolated were reopene I The inspectors had no further question concerning this c,>ent.
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'The NRC Inspection Procedures used as Fuidance are listed parenthetically throughout this report.
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2 Engineered Safety Feature Walkdown - Unit 1 IIigh Pressure Coolant injection System . i An engineered safety feature system walkdown was performed of the accessible portions of the Unit I high pressure coolant injection (HPCI) system components to verify operability of the system. The inspector verified that the system lineup procedure matched the piping and instrument drawing, and the actual system configuration. Drawings 8031-M-55, High Pressure Coolant Injection, Rev. 41, 8031-M-56, HPCI Pump / Turbine, Rev. 34, and , I procedure IS55.1.A, Equipment Alignment For Automatic Operation Of HPCI System, Re , were used for the lineup verificatio l
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A few minor discrepancies, such as missing labels, and typographical errors were identified by the inspectors. Plant management was given the specific discrepancies identified for resolution. The inspectors concluded that the Unit I high pressure coolant injection system was properly aligned for operability as required, and no equipment conditions existed that i might degrade overall performanc .4 System Walkdown - Unit 2 Fuel Pool Cooling and Cleanup System A walkdown of accessible portions of the Unit 2 fuel pool cooling and cleanup (FPCC) system was conducted by the inspectors. As an adjunct to this inspection, the FPCC system design was reviewed for susceptibility to concerns as described in recently issued NRC Information Notice (IN) 93-83. The inspectors' review was limited to the FPCC's electrical and seismic design and the fuel pool's level / temperature indication ' l Limerick Units 1 and 2 have Mark II containments and each unit has a spent fuel pool above each reactor in a reactor building common area. As described in the Updated Final Safety Analysis Report (UFSAR), most of the FPCC system is seismic Category 11 and lla; l however, the spent fuel pool, the skimmer surge tanks, and the residual heat removal (RHR) and emergency service water (ESW) interties are seismic Category 1. Further, the UFSAR states that the non-seismic portions are designed so as not to fail in the event of a scismic event. Two of the three FPCC pumps are powered from Class 1E powe As described in IN 93-83, a loss of coolant accident (LOCA) could result in piping stresses from LOCA-induced hydrodynamic effects in the reactor building. The FPCC system is assumed to be lost due to its non-seismic design. l.oss of the FPCC system coincident with a loss of off-site power (LOOP) would result in heatup of the spent fuel pool, eventual boiling of the pool, and release of steam into the reactor building, which would prevent access to the l reactor building and thereb,' .mit recovery action l l
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Limerick's FPCC system does have a seismic Category I intertie to the RHR syste However, assuming inaccessibility of the reactor building, this system could not be used to supply cooling and/or makeup to the pool as entry to the reactor building to install spoolpieces and perform manual valve manipulations is required. Limerick has a seismic Category I intertie to the ESW system. However, makeup water to the spent fuel pool can be supplied from the ESW system by simply opening two valves on the 200' elevation of the control building, which is outside the reactor building and would therefore be accessibl The ESW intertie is a 2 inch line that supplies makeup water directly into the spent fuel pool via the supply portion of the RHR intertie piping. The inspectors determined that the ESW st.pply would be available in post-LOCA/ LOOP conditions, and that the supply flowrate of makeup water to the spent fuel pool is accounted for in the ESW design basis for flowrates to safety-related systems in post-accident conditions. Also, viability of the ESW system would not be threatened by the conditions in the reactor building, as the Class IE power
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supplies and ESW pumps are outside the reactor buildin ' The inspectors noted that there is no level indication in the control room for monitoring spent fuel pool conditions. Each fuel pool has its own local control panel on the refuel floor that would be inaccessible in the conditions postulated by the IN. However, review of the UFSAR indicates that the worst case heat-up and boil-off rates from each spent fuel pool have been calculated by PECo. Knowing the time until boiling occurs and the rate of boil-off once it starts, and knowing the flowrate of ESW via the 2 inch makeup line, a methodology could be developed that would allow for periodic makeup to the spent fuel poo In summary, while it appcars the Limerick spent fuel pool cooling system is similar to the system described in IN 93-83, Limerick's design is significantly different in that one source of water would be available to provide makeup to the spent fuel pool and thereby prevent uncovering and damaging the fuel bundles. The inspectors concluded that the system was in :
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good material condition, was aligned in accordance with its operating procedures, and was able to perform its inter ded functio .5 Slissed Operator Log Readings The inspectors were noti 6ed, on October 13,1993, that an operator failed to log on the daily 1 I operations surveillance log, on October 12, 1993, data which is required to be taken at least once per shift, by technical specifications. The discrepancy was identified during a licensee review of the surveillance log on October 13, 1993. The omission was inadvertent, in that the operator logged some of the data in that location, but misvd some of the data. The log sheets were initialled as complete and signed off as reviewed and satisfactory. The missing data was for HPCI, RHR, and RWCU room temperatures. The data was subsequently l verified as acceptable since the readings are archived. When questioned, the operator could not explain how the reaaings were missed, since he logged other room temperatures from the same monitor. However, he stated that he verified that all the readings were within their acceptable ranges, prior to logging the readings, and that he must have been distracted l l
