IR 05000289/1999001

Insp Rept 50-289/99-01 on 990131-0313.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support

ML20205S685
Person / Time
Site:	Three Mile Island
Issue date:	04/16/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20205S682	List: IR 05000289/1999001 ML20205S679
References
50-289-99-01, 50-289-99-1, NUDOCS 9904260314
Download: ML20205S685 (16)

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U.S. NUCLEAR REGULATORY COMMISSION REGION 1 Docket N License N DPR-50 Report N Licensee: GPU Nuclear,Inc. (GPUN)

Facility: Three Mile Island Station, Unit 1 ,

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Location: P. O. Box 480 {

Middletown, PA 17057 4 Dates: January 31,1999 through March 13,1999 i inspectors: Craig W. Smith, Acting Senior Resident inspector Jason C. Jang, Senior Radiation Specialist, DRS Approved by: Wayne L. Schmidt, Acting Chief I Projects Branch No. 7 )

Division of Reactor Projects  !

9904260314 990416 PDR ADOCK 05000289 G PDR .

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EXECUTIVE SUMMARY Three Mile Island Nuclear Pcwer Station Report No. 50-289/99-01 This inspection included aspects of operations, engineering, maintenance, and plant suppor The report covers a six week period of resident inspection supplemented by a regional radiation specialis GPU Nuclear, Inc. (GPUN) operated Three Mile Island Unit 1 (TMI) safely at 100 percent power throughout the inspection perio Operations e The control room staff operated the unit safely; conducting required surveillance testing in a safe manner, including emergency safeguards actuation system testing and providing appropriate response to observed equipment malfuncticns, including an integrated control system demand fluctuation. (Section 01),

e Control room operators responded properly to a momentary increase in condenser of fgas activity, as indicated by an " alert" radiation monitor alarm. Operations management responded immediately to the control room to assess plant condition There was no apprecirble increase in once through steam generctor (OTSG) primary to secondary leakage. The most likely case for this momentary increase was a leaking OTSG tube plug. (Section O1.2)

Maintenance e GPUN performed observed maintenance activities well including nuclear river (NN) 1 pump (NR-P-1 A) preventive maintenance (PM) and modification activities; including proper post-maintenance testing and inservice testing. GPUN completed normal surveillance activities properly including the observed monthly emergency diesel generator testing. GPUN responded properly to indications of excessive vibration and noise from the NR-P-1C; identifying that the upper motor bearing had not been properly installed during a motor PMs prior to installation in October 1998. (Section M1)

e Maintenance, with assistance from engineering, diagnosed and replaced the failed air booster on the letdown containment isolation valve (MU-V-3). There was good coordination with operations to ensure the safety related functions of the valve remained operable. (Section M2.1)

e Maintenance techr:lcians identified and corrected deficiencies with the fit-up of Westinghouse Model DB-25 circuit breakers into the breaker cubicles. Maintenance technicians effectively used the corrective action process to identify the issue for further resolution. (Section M2.2)

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I Enaineerina e Engineering provided sound technical advice to operations and maintenance during the on-line repairs to MU-V-3. The supporting temporary modification and safety evaluation were well prepared. (Section E1)

e Engineering closely followed the issues identified concerning the fit-up of the Westinghouse Model DB-25 circuit breakers and provided good input to maintenance and operations concerning operability of the breakers. (Section E1)

e Engineering provided good technical advice to maintenance on replacement of the NR-

, P-1C upper motor bearing. A safety evaluation was prepared to evaluate the acceptability of the new style upper motor bearing. The inspectors found that GPUN's failure to initially identify that a different style upper motor bearing was installed on the replacement motor, and the resultant failure to perform a safety evaluation at that time, to be a minor issue. (Section E1)

Plant Support I

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i e The inspectors reviewed the qualifications of the individual identified to become the new Radiological Health / Safety Director against the requirements listed in Technical i Specification 6.3.2, " Unit Staff Qualif.ications" and found the individual met the minimum requirements. (Section R1.1)

• The GPUN Department of Environmental Affairs properly identified the possibility of a leak from the the waste evaporator condensate storage tank (WECST) discharge line using monitoring well grab sample analysis results. (Section R8.1)

e GPUN took appropriate actione to . sess the possibility of a leak from the buried normal l liquid radioactive waste discharge line from the WECST. As of March 10, the licensee closed and tagged the WECST discharge valve to avoid any inadvertent release. The l licensee intends to repair or install a new WECST discharge line. There was no

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radiological consequence to the public based on a projected annual dose to an adult of 0.0026 mrem, due to this leakage path. (Section R8.1)

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TABLE OF CONTENTS EXECUTIVE SUM MARY . . . . . . . . . . . . . . . . . . . . . . . . . ......... . .... . . ii TABLE OF CONTENTS . . . . . . . . . . ...... . .. ... ... . . .... . . . .iv 1. Ope ration s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 01 Conduct ef 0perations (71707,61726) . . . . . . . . .. ....... .........1 O1.1 GeneralComments . . ............. . ........ ..... .1 01.2 Operator Response to Observed increase in Condenser Offgas Radiation Monitor ........................ ........ .. . .. .. 1 01.3 Operator Response to Integrated Control Sys'.em Malfunction . ... 2 08 Miscellaneous Operations issues (92901) . . . . . . . . . . . . . . ... ........ 2 08.1 (Closed) VIO 97-09-02, Reactor Coolant System Overfill. . . . .. 2 11. Maintenance . . . . . . . . . . . . . . . . . . .. ...... ..... ... . .. . ...... ... .3 M1 Conduct of Maintenance (61726,62707) . . . . . . ...,.. ............ 3 M2 Maintenance and Material Condition of Facilities and Equipment (62707) . . . 4 M2.1 Letdown Isolation Valve, MU-V-3. Air Booster . . . . . . . . . . . ....4 M2.2 Westinghouse Model DB-25 Switchgear Breakers . . . . . . . . . . . . . . 5 111. Engineering . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... ....... ........ .... . .. 6 E1 Conduct of Engineering (37551) . . . . . . . . . . . . . . . . . . . . . . . . ....... 6 E8 Miscellaneous Engineering issues (37551) . . . . . . . . . ........ .......6 i E Closed LER 98-11 Thermo-Lag Fire Barrier Found InstallM Outside Approved Joint Arrangement . . . . . . . . . . . . . . . . . .... ... .... 6 I

IV. Pla nt Support . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ............ ..... 7 R1 Radiological Protection and Chemistry (RP&C) Controls (71750) . . . . . . . . . . 7 R Radiation Protection Manager Qualifications . . . . . . . . . . . . . ..7 R8 Miscellaneous RP&C lssues (71750) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 R Investigation of the Elevated Tritium (H-3) Activity in the Monitoring Well ( O S - 1 8) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... .7 V. Management Meetings . . . . . . . . . . . . . . . . . ................ ............... 9 X1 Exit Meeting Summary . . . . . . . . . . . . . . . .. ...... ... .......9 INSPECTION PROCEDURES USED . . . . . . . . . .... ... .. ..................... 10 ITEMS OPENED, CLOSED AND DISCUSSED . . . . . . . . . . . . . . .................10 LIST OF ACRONYM S U SED . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 iv l

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Report Details J Summary of Plant Status GPU Nuclear Inc. (GPUN) operated Three Mile Island Unit 1 (TMI) safely at 100 percent power throughout the inspection period, l. ODerations 01 Conduct of Operations (71707,61726) J l

The control room staff operated the unit safely; conducting required surveillance testing in a safe manner, including emergency safeguards actuation system (ESAS)

testing and providing appropriate response to observed equipment malfunctions, j including an integrated control system (ICS) demand fluctuatio .1 General Comments l l

Using Inspection Procedure 71707, " Plant Operations," the inspectors conducted frequent reviews of ongoing plant operations, in general, GPUN conducted plant operations in a professional manner with a good focus on safety. Specific events and noteworthy observations are detailed in the sections belo The inspectors observed significant portions of quarterly ESAS testing conducted on February 17 and 18 in accordance with GPUN procedure 1303-5.2, " Emergency Loading Sequence and HPl (High Pressure injection) Logic Channel / Component Test." The inspectors observed both control room and field activities. The l inspectors observed no procedural errors and found the test personnel to be very l knowledgeable of their dutie ]