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while logging the readings and failed to go back and complete the log sheet. He and another individual who reviewed the log could not explain how the missed data was not identified prior to signoff of the procedur The inspectors were concerned that the procedure was signed off as completed and reviewed and the missed data was not identified. At the conclusion of the inspection period, plant personnel had not completed their investigation of this event. This item will remain unresolved pending NRC review of the completed licensee investigation. (50-352/93-25-01) AINTINANCE (62703) aintenance Observations The inspectors reviewed the following safety-related maintenance activities to verify that repairs were made in accordance with approved procedures and in compliance with NRC regulations and recognized codes and standards. The inspectors also verified that the replacement parts and quality control used on the repairs were in compliance with PECo's Quality Assurance (QA) progra The following maintenance activities were reviewed:
* Springpack replacement and valve operation test and evaluation system (VOTES)
testing for HV-052-139
* VOTES test for HV-51-lF073
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The maintenance activities observed were performed correctly by knowledgeable plant personnel, with good management supervision and good coordination with operations personne .2 D14 Diesel Generator Failure to Start On October 26,1993, the D14 diesel generator failed to start during the performance of surveillance test (ST)-6-092-314-1, D14 Diesel Generator Slow Start Operability Test Ru This was the monthly ST to verify that D14 was operable per technical specifications and to demonstrate the operability of one of the redundant sets of starting air valves. The diesel generator is equipped with two independent air starting systems with redundant component Each starting systems consists of a reciprocating air compressor, an air receiver, a line filter, an air start solenoid, and an air distributor. The air receiver is sized to provide five normal starts of the diesel engine when fully charged. Prior to the start of the test, the ST coordinator determines whether the testing vill be performed on the ID1 or 1D2 starting air systems.
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. 5 ; i During this monthly test, the IDI starting air system was selected, since the ID2 air system was removed from service and tagged, due to the 092-1307D starting air solenoid valve
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leaking air. In accordance with the test, the D14 control switch was taken to start; however, I the diesel did not roll over. The system manager was immediately notified and commenced troubleshooting the problem. The first step in the troubleshooting process was to determine ; if the engine was seized. Starting air was applied to the engine from the IDI starting air I system using the ' engine air barring" portion of the ST. (Engine air barring is normally used to rotate the engine 2-3 revolutions to reduce the amount oflube oil that accumulates m I the exhaust manifold after the engine has been run.) The engine did not roll during this l attempt. The tags were removed from the ID2 starting air system and again engine air ; barring was attempted. This time the engine did roll indicating that it was not seized. The ) I 1D2 air system was then isolated and an attempt was made to apply air from the ID1 air system. This attempt was successful and the engine rolled. Following the troubleshooting l
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activities, it was determined that the most likely cause of the failure to start was the IDI air distributor, since the engine rolled over with air from the ID1 air system once the pistons were realigne l l D14 was declared inoperable and the remaining three diesel generators on Unit I were run, l
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in accordance with technical specifications, without incident. The IDI starting air header was isolated and tagged, and the 092-1307D starting air solenoid valve was replaced to restore the ID2 header to an operable statu On October 27,1993, ST-6-092-314-1 was successfully completed and the D14 diesel generator was declared operable. At the end of the inspection period the investigation and ,
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troubleshooting of the failure of the IDI starting air system was still ongoing. This issue will remain unresolved pending completion of NRC's review of PECo's final investigation (50-352/93-25-02). Shoreham Fuel Shipments The initial shipment of slightly irradiated fuel from the long Island Power Authority's (LIPA) Shoreham Nuclear Power Station to the Limerick Nuclear Generating Station was begun on the morning of September 25,1993. The initial 17 fuel assemblies (out of 560 to be transferred in 33 shipments) were contained in a shielded cask that was designed for the transport of radioactive spent fuel. The cask was placed on a barge at the Shoreham Station and towed to PECo's Eddystone Generating Station on the Delaware River near Philadelphia, PA. Following arrival on September 27, the cask was transferred to a rail car for transport ! to Limerick. The initial shipment arrived at Limerick on the morning of September 28, ! 1993. The movement of the cask and rail car, through the protected area boundary (PAB) fence, was observed by the inspectors. Good coordination between security and health physics allowed the rail car to be processed into the PAB without inciden _ - . - . - . , - . . . - - - - ,
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At the end of the inspection period, seven shipments of 17 fuel bundles (119) have been successfully delivered to Limerick and placed in the Unit I spent fuel pool. The inspectors have observed various portions of the operation including: 1) the transfer of the cask to the ' refueling floor cask washdown area; 2) insertion of the cask into the cask pit; 3) removal of the cask head; 4) removal of fuel from the cask; 5) removal of the cask from the cask pit; and 6) decontamination of the cask. All personnel involved in the activities were found to be knowledgeable and familiar with the activities. A good emphasis on teamwork has reduced the turnaround time on the cask at Liinerick to approximately one day. All activities observed were performed in accordance with approved procedures and were frequently monitored by members of PECo management. The inspectors will continue to observe the activities associated with future deliverie .4 General Plant Cleanup During the week of October 25 - 29,1993, Limerick plant personnel conducted a comprehensive plant cleanup. In addition to sweeping, mopping and painting, activities included removing untagged equipment, cleaning out storage boxes, replacing lights and oil pads, and verifying that equipment trouble tags were vali i The inspectors observed portions of the ongoing activities to ensure that plant safety was not reduced, and to ensure that radiological controls were appropriately implemented. In general, the inspectors had noted good housekeeping in the past at the plant, but an improvement was observed. Good direction concerning expectations was given to plant i personnel prior to activities, and the cleanup was conducted with no impact on plant operations. Additionally, radiological controls were found appropriate during cleanup and removal of items from the plant area .0 SURVEILLANCE (61726) l Surveillance Observations During this inspection period, the inspectors reviewed in-progress surveillance testing and completed surveillance packages. The inspectors veriBed that the surveillances were