I 01.2 Operator Resnonse to Observed increase in Condenser Offaas Radiation Monitor l l Insoection Scoce On February 18, the inspector observed control room operator response to an alert alarm for the offgas radiation monitor (RM-A-5). RM-A-5 monitors the condenser vacuum pump exhaust radiation level, with the " alert" alarm set at 200 counts per minute (cprn) to provide early indication of primary to secondary leakage from the once through steam generator (OTSG) tubes, Observations and Findinas The operators followed the alarm response procedere for an RM-A-5 " alert" alarm which directed the chemistry department to draw a condenser offgas and reactor coolant system (RCS) samples and for operators to perform a one-hour RCS leakrate computer calculation. The sample results and leakrate calcuiation did not indicate a sustained increase in primary to secondary leakage. A maximum peak value of 227 cpm was momentarily observed and within one minute RM-A-5 returned to its normal steady state value of approximately 130 cp .

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GPUN stated that a leaking OTSG tube plug most probably caused the momentary increase in offgas activity. Reactor coolant at normal operating pressure is postulated to have leaked past an OTSG tube plug into the plugged tube. Pressure built inside the tube and was relieved to the secondary side of the OTSG through a defect in the tube wall. The leakrate stops almost immediately as the pressure in the plugged tube equalized with secondary side pressure. GPUN has planned OTSG 1 tube plug inspections in the upcoming refueling outage scheduled to begin in l September 199 Operations management responded immediately to the control room to assess plant conditions. Based on the results of the computer leakrate calculation, shift management determined no emergency plan actions were required. Based on this information the inspector assessed that there was no appreciable increase in OTSG primary to secondary leakag Conclusion Control room operators responded properly to a momentary increase in condenser offgas activity, as indicated by an " alert" radiation monitor alarm. Operations management responded immediately to the control room to assess plant condition There was no appreciable increase in OTSG primary to secondary leakage. The most likely case frsr this momentary increase was a leaking OTSG tube plu .3 Ooerator Response to Intearated Control Svstem Malfunction The inspectors observed that control room operator responded well to an ICS malfunction, maintaining an awareness of important plant parameters. On March 4, the control room operator observed the ICS unit load demand output signal increasing above the demanded input. This resulted in core thermal power I increasing above the 100 percent rated value of 2568 megawatts thermal (MWt) for approximately 12 minutes. The maximum observed powei level was 2573 MWt, at which time the ICS self-corrected and lowered power back below the 100 percent rated value. No other plant responses were observed as a result of this malfunctio The inspectors noted that a similar ICS malfunction occurred in the previous inspection period on January 14. Efforts were ongoing at the end of the period to troubleshoot the exact cause of the ICS transient ,

l 08 Miscellaneous Operations issues (92901)

O8.1 (Closed) VIO 97-09-02. Reactor Coolant Svstem Overfill l

The NRC issued a Notice of Violation (NOV), concerning the RCS overfill event that

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occurred on October 15,1997, in a letter to GPUN dated January 27,1998. GPUN's response to the NOV, dated April 17,1998, provided a description of the circumstances surrounding the event and outlined several corrective actions. These corrective actions included: counseling the shift supervisor involved; revising plant operating procedures to specifically prohibit the use of the borated water storage tank fill path under similar

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I circumstances; reemphasizing management expectations on the control of significant plant evolutions and procedural compliance; and initiating communications enhancements for shift turnover meetings and the conduct of significant plant evolution In addition, GPUN's response described several corrective actions taken to avoid future

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procedure use violations. These actions included: revising the procedure use administrative procedure to increase the number of evolutions that require step-by-step procedure use and initiating prcgrammatic improvements to strengthen procedural I complianc }

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l The inspectors found the corrective actions appropriate and determined that GPUN satisfactorily implemented the specific procedural revisions and other corrective actions i committed to in their NOV response. This NOV is close l 11. Maintenance M1 Conduct of Maintenance (61726,62707)

GPUN performed observed maintenance activities well including nuclear river (NR)

pump preventive maintenance (PM) and modification activities; including proper post-maintenance testing (PMT) and inservice testing (IST.) GPUN completed normal surveillance activities properly including the observed monthly emergency diesel generator (EDG) testing. GPUN responded properly to indications of excessive vibration and noise from the NR-P-1C; identifying that the upper motor bearing had not been properly installed during a motor PMs prior to installation in October 199 * The inspectors observed significant portions of several planned PM and modification activities performed on the NR-P-1 A. Activities observed included:

pump packing replacement, modifications to the pump lubricating water manifold, modifications to the pump discharge strainer shaft key, and reduced sc>pe PM on the pump discharge motor operator valvo. With the exception of some minor procedure inadequacies identified by the inspectors during the pump repacking, the maintenance activites were conducted properly. The maintenance technicians were very knowledgeable anci job supervision was appropriate for the tasks being performed. The inspectors observed portions of the PMT and IST conducted following completion of the maintenanc e The inspectors observed the routine monthly surveillance on the "A" EDG (EG-Y-1 A) conducted in accordance with GPUN procedure 1303-4.16, " Emergency Power System." The inspectors observed operators starting and electrically loading the machine from the control room and also observed operation at the diesel generator. The evolution was well controlled and conducted in accordance with plant procedures. There were no abncrmal conditions identifie * GPUN properly responded to the identification that the NR-P1-C had an incorrectly installed upper motor bearing. The maintenance department had replaced the motor with a rebuilt spare from the warehouse in October 1998. The upper bearing on the replacement motor developed abnormal noise and vibrations after four months of operation.

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in October 1998 GPUN was unaware that the replacement motor had a different style upper bearing than the original equipment. The existing maintenance procedures did not reflect the correct installation procedure for the new style upper motor bearing. GPUN identified the problem and correctly installed a new upper motor bearing on February 11. The maintenance procedures and vendor technical manuals have been revised to reflect the new style upper motor bearing installed on NR-P-1 M2 Maintenance and Material Condition of Facilities and Equipment (62707)

M2.1 Letdown Isolation Valve. MU-V-3. Air Booster inspection Scooe On February 26, operators bypassed the air booster on the reactor coolant letdown outside containment isolation valve (MU-V-3) due to concerns with the continued reliability of the air booster to maintain pressure to keep the valve open. The air booster functions to supply air at an increased pressure (150 psig), from the instrument air system (90 psig), to the valve operator for MU-V-3 to keep the valve open. With the air booster bypassed, instrument air directly supplied the air to keep the valve open. MU-V-3 remained full open throughout the evolution. A job order was prepared to install a new air booste The safety related function of MU-V-3 is to shut and isolate letdown on receipt of an ESAS, using a combination of spring pressure and air pressure unrelated to air booste Observations and Findinos The inspector agreed with the GPUN evaluation that the MU-V-3 safety related function remained operable while the air booster was bypassed. Operators closely monitored MU-V-3 valve position and instrument air header pressure during the period the air booster was bypasse GPUN prepared an acceptable on-line risk document to provide guidance to the operators during the period the valve was gegged open to install the new air booste While the va!ve was gagged open, the operators entered the appropriate technical specification (TS) limiting conditions for operation and an operator was stationed at the valve to close the valve in the event of an emergenc A temporary modification was also prepared to install an air reservoir on the suction of the air booster to increase system reliability. The operation of the modified air system was bench tested in the shop prior to installation in the fiel The inspectors reviewed the job order package and the temporary modification paper work, and observed work in the field. The inspectors reviewed the PMT requirements at the completion of the work and found them to be appropriat Investigation revealed the air booster had failed due to normal usag Conclusions Maintenance, with assistance from engineering, diagnosed and replaced the failed air booster to MU-V-3. There was good coordination with operations to ensure the safety related functions of the valve remained operable.