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completed according to PECo approved procedures and plant technical specification requirements. The inspectors also verified that the instruments used were within calibration tolerance and that qualified technicians performed the surveillance The following surveillances were reviewed: ST-6-092-314-1 D14 Diesel Generator Slow Start Operability Test Run ST-6-092-311-2 D21 Diesel Generator Slow Start Operability Test Run ST-6-051-231-2 A RHR Pump, Valve and Flow Test
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The surveillance tests observed were properly conducted by knowledgeable plant personnel, and were properly supervised by managemen [ PLANT SUPPORT (71707) Radiological Protection During the inspection period, the inspectors examined work in progress in both units including health physics (HP) procedures and controls, ALARA implementation, dosimetry and badging, protective clothing use, adherence to radiation work permit (RWP) requirements, radiation surveys, radiation protection instrument use, and handling of potentially contaminated equipment and material The inspectors observed individuals frisking in accordance with HP procedures. A sampling of high radiation area doors was verified to be locked as required. Compliance with RWP l requirements was reviewed during plant tours. RWP line entries were reviewed to verify that personnel provided the required information and people working in RWP areas were ; observed as meeting the applicable requirements. Additionally, the inspectors verified that radiation surveys were accurate for certain areas of the plant, using a portable meter supplied by plant personnel. The activities observed by the inspectors were acceptabl .2 Security Selected aspects of plant physical security were reviewed during regular and backshift hours, to verify that controls were in accordance with the security plan and approved procedure This review included the following security measures: guard staffing, vital and protected area barrier integrity, and implementation of access controls including authorization, badging, escorting, and searches. The activities observed were acceptabl .0 REVIEW OF LICENSEE EVENT AND ROUTINE REPORTS (90712,90713) Licensee Event Reports The inspectors routinely reviewed Licensee Event Reports (LERs) and performed followup inspections to PECo's actions regarding the disposition of corrective initiatives. The inspectors reviewed the following LERs and found that the events were described accurately, PECo had identified the root causes, implemented appropriate corrective actions and made the required notification LER l-93-011, Partial Loss of Offsite Power that Resulted in a Unit 1 SCRAM and Various ESF Actuations on Unit 1, Unit 2, and Common Systems, Revision 00, Event Date: September 7,1993, Report Date: October 7,199 _- --
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Thi3 event is reviewed and documented in Combined Inspection Report Nos. 50-352/93-24 and 50-353/93-2 LER 1-93-012, Failure to comply with Technical Specifications Section 3.7.7 in that a one hour firewatch inspection was not performed due to cognitive personnel error, Revision 00, Event Date: September 22,1993, Report Date: October 21,199 ; This LER rel. orts an instance where an established firewatch inspection for an inoperable fire barrier was not performed within the time required by the applicable technical specificatio .
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Due to planned painting in the area of the inoperable fire barrier, a qualified security force member was designated to augment the firewatch patrol and inspect the area in question at the appropriate times. In one instance, the security force member failed to inspect the area, at the end of the shift, due to an inadvertent personnel error. A secondary cause of the event was that a "special order" should have been, but was not, issued to properly remind , personnel to perform the inspection. Corrective actions included counseling the person i i involved, and briefing all security force members on this event and the requirements of l attention to detail. Additionally, security force supervisors were instructed to generate a
"special order" whenever there is a deviation in the firewatch patrol. A procedure revision was made to require a "special order" addendum be made to the post orders of any patrol if the patrol must specifically inspect an inoperable fire barrier during the course of their normal rounds. Safety significance for this event is minimal since no fire occurred during the time in question, and the fire detection equipment in the area was operable and would have alerted operators of a fir l The inspectors reviewed the corrective actions taken and concluded that they were comprehensive. This violation, involving the failure to perform a required firewatch inspection for an inoperable fire barrier within the time required by the applicable technical specification, meets the criteria for enforcement discretion of Section VII of the NRC's Enforcement Policy and will not be cite ,
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LER 2-93-010, This LER reports a condition prohibited by Tech Specs in that a Primary Containment Isolation Valve was inoperable and the required ACTION wasn't taken due to personnel error, Revision 00, Event Date: July 21,1993, Discovery Date: September 9, 1993, Reportability Date: September 14, 1993, Report Date: October 14, 1993.
l The inspectors found that the LERs listed above met the requirements of 10 CFR 50.73 and had no further questions regarding these event .2 Routine Reports Routine reports submitted by PECo were reviewed to verify the reported information. The following report was reviewed and satisfied the requirements for which it was reporte Station Monthly Operating Report for September 1993, dated October 13, 1993 , j !
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9 MANAGEMENT MEETINGS Exit Interviews The inspectors discussed the issues in this report with PECo representatives throughout the inspection period, and summarized the findings at an exit meeting with the Plant Manager, Mr. R. Boyce, on November 1,1993. PECo personnel did not express any disagreement with the inspection findings. No written inspection material was provided to licensee representatives during the inspection period.
! Additional NRC Inspection this Period One Region-based inspection was conducted during this inspection period. Inspection results were discussed with senior plant management at the conclusion of the inspection.
l Subiect Inspection N Lead Inspector _Date 10/06/93 Engineering 50-352/93-26 Leanne Kay 50-353/93-26 Commissioner Visit On October 18,1993, NRC Commissioner E. Gail de Planque visited Limerick Generating Station. The visit included a tour of various areas in the plant, including the main control room, the refuel floor, the radwaste facilities, and the chemistry laboratories. After the tour, PECo management presented information concerning the ongoing Shoreham fuel shipments, the radiation protection program, low level radwaste handling, and plant and outage performance. Handouts from the PECo presentations are enclosed with this report as Attachment .. _. _ . --
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ATTACHMENT 1
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LIMERICK GENERATING STATION COMMISSIONER E. Gall de PLANQUE VISIT pf* 'NG 8-
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AGENDA 1:00 PM ARRIVAL ON SITE 1:30 PM PLANT TOUR 3:30 PM PRESENTATIONS 4:30 PM DEBRIEF WITH DAVE HELWIG ' 4:45 PM MEET WITH RESIDENT INSPECTORS 5:00 PM DEPART FROM SITE .
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PRESENTATIONS 1. PLANT PERFORMANCE PLANT MANAGER BOB BOYCE 11. OUTAGE PERFORMANCE DIRECTOR OUTAGE MANAGEMENT WALT MACFARLAND ll RADIATION PROTECTION PROGRAM MANAGER RADIATION PROTECTION GARY MURPHY I REACTOR VESSEL WATER LEVEL MOD DIRECTOR SITE ENGINEERING JIM MUNTZ LOW LEVEL RADWASTE HANDLING MANAGER RADWASTE KEN CENCI i , i i __ _ -- _ _ _ _ _ _ _ _ _ - _ _ _ _
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PLANT PERFORMANCE
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* GROSS MEGAWATT GENERATION * TWO YEAR OPERATING CYCLES . * CAPACITY FACTORS * SALP HISTORY
* REACTOR WATER CONDUCTIVITY ' * ECCS UNAVAILABILITY
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-
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i ,' { 0.0 - .,..,. , ,- r , ., .., , m ,e ;, . ..>.. , m r i... .. . ..-. ~ , - r ... m ,.. r. r y . t . 1 , 1 8 152229 5 121926 3 10172431 7 14 2128 5 121926 2 9 162330 6 132027 4 111825 1 MAR APR MAY JUN JUL AUG SEP OCT 1993
{
_ _ . . , _ _ _ _ _ _ _ _ _ . . _ _ _ . _ _ - . _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ . _ _ _ . _ . _ _ _ _ _ _ _ . _ _ _ _ _
- -
. - _ _ . _ _ _ _ _ _ _ _
--
_ _ _ _ . . _ . - - - - - + - . . -----.me...- ..-
_ .. _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ ~ _ . . _ . . _
. .
.
.
~
LIMERICK GENERATING STATION - UNIT 2 ECCS - HPCl/RCIC UNAVAILABILITY UNAVAILABILITY % .0 4.5 - - .0 - - .5 - - .0 - - .5 - < p - '
/
2.0 - # ,' - .5 - p - /
"
10-0.5 - f
,
- #, -10
- /
0.0 - i , , , , , , , i i , i i i i , , i J A SON D J F MAMJ J A SOND i 1992 1993 , EUNPLANNED EPLANNED - ACTUAL -GOAL = _ _..O
... . --p -
- - - - ._ .0 - _ _ 2.0 l ,,. _ 82% INPO BWR'S < 1995 INDUSTRY GOAL = _ ,..
* * * * +s O O J A 8 O N D J P M A M J J A e O N O 36 MONTH ROLLING AVERAGE
:
--_ _ _ __- _____ _ ____-__-- _ _ _- _ _ _ _ _ _ _ . . _ _ _ . _ . ._ _, - - .. ~.- . _ - . . . - .. . .-
. _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ .___ - _ _ _ _ _ _ _ _
..
.
.
~
LIMERICK GENERATING STATION - UNIT 1 ECCS - RHR UNAVAILABILITY UNAVAILABILITY % 2.50 2.50 4isottttn 2.00 - f . - 2.00 p l /
/ /
1.50 - l - 1.50 f , l , /
/ /
1.00 - l - 1.00 p 0.13 / 0.50 - ' / -0.50
/
0.00 - , , , , , , , , , , , , , , , , , , , 0.00 93 J ASONDJ FMAMJ J ASOND 1992 1993 E UNPLANNED $ PLANNED - ACTUAL - GOAL = .5 % INPO BWR'S < 1995 INDUSTRY GOAL = .0- = = = = - - - - = = = = = = -> - -- - . 5 - - ' 1.0 - - # 0.5 - - J AS O N D J F M A M J J A S O N D 36 MONTH ROLUNG AVERAGE l
__ _ _ _ _ _ _ _ _ _ . _ _ _ _
-
.