M2.2 Westinchouse Model DB-25 Switchaear Breakers Inspection Scope On February 24, and again on March 9, GPUN identified deficiencies in the alignment of Westinghcuse Mode! DB-25 480 volt switchgear breakers. These deficiencies, which were identmed in non-safety related applications of these breakers could lead to undet9cted wiring damage on non-safety and safety related application I Observations and Findinas i On February 24, during routine preventive maintenance on the "B" secondary closed cooling water pump breaker, maintenance technicians identified a wiring screw, on the amptector current transformer attached to the breaker, rubbing against an alignment plate in the back of the breaker cubicle. On March 9, during routine preventive maintenance on the "A" secondary closed cooling water pump breaker, maintenance techriicians identified the direct current (DC) control power wiring to secondary contacts in the back of the breaker cubicle rubbing against the amptector current transformers to the point where the wire insulation had torn back. Both deficiencies were immediately repaired, which involved work inside the energized breaker cubicle. GPUN evaluated that the deficiencies did not effect proper operation of either breake The problems identified to date were on balance of plant breakers and did not effect breaker operation. However, this same style breaker is used in 23 safety related applications in the plant and under certain circumstances the fit-up problems could lead to wiring degradation that could ultimately effect breaker operation. One safety related breaker inspected by GPUN during the period, after the other issues were identified, showed no abnormal conditions related to fit-up of the amptector current transformers in the breaker cubicl The maintenance technicians properly entered the breaker deficiencies into the corrective action process (CAP). GPUN was evaluating changes to the breaker maintenance procedure to specifically identify inspection of the amptector control wirin Conclusion Maintenance technicians performed well in first identifying and then correcting deficiencies identified with the fit-up of Westinghouse Model DB-25 circuit breakers into the breaker cubicles. Maintenance technicians effectively used the CAP to identify the issue for further resolutio .

lil. Enaineerina E1 Conduct of Engineering (37551)

The engineering department continued to provide good support to plant operations and maintenance activitie e Engineering provided sound technical advice to operations and maintenance during the on-line repairs to MU-V-3. The supporting temporary modification and safety evaluation were well prepare e Engineering closely followed the issues identified concerning the fit-up of the Westinghouse Model DB-25 circuit breakers and provided good input to maintenance and operations concerning operability of the breakers, l

e Engineering provided good technical advice to maintenance on replacement of the NR-P-1C upper motor bearing. A safety evaluation was prepared to evaluate 1 the acceptability of the new style upper motor bearing. The inspectors found that l GPUN's failure to initially identify that a different style upper motor bearing was )

installed on the replacement motor, and the resultant failure to perform a safety evaluation at that time, to be a minor issu E8 Miscellaneous Engineering issues (37551)

E8.1 Closed LER 98-11 Thermo-Lao Fire Barrier Found Installed Outside Acoroved Joint Arranaement On August 25,1998, while performing upgrades to the 10 CFR 50 Appendix R fire barriers, GPUN identified a discrepant condition on a Thermo-Lag fire barrier that had existed since installation in 1987. Specifically, a % to % inch gap was visible in the fire barrier joint. GPUN took immediate corrective actions to post a continuous fire watch in the area of the degraded fire barrier until the joint was seale GPUN was conducting the inspections in response to concerns documented in NRC Bulletin 92-01, " Failure of Thermo-Lag 330 Fire Barrier System to Perform its Specified Fire Endurance Function," and its supplements. GPUN has since completed a 100 percent inspection of the installed Thermo-Lag fire barriers, identifying additional deficiencies, similar to the item identified in this LER. These additional deficiencies will be the subject of a supplement to this LER to be submitted at a later date. For the specific fire barrier identified in this LER, the inspectors found GPUN's corrective actions to be appropriate. This LER is closed. NRC disposition of the fire barriers to be identified in the supplement to this LER will be discussed in a future inspection repor I l

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IV. Plant Support R1 Radiological Protection and Chemistry (RP&C) Controls (71750)

R1.1 Radiation Protection Manaaer Qualifications The inspectors reviewed the qualifications of the individual identified to become the new Radiological Health / Safety Director against the requireme.its listed in ,

TS 6.3.2, " Unit Staff Qualifications." The inspectors found the individual met the l

requirements which state in part that "the management position responsible for radiological controls shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977."

R8 Miscellaneous RP&C lssues (71750)