.
'
LIMERICK GENERATING STATION - UNIT 2 EGEN UNAVAILABILITY UN AVAILABILITY % " IS HETT E F4 3.5 - ,, - .0 - / - / 2.5 - f
- - p 2.0 - /
s s' - f / 1.5 - u , - .0 - - s
# ! 0.5 - p - #
i i l i , i i i , i i . . . . , , , i J A S ON D J F M A M J J A S ON D 1992 1993 j ' E UNPLANNED E PLANNED - ACTUAL -GOAL - y.yPO BWR'S < 1995 INDU B 5 _ _ _ ___ 2. 0 - - .5 - - 1.5 l 1.0 - - .5 - - 0.5 ' O O
- J A S O N D J F M A M J J A S O N D
{ 36 MONTH ROLLING AVERAGE i ,
-.
- - - _ _ - - - _ - - _ . _ _ _ _ _ . _ - - . _ - . _ _ - _ - - _ _ - - -
. , .
...
.
.
OUTAGE PERFORMANCE
* LIMERICK OUTAGE LENGTH
'
* BEST OUTAGE LENGTH
l
* SUCCESSFUL OUTAGE PERFORMANCE
! ! * OUTAGE RISK ASSESSMENT !
* 2R02 EXPOSURE i
l l l i
. . ...
_.,
- .
l e t
.
l l LIMERICK OUTAGE LENGTH DAYS 140
- 125
! 120 ,g 111 100
i
~ [- ~~
's 60 '
- 60 3 -
- .,42 '
i I
1
: 0 ; 86 87 88 89 90 91 92 93 94 .
YEAR
! ACTUAL -- PLANNED - FORECAST i
i i
_ _ ._ _ .__ _ _ _ _ - - ------ - --. --------- - - ----- --.-- _ .. _ -- . _ _ - - - - - . . - - - - - - - - - ._
'
BEST OUTAGE LENGTH FOR TOP 5 DOMESTIC BWR'S SINCE 1980 'BWR 4 AND 5} 60 La s/2no2 60 g 50 - LGS /1 R05
~
42 40 - 37 -
w g 30
- -
20 - -
10 - -
0 -
1 2 3 4 5 BWR 4,5
- - - - - - _ - - - - _ - _ - - _ - _ _ - _ _ - - - _ - - - - - - - - - - - - _ _ - - - - - - - - -
- - . - - -. - - - _ _ - - - - .. - - . - ._. - - . _ _ . . - _ - . _ - . - - . . . ,
...
~
OUTAGE PERFORMANCE WHAT MAKES US SUCCESSFUL? CLEAR MANAGEMENT FOCUS CLEAR ROLES DEFINED AND ENFORCED
- PROPER PREPARATIONS HAVE PRIORITY
l AGGRESSIVE SCOPE CONTROL ! ! . ! TEAM BUILDING AND INVOLVEMENT l l 1 A PLAN FOR SUCCESS i l i i i k
- - - - - - . - . . - - . - . - - - - _ - . - _ . - - . . _ . . - _ . - - - -
..
.
.
.
OTHER KEY ELEMENTS
* INNOVATIONS * SHARED LEADERSHIP
,
* ADOPTING BEST PRACTICES * ACCOUNTABILITY
,
- * POSITIVE REINFORCEMENT
! * PUBLICITY j * WORK CONTROLLED TO SINGLE SCHEDULE l l
* MANAGEMENT OF MAINTENANCE BACKLOG
! ! !
. - _-. _ _ - -
- - - _ _ _
..
NON-Oi3TAGE CM BACKLOG LIMERICK UNITS 0,1 & 2 2500 2500
. .
2000 - - 2000 . . . $1500 - 2R02
-
1500 0 1804 m - _ Z o 1000 - - 1000 s O _ _
500 - - 500
. .
0 i i i i i i i i i i i i i i i i 0 AMJJASOND JFMAMJJAS 1992 1993
.
- . _ - . . _ - - . _ , _ -
.
..
-l
'
OUTAGE RISK ASSESSMENT
= BASED ON COMPLIANCE WITH NUREG 91-06 * ALLOWS PRE-PLANNING OF LEVEL OF RISK AND REQUIRED CONTINGENCIES * PECo/EPRI COLLABORATION ON SOFTWARE PROGRAM DEVELOPMENT (ORAM-TIP) * INDUSTRY LEADER m_____.________ _ -
_ _ _ _ _ _ _ - - - - --- - - - -
. .
.
.
.
2R02 EXPOSURE ESTIMATE VS. ACTUAL 200
.
~
#
150 _.......... .......................... ........ . .. . . . _ 147 6
< d' w I __...................... . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. l ' s
%
_....... ........ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 ; ) j l
'
a5 I I I I i l l l < g
JAh 22 JAN 31 FEB 5 FEB 11 FEB 18 FEB 28 MAR 4 MAR 11 MAR 16 MAR 27 , i ESTIMATE * ACTUAL
'
l i
<
- JANUARY 22 - MARCH 16TH,1993
:
1 . _ - _ - . - _ .- - _ - - _ - _ _ _ - _ _ _ - _ _ -_-_--- _ ____ _ - . -- Il . - ..- _ _ .. _ -_.- .._.. .- _- - -._ _ _ - _ _ _ _ _ _ _ _ . -
'
.