R8.1 Investiaation of the Elevated Tritium (H-3) Activity in the Monitorina Well(OS-18) Inspection Scope GPUN identified a possible below grot.ad level water leak in one of the buried normal radioactive waste discharge knes, through identification of tritium (H-3) in routine sampling of a monitoring well. The inspector reviewed the normal methods of sampling and discharging radioactive waste and monitoring well sample results. The inspector also assessed the possible dose consequences of the leakag Observations and Findinas i Between January 9 and 18,1999, GPUN made 10 water batch discharges from the waste evaporator condensate storage tank (WESCT) located in the Unit 1 Auxiliary Building. Grab samples of water were properly taken from the WESCT and analyzed for H-3 and gamma emitters prior to release to the Susquehanna River. The total H-3 activity released was 'l33 curies. Projected doses to the public, based on these planned releases, were calculated priei to each release. The whole body projected annual dose i for an adult was 0.0026 mrem, a small fraction of TS limit of 3 mrem / yea On January 26, the GPUN Department of Environmental Affairs identified elevated H-3 l activities in the onsite monitoring well (OS-18). The licensee took grab samples of water from OS-18 and analyzed for H-3. In January, February, and March, tritium activities in the monitoring well indicated a potential leak from the WESCT discharge line, as shown in Table In February,12 Geoprobe (GP) monitoring wells (approximately 21 feet deep) were insta!Ied along the WECST discharge lines, as shown in Figure 1. Elevated H-3 activities were measured at monitoring wells GP-5, GP-6, GP-8, and GP-9. No Gamma emitters were identified in either soil or water sample .

Also H-3 was slightly elevated (average H-3 activity 1.8E-5 pCi/cc) in the Service Water Pump Wells A, B, and C (400 feet deep); however, this service water is not used for drinking or for showers. Water originating frcm the Service Water Wells will be measured for radioactivity before discharge to the environmen After identifying the possibility of a leak GPUN isolated the discharge line and planned to identify the exact location of the leak using hydrostatic testing methodology, As of March 10, the licensee closed and tagged the discharge valve to avoid any inadvertent releas The inspector confirmed that there were no radiological consequences to the public, from the discharge pipe leakage, based on a projected annual dose to an adult of 0.0026 mrem, due to this leakage pat c. Conclusion The GPUN Department of Environmental Affairs properly identified the possibility of a leak from the the waste evaporator condensate storage tank (WECST) discharge line using monitoring well grab sample analysis result GPUN took appropriate actions to assess the possibility of a leak from the buried normal liquid radioactive waste discharge line from the WECST. As of March 10, the licensee closed and tagged the WECST discharge valve to avoid any inadvertent release. The licensee intends to repair or install a new WECST discharge line. There was no radiological consequence to the public based a projected annual dose to an adult of 0.0026 mrem, due to this leakage path. (Section R8.1)

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Table 1, H-3' Activities in OS-18 DATE ACTMTY, pCl/cc January 5,1999 8.20E-6 January 12,1999 6.70E-6 January 19,1999 5.10E-6 January 26,1999 4.90E-5 February 2,1999 4.90E-5 February 9,1999 6.60E-5 February 16,1999 1.30E-4 February 23,1999 6.03E-5 March 2,1999 8.80E-5 March 9,1999 4.30E-5 H-3 Effluent Release Limit for water: 1E-3 pCi/cc (10 CFR 20 App. B Table 2)

V. Manaaement Meetings l

X1 Exit Meeting Summary Following the conclusion of the inspection period, the inspectors conducted an exit meeting with GPUN managers on March 18. GPUN staff comments concerning the issues in this report were documented in the applicable report sections. No proprietary information was include .

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INSPECTION PROCEDURES USED IP37551 Onsite Engineering IP61726 Surveillance Observations IP62707 Maintenance Observations IP71707 Plant Operations IP71750 Plant Support Activities IP92901 Miscellaneous Operations issues ITEMS OPENED, CLOSED AND DISCUSSED Opened:

Non Closed:

97-09-02 VIO Reactor Coolant System Overfill (Section 08.1)

98-11 LER Thermo-Lag Fire Barrier Found Installed Outside Approved Joint i Arrangement (Section E8.1)

Discussed:

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LIST OF ACRONYMS USED CAP Corrective Action Process epm Counts Per Minute DC Direct Current

'EDG Emergency Diesel Generator ESAS Engineered Safeguards Actuation System GP Geoprobe GPUN GPU Nuclear, In HPI High Pressure injection ICS Integrated Control System IR inspection Report IST Inservice Test LER Licensee Event Report MWt Megawatts Thermal NOV Notice of Violation NR Nuclear River Water NRC Nuclear Regulatory Commission OTSG Once Through Steam Generator PDR Public Document Room PMT Post-maintenance Test RCS Reactor Coolant System RP&C Radiological Protection and Chemistry TS Technical Specification TMl Three Mile Island Unit 1 UFSAR Updated Final Safety Analysis Report WECST Waste Evaporator Condensate Storage Tank

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