~
RADIATION PROTECTION I
* LIMERICK RADIATION EXPOSURE
* LIMERICK EFFLUENT DOSE
;
- * ENHANCING RADIATION WORKER SKILLS l * STATUS OF REViff5D 10CFR20 IMPLEMENTATION i
l ! ! !
i
_. _ . _ _ _ . - . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . . . _ _ . . _ _ _ _ _ _
.
..
a
.
LIMERICK RADIATION EXPOSURE DOSE VS YEAR FOR BWR's DOSE IN PERSON-REM PER UNIT 600 500 -
-
-
400 - 300 -
-
.+.. .
-
-
.+
... -
. .
, '
- 200 -
'
.-- .
.
^ '
.- 16 +-
-
131.65 .
-
+.-
, ! 8 ; 100 - 5 .9 !
i 0 l 1988 1989 1990 1991 1992 1993 i
- YEAR
! ! -l INPO BEST QUARTILE _ LIMERICK DOSE + INPO AVERAGE ! ! i
_ _ . - ._ _ _ _-- . _ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ . . _ _ . _ _ .
..
.
.
LGS L QU D EFFLUENT DOSE WHOLE BODY & ORGAN
- 1988-1993 mrem /yr 100: . : : .
. . .. . .
.
.
.
. .
.
.
.. . .:: .. .:.. . .. ..::...::.
. .. .........
. . . . . . . . . . .. . .......
. . . . . .. . .. ..... .. ..... ...
.. . . . . . .. .. . .. . ........
. . . . .. . . .. .. . . . ..... ... .. . .. . ........
. . ..g g 3 g g 3.....
10 7.:
: *: *: ;
........
.. *::::::
..
. ....... .......::;* : .
... . .........
:
.y ......:.............
:*** *
.....y....
:*:*
.:*:.::.::*:
.............. ........
.....y.......... :**:::::::
...... ............ . .... ......".
. .. ...
*
* * * l th . . . . . . . . . ./T .........A.........A........../Ts........../.T ..
... . .... ... .. . ....... .
. . . ....... .... . ..... .....................................
...............................................................1
.......:*::
1 7. : ::::
.
::::::*:::::*::* **** :: *:*** ::::::* ::*:**::*:**::::
.................................................................................................................
... ..........................................................
...... ............................................................
..................
............. .. .................................. ...............
...................................................................
...... ..................... ......................................
0e1 : ::::*:::*: *::*::: ::*::::::::*::::::::::::::*** :.
............
............
. .....
.....
........
. .
..
..........................
.... .....................
..........................
.
.
............ .... .......................... .
............ ... .......................... .
............ .... ....... ....... .... .
............ ... ... .... . ... .
i g_g3 , A A A A A_
1988 1989 1990 1991 1992 1993 i
Unit 2 on une YEAR .
- WHOLE BODY E ORGAN * TECH SPEC WB + TECH SPEC ORG l 6 mrem /yr 20 mrem /yr
,
; ZERO LIQUID RELEASES IN 1988
! i
_ ____ _ _ -. . _ _ _ _ . _ _ _ - _ _ _ . __ _ ,
. . . ..
l I l
. . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .
i j
. . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . . . . . .
y
. . . . . . . . . . . . . . . . . . . . . . . .
k , ...%y y . . . . . . . . . . . . . . . . . .
.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
m
< ... . . . . . . . . . . . . . r O .. . . . . . . . . . . . . . . . . . .
n
... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
g
. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
j
,
.
..
..
.
.
.
. . . . . .
. . . . . . . . . . . . . . . . . . . . .
. . . . . . . . . . . . . . . . . . . . .
..
ym 4
.%. / . , . . . . . . . . . . . .
g ,3 . .(
.
. . . . . . . . . . . . . . . . . . . ..
. . . . . . . .. .. ..
@
v= Z
; .. . . . . . . . . . . . . . . . . . .
'
. . . . . . . . . . . . . . . . . . . . . . . .. N . .. . . . . . . . . . . . . . . . . . . . . .
n. E h E i . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
: . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
e
..
. . .
.
. . . . . . . . . . . . . . . . . . . . . . . .
. . . . . . . . . . . . . . . . . . . . . . . . . . .
. . . . . .
y K +*
@
3 <
": X 8 .. . "::'. '"::': : : ::'::::: : ":::' .. . . . . . . . . . . . . . . . . . . . . . . .
CD O EO v
.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . T"" gh 4 ce> u
. , cn . .
. .
. . . . . . . . . . . . .
. . . . . . . . . . . . . . . . . . . . . . . . . . . .
. . .. . . . . . . . . . . . . .
4g 9m ~ x
@ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
!
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
. Q) y .
. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
o >- g
, co ., . .A, .. .. .. . . . . . . . . .
_ CD g ) .
. . . . . . . . . . . . . . . . . . . . . . . . . . .
CD
. . . . . . . . . . . . . . . . . . . . . . . . . . . .
- o O ,nC
-
...
.
-
.
. . . . .
-
.
. . . . . . . .
... . . .
. . . . . . . .
..... ..-
v-
>> 4
,
Z
. .
. .
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . s .,J g
. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
-
O cc g o O
. . . . . . . . . . . . . . . . . . . . ..
. . . . . . . . . . . . . . . . . . . . . . . . . . . . .
\s CD ") 0 *
Qg M o
. . . . . . .. . . . . . . . . . . . . . .
. y. I
.,w
. . . . . . . . . . . . . . . . . . . ..
. . . . . . . . . . . . . . . . . . . . . .
@M j . . . . . . . . . . CD y-w% ll
. . . . . . . . . . . . . . . . . . . . . .
4 g g) e y
.. .. .. .. . . .
s
. . . . . . . . . . . . . . . . . . .
i . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . g g)
); .. . . . . . .. . . . . . . . . . . . . .
u . . . . . . . . . . . . . . . . . . . . . . . . . . . . g
,
s 3 ..
.
.
.. . . . . . . . . . .
. . . . . . . . .. . , . . . . . . . . .
..
Ns m E
. . . . . . . . . . . . . . . . . ......e . . . . . & ,
e
. ,.
..
. . . .
. . . . . . .
. . . . . . . . . . . .
. . . . . . . . . . . . . . . .
z p, o 4 g . . . . . . . . . . .. .. .. . . . . . . v m
- . .. .
. . . . . .
... . .. . .. . . . . . . . . .
. . . . . . . .
.
. . . . . .. . . . . . . . . . . . . . . . .
m O O t- v- v- t-- J O r-r- f O , O O O . O
- .- - - . . - - - _ _- -__---- - . _ - _ .
.. _- _
--_-_ - - _-
.
.
e
.
LGS GASEOUS EFFLUENT DOSE PARTICULATE & IOD NE mrem /yr i 100 ' :: . . .
.
.
.
: *:*:
.
.
: ::*: .
. .
.
*
.
..
....
.
. *. .:
. . .. . . .:..:.: . .. .. .. .
..
:: * ::
.
. .
. .. .
: : *::::::
.
. .. .. .
... .. . .. . . .... .. . . . . . . . .. .. .
;
'
.. . . _l
. . .
,
. . .
{ ...
,
..
,
... .. .. .......- ,.
.
I 10 7: : . * ,: ** : :* : **
. *::: ::*:*:..: :: .: * *
:* :: *: : . : : :*::: :
; . .. : ::::
. .... .. ..:* :::**:..:.............
::::::: :
.... . .. ..............
:**
:::::::::.
*
. .. ..
. . .. . ....
. ..... .. ..
. .
. ..
.... .. . .... .. . ........ ..... .
. .. ....... ......... . . .... .... .
.. ... .......
. . ..... . ....... . .... .. ... ..... ...... ....... ...........
.. ... . . .... ... .... ...................... .... ...........
I I j .. .... ..............................:.;;.;; : ...............g , , , ,
=
,...
.. ..
::.: :* ........:*:*::..
........
.................
. . ..
* ::: ..... .... ........................................
...
..:;.:* * I:
... .... .. . ....................... ...........
::*** * **
.... .. ............ :;*:.::::.::*::*
. .. ....... ....
..... .... .. ........... .... ..................................
..... . . ................................ ......... ...........
I i
. -- :*:**:**:*:*.:*: :: :::: :*:*::*::::::::::::*:::::::::::. :::*** --..:: ;;:::.;;;;;;;;;::::::::::::::::::::::::::;. . ... . ..
, . ... ... ... ............................ ....................... .......... . l . ... ..... .............................. .. l . ... ..... ......... .................... .. 1 . .. ... ..................... . ... .. l 0.01 ::: ::: :.::.::::::*::::*::*:
.........::::::.:::::::.:
. : : :*
- :-
.
:::
... .::::: :: .................
.
: :
. .
::
..
. ... .............. ... ..
. ... ... .............. ... ..
. ... ... .............. ... ..
. ... ... .............. .... ..
1 ' ' O.001 , 1988 1989 1990 1991 1992 1993 i i Unit 2 l , , on une YEAR PART & IODINE l TECH SPEC LIMIT i (30 mrem /yr) i 1991 DOSE < 0.001 mrem /yr
- -t 1-
- . - -
- - _ _ _ _ _ _ _ _ - -
.
.
.I ENHANCING RADIATION WORKER SKILLS INTEGRATE RADIOLOGICAL MONITORING INTO ROUTINE TASKS ADVANTAGES
* ENHANCES THE WORKER AWARENESS
* REINFORCES INDIVIDUAL RESPONSIBILITY i * INCREASES JOB EFFICIENCY l
- . _ - - - _ . - - . . _ _ . . _ _ .
.
.
*
~
ENHANCING RADIATION WORKER SKILLS .
(CONTINUED) i
,
- APPLICATION i
* RADWASTE TECHNICIANS
* CHEMISTRY TECHNICIANS i
i
* I&C TECHNICIANS l
! * MAINTENANCE TECHNICIANS
I ' O
. - - - _ - - - - _ . _ _ _ - - _ . _ _ - _ _ _ .
..
.
.
ENHANCING RADIATION WORKER SKILLS (CONTINUED) KEYS TO SUCCESS .
* TRAINING REQUALIFICATION
- * LINE MANAGEMENT SUPPORT i
- * COACHING AND FOLLOW UP i
! ! i
,
i i "*i
. - _ . _ - - _ - .- - - - - - - . . -
_ - . -
-
.
.
! STATUS OF REVISED 10CFR20 lMPLEMENTATION l i l 1. PREPARATION BEGAN IN EARLY 1992 ! > 50 PROCEDURES AFFECTED l COMPUTER (PREMS} UPGRADE WHOLE BODY COUNTER UPGRADE ! INTERNAL DOSE PROGRAM TRAINING PROGRAMS REVISION OF LICENSE DOCUMENTS i l l l 1 - A
_ . . _ _ _ _ _ _ _ _
.
:
.
STATUS OF REVISED 10CFR20 IMPLEMENTATION (CON'T) 2. STATUS ! MOST PROCEDURES COMPLETE COMPUTER UPGRADE ON SCHEDULE ! TRAINING IN PROGRESS ! .
!
'
l _ _ _ - _ - - _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ - - _ . _ _ _ _ _ _ _
- . - - - - - - _ _ - - - . - - - .- - . - _ . . _ -
, - -
:
~
STATUS OF REVISED 10CFR20 IMPLEMENTATION 3. IMPACT ON WORKFORCE
:
TEDE CONCEPT: ! - LOWER DOSES l: - FEWER RESPIRATORS I i TERMINOLOGY CONFUSING TO SOME i
MOST CHANGES TRANSPARENT i i
! ! ! ! i
..,
.. . .
REACTOR VESSEL WATER LEVEL MODIFICATION
* BACKGROUND = RESULTS a
. _ - - _ - - . -_ - _ _ _ - -. _ -. - _ _ _ . -
.
..
~
REACTOR VESSEL LEVEL INSTRUMENTATION REFERENCE LEG CONCERN BACKGROUND ,
* BULLETIN 93-03 i -
SHORT TERM COMPENSATORY ACTIONS '
-
AUGMENTED OPERATOR TRAINING !
-
HARDWARE MODIFICATION l ! I i i ! !
l l , x-
,
. ,
l REACTOR VESSEL LEVEL INSTRUMENTATION I REFERENCE LEG CONCERN RESULTS . o BOTH UNITS INSTALLED BY 7/30/93 EXCEPT TIE-INS . o APPLIED INDUSTRY LESSONS LEARNED ^ o UNIT 1 TIE-INS COMPLETED oGOOD EXPERIENCE TO DATE j o COST: $400,000 - $500,000 PER UNIT
i k - - - - - - - - - - - _ - - _
.- _ . _ _ - - - - - . . - _ _ _ _ _ _ _ - _ _ _ _ _ - - - -
_ _ _ - -
.
.
.-
.
LOW LEVEL RADWASTE HANDLING
= WASTE DISPOSAL
,
- * WASTE REDUCTION 1 & 2 ;
i
* OVERALL PROCESS * FUTURE ON SITE STORAGE
! ! ! ! ! d
- _ __ _ _- - - - - - _- . --__- .
. _ _ - --
..
.
' WASTE DISPOSAL LGS 1 &2 THOUSANDS (CUBIC FEET)
: 25 -- - - - -- - - - - -- - - - -- -- -- -- -
20 --- - - ----- - -- - - -- 15 - -- - -- - -
i
, 10 -
. l 5 - ,
1 ! O i 1986 1987 1988 1989 1990 1991 1992 1993* f * Estimated Year Unit 2 on Line End Total ,
,
r !
_ _____ - _ ._ _ _ _ _ _ _ _ _ ....._ _ _
.._ _ _ _ _ _ _ ,_ _
-
.
.
.
l l l WASTE REDUCTION INITIATIVES
- * GlCPROGRAM
= DAW INCINERATION l
l * INCREASE PERFORMANCE OF FILTER DEMINERALIZERS l !
1 )
'
b ~
I 5 .
..l
- - - . _ - . . -.- -._.-.- - ----._ - . - _ . - _ . --
.
..
-
.
.
WASTE REDUCTION INITIATIVES (PAGE 2)
* INSTALLATION OF CONDENSATE DEEP BEDS
'I ! * RESIN EXPRESS
* REUSABLE LINERS l
! * DRAIN CONTROL
i i
i l l
1 i i ,I
? , _
- --. -- . _ - . . - - . - - . - .- -.. .. - - . .. .
. .
.
'.
O GIC RESIN DAW
. COLLECTION . COLLECTION . DEWATERED . PACKAGE . PACKAGE . SHIPPED TO . SHIP TO . SHIP TO PROCESSOR PROCESSOR PROCESSOR
_ DRIED NON COMPACTED INCINERABLE SORT INCINERABLE CLEAN FRISK CONTAMINATED FOR FREE RELEASE SHIPPED TO . BURNED BURIAL SITE , PACKAGED
! LANDFILL COMPACTED , SHIPPED AS , DAW j SHIPPED TO BURIAL SITE
-_
ll }}